ML18135A248

Draft Written Examination (Folder 2)

ML18135A248
Person / Time
Site:	Salem
Issue date:	05/21/2018
From:	D'Antonio J Operations Branch I
To:	Public Service Enterprise Group
Shared Package
ML17194A494	List: IR 05000272/2018301 ML18025A858 ML18074A052 ML18074A053 ML18074A054 ML18074A055 ML18134A128 ML18135A225 ML18135A248 ML18135A301 ML18135A333 ML18149A494
References
CAC 000500
Download: ML18135A248 (318)

Text

{{#Wiki_filter:EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Points: 1.00 Given:

• Unit 1 is at 25% Reactor Power and rising due to a plant startup At time 17:00:00
• The 13 RCP shaft shears At 17:00:30, which ONE of the following completes the statements below?

The Reactor is _(1 )_. Normal full PZR spray capability _(2)_ available. (1) (2) A. tripped is NOT B. tripped is C. at power is NOT D. at power is Answer: C Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, a reactor trip on RCS low flow has different coincidences based on reactor power level. Since the reactor is above P-7 (10% power) and there is a reactor trip based on RCS low flow when the reactor is > P-7, the candidate could incorrectly conclude that at 12:00:30, the reactor is tripped. Part 2 is correct. B. Incorrect but plausible. For Part 1, a reactor trip on RCS low flow has different coincidences based on reactor power level. Since the reactor is above P-7 ( 10% power) and there is a reactor trip based on RCS low flow when the reactor is > P-7, the candidate could incorrectly conclude that at 12:00:30, the reactor is tripped. For Part 2, since many other systems only require 1 pump to provide 100% flow (e.g. CCW, SW, SI, CS, eves and RHR), the candidate could incorrectly C. Correct. For Part 1, when the 13 RCP shaft shears at 17:00:00, the RCS low flow reactor trip setpoint will be met for only 13 Loop. Since the reactor is below P-8 (36% power), the reactor will not trip. For Part 2, PZR spray is produced from the 11 and 13 loop 0/Ps (created by the 13 and 11 RCPs ). However, 13 RCP actually produces most of the spray flow. Consequently, when 13 RCP trips, full PZR spray flow is not available. D. Incorrect but plausible. Part 1 is correct. For Part 2, since many other systems only require 1 pump to provide 100% flow (e.g. CCW, SW, SI, CS, eves and RHR), the candidate could incorrectly Question Number: 1 Tier: 2 Group 1 KIA: 003 Reactor Coolant Pump System-K3.01 Knowledge of the effect that a loss or malfunction of the RCPS will have on the following: RCS Importance Rating: 3.7 10 CFR Part 55: 41.7 / 45.6 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must how a trip of the 13 RCP will affect the RCS / PZR pressure control system. Page 2 of 6

EXAMINATION ANSWER KEY ' Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITIAL) <;RO Justification: NIA Technical 2-EOP-FRCE-3 ( LICENSED OPERATOR FLUENCY LIST)

References:

Proposed references None to be provided: Learning Objective: NOS05FLUNCY-09 ( LICENSED OPERATOR FLUENCY LIST) 1 State those items in the Licensed Operator Fluency List A. Permissives and Control Grade Interlocks

8. Reactor Trips Cognitive Level:

Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 2 Points: 1.00 Given:

• Unit 2 is at 95% Reactor Power and stable
• The Rod Bank Selector Switch is in MANUAL
• The 21 MIXED BED DEMINERALIZER is in service At time 20:00:00
• 2CC71 (Letdown Heat Exchanger Component Cooling Water Outlet Control Valve) malfunctions causing the letdown temperature to rise and stabilize at 130 °F Which ONE of the following completes the statements below?

When in service, the mixed bed demineralizer is used to _(1 )_. As the 21 MIXED BED DEMINERALIZER heats up, RCS TAVG will INITIALLY _(2)_. (1) (2) A. provide Lithium control and help maintain RCS pH rise

8. provide Lithium control and help maintain RCS pH lower C. chemical impurities from the RCS rise D. chemical impurities from the RCS lower A.nswer: D Page 1 of 5

EXAMINA110N ANSWER KEY Salem ILOT 16-01 RO NRC Exam-(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANAL YS/S; A. Incorrect but plausible. For Part 1, the Cation Demineralizer is used to remove Lithium from the RCS and to maintain RCS pH. Consequently, the candidate could incorrectly conclude that mixed bed demineralizer is used to help maintain RCS pH. For Part 2, the candidate could incorrectly conclude that the demineralizer will actually absorb more boron as it heats up which would cause TAVG to rise. B. Incorrect but plausible. For Part 1, the Cation Demineralizer is used to remove Lithium from the RCS and to maintain RCS pH. Consequently, the candidate could incorrectly conclude that mixed bed demineralizer is used to help maintain RCS pH. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that the demineralizer will actually absorb more boron as it heats up which would cause TAVG to rise. D. Correct. For Part 1, when is service, the mixed bed demineralizer is used to remove chemical impurities from the RCS. For Part 2, boron removal more efficient at lower temperatures. Consequently, the demineralizer will release boron as temperature rises resulting in a unplanned reactivity change. With more boron in the RCS, TAVG will lower to offset the negative reactivity inserted into the core when the demineralizer heated up and released boron. Question Number: 2 Tier: 2 Group 1 KIA: 004 Chemical and Volume Control System-K6.20 Knowledge of the effect of a loss or malfunction on the following CVCS components: Function of demineralizer, including boron loading and temperature limits Importance Rating: 2.5 10 CFR Part 55: 41.7 / 45.7 10 CFR 55.43.b NIA KIA Match: K/ A is matched because the candidate must how a malfunction of the CVCS mixed bed demineralizer (demineralizer heats up) affects performance of the demineralizer to include changes in RCS TA VG. Page 2 of 5

EXAMINA110N ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1RO Justification: N/A Technical NOS05CVCS00-17 (CHEMICAL AND VOLUME CONTROL

References:

SYSTEM) Proposed references None to be provided: Learning Objective: NOS05CVCS00-17 ( CHEMICAL AND VOLUME CONTROL SYSTEM) 4 Describe the function and how their normal and abnormal operations affects the Chemical and Volume Control System: xii Demineralizers (Mixed Bed, Cation, and Deborating) Cognitive Level: Higher X Lower -- Juestion Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 3 Points: 1.00 Which ONE of the following completes the statement below? The Residual Heat Removal System Pumps take suction from the _ ( 1) _ Hot Leg and can be aligned to discharge into the _(2)_ Hot Legs. (1) (2) A. 21 21 and 22 B. 21 23 and 24 C. 22 21 and 22 D. 22 23 and 24 Answer: B Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Since the RHR Pumps takes suction from an RCS hot leg and can be aligned to discharge into RCS two hot legs and selection of the 4 RCS loops is plausible.

8. Correct. The Residual Heat Removal System Pumps take suction from the 21 Hot Leg and can be aligned to discharge into the 23 and 24 Hot Legs.

C. Incorrect but plausible. Since the RHR Pumps takes suction from an RCS hot leg and can be aligned to discharge into RCS two hot legs and selection of the 4 RCS loops is plausible. D. Incorrect but plausible. Since the RHR Pumps takes suction from an RCS hot leg and can be aligned to discharge into RCS two hot legs and selection of the 4 RCS loops is plausible. Question Number: 3 Tier: 2 Group 1 &A: 005 Residual Heat Removal System (RHRS)-K1 .09 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the following systems: RCS Importance Rating: 3.6 10 CFR Part 55: 41.2 to 41.9 / 45.7 to 45.8 10 CFR 55.43.b NIA KIA Match: KIA is matched because the candidate must the physical connections of the RHR System (suction and discharge) SRO Justification: N/A Technical NOSOSRHR000-16 (RESIDUAL HEAT REMOVAL SYSTEM)

References:

Proposed references None to be provided: Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam-(T-75 SUBMITTAL) '_earning Objective: NOS05RHR000-16 (RESIDUAL HEAT REMOVAL SYSTEM) 3 Draw a one-line diagram of the Residual Heat Removal System which indicates the following: Major Components Cognitive Level: Higher Lower X Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 4

EXAMINATtON ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 4 Points: 1.00 Given:

• A LBLOCA has occurred
• The crew is performing 2-EOP-LOCA-3 (Transfer To Cold Leg Recirculation)
• 21SJ44 (Containment Sump Suction Valve) can NOT be opened Which ONE of the following completes the statements below?

The crew was required to realign ECCS valves for cold leg recirculation as soon as the RWST Level _(1 ) _ alarm was FIRST validated. With 21SJ44 closed, _(2)_ RHR Pump(s) will be able to draw suction from the Containment Sump and discharge ECCS flow into the RCS cold legs and to the suctions of the SI Pumps and Centrifugal Charging Pumps. (1) (2) A. LO ONLY 22 B. LO BOTH C. LO-LO ONLY 22 D. LO-LO BOTH A.nswer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, IAW EOP-LOCA-1, the crew is required to realign ECCS valves for cold leg recirculation as soon as the RWST Level LO alarm was FIRST validated. For Part 2, with 21 SJ44 closed only 22 RHR pump will be able to draw suction from the Containment Sump and discharge ECCS flow into the RCS cold legs and to the suctions of the SI Pumps and CCPs. B. Incorrect but plausible. Part 1 is correct. For Part 2, the valve arrangements for the ECCS pumps to take suction from a water source are not standardized. For example, if SJ1 (RWST Suction Valve to CCP) had failed to open, BOTH CCPs could take suction from the RWST. Consequently, the candidate could incorrectly the containment suction valves to the RHR pumps are arranged similarly to the SJ1 and SJ2. This would cause the candidate to further incorrectly deduce that with 21SJ44 closed, BOTH RHR Pump(s) will be able to draw suction from the Containment Sump and discharge ECCS flow into the RCS cold legs and to the suctions of the SI Pumps and CCPs. C. Incorrect but plausible. For Part 1, there is a RWST Level LO-LO alarm. Consequently, the candidate could incorrectly conclude that RWST Level LO alarm only warns the crew to prepare for transferring ECCS flow to cold leg recirculation and the transfer will actually occur when the RWST Level LO-LO alarm is validated. Part 2 is correct. D. Incorrect but plausible. For Part 1, there is a RWST Level LO-LO alarm. Consequently, the candidate could incorrectly conclude that RWST Level LO alarm only warns the crew to prepare for transferring ECCS flow to cold leg recirculation and the transfer will actually occur when the RWST Level LO-LO alarm is validated. For Part 2, the valve arrangements for the ECCS pumps to take suction from a water source are not standardized. For example, if SJ1 (RWST Suction Valve to CCP) had failed to open, BOTH CCPs could take suction from the RWST. Consequently, the candidate could incorrectly the containment suction valves to the RHR pumps are arranged similarly to the SJ1 and SJ2. This would cause the candidate to further incorrectly deduce that with 21SJ44 closed, BOTH RHR Pump(s) will be able to draw suction from the Containment Sump and discharge ECCS flow into the RCS cold legs and to the suctions of the SI Pumps and CCPs. Question Number: 4 Tier: 2 Group 1 KIA: 006 Emergency Core Cooling System (ECCS)-K6.05 Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: HPI/LPI cooling water Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) Importance Rating: 3.0 10 CFR Part 55: 41.7 / 45.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know how a malfunction of LPI water (containment suction valve fails close) during cold leg recirculation affects ECCS. SRO Justification: N/A Technical 2-EOP-LOCA-3 (Transfer To Cold Leg Recirculation)

References:

NOS05ECCS00-09 ( EMERGENCY CORE COOLING SYSTEM) Proposed references None to be provided: Learning Objective: NOS05ECCS00-09 ( EMERGENCY CORE COOLING SYSTEM) 3 Draw a one-line diagram of the Emergency Core Cooling System which indicates the following:

a. Major Emergency Core Cooling System Components

b. Major Emergency Core Cooling System Flowpaths Cognitive Level:

Higher X Lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 5 Points: 1.00 Given:

• Unit 2 is at 80% Reactor Power and stable
• 21 Charging Pump is in service
• PZR Pressure and Level are lowering
• Containment Pressure is rising At time 11 :00
• PZR Pressure is 1864 psig and lowering
• Containment Pressure is 4.1 psig At time 11 :08
• PZR Pressure is 1764 psig and lowering
• Containment Pressure is 5.2 psig Which ONE of the following completes the statements below?

_(1 ) _ is the earliest time that an AUTOMATIC Safety Injection occurred. After the Safety Injection has occurred, Centrifugal Charging Pump flow will be directed through 2CV55 (CCP Flow Control Valve) into the RCP Seals _(2)_. (1) (2) A. 11 :00 ONLY B. 11:00 and through the Regenerative HX into the RCS C. 11:08 ONLY D. 11 :08 and through the Regenerative HX into the RCS Answer: A Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - {T-75 SUBMITTAL) 1 Answer Explanation D/STRACTOR ANALYSIS: A. Correct. For Part 1, an automatic Safety Injection occurs when PZR Pressure is < 1765 psig or Containment Pressure is> 4 psig). Consequently, 11 :00:00 is the earliest time that an automatic Safety Injection occurred. For Part 2, as part of the Safety Injection, 2CV68/69 (Chg. Line Containment lsol. Valves) will close. Consequently, After the Safety Injection has occurred, CCP flow will be directed through 2CV55 (CCP Flow Control Valve) into the RCP Seals ONLY. B. Incorrect but plausible. Part 1 is correct. For Part 2, when a Safety Injection is not present, CCP flow will be directed through 2CV55 (CCP Flow Control Valve) into the RCP Seals and into the RCS (thru the Regenerative HX). Consequently, the candidate could incorrectly conclude that after the Safety Injection has occurred, CCP flow will be directed through 2CV55 (CCP Flow Control Valve) into the RCP Seals and thru the Regenerative HX into the RCS. C. Incorrect but plausible. For Part 1, the candidate may recognize that at 11 :08:00, the automatic Safety Injection setpoint for low RCS pressure has been reached and incorrectly determine that 11 :08:00 is the earliest time that an automatic Safety Injection setpoint was reached. D. Incorrect but plausible. For Part 1, the candidate may recognize that at 11 :08:00, the automatic Safety Injection setpoint for low RCS pressure has been reached and incorrectly determine that 11 :08:00 is the earliest time that an automatic Safety Injection setpoint was reached. Question Number: 5 Tier: 2 Group 1 KIA: 006 Emergency Core Cooling System (ECCS)-K6.05-EA4.09 Ability to manually operate and/or monitor in the control room: PZR LCS and PZR PCS Importance Rating: 4.1 10 CFR Part 55: 41.7 / 45.5 to 45.8 10 CFR 55.43.b N/A Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '<IA Match: K/A is matched because the candidate must monitor for the proper response of the PZR LCS after an automatic Safety Injection occurs (ECCS Actuation: 2CV55 CCP Flow Control Valve directs flow from the CCPs to the RCP Seals while the charging line isolates (2CV68/69 close)). SRO Justification: N/A Technical NOS05FLUNCY-09 ( LICENSED OPERATOR FLUENCY LIST)

References:

NOS05ECCS00-09 ( EMERGENCY CORE COOLING SYSTEM) NOS05CVCS00-17 ( CHEMICAL AND VOLUME CONTROL SYSTEM) Proposed references None to be provided: Learning Objective: NOS05ECCS00-09 ( EMERGENCY CORE COOLING SYSTEM) 3 Describe the function and how their normal and abnormal operations affects the Chemical and Volume Control System:

• CCP Flow Control Valve, CV55
• Chg. Line Containment lsol. Valves, CV68, CV69 Cognitive Level:

Higher X Lower Question Source New -- Modified Bank X Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 6 Points: 1.00 Given:

• Cooling of the PRT is required Which ONE of the following completes the statements below?

Cooling of the PRT can be initiated MANUALLY _(1 )_. During PRT Cooling, the PRT is drained directly to the _(2)_. (1) (2) A. or AUTOMATICALLY RCDT B. or AUTOMATICALLY RCDT pump suction header ".,. ONLY RCDT D. ONLY RCDT pump suction header Answer: D Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Form Part 1, since there are many other processes that have automatic functions, the candidate could incorrectly conclude that PRT Cooling can be performed manually and automatically. For Part 2, since the draining of the PRT is ultimately pumped from the RCDTs, the candidate could incorrectly conclude that when the PRT is drained via PR14 directly into the RCDT (like so many other water sources). B. Incorrect but plausible. Form Part 1, since there are many other processes that have automatic functions, the candidate could incorrectly conclude that PRT Cooling can be performed manually and automatically. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, since the draining of the PRT is ultimately pumped from the RCDTs, the candidate could incorrectly conclude that when the PRT is drained via PR14 directly into the RCDT (like so many other water sources). D. Correct. For Part 1, PRT cooling is accomplished by a feed (via 2WR82) and bleed (via 2PR14) of the tank. Operation ofWR82 and PR14 can only be performed manually. For Part 2, during PRT Cooling, the PRT is drained directly to the RCDT pump suction header. Question Number: 6 Tier: 2 Group 1 KIA: 007 Pressurizer Relief Tank/Quench Tank System (PRTS)-K4.01 Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the following: Quench tank cooling Importance Rating: 2.6 10 CFR Part 55: 41.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know that a design feature of PRT cooling is that cooling can only be initiated manually with no automatic feature SRO Justification: N/A Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) Technical NOS05PZRPRT-06 ( PRESSURIZER AND PRESSURIZER

References:

RELIEF TANK) Proposed references None to be provided: Learning Objective: NOS05PZRPRT-06 ( PRESSURIZER AND PRESSURIZER RELIEF TANK) 3 Identify and describe the Control Room controls, indications, and alarms associated with the Pressurizer and Pressurizer Relief Tank, including:

a. The Control Room location of Pressurizer and Pressurizer Relief Tank control bezels and indications. (Licensed Operator & STA only)

b. The function of each Pressurizer and Pressurizer Relief Tank Control Room control and indication. (Licensed Operator & STA only)

c. The effect each Pressurizer and Pressurizer Relief Tank control has upon Pressurizer and Pressurizer Relief Tank components and operation. (Licensed Operator & STA only)

Cognitive Level: Higher - - Lower X Question Source New - - Modified Bank X Bank Question History: Comments: Page 3 of 7

EXAMINATION.ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 7 Points: 1.00 Given:

• Unit 2 is in MODE 3 At time 15:00:00
• BOTH 2R17A/B (Component Cooling Process Monitors) have just come into HI alarm At time 15:01 :00
• The crew has also initiated S2.0P-AB.CC-0001 (Component Cooling Abnormality) and S2.0P-AB.RAD-0001 (Abnormal Radiation)

At time 15:15:00

• Chemistry has verified a rise in Component Cooling activity Which ONE of the following completes the statements below?

At 15:00:30, 2CC149 (Surge Tank Vent Valve) is _(1 )_. i' CCW Surge Tank overflows, then the in-service Waste Holdup Tank _(2)_ will become contaminated. (1) (2) A. open and the 22 ABV Exhaust Filter Unit B. open ONLY C. closed and the 22 ABV Exhaust Filter Unit D. closed ONLY \nswer: C Page 1 of 6

EXAMINATION.ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Form Part 1, 2CC149 is normally open and the candidate could not recall that 2CC149 closes when 2R17A/B being in alarm. Consequently at 15:00:30, the candidate could incorrectly conclude that 2CC149 is open. Part 2 is correct. B. Incorrect but plausible. Form Part 1, 2CC149 is normally open and the candidate could not recall that 2CC149 closes when 2R17A/B being in alarm. Consequently at 15:00:30, the candidate could incorrectly conclude that 2CC149 is open. For Part 2, the candidate could fail to recognize the 22 ABV Exhaust Filter Unit will also become contaminated when the CCW Surge Tank overflows. C. Correct. For Part 1, 2CC149 automatically closes on high radiation alarm on 2R17 A/B. For Part 2, IAW S2.0P-AB.CC-0001 Step 3.8 NOTE, "Allowing CCW Surge Tank to overflow will contaminate the in-service Waste Holdup Tank and the 22 ABV Exhaust Filter Unit". D. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could fail to recognize the 22 ABV Exhaust Filter Unit will also become contaminated when the CCW Surge Tank overflows . .luestion Number: 7 Tier: 2 Group 1 KIA: 008 Component Cooling Water System (CCWS)-A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PRMS alarm. Importance Rating: 3.3 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.13 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must be able to predict how the CCWS will respond when 2R17 A/B (Component Cooling Process Monitors) come into alarm. Additionally, the candidate must also know what components will be contaminated if the CCWS Surge Tank Overflows. Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) <iRO Justification: N/A Technical NOS05CCW000-11 (COMPONENT COOLING WATER)

References:

Proposed references None to be provided: Learning Objective: NOS05CCW000-11 (COMPONENT COOLING WATER) 3 Describe how the following components impact the Component Cooling Water System during normal and abnormal conditions:

• CC-149, Surge Tank Vent Valve Cognitive Level:

Higher Lower X Question Source New X Modified Bank Bank - - Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 8 Points: 1.00 Given:

• The crew is attempting to maintain the PZR water saturated so 13 RCP can be restarted in accordance with 1-EOP-TRIP-5 (Natural Circulation Rapid Cooldown Without RVLIS)

Step 4

• PZR Pressure is 2005 psig
• PZR Liquid Temperature is 635 °F Which ONE of the following completes the statements below?

The PZR is _(1 )_. In accordance with the 1-EOP-TRIP-5, the reason for establishing and maintaining saturation conditions in the PZR is to limit the PZR pressure _(2)_ upon RCP restart. (1) (2) subcooled rise B. subcooled reduction C. water saturated rise D. water saturated reduction A.nswer: B Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, there are concerns for pressure to rise when an RCP is started when the plant is water solid. Consequently, the candidate could incorrectly that the reason for establishing and maintaining saturation conditions in the PZR is to limit the PZR pressure increase upon RCP restart IAW 1-EOP-TRIP-5. B. Correct. For Part 1, with PZR Pressure at 2005 psig (2020 psia), saturation temperature is 637 °F. Consequently, with PZR liquid temperature at 635 °F, the PZR is NOT water saturated. For Part 2, IAW 1-EOP-TRIP-5, "To limit the pressure decrease upon RCP restart, saturated conditions should first be established in the PZR." C. Incorrect but plausible. For Part 1, since the steam tables are listed in psia (not psig), the candidate could enter the steam tables at 1990 psia and incorrectly interpolate to determine that the PZR is watere saturated. For Part 2, there are concerns for pressure to rise when an RCP is started when the plant is water solid. Consequently, the candidate could incorrectly that the reason for establishing and maintaining saturation conditions in the PZR is to limit the PZR pressure increase upon RCP restart IAW 1-EOP-TRIP-5. D. Incorrect but plausible. For Part 1, since the steam tables are listed in psia (not psig), the candidate could enter the steam tables at 1990 psia an incorrectly interpolate to determine that the PZR is watered saturated. Part 2 is correct. Question Number: 8 Tier: 2 Group 1 KIA: 010 Pressurizer Pressure Control System (PZR PCS)-K5.01 Knowledge of the operational implications of the following concepts as they apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables Importance Rating: 3.5 10 CFR Part 55: 41.5 / 45.7 10 CFR 55.43.b N/A Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) KIA Match: KIA is matched because the candidate must be able to determine if the PZR is water saturated (using steam tables) and the reason (operational implication) the PZR is maintained water saturated when restarting an RCP IAW 1-EOP-TRIP-5 (Natural Circulation Rapid Cooldown Without RVLIS). SRO Justification: N/A Technical Steam Tables

References:

1-EOP-TRIP-5 (Natural Circulation Rapid Cooldown Without RVLIS) Proposed references None to be provided: Learning Objective: NOS05TRP004-06 ( EOP-TRIP 4,5,6; NATURAL CIRCULATION COOLDOWN) 4 Determine the basis for each step, caution, note or continuous action step relative to a NATURAL CIRCULATION COOLDOWN. ':ognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 9 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power
• A secondary transient is causing PZR pressure to rise At time 12:00:00
• PZR pressure is 2312 psig At time 12:00:30
• PZR pressure is 2340 psig Which ONE of the following completes the statements below?

At 12:00:00, PZR Spray Valves (2PS1 and 2PS3) are _(1 )_. At 12:00:30, PZR PORVs (2PR1 and 2PR2) are _(2)_. (1} (2) A. throttled open B. throttled closed C. fully open open D. fully open closed Answer: C Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANAL YS/S: A. Incorrect but plausible. For Part 1, 2315 psig is the PZR Pressure set point at which the PORVs would fully close. Consequently, the candidate could mistake the 2315 psig set point for when the PZR Spray valves go fully open. Consequently, the candidate would incorrectly conclude that at 12:00:00, the PZR Spray valves are throttled (and not fully open). Part 2 is correct. B. Incorrect but plausible. For Part 1, 2315 psig is the PZR Pressure set point at which the PORVs would fully close. Consequently, the candidate could mistake the 2315 psig set point for when the PZR Spray valves go fully open. Consequently, the candidate would incorrectly conclude that at 12:00:00, the PZR Spray valves are throttled (and not fully open). For Part 2, the PZR master controller setpoint is at 100% when PZR pressure is 2355 psig. The candidate could incorrectly conclude that the PZR PORVs open when the PZR master controller is at 100% (or 2355 psig). This would then cause the candidate to incorrectly conclude that at 12:00:30, the PZR PORVs are closed. C. Correct. For Part 1, with PZR Pressure at 2312, the PZR Spray Valves are fully open. For Part 2, with PZR Pressure at 2340, the PZR PORVS are open. D. Incorrect but plausible. Part 1 is correct. For Part 2, the PZR master controller setpoint is at 100% when PZR pressure is 2355 psig. The candidate could incorrectly conclude that the PZR PORVs open when the PZR master controller is at 100% (or 2355 psig). This would then cause the candidate to incorrectly conclude that at 12:00:30, the PZR PORVs are closed. Question Number: 9 Tier: 2 Group 1 KIA: 010 Pressurizer Pressure Control System (PZR PCS)-A3.02 Ability to monitor automatic operation of the PZR PCS, including: PZR pressure Importance Rating: 3.6 10 CFR Part 55: 41.7/45.5 10 CFR 55.43.b NIA KIA Match: K/A is matched because the candidate must be able to determine the automatic operation of PZR PCS components (PZR Spray Valves and PZR PO RVs) as a secondary transient causes PZR Pressure to rise over time. Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) SRO Justification: N/A Technical NOS05PZRP&L-10 ( PRESSURIZER PRESSURE AND LEVEL

References:

CONTROL) Proposed references None to be provided: Learning Objective: NOS05PZRP&L-10 ( PRESSURIZER PRESSURE AND LEVEL CONTROL) 4 Describe how the following components impact the Pressurizer Pressure and Level Control System during normal and abnormal conditions:

• Pressurizer Pressure Control and Alarm Channels
• Master Pressure Controller
• Spray Valves
• Power-Operated Relief Valves (PORVs)

Cognitive Level: Higher X Lower - - Question Source New X Modified Bank Bank - - Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 Points: 1.00 Which ONE of the following completes the statements below concerning the design of the Reactor Protection System (RPS)? Channel Redundancy_(1 ) _ prevent(s) a spurious reactor trip due to a single failure or malfunction within RPS. Bistables associated with a Reactor Trip are _(2)_ to actuate. (1) (2) A. ONLY energized

8. ONLY de-energized C. and Independence energized D. and Independence de-energized Answer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, candidates memorize Reactor Trip set points setpoint and the coincidences (e.g. 1865 psig 2 out 4 channels). Consequently, the candidate could incorrectly conclude that Channel Redundancy ONLY prevents a spurious reactor trip due to a single failure or malfunction within RPS. For Part 2, there are some ESF / RPS Bistables that energize to actuate (e.g. Containment Spray, P-6 and P-11 ). Consequently, the candidate could incorrectly conclude that bistables associated with a Reactor Trip are energized to actuate. B. Incorrect but plausible. For Part 1, candidates memorize Reactor Trip set points setpoint and the coincidences (e.g. 1865 psig 2 out 4 channels). Consequently, the candidate could incorrectly conclude that Channel Redundancy ONLY prevents a spurious reactor trip due to a single failure or malfunction within RPS. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, there are some ESF / RPS Bistables that energize to actuate (e.g. Containment Spray, P-6 and P-11 ). Consequently, the candidate could incorrectly conclude that bistables associated with a Reactor Trip are energized to actuate. D. Correct. For Part 1, Channel Redundancy and Independence prevent a spurious reactor trip due to a single failure or malfunction within RPS. For Part 2, bistables associated with a Reactor Trip are energized to actuate. Question Number: 10 Tier: 2 Group 1 KIA: 012 Reactor Protection System-K4.05 Knowledge of RPS design feature(s) and/or interlock(s) which provide for the following: Spurious trip protection Importance Rating: 2. 7 10CFRPart55: 41.7 10 CFR 55.43.b N/A Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) KIA Match: KIA is matched because the candidate must know that Channel Redundancy and Independence are the design features of RPS that prevent a spurious reactor trip due to a single failure or malfunction within RPS. SRO Justification: N/A Technical NOS05RXPROT-12 (REACTOR PROTECTION SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS05RXPROT-12 (REACTOR PROTECTION SYSTEM) 4 Describe the design bases of the RPS, including: (License Operator and STA only)

• Redundancy
• Independence
• Diversification
• Fail Safe
• Testability Cognitive Level:

Higher -- Lower X Question Source New X Modified Bank Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) 11 Points: 1.00 Which ONE of the following completes the statement below concerning RCP Undervoltage Reactor Trip Setpoint and Coincidence? If the associated Permissive Interlock is satisfied, a Reactor Trip Signal will be generated when 4KV Group Susses H and _(1 ) _ are less than a maximum of _(2)_ % of normal bus voltage. (1) (2) A. G 70 B. G 90 C. E 70 D. E 90 A.nswer: A Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - {T-75 SUBMITTAL) Answer Explanation DISTRACTOR ANALYSIS: A. Correct. If the associated Permissive Interlock is satisfied, a Reactor Trip Signal will be generated when 4KV Group Busses H and G are less than a maximum of 70% of normal bus voltage. B. Incorrect but plausible. Part 1 is correct. For Part 2, 90% is setpoint for the RCP Low Flow Reactor Trip. Consequently, the candidate could incorrectly conclude that 90% normal bus voltage is the set point for the RCP Undervoltage Reactor Trip. C. Incorrect but plausible. For Part 1, the RCP Undervoltage Reactor Trip is based on two selected 4KV Group Busses in an undervoltage condition. Consequently, the candidate could incorrectly conclude that 2 of the selected 4KV Group Busses are H and E. Part 2 is correct. Part 2 is correct. D. Incorrect but plausible. For Part 1, the RCP Undervoltage Reactor Trip is based on two selected 4KV Group Busses in an undervoltage condition. Consequently, the candidate could incorrectly conclude that 2 of the selected 4KV Group Busses are H and E. Part 2 is correct. For Part 2, 90% is setpoint for the RCP Low Flow Reactor Trip. Consequently, the candidate could incorrectly conclude that 90% normal bus voltage is the set point for the RCP Undervoltage Reactor Trip. Question Number: 11 Tier: 2 Group 1 KIA: 013 Engineered Safety Features Actuation System (ESFAS)-K1 .02 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems: RCP Importance Rating: 3.2 10 CFR Part 55: 41.2 to 41.9 / 45.7 to 45.8 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must the physical connection between the RCP and ESFAS. The physical connection is RCP undervoltage causes a Reactor Trip (ESFAS Function). SRO Justification: N/A Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) Technical NOS05FLUNCY-09 (LICENSED OPERATOR FLUENCY LIST)

References:

Proposed references None to be provided: Learning Objective: NOS05FLUNCY-09 (LICENSED OPERATOR FLUENCY LIST) 4 State those items in the Licensed Operator Fluency List

• Permissives and Control Grade Interlocks
• Reactor Trips Cognitive Level:

Higher - - Lower X Question Source New - - Modified Bank - - Bank X Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 12 Points: 1.00 Consider the following Containment Cooling configurations with a OBA occurring inside containment:

1. ONLY ONE CS Pump operating

2. ONLY ONE CS Pump operating plus ONLY 3 CFCUs operating

3. ONLY ONE CS Pump operating plus ONLY 2 CFCUs operating

4. ONLY 5 CFCUs operating Which ONE of the following completes the statements below?

Containment Cooling configurations will maintain Containment Pressure, Temperature and Humidity with design limits with a OBA occurring inside containment. A. 1 and 3 B. 1 and 4 C. 2 and 4

0. 2 and 3 Answer: C Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Since all of the given Containment Cooling configurations are possible containment cooling configurations, then all of the distractors are plausible. B. Incorrect but plausible. Since all of the given Containment Cooling configurations are possible containment cooling configurations, then all of the distractors are plausible. C. Correct. The following Containment Cooling configurations will maintain Containment Pressure, Temperature and Humidity with design limits with a OBA occurring inside containment: 2 CS Pumps (not given in question stem), 1 CS Pump + 3 CFCUs, and 5 CFCUs. D. Incorrect but plausible. Since all of the given Containment Cooling configurations are possible containment cooling configurations, then all of the distractors are plausible. Question Number: 12 Tier: 2 Group 1 KIA: 022 Containment Cooling System (CCS)-A1 .03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Containment humidity Importance Rating: 3.2 10 CFR Part 55: 41.5 / 45.5 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the operating Containment Cooling configuration (CS Pumps and CFCUs) that will maintain Containment Pressure, Temperature and Humidity with design limits with a OBA occurring inside containment SRO Justification: N/A Technical NOSOSCONTMT-15 ( CONTAINMENT AND CONTAINMENT

References:

SUPPORT SYSTEMS) Proposed references None to be provided: Page 2 of 4

EXAMINATION AbJSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL)

• .earning Objective: NOS05CONTMT-15 ( CONTAINMENT AND CONTAINMENT SUPPORT SYSTEMS) 4 Describe how the following components impact the Containment and Containment Support Systems during normal and abnormal conditions
• Containment Fan Cooler System Cognitive Level:

Higher - - Lower X Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) 13 Points: 1.00 Which ONE of the following completes the statements below? _(1 ) _ is added to Containment Spray flow to remove elemental iodine from the containment atmosphere _(2)_. (1) (2) A. Sodium Hydroxide ONLY B. Sodium Hydroxide and to reduce corrosion of containment components C. Hydrazine ONLY D. Hydrazine and to reduce corrosion of containment components Answer: B Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANAL YS/S: A. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate may fail to recall that NaOH is also used to prevent corrosion of containment components.

8. Correct. NaOH is added to Containment Spray flow to remove elemental iodine from the containment atmosphere and to prevent corrosion of containment components.

C. Incorrect but plausible. For Part 1, Hydrazine is a familiar chemical added to the RCS to scavenge oxygen. Consequently, the candidate may incorrectly conclude Hydrazine is added to Containment Spray flow. For Part 2, the candidate may fail to recall that NaOH is also used to prevent corrosion of containment components. D. Incorrect but plausible. For Part 1, Hydrazine is a familiar chemical added to the RCS to scavenge oxygen. Consequently, the candidate may incorrectly conclude Hydrazine is added to Containment Spray flow. Question Number: 13 Tier: 2 Group 1 KIA: 026 Containment Spray System (CSS)-G2.1.27 Knowledge of system purpose and/or function Importance Rating: 3.9 10 CFR Part 55: 41.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know that removing elemental iodine from the containment atmosphere and preventing corrosion of containment components are functions of the Containment Spray System. SRO Justification: N/A Technical NOSOSCSPRAY-06 ( CONTAINMENT SPRAY SYSTEM)

References:

Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) Proposed references None to be provided: Learning Objective: NOS05CSPRAY-06 ( CONTAINMENT SPRAY SYSTEM) 2 Describe the purpose of the Containment Spray System.

3. Describe the design bases of the Containment Spray System Cognitive Level:

Higher - - Lower X Question Source New - - Modified Bank X Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 14 Points: 1.00 Given:

• A LOCA coincident with a Loss Of Offsite Power has occurred at Unit 2
• The 2C 4KV Vital Bus is de-energized due to a fault on the bus At time 16:30:00
• Containment Pressure is 15.1 psig and slowly rising At 16:30:30, which ONE of the following completes the statements below?

___ Containment Spray Pump(s) is/ are running A. NO

8. BOTH V, ONLY21 D. ONLY 22 Answer: C Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. The candidate could incorrectly conclude that at 16:30:00, the Containment Spray setpoint has not been reached or that the electrical transient has affected both CS pumps. In either case, the candidate would then incorrectly deduce that at 16:30:00, no CS pumps are running. B. Incorrect but plausible. The candidate could incorrectly conclude that both CS pumps are not powered from the 2C 4KV Vital Bus. Consequently, with a valid Containment Spray signal present at 16:30:00, the candidate would incorrectly deduce that both CS pumps are running. C. Correct. 21 CS Pump is powered from 2A KV Vital Bus and 22 CS Pump is powered from 2C 4K Vital Bus. Additionally, a Containment Spray actuation occurs at 15 psig Containment pressure. At 16:30:00, a containment spray actuation signal exists and 2C 4K Vital Bus is de-energized. Consequently, ONLY 21 CS Pump is running. D. Incorrect but plausible. The candidate could incorrectly conclude that only the 21 CS Pump is powered from 2C KV Vital Bus. Consequently, with a valid Containment Spray signal present at 16:30:00, the candidate would incorrectly deduce that only 22 CS pump is running. Question Number: 14 Tier: 2 Group 1 KIA: 026 Containment Spray System (CSS)-K2.01 Knowledge of bus power supplies to the following: Containment spray pumps Importance Rating: 3.4 10 CFR Part 55: 41.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must demonstrate knowledge of the power supplies to both Containment Spray Pumps by determining which pumps will be running after an electrical transient has cause the 2C 4KV Vital bus to de-energize. SRO Justification: N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Technical NOS05FLUNCY-09 (LICENSED OPERATOR FLUENCY LIST)

References:

NOS05CSPRAY-06 ( CONTAINMENT SPRAY SYSTEM) Proposed references None to be provided: Learning Objective: NOS05CSPRAY-06 ( CONTAINMENT SPRAY SYSTEM) 3 State the power supply to the following Containment Spray System components:

a. Containment Spray Pumps.

Cognitive Level: Higher X Lower Question Source New - - Modified Bank X Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 15 Points: 1.00 Given:

• 21 SG has a confirmed tube leak
• The crew is preparing to adjust 21MS10 (MS PWR RELIEF Viv) setpoint in accordance with S2.0P-AB.SG-0001 (Steam Generator Tube Leak)

Which ONE of the following completes the statements below? The PO will set the 21MS10 setpoint to _(1 ) _ psig by depressing button _(2)_ .. (1) (2) A. 1045 A B. 1045 B C. 1070 A D. 1070 B Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation D/STRACTOR ANAL YS/S: A. Correct. For Part 1, IAW S2.0P-AB.SG-0001 Step 3.31, the 21MS10 setpoint will be set to 1045 psig. For Part 2, button 1 will be depressed on the 21MS10 controller to raise the set point. B. Incorrect but plausible. Part 1 is correct. For Part 2, button 2 on the 21MS10 is used to raise the manual output to the valve so it opens more. Consequently, the candidate could incorrectly conclude that button 2 actually raises the controller's setpoint. C. Incorrect but plausible. For Part 1, 1070 psig is a familiar pressure (setpoint for MS15 (Main Steam Safety Valve). Consequently, the candidate could incorrectly conclude that the MS10 controller will be adjusted to 1070 psig. Part 2 is correct. D. Incorrect but plausible. For Part 1, 1070 psig is a familiar pressure (setpoint for MS15 (Main Steam Safety Valve). Consequently, the candidate could incorrectly conclude that the MS10 controller will be adjusted to 1070 psig. For Part 2, button 2 on the 21MS10 is used to raise the manual output to the valve so it opens more. Consequently, the candidate could incorrectly conclude that button 2 actually raises the controller's setpoint. Question Number: 15 Tier: 2 Group 1 KIA: 039 Main and Reheat Steam System (MRSS)-G2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels Importance Rating: 4.6 10 CFR Part 55: 41.6/41.7/45.2 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know how to adjust the 21MS10 (MS PWR RELIEF Viv) controller due to a confirmed 21 SG Tube Leak SRO Justification: N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Technical NOS05ABSGTL-05 ( STEAM GENERATOR TUBE LEAK) i{eferences: Proposed references None to be provided: Learning Objective: NOS05ABSGTL-05 ( STEAM GENERATOR TUBE LEAK) 3 Describe, in general terms, the actions taken in S1/S2.0P-AB.SG-0001 and the bases for the actions in accordance with the Technical Bases Document Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 16 Points: 1.00 Given:

• The crew is performing S2.0P-SO.MS-0001 (Main, Reheat, Turbine Bypass Steam Warmup) and is preparing to open 21-24MS167 (Main Steam Isolation Valves)

In accordance with S2.0P-S0.MS-0001, which ONE of the following completes the statements below? The reason that 21-24MS7 (Main Steam Loop Drain Valves) are opened before 21-24MS167 is to _(1)_. The crew will open 21-24MS167 when there is less than a MAXIMUM of _(2)_ psid across each valve. A. (1) prevent pressurized steam from forcing residual water in the piping to cause water hammer on downstream components (2) 15 B. (1) prevent pressurized steam from forcing residual water in the piping to cause water hammer on downstream components (2) 50 C. (1) remove any collected corrosion products or impurities to ensure Main Turbine blading is not impinged (2) 15 D. (1) remove any collected corrosion products or impurities to ensure Main Turbine blading is not impinged (2) 50 Answer: B Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, there are multiple steps in S2.0P-SO.MS-0001 that require actions to be performed when MS Header pressure is~ 15 psig. Consequently, the candidate could incorrectly conclude that 21-24MS167 will be opened when there is less than a maximum of 15 psid across each valve. B. Correct. For Part 1, the reason that 21-24MS7 (Main Steam Loop Drain Valves) are opened before 21-24MS 167 is to prevent pressurized steam from forcing residual water in the piping to cause water hammer on downstream components. For Part 2, The crew will open 21-24MS167 when there is less than a maximum of 50 psid across each valve. C. Incorrect but plausible. For Part 1, preventing damage to the Turbine is a general concern and the candidate could incorrectly conclude that The reason that 21-24MS7 (Main Steam Loop Drain Valves) are opened before 21-24MS167 is to remove any collected corrosion products or impurities to ensure Main Turbine blading is not impinged. For Part 2, there are multiple steps in S2.0P-SO.MS-0001 that require actions to be performed when MS Header pressure is~ 15 psig. Consequently, the candidate could incorrectly conclude that 21-24MS167 will be opened when there is less than a maximum of 15 psid across each valve. D. Incorrect but plausible. For Part 1, preventing damage to the Turbine is a general concern and the candidate could incorrectly conclude that The reason that 21-24MS7 (Main Steam Loop Drain Valves) are opened before 21-24MS167 is to remove any collected corrosion products or impurities to ensure Main Turbine blading is not impinged. Part 2 is correct. Question Number: 16 Tier: 2 Group 1 KIA: 039 Main and Reheat Steam System (MRSS)- K5.01 Knowledge of the operational implications of the following concepts as the apply to the MRSS: Definition and causes of steam/water hammer Importance Rating: 2.9 10 CFR Part 55: 41.5 / 45.7 10 CFR 55.43.b NIA Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) KIA Match: KIA is matched because the candidate must know could cause water hammer when the MSS is warmed. SRO Justification: N/A Technical S2.0P-SO.MS-0001

References:

Proposed references None to be provided: Learning Objective: NOSOSMSTEAM-11 ( MAIN STEAM SYSTEM ) 14 Given internal or external industry operating experience, review the OE and outline a course of action, which could prevent recurrence. Cognitive Level: Higher -- Lower X Question Source New -- Modified Bank X Bank Question History: Modified From a Question that was on the ILOT 0901 NRC RO Exam Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem !LOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 17 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power and stable At time 09:00:00
• The suction pressure transmitter for the 22 SGFP FAILS to 200 psig Which ONE of the following completes the statements below?

The 22 SGFP will TRIP _(1)_. After 22 SGFP has tripped, Reactor Power will stabilize at approximately _(2)_ %. (1) (2) A. IMMEDIATELY (at 09:00:00) 50

8. IMMEDIATELY (at 09:00:00) 66 C. at 09:00:10 (after a 10 second delay) 50 D. at 09:00:10 (after a 10 second delay) 66 Answer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITIAL) ' Answer Explanation D/STRACTOR ANAL YS/S: A. Incorrect but plausible. For Part 1, there is an instantaneous SGFP trip on low suction pressure (< 190 psig). The candidate could incorrectly conclude that given the question stem, that the SGFP will trip instantaneously at 09:00:01. For Part 2, there are only two SGFPs. The candidate could incorrectly conclude that each SGFP provides 50% total flow. Consequently when 22 SGFP trips, the candidate could incorrectly conclude that a turbine runback will occur to 50% and reactor power will then stabilize at 50%. B. Incorrect but plausible. For Part 1, there is an instantaneous SGFP trip on low suction pressure ( < 190 psig). The candidate could incorrectly conclude that given the question stem, that the SGFP will trip instantaneously at 09:00:01. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, there are only two SGFPs. The candidate could incorrectly conclude that each SGFP provides 50% total flow. Consequently when 22 SGFP trips, the candidate could incorrectly conclude that a turbine runback will occur to 50% and reactor power will then stabilize at 50%. D. Correct. For Part 1, the SGP will trip when suction pressure is less than 215 psig for 10 seconds. Consequently, given the question stem, 09:00:11 is the LATEST time that the 22 SGFP TRIPS. For Part 2, once 22 SGFP trips and turbine runback to 66% will be generated. Since Reactor Power follows steam demand, Reactor Power will stabilize at approximately 66%. Question Number: 17 Tier: 2 Group 1 KIA: 059 Main Feedwater (MFW) System-A 1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including: Power level restrictions for operation of MFW pumps and valves Importance Rating: 2.7 10 CFR Part 55: 41.5 / 45.5 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the maximum allowable reactor power following a SGFP trip with the Reactor Power initially at 100% power. Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) <3RO Justification: N/A Technical NOS05CN&FDW-15 (CONDENSATE AND FEEDWATER

References:

SYSTEM) Proposed references None to be provided: Learning Objective: NOS05CN&FDW-15 (CONDENSATE AND FEEDWATER SYSTEM) 8 Identify and describe the Control Room controls, indications, and alarms associated with the Condensate and Feedwater System, including:

a. The Control Room location of Condensate and Feedwater System control bezels and indications.

(Licensed Operator & STA only)

b. The function of each Condensate and Feedwater System Control Room control and indication. (Licensed Operator

                                      & STA only)

c. The effect each Condensate and Feedwater System control has upon Condensate and Feedwater System components and operation. (Licensed Operator & STA only)

Cognitive Level: Higher X Lower Question Source New - - Modified Bank X Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) 18 Points: 1.00 Given:

• Unit 2 is 100% Reactor Power and stable
• S2.0P-PT.AF-0002 (Auxiliary Feedwater Backleakage) Section 5.1 (Backleakage Monitoring and Determination) has just been completed
• Indications show there is backleakage on the 23 Auxiliary Feedwater line In accordance with S2.0P-PT.AF-0002, which ONE of the following completes the statements below?

S2.0P-PT.AF-0002 was REQUIRED to be performed _(1 ) _ after an AFW Pump was initially shutdown in MODES 1-3. The crew will start _(2)_ AFW Pump to cooldown the 23 Auxiliary Feedwater line and help reseat the leaking check valve which is causing the backleakage. (1) (2) A. IMMEDIATELY 22 B. IMMEDIATELY 21 C. between 30 to 60 minutes 22 D. between 30 to 60 minutes 21 Answer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) ! Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that S2.0P-PT.AF-0002 is required to be performed immediately after an Auxiliary Feedwater Pump is shutdown in Modes 1-3. For Part 2, if the backleakage had been on the 21 or 22 AF lines then the crew would start the 22 AFW Pump to cooldown the affected line and help reseat the leaking check valve which is causing the backleakage. Consequently, the candidate could fail to properly recall which AF lines are fed by the 21 and 22 AFW pumps. This would cause the candidate to incorrectly conclude that the 22 AFW pump is started when backleakage is indicated on the 23 AF line. B. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that S2.0P-PT.AF-0002 is required to be performed immediately after an Auxiliary Feedwater Pump is shutdown in Modes 1-3. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, if the backleakage had been on the 21 or 22 AF lines then the crew would start the 22 AFW Pump to cooldown the affected line and help reseat the leaking check valve which is causing the backleakage. Consequently, the candidate could fail to properly recall which AF lines are fed by the 21 and 22 AFW pumps. This would cause the candidate to incorrectly conclude that the 22 AFW pump is started when backleakage is indicated on the 23 AF line. D. Correct. For Part 1, IAW S2.0P-PT.AF-0002 P&L 3.1, "This procedure shall be performed 30 to 60 minutes after an Auxiliary Feedwater Pump is shutdown in Modes 1-3". For Part 2, 23 AF line was the affected AF line with the backleakage. Consequently, the crew will perform IAW S2.0P-PT.AF-0002 Section 5.3 (21 Auxiliary Feedwater Pump/Piping Cooldown) which has the crew start 21 AFW Pump to provide AFW flow through the 23 AF line which will cooldown the 23 AF line and help reseat the leaking check valve which is causing the backleakage. Question Number: 18 Tier: 2 Group 1 KIA: 061 Auxiliary/ Emergency Feedwater (AFW) System - A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Back leakage of MFW Importance Rating: 2.7 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.13 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know when to test for backleakage from the MFW into the AFW system and how to mitigate the backleakage IAW S2.0P-PT.AF-0002 (Auxiliary Feedwater Backleakage ). SRO Justification: N/A Technical NOS05AFW000-15 (AUXILIARY FEEDWATER SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS05AFW000-15 (AUXILIARY FEEDWATER SYSTEM) 10 Given a situation dealing with Auxiliary Feedwater System operability, examine the situation and apply the appropriate Technical Specification action. 13 Discuss the procedural requirements associated with the Auxiliary Feedwater System, including an explanation of major precaution and limitations in the Auxiliary Feedwater System procedures Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 19 Points: 1.00 Given:

• Unit 2 is MODE 3
• 2A 4KV Vital Bus is powered from 23 SPT
• 28 and 2C 4KV Vital Susses are powered from 24 SPT Subsequently
• The 23 SPT fails to O VAC Which ONE of the following completes the statement below?

The 23 SPT Supply Breaker to 2A 4KV Vital Bus will FIRST open when 23 SPT Voltage lowers to less than a MAXIMUM of _(1 )_%of normal voltage. After the electrical transient is complete, 2A 4KV Vital Bus will be powered by _(2)_ . (1) (2) A. 70 EDG2A B. 35 EDG2A C. 70 24SPT D. 35 24SPT Answer: C Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANAL YS/S: A. Incorrect but plausible. Part 1 is correct. For Part 2, EDG 2A can power the 2A 4KV Vital bus. Consequently, the candidate could incorrectly conclude that when 23ASD breaker opens, EDG 2A will power the 2A 4KV Bus.

8. Incorrect but plausible. For Part 1, 35% of bus normal voltage is permissive setpoint which allows breaker 24 ASD to close to power the 2A 4KV Vital Bus. Consequently, the candidate could incorrectly conclude that the 23 SPT Supply Breaker to 2A 4KV Vital Bus will FIRST open when 23 SPT Voltage lowers to less than a MAXIMUM of 35 % of normal voltage. For Part 2, EDG 2A can power the 2A 4KV Vital bus. Consequently, the candidate could incorrectly conclude that when 23ASD breaker opens, EDG 2A will power the 2A 4KV Bus.

C. Correct. For Part 1, the 23 SPT Supply Breaker to 2A 4KV Vital Bus will FIRST open when 23 SPT Voltage lowers to less than a MAXIMUM of 70 % of normal voltage. For Part 2, after the electrical transient is complete, 2A 4KV Vital Bus will be powered by 24 SPT. D. Incorrect but plausible. For Part 1, 35% of bus normal voltage is permissive setpoint which allows breaker 24 ASD to close to power the 2A 4KV Vital Bus. Consequently, the candidate could incorrectly conclude that the 23 SPT Supply Breaker to 2A 4KV Vital Bus will FIRST open when 23 SPT Voltage lowers to less than a MAXIMUM of 35 % of normal voltage. Part 2 is correct. Question Number: 19 Tier: 2 Group 1 KIA: 062 AC Electrical Distribution System-A1 .03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Effect on instrumentation and controls of switching power supplies Importance Rating: 2.5 10 CFR Part 55: 41.5 / 45.5 10 CFR 55.43.b NIA Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) KIA Match: K/A is matched because the candidate must know the instrumentation / controls that starts the power transfer from the failed 23 SPT to 2A 4KV Vital Bus. The candidate must also predict and monitor the proper power transfer of the 2A 4KV Vital Bus after the 23 SPT supply breaker opens. SRO Justification: N/A Technical NOS054KVAC0-08 (4160 ELECTRICAL SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS054KVAC0-08 (4160 ELECTRICAL SYSTEM) 9 State the setpoints, coincidence, blocks and permissives for automatic actuations associated with the 4160 Electrical System Cognitive Level: Higher X Lower Question Source New - - Modified Bank - - Bank X Question History: Comments: Page 3 of 6

    *I             EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T -75 SUBMITTAL) 20                                                                            Points: 1.00 Which ONE of the following completes the statements below concerning the Unit 1 250 VDC system?

The Unit 1 ___ is / are powered from the Unit 1 250 VDC Battery and Charger System. A. Field Excitation Circuitry for the EDGs

8. Main Turbine Emergency Oil Pump C. Vital Instrument Bus Inverters D. Emergency Lighting Inverters Answer: 8 Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. All of the distractors are powered from the Unit 1 125 VDC Battery and Charger System. Consequently, the candidate could incorrectly conclude that any of the distractors are powered from the Unit 1 250 VDC Battery and Charger System.

8. Correct. The Unit 1 Main Turbine Emergency Oil Pump is powered from the Unit 1 250 voe Battery and Charger System.

C. Incorrect but plausible. All of the distractors are powered from the Unit 1 125 VDC Battery and Charger System. Consequently, the candidate could incorrectly conclude that any of the distractors are powered from the Unit 1 250 VDC Battery and Charger System. D. Incorrect but plausible. All of the distractors are powered from the Unit 1 125 VDC Battery and Charger System. Consequently, the candidate could incorrectly conclude that any of the distractors are powered from the Unit 1 250 VDC Battery and Charger System. Question Number: 20 Tier: 2 Group 1 KIA: 063 D.C. Electrical Distribution-K2.01 Knowledge of bus power supplies to the following: Major DC loads Importance Rating: 2.9 10 CFR Part 55: 41.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know that the Unit 1 Main Turbine Emergency Oil Pump is a major DC load that is powered from the Unit 1 250 VDC Battery and Charger System SRO Justification: N/A Page 2 of 7

    ,.          EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL)

""echnical NOS05DCELEC-09 (DC ELECTRICAL SYSTEMS) Keferences: Proposed references None to be provided: Learning Objective: NOS05DCELEC-09 (DC ELECTRICAL SYSTEMS) 3 Identify and describe the local controls and indications associated with the DC Electrical System, including:

a. The location of DC Electrical System local controls and indications. (Licensed Operator & Non-licensed Operator only)

b. The function of DC Electrical System local controls and indications. (Licensed Operator & Non-licensed Operator only)

c. The plant and conditions or permissives required for DC Electrical System local controls to perform their intended function. (Licensed Operator & Non-licensed Operator only)

d. The setpoints associated with the DC Electrical Systems local alarms.

Cognitive Level: Higher - - Lower X Question Source New - - Modified Bank X Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -{T-75 SUBMITTAL) 21 Points: 1.00 In accordance LCO 3.8.1.2 (ELECTRICAL POWER SYSTEMS - SHUTDOWN), which ONE of the following completes the statements below? LCO 3.8.1.2 requires a MINIMUM of _(1 ) _ separate and independent diesel generators to be OPERABLE. If ALL REQUIRED EDGs are inoperable, the crew _(2)_ required to IMMEDIATELY suspend all operations involving positive reactivity changes. (1) (2) A. two is B. two is NOT C. three is D. three is NOT Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, LCO 3.8.1.2 requires a minimum of two separate and independent diesel generators to be OPERABLE. For Part 2, If ALL REQUIRED EDGs are inoperable, the crew is required to IMMEDIATELY suspend all operations involving positive reactivity changes B. Incorrect but plausible. Part 1 is correct. For Part 2, LCO 3.8.1.2 REQUIRED ACTION A has an option to ONLY declare the affected required features inoperable in lieu of suspending all operations involving positive reactivity changes. Consequently, the candidate could incorrectly conclude that LCO 3.8.1.2 REQUIRED ACTION B does not require suspending all operations involving positive reactivity changes. C. Incorrect but plausible. For Part 1, LCO 3.8.1.2 (ELECTRICAL POWER SYSTEMS - OPERATING) requires a minimum of three separate and independent diesel generators to be OPERABLE. Consequently, the candidate could incorrectly conclude that LCO 3.8.1.2 also requires a minimum of three separate and independent diesel generators to be OPERABLE. Part 2 is correct. D. Incorrect but plausible. For Part 1, LCO 3.8.1.2 (ELECTRICAL POWER SYSTEMS - OPERATING) requires a minimum of three separate and independent diesel generators to be OPERABLE. Consequently, the candidate could incorrectly conclude that LCO 3.8.1.2 also requires a minimum of three separate and independent diesel generators to be OPERABLE. For Part 2, LCO 3.8.1.2 REQUIRED ACTION A has an option to ONLY declare the affected required features inoperable in lieu of suspending all operations involving positive reactivity changes. Consequently, the candidate could incorrectly conclude that LCO 3.8.1.2 REQUIRED ACTION B does not require suspending all operations involving positive reactivity changes. Question Number: 21 Tier: 2 Group 1 KIA: 064 Emergency Diesel Generators (ED/G)-G2.2.22 Knowledge of limiting conditions for operations and safety limits Importance Rating: 4.0 10 CFR Part 55: 41.5 / 43.2 / 45.2 10 CFR 55.43.b N/A Page 2 of S

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) '<IA Match: K/A is matched because the candidate must how many separate and independent diesel generators are required to be OPERABLE per LCO 3.8.1.2 (ELECTRICAL POWER SYSTEMS - SHUTDOWN). SRO Justification: N/A Technical NOS05EDG000-12 (EMERGENCY DIESEL GENERATORS)

References:

Proposed references None to be provided: Learning Objective: NOS05EDG000-12 (EMERGENCY DIESEL GENERATORS) 10 Given a situation dealing with Emergency Diesel Generator operability, examine the situation and apply the appropriate Technical Specification action Cognitive Level: Higher Lower X Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam-(T-75 SUBMITTAL- MGMT ONLY) 22 Points: 1.00 Given: At time 10:00:00

• A Reactor Trip and Safety Injection have occurred coincident with a LOOP at Unit 2
• EOG 28 can NOT be started At 10:15:00, which ONE of the following completes the statement below?

22 RHR Pump is _(1 ) _ and 22 SI Pump is _(2)_. (1) (2) A. stopped running B. stopped stopped C. running running D. running stopped Answer: A Page 1 of 4

EXAMINATION ANSWER KEY *I Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL- MGMT ONLY) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. 22 RHR pump is powered from 2B 4KV Vital Bus and 22 SI Pump is powered from 2C 4KV Vital Bus. Additionally, 28 EOG can not be started after the LOOP occurs. Consequently, 15 minutes after a reactor trip and safeguards have occurred (coincident with the loop), 2A and 2C Vital Susses are being powered from EOG 2A and EOG 2C and all of the appropriate ECCS loads have been loaded onto the running EDGs. Therefore, at 10:15:00, 22 RHR Pump is stopped and 22 SI Pump is running.

8. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that 22 SI pump is powered from 28 4KV Vital Bus. This would result in the candidate incorrectly deducing that at 10:15:00, the 22 SI Pump is stopped.

C. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that 22 RHR pump is powered from 2C 4KV Vital Bus. This would result in the candidate incorrectly deducing that at 10:15:00, the 22 RHR Pump is running. Part 2 is correct. D. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that 22 RHR pump is powered from 2C 4KV Vital Bus. This would result in the candidate incorrectly deducing that at 10:15:00, the 22 RHR Pump is running. For Part 2, the candidate could incorrectly conclude that 22 SI pump is powered from 28 4KV Vital Bus. This would result in the candidate incorrectly deducing that at 10:15:00, the 22 SI Pump is stopped. Question Number: 22 Tier: 2 Group 1 KIA: 064 Emergency Diesel Generators (ED/G)-K3.02 Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following: ESFAS controlled or actuated systems Importance Rating: 4.2 10 CFR Part 55: 41.7 / 45.6 10 CFR 55.43.b N/A Page 2 of 4

EXAM.INATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T*75 SU BM ITTAL - MGMT ONLY) '<IA Match: K/A is matched because the candidate must be determine the status of the 22 RHR Pump and 22 SI Pump (ESFAS actuated components) following a Reactor Trip and Safety Injection actuation coincident with a LOOP and failure of EOG 28. SRO Justification: N/A Technical NOS054KVAC0-08 (4160 ELECTRICAL SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS054KVAC0-08 (4160 ELECTRICAL SYSTEM) 9 State the setpoints, coincidence, blocks and permissives for automatic actuations associated with the 4160 Electrical System Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 4

EXAMlNATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) 23 Points: 1.00 Given:

• Unit 1 and Unit 2 are at 100% Reactor Power At time 17:00
• 1R19A (Steam Generator Slowdown Liquid Monitor) goes into WARNING At time 19:45
• 2R19C (Steam Generator Slowdown Liquid Monitor) goes into WARNING Which ONE of the following completes the statements below?

At 17:01, 11GB185 (Slowdown Discharge to Condenser) is_(1)_. At 19:46, 23GB185 (Slowdown Discharge to Condenser) is _(2)_. (1} (2) A. closed open

8. closed closed C. open open D. open closed Answer: D Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the candidate may incorrectly conclude that for Unit 1, there are automatic functions when a R19 goes in to warning. Consequently, the candidate would then incorrectly deduce that at 19:46:00, 23GB185 (Slowdown Discharge to Condenser) is closed. For Part 2, the candidate may incorrectly conclude that for Unit 2, there are no automatic functions when a R19 goes in to warning. Consequently, the candidate would then incorrectly deduce that at 19:46:00, 23GS185 (Slowdown Discharge to Condenser) is open. S. Incorrect but plausible. For Part 1, the candidate may incorrectly conclude that for Unit 1, there are automatic functions when a R19 goes in to warning. Consequently, the candidate would then incorrectly deduce that at 19:46:00, 23GS185 (Slowdown Discharge to Condenser) is closed. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate may incorrectly conclude that for Unit 2, there are no automatic functions when a R19 goes in to warning. Consequently, the candidate would then incorrectly deduce that at 19:46:00, 23GS185 (Slowdown Discharge to Condenser) is open. D. Correct. For Part 1, Unit 1 has no automatic functions when a R19 goes in to warning. Automatic functions only occur when the monitor goes into alarm. Consequently, with 1R19A in warning (at 17:01 :00), 11GS185 (Slowdown Discharge to Condenser) is open. For Part 2, Unit 2 has automatic functions that occur when a R19 goes in to warning. Consequently, with 2R19C in warning (at 19:46:00), 23GS185 (Slowdown Discharge to Condenser) is closed. Question Number: 23 Tier: 2 Group 1 KIA: 073 Process Radiation Monitoring (PRM) System-K4.01 Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint Importance Rating: 4.0 10 CFR Part 55: 41.7 10 CFR 55.43.b N/A Page 2 of 5

EXAMLNATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) '<IA Match: KIA is matched because the candidate must know the design features of the R19 process radiation monitors at Unit 1 and Unit 2. In this case, there are unit differences and only Unit 2 will automatically terminate the release when the applicable R19 monitor goes into warning. SRO Justification: N/A Technical NOS05RMS000-17 (RADIATION MONITORING SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS05RMS000-17 (RADIATION MONITORING SYSTEM) 5 NCT Outline the interlocks associated with the following Radiation Monitoring System components:

• R19A, B, C, & D, Steam Generator Slowdown Liquid Monitors Cognitive Level:

Higher X Lower Question Source New -- Modified Bank X Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 24 Points: 1.00 Given:

• The crew is performing S2.0P-AB.SW-0001 (Loss of Service Water Header Pressure)
• The leak is determined to be downstream of 21 SW22 (NUCLEAR HEADER)

Which ONE of the following completes the statements below? In accordance with is S2.0P-AB.SW-0001, the crew will CLOSE 21 SW22 and ENSURE _(1)_ 21SW23 and 22SW23 (TIE VALVES). After the valve manipulations have been completed, SW cooling _(2)_ available to 21 CFCU and 22CFCU. (1) (2) closed is B. closed is NOT C. open is D. open is NOT Answer: B Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANAL YS/S: A. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could not recall the proper cooling arrangement between 21 and 22 SW headers. Additionally, 23 CFCU is the only CFCU that can be cooled by both SW headers. Either way, the candidate could then incorrectly determine that 21 and 22 CFCUs will have still have SW cooling. B. Correct. For Part 1 and in accordance with S2.0P-AB.SW-0001 Attachment 4 Step 2.0, the crew will CLOSE 21 SW22 and ENSURE CLOSE 21 SW23 and 22SW23 (TIE VALVES). For Part 2, after the valve manipulations have been completed, SW cooling is NOT available to 21 CFCU and 22CFCU. C. Incorrect but plausible. For Part 1 and in accordance with S2.0P-AB.SW-0001 Attachment 4 Step 3.0, if the 21 SW header was leaking upstream of 21 SW22, the crew would CLOSE 21SW22 and ENSURE OPEN 21SW23 and 22SW23 {TIE VALVES). Consequently, given the question stem, the candidate could incorrectly conclude that opening 21 SW23 and 22SW23 is required. D. Incorrect but plausible. For Part 1 and in accordance with S2.0P-AB.SW-0001 Attachment 4 Step 3.0, if the 21 SW header was leaking upstream of 21 SW22, the crew would CLOSE 21SW22 and ENSURE OPEN 21SW23 and 22SW23 (TIE VALVES). Consequently, given the question stem, the candidate could incorrectly conclude that opening 21 SW23 and 22SW23 is required. Part 2 is correct. For Part 2, the candidate could not recall the proper cooling arrangement between 21 and 22 SW headers. Additionally, 23 CFCU is the only CFCU that can be cooled by both SW headers. Either way, the candidate could then incorrectly determine that 21 and 22 CFCUs will have still have SW cooling. Question Number: 24 Tier: 2 Group 1 KIA: 076 Service Water System (SWS)-A2.02 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: Service water header pressure Importance Rating: 2.7 10 CFR Part 55: 41 .5 / 43. 5 / 45. 3 / 45 .13 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the procedural guidance of S2.0P-AB.SW-0001 (Loss of Service Water Header Pressure) for isolating a leak downstream of 21SW22 (NUCLEAR HEADER). SRO Justification: N/A Technical NOS05ABSW01-03 ( LOSS OF SERVICE WATER HEADER

References:

PRESSURE) Proposed references None to be provided: Learning Objective: NOS05ABSW01-03 ( LOSS OF SERVICE WATER HEADER PRESSURE) 1 Describe the operation of the SW system as applied to S1/S2.0P-AB.SW-0001:

• Loads supplied from the nuclear header 4 Given a set of initial plant conditions:
• Determine the appropriate abnormal procedure (AOP)
• Describe the plant response to actions taken in the AOP
• Describe the final plant condition that is established by the AOP Cognitive Level:

Higher X Lower Question Source New - - Modified Bank X Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY . Salem ILOT 16-01 RO NRC Exam-(T-75 SUBMITTAL) 25 Points: 1.00 Which ONE of the following completes the statement below? 11CA330 (CONT SUP INLET VALVE) and 12CA330 (CONT SUP INLET VALVE) fail CLOSED on a Loss of_( 1)_. With BOTH 11CA330 and 12CA330 closed, EACH PZR PORV _(2)_ be operated if needed. (1) (2) A. Control Air can B. Control Air can NOT C. 125 VOC or 28 VOC Power can

0. 125 VOC or 28 VOC Power can NOT Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, the CA330s fail closed on a loss of control air. For Part 2, each PORV has 2 accumulators and the accumulators are sized for 100 opening/closing cycles (50/accumulator). Consequently, with BOTH 11 CA330 and 12CA330 CLOSED, each PZR PORV can be operated if needed.

8. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could fail to recall that each PORV have accumulators. Consequently, with BOTH 11 CA330 and 12CA330 CLOSED, the candidate would then incorrectly conclude that the PORVs can not be operated if needed.

C. Incorrect but plausible. For Part 1, since the CA330s are Containment Isolation Valves, the candidate could incorrectly that the CA330s fail closed on a loss of 125 VDC or 28 voe Power. Part 2 is correct. D. Incorrect but plausible. For Part 1, For Part 1, since the CA330s are Containment Isolation Valves, the candidate could incorrectly that the CA330s fail closed on a loss of 125 VDC or 28 voe Power. For Part 2, the candidate could fail to recall that each PORV have accumulators. Consequently, with BOTH 11 CA330 and 12CA330 CLOSED, the candidate would then incorrectly conclude that the PORVs can not be operated if needed. Question Number: 25 Tier: 2 Group 1 KIA: 078 Instrument Air System (IAS)-K3.01 Knowledge of the effect that a loss or malfunction of the IAS will have on the following: Containment air system Importance Rating: 3.1 10 CFR Part 55: 41.7/45.6 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know that a loss of Control Air to 11CA330 (CONT SUP INLET VALVE) and 12CA330 (CONT SUP INLET VALVE) will cause both valves to close. Additionally, the candidate must know that PZR PORV operation is possible with 11 CA330 and 12CA330 valves closed. Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) SRO Justification: N/A Technical NOS05CONAIR-12 (CONTROL AIR SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS05CONAIR-12 (CONTROL AIR SYSTEM) 1 Describe how each impact the Control Air System during normal and abnormal conditions.

• CA Containment Isolation Valves Cognitive Level:

Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of S

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam-(T-75 SUBMITTAL) 26 Points: 1.00 Given:

• The PO observes the following:

                         ~   ""' "' '
                                          ~     '
                                            '~ ~*'"t_,s,                     . .

EMERG~~CY AIR

                         ,MANUAL!
                         .                           ,,                  START ,\,

Nhich ONE of the following completes the statements below? The 2 Emergency Air Compressor _(1 ) _ reached its AUTOMATIC start setpoint. If the PO is required to MANUALLY start the 2 Emergency Air Compressor, depressing BEZEL button(s) _(2)_ is/ are the MINIMUM pushbutton manipulation(s) required to start the emergency air compressor. (1) (2) A. has A then B S. has SONLY C. has NOT A then S D. has NOT SONLY Answer: C Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, S2.0P-AB.CA-0001 (Loss of Control Air) requires the crew to manually start ECAC when control air pressure reaches 88 psig. Consequently, the candidate could incorrectly deduce that the automatic start set point for the ECAC is 88 psig. Part 1 is correct. B. Incorrect but plausible. For Part 1, S2.0P-AB.CA-0001 (Loss of Control Air) requires the crew to manually start ECAC when control air pressure reaches 88 psig. Consequently, the candidate could incorrectly deduce that the automatic start set point for the ECAC is 88 psig. For Part 2, since the crew is attempting to manually start the emergency air compressor (ECAC), the candidate could incorrectly deduce the controller is designed to start the ECAC with only one button. C. Correct. For Part 1, the 2 ECAC will automatically start when control air pressure is less than 85 psig. Consequently, since the lowest control air pressure is 86 psig, The 2 Emergency Air Compressor has NOT reached its AUTOMATIC start setpoint. For Part 2, depressing BEZEL button(s) 1 then 2 are the MINIMUM pushbutton manipulation(s) required to start the emergency air compressor. D. Incorrect but plausible. Part 1 is correct. For Part 2, since the crew is attempting to manually start the emergency air compressor (ECAC), the candidate could incorrectly deduce the controller is designed to start the ECAC with only one button. Question Number: 26 Tier: 2 Group 1 KIA: 078 Instrument Air System (IAS)-A4.01 Ability to manually operate and/or monitor in the control room: Pressure gauges Importance Rating: 3.1 10 CFR Part 55: 41.7 / 45.5 to 45.8 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must monitor the compressed air gauge (located on the compressed air control room BEZEL) and Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) determine if the ECAC has reached its automatic start setpoint. Additionally, the candidate must know how to manually start the ECAC from the control room. SRO Justification: N/A Technical NOS05CONAIR-12 (CONTROL AIR SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS05CONAIR-12 (CONTROL AIR SYSTEM) 8 Identify and describe the Control Room controls, indications, and alarms associated with the Control Air System, including:

• The Control Room location of Control Air System control bezels and indications.
• The function of each Control Air System Control Room control and indication.
• The effect each Control Air System control has upon Control Air System components and operation.
• The plant conditions or permissives required for Control Air System Control Room controls to perform their intended function.
• The setpoints associated with the Control Air System control room alarms. (Licensed Operator & STA only)

Cognitive Level: Higher X Lower - - - Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 27 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power and stable
• 21-24 CFCUs are running in high speed
• 25 CFCU is stopped At time 13:50
• A Reactor Trip and Safety Injection have occurred Ten minutes later at 14:00, which ONE of the following completes the statement below?

21-24 CFCUs are running in _ ( 1) _ speed and 25CFCU is _(2)_. (1) (2)

\.                       high                                      stopped B.                        high                               running in high speed C.                        low                                       stopped D.                        low                                 running in low speed Answer:       D Page 1 of 4

EXAM.INATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. The candidate could incorrectly conclude that with the SECs in Mode 1, this will cause on the previously running CFCUs to shift to high speed. B. Incorrect but plausible. The candidate could incorrectly conclude that with the SECs in Mode 1, this will cause all of the CFCUs to shift to high speed. C. Incorrect but plausible. The candidate could incorrectly conclude that with the SECs in Mode 1, this will cause only the previously running CFCUs to shift to low speed. D. Correct. At 14:00:00 the SECs will be in MODE 1. This will cause the running CFCUs to stop and then all of the CFCUs will be started in low speed. Consequently, at 14:10:00, 21-24 CFCUs are running in low speed and 25CFCU is running in low speed. Question Number: 27 Tier: 2 Group 1 KIA: 103 Containment System-K1.01 Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: CCS Importance Rating: 3.6 10 CFR Part 55: 41.2 to 41.9 / 45.7 to 45.8 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know how the CCS (containment cooling system CFCUs) will physically circulate and cool the containment atmosphere following a reactor trip and safety injection actuation. SRO Justification: N/A Technical NOS05ESF000-02 ( INTRODUCTION TO ENGINEERED SAFETY

References:

FEATURES AND DESIGN CRITERIA) Proposed references None to be provided: Page 2 of 4

EXAMl,NATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL)

• .earning Objective: NOS05ESF000-02 ( INTRODUCTION TO ENGINEERED SAFETY FEATURES AND DESIGN CRITERIA) 4 Describe the function and operating characteristics for the following Engineered Safety Features Standby Power System components:

a) The power sources b) The Safeguards Equipment Cabinets Cognitive Level: Higher X Lower Question Source New - - Modified Bank - - Bank X Question History: Comments: Page 3 of 4

EXAMlNATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 28 Points: 1.00 Given:

• Unit 1 is at 100% Reactor Power and stable
• 1CV5 (75 GPM ORIFICE) is in service At time 12:00:00
• A spurious Phase A Containment Isolation occurs At 12:01 :00, which ONE of the following completes the statements below?

Seal Return flow is being directed to the _(1 )_ _ (2)_ are BOTH closed. NOTE:

• 1CV2 (LTOWN LINE ISOL V)
• 1CV277 (LTOWN LINE ISOL V)
• 1CV? (L TOWN HX INLET V)

(1) (2) A. PRT 1CV2 and 1CV277

8. PRT 1CV5 and 1CV?

C. VCT 1CV2 and 1CV277 D. VCT 1CV5 and 1CV? Answer: B Page 1 of 7

EXAMtNATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, 1CV2 and 1CV277 will automatically close on low PZR level. Consequently, the candidate could incorrectly conclude that 1CV-2 and 1VC277 also automatically close on a Phase A Containment Isolation. B. Correct. For Part 1, 1CV284 & 1CV116 (RCP SW RET HOR STOP VALVES) will close. This causes seal return flow to be redirected from the VCT to the PRT via Relief Valve 1CV15. For Part 2, letdown will be isolated during a Phase A isolation. This is accomplished by closing 1CV5 and 1CV7. C. Incorrect but plausible. For Part 1, seal injection flow is normally directed to the VCT. The candidate could incorrectly conclude that redirecting seal injection to the PRT is not desirable since this will cause a loss of RCS inventory. Incorrect but plausible. Part 1 is correct. For Part 2, 1CV2 and 1CV277 will automatically close on low PZR level. Consequently, the candidate could incorrectly conclude that 1CV-2 and 1VC277 also automatically close on a Phase A Containment Isolation. D. Incorrect but plausible. For Part 1, seal injection flow is normally directed to the VCT. The candidate could incorrectly conclude that redirecting seal injection to the PRT is not desirable since this will cause a loss of RCS inventory. Part 2 is correct. Question Number: 28 Tier: 2 Group 1 KIA: 103 Containment System-A3.01 Ability to monitor automatic operation of the containment system, including: Containment isolation Importance Rating: 3.9 10 CFR Part 55: 41.7 I 45.5 10 CFR 55.43.b NIA KIA Match: KIA is matched because the candidate must monitor the automatic operation of the CVCS containment isolation valves following a Phase A Containment Isolation. SRO Justification: NIA Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Technical NOS05CVCS00-17 (CHEMICAL AND VOLUME CONTROL

References:

SYSTEM) Proposed references None to be provided: Learning Objective: NOS05CVCS00-17 (CHEMICAL ANO VOLUME CONTROL SYSTEM) 9 State the setpoints for automatic actuations associated with the Chemical and Volume Control System. Cognitive Level: Higher X Lower Question Source New - - Modified Bank X Bank - - Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY

• Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 29 Points: 1.00 Which ONE of the following completes the statements below?

21 Centrifugal Charging Pump is powered from the _(1 ) _ 4KV Vital Bus. 22 Centrifugal Charging Pump is powered from the _(2)_ 4KV Vital Bus. (1) (2) A. 2A 28

8. 2A 2C C. 28 2A D. 28 2C Answer: D Page 1 of 4

EXAMINATION ANSWER KEY II Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Since there are three 4KV Vital Susses that power two trains of each type of ECCS pumps, selecting any combination of two separate 4K Vital busses is plausible. B. Incorrect but plausible. Since there are three 4KV Vital Susses that power two trains of each ECCS pumps, selecting any combination of two separate 4K Vital busses is plausible. C. Incorrect but plausible. Since there are three 4KV Vital Susses that power two trains of each ECCS pumps, selecting any combination of two separate 4K Vital busses is plausible. D. Correct. 21 Centrifugal Charging Pump is powered from the 28 4KV Vital Bus. 22 Centrifugal Charging Pump is powered from the 2C 4KV Vital Bus. Question Number: 29 Tier: 2 Group 2 .(IA: 011 Pressurizer Level Control System-K2.01 Knowledge of bus power supplies to the following: Charging pumps Importance Rating: 3.1 10 CFR Part 55: 41.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the power supplies for the 21 and 22 Charging Pumps. SRO Justification: N/A Technical NOSOSCVCS00-17 (CHEMICAL AND VOLUME CONTROL

References:

SYSTEM) Proposed references None to be provided: Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL)

• _earning Objective: NOS05CVCS00-17 (CHEMICAL AND VOLUME CONTROL SYSTEM) 9 State the power supply to the following Chemical and Volume Control System components:

a. Charging Pumps

b. Boric Acid Transfer Pumps

c. Primary Water Pumps Cognitive Level:

Higher -- Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - {T-75 SUBMITTAL) 30 Points: 1.00 Given:

• The crew is recovering a dropped Control Bank A Rod in accordance with S2.0P-AB.ROD-0002 (Dropped Rod)
• The ROD BANK SELECTOR SWITCH has just been placed in CBA Which ONE of the following completes the statement below?

With the ROD BANK SELECTOR SWITCH in CBA, the dropped rod will be withdrawn at _ __ steps per minute in small increments per reactor Engineering guidance. A. 72 B. 64 C. 48 'J. 8 Answer: C Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. 72 steps per minute is maximum speed for withdrawing rods when the ROD BANK SELECTOR SWITCH is in AUTO. Consequently, the candidate could incorrectly conclude that with ROD BANK SELECTOR SWITCH in CSA, the dropped rod will be withdrawn at 72 steps per minute.

8. Incorrect but plausible. 64 steps per minute is the speed for withdrawing rods when the ROD BANK SELECTOR SWITCH is in SBA, SBB, SBC or SBD. Consequently, the candidate could incorrectly conclude that with ROD BANK SELECTOR SWITCH in CSA, the dropped rod will be withdrawn at 64 steps per minute.

C. Correct. With the ROD BANK SELECTOR SWITCH in CBA, the dropped rod will be withdrawn at 48 steps per minute. D. Incorrect but plausible. 8 steps per minute is minimum speed for withdrawing rods when the ROD BANK SELECTOR SWITCH is in AUTO. Consequently, the candidate could incorrectly conclude that with ROD BANK SELECTOR SWITCH in CBA, the dropped rod will be withdrawn at 8 steps per minute. Question Number: 30 Tier: 2 Group 2 KIA: 014 Rod Position Indication System (RPIS)-A4.02 Ability to manually operate and/or monitor in the control room: Control rod mode-select switch Importance Rating: 3.4 10 CFR Part 55: 41. 7 / 45.5 to 45.8 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must be able to monitor in the control room the expected rod speed when withdrawing control rods with the ROD BANK SELECTOR SWITCH in the CSA position. SRO Justification: N/A Technical NOS05RODS00-12 (ROD CONTROL AND POSITION

References:

INDICATION SYSTEMS) Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) Proposed references None £O be provided: Learning Objective: NOS05RODS00-12 (ROD CONTROL AND POSITION INDICATION SYSTEMS) 11 Identify and describe the Control Room controls, indications, and alarms associated with the Rod Control and Position Indication Systems, including:

a. The Control Room location of Rod Control and Position Indication Systems control bezels and indications

b. The function of each Rod Control and Position Indication Systems Control Room control and indication

c. The effect each Rod Control and Position Indication Systems control has upon Rod Control and Position Indication Systems components and operation

d. The plant conditions or permissives required for Rod Control and Position Indication Systems Control Room controls to perform their intended function Cognitive Level:

Higher - - Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 31 Points: 1.00 Given:

• Unit 2 is in MODE 3 preparing to do a plant startup At Time 07:00
• An AUTOMATIC RCS Makeup starts At Time 07:01
• 125 voe power to 2CV179 (PRIMARY WATER FLOW) has been lost
• The Primary Water Flow Deviation Alarm actuates At Time 07:02
• 2CV185 (MAKEUP FLOWPATH} fails to AUTOMATICALLY close Which ONE of the following completes the statements below?

The Primary Water Flow Deviation Alarm actuates when primary water flow is greater than a MINIMUM of +/-_(1 ) _ gpm above the setpoint. The Source Range NI Audible Count Rate indication is expected to _(2)_ as the makeup continues with 2CV179 in its failed position. (1) (2) A. 5.0 rise B. 5.0 lower C. 0.8 rise D. 0.8 lower Answer: B Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANAL YS/S: A. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that 2CV179 fails open. With 2CV179 open during an automatic RCS makeup, actual RCS Boron Concentration will lower. Lowering actual RCS Concentration will add positive reactivity which will cause the Source Range NI Audible Count Rate indication to rise.

8. Correct. For Part 1 and IAW S2.0P-AR-ZZ-0012, the Primary Water Flow Deviation Alarm actuates when primary water flow is greater than a MINIMUM of+/- 5.0 gpm above the setpoint. For Part 2, 2CV179 fails closed. Consequently, actual boron flow into the boric acid blender will higher than the predetermined setpoint for the auto makeup (based on current RCS Boron concentration). This will cause actual RCS boron concentration to rise since the boron concentration of auto makeup flow is higher than the setpoint for the existing RCS Boron concentration. An increase in actual RCS Boron concentration will insert negative reactivity which will cause the Source Range NI Audible Count Rate indication to lower.

C. Incorrect but plausible. For Part 1 , the Boric Acid Flow Deviation actuates when boric acid flow is greater than a MINIMUM of+/- 0.8 gpm above the setpoint. Consequently, the candidate could incorrectly conclude that the Primary Water Flow Deviation Alarm actuates when primary water flow is greater than a MINIMUM of+/- 0.8 gpm above the setpoint. For Part 2, the candidate could incorrectly conclude that 2CV179 fails open. With 2CV179 open during an automatic RCS makeup, actual RCS Boron Concentration will lower. Lowering actual RCS Concentration will add positive reactivity which will cause the Source Range NI Audible Count Rate indication to rise. D. Incorrect but plausible. For Part 1, the Boric Acid Flow Deviation actuates when boric acid flow is greater than a MINIMUM of+/- 0.8 gpm above the setpoint. Consequently, the candidate could incorrectly conclude that the Primary Water Flow Deviation Alarm actuates when primary water flow is greater than a MINIMUM of+/- 0.8 gpm above the setpoint. Part 2 is correct. Question Number: 31 Tier: 2 Group 2 KIA: 015 Nuclear Instrumentation System (NIS)-A3.05 Ability to monitor automatic operation of the NIS, including: Recognition of audio output expected for a given plant condition Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -{T-75 SUBMITTAL) Importance Rating: 2.6 10 CFR Part 55: 41.7 / 45.5 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know how the Source Range NI Audible Count Rate indication will automatically respond during an automatic RCS makeup with 2CV172 (BORIC ACID FLOW) failed open. SRO Justification: N/A Technical NOS05CVCS00-17 (Chemical and Volume Control System)

References:

Proposed references None to be provided: Learning Objective: NOS05CVCS00-17 (Chemical and Volume Control System) 11 Given a Chemical and Volume Control System failure, predict the effect of the Chemical and Volume Control System failure on the following:

• Reactor Coolant System Cognitive Level:

Higher X Lower - - Question Source New X Modified Bank Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 32 Points: 1.00 Given:

• Unit 2 is at 25% Reactor Power and stable
• Emergent maintenance activities are ongoing inside containment
• Containment pressure is slowly rising due to the maintenance activities In accordance with Unit 2 Technical Specifications, which ONE of the following completes the statements below?

LCO 3.6.1.4 (CONTAINMENT INTERNAL PRESSURE) will NOT be met when containment pressure is greater than a MINIMUM of+ _(1 ) _ psig. When LCO 3.6.1.4 is NOT met, the crew is required to restore containment internal pressure within limits within a MAXIMUM of _(2)_ minutes or place the Unit in HOT STANDBY within the next 6 hours. (1) (2) A. 0.2 30 B. 0.2 60 C. 0.3 30 D. 0.3 60 Answer: D Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the BEZEL Hi CNTMT Pressure Alarm is 0.2 psid. Consequently, the candidate could incorrectly determine that LCO 3.6.1.4 (INTERNAL PRESSURE) will NOT be met when containment pressure is greater than a minimum of+ 0.2 psig. For Part 2, there are other LCOs with 30 minutes REQUIRED ACTION (LCOs 3.2.1, 3.2.4, 3.4.10.2 and 3.7.2). Consequently, the candidate could incorrectly conclude that when LCO 3.6.1.4 is NOT met, the crew is required to restore containment internal pressure within limits within a MAXIMUM of 30 minutes or place the Unit in HOT STANDBY within the next 6 hours B. Incorrect but plausible. For Part 1, the BEZEL Hi CNTMT Pressure Alarm is 0.2 psid. Consequently, the candidate could incorrectly determine that LCO 3.6.1.4 (INTERNAL PRESSURE) will NOT be met when containment pressure is greater than a minimum of+ 0.2 psig. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, there are other LCOs with 30 minutes REQUIRED ACTION (LCOs 3.2.1, 3.2.4, 3.4.10.2 and 3. 7.2). Consequently, the candidate could incorrectly conclude that when LCO 3.6.1.4 is NOT met, the crew is required to restore containment internal pressure within limits within a MAXIMUM of 30 minutes or place the Unit in HOT STANDBY within the next 6 hours D. Correct. For Part 1, LCO 3.6.1.4 (INTERNAL PRESSURE) will NOT be met when containment pressure is greater than a minimum of+ 0.3 psig. For Part 2, When LCO 3.6.1.4 is NOT met, the crew is required to restore containment internal pressure within limits within a MAXIMUM of 60 minutes or place the Unit in HOT STANDBY within the next 6 hours. Question Number: 32 Tier: 2 Group 2 KIA: 029 Containment Purge System (CPS)-A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Maintenance or other activity taking place inside containment Importance Rating: 2.9 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.13 Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b N/A K/A Match: KIA is matched because the candidate must use Technical Specifications (a procedure) to mitigate containment internal pressure rising (using CPS) due to emergent maintenance activities taking place inside containment. SRO Justification: N/A Technical NOSOSCONTMT-15 (CONTAINMENT AND CONTAINMENT

References:

SUPPORT SYSTEMS) Proposed references None to be provided: Learning Objective: NOSOSCONTMT-15 (CONTAINMENT AND CONTAINMENT SUPPORT SYSTEMS) 9 Given a situation dealing with Containment and Containment Support Systems operability, examine the situation and apply the appropriate Technical Specification action. Cognitive Level: Higher - - Lower X Question Source New - - Modified Bank X Bank - - Question History: Comments: Page 3 of 7

EXAMINATlON ANSWER KEY Salem ILOT 16-01 RO NRC Exam - {T-75 SUBMITTAL) 33 Points: 1.00 Which ONE of the following completes the statements below concerning Unit 2 Spent Fuel Pool? Remote Spent Fuel Pool Level indication is provided in the Control Room _(1 )_. In accordance S2.0P-SO.SF-0001 (Fill And Transfer Of The Spent Fuel Pool), Fire Protection Water _(2)_ a source of water that can be used to provide ROUTINE makeup to the Spent Fuel Pool. (1) (2) A. and in the Unit 2 Relay Room is NOT

8. and in the Unit 2 Relay Room is C. ONLY is NOT

0. ONLY is Answer: A Page 1 of 5

EXAMINATLON ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANAL YS/S: A. Correct. For Part 1, Remote Spent Fuel Pool Level indication is provided in the Control Room on RP4 and in the Unit 2 Relay Room. For Part 2, In accordance S2.0P-SO.SF-0001 (Fill And Transfer Of The Spent Fuel Pool), Fire Protection Water is NOT a source of water that can be used to provide routine makeup to the Spent Fuel Pool. B. Incorrect but plausible. Part 1 is correct. For Part 2, IAW S2.0P-SO.SF-0001, DWS, PWST, RWST/Refueling Cavity and eves HUTs are the possible sources that can be used to provide routine makeup to the Spent Fuel Pool. PWST and DWS are both un-borated sources of water. Given that maintaining level in the SFP is a safety related requirement and S2.0P-SO.SF-0001 allows un-borated water to be used to provide routine makeup to the SFP, the candidate could incorrectly conclude that S2.0P-SO.SF-0001 also allows Fire Water Protection Water as a source of routing SFP makeup. C. Incorrect but plausible. For Part 1, the candidate could incorrectly that the only remote SFP Level indication is provided in the Control Room. Part 2 is correct. D. Incorrect but plausible. For Part 1, the candidate could incorrectly that the only remote SFP Level indication is provided in the Control Room. For Part 2, IAW S2.0P-SO.SF-0001, DWS, PWST, RWST/Refueling Cavity and CVCS HUTs are the possible sources that can be used to provide routine makeup to the Spent Fuel Pool. PWST and DWS are both un-borated sources of water. Given that maintaining level in the SFP is a safety related requirement and S2.0P-SO.SF-0001 allows un-borated water to be used to provide routine makeup to the SFP, the candidate could incorrectly conclude that S2.0P-SO.SF-0001 also allows Fire Water Protection Water as a source of routing SFP makeup. Question Number: 33 Tier: 2 Group 2 KIA: 033 Spent Fuel Pool Cooling System (SFPCS)-K4.01 Knowledge of design feature(s) and/or interlock(s) which provide for the following: Maintenance of spent fuel level Importance Rating: 2.9 10 CFR Part 55: 41.7 10 CFR 55.43.b N/A Page 2 of 5

EXAMINATI.ON ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) KIA Match: KIA is matched because the candidate must know where SFP Level Indication can be viewed remotely and if Fire Protection Water can be used as a source of water that can be used to provide routine makeup to the SFP. Both knowledge items are design features of the SFP Cooling System that provides maintenance of SFP level. SRO Justification: NIA Technical NOSOSSFP000-10 (SPENT FUEL POOL COOLING SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOSOSSFP000-10 (SPENT FUEL POOL COOLING SYSTEM) 11 Discuss the procedural requirements associated with the Spent Fuel Pool Cooling System, including an explanation of major precaution and limitations in the Spent Fuel Pool Cooling procedures . Cognitive Level: Higher - - Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 34 Points: 1.00 Given:

• A Unit 1 Core reload is in progress
• The Fuel Transfer Cart is in the Fuel Handling Building with the upender in the horizontal position At 09:00:00
• The limit switch on the Fuel Transfer Tube Gate Valve fails and the valve no longer indicates open
• An NEO has verified that the Fuel Transfer Tube Gate Valve is open At 09:05:00
• Water level in the refueling canal begins to rapidly lower
• The crew is preparing to close the Fuel Transfer Tube Gate Valve Which ONE of the following completes the statements below concerning?

At 09:00:00 and if desired, the Fuel Transfer Cart can be moved MANUALLY _(1 ) _ to Containment with the failed limit switch on the Fuel Transfer Tube Gate Valve. At 09:05:00, the crew _(2)_ FULLY close the Fuel Transfer Tube Gate Valve with the Fuel Transfer Cart locate in the Fuel Handling Building. (1) (2) A. ONLY can

8. ONLY can NOT C. or ELECTRICALLY can D. or ELECTRICALLY can NOT Answer: B Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could in correctly conclude that the Fuel Transfer Tube Gate Valve can be closed regardless of its location (inside containment or inside the fuel handling building).

8. Correct. For Part 1, the Fuel Transfer Cart has two interlocks that will prevent / allow cart movement: upender must be in the horizontal position and the Fuel Transfer Tube Gate Valve must be open (as indicated with the open limit switch). At 09:00:00, both interlocks are not satisfied and the Fuel Transfer Cart can not be moved to containment.

For Part 2, the crew can not close the Fuel Transfer Tube Gate Valve with the Fuel Transfer Cart locate in the Fuel Handling Building C. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that the fuel cart interlock was only based on position of the upender and the Fuel Transfer Tube Gate Valve was verified open administratively prior to moving the fuel transfer cart. For Part 2, the candidate could in correctly conclude that the Fuel Transfer Tube Gate Valve can be closed regardless of its location (inside containment or inside the fuel handling building). D. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that the fuel cart interlock was only based on position of the upender and the Fuel Transfer Tube Gate Valve was verified open administratively prior to moving the fuel transfer cart. Part 2 is correct. Question Number: 34 Tier: 2 Group 2 KIA: 034 Fuel Handling Equipment System (FHES)-A 1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including: Water level in the refueling canal Importance Rating: 2.9 10 CFR Part 55: 41.5 / 45.5 10 CFR 55.43.b N/A Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '<IA Match: KIA is matched because the candidate must know that as water level in the refueling canal lowers, what condition must be met to close the Fuel Transfer Tube Gate Valve (fuel transfer cart must be inside containment). SRO Justification: NIA Technical S2.0P-AB.FUEL-0002 (Loss Of Refueling Cavity Or Spent Fuel

References:

Pool Level) NOS05REFUEL-11 (REFUELING SYSTEM) Proposed references None to be provided: Learning Objective: NOS05REFUEL-11 (REFUELING SYSTEM) 5 Outline the interlocks associated with the following Refueling System components:

a. Manipulator Crane Bridge and Trolley

b. Manipulator Crane Hoist and Gripper

c. Fuel Transfer System Conveyor Car

d. Fuel Transfer System Upender

e. Fuel Handling Crane Cognitive Level:

Higher X Lower - - Question Source New - - Modified Bank X Bank - - Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 35 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power and stable At time 10:00:00
• The 21BF19 Main Feedwater Control Valve controller malfunctions causing 21BF19 to close At time 10:00:30
• The crew performs a MANUAL Reactor Trip
• ONLY Reactor Trip Train A Breaker opens Which ONE of the following completes the statement below?

The Steam Dump System will use the _(1 ) _ to stabilize RCS TAvG at _(2)_ °F. (1) (2) A. Plant Trip Controller 552

8. Plant Trip Controller 547 C. Load Rejection Controller 552 D. Load Rejection Controller 547 Answer: C Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that steam dump plant trip controller is based on Reactor Trip Train A Breaker opening. For Part 2, the candidate could incorrectly recall which steam dump controller has a dead band and incorrectly concludes that the plant trip controller has a dead band. This would then cause the candidate to incorrectly conclude that following the reactor trip, RCS TAVG will stabilize at 552°F. B. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that steam dump plant trip controller is based on Reactor Trip Train A Breaker opening. For Part 2, the plant trip controller has no dead band and will normally restore RCS TAVG to RCS No-Load TAVG (547°F). C. Correct. For Part 1, with the Plant initially at 100% Power, the Steam Dump System is in the TAVG Mode. Consequently when the plant trips and ONLY Reactor Trip Train A Breaker opens, the Load Rejection Controller will control the steam dumps. If Reactor Trip Train B Breaker had opened then the Plant Trip Controller would have controlled the steam dumps. For Part 2, with the Load Rejection Controller in control of the steam dumps, there is a 5°F dead band associated with the controller. Consequently, the steam dumps will maintain RCS TAVG at 552 °F (547°F (no load TAVG) + 5 °F). D. Incorrect but plausible. Part 1 is correct. For Part 2, the distractor is plausible for two different reasons. First, following a reactor trip in which both Reactor Trip Train A and B Breakers open, the steam dump system would maintain RCS TAVG at 547°F. Secondly, the candidate could incorrectly recall which steam dump controller has a dead band. Either way, the candidate could incorrectly determine that following the reactor trip, RCS TAVG will stabilize at 547°F. Question Number: 35 Tier: 2 Group 2 KIA: 041 Steam Dump System (SDS)/Turbine Bypass Control-K6.03 Knowledge of the effect of a loss or malfunction on the following will have on the SOS: Controller and positioners, including ICS, SIG, CRDS Importance Rating: 2.7 10 CFR Part 55: 41.7 / 45.7 Page 2 of 6

EXAMINATIO~ ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know how the SOCS will respond following a malfunction of the 21BF19 controller which requires a manual a reactor trip from 100% power in which ONLY Reactor Trip Train A Breaker opens. SRO Justification: N/A Technical NOSOSSTDUMP-12 (STEAM DUMP SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOSOSSTDUMP-12 (STEAM DUMP SYSTEM) 7: Describe the function of the following controllers and how their normal and abnormal operation affects the Steam Dump System:

a. Steam Pressure Controller

b. Load Rejection Controller

c. Plant Trip Controller Cognitive Level:

Higher X Lower - - Question Source New -- Modified Bank -- Bank X Question History: Comments: Page 3 of 6

EXAMINATION ANSWER,KEY Salem ILOT 16-01 RO NRC Exam-(T-75 SUBMITTAL) 36 Points: 1.00 Which ONE of the following completes the statement below? ___ can cause Main Condenser vacuum to degrade. A. Excessively low TAC supply temperature B. Excessively high Vacuum Pump Seal Water flow C. Vacuum Pump Separating Tank releasing through the overflow D. Excessively high Vacuum Pump Seal Water Temperature Answer: D Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation D/STRACTOR ANALYSIS: A. Incorrect but plausible. All of the other distractors will cause Seal Water Temperature to lower which would actually improve Condenser Vacuum. However, the candidate could incorrectly conclude that any of the distractors would degrade condenser vacuum. B. Incorrect but plausible. All of the other distractors will cause Seal Water Temperature to lower which would actually improve Condenser Vacuum. However, the candidate could incorrectly conclude that any of the distractors would degrade condenser vacuum. C. Incorrect but plausible. All of the other distractors will cause Seal Water Temperature to lower which would actually improve Condenser Vacuum. However, the candidate could incorrectly conclude that any of the distractors would degrade condenser vacuum. D. Correct. As Seal Water temperature increases, Vacuum Pump performance decreases, and can result in degrading vacuum. Question Number: 36 Tier: 2 Group 2 CIA: 055 Condenser Air Removal System (CARS)-K3.01 Knowledge of the effect that a loss or malfunction of the CARS will have on the following: Main condenser Importance Rating: 2.5 10 CFR Part 55: 41.7 / 45.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know how a malfunction in CARS (seal water temperature rising) will affect Condenser Vacuum. SRO Justification: N/A Technical NOS05CAR000-07 (CONDENSER AIR REMOVAL AND PRIMING

References:

SYSTEM) Proposed references None to be provided: Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Learning Objective: NOS05CAR000-07 (CONDENSER AIR REMOVAL AND PRIMING SYSTEM) 13: Given plant conditions, relate the Condenser Air Removal and Priming System with the following:

a. Main Turbine/Generator

b. Main Condenser C. Condensate System

d. Steam Generator

e. Condensate Polishers

f. Radiation Monitoring

g. Steam Dump System Cognitive Level:

Higher X Lower - - Question Source New - - Modified Bank - - Bank X Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 37 Points: 1.00 Given:

• Unit 2 is at 90% Reactor Power At time 17:00:00
• 21CN22 (LP Feedwater Heaters 21A/22A Inlet Control Valve) and 23CN22 (LP Feedwater Heaters 21 C / 22C Inlet Control Valve) SPURIOUSLY close Which ONE of the following completes the statements below?

With 21CN22 and 23CN22 closed, Reactor Power will _(1 )_. The crew _(2)_ open 21 CN22 and 23CN22 from the Control Room. (1} (2) A. remain stable can .J. remain stable can NOT C. rise can D. rise can NOT Answer: D Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the candidate could fail to recognize that with the given condensate transient, that Feedwater temperature will lower. Consequently, if the candidate incorrectly concluded Feedwater temperature is stable, then the candidate would also conclude that reactor power is stable. For Part 2, other CN valves associated with Feedwater heaters can be operated in the Control Room (e.g. 2CN45 and 2CN47). Consequently, the candidate could incorrectly conclude that 21 CN22 and 23CN22 can also be opened from the control room. B. Incorrect but plausible. For Part 1, the candidate could fail to recognize that with the given condensate transient, that Feedwater temperature will lower. Consequently, if the candidate incorrectly concluded Feedwater temperature is stable, then the candidate would also conclude that reactor power is stable. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, other CN valves associated with Feedwater heaters can be operated in the Control Room (e.g. 2CN45 and 2CN47). Consequently, the candidate could incorrectly conclude that 21 CN22 and 23CN22 can also be opened from the control room. D. Correct. For Part 1, with 21 CN22 and 23CN22 closed, 2CN45 will modulate open to maintain <65 psid across 21 and 22 LP Heaters. With 2CN45 modulated, Feedwater temperature will lower. With SG Steam flow constant, Reactor power will rise. For Part 2, the CN22s only have indications in the Control Room (no controls). Consequently, The crew can not open 21 CN22 and 23CN22 from the Control Room. Question Number: 37 Tier: 2 Group 2 KIA: 056 Condensate System-G2.1.30 Ability to locate and operate components, including local controls, Importance Rating: 4.4 10 CFR Part 55: 41.7 / 45.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know that 21 &23CN22 (Condensate Valves) can only be operated locally and not in the control room. Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) SRO Justification: N/A Technical NOS05CN&FDW-15 (CONDENSATE AND FEEDWATER

References:

SYSTEM) Proposed references None to be provided: Learning Objective: NOS05CN&FDW-15 (CONDENSATE AND FEEDWATER SYSTEM) 7: Identify and describe the local controls, indications, and alarms associated with the Condensate and Feedwater System, including:

a. The location of Condensate and Feedwater System local controls and indications.

b. The function of Condensate and Feedwater System local controls and indications.

c. The plant conditions or permissives required for Condensate and Feedwater System local controls to perform their intended function.

d. The setpoints associated with the Condensate and Feedwater System local alarms.

Cognitive Level: Higher X Lower Question Source New X Modified Bank -- Bank -- Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) 38 Points: 1.00 Which ONE of the following completes the statements below concerning the Unit 2 Radioactive Liquid Waste System Tanks? ONLY the ___ has a physical connection to the Waste Gas Compressor Header. A. RCDT B. 21 WHUT C. Chemical Drain Tank D. Auxiliary Building Sump Tank Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANAL YS/S: A. Correct. ONLY the RCDT has a physical connection to the Waste Gas Compressor Header. B. Incorrect but plausible. Since all of the distractors are part of the tanks that comprise the Liquid Waste System, all of the distractors are plausible. C. Incorrect but plausible. Since all of the distractors are part of the tanks that comprise the Liquid Waste System, all of the distractors are plausible. D. Incorrect but plausible. Since all of the distractors are part of the tanks that comprise the Liquid Waste System, all of the distractors are plausible. Question Number: 38 Tier: 2 Group 2 KIA: 068 Liquid Radwaste System (LRS)-K1 .02 Knowledge of the physical connections and/or cause effect relationships between the Liquid Radwaste System and the following systems: Waste gas vent header Importance Rating: 2.5 10 CFR Part 55: 41.2 to 41.9 / 45.7 to 45.8 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know which Radioactive Liquid Waste System Tank is physically connected to the Waste Gas Compressor Header. SRO Justification: N/A Technical NOS05WASLIQ-09 (RADIOACTIVE LIQUID WASTE SYSTEM)

References:

Proposed references None to be provided: Page 2 of 5

EXA.MINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '-earning Objective: NOS05CN&FDW-15 (CONDENSATE AND FEEDWATER SYSTEM) 14: Given plant conditions, relate the Radioactive Liquid Waste System with the following:

a. Reactor Coolant System

b. Chemical Volume Control System C. Waste gas vent header

d. Pressurizer Relief Tank

e. Reactor Coolant Drain Tank

f. Circulating Water System

g. Service Water System

h. Radiation Monitoring System Cognitive Level:

Higher -- Lower X Question Source New X Modified Bank -- Bank -- Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 39 Points: 1.00 In accordance with S2.0P-IO.ZZ-0003 (Hot Standby To Minimum Load), which ONE of the following completes the statement below? The crew will record the time of MODE 2 entry in the Control Room Narrative Log when _ __ A. the reactor is announced to be critical B. withdrawal of Control Bank "A" is imminent C. withdrawal of Shutdown Bank "A" is imminent D. when IR power level has been stabilized at 2E-3% Answer: B Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. The candidate could incorrectly conclude that the plant enters Mode 2 when the reactor becomes critical. B. Correct. In accordance with S2.0P-IO.ZZ-0003, The crew will record the time of MODE 2 entry in the Control Room Narrative Log when withdrawal of Control Bank "A" is imminent. C. Incorrect but plausible. The candidate could incorrectly conclude that the plant enters Mode 2 when the first bank of control rods is withdrawn. D. Incorrect but plausible. The candidate could incorrectly conclude that the plant enters Mode 2 when the IR power has been stabilized at 2E-3% which is when data is collected IAW SC.RE-RA.ZZ-0002 (Inverse Count Rate Ratio During Reactor Startup). Question Number: 39 Tier: 3 Group KIA: G2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports Importance Rating: 3.6 10 CFR Part 55: 41.10 / 45.12 / 45.13 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the requirement of S2.0P-IO.ZZ-0003 (Hot Standby To Minimum Load) to accurately document in the Control Room Narrative Log when the Unit enters MODE 2 during a plant startup. SRO Justification: N/A Technical NOS0510P300-09 (REACTOR STARTUP)

References:

Proposed references None to be provided: Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) '.earning Objective: NOS0510P300-09 (REACTOR STARTUP) 1: Summarize the purpose of S1/S2.0P-IO.ZZ-0003(Q), Hot Standby to Minimum Load Cognitive Level: Higher -- Lower X Question Source New -- Modified Bank -- Bank X Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 40 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power and stable At time 10:00
• 2LT-112 (VCT Level Transmitter) fails to 80%

Which ONE of the following completes the statements below? At 10:01, ACTUAL VCT Level is _(1 )_. If ACTUAL VCT Level reaches the AUTO MAKE-UP set point with 2LT-112 failed at 85%, an AUTO MAKE-UP_(2)_ start. (1) (2) L\. lowering will NOT

8. lowering will C. stable will NOT D. stable will L\nswer: C Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the VCT has two level transmitters (L T-112 and LT-114). If LT-114 had failed to 85%, CV-35 would be almost fully diverted to the eves Holdup Tanks. Consequently, the candidate could incorrectly conclude that CV-35 would be almost fully diverted to the CVCS Holdup Tanks which would cause ACTUAL VCT level to lower. Part 2 is correct. B. Incorrect but plausible. For Part 1, the VCT has two level transmitters (LT-112 and LT-114). If LT-114 had failed to 85%, CV-35 would be almost fully diverted to the eves Holdup Tanks. Consequently, the candidate could incorrectly conclude that CV-35 would be almost fully diverted to the CVCS Holdup Tanks which would cause ACTUAL VCT level to lower. For Part 2, the VCT has two level transmitters (LT-112 and LT-114). The candidate could incorrectly conclude that LT-114 controls the AUTO MAKE-UP function. Consequently, the candidate would then incorrectly deduce that with LT-112 failed at 85%, an AUTO MAKE-UP would start when ACTUAL VCT level reaches the AUTO MAKE-UP set point. C. Correct. For Part 1, LT-112 will cause CV-35 to ONLY fully divert to the eves Holdup Tanks at 87% (no modulation of CV-35). Consequently, when LT-112 fails to 85%, CV-35 will remain fully aligned to the VCT and ACTUAL VCT Level will remain stable. For Part 2, LT-112 is the controlling transmitter for AUTO MAKE-UP. Consequently, with LT-112 failed at 85%, an AUTO MAKE-UP will NOT start when ACTUAL VCT level reaches the AUTO MAKE-UP set point. D. Incorrect but plausible. Part 1 is correct. For Part 2, the VCT has two level transmitters {LT-112 and LT-114). The candidate could incorrectly conclude that LT-114 controls the AUTO MAKE-UP function. Consequently, the candidate would then incorrectly deduce that with L T-112 failed at 85%, an AUTO MAKE-UP would start when ACTUAL VCT level reaches the AUTO MAKE-UP set point. Question Number: 40 Tier: 3 Group KIA: G2.1.28 Knowledge of the purpose and function of major system components and controls Importance Rating: 4.1 10 CFR Part 55: 41.7 Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 10 CFR 55.43.b N/A KIA Match: K/A is matched because the candidate must know how the eves Auto Makeup Controller functions when LT-112 (VCT Level Transmitter) fails to 85% SRO Justification: N/A Technical NOS05CVCS00-17 (CHEMICAL AND VOLUME CONTROL

References:

SYSTEM) Proposed references None to be provided: Learning Objective: NOS05CVCS00-17 (CHEMICAL AND VOLUME CONTROL SYSTEM) 7: Identify and describe the local controls, indications, and alarms associated with the Chemical and Volume Control System, including:

a. The location of Chemical and Volume Control System local controls and indications.

b. The function of Chemical and Volume Control System local controls and indications.

c. The plant conditions or permissives required for Chemical and Volume Control System local controls to perform their intended function.

d. The setpoints associated with the Chemical and Volume Control System local alarms.

Cognitive Level: Higher X Lower Question Source New - - Modified Bank Bank X Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 41 Points: 1.00 Given:

• Unit 1 is at 80% Reactor Power and stable At time 10:00:00
• A VCT AUTO MAKE-UP starts
• A malfunction within CVC causes 1CV175 (Rapid Borate Stop Valve) to open At 10:04:00 and with the VCT AUTO MAKE-UP still in progress, which ONE of the following completes the statements below?

Control Rods are _ ( 1) _ . S1 .OP-AB.ROD-0003 (Continuous Rod Motion) Entry Conditions _(2)_ met. (1) (2) A. withdrawing are B. withdrawing are NOT C. inserting are D. inserting are NOT Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, when the AUTO-MAKEUP starts with 1CV175 open, this will cause RCS Boron Concentration to rise and RCS T AVG will lower. Eventually the TAVG - TREF Deviation will large enough to cause control rods to withdraw. For Part 2, since the plant is in steady state conditions with rods moving, S1 .OP-AB.ROD-0003 (Continuous Rod Motion) Entry Conditions are met. B. Incorrect but plausible. Part 1 is correct. For Part 2, since Rod Control is operating properly (responding to an actual TAVG - TREF Deviation cause by an actual boration), the candidate could incorrectly conclude that S1 .OP-AB.ROD-0003 entry conditions are not met. Additionally, the candidate could consider entry into the CVC Abnormal Procedure is the proper procedure to deal with a CVC malfunction. C. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that TAVG would actually rise based on the CVC malfunction which would then cause rods to automatically insert. Part 2 is correct. D. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that TAVG would actually rise based on the CVC malfunction which would then cause rods to automatically insert. Part 2 is correct. For Part 2, since Rod Control is operating properly (responding to an actual TAVG - TREF Deviation cause by an actual boration), the candidate could incorrectly conclude that S1 .OP-AB.ROD-0003 entry conditions are not met. Additionally, the candidate could consider entry conditions into the CVC Abnormal Procedure is the proper procedure to deal with a CVC malfunction. Question Number: 41 Tier: 3 Group KIA: G2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. Importance Rating: 4.1 10 CFR Part 55: 41.10 / 43.6 / 45.6 10 CFR 55.43.b N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) '</A Match: KIA is matched because the candidate must know that S1 .OP-AB.ROD-0003 (Continuous Rod Motion) Entry Conditions are met due to a plant malfunction which causes plant boron concentration to rise adding negative reactivity. SRO Justification: N/A Technical NOS05ABROD3-05 (CONTINUOUS ROD MOTION)

References:

Proposed references None to be provided: Learning Objective: NOS05CVCS00-17 (CHEMICAL AND VOLUME CONTROL SYSTEM) 4: Analyzed the transient/accident for a Continuous Rod Motion: A. Determine the expected alarms and indications; B. Describe the analysis assumptions; C. Describe the protective features that mitigate the event; D. Describe the expected plant response. Cognitive Level: Higher X Lower Question Source New - - - Modified Bank - - - Bank X Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 42 Points: 1.00 Given:

• Corrective Maintenance has just been completed on 2A Emergency Diesel Generator (EOG)
• Operations is preparing to perform a Load Test on 2A EOG as part of the Post -

Maintenance Operability Retest In accordance with S2.0P-ST.DG-0001 (2A Diesel Generator Surveillance Test), which ONE of the following completes the statements below? To prevent tripping the Diesel Generator Breaker on reverse power, generator load must be IMMEDIATELY raised to greater than a MINIMUM of _(1 )_ KW after the breaker is closed. During the Load Test, the 2A EOG may NOT exceed its _(2)_ KW Continuous Load Rating. (1) (2) 500 2600 B. 500 2750 C. 200 2600 D. 200 2750 Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANAL YS/S: A. Correct. For Part 1 and IAW S2.0P-ST.DG-0001, to prevent tripping the Diesel Generator Breaker on reverse power, generator load must be IMMEDIATELY raised to greater than a minimum of 500 KW after the breaker is closed. For Part 2 and IAW S2.0P-ST.DG-0001, during the Load Test, the 2A EOG may NOT exceed its 2600 KW Continuous Load Rating. B. Incorrect but plausible. Part 1 is correct. For Part 2, S2.0P-ST.DG-0001 Precautions And Limitations states that the EOG is rated to 2750 KW for 2000 hours (2681 KW Local). Consequently, the candidate could incorrectly conclude that 2750 KW is the Continuous Loading Rating on the EOG. C. Incorrect but plausible. For Part 1, S2.0P-ST.DG-0001 states that when unloading the EOG, generator load must be maintained at greater than 200 KW until the breaker is opened (to prevent tripping the Diesel Generator Breaker on reverse power). Consequently, the candidate could incorrectly conclude that to prevent tripping the Diesel Generator Breaker on reverse power, generator load must be IMMEDIATELY raised to greater than a minimum of 200 KW after the breaker is closed. Part 2 is correct. D. Incorrect but plausible. For Part 1, S2.0P-ST.DG-0001 states that when unloading the EOG, generator load must be maintained at greater than 200 KW until the breaker is opened (to prevent tripping the Diesel Generator Breaker on reverse power). Consequently, the candidate could incorrectly conclude that to prevent tripping the Diesel Generator Breaker on reverse power, generator load must be IMMEDIATELY raised to greater than a minimum of 200 KW after the breaker is closed. For Part 2, S2.0P-ST.DG-0001 Precautions And Limitations states that the EOG is rated to 2750 KW for 2000 hours (2681 KW Local). Consequently, the candidate could incorrectly conclude that 2750 KW is the Continuous Loading Rating on the EOG. Question Number: 42 Tier: 3 Group KIA: G2.2.21 Knowledge of pre- and post-maintenance operability requirements Importance Rating: 2.9 10 CFR Part 55: 41.10 / 43.2 10 CFR 55.43.b N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) KIA Match: KIA is matched because the candidate must know the post-maintenance operability requirements for the 2A EOG in accordance with S2.0P-ST.DG-0001 (2A Diesel Generator Surveillance Test). SRO Justification: N/A Technical NOS05EDG000-12 (EMERGENCY DIESEL GENERATORS)

References:

Proposed references None to be provided: Learning Objective: NOS05EDG000-12 (EMERGENCY DIESEL GENERATORS) 12: Discuss the procedural requirements associated with the Emergency Diesel Generator, including an explanation of major precaution and limitations in the Emergency Diesel Generator procedures Cognitive Level: Higher -- Lower X Question Source New X Modified Bank -- Bank -- Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 43 Points: 1.00 In accordance with Unit 2 Technical Specifications, which ONE of the following completes the statements below? Safety Limit 2.1.2 (Reactor Coolant System Pressure) will NOT be met when RCS pressure is greater than a MINIMUM of _(1 ) _ psig. If the Unit is in MODE 3 when RCS Pressure has exceeded the Safety Limit 2.1.2 limit, then RCS pressure must be reduced within its limit within a MAXIMUM of _(2)_ minutes. (1) (2) A. 2485 5 B. 2485 60 C. 2735 5 D. 2735 60 Answer: C Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, 2485 psig is the setpoint for the PZR safety valves. Consequently, the candidate could incorrectly conclude that SL 2.1.2 (Reactor Coolant System Pressure) will NOT be met when RCS pressure is greater than a MINIMUM of 2485 psig. Part 2 is correct. B. Incorrect but plausible. For Part 1, 2485 psig is the setpoint for the PZR safety valves. Consequently, the candidate could incorrectly conclude that SL 2.1.2 (Reactor Coolant System Pressure) will NOT be met when RCS pressure is greater than a MINIMUM of 2485 psig. For Part 2, IAW SL 2.1.2, if the Unit was in Mode 1 or 2 when SL 2.1.2 limits were exceeded, then RCS pressure must be reduced within its limit within a MAXIMUM of 60 minutes. Consequently, the candidate could incorrectly conclude that if the Unit was in Mode 3 when SL 2.1.2 limits were exceeded, then RCS pressure must be reduced within its limit within a MAXIMUM of 60 minutes. C. Correct. For Part 1, SL 2.1.2 (Reactor Coolant System Pressure) will NOT be met when RCS pressure is greater than a MINIMUM of 2735 psig. For Part 2, if the Unit is in MODE 3 when RCS Pressure has exceeded the SL 2.1.2 limit, then RCS pressure must be reduced within its limit within a MAXIMUM of 5 minutes. D. Incorrect but plausible. Part 1 is correct. For Part 2, IAW SL 2.1.2, if the Unit was in Mode 1 or 2 when SL 2.1.2 limits were exceeded, then RCS pressure must be reduced within its limit within a MAXIMUM of 60 minutes. Consequently, the candidate could incorrectly conclude that if the Unit was in Mode 3 when SL 2.1.2 limits were exceeded, then RCS pressure must be reduced within its limit within a MAXIMUM of 60 minutes. Question Number: 43 Tier: 3 Group KIA: G2.2.38 Knowledge of conditions and limitations in the facility license Importance Rating: 3.6 10 CFR Part 55: 41.7 / 41.10 / 43.1 / 45.13 10 CFR 55.43.b N/A Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '</A Match: K/A is matched because the candidate must know the RCS Safety Limit Requirement for RCS Pressure IAW Technical Specifications. Technical Specifications are part of the Facility License. SRO Justification: N/A Technical NOS05TECHSPEC-12 (TECHNICAL SPECIFICATIONS)

References:

Proposed references None to be provided: Learning Objective: NOS05TECHSPEC-12 (TECHNICAL SPECIFICATIONS)

6. Explain the term "Safety Limit" as it applies to the Technical Specifications, and describe the Safety Limits for Salem Nuclear Generating Station.

7. Describe the consequences of exceeding a Safety Limit.

Cognitive Level: Higher Lower X Question Source New - - Modified Bank X Bank - - Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 44 Points: 1.00 Given:

• An NEO has signed onto the appropriate RWP to perform work inside a HIGH Radiation Area In accordance with RP-AA-4000 (Personnel Conduct in Radiologically Controlled Areas), which ONE of the following completes the statements below?

In order to ensure the dose limits of the RWP are not exceeded, RP-AA-4000 states that self-reading dosimeters should be read approximately every _(1 ) _ minutes while working in a HIGH Radiation Area. If an unexpected self-reading dosimeter comes into alarm, the NEO is REQUIRED to _(2)_ and notify RP personnel. (1) (2) A. 30 go to a low dose area within the HRA B. 30 exit the HRA immediately C. 15 go to a low dose area within the HRA D. 15 exit the HRA immediately Answer: D Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, RP-AA-4000 states that self-reading dosimeters should be read approximately every 30 minutes while working in a Radiation Area. Consequently, the candidate could incorrectly conclude that self-reading dosimeters should always be read every 30 minutes. For Part 2, the candidate could incorrectly conclude that exiting the RA is not required until RP has verified the alarm is valid. Consequently, the candidate could incorrectly conclude that going to a low dose area and notifying RP is the required response IAW RP-AA-4000. B. Incorrect but plausible. For Part 1, RP-AA-4000 states that self-reading dosimeters should be read approximately every 30 minutes while working in a Radiation Area. Consequently, the candidate could incorrectly conclude that self-reading dosimeters should always be read every 30 minutes. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that exiting the RA is not required until RP has verified the alarm is valid. Consequently, the candidate could incorrectly conclude that going to a low dose area and notifying RP is the required response IAW RP-AA-4000. D. Correct. For Part 1, RP-AA-4000 states that self-reading dosimeters should be read approximately every 15 minutes while working in a High Radiation Area. For Part 2, If an unexpected self-reading dosimeter comes into alarm, the NEO is REQUIRED to exit the area and notify RP personnel. Question Number: 44 Tier: 3 Group KIA: G2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions Importance Rating: 3.6 10 CFR Part 55: 41. 7 / 41.10 / 43.1 / 45.13 10 CFR 55.43.b N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '(IA Match: KIA is matched because the candidate must know the requirements of working in a High Radiation Area in order to comply with an RWP IAVv RP-AA-4000 (Personnel Conduct in Radiologically Controlled Areas). SRO Justification: N/A Technical NOS05RADCON-05 (RADIATION PROTECTION PROGRAM)

References:

Proposed references None to be provided: Learning Objective: NOS05RADCON-05 (RADIATION PROTECTION PROGRAM)

6. In accordance with applicable station procedures:

b) Describe the following posting requirements, as well as any applicable restrictions: i) Contaminated Area ii) High Contamination Area iii) Airborne Radioactivity Area iv) Radiation Area v) High Radiation Area vi) Locked High Radiation Area vii) Exclusion Area viii) Very High Radiation Area Cognitive Level: Higher -- Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 45 Points: 1.00 Given:

• A Licensed Operator notices that a Locked High Radiation Area (LHRA) is unlocked and unmanned In accordance with RP-AA-460 (Controls For High And Very High Radiation Areas), which ONE of the following completes the statements below?

After immediately notifying RP of the unmanned and unlocked LHRA, the Licensed Operator _(1 )_ required to return to the area and maintain positive control until an RP representative arrives. The dose rate for a LHRA is greater than a MINIMUM of _(2)_ mrem / hr@ 30 cm. (1} (2) A. is 100 B. is 1000 C. is NOT 100 D. is NOT 1000 Answer: B Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, greater than 100 mrem @ 30 cm is the definition for a High Radiation Area. Consequently, the candidate could incorrectly determine that the dose rate for a LHRA is greater than a MINIMUM of 100 mrem / hr@ 30 cm. B. Correct. For Part 1 and IAW RP-AA-460 Precautions and Limitations, "Any individual who determines that a HRA, LHRA, or VHRA is not being controlled adequately shall notify RP immediately (while maintaining positive control over the area to the extent possible during this notification period). After notifying RP, the individual shall return to the area and maintain positive control of the area, without personal endangerment, until an RP representative arrives." For Part 2 and IAW RP-AA-460, The dose rate for a LHRA is greater than a MINIMUM of _(2)_ mrem /hr@ 30 cm. C. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that the only requirement in RP-AA-460 for finding an unlocked and unmanned LHRA is to immediately notify RP. For Part 2, greater than 100 mrem@ 30 cm is the definition for a High Radiation Area. Consequently, the candidate could incorrectly determine that the dose rate for a LHRA is greater than a MINIMUM of 100 mrem /hr@ 30 cm. D. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that the only requirement in RP-AA-460 for finding an unlocked and unmanned LHRA is to immediately notify RP. Part 2 is correct. Question Number: 45 Tier: 3 Group KIA: G2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation I areas, aligning filters, etc. Importance Rating: 3.4 10 CFR Part 55: 41.12 / 43.4 / 45.9 I 45.10 10 CFR 55.43.b N/A Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) KIA Match: KIA is matched because the candidate must know the duties of a licensed operator when finding a LHRA unlocked and unmanned IAW RP-AA-460 (Controls For High And Very High Radiation Areas). SRO Justification: N/A Technical NOS05PROCED-08 (USE AND CONTROL OF PROCEDURES)

References:

Proposed references None to be provided: Learning Objective: NOS05PROCED-08 (USE AND CONTROL OF PROCEDURES)

4. In accordance with applicable station procedures:

• Define the following terms:
• Protected Area
• Radiologically Controlled Area (RCA)
• Restricted Area
• Contaminated Area
• High Contamination Area
• Airborne Radioactivity Area
• Radiation Area
• High Radiation Area
• Locked High Radiation Area
• Exclusion Area
• Very High Radiation Area
• ALARA Cognitive Level:

Higher - - Lower X Question Source New - - Modified Bank X Bank - - Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 46 Points: 1.00 Given:

• Unit 1 and Unit 2 are at 100% Reactor Power At time 12:00
• 2R1 B-2 (Unit 1 Control Room Intake Duct) goes into WARNING At time 12:10
• 2R1 B-2 goes into ALARM Which ONE of the following completes the statement below?

_(1 ) _ is the EARLIEST time that Control Room Ventilation has shifted to ACCIDENT PRESSURIZED MODE with _(2)_ EACS Intake dampers AUTOMATICALLY opening. (1) (2) A. 12:00 ONLY Unit 2 B. 12:00 Unit 1 and Unit 2 C. 12:10 ONLY Unit 2 D. 12:10 Unit 1 and Unit 2 Answer: C Page 1 of 8

EXAMINATION ANSWER KEY . Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, other Radiation Monitors (2R19s and 1R19s) have automatic functions when the monitor goes into WARNING. Consequently, the candidate could incorrectly conclude that Control Room Ventilation will shift to ACCIDENT PRESSURIZED MODE when 2R1 B-2 goes into WARNING. Part 2 is correct. B. Incorrect but plausible. For Part 1, other Radiation Monitors (2R19s and 1R19s) have automatic functions when the monitor goes into WARNING. Consequently, the candidate could incorrectly conclude that Control Room Ventilation will shift to ACCIDENT PRESSURIZED MODE when 2R1 B-2 goes into WARNING. For Part 2, since Unit 1 and Unit 2 control room share the same Control Room Envelop, the candidate could incorrectly conclude that Unit 1 and Unit 2 EACS Intake dampers will automatically open. C. Correct. For Part 1, the Control Room Ventilation will shift to ACCIDENT PRESSURIZED MODE when 2R1 B-2 goes into ALARM. This first occurs at 12:10:00. For Part 2, when 2R1 B-2 (Rad monitor is located in Unit 1 Normal Intake Duct) goes into alarm, ONLY the Unit 2 EACS Intake dampers AUTOMATICALLY open. D. Incorrect but plausible. Part 1 is correct. For Part 2, since Unit 1 and Unit 2 control room share the same Control Room Envelop, the candidate could incorrectly conclude that Unit 1 and Unit 2 EACS Intake dampers will automatically open. Question Number: 46 Tier: 3 Group KIA: G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Importance Rating: 3.4 10 CFR Part 55: 41.12 / 43.4 / 45.10 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know how the Control Room Ventilation system will respond when a contamination hazard arises during normal operations. SRO Justification: N/A Page 2 of 8

EXAMINATION ANSWER KEY ... Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Technical NOS05CAVENT-11 (CONTROL AREA VENTILATION SYSTEM)

References:

Proposed references None to be provided: Learning Objective: NOS05CAVENT-11 (CONTROL AREA VENTILATION SYSTEM)

9. State the setpoints, coincidence, blocks and permissives for automatic actuations associated with the Control Area Ventilation System.

Cognitive Level: Higher X Lower Question Source New - - Modified Bank X Bank - - Question History: Comments: Page 3 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 47 Points: 1.00 Given:

• The crew is monitoring the Critical Safety Functions
• The STA has verified the following Critical Safety Function Status Trees (CFSTs):

n accordance with OP-AA-101-111-1003 (Use Of Procedures), which ONE of the following completes the statements below? Based on the Functional Restoration Implementation Priority, the crew is required to FIRST address the challenge to _(1 )_. With verified Red and Purple CFSTs, OP-AA-101-111-1003 states that the CFSTs should be monitored _(2)_. (1) (2) A. Core Cooling every 10-20 minutes B. Core Cooling continuously C. Heat Sink every 10-20 minutes D. Heat Sink continuously Answer: D Page 1 of 6

EXAMINATION ANSWER KEY , Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Since Core Cooling is a higher CSF than Heat Sink, the candidate could incorrectly conclude that based on the status of the CSFTs, the crew is required to first address the challenge to Core Cooling. For Part 2, OP-AA-101-111-1003 does have a provision to monitor CSFTs every 10-20 minutes (if no condition more serious than YELLOW is encountered). Consequently, the candidate could incorrectly conclude that with verified Red and Purple CSFTs, OP-AA-101-111-1003 states that the CFSTs should be monitored every 10-20 minutes.

8. Incorrect but plausible. Since Core Cooling is a higher CSF than Heat Sink, the candidate could incorrectly conclude that based on the status of the CSFTs, the crew is required to first address the challenge to Core Cooling. Part 2 is correct.

C. Incorrect but plausible. Part 1 is correct. For Part 2, OP-AA-101-111-1003 does have a provision to monitor CSFTs every 10-20 minutes (if no condition more serious than YELLOW is encountered). Consequently, the candidate could incorrectly conclude that with verified Red and Purple CSFTs, OP-AA-101-111-1003 states that the CFSTs should be monitored every 10-20 minutes. D. Correct. For Part 1, IAW OP-AA-101-111-1003, CSF Hierarchy (high to low) is SHUTDOWN MARGIN, CORE COOLING, HEAT SINK, THERMAL SHOCK, CONTAINMENT ENVIRONMENT and COOLANT INVENTORY. Additionally, CFST Color Hierarchy (high to low) is red, purple, yellow, and green. Based on the status of the CSFTs, the crew is required to first address the challenge to Heat Sink. For Part 2, with verified Red and Purple CSFTs, OP-AA-101-111-1003 states that the CFSTs should be monitored continuously. Question Number: 47 Tier: 3 Group KIA: G2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations Importance Rating: 3.6 10 CFR Part 55: 41. 7 / 41.10 / 43.1 / 45.13 10 CFR 55.43.b N/A Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '<IA Match: K/A is matched because the candidate must know the bases of how to prioritize implementing Functional Restoration Procedures (part of the EOP network) by actually prioritizing FRP implementation IAW OP-AA-101-111-1003 (Use Of Procedures). SRO Justification: N/A Technical NOS05PROCED-08 (USE AND CONTROL OF PROCEDURES)

References:

Proposed references None to be provided: Learning Objective: NOS05PROCED-08 (USE AND CONTROL OF PROCEDURES)

5. Implement Rules Of Usage For Emergency Operating Procedures Cognitive Level:

Higher X Lower luestion Source New X Modified Bank Bank - - Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) 49 Points: 1.00 Given:

• Unit 1 is at 100% Reactor Power and stable At time 10:00:00
• A valid reactor trip signal is generated by RPS but the Reactor Trip Breakers do NOT open At time 10:00:03
• The Immediate Actions of 1-EOP-TRIP-1 (Reactor Trip Or Safety Injection) have been initiated At time 10:00:25
• The RO attempts to manually trip the Turbine using the Turbine Trip BEZEL but the Turbine does NOT trip In accordance with 1-EOP-TRIP-1, which ONE of the following completes the statements below?

\t 10:00:03, the RO will attempt to manually trip the REACTOR by FIRST actuating the

_(1)_. At 10:00:25, the R0 _(2)_ required to perform a manual MAIN STEAM ISOLATION. (1} (2) A. Trip Breaker BEZELS is NOT

8. Trip Breaker BEZELS is C. Reactor Trip Switches is NOT D. Reactor Trip Switches is Answer: D Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1 and IAW, actuating the Reactor Trip BEZELS is the second option to trip the reactor manually. Consequently, the candidate could incorrectly conclude that using the BEZELS is the actual first required immediate action. For Part 2, the candidate could incorrectly conclude that another action with doesn't isolate the entire Main Steam System (like tripping the turbine locally) could be used to ONLY trip the turbine. B. Incorrect but plausible. For Part 1 and IAW, actuating the Reactor Trip BEZELS is the second option to trip the reactor manually. Consequently, the candidate could incorrectly conclude that using the BEZELS is the actual first required immediate action. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that another action with doesn't isolate the entire Main Steam System (like tripping the turbine locally) could be used to ONLY trip the turbine. D. Correct. 1-EOP-TRIP-1 IMMEDIATE ACTIONS are expected to be performed from memory and in order. For Part 1and IAW 1-EOP-TRIP-1 Step 1, the RO will attempt to trip the Reactor manually by FIRST actuating the Reactor Trip Switches. For Part 2 and IAW 1-EOP-TRIP-1 Step 2.1, since the turbine was not manually tripped using the Turbine BEZELS (or the Turbine Trip Switch), the RO is required to perform a manual MAIN STEAM ISOLATION. Question Number: 49 Tier: 1 Group 1 KIA: EPE: 007 Reactor Trip-EK2.02 Knowledge of the interrelations between a reactor trip and the following: Breakers, relays and disconnects Importance Rating: 2.6 10 CFR Part 55: 41.7 / 45.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the procedural guidance of EOP-TRIP-1 (Reactor Trip Or Safety Injection) when the RTBs fail to open. Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) SRO Justification: N/A Technical 1-EOP-TRIP-1 (Reactor Trip Or Safety Injection)

References:

Proposed references None to be provided: Learning Objective: NOS05TRP001-08 ( REACTOR TRIP OR SAFETY INJECTION) 16 State the Immediate Actions of EOP-TRIP-1 Cognitive Level: Higher -- Lower X Question Source New -- Modified Bank -- Bank X Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 50 Points: 1.00 Given:

• The crew is performing 1-EOP-LOCA-2 (Post LOCA Cooldown and Depressurization)

Step 29, "Monitor For Natural Circulation Flow"

• The RO observes the following:

o CETs are 600 °F and stable o RCS Pressure is 1645 psig and slowly lowering o 11 SG pressure is 725 psig and stable o 11 T-COLD is 509 °F and stable o 11 T-HOT is 530 °F and stable In accordance with 1-EOP-LOCA-2, which ONE of the following completes the statements below? Natural Circulation _(1 ) _ established . .{ Natural Circulation is NOT established, the crew will _(2)_ 11 SG steam dumping rate. (1) (2) A. is raise

8. is lower C. is NOT raise D. is NOT lower Answer: A Page 1 of 5

EXAMINATION ANSWER KEY ., Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANAL YS/S: A. Correct. For Part 1 and IAW 1-EOP-LOCA-2 Step 29, to have proper Natural Circulation flow, the following are required:

• RCS Subcooling based on CETs > 0° F
• RCS Subcooling is 9 °F (TsAT for 1645 psig (1660 psia - RCS Pressure) is 609 °F and CETs are 600 °F)
• SG Pressure stable or lowering (11 SG pressure is 725 psig and stable)
• RCS T HOT stable or lowering (Loop 1 T HOT is 530 °F and stable)
• CETs stable or lowering (CETs are 600 °F and stable)
• 11 SG pressure at saturation pressure for RCS T COLD temperature.
• 11 T coLD is 509 °F (PsAT is 725 psig or 740 psia) and 11 SG pressure is 725 psig Consequently, natural circulation flow is indicated. For Part 2, 1-EOP-LOCA-2 Step 29, "Raise steam dumping rate to establish natural circulation flow."

8. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly raising 11 SG pressure (which is caused by lowering steam dumping rate) will establish natural circulation flow.

C. Incorrect but plausible. For Part 1, since there are 5 separate evaluations required to determine if natural circulation has been established, the candidate could incorrectly perform one of the evaluations and determine that natural circulation is not establish. Part 2 is correct. D. Incorrect but plausible. For Part 1, since there are 5 separate evaluations required to determine if natural circulation has been established, the candidate could incorrectly perform one of the evaluations and determine that natural circulation is not establish. For Part 2, 1-EOP-LOCA-2 Step 29, "Raise steam dumping rate to establish natural circulation flow." Question Number: 50 Tier: -- 1 Group 1 KIA: EPE: 011 Large Break LOCA-EK1 .01 Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA : Natural circulation and cooling, including reflux boiling Page 2 of 5

EXAMINATION ANSWER KEY '. Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 'mportance Rating: 4.1 10 CFR Part 55: 41.8 / 41.10 / 45.3 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the procedural guidance of 1-EOP-LOCA-2 to determine if natural circulation has been established and the actions to take if natural circulation has not been established SRO Justification: N/A Technical 1-EOP-LOCA-2 (Post LOCA Cooldown and Depressurization)

References:

Proposed references None to be provided: Learning Objective: NOS05LOCA02-03 (EOP-LOCA-2, POST-2 POST-LOCA COOL DOWN AND DEPRESSURIZATION) 5 Determine the indications that are monitored to ensure proper system/component operation for each step in the EOP for POST LOCA COOLDOWN AND DEPRESSURIZATION Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 51 Points: 1.00 Given:

• Unit 2 is at 75% Reactor Power
• 22 RCP is experiencing abnormal vibrations At time 07:00:00
• The crew is performing S2.0P-AB-RCP-0001 (Reactor Coolant Pump Abnormality)

Attachment 2 (Stopping Reactor Coolant Pumps)

• The Reactor TRIP has been CONFIRMED
• Reactor Trip Breaker 'A' is closed
• 22 RCP has been stopped At 07:00:00, which ONE of the following completes the statements below?

In accordance with S2.0P-AB-RCP-0001, the crew was required to stop 22 RCP when the

*alidated motor flange vibration exceeded a MINIMUM of _(1 ) _ mils.

LCO 3.4.1.2 (Reactor Coolant Loops And Coolant Circulation Hot Standby) _(2)_ met. (1} (2) A. 5 is NOT B. 5 is C. 20 is NOT D. 20 is Answer: B Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, LCO 3.4.1.2 requires all loops to be OPERABLE if rod control is energized. Consequently, based on the question stem conditions, the candidate could incorrectly conclude that all four of the reactor coolants are required to be OPERABLE. This would then cause the candidate to further incorrectly deduce that LCO 3.4.1.2 is not met. B. Correct. For Part 1, IAW S2.0P-AB-RCP-0001 CAS, when motor flange vibration greater than 5 mils, the crew will perform S2.0P-AB-RCP-0001 Attachment 2 and stop 22 RCP. For Part 2, LCO 3.4.1.2 only requires two of the reactor coolants to be OPERABLE (if the rod control system is de-energized). Consequently, at 07:00:00, RTB B is open and BOTH RTB Bypass Breakers are not racked in, so LCO 3.4.1.2 is met. C. Incorrect but plausible. For Part 1, S2.0P-AB-RCP-0001 CAS requires the RCP to be secured when shaft vibration is greater than 20 mils or motor flange vibration is greater than 5 mils. Consequently, the candidate could incorrectly conclude that the 22 RCP is stopped when the motor flange vibration exceeded a minimum of 20 mils. For Part 2, LCO 3.4.1.2 requires all loops to be OPERABLE if rod control is energized. Consequently, based on the question stem conditions, the candidate could incorrectly conclude that all four of the reactor coolants are required to be OPERABLE. This would then cause the candidate to further incorrectly deduce that LCO 3.4.1 .2 is not met. D. Incorrect but plausible. For Part 1, S2.0P-AB-RCP-0001 CAS requires the RCP to be secured when shaft vibration is greater than 20 mils or motor flange vibration is greater than 5 mils. Consequently, the candidate could incorrectly conclude that the 22 RCP is stopped when the motor flange vibration exceeded a minimum of 20 mils. Part 2 is correct. Question Number: 51 Tier: 1 Group 1 KIA: APE: 015/017 Reactor Coolant Pump (RCP) Malfunctions-G2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications. Importance Rating: 3.9 10 CFR Part 55: 41.7 / 41.10 / 43.2 / 43.3 / 45.3 Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b N/A KIA Match: K/A is matched because the candidate must knowthe status of LCO 3.4.1.2 (Reactor Coolant Loops And Coolant Circulation Hot Standby) when the 22 RCP is secured after the reactor has been tripped from 75% power IAW S2.0P-AB-RCP-0001 (Reactor Coolant Pump Abnormality) SRO Justification: N/A Technical S2.0P-AB-RCP-0001

References:

LCO 3.4.1.2 Proposed references None to be provided: Learning Objective: NOS05ABRCP0-06 (REACTOR COOLANT PUMP ABNORMALITY) 3 Describe, in general terms, the actions taken in S2.0P-AB.RCP-0001 and the bases for the actions in accordance with the Technical Bases Document Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 52 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power and stable At time 16:00:00
• 2R41 (Plant Radiation Monitor) reading is trending up
• PZR Level is lowering
• Seal Injection flow is lowering
• Letdown line flashing is occurring At 16:00:00, which ONE of the following completes the statements below?

There is a leak on the eves _(1 ) _ line. S2.0P-AB.CVC-0001 (Loss Of Charging) entry conditions _(2)_ met. (1} (2) A. letdown are B. letdown are NOT C. charging are D. charging are NOT Answer: C Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, many of the indications given are also indicative of a letdown line leak (PZR level J and Plant Radiation Monitor t ). Consequently, the candidate could incorrectly conclude that a leak on the CVCS letdown line exists. For Part 2, the candidate could incorrectly that a leak on the letdown would ultimately affect charging flow rate. A reduction in charging flow is an entry condition to S2.0P-AB.CVC-0001.

8. Incorrect but plausible. For Part 1, many of the indications given are also indicative of a letdown line leak (PZR level J and Plant Radiation Monitor i ). Consequently, the candidate could incorrectly conclude that a leak on the CVCS letdown line exists. For Part 2, a leak on the letdown line is not an entry condition to S2.0P-AB.CVC-0001.

C. Correct. For Part 1 , based on the question stem conditions, there is a leak on the eves charging line (seal injection t, PZR level J, Plant Radiation Monitor i and flashing in the letdown line). For Part 2, a leak in the charging supply line is an entry condition for S2.0P-AB.CVC-0001. D. Incorrect but plausible. Part 1 is correct. For Part 2, since RCS inventory is being lost, the candidate could incorrectly conclude that only entry conditions to S2.0P-AB.RC-0001 (Reactor Coolant System Leak) are met. Additionally, since the charging pump is providing flow to seal injection and the regenerative heat exchanger, the candidate could also incorrectly conclude S2.0P-AB.CVC-0001 are not met. Question Number: 52 Tier: 1 Group KIA: APE: 022 Loss of Reactor Coolant Makeup-AA2.01 Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Whether charging line leak exists Importance Rating: 3.2 10 CFR Part 55: 43.5 / 45.13 10 CFR 55.43.b N/A Page 2 of 6

EXAMINATION ANSWER. KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) l,{JA Match: KIA is matched because the candidate must determine if a charging line leak exists based on plant conditions and if so, are the entry conditions to S2.0P-AB.CVC-0001 (Loss Of Charging) met. SRO Justification: N/A Technical S2.0P-AB.CVC-0001 (Loss Of Charging)

References:

Proposed references None to be provided: Learning Objective: NOS05ABRCP0-06 (REACTOR COOLANT PUMP ABNORMALITY) 3 Given a set of initial plant conditions:

a. Determine the appropriate abnormal procedure.

b. Describe the plant response to actions taken in the abnormal procedure.

c. Describe the final plant condition that is established by the abnormal procedure Cognitive Level:

Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 53 Points: 1.00 Given:

• The crew is preparing to perform S1 .OP-AB.RHR-0001 (Loss Of RHR) Attachment 13 (Cold Leg Recirculation)

In accordance with S1 .OP-AB.RHR-0001 Attachment 13, which ONE of the following completes the statements below? The crew _(1 ) _ align an intact RHR Train to take suction from the Containment Sump. Performance of S1 .OP-AB.RHR-0001 Attachment 13 will _(2)_. (1) (2) A. will ensure long term decay heat removal

8. will maintain adequate Shutdown Margin

"'                   will NOT                           ensure long term decay heat removal D.                    will NOT                           maintain adequate Shutdown Margin Answer:       A Page 1 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, IAW S2.0P-AB.RHR-0001 Attachment 13, the crew will align an intact RHR Train to take suction from the Containment Sump. For Part 2, IAW S2.0P-AB.RHR-0001, the purpose of Attachment 13 is to provide long term decay heat removal. B. Incorrect but plausible. Part 1 is correct. For Part 2, S2.0P-AB.RHR-0001 Attachments 7, 8, 9, and 11 mentions that proper completion of these attachments will maintain adequate Shutdown Margin. Consequently, the candidate could incorrectly conclude that performance of Attachment 13 will also maintain adequate Shutdown Margin. C. Incorrect but plausible. For Part 1, RHR is isolated during the performance of S2.0P-AB.RHR-0001. During performance of Attachments 7 and 8, charging pumps and/or SI pumps are used to inject water into the core. Consequently, the candidate could incorrectly conclude that some other pump (other than an RHR Pump) will be aligned to the containment sump to provide cold leg recirculation. Part 2 is correct.

• D. Incorrect but plausible. For Part 1, RHR is isolated during the performance of S2.0P-AB.RHR-0001. During performance of Attachments 7 and 8, charging pumps and/or SI pumps are used to inject water into the core. Consequently, the candidate could incorrectly conclude that some other pump (other than an RHR Pump) will be aligned to containment sump to provide cold leg recirculation. For Part 2, S2.0P-AB.RHR-0001 Attachments 7, 8, 9, and 11 mentions that proper completion of these attachments will maintain adequate Shutdown Margin. Consequently, the candidate could incorrectly conclude that performance of Attachment 13 will also maintain adequate Shutdown Margin.

Question Number: 53 Tier: -- 1 Group 1 KIA: 025 Loss of Residual Heat Removal System (RHRS)-AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Shift to alternate flowpath Importance Rating: 3.1 10 CFR Part 55: 41.5,41.10 / 45.6 / 45.13 10 CFR 55.43.b N/A Page 2 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '<IA Match: KIA is matched because the candidate must know why the alternate RHR flowpath (cold leg recirculation) is aligned during performance of S1 .OP-AB.RHR-0001 (Loss Of RHR). SRO Justification: N/A Technical S1 .OP-AB.RHR-0001 (Loss Of RHR)

References:

Proposed references None to be provided: Learning Objective: NOS05ABRCP0-06 (REACTOR COOLANT PUMP ABNORMALITY) 1 Describe the operation of the following system as applied to S2.0P-AB.RHR-0001: A. General arrangement of the RHR system

8. RHR system lineup for Shutdown Cooling .

.;ognitive Level: Higher -- Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 54 Points: 1.00 Given:

• Unit 1 is at 100% Reactor Power and stable
• 12 CC Heat Exchanger is in service
• 12 Charging Pump is in service
• CCW Surge Tank level is 61 % and rising
• The crew is performing S1 .OP-AB.CC-0001 (Component Cooling Abnormality)
• Chemistry has sampled CCW and reports the following parameters have changed based on the previous CCW sample before S1 .OP-AB.CC-0001 was entered:

o Chromate concentration has lowered o Chloride concentration has risen In accordance with S1 .OP-AB.CC-0001, which ONE of the following completes the statement below? The leak is located in the - - - A. Seal Water Heat Exchanger B. Letdown Heat Exchanger C. 12 CC Heat Exchanger D. 12 Charging Pump Answer: C Page 1 of 5

      ,,                EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL)

I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Since ALL three distractors will cause CCW Surge Tank level to rise and chromate concertation to lower, the candidate could incorrectly conclude any of the distractors are the source of the CCW leak. B. Incorrect but plausible. Since ALL three distractors will cause CCW Surge Tank level to rise and chromate concertation to lower, the candidate could incorrectly conclude any of the distractors are the source of the CCW leak. C. Correct. IAW S1 .OP-AB.CC-0001, "Any inleakage will dilute CC System Chromates and SW inleakage will increase Chloride concentration." Consequently, since Chemistry has reported that Chloride concentration has risen, there is SW inleakage into CCW. 12 CC Heat Exchanger is the source of the CCW Leakage. D. Incorrect but plausible. Since ALL three distractors will cause CCW Surge Tank level to rise and chromate concertation to lower, the candidate could incorrectly conclude any of the distractors are the source of the CCW leak. Question Number: 54 Tier: Group 1 KIA: APE: 026 Loss of Component Cooling Water (CCW)-AA2.01 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS Importance Rating: 3.1 10 CFR Part 55: 41.5,41.10 / 45.6 / 45.13 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know must analyze plant conditions and use the procedural guidance contained in S1 .OP-AB.CC-0001 (Component Cooling Abnormality) to determine the location of a leak into the CCW system SRO Justification: N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Technical S1 .OP-AB.CC-0001 (Component Cooling Abnormality) ,{eferences: Proposed references None to be provided: Learning Objective: N0S05ABCC01-09 (COMPONENT COOLING ABNORMALITY) 5 Given a set of initial plant conditions: A. Determine the appropriate abnormal procedure. B. Describe the plant response to actions taken in the abnormal procedure. C. Describe the final plant condition that is established by the abnormal procedure. Cognitive Level: Higher X Lower Question Source New Modified Bank X Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 55 Points: 1.00 Given:

• Unit 2 is at 50% Reactor Power and stable
• PT-455 (Channel I PZR Pressure) is the controlling PZR Pressure channel At time 22:00:00
• PT-455 (Channel I PZR Pressure) fails high At time 22:00:10
• The crew enters S2.0P-AB.PZR-0001 (Pressurizer Pressure Malfunction)

Which ONE of the following completes the statements below? At 22:00:05, 2PR1 (Power Relief Valve) was _(1 )_. In accordance with S2.0P-AB.PZR-0001, the crew _(2)_ place the Master Pressure Controller in MANUAL before selecting PT-457 (Channel Ill PZR Pressure) as the controlling PZR

,ressure channel.

(1) (2) A. closed will NOT

8. closed will C. open will NOT D. open will Answer: B Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation 0/STRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, the Master Pressure Controller controls are laid out such that the controlling channel can be selected without the controller being in MANUAL. Consequently, the candidate could incorrectly conclude that S2.0P-AB.PZR-0001 allows the operator to select the controlling channel with the controller in AUTOMATIC. B. Correct. For Part 1, 2PR1 requires 2 channels (PT-455 and PT-457) to read greater than 2335 for the PORV to open. Consequently, at 22:00:05 with ONLY PT-455 reading greater than 2335 psig (due to PT-455 failing high}, 2PR1 is closed. For Part 2, IAW with S2.0P-AB.PZR-0001, the crew will place the Master Pressure Controller in MANUAL before selecting PT-457 (Channel Ill PZR Pressure) as the controlling PZR Pressure channel. C. Incorrect but plausible. For Part 1, Since the controlling pressurizer pressure channel has failed high, the candidate could incorrectly conclude that 2PR1 will open (since the Pressurizer PORVs are designed to open on an actual high pressure condition). For Part 2, the Master Pressure Controller controls are laid out such that the controlling channel can be selected without the controller being in MANUAL. Consequently, the candidate could incorrectly conclude that S2.0P-AB.PZR-0001 allows the operator to select the controlling channel with the controller in AUTOMATIC. D. Incorrect but plausible. For Part 1, Since the controlling pressurizer pressure channel has failed high, the candidate could incorrectly conclude that 2PR1 will open (since the Pressurizer PORVs are designed to open on an actual high pressure condition). Part 2 is correct. Question Number: 55 Tier: 1 Group 1 KIA: 027 Pressurizer Pressure Control System (PZR PCS) Malfunction-AK2.03 Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners Importance Rating: 2.6 10 CFR Part 55: 41.7 / 45.7 10 CFR 55.43.b NIA Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '<lA Match: K/A is matched because the candidate must know the procedural guidance per S2.0P-AB.PZR-0001 (Pressurizer Pressure Malfunction) for selecting the alternate pressurizer pressure control channel (PT-457) after the controlling channel has failed high (PT-455) SRO Justification: N/A Technical S2.0P-AB.PZR-0001 (Pressurizer Pressure Malfunction)

References:

Proposed references None to be provided: Learning Objective: NOS05ABPZR1-03 (PRESSURIZER PRESSURE MALFUNCTION) 3 Given a set of initial plant conditions: A. Determine the appropriate abnormal procedure.

8. Describe the plant response to actions taken in the abnormal procedure.

C. Describe the final plant condition that is established by the abnormal procedure. Cognitive level: Higher X lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 56 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power and stable
• 21 Charging Pump is in service At time 10:00:00
• A valid reactor trip signal is generated by RPS but the Reactor Trip Breakers do NOT open At time 10:00: 10
• The crew has transitioned to 2-EOP-FRSM-1 (Response To Nuclear Power Generation)
• SI has NOT actuated In accordance with 2-EOP-FRSM-1, which ONE of the following completes the statements below?

The crew will ensure _(1 ) _ Charging Pumps are running.

'\fter the REQUIRED Charging Pumps have been started, the crew _(2)_ REQUIRED to MANUALLY actuate Safety Injection.

(1) (2) A. ALL three is B. ALL three is NOT C. AT LEAST two is D. AT LEAST two is NOT Answer: D Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANAL YS/S: A. Incorrect but plausible. For Part 1, having 3 Charging Pumps running will inject Boron faster than only 2 Charging Pumps. Since an A TWS is in progress, the candidate could incorrectly conclude that FRSM-1 requires all 3 Charging Pumps in operation. For Part 2, 2-EOP-FRSM-1 has a provision for aligning the charging pumps to take suction from the RWST. Consequently, the candidate could incorrectly conclude that for the given plant conditions, the crew will align the charging pumps to take suction from the RWST. B. Incorrect but plausible. For Part 1, having 3 Charging Pumps running will inject Boron faster than only 2 Charging Pumps. Since an ATWS is in progress, the candidate could incorrectly conclude that FRSM-1 requires all 3 Charging Pumps in operation. in Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that actuating Safety Injection is advantageous and required per FRSM-1. D. Correct. For Part 1 and IAW 2-EOP-FRSM-1 Step 3, the crew will ensure at least two charging pumps are running. For Part 2 and IAW 2-EOP-FRSM-1 Step 3.1, the crew is not required to actuate Safety Injection. Question Number: 56 Tier: 1 Group 1 KIA: EPE: 029 Anticipated Transient Without Scram (ATWS)-EA1 .01 Ability to operate and monitor the following as they apply to a ATWS: Charging pumps Importance Rating: 3.4 10 CFR Part 55: 41.7 I 45.5 I 45.6 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the procedural guidance per 2-EOP-FRSM-1 (Response To Nuclear Power Generation) for operating and aligning the charging pumps. SRO Justification: N/A Technical 2-EOP-FRSM-1 (Response To Nuclear Power Generation) Page 2 of 4

' EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL)

References:

Proposed references None to be provided: Learning Objective: NOS05FRSM00-04 (EOP-FRSM-1 AND 2 RESPONSE TO NUCLEAR POWER GENERATION) 3 Describe the plant response to actions taken in the following EOP step sequence(s): A. Response To Nuclear Power Generation: 1, 3, 4.1, 10, and 12 thru 15 Cognitive Level: Higher - - Lower X Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 57 Points: 1.00 Given:

• The crew has just terminated SI in accordance with 1-EOP-SGTR-1 (Steam Generator Tube Rupture)
• 14 SG is ruptured Which ONE of the following completes the statements below?

The reason SI was terminated during performance of 1-EOP-SGTR-1 is to prevent overfill of _(1)_. In accordance with 1-EOP-SGTR-1 CAS, the crew will reestablish ECCS flow if _(2)_ . (1) (2) A. 14 SG PZR level can NOT be maintained ~ 11 % OR Subcooling is s 0°F 14 SG ONLY PZR level can NOT be maintained ~ 11 % C. the pressurizer PZR level can NOT be maintained ~ 11 % OR Subcooling is s 0°F D. the pressurizer ONLY PZR level can NOT be maintained ~ 11 % Answer: A Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, the reason ECCS flow is terminated during performance of 1-EOP-SGTR-1 is to prevent overfill of the ruptured SG (14 SG). For Part 2 and IAW -EOP-SGTR-1 CAS, the crew will reestablish ECCS flow if PZR level can not be maintained~ 11 % OR Subcooling is~ 0°F. B. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that 1-EOP-SGTR-1 CAS requirements are to reestablish ECCS flow if ONLY PZR level can NOT be maintained ~ 11 %. C. Incorrect but plausible. For Part 1, 14 SG and the PZR are in hydraulic communication during a SGTR. The candidate may misunderstand the hydraulics between the RCS and the ruptured SG and incorrectly conclude that prolonged full ECCS flow will cause pressurizer level to rise and even possible overfill. Additionally, the steps prior to terminating ECCS flow include depressurization of the RCS. When the RCS is depressurized during EOP-SGTR-1, voiding in the upper head may occur which will cause PZR level to rapidly increase. The candidate could misapply the concern for rapidly rising PZR during RCS depressurization and incorrectly apply this concern to prolonged ECCS full flow during the performance of EOP-SGTR-1. Part 2 is correct. D. Incorrect but plausible. For Part 1, 14 SG and the PZR are in hydraulic communication during a SGTR. The candidate may misunderstand the hydraulics between the RCS and the ruptured SG and incorrectly conclude that prolonged full ECCS flow will cause pressurizer level to rise and even possible overfill. Additionally, the steps prior to terminating ECCS flow include depressurization of the RCS. When the RCS is depressurized during EOP-SGTR-1, voiding in the upper head may occur which will cause PZR level to rapidly increase. The candidate could misapply the concern for rapidly rising PZR during RCS depressurization and incorrectly apply this concern to prolonged ECCS full flow during the performance of EOP-SGTR-1. For Part 2, the candidate could incorrectly conclude that 1-EOP-SGTR-1 GAS requirements are to reestablish ECCS flow if ONLY PZR level can NOT be maintained ~ 11 %. Question Number: 57 Tier: 1 Group 1 KIA: EPE: 038 Steam Generator Tube Rupture (SGTR)-EK3.09 Knowledge of the reasons for the following responses as the apply to the SGTR: Criteria for securing/throttling ECCS Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -{T-75 SUBMITTAL) Importance Rating: 4.1 10 CFR Part 55: 41.5 / 41.10 / 45.6 / 45.13 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the reason ECCS flow is terminated during the performance of 1-EOP-SGTR-1 (Steam Generator Tube Rupture). SRO Justification: NIA Technical 1-EOP-SGTR-1 (Steam Generator Tube Rupture)

References:

Proposed references None to be provided: Learning Objective: NOS05SGTR01-04 ( STEAM GENERATOR TUBE RUPTURE) 3 Describe the EOP mitigation strategy for a steam generator tube rupture Cognitive Level: Higher - - Lower X Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 58 Points: 1.00 In accordance with S2.0P-AB.CN-0001 (Main Feedwater / Condensate System Abnormality), which ONE of the following completes the statements below? If Reactor Power is greater than 5%, and _(1 ) _ SG narrow range level(s) on any SIG is/ are less than _(2)_%, then the crew will TRIP the Reactor and GO TO 2-EOP-TRIP-1 (Reactor Trip or Safety Injection) (1) (2) A. AT LEAST two 14 B. AT LEAST two 16 C. ONLY one 14 D. ONLY one 16 Answer: B Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. The candidate could incorrectly conclude that S2.0P-AB.CN-0001 requires the reactor to be tripped when any one of the three SG NR Levels are less than 16%. B. Correct. For Part 1, IAW S2.0P-AB.CN-0001 CAS, "IF AT ANY TIME Reactor Power is greater than 5%, AND two SIG narrow range levels on any S/G are less than 16%, THEN TRIP Reactor, AND GO TO 2-EOP-TRIP-1. C. Incorrect but plausible. 14% SG NR Level is the LO-LO alarm setpoint. The candidate could incorrectly conclude that S2.0P-AB.CN-0001 requires the reactor to be tripped when any one of the three SG NR Levels are less than the LO-LO alarm setpoint (14%). D. Incorrect but plausible. 14% SG NR Level is the LO-LO alarm setpoint. The candidate could incorrectly conclude that S2.0P-AB.CN-0001 requires the reactor to be tripped when any two of the three SG NR Levels are less than the LO-LO alarm setpoint (14%). Question Number: 58

 'ier:     1     Group       1 KIA:      054 Loss of Main Feedwater (MFW)-G2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs Importance Rating:          3.8 10 CFR Part 55:             41.10 / 43.5 / 45.13 10 CFR 55.43.b             N/A KIA Match:                  KIA is matched because the candidate must know the procedural guidance in S2.0P-AB.CN-0001 (Main Feedwater / Condensate System Abnormality) which requires tripping the reactor and going to 2-EOP-TRIP-1 (Reactor Trip or Safety Injection). This is using an AOP in conjunction with an EOP.

SRO Justification: N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) Technical S2.0P-AB.CN-0001 (Main Feedwater / Condensate System ,{eferences: Abnormality) Proposed references None to be provided: Learning Objective: NOS05ABCN01-06 ( MAIN FEEDWATER/CONDENSATE SYSTEM ABNORMALITY} 3 Describe, in general terms, the actions taken in AB.CN-0001 and the bases for the actions in accordance with the technical bases document. Cognitive Level: Higher - - Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 59 Points: 1.00 Given:

• The crew is preparing to perform the Vital Power Restoration Steps of 1-EOP-LOPA-1 (Loss Of All AC Power)

In accordance with 1-EOP-LOPA-1, which ONE of the following completes the statements below? Prior to restoring AC power, the crew will ensure ALL SE Cs are _(1 ) _ . Preventing damage to the RCP seals _(2)_ a reason that the centrifugal charging pumps are NOT allowed to start automatically following power restoration. (1) (2) A. de-energized is NOT B. de-energized is

"'.,,              blocked and reset                                  is NOT D.                  blocked and reset                                      is Answer:        B Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) ' Answer Explanation D/STRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, restoring seal injection is normally desirable and will usually help protect the RCPs seals. Consequently, the candidate could incorrectly conclude that preventing RCS seal damage is NOT a reason for preventing auto start of the centrifugal charging pumps following power restoration. B. Correct. For Part 1, IAW 1-EOP-LOPA-1, prior to restoring AC power, the crew will ensure ALL SECs are de-energized. For Part 2, IAW 1-EOP-LOPA-1, preventing damage to the RCP seals is a reason that the centrifugal charging pumps are not allowed to start automatically following power restoration. C. Incorrect but plausible. For Part 1, blocking and resetting the SECs is performed throughout the EOP Network (e.g. EOP-TRIP-1 ). Consequently, the candidate could incorrectly conclude that EOP-LOPA-1 requires ALL SECs to be blocked and reset. D. Incorrect but plausible. For Part 1, blocking and resetting the SECs is performed throughout the EOP Network (e.g. EOP-TRIP-1 ). Consequently, the candidate could incorrectly conclude that EOP-LOPA-1 requires ALL SECs to be blocked and reset. Part 2 is correct. Question Number: 59 Tier: 1 Group 1 KIA: EPE: 055 Loss of Offsite and Onsite Power (Station B1ackout)-EK3.02 Knowledge of the reasons for the following responses as the apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power Importance Rating: 4.3 10 CFR Part 55: 41.5 / 41.10 / 45.6 / 45.13 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the reason the centrifugal charging pumps are not allowed to start automatically following power restoration IAW 1-EOP-LOPA-1 (Loss Of All AC Power) Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) <,RO Justification: N/A Technical 1-EOP-LOPA-1 (Loss Of All AC Power)

References:

Proposed references None to be provided: Learning Objective: NOS05LOPA00-06 (EOP-LOPA-1, 2, 3; LOSS OF ALL AC POWER AND RECOVERY) 3 Describe the consequences of an uncontrolled restoration of seal cooling to the reactor coolant pump seals. Cognitive Level: Higher -- Lower X Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 60 Points: 1.00 Given

• Unit 2 is in MODE 4
• RCS TAVG is 300°F and stable
• 21 RHR Loop is in service for shutdown cooling
• 22 RHR Loop is aligned for ECCS
• 2C EOG is running and paralleled with the Grid in accordance with S2.0P-ST.DG-0003 (2C Diesel Generator Surveillance Test)

At time 12:00

• A Loss of Offsite Power (LOOP) occurs Which ONE of the following completes the statements below?

During the electrical transient, the 2C EOG Output Breaker will _(1 ) _ . ,*U 12:15, 21 RHR Pump is_(2)_. (1) (2) A. remain closed stopped B. remain closed running C. open then reclose stopped D. open then reclose running Answer: C Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, since 2C EOG was already running loaded during the LOOP, the candidate could incorrectly conclude that 2C EOG would remain closed as SEC 2C strips the loads off of 2C 4KV Vital Bus and then automatically loads the blackout loads. Part 2 is correct. For Part 2, the RHR pumps are automatically sequenced on their respective Vital Susses when the SECs are in Mode I (SI only) and Mode Ill (SI & Blackout). Consequently, the candidate could incorrectly conclude that following a LOOP that an RHR pump that had been running in Shutdown Cooling will automatically restart after the SECs complete their sequencing. B. Incorrect but plausible. For Part 1, since 2C EOG was already running loaded during the LOOP, the candidate could incorrectly conclude that 2C EOG would remain closed as SEC 2C strips the loads off of 2C 4KV Vital Bus and then automatically loads the blackout loads. C. Correct. For Part 1, when the LOOP occurs at 12:00, 2A and 28 4K Vital Susses will sense an Instantaneous UV condition which will cause ALL three 3 SECs (2A, 28 and 2C) to enter Mode II - Blackout Only (2 / 3 Vital Susses sensing Instantaneous UV condition). Since the 2C SEC has gone into Mode II, this will cause the running 2C EOG Output Breaker to OPEN. At the SEC 2C continues its sequencing, the 2C EOG Output Breaker will reclose. For Part 2, 21 RHR Pump is powered from 2A 4KV Vital Bus. With 2A SEC in Mode II, the 21 RHR will NOT be automatically loaded (during the 2A SEC sequencing). Consequently, at 12:15 (after SEC 2A has completed its sequencing), 21 RHR pump is stopped.

0. Incorrect but plausible. Part 1 is correct. For Part 2, the RHR pumps are automatically sequenced on their respective Vital Susses when the SECs are in Mode I (SI only) and Mode Ill (SI & Blackout). Consequently, the candidate could incorrectly conclude that following a LOOP that an RHR pump that had been running in Shutdown Cooling will automatically restart after the SECs complete their sequencing.

Question Number: 60 Tier: 1 Group 1 KIA: APE: 056 Loss of Offsite Power-AA2.54 Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Breaker position (remote and local) Importance Rating: 2.9 Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 10 CFR Part 55: 43.5 I 45.13 10 CFR 55.43.b NIA KIA Match: KIA is matched because the candidate must know how the 2C EOG Output Breaker responds following a LOOP and the 2C EOG initially paralleled to the Grid. SRO Justification: N/A Technical NOS05EDG000-12 (Emergency Diesel Generators)

References:

Proposed references None to be provided: Learning Objective: NOS05EDG000-12 (Emergency Diesel Generators) 14 Given plant conditions, relate the Emergency Diesel Generator with the following:

a. 4160 Electrical System

b. Service Water System

c. DC Distribution System

d. Diesel Starting Air

e. Safeguards Equipment Controller.

Cognitive Level: Higher X Lower -- Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 61 Points: 1.00 Given: At time 10:00:00

• Unit 2 is at 100% Reactor Power and stable
• The crew enters S2.0P-AB.CA-0001 (Loss of Control Air)
• NEOs are walking down the Control Air System searching for a large air leak
• Control Air Header Pressure is observed as follows:

Time 10:00 10:05 10:10 10:15 2A Control Air Header 99 psig 88 psig 79 psig 72 psig 28 Control Air Header 103 psig 93 psig 85 psig 79 psig 1n accordance with S2.0P-AB.CA-0001, which ONE of the following completes the statements Jelow? _(1 ) _ is the EARLIEST time the crew is required to attempt to MANUALLY start the 2 Emergency Control Air Compressor. _(2)_ is the EARLIEST time the crew is required to TRIP the Reactor. (1) (2) A. 10:00 10:10 B. 10:00 10:15 C. 10:05 10:10 D. 10:05 10:15 '\nswer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, IAW S2.0P-AB.CA-001 Step 3. 7, if either Station Air Header is indicating less than 100 psig, the crew is required to attempt to start the remaining Station Air Compressor. Consequently, the candidate could incorrectly conclude that the crew is required to attempt to start the 2 Emergency Air Compressor when 2A Control Air Header pressure is less than 100 psig. For Part 2, the candidate may recognize the 80 psig Control Air Header threshold for tripping the reactor. However, the candidate may incorrectly conclude that reactor is required to be tripped when only one of the Control Air Header pressures is less than 80 psig.

8. Incorrect but plausible. For Part 1, IAW S2.0P-AB.CA-001 Step 3.7, if either Station Air Header is indicating less than 100 psig, the crew is required to attempt to start the remaining Station Air Compressor. Consequently, the candidate could incorrectly conclude that the crew is required to attempt to start the 2 Emergency Air Compressor when 2A Control Air Header pressure is less than 100 psig. Part 2 is correct.

C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate may recognize the 80 psig Control Air Header threshold for tripping the reactor. However, the candidate may incorrectly conclude that reactor is required to be tripped when only one of the Control Air Header pressures is less than 80 psig. D. Correct. For Part 1, IAW S2.0P-AB.CA-001 Step 3.10, the crew is required to attempt to start the 2 Emergency Control Air Compressor when 2A Control Air Header less than or equal to 88 psig. The earliest time this occurs is 10:05:00. For Part 2, IAW S2.0P-AB.CA-0001 (Selected GAS Items), the reactor is first required to be trip when BOTH 2A and 28 Control Air Headers indicate less than 80 psig. The earliest time this occurs is at 1015:00. Question Number: 61 Tier: Group 1 KIA: APE: 065 Loss of Instrument Air-G2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material Importance Rating: 4.2 10 CFR Part 55: 41.10 / 43.5 / 45.12 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) ~o CFR 55.43.b N/A KIA Match: K/A is matched because the candidate must analyze a trend of Control Air Header Pressures over time and determine the required crew response IAW S2.0P-AB.CA-0001 (Loss of Control Air) SRO Justification: N/A Technical S2.0P-AB.CA-0001 (Loss of Control Air)

References:

Proposed references None to be provided: Learning Objective: NOS05ABCA01-07 ( LOSS OF CONTROL AIR) 2 Describe, in general terms, the actions taken in S2.0P-AB.CA-0001 (Q) and the bases for the actions in accordance with the Technical Bases Document. Cognitive Level: Higher X Lower Question Source New -- Modified Bank X Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 62 Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power
• The crew is performing S2.0P-AB.GRID-0001 (Abnormal Grid) Attachment 2 (Solar Magnetic Disturbance)
• The crew is preparing to initiate a generator load reduction to less then to 942 MW (-

77.6% RTP) at 15% / MIN from the TURBINE E-H CONTROL & STATUS touch screen monitor SETTER 1UR9 INLET l'RUSURI! ACTUAL:-% SETTER:-%

REFERENCE:

In accordance S2.0P-AB.GRID-0001, which ONE of the following completes the statements below? With the turbine controls in OPERATOR MODE - AUTO, the PO will select - - - to initiate the generator load reduction. A. SMD#1 RUNBACK ONLY B. SMD#2 RUN BACK ONLY C. SMD#1 RUNBACK then GO D. SMD#2 RUNBACK then GO Answer: C Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. The TURBINE E-H CONTROL & STATUS touch screen monitor allows for manual entry of the setter and the reduction ramp rate. During manual entry the turbine won't move until the go button is depressed. Since the SMD#1 RUNBACK is a preset setter position with a preset ramp rate, the candidate could incorrectly that only the SMD#1 RUNBACK button is depressed to start the load reduction. B. Incorrect but plausible. The TURBINE E-H CONTROL & STATUS touch screen monitor allows for manual entry of the setter and the reduction ramp rate. During manual entry the turbine won't move until the go button is depressed. Additionally, since there is a SMD#2 RUNBACK with a preset setter position with a preset ramp rate, the candidate could incorrectly that only the SMD#2 RUNBACK button is depressed to start the load reduction. C. Correct. For Part 1, IAW S2.0P-AB.GRID-0001 (Abnormal Grid) Attachment 2 (Solar Magnetic Disturbance), the PO will depress SMD#1 RUNBACK and GO to initiate the generator load reduction. D. Incorrect but plausible. The candidate could incorrectly conclude that using the SMD#2 RUNBACK is required per S2.0P-AB.GRID-0001 Attachment 2. Pressing GO is required to start the turbine load reduction. Question Number: 62 Tier: 1 Group 1 KIA: APE: 077 Generator Voltage and Electric Grid Disturbances-AA 1.02 Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: Turbine / generator controls Importance Rating: 3.8 10 CFR Part 55: 41.5 and 41.10 / 45.5, 45.7, and 45.8 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must be able to use the turbine controls to lower turbine load IAW S2.0P-AB.GRID-0001 (Abnormal Grid) Attachment 2 (Solar Magnetic Disturbance) Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) <:;RO Justification: N/A Technical S2.0P-AB.GRID-0001 (Abnormal Grid) Aaachment 2

References:

Proposed references None to be provided: Learning Objective: N0S05ABGRID-12(ABNORMAL GRID) 2 Describe, in general terms, the actions taken in S2.0P-AB.GRID-0001 (Q) and the bases for the actions in accordance with the Technical Bases Document. Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 4

EXAMINATION.ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 63 Points: 1.00 Given:

• The crew has just transitioned to 1-EOP-LOCA-6 (LOCA Outside Containment)

In accordance with 1-EOP-LOCA-6, which ONE of the following completes the statements below? As part of the leak isolation strategy, the crew _(1 ) _ separate the 11 and 12 RHR discharge lines by closing 11RH19 (RHR Discharge X-CONN Valve) and 12RH19 (RHR Discharge X-CONN Valve). The crew will monitor rising _(2)_ to determine when the leak has been successfully isolated. (1} (2) A. will RCS pressure 'l. will Pressurizer level C. will NOT RCS pressure D. will NOT Pressurizer level Answer: A Page 1 of 6

EXAMINATION~ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, IAW 1-EOP-LOCA-6 Step 2, the crew will close 11RH19 and 12RH19 which will separate the 11 and 12 RHR discharge lines. This will enhance the operator's ability to diagnose the success or failure of leak isolation. For Part 2, IAW 1-EOP-LOCA-6, the crew will monitor rising RCS Pressure to determine when the leak has been successfully isolated

8. Incorrect but plausible. Part 1 is correct. For Part 2, since ECCS flow is injecting water into the core during performance of 1-EOP-LOCA-6, RCS inventory will increase once the leak has been isolated. An increase in RCS inventory can be measured by rising PZR level. Consequently, the candidate could incorrectly conclude that 1-EOP-LOCA-6 monitors rising PZR level as a determination that the leak has been successfully isolated.

C. Incorrect but plausible. For Part 1, separating the 11 and 12 RHR discharge lines is not required to isolate the leak when performing 1-EOP-LOCA-6. Consequently, the candidate could fail to recognize the advantage of separating the 11 and 12 RHR discharge lines and incorrectly conclude that closing 11RH19 and 12RH19 is not required per 1-EOP-LOCA-6. Part 2 is correct. D. Incorrect but plausible. For Part 1, separating the 11 and 12 RHR discharge lines is not required to isolate the leak when performing 1-EOP-LOCA-6. Consequently, the candidate could fail to recognize the advantage of separating the 11 and 12 RHR discharge lines and incorrectly conclude that closing 11RH19 and 12RH19 is not required per 1-EOP-LOCA-6. For Part 2, since ECCS flow is injecting water into the core during performance of 1-EOP-LOCA-6, RCS inventory will increase once the leak has been isolated. An increase in RCS inventory can be measured by rising PZR level. Consequently, the candidate could incorrectly conclude that 1-EOP-LOCA-6 monitors rising PZR level as a determination that the leak has been successfully isolated. Question Number: 63 Tier: -- 1 Group 1 KIA: EPE: LOCA Outside Containment-EA 1.2 Ability to operate and / or monitor the following as they apply to the (LOCA Outside Containment): Operating behavior characteristics of the facility Importance Rating: 3.6 10 CFR Part 55: 41 .7 / 45. 5 / 45. 6 Page 2 of 6

EXAMINATION.ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b NIA KIA Match: KIA is matched because the candidate must know what parameter to monitor (rising RCS pressure) which determines when the leak has been isolated IAW EOP-LOCA-6 (LOCA Outside Containment) SRO Justification: NIA Technical EOP-LOCA-6 (LOCA Outside Containment)

References:

Proposed references None to be provided: Learning Objective: NOS05LOCA06-03 (LOCA OUTSIDE CONTAINMENT) 1 Describe the EOP mitigation strategy during LOCA OUTSIDE CONTAINMENT Cognitive Level: Higher - - Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 64 Points: 1.00 Given:

• The crew is performing the Bleed and Feed Initiation Steps of 1-EOP-FRHS-1 (Response To Loss Of Secondary Heat Sink)
• 11 Charging Pump and 11 SI Pump are the ONLY ECCS pumps running In accordance with 1-EOP-FRHS-1, which ONE of the following completes the statements below?

The crew _(1 ) _ proceed in 1-EOP-FRHS-1 and establish the required RCS Bleed Path. When establishing a Bleed Path, the crew will open _(2)_. (1) (2) A. can NOT BOTH PORVs .J. can NOT ALL Reactor Head Vents C. can BOTH PORVs D. can ALL Reactor Head Vents Answer: C Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, The desired feed path in 1-EOP-FRHS-1 is to have BOTH SI Pumps and BOTH Charging Pumps feeding the RCS. Consequently, the candidate could incorrectly conclude that an RCS Bleed Path can not be established until BOTH SI Pumps and BOTH Charging Pumps are running. Part 2 is correct. B. Incorrect but plausible. For Part 1, The desired feed path in 1-EOP-FRHS-1 is to have BOTH SI Pumps and BOTH Charging Pumps feeding the RCS. Consequently, the candidate could incorrectly conclude that an RCS Bleed Path can not be established until BOTH SI Pumps and BOTH Charging Pumps are running. For Part 2, the Reactor Head Vents and the PORVs will both vent the RCS to the PRT. Consequently, the candidate could incorrectly conclude that 1-EOP-FRHS-1 requires ALL Reactor head Vents to be opened as part of the RCS Bleed Path. C. Correct. For Part 1, IAW 1-EOP-FRHS-1 Step 23.2, as long as 1 Charging Pump and 1 SI Pump are running, the crew will continue attempts to start the 12 Charging Pump and 12 SI Pump while establishing an RCS Bleed Path. For Part 2, IAW 1-EOP-FRHS-1 Step 24, the crew will establish an RCS Bleed Path by opening BOTH PORVs. D. Incorrect but plausible. Part 1 is correct. For Part 2, the Reactor Head Vents and the PORVs will both vent the RCS to the PRT. Consequently, the candidate could incorrectly conclude that 1-EOP-FRHS-1 requires ALL Reactor head Vents to be opened as part of the RCS Bleed Path. Question Number: 64 Tier: 1 Group 1 KIA: W/E05 Loss of Secondary Heat Sink-EK2.2 Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility Importance Rating: 3.9 10 CFR Part 55: 41.8 / 41.10, 45.3 10 CFR 55.43.b N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) l<../A Match: K/A is matched because the candidate must know the feed requirements (ECCS Pump configuration) and bleed requirements (RCS PORVs) which are heat removal systems IAW EOP-FRHS-1 (Response To Loss Of Secondary Heat Sink) SRO Justification: N/A Technical EOP-FRHS-1 (Response To Loss Of Secondary Heat Sink)

References:

Proposed references None to be provided: Learning Objective: NOS05FRHS00-02 (HEAT SINK FUNCTIONAL RESTORATION) 5 Describe the EOP mitigation strategy for the following: A. Response to Loss of Secondary Heat Sink Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 65 Points: 1.00 Given:

• The crew is preparing to perform the RCS Depressurization To Minimize Subcooling Steps of 1-EOP-LOCA-5 (Loss Of Emergency Recirculation)
• ALL RCPs are stopped
• PZR Level is 10%
• RCS Subcooling is 35 °F At time 16:15:00
• The RCS depressurization has started At time 16: 15:30 (30 seconds later)
• PZR Level is 45% and rising
• RCS Subcooling is 25 °F

., accordance with 1-EOP-LOCA-5, which ONE of the following completes the statements below?

At 16:15:00, the crew used _(1 ) _ to depressurize the RCS. At 16:15:30, there _(2)_ indications that voiding is occurring in the upper head region. (1) (2) A. AUX SPRAY are NOT B. AUX SPRAY are C. a PZR PORV are NOT D. a PZR PORV are Answer: D Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) ' ~nswer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, depressurizing the RCS using a PZR PORV will result in a loss of RCS inventory. The candidate may conclude that losing RCS inventory is not desirable and incorrectly conclude that the RCS will be depressurized using AUX SPRAY. For Part 2, the candidate may not understand the expected indications associated with voiding in the upper head region. Consequently, the candidate could incorrectly conclude that at 10:00:30, there are not indications that voiding is occurring in the upper head region. B. Incorrect but plausible. For Part 1, depressurizing the RCS using a PZR PORV will result in a loss of RCS inventory. The candidate may conclude that losing RCS inventory is not desirable and incorrectly conclude that the RCS will be depressurized using AUX SPRAY. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate may not understand the expected indications associated with voiding in the upper head region. Consequently, the candidate could incorrectly conclude that at 10:00:30, there are not indications that voiding is occurring in the upper head region. D. Correct. For Part 1, IAW 1-EOP-LOCA-5 Step 24, with normal spray not available, the crew will depressurize the RCS using a PZR PORV. For Part 2, IAW 1-EOP-LOCA-5 Step 24, voiding in the upper head region will result in rapidly rising PZR Level. Since RCS Level has risen 35% in 30 seconds, there are indications that voiding is occurring in the upper head region. Question Number: 65 Tier: -- 1 Group 1 KIA: W/E11 Loss of Emergency Coolant Recirculation-EK1 .1 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Components, capacity, and function of emergency systems Importance Rating: 3.7 10 CFR Part 55: 41.8 / 41.10, 45.3 10 CFR 55.43.b N/A Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '1<./A Match: KIA is matched because the candidate must know that the RCS will be depressurized using a PZR PORV (a safety related component) IAW 1-EOP-LOCA-5 (Loss Of Emergency Recirculation). SRO Justification: N/A Technical 1-EOP-LOCA-5 (Loss Of Emergency Recirculation)

References:

Proposed references None to be provided: Learning Objective: NOS05LOCA05-04 (LOSS OF EMERGENCY RECIRCULATION) 5 Determine the indications that are monitored to ensure proper system/component operation for each step in the EOP for LOSS OF EMERGENCY RECIRCULATION Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam -(T-75 SUBMITTAL) 66 Points: 1.00 Given:

• A Reactor Trip and Safety Injection Actuation have occurred
• The 1A 4KV VITAL BUS is de-energized due to an electrical fault on the bus
• The 12 AFW Pump will NOT start
• The crew has just transitioned to 1-EOP-LOSC-2 (Multiple Steam Generator Depressurization)
• The RCS cooldown rate is 120 °F / HR In accordance with 1-EOP-LOSC-2, which ONE of the following completes the statements below?

The crew _(1 ) _ isolate steam to the 13 AFW Pump. AFW flow will be controlled / reduced to _(2)_. (1) (2) A. will NOT maintain SG NR Levels less than 33% B. will NOT no less than 1.0E04 LB / HR to each SG C. will maintain SG NR Levels less than 33% D. will no less than 1.0E04 LB/ HR to each SG Answer: B Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, if the RCS cooldown rate was less than 100 °F / HR, the crew will control AFW flow to maintain SG NR Levels less than 33%. Consequently, the candidate could incorrectly conclude that with the given plant conditions, AFW flow will be controlled to maintain SG NR Levels less than 33%. B. Correct. For Part 1, based on the question stem, BOTH MDAFW Pumps are not available (11 AFW Pump due to 1A 4KV bus being de-energized and 12 AFW Pump will NOT start). IAW 1-EOP-LOSC-2 Step 1, since the 13 AFW Pump is the only source of AFW flow, steam must be maintained to the 13 AFW pump. For Part 2, IAW 1-EOP-LOSC-2 Step 5, with RCS cooldown rate greater than 100 °F / HR, AFW flow will be reduced to no less than 1.0E04 LB/ HR to each SG. C. Incorrect but plausible. For Part 1, if a MDAFW Pump is available, then 1-EOP-LOSC-2 requires steam to be isolated the 13 AFW Pump. Based on the plant conditions, the candidate could not recognize that the 11 AFW Pump is also not available. This would cause the candidate to incorrectly deduce that steam will be isolated to the 13 AFW Pump. For Part 2, if the RCS cooldown rate was less than 100 °F / HR, the crew will control AFW flow to maintain SG NR Levels less than 33%. Consequently, the candidate could incorrectly conclude that with the given plant conditions, AFW flow will be controlled to maintain SG NR Levels less than 33%. D. Incorrect but plausible. For Part 1, if a MDAFW Pump is available, then 1-EOP-LOSC-2 requires steam to be isolated the 13 AFW Pump. Based on the plant conditions, the candidate could not recognize that the 11 AFW Pump is also not available. This would cause the candidate to incorrectly deduce that steam will be isolated to the 13 AFW Pump. Part 2 is correct. Question Number: 66 Tier: 1 Group 1 KIA: W/E12 Uncontrolled Depressurization of all Steam Generators-EK1 .1 Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators): Components:, capacity, and function of emergency systems Importance Rating: 3.4 10 CFR Part 55: 41.8 / 41.10, 45.3 Page 2 of 5

EXAMINATIOtN ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b NIA KIA Match: KIA is matched because the candidate must know how much AFW Pump flow (a safety related component) must be reduce IAW 1-EOP-LOSC-2 (Multiple Steam Generator Depressurization). SRO Justification: NIA Technical 1-EOP-LOSC-2 (Multiple Steam Generator Depressurization)

References:

Proposed references None to be provided: Learning Objective: NOS05LOCS02-03 ( MULTIPLE SG DEPRESSURIZATION ) 5 Given EOP-LOSC-2 and a set of plant conditions: A. Determine a discrete path through the EOP Cognitive Level: Higher X Lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 67 Points: 1.00 Given:

• The Unit 2 Control Room has been evacuated in accordance with S2.0P-AB.CR-0001 (Control Room Evacuation)
• The Reactor Trip has been confirmed but 2 Control Rods did not fully insert into the core At time 08:00:00
• The RO and PO are preparing to perform an Emergency Boration in accordance with S2.0P-AB.CR-0001 Attachment 5 (Reactor Operator) and Attachment 6 (Plant Operator)

Which ONE of the following completes the statements below? In accordance with S2.0P-AB.CR-0001 Attachment 6, the crew will perform the Emergency Boration for a duration of _(1 ) _ minutes. During the Emergency Boration, the RO will throttle 2CV55 (Cent Chg Pmp Flow Cont Valve) by adjusting the 2CV55 Manual HAND/AIR Regulator Controller located at Panel _(2)_. I\JOTE:

• Panel 213-2 = Unit 2 Hot Shutdown Panel
• Panel 216-2 = Unit 2 eve Chg Pmps FL & PR Inst Panel (1) (2)

A. 70 213-2 B. 70 216-2 C. 240 213-2 D. 240 216-2 Answer: B Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that Panel 216-2 only contains instrumentation readings and the 2CV55 Manual HAND/AIR Regulator Controller is actually located the Hot Shutdown Panel. B. Correct. For Part 1, IAW S2.0P-AB.CR-0001 Attachment 6, the crew is required to perform an Emergency Boration for a duration of 35 minutes per each stuck rod. Consequently, with 2 Control Rods stuck, the crew is required to perform an Emergency Boration for a duration of 70 minutes. For Part 2, the RO throttle 2CV55 (Cent Chg Pmp Flow Cont Valve) by adjusting the 2CV55 Manual HAND/AIR Regulator Controller located at Panel 216-2. C. Incorrect but plausible. For Part 1, EOP-TRIP-2 also contains Emergency Boration guidelines. In EOP-TRIP-2, if the RWST is used as the source of the Emergency Boration, then the emergency boration duration will be 120 minutes for each stuck rod. Consequently, the candidate could incorrectly conclude that S2.0P-AB.CR-0001 Attachment 6 requires the emergency boration duration to be 120 minutes for each stuck rod (240 minutes total). For Part 2, the candidate could incorrectly conclude that Panel 216-2 only contains instrumentation readings and the 2CV55 Manual HAND/AIR Regulator Controller is actually located the Hot Shutdown Panel. D. Incorrect but plausible. For Part 1, EOP-TRIP-2 also contains Emergency Boration guidelines. In EOP-TRIP-2, if the RWST is used as the source of the Emergency Boration, then the emergency boration duration will be 120 minutes for each stuck rod. Consequently, the candidate could incorrectly conclude that S2.0P-AB.CR-0001 Attachment 6 requires the emergency boration duration to be 120 minutes for each stuck rod (240 minutes total). Part 2 is correct. Question Number: 67 Tier: -- 1 Group 2 KIA: APE: 024 Emergency Boration-G2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Importance Rating: 4.2 10 CFR Part 55: 41.10 / 43.5 / 45.13 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b N/A KIA Match: K/A is matched because the candidate must know the ROs and POs actions performed outside of the control room for an Emergency Boration IAW S2.0P-AB.CR-0001 (Control Room Evacuation). SRO Justification: N/A Technical S2.0P-AB.CR-0001 (Control Room Evacuation)

References:

Proposed references None to be provided: Learning Objective: NOS05ABCR01-05 ( CONTROL ROOM EVACUATION) 2 Describe, in general terms, the actions taken in S1/S2.0P-AB.CR-0002(Q) and the bases for the actions. Cognitive Level: Higher X Lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) 68 Points: 1.00 Given: At time 11 :00

• The crew is attempting to control PZR level in accordance with S2.0P-AB.SG-0001 (Steam Generator Tube Leak)

At time 11 :02

• PZR level can NOT be maintained
• The crew has TRIPPED the Reactor and the Reactor Trip has been confirmed In accordance with S2.0P-AB.SG-0001, which ONE of the following completes the statements below?

At 11 :00, the crew will _(1 ) _ letdown. At 11 :02, the crew _(2)_ initiate a Safety Injection prior to transitioning to 2-EOP-TRIP-1 (Reactor Trip or Safety Injection). (1) (2) A. isolate will B. isolate will NOT C. reduce will D. reduce will NOT Answer: C Page 1 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the candidate could conclude that avoiding a safety injection and doing a controlled plant shutdown is preferable. Consequently, isolating letdown will give the crew the most margin to maintain PZR level and to prevent a safety injection. Consequently, the candidate could incorrectly conclude that S2.0P-AB.SG-0001 directs the crew to isolate letdown. Part 2 is correct. B. Incorrect but plausible. For Part 1, the candidate could conclude that avoiding a safety injection and doing a controlled plant shutdown is preferable. Consequently, isolating letdown will give the crew the most margin to maintain PZR level and to prevent a safety injection. Consequently, the candidate could incorrectly conclude that S2.0P-AB.SG-0001 directs the crew to isolate letdown. For Part 2, the candidate could incorrectly conclude that a manual safety injection is not required until the crew reaches 2-EOP-TRIP-1 Step 5 (is SI actuated or required). C. Correct. For Part 1, IAW S2.0P-AB.SG-0001 Step 3.7, the crew will reduce letdown to minimum by ONLY placing 2CV3 (45 gpm ORIFICE) in service. For Part 2, IAW S2.0P-AB.SG-0001 Step 3.11, the crew will initiate a safety injection prior to going to 2-EOP-TRIP-1. D. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that a manual safety injection is not required until the crew reaches 2-EOP-TRIP-1 Step 5 (is SI actuated or required). Question Number: 68 Tier: 1 Group 2 KIA: APE: 037 Steam Generator (S/G) Tube Leak-AA1 .07 Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak: CVCS letdown flow indicator Importance Rating: 3.1 10 CFR Part 55: 41.7 / 45.5 / 45.6 10 CFR 55.43.b N/A Page 2 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRe Exam - (T-75 SUBMITTAL) '<IA Match: KIA is matched because the candidate must know how eves letdown flow will be adjusted to maintain PZR level IAW S2.0P-AB.SG-0001 (Steam Generator Tube Leak). There is no specific procedural guidance concerning the eves letdown flow indicator. SRO Justification: N/A Technical S2.0P-AB.SG-0001 (Steam Generator Tube Leak)

References:

Proposed references None to be provided: Learning Objective: NOS05ABSGTL-05 (STEAM GENERATOR TUBE LEAK) 4 Given a set of initial plant conditions: A. Determine the appropriate abnormal procedure B. Describe the plant response to actions taken in the abnormal procedure

e. Describe the final plant condition that is established by the abnormal procedure Cognitive Level:

Higher -- Lower X Question Source New X Modified Bank -- Bank -- Question History: Comments: Page 3 of 4

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 69 Points: 1.00 Given:

• Unit 1 is at 100% Reactor Power and stable
• The crew is performing S1 .OP-AB.RC-0002 (High Activity In Reactor Coolant System)
• 13 Charging Pump is in service
• 1CV4 (75 GPM ORIFICE) is in service
• Chemistry has just reported that the confirmatory sample has confirmed increasing activity in the RCS but below LCO 3.4.9 (Specific Activity) limits In accordance with S1 .OP-AB.RC-0002, which ONE of the following completes the statements below?

The crew _(1 ) _ required to place either 11 Charging Pump or 12 Charging Pump in service and secure the 13 Charging Pump. In addition to 1CV4, the crew _(2)_ required to also place 1CV3 (45 GPM ORIFICE) in ,;ervice. (1) (2) A. is is B. is is NOT C. is NOT is D. is NOT is NOT Answer: A Page 1 of 6

EXAMINATION.ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, IAW S1 .OP-AB.RC-0002 Step 3.15, the crew is required to transfer to a Centrifugal Charging Pump (CCP). Consequently, the crew is required to secure the 13 Charging Pump (PDP) and place either 11 Charging Pump or 12 Charging Pump (CCPs) is service. For Part 2, IAW S1 .OP-AB.RC-0002 Step 3.16, the crew is required to maximize letdown flow. Consequently, in addition to 1CV4, the crew is required to also place 1CV3 (45 GPM ORIFICE) in service. B. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could know that letdown should be maximized. However, the candidate could misinterpret this requirement to be having only the highest rated orifice (75 GPM) in service. C. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that either the 13 Charging pump is a CCP or that the PDP Charging pump may remain in service when performing S1 .OP-AB.RC-0002. Part 2 is correct. D. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that either the 13 Charging pump is a CCP or that the PDP Charging pump may remain in service when performing S1 .OP-AB.RC-0002. For Part 2, the candidate could know that letdown should be maximized. However, the candidate could misinterpret this requirement to be having only the highest rated orifice (75 GPM) in service. Question Number: 69 Tier: 1 Group 2 KIA: APE: 076 High Reactor Coolant Activity-AA2.02 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity: Corrective actions required for high fission product activity in RCS Importance Rating: 2.8 10 CFR Part 55: 43.5 I 45.13 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate know how letdown and charging will be maximized (corrective actions for high fission product activity in RCS) IAW S1 .OP-AB.RC-0002 (High Activity In Reactor Coolant System). Page 2 of 6

EXAMINATION,ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) SRO Justification: N/A Technical S1 .OP-AB.RC-0002 (High Activity In Reactor Coolant System)

References:

Proposed references None to be provided: Learning Objective: NOS05ABRC02-05 (HIGH ACTIVITY IN REACTOR COOLANT SYSTEM) 3 Describe, in general terms, the actions taken in S2.0P-AB.RC-0002 and the bases for the actions in accordance with the Technical Bases Document. Cognitive Level: Higher -- Lower X Question Source New -- Modified Bank X Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 70 Points: 1.00 Given:

• The crew is performing the RCS Cooldown To Cold Shutdown Steps of 2-EOP-LOCA-2 (Post LOCA Cooldown and Depressurization)
• Condenser Steam Dumps are available

                                                                 +--STEAM DJMP CONTROLS-TRAIN A          TRAIN B                                .

I ::JSS l Ill; I l !

                                                                               "l: . : :
                                                                                         *II

( AUfO I BYPASS TAVG BYPASS TAVG

                                                                                *it
                                                                                .: ~
                                                                                    . * .lI  :
                                                                                ,.; Ill,  **

1111 ,'/( ,:it, (/(

                                                                                  !:         l
                                                                                'l :      '* *
                                                                                *i Which ONE of the following completes the statements below?

In accordance with 2-EOP-LOCA-2, the crew will maintain T-COLD Cooldown Rate less than a MAXIMUM of _(1 ) _ °F / HR. Depressing BEZEL Pushbutton(s) _(2)_ is/ are the MINIMUM pushbutton manipulation(s) required to have the Condenser Steam Dumps function when TAVG is less than 543 °F. (1) (2) A. 50 AORB

8. 50 AANDB C. 100 AORB D. 100 AANDB Answer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, other procedures (S2.0P-IO.ZZ-0006 (HOT STANDBY TO COLD SHUTDOWN)) have an RCS Cooldown limit of 50 °F / HR. Consequently, the candidate could incorrectly conclude that 2-EOP-LOCA-2 also has an RCS Cooldown Rate limit of 100 °F / HR. For Part 2, if the Steam Dump Train A and Train B Blocking solenoids were in parallel, depressing BEZEL Pushbutton(s) 1 OR 2 would be the minimum pushbutton manipulation(s) to have the Condenser Steam Dumps function when TAVG is less than 543 °F. Additionally, for many safety systems, only 1 train is required to be OPERABLE for the safety system to perform its safety function. Consequently, the candidate could apply this logic to the steam dumps and incorrectly conclude that ONLY one Train of Steam Dumps need to be taken to "BYPASS TAVG" for Steam Dumps to function when TAVG is less than 543 °F. B. Incorrect but plausible. For Part 1, other procedures (S2.0P-IO.ZZ-0006 (HOT STANDBY TO COLD SHUTDOWN)) have an RCS Cooldown limit of 50 °F / HR. Consequently, the candidate could incorrectly conclude that 2-EOP-LOCA-2 also has an RCS Cooldown Rate limit of 100 °F / HR. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, if the Steam Dump Train A and Train B Blocking solenoids were in parallel, depressing BEZEL Pushbutton(s) 1 OR 2 would be the minimum pushbutton manipulation(s) to have the Condenser Steam Dumps function when TAVG is less than 543 °F. Additionally, for many safety systems, only 1 train is required to be OPERABLE for the safety system to perform its safety function. Consequently, the candidate could apply this logic to the steam dumps and incorrectly conclude that ONLY one Train of Steam Dumps need to be taken to "BYPASS TAVG" for Steam Dumps to function when TAVG is less than 543 °F. D. Correct. For Part 1, IAW 2-EOP-LOCA-2 Step 11, The crew will maintain T-COLD Cooldown Rate less than a maximum of 100 °F / HR. For Part 2, IAW 2-EOP-LOCA-2 Step 11, depressing BOTH "BYPASS TAVG" BEZEL Pushbuttons are the is the MINIMUM pushbutton manipulation(s) required to have the Condenser Steam Dumps function when TAVG is less than 543 °F. Question Number: 70 Tier: 1 Group 2 KIA: W/E03 LOCA Cooldown and Depressurization-EK2.1 Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) Importance Rating: 3.6 10 CFR Part 55: 41.7 I 45.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the 2-EOP-LOCA-2 (Post LOCA Cooldown and Depressurization) procedural guidance concerning RCS Cooldown Rate and manual bypass of Condenser Steam Dump Automatic LO TAVG block feature. SRO Justification: N/A Technical 2-EOP-LOCA-2 (Post LOCA Cooldown and Depressurization)

References:

Proposed references None to be provided: Learning Objective: NOS05LOCA02-03 ( POST-LOCA COOLDOWN AND DEPRESSURIZATION) 5 Determine the indications that are monitored to ensure proper system/component operation for each step in the EOP for POST LOCA COOLDOWN AND DEPRESSURIZATION Cognitive Level: Higher X Lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 71 Points: 1.00 Given:

• The crew is performing the SG Level Control Steps of 2-EOP-FRCC-2 (Response To Degraded Core Cooling)
• The PO observes the following on the AUX FEEDWATER STORAGE TANK BEZEL (Red Box= VALID ALARM):

LEVEL APPRCH In accordance with 2-EOP-FRCC-2, which ONE of the following completes the statements below? The crew _(1 ) _ required to shift AFW suction to an alternate source. If NO INTACT SG is available, the crew can feed a RUPTURED SG _(2)_ . (1) (2) A. is ONLY

8. is or a FAULTED SG C. is NOT ONLY D. is NOT or a FAUL TED SG Answer: D Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation D/STRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, since the AFWST Lo Level alarm is valid, the candidate could incorrectly conclude that the crew is required to shift AFW suction to an alternate source. For Part 2, 2-EOP-FRHS-1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK) specifically forbids feeding a FAUL TED SG if an INTACT or RUPTURED SG is available. Consequently, the candidate could incorrectly conclude that 2-EOP-FRCC-2 also forbids feeding a FAUL TED SG if an INTACT or RUPTURED SG is available. B. Incorrect but plausible. For Part 1, since the AFWST Lo Level alarm is valid, the candidate could incorrectly conclude that the crew is required to shift AFW suction to an alternate source. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, 2-EOP-FRHS-1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK) specifically forbids feeding a FAULTED SG if an INTACT or RUPTURED SG is available. Consequently, the candidate could incorrectly conclude that 2-EOP-FRCC-2 also forbids feeding a FAULTED SG if an INTACT or RUPTURED SG is available. D. Correct. For Part 1, IAW 2-EOP-FRCC-2 Step 12, since only the AFWST LO LEVEL is illuminated, the crew is NOT required to shift AFW suction to an alternate source (need the AFWST LO-LO Level Alarm to switch to the alternate suction source). For Part 2, IAW 2-EOP-FRCC-2 Step 12, If NO INTACT SG is available, the crew can feed a FAULTED SG or RUPTURED SG. Question Number: 71 Tier: 1 Group 2 KIA: E06 Degraded Core Cooling-EK1 .3 Knowledge of the operational implications of the following concepts as they apply to the (Degraded Core Cooling): Annunciators and conditions indicating signals, and remedial actions associated with the (Degraded Core Cooling). Importance Rating: 3.7 10 CFR Part 55: 41.8 / 41.10, 45.3 10 CFR 55.43.b N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '<IA Match: KIA is matched because the candidate must know the operational implications (the need to shift AFW flow to an alternate source) after analyzing annunciators associated with AFWST level IAW EOP-FRCC-2 (Response To Degraded Core Cooling) SRO Justification: N/A Technical EOP-FRCC-2 (Response To Degraded Core Cooling)

References:

Proposed references None to be provided: Learning Objective: NOS05LOCA02-03 ( POST-LOCA COOLDOWN AND DEPRESSURIZATION) 5 Describe the EOP mitigation strategy for the following:

a. Response to Inadequate Core Cooling.

b. Response to Degraded Core Cooling.

c. Response to Saturated Core Cooling Conditions.

Cognitive Level: Higher X Lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 72 Points: 1.00 Given:

• The crew is performing 1-EOP-FRHS-2 (Response To Steam Generator Overpressure)
• 11 SG is 1150 psig At time 12:00
• The crew is attempting to release steam from 11 SG
• 11MS18 (MS Warmup) and 11MS10 (Atmospheric Relief Valves) can NOT be opened
• RCS T-HOTs are 550 °F In accordance with 1-EOP-FRHS-2, which ONE of the following completes the statements below?

At 12:00, the crew_( 1) _ start the 13 AFW Pump in an effort to release steam from 11 SG. If the crew is unable to release steam from 11 SG, then crew will _(2)_. (1) (2) A. will cool down the RCS to< 540 °Fusing UNAFFECTED SGs

8. will establish AFW flow to 11 SG C. will NOT cool down the RCS to< 540 °Fusing UNAFFECTED SGs D. will NOT establish AFW flow to 11 SG Answer: A Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1, IAW 1-EOP-FRHS-2 Step 5, lists the 13 AFW Pump as a permitted release path for the affected SG. Since the other permitted release paths are not available and 11 SG is a source of steam for the 13 AFW, the crew will start the 13 AFW Pump in an effort to release steam from 11 SG. For Part 2, IAW 1-EOP-FRHS-2 Step 9, if the crew is unable to release steam from 11 SG, then RCS T-HOTs will be maintained less than a maximum of 540 °F by using the unaffected SGs.

8. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that establish cool AFW flow to 11 SG will help reduce 11 SG pressure.

C. Incorrect but plausible. For Part 1, the candidate may incorrectly determine that the 11 SG is not a source of steam to the 13 AFW Pump. Consequently, the candidate would then incorrectly determine that the crew will not start the 13 AFW Pump in an effort to release steam from 11 SG. Part 2 is correct. D. Incorrect but plausible. For Part 1, the candidate may incorrectly determine that the 11 SG is not a source of steam to the 13 AFW Pump. Consequently, the candidate would then incorrectly determine that the crew will not start the 13 AFW Pump in an effort to release steam from 11 SG. For Part 2, the candidate could incorrectly conclude that establish cool AFW flow to 11 SG will help reduce 11 SG pressure. Question Number: 72 Tier: -- 1 Group 2 KIA: W/E13 Steam Generator Overpressure-EK2.2 Knowledge of the interrelations between the (Steam Generator Overpressure) and the following: Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. Importance Rating: 3.0 10 CFR Part 55: 41.7 / 45.7 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the RCS heat removal (via unaffected SGs) requirements IAW 1-EOP-FRHS-2 (Response To Steam Generator Overpressure). Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) <;RO Justification: N/A Technical EOP-FRHS-2 (Response To Steam Generator Overpressure)

References:

Proposed references None to be provided: Learning Objective: NOS05FRHS00-02 (HEAT SINK FUNCTIONAL RESTORATION) 6 Describe the plant response to actions taken in the following EOP step sequence(s). A. EOP-FRHS-1: 7, 9, 13, 18.5, 22, 24, 29,35, 38, 39,40 and 41 B. EOP-FRHS-2: 3, 6, 9, and 10 C. 2-EOP-FRHS-3: 4, 8, 9, and 11 D. EOP-FRHS-5: 4, 7.1, and 7.2 .

.;ognitive Level:

Higher X Lower Question Source New X Modified Bank -- Bank -- Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) 73 Points: 1.00 Given:

• The crew has just transitioned to 1-EOP-FRCE-1 (Response To Excessive Containment Pressure) from 1-EOP-LOCA-5 (Loss Of Emergency Recirculation)
• BOTH Containment Spray Pumps have stopped in accordance with 1-EOP-LOCA-5
• Containment Pressure is 25 psig and slowly rising
• The crew is performing 1-EOP-FRCE-1 Step 3, "Has Containment Pressure Remained Less Than 15 psig" Which ONE of the following completes the statements below?

In accordance with 1-EOP-FRCE-1 Step 3, the crew _(1 ) _ start BOTH Containment Spray Pumps. With 1-EOP-LOCA-5 in effect, conserving RWST water _(2)_ a reason for how Containment Spray Pumps are operated in 1-EOP-FRCE-1 Step 3. (1) (2) A. will NOT is NOT B. will NOT is C. will is NOT D. will is Answer: B Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate may incorrectly conclude that high containment pressure (last fission product barrier) is the highest priority and conserving RWST water is not a reason for how the CS pumps are operated in EOP-FRCE-1. B. Correct. For Part 1, IAW 1-EOP-FRCE-1 Step 2, the CS pumps will be operated in as directed by 1-EOP-LOCA-5. Since LOCA-5 directed both CS Pumps to be started, the crew will NOT start both CS Pumps. For Part 2, with 1-EOP-LOCA-5 in effect, conserving RWST water is a reason for how Containment Spray Pumps are operated in 1-EOP-FRCE-1 Step 3. For Part 2, the candidate may incorrectly conclude that high containment pressure (last fission product barrier) is the highest priority and conserving RWST water is not a reason for how the CS pumps are operated in EOP-FRCE-1. C. Incorrect but plausible. For Part 1, both CS Pumps will be normally be started in EOP-FRCE-1. The candidate could not recall the provision to operate the CS pumps as directed by EOP-LOCA-5 and incorrectly conclude that bot CS Pumps will be started. For Part 2, the candidate may incorrectly conclude that high containment pressure (last fission product barrier) is the highest priority and conserving RWST water is not a reason for how the CS pumps are operated in EOP-FRCE-1. D. Incorrect but plausible. For Part 1, both CS Pumps will be normally be started in EOP-FRCE-1. The candidate could not recall the provision to operate the CS pumps as directed by EOP-LOCA-5 and incorrectly conclude that bot CS Pumps will be started. Part 2 is correct. Question Number: 73 Tier: 1 Group 2 KIA: W/E14 High Containment Pressure-EK3.2 Knowledge of the reasons for the following responses as they apply to the (High Containment Pressure): Normal, abnormal and emergency operating procedures associated with (High Containment Pressure). Importance Rating: 3.1 10 CFR Part 55: 41.5 / 41.10, 45.6, 45.13 10 CFR 55.43.b N/A Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) KIA Match: KIA is matched because the candidate must know the reason for how the Containment Spray Pumps are operated when performing EOP-FRCE (Response To Excessive Containment Pressure) with EOP-LOCA-5 (Loss Of Emergency Recirculation) also in effect. SRO Justification: N/A Technical EOP-FRCE-1 (Response To Excessive Containment Pressure)

References:

Proposed references None to be provided: Learning Objective: NOS05FRCE00-06 ( EOP-FRCE-1, 2, AND 3 CONTAINMENT ENVIRONMENT ) 2 Describe the plant response to actions taken in the following EOP step sequence(s).

2.1. 2-EOP-FRCE-1

1, 2, 3, 3.4, 4, 7, and 9

2.2. 2-EOP-FRCE-2

1

2.3. 2-EOP-FRCE-3

1 and 2 Cognitive Level: Higher -- Lower X Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) 74 Points: 1.00 Given:

• The crew is performing 2-EOP-FRCE-2 (Response To High Containment Sump Level)
• SW flow to 25 CFCU is abnormally high
• 25 CFCU has just been stopped Which ONE of the following completes the statements below?

In accordance with 2-EOP-CFST-1 (Critical Safety Function Status Trees), the crew entered 2-EOP-FRCE-2 when Containment Sump Level reached a minimum of _(1 ) _ %. In accordance with 2-EOP-FRCE-2, the crew will close 25SW58 (Inlet Water Valve) _(2)_. (1) (2) 75 and 25SW72 (Outlet Water Valve)

8. 75 ONLY C. 78 and 25SW72 (Outlet Water Valve)

D. 78 ONLY '\nswer: C Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRG Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, Containment Sump Level of 75% is the adverse level in which EOP-CFST-1 requires performance of EOP-FRCE-2. Consequently, the candidate could incorrectly conclude for the given plant conditions that 2-EOP-FRCE-2 is entered when Containment Sump Level reached a minimum of 75%. Part 2 is correct. B. Incorrect but plausible. For Part 1, Containment Sump Level of 75% is the adverse level in which EOP-CFST-1 requires performance of EOP-FRCE-2. Consequently, the candidate could incorrectly conclude for the given plant conditions that 2-EOP-FRCE-2 is entered when Containment Sump Level reached a minimum of 75%. For Part 2, when 25 CFCU was stopped, 25SW223 automatically closed. 25SWS223 is directly downstream on 25SW72. Consequently, the candidate could incorrectly conclude that 2-EOP-FRCE-2 only requires the affected CFCU's SW Inlet valve (SW58) to be closed. C. Correct. For Part 1, IAW 2-EOP-CFST-1, the crew entered 2-EOP-FRCE-2 when Containment Sump Level reached a minimum of 78 % (75% adverse). Since the question stem indicates containment pressure is normal, the crew entered 2-EOP-FRCE-2 when Containment Sump Level reached a minimum of 78 %. For Part 2, in accordance with 2-EOP-FRCE-2 Step 1, the crew will close 25SW58 (Inlet Water Valve) and 25SW72 (Outlet Water Valve). D. Incorrect but plausible. Part 1 is correct. For Part 2, when 25 CFCU was stopped, 25SW223 automatically closed. 25SWS223 is directly downstream on 25SW72. Consequently, the candidate could incorrectly conclude that 2-EOP-FRCE-2 only requires the affected CFCU's SW Inlet valve (SW58) to be closed. Question Number: 74 Tier: 1 Group 2 KIA: W/E15 Containment Flooding-EA1 .2 Ability to operate and/ or monitor the following as they apply to the (Containment Flooding): Operating behavior characteristics of the facility Importance Rating: 2.7 10 CFR Part 55: 41 .7 / 45. 5 / 45. 6 10 CFR 55.43.b N/A Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) '<IA Match: KIA is matched because the candidate must know the procedural guidance of 2-EOP-FRCE-2 (Response To High Containment Sump Level) to properly isolate SW to a leaking CFCU (which is the cause of the containment flooding). SRO Justification: N/A Technical 2-EOP-FRCE-2 (Response To High Containment Sump Level)

References:

Proposed references None to be provided: Learning Objective: NOSOSFRCE00-06 ( EOP-FRCE-1, 2, AND 3 CONTAINMENT ENVIRONMENT) 1 Describe the EOP mitigation strategy for the following: 1.1. 2-EOP-FRCE-1 1.2. 2-EOP-FRCE-2 1.3. 2-EOP-FRCE-3 Cognitive Level: Higher Lower X Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) 75 Points: 1.00 Given:

• 2R44A and 2R44B (High Range Containment Accident Monitors) are in alarm
• Containment Radiation is 7E2 R/HR
• The crew has just entered 2-EOP-FRCE-3 (Response To High Containment Radiation)

Which ONE of the following completes the statements below? In accordance with 2-EOP-CFST-1 and based on the Containment Radiation levels, Containment is considered _(1 )_. In accordance with 2-EOP-FRCE-3, the crew is required to operate the 21 THRU 25 CFCUs in _(2)_ speed. (1} (2) A. NORMAL low B. NORMAL high C. ADVERSE low D. ADVERSE high Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam - (T-75 SUBMITTAL) ' Answer Explanation DISTRACTOR ANAL YS/S: A. Correct. For Part 1, IAW 2-EOP-CFST-1, since containment radiation is less than 1 E05 R/HR, contain is considered NORMAL. For Part 2, IAW 2-EOP-FRCE-3 Step 2, the crew is required to operate the 21 THRU 25 CFCUs in low speed. B. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that running the CFCUs in high speed would better circulate the containment atmosphere which would better mitigate the high radiation condition. C. Incorrect but plausible. For Part 1, since 2R44A and 2R44B (High Range Containment Accident Monitors) are in alarm, the candidate could incorrectly conclude that containment is ADVERSE. Part 2 is correct. D. Incorrect but plausible. For Part 1, since 2R44A and 2R44B (High Range Containment Accident Monitors) are in alarm, the candidate could incorrectly conclude that containment is ADVERSE. For Part 2, the candidate could incorrectly conclude that running the CFCUs in high speed would better circulate the containment atmosphere which would better mitigate the high radiation condition.

~uestion Number:        75 Tier:   --

1 Group 2 KIA: W/E16 High Containment Radiation-EK1 .2 Knowledge of the operational implications of the following concepts as they apply to the (High Containment Radiation): Normal, abnormal and emergency operating procedures associated with (High Containment Radiation). Importance Rating: 2.7 10 CFR Part 55: 41.8 / 41.10, 45.3 10 CFR 55.43.b N/A KIA Match: KIA is matched because the candidate must know the procedural guidance of 2-EOP-FRCE-3 (Response To High Containment Radiation) concerning operation of the CFCUs. SRO Justification: N/A Page 2 of S

EXAMINATION ANSWER KEY Salem ILOT 16-01 RO NRC Exam -(T-75 SUBMITTAL) Technical 2-EOP-FRCE-3 (Response To High Containment Radiation)

References:

Proposed references None to be provided: Learning Objective: NOS05FRCE00-06 (EOP-FRCE-1, 2, AND 3 CONTAINMENT ENVIRONMENT) 1 Describe the EOP mitigation strategy for the following: 1.1. 2-EOP-FRCE-1 1.2. 2-EOP-FRCE-2 1.3. 2-EOP-FRCE-3 Cognitive Level: Higher X Lower Question Source New X Modified Bank -- Bank -- Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Points: 1.00 Given:

• A Reactor Trip and Safety Injection have occurred due to a PZR Vapor Space LOCA
• There are indications that a bubble has formed in the Reactor Vessel
• The crew has just transitioned to 1-EOP-FRCl-3 (Response To Void In Reactor Vessel) from 1-EOP-LOCA-1 (Loss Of Reactor Coolant)

Which ONE of the following completes the statements below? During a PZR Vapor Space LOCA, PZR level _(1 ) _ a valid indication of RCS inventory. In accordance with 1-EOP-FRCl-3, the crew will _(2)_ . (1) (2) A. is ensure normal Charging Flow has been established c3. is Return To 1-EOP-LOCA-1 C. is NOT ensure normal Charging Flow has been established D. is NOT Return To 1-EOP-LOCA-1 Answer: D Page 1 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the WOG Transient and Accident Analysis documentation states that during all other LOCAs, PZR level is a valid indication of RCS inventory. Consequently, the candidate could incorrectly conclude that during a PZR Vapor Space LOCA, PZR level is also a valid indication of RCS inventory. For Part 2, establishing normal flow is the first step of 1-EOP-FRCl-3 in which components are realigned (Step 3). Consequently, if the candidate fails to recognize the transition out of 1-EOP-FRCl-3 at Step 2, the candidate would incorrectly conclude that establishing normal charging is the proper action given the plant conditions. B. Incorrect but plausible. For Part 1, the WOG Transient and Accident Analysis documentation states that during all other LOCAs, PZR level is a valid indication of RCS inventory. Consequently, the candidate could incorrectly conclude that during a PZR Vapor Space LOCA, PZR level is also a valid indication of RCS inventory. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, establishing normal flow is the first step of 1-EOP-FRCl-3 in which components are realigned (Step 3). Consequently, if the candidate fails to recognize the transition out of 1-EOP-FRCl-3 at Step 2, the candidate would incorrectly conclude that establishing normal charging is the proper action given the plant conditions. D. Correct. For Part 1 and per the WOG Transient and Accident Analysis documentation, during a PZR Vapor Space LOCA, PZR level is NOT a valid indication of RCS inventory. For Part 2 and IAW 1-EOP-FRCl-3 Step 2, since BOTH SI Pumps are running (Safety Injection has occurred), then the crew will immediately return to procedure in effect (1-EOP-LOCA-1 ). Question Number: 1 Tier: -- 1 Group 1 KIA: APE : 008 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)-AA2.29 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: The effects of bubble in reactor vessel Importance Rating: 4.2 10 CFR Part 55: 43.5/45.13 Page 2 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 10 CFR 55.43.b 5 KIA Match: K/A is matched because the candidate must know the procedural guidance contained in 1-EOP-FRCl-3 (Response To Void In Reactor Vessel) when a bubble forms in the reactor vessel during a PZR Vapor Space LOCA. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate perform a procedure selection by determining if the crew should remain in 1-EOP-FRCl-3 or transition to 1-EOP-LOCA-1 during a PZR Vapor Space LOCA. Technical NOS05TAA007-00 (LOSS OF COOLANT ACCIDENTS)

References:

1-EOP-LOCA-1 1-EOP-FRCl-3 Proposed references None to be provided: Learning Objective: NOS05TAA007-00 (LOSS OF COOLANT ACCIDENTS) 3 Compare the sequences of core cooling mechanisms for various size LOCAs, including the following specific cases:

e. Pressurizer vapor-space LOCA NOS05FRCI00-04 (EOP-FRCl-1 THRU 3, COOLANT INVENTORY FUNCTIONAL RESTORATION PROCEDURES)

2. Describe the plant response to actions taken in the following EOP step sequence(s):

A. 2-EOP-FRCl-1: 3, 4, 5, 7.1, 8, 9, and 10 B. 2-EOP-FRCl-2: 4, 5, and 6 C. 2-EOP-FRCl-3: 2, 5, 7, 8, 11.4, 14, 15, 17, 19, 20, and 22 Page 3 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Cognitive Level: Higher X Lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 4 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Question 1 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b}(5) {Assessment and Selection of Procedures) Can the question be answered solely by kno....,ing "systems knowledge" (i.e., how the system *works, flowpath, logic, component location)? Yes I:I RO question I I No Can the question be answered solely by kno*.ving immediate operator actions? Yes I-_,I RO question I I No 1* Can the question be ans*itrered solely by kno....,ing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes I-,_I RO question I

                       ~

1* Can the question be answered solely by kno....,ing the purpose, overall sequence of events, or overall mitiQative strateQy of a procedure? Yes I;cj RO question I

                       ~

Does the question require one or more of the following:

• assessment of plant conditions (normal, abnoonal. or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps I Yes I_- SRO-only question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to e*vent-specific sub-procedures or emergency contingency procedures
• knowledge of administrati11e procedures that specify hierarchy, implementation, andlor coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(bX5)for SRO-only Page 5 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 2 Points: 1.00 Given: At time 07:00

• A Reactor Trip and Safety Injection have occurred due to a LBLOCA At time 07:20
• The crew has transitioned to 1-EOP-LOCA-1 (Loss Of Reactor Coolant)

In accordance with 1-EOP-LOCA-1 (Loss Of Reactor Coolant), which ONE of the following completes the statements below? The crew will start _(1 ) _ Hydrogen Recombiner(s) when Containment Hydrogen Concentration is greater than a 0.5%. _(2)_ is the EARLIEST time that the crew is required to perform 1-EOP-LOCA-4 (Transfer To Hot Leg Recirculation). (1) (2) A. ONLY one 19:00 B. ONLY one 21:00 C. BOTH 19:00 D. BOTH 21:00 Answer: B Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, EOP-LOCA-1 has a requirement to start preparations for Hot Leg Recirculation 12 hours after the SI Actuation. Consequently, the candidate could incorrectly conclude that that the crew is required to perform 1-EOP-LOCA-4 at 19:00.

8. Correct. For Part 1 and IAW 1-EOP-LOCA-1, the crew will start ONLY one Hydrogen Recombiner when Containment Hydrogen Concentration is greater than a 0.5%. For Part 2 and IAW 1-EOP-LOCA-1, the crew is required to perform 1-EOP-LOCA-4 14 hours after the SI Actuation. Since the SI Actuation occurred at 07:00, the crew is required to perform 1-EOP-LOCA-4 at 21 :00.

C. Incorrect but plausible. For Part 1, there are two hydrogen recombiners. Consequently, the candidate could incorrectly conclude that both hydrogen recombiners will be started during the performance of EOP-LOCA-1. For Part 2, EOP-LOCA-1 has a requirement to start preparations for Hot Leg Recirculation 12 hours after the SI Actuation. Consequently, the candidate could incorrectly conclude that that the crew is required to perform 1-EOP-LOCA-4 at 19:00. D. Incorrect but plausible. For Part 1, there are two hydrogen recombiners. Consequently, the candidate could incorrectly conclude that both hydrogen recombiners will be started during the performance of EOP-LOCA-1. Part 2 is correct. Question Number: 2 Tier: 1 Group 1 KIA: EPE: 011 Large Break LOCA-G2.1.2 Knowledge of operator responsibilities during all modes of plant operation. Importance Rating: 4.4 10 CFR Part 55: 41.10 / 45.13 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must know the operators responsibility to perform 1-EOP-LOCA-4 (Transfer To Hot Leg Recirculation) following a LBLOCA IAW 1-EOP-LOCA-1 (Loss Of Reactor Coolant). Page2of6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) C:,RQ Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate perform a procedure selection by determining how long following an SI Actuation is the crew required to perform 1-EOP-LOCA-4 (Transfer To Hot Leg Recirculation). Technical 1-EOP-LOCA-1

References:

Proposed references None to be provided: Learning Objective: NOS05LOCA01-05 (EOP-LOCA-01, LOSS OF REACTOR COOLANT)

5. Describe the EOP mitigation strategy for a Loss of Coolant Accident.

6. Describe the plant response to actions taken in the following EOP step sequence(s): 1, 2, 5, 6, 8, 13, 20, 22, 23, 24 Cognitive Level:

Higher X Lower Question Source New X Modified Bank Bank - - Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) ':luestion 2 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b)(5) (Assessment and Selection of Procedures) Can the question be answered solely by knowing "systems knowledge" (i.e., how the system -....,orks, flowpath. logic, component location)? Yes I~-i RO question I I No Can the question be ans*Nered solely by knowing immediate operator actions? Yes I_I RO question i I I No Can the question be answered solely by knowing entry conditions for AOPs or ptant parameters Yes l I RO question I that require direct entry into major EOPs? 1 I No Can the question be answered solely by knowing Yes the purpose, overall sequence of events, or overall miti~ative strat~y of a procedure? I. . RO question I 1 I No Does the question require one or more of the following:

• assessment of plant condtions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or'Wilh which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with :I Yes I_ SR~ly procedure steps question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, andlor coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5)for SRO-ont; Page4of6

EXAMINATION ANSWER, KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 3 Points: 1.00 Given:

• Unit 2 is at 24% Reactor Power
• The crew is implementing S2.0P-AB.CN-0001 (Main Feedwater I Condensate System Abnormality)

At time 12:00

• TAVG is 547 °F and lowering At time 12:05
• TAVG is 543 °F and lowering Which ONE of the following completes the statements below?

_(1 ) _ is the EARLIEST time that the crew is required to perform S2.0P-AB.CN-0001 (Maintaining Minimum Temperature For Criticality). In accordance with S2.0P-AB.CN-0001 Attachment 3, the crew will FIRST _(2)_ in an effort .o restore TAVG. (1) (2) A. 12:00 WITHDRAW control rods B. 12:00 REDUCE Turbine load C. 12:05 WITHDRAW control rods D. 12:05 REDUCE Turbine load Answer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that S2.0P-AB.CN-0001 Attachment 3 is required to be performed as soon as No-Load TAVG is met (547 °F). For Part 2, withdrawing control rods would help raise TAVG and prevent noncompliance with LCO 3.1.1.4. Consequently, the candidate could incorrectly conclude that S2.0P-AB.CN-0001 Attachment 3 allows the crew to withdraw control rods while TAVG is still lowering. B. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that S2.0P-AB.CN-0001 Attachment 3 is required to be performed as soon as No-Load TAVG is met (547 °F). Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, withdrawing control rods would help raise TAVG and prevent noncompliance with LCO 3.1.1.4. Consequently, the candidate could incorrectly conclude that S2.0P-AB.CN-0001 Attachment 3 allows the crew to withdraw control rods while TAVG is still lowering. D. Correct. For Part 1 and IAW S2.0P-AB.CN-0001 CAS, "IF AT ANY TIME RCS temperature is less than or equal to 543°F, THEN INITIATE Attachment 3, Maintaining Minimum Temperature For Criticality". Consequently, 12:05 is the EARLIEST time that the crew is required to perform S2.0P-AB.CN-0001 Attachment 3 (Maintaining Minimum Temperature For Criticality). For Part 2, S2.0P-AB.CN-0001 Attachment 3 has a NOTE that states, "Do NOT attempt to raise temperature by withdrawing Control Rods until directed by Step 7.0 of this attachment". Attachment 3 Step 1 has the crew reduce turbine load in an effort to restore TAVG. Question Number: 3 Tier: 1 Group 1 KIA: APE: 054 Loss of Main Feedwater (MFW)-G2.1.6 Ability to manage the control room crew during plant transients Importance Rating: 4.8 10 CFR Part 55: 41.10 / 43.5 I 45.12 I 45.13 10 CFR 55.43.b 5 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) '<IA Match: K/A is matched because the candidate must know the crew's response when RCS TAVG falls below 543 °F due to a feedwater malfunction IAW S2.0P-AB.CN-0001 (Main Feedwater / Condensate System Abnormality). SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate determine when S2.0P-AB.CN-0001 Attachment 3 (Maintaining Minimum Temperature For Criticality) is required to be performed. Technical S2.0P-AB.CN-0001

References:

Proposed references None to be provided: Learning Objective: NOS05ABCN01-06 ( MAIN FEEDWATER/CONDENSATE SYSTEM ABNORMALITY)

3. Describe, in general terms, the actions taken in AB.CN-0001 and the bases for the actions in accordance with the technical bases document.

Cognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Question 3 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b)(5) (Assessment and Selection of Procedures) Can the question be answered solely by knowing

             *systems knowfedge" (i.e., how the system 'WOrks,       Yes flowpath. logic, component location)?                        1_1 RO question   I I  No Can the question be answered solely by knowing immediate operator actions?                             Yes  I-1J RO question I I  No Can the question be answered solely by knowing entry conditions for AOPs or ptant parameters that require direct entry into major EOPs?

Yes I1J RO question I I No Can the question be answered solely by knowing the purpose, overall sequence of events, or Yes 1_ RO question overall mitiQative strateQy of a procedure? 1 I No 1 Does the question require one or more of the following:

• assessment of ptant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or 'hith which to proceed
• knowledge of when to inplement attachments and appendices, including how to coordinate these items with I Yes I_ SRO-<>nly procedure steps question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5)for SRO-only Page 4 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 4 Points: 1.00 Given:

• Unit 2 is in MODE 3 with ALL Reactor Trip Breakers CLOSED
• 21 CV Pump is running At time 18:00:00
• 2CC131 (RCP THERM BAR CC CONT VALVE) goes closed
• 21 CV Pump trips and 22 and 23 CV Pumps can NOT be started
• The crew enters S2.0P-AB.RCP-0001(Reactor Coolant Pump Abnormality)

At time 18:20:00

• While performing S2.0P-AB.RCP-0001 Attachment 2 (Stopping Reactor Coolant Pumps) the crew observes the following temperatures:

21 RCP 22 RCP 23 RCP 24 RCP RCP Seal Inlet Temperatures 222 °F 227 °F 220 °F 223 °F In accordance with S2.0P-AB.RCP-0001 Attachment 2, which ONE of the following completes the statements below? The crew _(1 ) _ REQUIRED to close 21-24CV104s (SEAL LEAKOFF) within 3-5 minutes after stopping 21-24 RCPs. At 18:20:00, the crew will cool the RCP seals by performing _(2)_. (1) (2) A. is NOT S2.0P-AB.RC-0004 (Natural Circulation) B. is NOT S2.0P-AB.RCP-0001 Attachment 4 (Re-establishing RCP Seal Cooling) C. is S2.0P-AB.RCP-0001 Attachment 4 (Re-establishing RCP Seal Cooling) D. is S2.0P-AB.RC-0004 (Natural Circulation) Answer: A Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) I Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1 and based on the question stem, RCP Seal Injection Flow AND RCP Thermal Barrier Component Cooling flows are lost concurrently. Since Seal Leakoff is< 6 gpm, then IAW S2.0P-AB.RCP-0001 Attachment 2, the crew is not REQUIRED to close 21-24CV104s (SEAL LEAKOFF) within 3-5 minutes after stopping 21-24 RCPs (Step 1.4). For Part 2, IAW S2.0P-AB.RCP-0001 Attachment 2 Step 5.0, since ALL RCP Seal Inlet Temperatures are NOT less than 225 °F, the crew will cool the RCP seals by performing S2.0P-AB.RC-0004 (Natural Circulation).

8. Incorrect but plausible. Part 1 is correct. For Part 2, if ALL RCP Seal Inlet Temperatures were less than 225 °F, the crew will cool the RCP seals by performing S2.0P-AB.RCP-0001 Attachment 4. Consequently, the candidate could incorrectly conclude that at 18:20:00, performing S2.0P-AB.RCP-0001 Attachment 4 is required.

C. Incorrect but plausible. For Part 1, Since RCP Seal Injection Flow AND RCP Thermal Barrier Component Cooling flows are lost concurrently, the candidate could incorrectly conclude that the crew is REQUIRED to close 21-24CV104s (SEAL LEAKOFF) within 3-5 minutes after stopping 21-24 RCPs For Part 2, if ALL RCP Seal Inlet Temperatures were less than 225 °F, the crew will cool the RCP seals by performing S2.0P-AB.RCP-0001 Attachment 4. Consequently, the candidate could incorrectly conclude that at 18:25:00, performing S2.0P-AB.RCP-0001 Attachment 4 is required. D. Incorrect but plausible. For Part 1, IAW S2.0P-AB.RCP-0001 CAS states that RCPs are required to be stopped 5 minutes after not restoring CCW flow to the affected RCPs. Consequently, the candidate could incorrectly conclude that given the current plant conditions, 18:05:00 is the latest time that ALL of the RCPs can be stopped without causing damage to the RCPs. Part 2 is correct. Question Number: 4 Tier: 1 Group 1 KIA: 015/017 Reactor Coolant Pump (RCP) Malfunctions-AA2.10 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):When to secure RCPs on loss of cooling or seal injection Importance Rating: 3. 7 Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 10 CFR Part 55: 43.5 / 45.13 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must know the S2.0P-AB.RCP-0001 (Reactor Coolant Pump Abnormality) guidance for stopping the RCPs when RCP Seal Injection Flow AND RCP Thermal Barrier Component Cooling flows are lost concurrently and a procedure selection on how to cool the RCP seals. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and perform an assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed. Technical S2.0P-AB.RCP-0001 (Reactor Coolant Pump Abnormality)

References:

Proposed references None to be provided: ..earning Objective: NOS05ABRCP0-06 (REACTOR COOLANT PUMP ABNORMALITY)

3. Describe, in general terms, the actions taken in S2.0P-AB.RCP-0001 and the bases for the actions in accordance with the Technical Bases Document.

Cognitive Level: Higher X Lower Question Source New -- Modified Bank X Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam - (T-75 SUBMITTAL) Question 4 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b)(5) (Assessment and Selection of Procedures) Can the question be answered soleJ'y by knowing "systems knowledge'" (i.e., how the system 11,'0rks, flowpath, logic, component location)? Yes I~1 RO question I I No

                              +

Can the question be answered solely by knowing immediate operator actions? Yes I-1I RO question I I No Can the question be answered solely by knowing entry conditions for AOPs or p4ant parameters that require direct entry into major EOPs? Yes I~ RO question I I No

                              *~

Can the question be answered solely by knmving the purpose, overall sequence of events, or overall miti~ative strategy of a procedure? Yes I:cj RO question I I No 1 Does the question require one or more of the following:

• assessment of plant concfitions (normal, abnormal. or emergency) and then selection of a procedwe or section of a procedure to mitigate or recover. or 'Mlh which to

             *    ~           of when to implement attachments and appendices. including how to coordinate these items with procedure steps I Yes I~   SRO-only question

• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal. abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5)for SRO-only Page 4 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 5 Points: 1.00 Given:

• The crew is trying to established flow from the Condensate System to feed 12 SG in accordance with 1-EOP-FRHS-1 (Response To Loss Of Secondary Heat Sink)
• ALL SGs NR levels are off scale low
• 12 SG Pressure is 550 psig and slowly lowering
• Containment Pressure is 6 psig and slowly rising
• Bleed and Feed has NOT been initiated Which ONE of the following completes the statements below?

1-EOP-FRHS-1 can be performed as a RED Path _(1 ) _ Functional Restoration Procedure(s). In accordance with 1-EOP-FRHS-1, the crew can Return To Procedure in Effect _(2)_. (1) (2) A. ONLY when 12 SG WR level starts to rise

8. ONLY ONLY after 12 SG NR is > than a MINIMUM of 15%

C. or PURPLE Path when 12 SG WR level starts to rise D. or PURPLE Path ONLY after 12 SG NR is > than a MINIMUM of 15% Answer: A Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANAL YS/S: A. Correct. For Part 1 and IAW EOP-CFST-1, 1-EOP-FRHS-1 can be performed as a RED Path ONLY Functional Restoration Procedure. For Part 2 and IAW 1-EOP-FRHS-1 Step 19, since Bleed and Feed has NOT been initiated and the condensate line has just been aligned to feed 12 SG, the crew will return to procedure when 12 SG WR level starts to rise. B. Incorrect but plausible. Part 1 is correct. For Part 2, 1-EOP-FRHS-1 Step 19 also uses ANY SG NR is> than a MINIMUM of 15% (adverse) as a criteria to return to procedure and step in effect. Consequently, the candidate could incorrectly conclude that the crew will Return To Procedure in Effect ONLY after 12 SG NR is > than a MINIMUM of 15%. C. Incorrect but plausible. For Part 1, other Functional Restoration Procedures can be performed as Red Path or Purple Path Procedures (e.g.FRSM-1, FRTS-1 and FRCE-1 ). Consequently, the candidate could incorrectly conclude that FRHS-1 can also be performed as a RED Path or Purple Path Procedures. Part 2 is correct.

0. Incorrect but plausible. For Part 1, other Functional Restoration Procedures can be performed as Red Path or Purple Path Procedures (e.g.FRSM-1, FRTS-1 and FRCE-1 ).

Consequently, the candidate could incorrectly conclude that FRHS-1 can also be performed as a RED Path or Purple Path Procedures. For Part 2, 1-EOP-FRHS-1 Step 19 also uses ANY SG NR is> than a MINIMUM of 15% (adverse) as a criteria to return to procedure and step in effect. Consequently, the candidate could incorrectly conclude that the crew will Return To Procedure in Effect ONLY after 12 SG NR is > than a MINIMUM of 15%. Question Number: 5 Tier: 1 Group 1 KIA: W/E05-EA2.1 Ability to determine and interpret the following as they apply to the (Loss of Secondary Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations Importance Rating: 4.4 10 CFR Part 55: 43.5 / 45.13 10 CFR 55.43.b 5 Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) "'<IA Match: K/A is matched because the candidate must analyze plant conditions while performing 1-EOP-FRHS-1 (Response To Loss Of Secondary Heat Sink), and select an appropriate procedure in which to proceed. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and determine what procedure(s) to perform ( when to return to procedure in effect) Technical NOS05FRHS00-02 (HEAT SINK FUNCTIONAL RESTORATION)

References:

Proposed references None to be provided: Learning Objective: NOS05TRP001-08 ( REACTOR TRIP OR SAFETY INJECTION) 12 Given 2-EOP-FRHS-1 Thru 5 and a set of plant conditions: A. Determine a discrete path through the EOP. B. Determine an appropriate transition out of the EOP Cognitive Level: Higher X Lower -- Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) Question 5 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b)(5) (Assessment and Selection of Procedures) Can the question be ans*..rvered solely by knowing "systems knowledge" (i.e., how the system works, flowpath, logic, component location)? Yes I;c! RO question I I No

                              +

Can the question be ans*..rvered solely by knowing immediate operator actions? Yes I_I RO question I

                                                                           -1 I No Can the question be answered solely by knowing entry cond.itions for AOPs or plant parameters that require direct entry into major EOPs?

Yes I-1_I RO question I I No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall miti~ative strategy of a procedure? Yes I_ RO question I 1 I No Does the question require one or more of the following:

• assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps I Yes I_- SRO-only question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5)for SRO-only Page 4 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) 6 Points: 1.00 Given:

• The crew is performing 2-EOP-LOCA-5 (Loss Of Emergency Recirculation)
• Containment Pressure is 12.0 psig and slowly rising In accordance with 2-EOP-LOCA-5, which ONE of the following completes the statements below?

The crew will add makeup to the RWST per _(1 )_. After the crew has initiated an RWST makeup, the crew will maintain TOTAL feed flow greater than 22E04 LB/HR until at least one SG NR Level is greater than _(2)_ %. NOTE:

• S2.0P-SO.CVC-0006 (Boron Concentration Control) Section 5.8, "Makeup to RWST Using eves Makeup System"
• S2.0P-SO.SF-0001 (Fill And Transfer Of Spent Fuel Pool) Section 5.6, "Transferring Spent Fuel Pool Water to RWST" (1) (2)

A. S2.0P-SO.CVC-0006 Section 5.8 15% B. S2.0P-SO.CVC-0006 Section 5.8 9% C. S2.0P-SO.SF-0001 Section 5.6 15% D. S2.0P-SO.SF-0001 Section 5.6 9% Answer: A Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1 and IAW 2-EOP-LOCA-5, the crew will add makeup to the RWST per S2.0P-SO.CVC-0006 Section 5.8. For Part 2, Since Containment Pressure is 12 psig, containment is ADVERSE. Therefore IAW 2-EOP-LOCA-5, after the crew has initiated an RWST makeup, the crew will maintain TOTAL feed flow greater than 22E04 LB/HR until at least one SG NR Level is greater than 15 %. B. Incorrect but plausible. Part 1 is correct. For Part 2, if containment was normal, IAW 2-EOP-LOCA-5, after the crew has initiated an RWST makeup, then the crew will maintain TOTAL feed flow greater than 22E04 LB/HR until at least one SG NR Level is greater than 9 %. Consequently, given the plant conditions, the candidate could incorrectly conclude that the crew will maintain TOT AL feed flow greater than 22E04 LB/HR until at least one SG NR Level is greater than 15 %. C. Incorrect but plausible. For Part 1, S2.0P-SO.SF-0001 Section 5.6 is an approved operations procedure to provide makeup to the RWST. Consequently, the candidate could incorrectly conclude that 2-EOP-LOCA-5 directs the crew to initiate an RWST makeup per S2.0P-SO.SF-0001 Section 5.6. Part 2 is correct. D. Incorrect but plausible. For Part 1, S2.0P-SO.SF-0001 Section 5.6 is an approved operations procedure to provide makeup to the RWST. Consequently, the candidate could incorrectly conclude that 2-EOP-LOCA-5 directs the crew to initiate an RWST makeup per S2.0P-SO.SF-0001 Section 5.6. For Part 2, if containment was normal, IAW 2-EOP-LOCA-5, after the crew has initiated an RWST makeup, then the crew will maintain TOTAL feed flow greater than 22E04 LB/HR until at least one SG NR Level is greater than 9 %. Consequently, given the plant conditions, the candidate could incorrectly conclude that the crew will maintain TOT AL feed flow greater than 22E04 LB/HR until at least one SG NR Level is greater than 15 %. Question Number: 6 Tier: 1 Group 1 KIA: W/E11 Loss of Emergency Coolant Recirculation-G2.1.9 Ability to direct personnel activities inside the control room Importance Rating: 4.5 10 CFR Part 55: 41.10 / 45.5 / 45.12 / 45.13 10 CFR 55.43.b 5 Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam -(T-75 SUBMITTAL) VJA Match: KIA is matched because the candidate must know how the CRS will direct the crew to perform an RWST makeup in accordance with 2-EOP-LOCA-5 (Loss Of Emergency Recirculation). SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to determine what procedure to perform to mitigate a Loss Of Emergency Recirculation event. Technical 2-EOP-LOCA-5

References:

Proposed references None to be provided: Learning Objective: NOS05LOCA05-04 ( EOP-LOCA-05, LOSS OF EMERGENCY RECIRCULATION) 1 Describe the EOP mitigation strategy during LOSS OF EMERGENCY RECIRCULATION ';ognitive Level: Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Question 6 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b)(5) (Assessment and Selection of Procedures) Can the question be answered solely by knowing Yes "systems knowtedge~ (i.e., how the system works, flowpath, logic, component location)? I_I RO question I I No Can the question be answered solely by knowing immediate operator actions? Yes IJ~I RO question I I No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes I-1I RO question I I No Can the question be answ*ered solely by knowing the purpose, overall sequence of events, or overall mitiQative strateQy of a procedure? Yes I;I RO question I I No Does the question require one or more of the following:

• assessment of plant conditions (normal, abnoonal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps I Yes I_ SRO-only question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5}for SRO-only Page 4 of 7

                 . . EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) 7                                                                             Points: 1.00 Given:

• Unit 2 is at 100% Reactor Power
• PZR pressure is 2240 psig and slowly rising
• 21 Backup Heaters are in MANUAL and ON
• 2L T-459 (Channel I PZR Level) is the controlling PZR Level channel At time 15:00:00
• 2L T-459 Fails high At time 15:09:00
• In accordance with S2.0P-AB.CVC-0001 (Loss of Charging), the crew has restored PZR level and placed the Master Flow Controller in AUTOMATIC with 2L T-461 (Channel Ill PZR Level) controlling PZR Level Nhich ONE of the following completes the statements below?

At 15:00:30, 22 Backup Heaters are _(1 )_. At 15:09:00 and in accordance with S2.0P-AB.CVC-0001, the crew _(2)_ required to perform S2.0P-SO.RPS-0003 (Placing Pressurizer Channel in Tripped Condition) for 2LT-459. (1) (2) A. ON is NOT B. ON is C. OFF is NOT D. OFF is A..nswer: B Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) ' Answer Explanation D/STRACTOR ANAL YS/S: A. Incorrect but plausible. Part 1 is correct. For Part 2, with LT-459 failed high, the bistable for Reactor Trip on PZR High Level has automatically tripped. Additionally, the majority of the actions contained in S2.0P-SO.RPS-0003 were already performed in S2.0P-AB.CVC-0001. Consequently, the candidate could incorrectly conclude that performance of S2.0P-SO.RPS-0003 is NOT required. B. Correct. For Part 1 since the controlling LT has failed high, 22 Backup heaters will automatically energize since there is a +5% PZR level deviation (LAcTUAL - LREF ). For Part 2, IAW S2.0P-AB.CVC-0001, the crew is required to perform S2.0P-SO.RPS-0003 (Placing Pressurizer Channel in Tripped Condition) for LT-459. C. Incorrect but plausible. For Part 1, PZR B/U Heaters have an automatic function to energize when PZR pressure is less than 2210 psig. Since PZR pressure is> 2210 psig when LT-459 fails high, the candidate could incorrectly conclude that the 22 Backup heaters are OFF. For Part 2, with LT-459 failed high, the bistable for Reactor Trip on PZR High Level has automatically tripped. Additionally, the majority of the actions contained in S2.0P-S0.RPS-0003 were already performed in S2.0P-AB.CVC-0001. Consequently, the candidate could incorrectly conclude that performance of S2.0P-SO.RPS-0003 is NOT required. D. Incorrect but plausible. For Part 1, PZR B/U Heaters have an automatic function to energize when PZR pressure is less than 2210 psig. Since PZR pressure is> 2210 psig when L T-459 fails high, the candidate could incorrectly conclude that the 22 Backup heaters are OFF. Part 2 is correct. Question Number: 7 Tier: 1 Group 2 KIA: 028 Pressurizer (PZR) Level Control Malfunction-AA2.12 Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Cause for PZR level deviation alarm: controller malfunction or other instrumentation malfunction Importance Rating: 3.5 10 CFR Part 55: 43.5 I 45.13 10 CFR 55.43.b 5 Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam -(T-75 SUBMITTAL) '{/A Match: KIA is matched because the candidate must know the procedural guidance of S2.0P-AB.CVC-0001 (Loss of Charging) for a failure of LT-459 (Channel I PZR Level) and select an appropriate procedure in which to proceed. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and determine if S2.0P-AB.CVC-0001 requires performance of S2.0P-SO.RPS-0003 (Placing Pressurizer Channel in Tripped Condition) for LT-459 Technical NOS05ABCVC1-04 (AB.CVC-1: LOSS OF CHARGING)

References:

Proposed references None to be provided: Learning Objective: NOS05ABCVC1-04 (AB.CVC-1: LOSS OF CHARGING) 1 Describe the impact of the following on unit operation, as applied to AB.CVC-0001:

a. Loss of all charging flow

b. PZR level channel failure

c. VCT level channel failure Cognitive Level:

Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL)

luestion 7 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b)(5)

(Assessment and Selection of Procedures) Can the question be answered solely by knowing usystems knowtedge" (i.e., how the system works, flowpath, logic, component location)? Yes I_I RO question I I No ... Can the question be answered solely by knowing immediate operator actions? Yes I_! RO question I I No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes I::.-j RO question I I No

                                ,Ir Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitiQative strateQy of a procedure?

Yes I-l RO question I I No Does the question require one or more of the following:

• assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps I Yes I_ SRO-only question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(bX5)for SRO-only Page 4 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 8 Points: 1.00 Given:

• An unplanned gaseous radioactive release from the 11 Gas Decay Tank is in progress Which ONE of the following completes the statements below?

An alarm on _(1 ) _ will alert the crew to the unplanned gaseous radioactive release. The crew will perform S1 .OP-AB.RAD-0001 (Abnormal Radiation) _(2)_ to ensure the unplanned gaseous radioactive release is stopped. NOTE:

• S1 .OP-AB.RAD-0001 Attachment 1 (Process Radiation Monitors)
• S1 .OP-AB.RAD-0001 Attachment 2 (Process Filter Radiation Monitors)

(1) (2) \. 1R12A-B (Cont or Vent Gas Effluent/Iodine) Attachment 1 B. 1R41 D (Plant Vent Noble Gas Release Rate) Attachment 1 C. 1R12A-B (Cont or Vent Gas Effluent/Iodine) Attachment 2 D. 1R41 D (Plant Vent Noble Gas Release Rate) Attachment 2 Answer: B Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, 1R12A-B is a gaseous process radiation monitor. Consequently, the candidate could incorrectly conclude that an alarm on 1R12A-B (Cont or Vent Gas Effluent/Iodine) will alert the crew to the unplanned gaseous radioactive release. Part 2 is correct. B. Correct. For Part 1, the 11 GOT discharges to the plant vent. Consequently, an alarm on R41 D will alert the crew to the unplanned gaseous radioactive release. For Part 2, the crew will perform S1 .OP-AB.RAD-0001 (Abnormal Radiation) Attachment 1 to ensure the unplanned gaseous radioactive release is stopped. C. Incorrect but plausible. For Part 1, 1R12A-B is a gaseous process radiation monitor. Consequently, the candidate could incorrectly conclude that an alarm on 1R12A-B (Cont or Vent Gas Effluent/Iodine) will alert the crew to the unplanned gaseous radioactive release. For Part 2, most gaseous systems have some type of filter arrangement. Consequently, the candidate could incorrectly conclude that 1 R41 D monitors a filter and S1 .OP-AB.RA0-0001 (Abnormal Radiation) Attachment 2 will be used to ensure the unplanned gaseous radioactive release is stopped. D. Incorrect but plausible. Part 1 is correct. For Part 2, most gaseous systems have some type of filter arrangement. Consequently, the candidate could incorrectly conclude that 1R41 D monitors a filter and S1 .OP-AB.RAD-0001 (Abnormal Radiation) Attachment 2 will be used to ensure the unplanned gaseous radioactive release is stopped. Question Number: 8 Tier: 1 Group 2 KIA: 060 Accidental Gaseous-Waste Release-AA2.04 Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste: The effects on the power plant of isolating a given radioactive-gas leak Importance Rating: 3.4 10 CFR Part 55: 43.5 / 45.13 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must know what Attachment of S1 .OP-AB.RAD-0001 (Abnormal Radiation) must be performed to isolate an unplanned gaseous radioactive release. Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) C,RO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to know when to implement an Attachment of S1 .OP-AB.RAD-0001 (Abnormal Radiation). Technical S1 .OP-AB.RAD-0001

References:

Proposed references None to be provided: Learning Objective: N0S05ABRAD1-06 (ABNORMAL RADIATION) 2 Describe, in general terms, the actions taken in S2.0P-AB.RAD-0001 (Q) and the bases for the actions in accordance with the Technical Bases Document Cognitive Level: Higher X Lower - -

,luestion Source New    X Modified Bank - -

Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) ~uestion 8 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b}(5) {Assessment and Selection of Procedures) Can the question be answered solely by knowing "systems knowledge" {i.e., how the system works, flowpath, logic, component location)? Yes I~ I RO question I

                       ~

Can the question be answered solely by knowing immediate operator actions? Yes I I RO question I

                       ~

Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes I-1I RO question I I No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitiQative strat09y of a procedure? Yes I:: RO question I I No 1 Does the question require one or more of the following:

• assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to .-nple,nent attachments and appendices. including how to coordinate these items with procedure steps I Yes I_ SRO-on(y question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b){5)for SRO-only Page 4 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 9 Points: 1.00 Given:

• A Core offload has just begun
• A loss of RHR has occurred
• The crew is performing S2.0P-AB.RHR-0001 (Loss Of RHR) and S2.0P-AB.CONT-0001 (Containment Closure)
• The Outage Equipment Hatch is currently open In accordance with S2.0P-AB.CONT-0001, which ONE of the following completes the statements below?

S2.0P-AB.CONT-0001 states that Containment Closure should be established _(1 )_. S2.0P-AB.CONT-0001 states that the crew may close the Outage Equipment Hatch using a MINIMUM of _(2)_. NOTE:

• SC.MD-FR.CAN-0001 (Outage Equipment Hatch Installation, Removal, Seal Replacement And Door Manipulation For Containment Closure)

(1) (2) A. prior to Core Boiling 10 bolts per SC.MD-FR.CAN-0001 B. prior to Core Boiling 4 corner bolts per S2.0P-AB.CONT-0001 C. within a MAXIMUM of four hours 10 bolts per SC.MD-FR.CAN-0001 D. within a MAXIMUM of four hours 4 corner bolts per S2.0P-AB.CONT-0001 Answer: B Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, if the reason for entering S2.0P-AB.CONT-0001 was due to something other than Loss of RHR, then the crew would install the Outage Equipment Hatch ( using the ALL 10 bolts) by using the guidance contained in SC.MD-FR.CAN-0001. Consequently, the candidate could incorrectly conclude that with a loss of RHR in progress, the crew will install the Outage Equipment Hatch for Containment Closure by using the guidance contained in S2.0P-AB.CONT-0001.

8. Correct. For Part 1, S2.0P-AB.CONT-0001 states that for a loss of RHR, Containment Closure should be established prior to Core Boiling. For Part 2, S2.0P-AB.CONT-0001 states that for a loss of RHR, the Outage Equipment Hatch may be closed using 4 corner bolts.

C. Incorrect but plausible. For Part 1, S2.0P-AB.CONT-0001 states that when the initiating event is other than a Fuel handling Incident or Loss Of RHR, Containment Closure should be established within four hours. Additionally, with the cavity flooded, time to boil on a Loss of RHR can be several hours. Consequently, the candidate could incorrectly conclude that with a Loss of RHR in progress and the cavity flooded, S2.0P-AB.CONT-0001 states that Containment Closure should be established within a MAXIMUM of four hours. For Part 2, if the reason for entering S2.0P-AB.CONT-0001 was due to something other than Loss of RHR, then the crew would install the Outage Equipment Hatch (using the ALL 10 bolts) by using the guidance contained in SC.MD-FR.CAN-0001. Consequently, the candidate could incorrectly conclude that with a loss of RHR in progress, the crew will install the Outage Equipment Hatch for Containment Closure by using the guidance contained in S2.0P-AB.CONT-0001. D. Incorrect but plausible. Incorrect but plausible. For Part 1, S2.0P-AB.CONT-0001 states that when the initiating event is other than a Fuel handling Incident or Loss Of RHR, Containment Closure should be established within four hours. Additionally, with the cavity flooded, time to boil on a Loss of RHR can be several hours. Consequently, the candidate could incorrectly conclude that with a Loss of RHR in progress and the cavity flooded, S2.0P-AB.CONT-0001 states that Containment Closure should be established within a MAXIMUM of four hours. Part 2 is correct. Question Number: 9 Tier: 1 Group 2 Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) '<IA: APE: 069 Loss of Containment lntegrity-G2.4.6 Knowledge of EOP mitigation strategies Importance Rating: 4. 7 10 CFR Part 55: 41.10 / 43.5 / 45.13 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must know the procedural guidance (mitigation strategy) of S2.0P-AB.CONT-0001 (Containment Closure) for reestablishing containment integrity following a Loss of RHR. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to perform a procedure selection to perform containment closure following a Loss of RHR. Technical S2.0P-AB.CONT-0001

References:

~roposed references None co be provided: Learning Objective: NOS05ABCONT-07 (CONTAINMENT CLOSURE)

2. Describe, in general terms, the actions taken in S1/S2.0P-AB.CONT-0001 (Q) and the bases for the actions in accordance with the Technical Bases Document Cognitive Level:

Higher X Lower Question Source New X Modified Bank - - Bank - - Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Question 9 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b)(5) (Assessment and Selection of Procedures) Can the question be answered solely by knowing Yes "systems knowledge" (i.e., how the system works, flowpath, logic, component location}? '-, RO question I I No Can the question be answered solely by knowing immediate operator actions? Yes I-1I RO question I I No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entrv into major EOPs? Yes I-1_I RO question I I No Can the question be answered solely by knowing Yes the purpose, overall sequence of events, or overall mitiQative strateQY of a procedure? I:-I RO question I I No 1 Does the question require one or more of the following:

• assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items *.Nith procedure steps I Yes I~ SRO-only question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5) for SRO-only Page 4 of 7

EXAMINATION ANSWER KEY ,, Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) 10 Points: 1.00 Given:

• A LOCA is in progress at Unit 2 At time 14:00
• 2R44A and 2R448 (High Range Containment Accident Monitors) are reading 2 R/HR At time 15:00
• 2R44A and 2R448 (High Range Containment Accident Monitors) are reading 100 R/HR Which ONE of the following completes the statements below?

In accordance with 2-EOP-CFST-1 (Critical Safety Function Status Trees), _(1 ) _ is the EARLIEST time that 2-EOP-FRCE-3 (Response To High Containment Radiation) entry conditions are met. In accordance with OP-AA-101-111-1003 (Use Of Procedures), the crew_(2)_ REQUIRED

• to perform 2-EOP-FRCE-3 (when entry conditions are met).

(1) (2) A. 15:00 is

8. 15:00 is NOT C. 14:00 is D. 14:00 is NOT A.nswer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, 100 R / HR is the warning setpoint for R44A/B. The candidate could incorrectly FRCE-3 entry conditions are first met when R44A/B go into warning. For Part 2, since most procedures are required to be performed when entry conditions are met, the candidate could incorrectly conclude that FRCE-3 is required to be performed when the entry conditions are met. B. Incorrect but plausible. For Part 1, 100 R / HR is the warning setpoint for R44A/B. The candidate could incorrectly FRCE-3 entry conditions are first met when R44A/B go into warning. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, since most procedures are required to be performed when entry conditions are met, the candidate could incorrectly conclude that FRCE-3 is required to be performed when the entry conditions are met. D. Correct. For Part 1 and in accordance with 2-EOP-CFST-1 (Critical Safety Function Status Trees), 2-EOP-FRCE-3 entry conditions are met when R44 radiation is~ 2 R/HR. The earliest time that this occurs is at 14:00. For Part 2, FRCE-3 is a yellow path procedure. In accordance with OP-AA-101-111-1003 (Use Of Procedures), yellow path function restoration procedures are not required to be performed. Question Number: 10 Tier: -- 1 Group 2 KIA: W/E16 High Containment Radiation-G2.4.1 Knowledge of EOP entry conditions and immediate action steps Importance Rating: 4.7 10 CFR Part 55: 41.10 / 43.5 / 45.13 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must know the entry conditions for FRCE-3 ( High Range Containment Accident Monitors). SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to perform a procedure selection of a yellow path functional restoration procedure which will mitigate the given plant conditions. Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - {T-75 SUBMITTAL) fechnical 2-EOP- CFST-1

References:

OP-AA-101-111-1003 Proposed references None to be provided: Learning Objective: NOS05PROCED-08 (USE AND CONTROL OF PROCEDURES)

5. Implement Rules Of Usage For Emergency Operating Procedures NOS05FRCE00-06 ( EOP-FRCE-1, 2 AND 3 CONTAINMENT ENVIRONMENT FUNCTIONAL RESTORATION)

1. Describe the EOP mitigation strategy for the following:

• 2-EOP-FRCE-1
• 2-EOP-FRCE-2
• 2-EOP-FRCE-3 Cognitive Level:

Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 'luestion 10 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(bJ(5) {Assessment and Selection of Procedures) Can the question be answered solely by knowing "systems knowledge" (i.e., how the system works. flowpath, logic, component location)? Yes I_I RO question I I No I Can the question be answered solely by knowing immediate operator actions? Yes IrlI RO question I I No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes I-,I RO question I I No 1* Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitiQative strat~ of a procedure? Yes I:I RO question I I No 1 Does the question require one or more of the following:

• assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with I Yes I_ SRO-only

         ~

• procedure steps knowledge of diagnostic steps and decision points in the question EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5) for SRO-only Page 4 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 11 Points: 1.00 REFERENCE PROVIDED Given:

• Unit 2 is at 100% Power and stable At time 13:00:00
• TWO accumulators are declared inoperable due to boron concentration being too low In accordance with LCO 3.5.1 (ACCUMULATORS), which ONE of the following completes the statements below?

Accumulator boron concentration is less than a MAXIMUM of _(1 )_ppm. With TWO accumulators inoperable, the Unit is required to be in HOT STANDBY within a MAXIMUM of _(2)_ hours. (1) (2) A. 2300 7 B. 2300 78 C. 2200 7 D. 2200 78 Answer: C Page 1 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, the RWST lower boron concentration limit is 2300 per LCO 3.5.5. Consequently, the candidate could incorrectly conclude that the accumulator lower boron concentration limit is also 2300 ppm. For Part 2, the candidate could fail to recognize that LCO 3.0.3 is in effect. Consequently, the Unit is required to be in HOT STANDBY within a MAXIMUM of 7 hours B. Incorrect but plausible. For Part 1, the RWST lower boron concentration limit is 2300 per LCO 3.5.5. Consequently, the candidate could incorrectly conclude that the accumulator lower boron concentration limit is also 2300 ppm. Part 2 is correct. C. Correct. For Part 1 and IAW LCO 3.5.1, with BOTH accumulators are declared inoperable due to boron concentration being too low, then Accumulator boron concentration is less than a MAXIMUM of 2200 ppm. For Part 2, since BOTH accumulators are inoperable, LCO 3.0.3 is applicable and the Unit is required to be in HOT STANDBY within a MAXIMUM of 7 hours. D. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could fail to recognize that LCO 3.0.3 is in effect. Consequently, the Unit is required to be in HOT STANDBY within a MAXIMUM of 7 hours. Question Number: 11 Tier: 2 Group 1 KIA: 006 Emergency Core Cooling System (ECCS)-AA2.1 O Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low boron concentration in SIS Importance Rating: 3.9 10 CFR Part 55: 41.5 / 45.5 10 CFR 55.43.b 2 KIA Match: KIA is matched because the candidate must use procedure (technical Specifications) to mitigate low boron concentration in the Safety Injection System (SIS). The accumulators are a source of water to the SIS. Page 2 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 5RO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to use application of LCO 3.0.3. Technical LCO 3.5.5

References:

Proposed references Redacted LCO 3.5.5 to be provided: Learning Objective: NOS05ECCS00-09 (EMERGENCY CORE COOLING SYSTEM)

10. Given a situation dealing with Emergency Core Cooling System operability, examine the situation and apply the appropriate Technical Specification action. (License Operator and STA only)

Cognitive Level: Higher X Lower ":luestion Source New X Modified Bank Bank - - Question History: Comments: Page 3 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) "luestion 11 References ES-401 5 Attachment 2 Figure 2-1 Screening for SRO-Only Linked to 10 CFR 55.43{b)(2) (Technical Specifications) Can the question be answered solely by knowing Yes I 1

                                                                             .-; RO question S:1-hour TSffRM Action?

I I No Can the question be answered solely by knowing the LCO/TRM information listed "above the line?" Yes I l RO question I I No Can the question be answered solely by knowing Yes I RO question the TS safety limits? I I No . Does the question involve one or more of the following for the TS, TRM, or ODCM:

• application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements {TS Section 1)
• appicatian of ~*LOO requiremenfS (LCO 3.0.1 lhrough Yes I.

SRO-only 3.0~7 and SR. 4.0.1 lhrough ...o.4i question

• knowledge of TS bases that is required to analyze TS-required actions and terminology I No Question might not be linked to 10 CFR 55.43(b)(2) for SRO-only Page 4 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 12 Points: 1.00 Given:

• A valid Unit 2 PRT LEVEL HI-LO Alarm exists
• PRT level is 58% and slowly rising In accordance with the PRT LEVEL HI-LO Alarm Response Procedure, which ONE of the following completes the statements below?

Leak-by of the Reactor Vessel _(1 ) _ is a possible cause of the PRT high level. The crew will lower actual PRT level by performing steps in _(2)_. NOTE:

• S2.0P-SO.PZR-0003 (Pressurizer Relief Tank Operation)
• S2.0P-AB.RC-0001 (Reactor Coolant System Leak)

(1) (2) A. Head Vents S2.0P-AB.RC-0001

8. Head Vents S2.0P-SO.PZR-0003 C. Flange Seals S2.0P-AB.RC-0001 D. Flange Seals S2.0P-SO.PZR-0003 Answer: B Page 1 of 9

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITIAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, since RCS inventory is being lost, the candidate could incorrectly conclude that S2.0P-AB.RC-0001 (Reactor Coolant System Leak) has steps to lower PRT Level and the PRT LEVEL HI-LO Alarm Response Procedure sends the crew to S2.0P-AB.RC-0001. B. Correct. For Part 1, the flow through the Reactor Head Vents is directed to the PRT. Consequently, Leak-by of the Reactor Vessel Head Vents is a possible cause of the PRT high level. For Part 2, the crew will lower PRT level by performing steps in S2.0P-SO.PZR-0003. C. Incorrect but plausible. For Part 1, leak-by of the Reactor Head Vessel Flange is directed to the RCDT. The candidate could incorrectly conclude that leak-by of the Reactor Head Vessel Flange is directed to the PRT which could cause the high PRT level. For Part 2, since RCS inventory is being lost, the candidate could incorrectly conclude that S2.0P-AB.RC-0001 (Reactor Coolant System Leak) has steps to lower PRT Level and the PRT LEVEL HI-LO Alarm Response Procedure sends the crew to S2.0P-AB.RC-0001. D. Incorrect but plausible. For Part 1, leak-by of the Reactor Head Vessel Flange is directed to the RCDT. The candidate could incorrectly conclude that leak-by of the Reactor Head Vessel Flange is directed to the PRT which could cause the high PRT level. Part 2 is correct. Question Number: 12 Tier: 2 Group 1 KIA: 007 Pressurizer Relief Tank/Quench Tank System (PRTS)-A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Recirculating quench tank Importance Rating: 2.6 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.13 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must know what malfunction will cause a high PRT level and what procedure to use to lower PRT. Page 2 of 9

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed (which procedure will be used to lower PRT level). Technical S2.0P-AR-ZZ-0012 Bezel 3-22 ARP

References:

Proposed references None to be provided: Learning Objective: NOS05PZRPRT-06 ( PRESSURIZER AND PRESSURE RELIEF TANK)

8. Identify and describe the Control Room controls, indications, and alarms associated with the Pressurizer and Pressurizer Relief Tank, including:

a. The Control Room location of Pressurizer and Pressurizer Relief Tank control bezels and indications.

b. The function of each Pressurizer and Pressurizer Relief Tank Control Room control and indication.

c. The effect each Pressurizer and Pressurizer Relief Tank control has upon Pressurizer and Pressurizer Relief Tank components and operation.

Cognitive Level: Higher X Lower Question Source New - - Modified Bank X Bank Question History: Comments: Page 3 of 9

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam-(T-75 SUBMITTAL) Question 12 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b)(5) {Assessment and Selection of Procedures) Can the question be answered solely by knowing "systems knowledge" (i.e., how the system works, Yes flowpath, logic, component location)? 1 _1 RO question

                        ~

Can the question be answered solely by knowing immediate operator actions? Yes I I RO question

                                                                                            -1 I
                        ~

Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes I-1I RO question I

                        ~

Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitiQative strateQY of a procedure? Yes I_: RO question I

                        ~

Does the question require one or more of the following:

• assessment o f ~ ~ . { ~ ~ . or emergency) atd ......then . ***** ..a~<<

                                           *. .selectimHi      * . **.* .. ***** .. sedion of a procedure to mitigate or rec:over. or with wfiicb*t, proceed

• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps I Yes I_ SRO-only question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5)for SRO-only Page 4 of 9

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 13 Points: 1.00 REFERENCE PROVIDED Given:

• Unit 2 is at 100% Reactor Power and stable At 08:00 on June 1ih
• BOTH Trains of Containment Spray are declared INOPERABLE At 10:00 on June 1ih
• ONE Train of Containment Spray is declared OPERABLE In accordance with Technical Specifications, which ONE of the following completes the statement below?

_(1 ) _ is the LATEST time/ date that Unit 2 is REQUIRED to be in HOT STANDBY.

\. 14:00 on June 1ih B. 15:00 on June 1ih C. 08:00 on June 15th D. 14:00 on June 15th Answer:        D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. 14:00 on June 1ih is the date/ time if the candidate incorrectly concludes that the required actions of LCO 3.0.3 must be performed. Additionally, the candidate must also incorrectly apply LCO 3.0.3 to require being in HOT STANDBY within 6 hours. B. Incorrect but plausible. 15:00 on June 1ih is the date/ time if the candidate incorrectly concludes that the required actions of LCO 3.0.3 must be performed (1 hour to initiate actions to place the Unit in a Mode in which the specification does not apply+ 6 more hours to be in HOT STANDBY). C. Incorrect but plausible. 08:00 on June 15th is the date / time if the candidate incorrectly interprets the required action of LCO 3.6.2.1 as only allowing 72 hours from 08:00 on June 12th to place Unit 2 in HOT STANDBY. D. Correct. At 08:00 on June 1ih, LCO 3.6.2.1 is NOT met (BOTH Trains of Containment Spray are INOPERABLE). LCO 3.6.2.1 does not have any required actions for BOTH Trains of Containment Spray being INOPERABLE. Consequently, the crew must comply with the required actions of LCO 3.0.3. Since ONE Train of Containment Spray is declared OPERABLE at 10:00 on June 1ih, the crew no longer has to complete the required actions of LCO 3.0.3. This results in the crew having to comply with the required action of LCO 3.6.2.1 ("With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours). Consequently, the crew has 72+6 hours from 08:00 on June 1ih to place Unit 2 in HOT STANDBY (14:00 on June 15th) Question Number: 13 Tier: 2 Group 1 KIA: 025 Containment Spray-G2.2.40 Ability to apply Technical Specifications for a system Importance Rating: 4.7 10 CFR Part 55: 41.10 / 43.2 / 43.5 / 45.3 10 CFR 55.43.b 2 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) KIA Match: K/A is matched because the candidate must lower apply LCO 3.0.3 and LCO 3.6.2.1 as it pertains to the Containment Spray System to determine the latest time the Unit 2 is required to be in HOT STANDBY. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate apply required actions (TS Section 3) and generic LCO requirements to determine the required time / date for placing Unit 2 in HOT STANDBY. Technical Technical Specifications

References:

Proposed references LCO 3.6.2.1 to be provided: Learning Objective: NOS05CSPRAY-06 (CONTAINMENT SPRAY SYSTEM)

10. Given a situation dealing with Containment Spray System operability, examine the situation and apply the appropriate Technical Specification action

ognitive Level

Higher X Lower Question Source New X Modified Bank - - Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) Question 13 References ES-401 5 Attachment 2 Figure 2-1 Screening for SRO-Only Linked to 10 CFR 55.43{b}(2) (Technical Specifications) Can the question be answered solely by knowing Yes I - RO question

             ~1-hour TSffRM Action?

I I No r Can the question be answered solely by knowing Yes I the LCOfTRM information listed "above the liner  ;;. ' RO question l I No Can the question be answered solely by knowing Yes I r RO question the TS safety limits?

                                                                             '                   l I No 1*

Does the question involve one or more of the following for the TS, TRM, or ODCM:

• application of .. uired actions (TS Sepion. 3) .and SRs (TS Section 4) in ~tewith ruh!s*ofapplcation requirements (TS Sedioo 1)
• application of generic LCO requifemenfs (LCO 3.0.1 through Yes I--. SRO-only 3.0.7 and SR 4.0.1 through 4~0.4) ~
• knowledge of TS bases that is required to analyze TS-required actions and terminology I No Question might not be linked to 10 CFR 55.43(b}{2) for SRO-only Page 4 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 14 Points: 1.00 REFERENCE PROVIDED Given:

• Unit 2 is at 100% Reactor Power and stable
• The crew is performing S2.0P-SO.CBV-0002 (Containment Pressure - Vacuum Relief System Operation) Section 5.3, "Performing a Containment Vacuum Relief'
• 2R12A (CNTMT NOBLE GAS) has failed In accordance with Technical Specifications, which ONE of the following completes the statement below?

LCO 3.3.3.1 (RADIATION MONITORING INSTRUMENTATION) is _ _ A. NOT met and the crew must perform Actions 24 and 26

8. NOT met and the crew must perform Action 26 ONLY C. NOT met and the crew must perform Action 24 ONLY D. met A.nswer: C Page 1 of 10

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. The candidate could correctly conclude that R12A only meets the Table 3.3-6 requirements of 2.a.1.a (Containment- Gaseous Activity- Purge & Pressure Vacuum Relief Isolation) and 2.a.1.b (Containment- Gaseous Activity- RCS Leak Detection). However, the candidate could then incorrectly conclude that R41 is not allowed to be an alternate monitor to meet Table 3.3-6 requirements of 2.a.1.a (Containment- Gaseous Activity- Purge & Pressure Vacuum Relief Isolation). Consequently, the crew would only be required to perform Action2 24 and 26. B. Incorrect but plausible. The candidate could incorrectly conclude that R12A only meets the Table 3.3-6 requirements of 2.a.1.a (Containment- Gaseous Activity- Purge & Pressure Vacuum Relief Isolation). Consequently, the crew would only be required to perform Action 26. C. Correct. When analyzing LCO 3.3.3.1 against the given plant conditions, the candidate will need to analyze Table 3.3-6. To properly analyze, Table 3.3-6, the candidate must also know information contained in the Bases of LCO 3.3.3.1. R12A is the credited monitor to meet the Table 3.3-6 requirements of 2.a.1.a (Containment- Gaseous Activity-Purge & Pressure Vacuum Relief Isolation) and 2.a.1.b (Containment- Gaseous Activity-RCS Leak Detection). Since S2.0P-SO.CBV-0002 (Containment Pressure - Vacuum Relief System Operation) Section 5.3, "Performing a Containment Vacuum Relief' is in progress, 2R41 (2R41A, Band D) can also be used to meet the requirements of Table 3.3-6 requirements of 2.a.1.a (Containment- Gaseous Activity- Purge & Pressure Vacuum Relief Isolation). Consequently, with 2R12A failed, LCO 3.3.3.1 (RADIATION MONITORING INSTRUMENTATION) is NOT met and the crew must perform Action 24 ONLY. D. Incorrect but plausible. Since there are multiple R12s (R12A, R12B, R12C) and multiple R41 s (A-D), the candidate could incorrectly conclude that LCO 3.3.3.1 is met with ONLY a failure of R12A. Question Number: 14 Tier: 2 Group 1 Page 2 of 10

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - {T-75 SUBMITTAL) KIA: 073 Process Radiation Monitoring (PRM) System Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure Importance Rating: 3.2 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.13 10 CFR 55.43. b 2 KIA Match: KIA is matched because the candidate must use a Procedure (Technical Specifications) to determine the required actions to mitigate failure of a process radiation monitor {R12A) . SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to have knowledge of TS bases that is required to analyze TS-required actions Technical Technical Specifications

References:

Proposed references LCO 3.3.3.1 to be provided: Learning Objective: NOS05CONTMT-15 (CONTAINMENT AND CONTAINMENT SUPPORT SYSTEMS)

9. Given a situation dealing with Containment and Containment Support Systems operability, examine the situation and apply the appropriate Technical Specification action Cognitive Level:

Higher X Lower Question Source New X Modified Bank Bank - - Question History: Comments: Page 3 of 10

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam- (T-75 SUBMITTAL) Question 14 References ES-401 5 Attachment 2 Figure 2-1 Screening for SRO-Only Linked to 10 CFR 55.43(b)(2) (Technical Specifications) Can the question be answered solely by knowing Yes

          ~1-hourTSITRM Action?                                ,___ _..___ RO question No Can the question be answered solely by knowing         Yes the LCOITRM information listed "above the line?"     ,___ _.__ RO question No Can the question be answered solely by knowing         Yes the TS safety limits?                                             RO question No Does the question involve one or more of the following for the TS, TRM, or ODCM:

• application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements (TS Section 1 )
• application of generic LCO requirements (LCO 3.0.'I through 1--Yes

_ __._-9'1 SRO-only 3.0.7 and SR 4.0:1 through 4.0.4) question

• ed to*analyze No Question might not be linked to

                          *10 CFR 55.43{b )(2) for SRO-only Page 4 of 10

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 15 Points: 1.00 Given:

• Unit 2 is at 100% Power and stable At time 13:00:00
• The crew enters S2.0P-AB.CA-0001 (Loss Of Control Air)

In accordance with S2.0P-AB.CA-0001, which ONE of the following completes the statements below? If Control Air pressure can NOT be restored, SG levels are expected to _(1)_ until local control of the 21-24BF19 (SG FW CONT V) can be established. If the crew MANUALLY trips the reactor because SG Levels can NOT be maintained, the crew will perform 2-EOP-TRIP-1 (Reactor Trip Or Safety Injection) _(2)_. (1) (2) A. rise and S2.0P-AB.CA-0001 concurrently

8. rise ONLY C. lower and S2.0P-AB.CA-0001 concurrently D. lower ONLY Answer: C Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) ' Answer Explanation D/STRACTOR ANAL YS/S: A. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that the BF19s (FW CONT VALVE) will fail open as Control Air pressure lowers. Consequently, the candidate would then incorrectly deduce that the SG levels are expected to rise. Part 2 is correct. B. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that the BF19s (FW CONT VALVES) will fail open as Control Air pressure lowers. Consequently, the candidate would then incorrectly deduce that the SG levels are expected to rise. For Part 2, other Abnormal Procedures (e.g. OP-AB-COND-001) require the crew to only perform EOP-TRIP-1 when reactor trip criteria have been met. Consequently, the candidate could incorrectly conclude that when reactor trip criteria have been met in S2.0P-AB.CA-001, the crew will only perform 2-EOP-TRIP-1. C. Correct. For Part 1, IAW S2.0P-AB.CA-001, the BF19s (FW CONT VALVE) will fail closed as Control Air pressure lowers. Consequently, SG levels are expected to lower. For Part 2, IAW S2.0P-AB.CA-001 (Selected CAS Items), once the reactor is tripped, the crew will perform 2-EOP-TRIP-1 and S2.0P-AB.CA-001Q concurrently. D. Incorrect but plausible. Part 1 is correct. For Part 2, other Abnormal Procedures (e.g. OP-AB-COND-001) require the crew to only perform EOP-TRIP-1 when reactor trip criteria have been met. Consequently, the candidate could incorrectly conclude that when reactor trip criteria have been met in S2.0P-AB.CA-001, the crew will only perform 2-EOP-TRIP-1. Question Number: 15 Tier: 2 Group 1 KIA: 078 Instrument Air System (IAS)-G2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. Importance Rating: 4.3 10 CFR Part 55: 41 .10 / 43.3 / 45.13 10 CFR 55.43.b 5 Page 2 of 7

EXAMINATION ANSWER KEY ' Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) '<IA Match: KIA is matched because the candidate must use S2.0P-AB.CA-0001 (Loss Of Control Air) to determine the expected plant configuration (BF19s (FW CONT VALVES) will close) of the FW system. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and determine what procedure(s) to perform (whether to remain in the Loss of Control Air AOP after the reactor is tripped) Technical S2.0P-AB.CA-0001

References:

Proposed references None to be provided: Learning Objective: NOS05ABCA01-07 (LOSS OF CONTROL AIR)

2. Describe, in general terms, the actions taken in S2.0P-AB.CA-0001 (Q) and the bases for the actions in accordance with the Technical Bases Document Cognitive Level:

Higher X Lower Question Source New -- Modified Bank X Bank Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY .. Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) 'luestion 15 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b)(5) {Assessment and Selection of Procedures) Can the question be answered solely by knowing "systems knowledge" {i.e_, how the system works, Yes flowpath. logic, component location)? 1_1 RO question j

                          ~...

Can the question be answered solely by knowing immediate operator actions? Yes I I RO question I

                          ~

Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes

                                                                              ~,

IJ RO question j

                          ~

Can the question be answered solely by knowing Yes the purpose, overall sequence of events, or overall miti~ative strat~v of a procedure? I:cl RO question j

                          ~

Does the question require one or more of the following:

• assessment d plant concitiolas ( ~ abnormal. or emergency) :and then~ ":*~or sec:fion of a procedure to mitigate or recover. or with which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps I Yes I. SRO-Only question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures

                          ~

Question might not be linked to 10 CFR 55.43(bX5) for SRO-only ES--401, Page 24 of 52 Page 4 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) 16 Points: 1.00 Given:

• A Unit 2 Turbine Run back from 100% Reactor Power has occurred
• Valid ROD INSERT LIMIT LO and ROD INSERT LIMIT LO-LO alarms are present Which ONE of the following completes the statements below?

LCO 3.1.1.1 (SHUTDOWN MARGIN-TAVG ~ 200 °F) _(1)_ met. In accordance with the ROD INSERT LIMIT LO-LO Alarm Response Procedure, the crew can perform S2.0P-SO.CVC-0008 (Rapid Boration) _(2)_ to restore Control Rods above the Rod Insertion Limit. NOTE:

• LCO NOT met= REQUIRED ACTIONS must be performed
• LCO met= NO REQUIRED ACTIONS must be performed (1) (2)

A. is NOT or S2.0P-SO.CVC-0006 (Boron Concentration Control)

8. is NOT ONLY C. is or S2.0P-SO.CVC-0006 (Boron Concentration Control)

D. is ONLY Answer: 8 Page 1 of 9

EXAMIN,ATION ANSWER KEY )) Salem ILOT 16-01 SRO NRG Exam -(T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, S2.0P-AB.LOAD-0001 (Rapid Load Reduction) allows performance of S2.0P-SO.CVC-0006 or S2.0P-SO.CVC-0008 to maintain control rods above the RIL. Consequently, the candidate could incorrectly conclude that the ROD INSERT LIMIT LO-LO Alarm Response Procedure also allows performance of S2.0P-SO.CVC-0006 or S2.0P-SO.CVC-0008 to restore control rods above the RIL.

8. Correct. For Part 1, with the ROD INSERT LIMIT LO-LO alarm present, the control rods are actually below the RIL. Consequently, SR 4.1.1.1 b (When in MODE 1 or MODE 2 with Keff greater than or equal to 1.0, in accordance with the Surveillance Frequency Control Program by verifying that control banks are within the limits in the COLR per Specification 3.1.3.5) is not met. With SR 4.1.1.1 not being met, LCO 3.1.1.1 is also NOT met. For Part 2 and in accordance with the ROD INSERT LIMIT LO-LO Alarm Response Procedure, the crew can perform S2.0P-SO.CVC-0008 (Rapid Boration) ONLY to restore Control Rods above the Rod Insertion Limit.

C. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that SR 4.1.1.1 only requires a calculation of Shutdown Margin (SOM) and LCO 3.1.1.1 is met until the SOM calculation confirms that SOM is not adequate. For Part 2, S2.0P-AB.LOAD-0001 (Rapid Load Reduction) allows performance of S2.0P-SO.CVC-0006 or S2.0P-SO.CVC-0008 to maintain control rods above the RIL. Consequently, the candidate could incorrectly conclude that the ROD INSERT LIMIT LO-LO Alarm Response Procedure also allows performance of S2.0P-SO.CVC-0006 or S2.0P-SO.CVC-0008 to restore control rods above the RIL. D. Incorrect but plausible. For Part 1, the candidate could incorrectly conclude that SR 4.1.1.1 only requires a calculation of Shutdown Margin (SOM) and LCO 3.1.1.1 is met until the SOM calculation confirms that SOM is not adequate. Part 2 is correct. Question Number: 16 Tier: 2 Group 2 KIA: 045 Main Turbine Generator (MT/G) System-A2.12 Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Control rod insertion limits exceeded (stabilize secondary) Page 2 of 9

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam -(T-75 SUBMITTAL) ,mportance Rating: 2.8 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.5 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must know how to mitigate control rods being below the RIL after a Turbine Runback has been performed. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and determine what procedure can be implemented after rods go below the RIL during a turbine runback. Technical ROD INSERT LIMIT LO-LO Alarm Response Procedure

References:

LCO 3.1.1.1 Proposed references None to be provided:

• .earning Objective: NOS05RODS00-12 (ROD CONTROL AND POSITION INDICATION SYSTEMS)

13. Given a situation dealing with Rod Control and Position Indication Systems operability, examine the situation and apply the appropriate Technical Specification action Cognitive Level:

Higher X Lower Question Source New -- Modified Bank X Bank Question History: Comments: Page 3 of 9

EXAMINATION ANSWER KEY , Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) ~uestion 16 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b}(5) (Assessment and Selection of Procedures) Can the question be answered solely by knowing

             ~systems knowledge" (i.e., how the system 'li'Orks,            Yes flowpath, logic, component location}?                              I_1 RO question  I I  No Can the question be answered solely by knowing immediate operator actions?                                    Yes I_I RO question  I
                                                                                 -1 I No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs?

Yes I~ RO question I I No Can the question be answered solely by knowing the purpose, overall sequence of events, or Yes 1_ RO question I overall miti~ative strateqy of a procedure? 1 I No Does the question require one or more of the following:

             *    -,:n:nc:=~~of erne,gency . . J' .. . . . .  . . . .. * . *. *.*

• a procedure fo*milQate.or rac:over,otliilh ~ to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with I Yes I_ SRO-only procedure steps - question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(S)for SRO-only Page 4 of 9

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam-(T-75 SUBMITTAL) 17 Points: 1.00 Given:

• The crew is performing S2.0P-AB.SF-0001 (Loss Of Spent Fuel Pool Cooling)
• Spent Fuel Pool temperature is 212 °F
• Spent Fuel Pool level is 128 feet, 0 inches In accordance with S2.0P-AB.SF-0001, which ONE of the following completes the statements below?

The crew will makeup to the Spent Fuel Pool until the Spent Fuel Pool _(1 )_. The crew can perform S2.0P-SO.SF-0006 (Spent Fuel Pool Emergency Fill) _(2)_ to raise Spent Fuel Pool Level. NOTE:

• S2.0P-SO.SF-0001 (Fill and Transfer of the Spent Fuel Pool)

(1) (2) A. HI LEVEL ALARM actuates or S2.0P-SO.SF-0001 B. HI LEVEL ALARM actuates ONLY C. LOW LEVEL ALARM clears or S2.0P-SO.SF-0001 D. LOW LEVEL ALARM clears ONLY Answer: A Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. For Part 1 and IAW S2.0P-AB.SF-0001, since SFP water is at the boiling point and SFP level at the Low Level alarm setpoint (128 feet, 0 inches), the crew is required to initiate makeup to the Spent Fuel Pool until the HI LEVEL ALARM actuates. For Part 2 and IAW S2.0P-AB.SF-0001, the crew can perform S2.0P-SO.SF-0006 (Spent Fuel Pool Emergency Fill) or S2.0P-SO.SF-0001 to raise Spent Fuel Pool Level. B. Incorrect but plausible. Part 1 is correct. For Part 2, since the SFP is boiling, the candidate could conclude that any makeup must be done as fast as possible. Consequently, the candidate could incorrectly conclude that S2.0P-AB.SF-0001 only allows a SFP makeup using S2.0P-SO.SF-0006 (Spent Fuel Pool Emergency Fill). C. Incorrect but plausible. For Part 1, since SFP Level is above the low level alarm setpoint (128 feet, 2inches), the candidate could incorrectly conclude that S2.0P-AB.SF-0001 does not require a SFP makeup. Part 2 is correct. D. Incorrect but plausible. For Part 1, since SFP Level is above the low level alarm setpoint (128 feet, 2inches), the candidate could incorrectly conclude that S2.0P-AB.SF-0001 does not require a SFP makeup. For Part 2, since the SFP is boiling, the candidate could conclude that any makeup must be done as fast as possible. Consequently, the candidate could incorrectly conclude that S2.0P-AB.SF-0001 only allows a SFP makeup using S2.0P-SO.SF-0006 (Spent Fuel Pool Emergency Fill). Question Number: 17 Tier: 2 Group 2 KIA: 033 Spent Fuel Pool Cooling-G.2.1.20 Ability to interpret and execute procedure steps Importance Rating: 4.6 10 CFR Part 55: 41.10 / 43.5 / 45.12 10 CFR 55.43.b 5 KIA Match: K/A is matched because the candidate must know how interpret and execute CAS Step 5.0 of S2.0P-AB.SF-0001 (Loss Of Spent Fuel Pool Cooling) Page 2 of 5

EXAMINA110N ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 5RO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze SFP parameters and select a procedure to mitigate during a Loss of SFP Cooling. Technical S2.0P-AB.SF-0001

References:

Proposed references None to be provided: Learning Objective: NOS05ABSFP1-06 ( LOSS OF SPENT FUEL POOL COOLING)

2. Discuss the response to loss of SFP cooling Cognitive Level:

Higher X Lower Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Question 17 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b)(5) (Assessment and Selection of Procedures) Can the question be ans*iNered solely by knowing "systems kno'ltlledge~ (i.e., how the system works, flowpath, logic, component location)? Yes I~I RO question I I No ... Can the question be ans*iNered solely by knowing immediate operator actions? Yes I I RO question

                                                                           -1 I

I No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes

                                                                           ~,

I I RO question I I No Can the question be answ-ered solely by knowing the purpose, overall sequence of events, or overall miti~ative stratew, of a procedure? Yes I:I RO question I I No Does the question require one or more of the following:

• assessment al plant~~ (~abnuqnal*. or emergency) *tm~afa ~<<section of a procedure to mifigam or recover; or with *which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps I Yes I_ SROanly question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(bX5)fOf SRO-only Page 4 of S

EXAMINATI.ON ANSWER KEY Salem ILOT 16-01 SRO NRG Exam - (T-75 SUBMITTAL) 18 Points: 1.00 Given:

• Unit 1 is at 25% Power and stable
• The crew is performing S1 .OP-A8.CA-0001 (Loss Of Control Air) due to a large non-isolable Station Air Leak Which ONE of the following completes the statements below?

The CRS will direct performance of S2.0P-A8.CA-0001 Attachment 12, "Local Control Of SG Pressure and Level", when _(1 ) _ Control Air Header(s) indicate(s) less than 80 psig. In accordance with S2.0P-A8.CA-0001 Attachment 12, individual Steam Generator pressures should be maintained within 50 psig of each other to avoid an INADVERTANT_(2)_. (1) (2) A. EITHER 1A or 18 Main Steam Isolation

8. EITHER 1A or 18 Safety Injection C. BOTH 1A and 18 Main Steam Isolation D. BOTH 1A and 18 Safety Injection Answer: D Page 1 of 5

EXAMINATI.ON ANSWER KEY Salem ILOT 16-01 SRO NRG Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, as Control Air pressure lowers below 80 psig, AOV operation will start to be compromised. Consequently, the candidate could incorrectly conclude that the CRS will direct performance of S2.0P-AB.CA-0001 Attachment 12, "Local Control Of SG Pressure and Level", when EITHER 1A or 1 B Control Air Headers indicates less than 80 psig. For Part 2, the candidate could fail to properly recall the conditions which cause an automatic safety injection and / or automatic main steam isolation. Consequently, the candidate could then incorrectly conclude that individual Steam Generator pressures should be maintained within 50 psig of each other to avoid a Main Steam isolation. B. Incorrect but plausible. For Part 1, as Control Air pressure lowers below 80 psig, AOV operation will start to be compromised. Consequently, the candidate could incorrectly conclude that the CRS will direct performance of S2.0P-AB.CA-0001 Attachment 12, "Local Control Of SG Pressure and Level", when EITHER 1A or 1 B Control Air Headers indicates less than 80 psig. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could fail to properly recall the conditions which cause an automatic safety injection and / or automatic main steam isolation. Consequently, the candidate could then incorrectly conclude that individual Steam Generator pressures should be maintained within 50 psig of each other to avoid a Main Steam isolation. D. Correct. For Part 1 and IAW S1 .OP-AB.CA-0001, the CRS will direct performance of S2.0P-AB.CA-0001 Attachment 12, "Local Control Of SG Pressure and Level", when BOTH 1A and 1B Control Air Headers indicate less than 80 psig. For Part 2 and IAW S1 .OP-AB.CA-0001 Attachment 12, individual Steam Generator pressures should be maintained within 50 psig of each other to avoid a Safety Injection on Main Steam Line Differential Pressure. Question Number: 18 Tier: 2 Group 2 KIA: 079 Station Air System (SAS)-A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Cross-connection with IAS Importance Rating: 3.2 Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam - (T-75 SUBMITTAL) 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.13 10 CFR 55.43.b 5 KIA Match: At Salem Generating Station, Station Air provides the air for the Control Air System (Instrument Air System). Consequently, a malfunction in Service Air affects Control Air. Therefore, the KIA is matched because the candidate must know when S2.0P-AB.CA-0001 Attachment 12, "Local Control Of SG Pressure and Level" is required to be performed which mitigates a malfunction between the connection between Service Air and Control Air. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and determine what when to implement an attachment of a procedure Technical S2.0P-AB.CA-0001

References:

Proposed references None

o be provided:

Learning Objective: NOS05ABCA01-07 (LOSS OF CONTROL AIR)

2. Describe, in general terms, the actions taken in S2.0P-AB.CA-0001 (Q) and the bases for the actions in accordance with the Technical Bases Document Cognitive Level:

Higher - - Lower X Question Source New X Modified Bank -- Bank Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam -(T-75 SUBMITTAL) ~uestion 18 References Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43{b)(5} {Assessment and Selection of Procedures) Can the question be answ*ered solely by knowing "systems knowledge~ (i.e., how the system works, flowpath. logic, component location)? Yes I_ I RO question I I No Can the question be answered solely by knowing immediate operator actions? Yes I_! RO question I I No

                          ,1r Can the question be answered solely by knowing entry conditions for AOPs or piant parameters that require direct entry into major EOPs?

Yes J 1 I RO question I I No Can the question be ansitwered solely by knowing the purpose, overall sequence of events, or overall miti~ative strat~y of a procedure? Yes 1 1 RO question I I No Does the question require one or more of the following:

• assessment of piant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of wlal to implement attachmenls aJli appendices. n:luding how to toorcfimde these items with I Yes I_ $RO,onfy procecbe steps question
• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures I No Question might not be linked to 10 CFR 55.43(b)(5}for SRO-only Page 4 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam - (T-75 SUBMITTAL) 19 Points: 1.00 In accordance with OP-AA-105-102 (NRC Active License Maintenance), which ONE of the following completes the statements below? The quarterly shift requirement to maintain an SRO License is a MINIMUM of _(1 ) _ hours to be completed with a combination of complete 8- and 12-hour shifts. During a credited shift to meet the quarterly shift requirement, the SRO _(2)_ permitted to perform non-position related administrative tasks outside the control room (e.g. NRG physical). (1) (2) A. 40 is

8. 40 is NOT G. 56 is D. 56 is NOT Answer: D Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, OP-AA-105-102 has a 40 hour OJT requirement to reactivate a license. Consequently, the candidate could incorrectly conclude that the quarterly shift requirement to maintain an SRO License is a MINIMUM of 40 hours to be completed with a combination of complete 8- and 12-hour shifts. For Part 2, since an activity such as receiving periodic NRC physicals is required to maintain an active license, the candidate could incorrectly conclude that an SRO is permitted to perform non-position related administrative tasks outside the control room for a credited shift. B. Incorrect but plausible. For Part 1, OP-AA-105-102 has a 40 hour OJT requirement to reactivate a license. Consequently, the candidate could incorrectly conclude that the quarterly shift requirement to maintain an SRO License is a MINIMUM of 40 hours to be completed with a combination of complete 8- and 12-hour shifts. Part 2 is correct. C. Incorrect but plausible. Part 1 is correct. For Part 2, since an activity such as receiving periodic NRC physicals is required to maintain an active license, the candidate could incorrectly conclude that an SRO is permitted to perform non-position related administrative tasks outside the control room for a credited shift. D. Correct. For Part 1, IAW OP-AA-105-102, the quarterly shift requirement to maintain an SRO License is a MINIMUM of 56 hours to be completed with a combination of complete 8- and 12-hour shifts. For Part 2, IAW OP-AA-105-102, During a credited shift to meet the quarterly shift requirement, the SRO is NOT permitted to perform non-position related administrative tasks outside the control room Question Number: 19 Tier: 3 Group KIA: G2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. Importance Rating: 3.8 10 CFR Part 55: 41.10 / 43.2 10 CFR 55.43. b 1 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) KIA Match: K/A is matched because the candidate must know the requirements to maintain an active license IAW OP-AA-105-102 (NRC Active License Maintenance). SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to know Conditions and Limitations in the Facility License. Technical OP-AA-105-102

References:

Proposed references None to be provided: Learning Objective: Cognitive Level: Higher Lower X Question Source New - - - Modified Bank X Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 20 Points: 1.00 Given:

• Unit 2 is in MODE 3
• Reactor Trip Breakers are CLOSED
• ALL control rods are fully inserted into the core
• The crew is performing S2.0P-AB.CC-0001 (Component Cooling Abnormality)

At time 10:00

• 21 RCP BRG CLG WTR FLO LO alarm actuates In accordance with S2.0P-AB.CC-0001, which ONE of the following completes the statements below?

If the 21 RCP BRG CLG WTR FLO LO alarm is still valid, _(1 ) _ is the EARLIEST time that the crew is required to perform S2.0P-AB.CC-0001 Attachment 2 (Stopping Reactor Coolant Pumps) . .Nhile performing S2.0P-AB.CC-0001 Attachment 2, the crew _(2)_ required to manually TRIP the Reactor. (1) (2) A. 10:02 is B. 10:02 is NOT C. 10:05 is D. 10:05 is NOT Answer: C Page 1 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. For Part 1, S2.0P-AB.CC-0001 (Selected CAS Items) has an action which requires RCPs to be secured within 2 minutes to prevent RCP damage (RCP Seal Injection Flow AND RCP Thermal Barrier Component Cooling flow are lost concurrently). Consequently, the candidate could incorrectly conclude that if the 21 RCP BRG CLG WTR FLO LO alarm is still active, 10:02:00 is the earliest time that the crew is required to perform S2.0P-AB.CC-0001 Attachment 2 (Stopping Reactor Coolant Pumps). B. Incorrect but plausible. For Part 1, S2.0P-AB.CC-0001 (Selected CAS Items) has an action which requires RCPs to be secured within 2 minutes to prevent RCP damage (RCP Seal Injection Flow AND RCP Thermal Barrier Component Cooling flow are lost concurrently). Consequently, the candidate could incorrectly conclude that if the 21 RCP BRG CLG WTR FLO LO alarm is still active, 10:02:00 is the earliest time that the crew is required to perform S2.0P-AB.CC-0001 Attachment 2 (Stopping Reactor Coolant Pumps). C. Correct. For Part 1, IAW S2.0P-AB.CC-0001 (Selected CAS Items), if five minutes have elapsed since RCP BRG CLR WTR FLO LO alarm actuated, the crew will perform Attachment 2, Stopping Reactor Coolant Pumps. Since the 21 RCP BRG CLG WTR FLO LO alarm actuated at 10:00:00, 10:05:00 is the earliest time that the crew is required to perform S2.0P-AB.CC-0001 Attachment 2. For Part 2, IAW S2.0P-AB.CC-0001 Attachment 2, if the Reactor Trip Breakers are CLOSED, the crew will perform a manual Reactor TRIP prior to stopping the affected RCPs. D. Incorrect but plausible. Part 1 is correct. For Part 2, since the plant is in MODE 3 with ALL of the control rods already inserted fully into the core, the candidate could incorrectly conclude that a manual reactor trip is not required which allows the crew to secure the affected RCP faster. Question Number: 20 Tier: 3 Group KIA: G2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Importance Rating: 4. 7 Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam -(T-75 SUBMITTAL) 10 CFR Part 55: 41.5 / 43.5 / 45.12 / 45.13 10 CFR 55.43.b 5 KIA Match: KIA is matched because the candidate must analyze Component Cooling System performance and determine if the RCPs must be secured and if a manual Reactor Trip is required. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and determine when to implement attachments and appendices, including how to coordinate these items with procedure steps (performing Attachment 2 of the Component Cooling Abnormality Procedure). Technical S2.0P-AB.CC-0001

References:

Proposed references None to be provided: Learning Objective: NOS05ABCC01-09 (COMPONENT COOLING ABNORMALITY)

4. Describe, in general terms, the actions taken in S2.0P-AB.CC-0001 and the bases for the actions in accordance with the Technical Bases Document Cognitive Level:

Higher X Lower - - Question Source New - - Modified Bank Bank X Question History: Comments: Page 3 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Question 20 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b)(5) (Assessment and Selection of Procedures) Can the question be answered solely by knowing usystems knowledgen {i.e., how the system works, flowpath, logic, component location)? Yes I:I RO question I

                         ~

Can the question be answered solely by knowing immediate operator actions? Yes I_I RO question I

                         ~

Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry into major EOPs? Yes I~ RO question I

                         ~

Can the question be answered solely by knowing the purpose, overall sequence of events, or overall miti~ative strat~ of a procedure? Yes I_1 RO question I

                         ~

Does the question require one or more of the following:

• assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed
• knowledge of when to implement alfachrnants a.nd appendices. ncluding hcM to eooninale hse items with procedUre steps kno..,..iedge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant I Yes I

                                                                                               =

normal, abnormal, and emergency procedures

                         ~

Question might not be linked to 10 CFR 55.43(b)(5) for SRO-only Page 4 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 21 Points: 1.00 Given:

• Unit 2 is at 100% power and stable At time 13:00:00 on November 21st
• It was discovered that SR 4.5.2.b.2 (Verify that ECCS Piping Is Full Of Water) was last performed on October 11th at 13:00:00
• SR 4.5.2.b.2 has a MONTHLY Surveillance Frequency In accordance with Technical Specifications, which ONE of the following completes the statement below?

Assuming ALL other administrative requirements have been met, at 13:00:00 is the LATEST time/ date that SR 4.5.2.b.2 can be performed without having to perform the applicable REQUIRED ACTION(s) of LCO 3.5.2 (ECCS SUBSYSTEMS -TAVG ~ 350 °F). A. November 22nd

8. December 21st C. December 22nd D. December 29th Answer: C Page 1 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. November 21st is the date if the candidate incorrectly deduces that SR 4.0.2 allows a delay time of 24 hours OR up to the limit of the specified frequency, whichever is LEAST. November 21st+ 24 hours= November 21st). B. Incorrect but plausible. December 21st is the date if the candidate incorrectly assumes a MONTH frequency= 30 days (November 21st+ 30 days= December 21st). C. Correct. SR 4.0.3 allows a delay time of 24 hours OR up to the limit of the specified frequency, whichever is greatest. Since the specified frequency is MONTHLY (every 31 days), then November 21st+ 31 days= December 22nd_ A risk assessment also needs to be performed for delay periods greater than 24 hours. Consequently, assuming ALL other administrative requirements have been met, December 22nd at 13:00:00 is the LATEST time/ date that SR 4.5.2.b.2 can be performed without having to perform the applicable REQUIRED ACTION($) of LCO 3.5.2 (ECCS SUBSYSTEMS - TAVG 2! 350 OF D. Incorrect but plausible. December 29th is the date if the candidate incorrectly deduces that SR 4.0.3 also allows a 25% extension to the specified frequency (as defined in SR 4.0.2). November 21st+ 31 days+ 7 days (25% of 31 days)= December 29th_ Question Number: 21 Tier: 3 Group KIA: G2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits Importance Rating: 4.2 10 CFR Part 55: 41 .5 / 41 .7 / 43. 2 10 CFR 55.43.b 2 KIA Match: KIA is matched because the candidate must know the bases of SR 4.0.3 to apply surveillance delay times for SR 4.5.2.b.2 before having to perform the REQUIRED ACTION($) of LCO 3.5.2. Page 2 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) ~RO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to application of application of generic LCO requirements (LCO 3.0.1 through 3.0.7 and SR 4.0.1 through 4.0.4) and knowledge of TS bases that is required to analyze TS-required actions and terminology Technical SR 4.0.2

References:

LCO 3.5.2 Proposed references None to be provided: Learning Objective: NOS05TECHSPEC-12 (TECHNICAL SPECIFICATIONS)

13. Describe the general requirements associated with Specifications 4.0.1 through 4.0.4 relating to implementation of the Technical Specification Surveillance Requirements Cognitive Level:

Higher X Lower Question Source New Modified Bank - - Bank X Question History: Comments: Page 3 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) ~uestion 21 References ES-401 5 Attachment 2 Figure 2-1 Screening for SRO-Only Linked to 10 CFR 55.43{b)(2) (Technical Specifications) Can the question be answered solely by knowing Yes I

             !::1-hour TSITRM Action?

I No

                                                                              - RO question I

Can the question be answered solely by knowing Yes I 1 the LCO/TRM information listed "above the liner - RO question I I No Can the question be answered solely by knowing Yes I the TS safety limits? -- RO question I I No .. Does the question involve one or more of the following for the TS, TRM. or ODCM:

• application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements (TS Section 1)
• application of generic LCO requirements (LCO 3.0.1 through Yes I- SRO-only question 3.0.7 and SR 4.0.1 through 4.0.4)
• knowledge of TS bases that is required to analyze TS-required actions and temunology I No Question might not be linked to 10 CFR 55.43(b){2} for SRO-only Page 4 of 7

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 22 Points: 1.00 Given:

• Unit 2 is at 95% Power At time 15:30
• The CRS has declared LCO 3.2.1 (AXIAL FLUX DIFFERENCE (AFD)) NOT met In accordance with LCO 3.2.1, which ONE of the following completes the statements below?

The crew is REQUIRED to reduce THERMAL POWER to less than _(1 )_%of RATED THERMAL POWER by 15:45 (15 minutes after LCO 3.2.1 was NOT met). The LCO 3.2.1 REQUIRED power reduction will ensure _(2)_ limit as specified in the COLR is NOT exceeded. (1) (2) A. 90 Fa(Z) (Heat Flux Hot Channel Factor)

8. 90 Fxv(Z) (Radial Peaking Factor)

C. 50 Fa(Z) (Heat Flux Hot Channel Factor) D. 50 Fxv(Z) (Radial Peaking Factor) Answer: A Page 1 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) ' Answer Explanation D/STRACTOR ANALYSIS: A. Correct. For Part 1 and IAW LCO 3.2.1, with Reactor Power at 95% power and LCO 3.2.1 NOT met at 15:30, the crew is required to reduce THERMAL POWER to less than 90% of RATED THERMAL POWER by 15:45 (within 15 minutes). For PART 2 and IAW LCO Bases, The LCO 3.2.1 REQUIRED power reduction will ensure Fa(Z) (Heat Flux Hot Channel Factor) limit as specified in the COLR is NOT exceeded. B. Incorrect but plausible. Part 1 is correct. For Part 2, the LCO Bases for the Power Distribution LCOs (LCO 3.2.x) are designed to protect three different hot channel factors (Heat Flux Hot Channel, Nuclear Enthalpy Rise Hot Channel Factor and Radial Peaking Factor). Consequently, the candidate could incorrectly conclude that LCO 3.2.1 is designed to prevent exceeding the Radial Peaking Factor. C. Incorrect but plausible. For Part 1 and IAW LCO 3.2.1, once reactor power is between 90%-50%, the crew must then reduce power to less than 50% in the next 30 minutes. Consequently, the candidate could incorrectly conclude that when LCO 3.2.1 was first not met (with RX Power at 95%), the crew is required to reduce THERMAL POWER to less than 50% of RATED THERMAL POWER by 15:45 (within 15 minutes). PART 2 is correct. D. Incorrect but plausible. For Part 1 and IAW LCO 3.2.1, once reactor power is between 90%-50%, the crew must then reduce power to less than 50% in the next 30 minutes. Consequently, the candidate could incorrectly conclude that when LCO 3.2.1 was first not met (with RX Power at 95%), the crew is required to reduce THERMAL POWER to less than 50% of RATED THERMAL POWER by 15:45 (within 15 minutes). For Part 2, the LCO Bases for the Power Distribution LCOs (LCO 3.2.x) are designed to protect three different hot channel factors (Heat Flux Hot Channel, Nuclear Enthalpy Rise Hot Channel Factor and Radial Peaking Factor). Consequently, the candidate could incorrectly conclude that LCO 3.2.1 is designed to prevent exceeding the Radial Peaking Factor. Question Number: 22 Tier: 3 Group KIA: G2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems Importance Rating: 4.5 Page 2 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam - (T-75 SUBMITTAL) 10 CFR Part 55: 41. 7 / 41.10 / 43.2 / 45.13 10 CFR 55.43.b 2 KIA Match: KIA is matched because the candidate must have bases knowledge of a 1 hour or less Technical Specification action for LCO 3.2.1 (AXIAL FLUX DIFFERENCE (AFD)) . SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to have knowledge of TS bases. Technical LCO 3.2.1

References:

Proposed references None to be provided: Learning Objective: NOS05TECHSPEC-12 ( TECHNICAL SPECIFICATIONS)

14. Describe the general component and parameter categories that are addressed by Technical Specification Sections 3/4.1 through 3/4.12. (Licensed Operator & STA only).

Cognitive Level: Higher - - Lower X Question Source New X Modified Bank Bank Question History: Comments: Page 3 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) ~uestion 22 References ES-401 5 Attachment 2 Figure 2-1 Screening for SRO-Only Linked to 10 CFR 55.43(b)(2) (Technical Specifications) Can the question be ans*wered solely by knowing Yes I 1

            !1-hour TS/TRM Action?                                            .; RO question I

I No Can the question be answered solely by knowing Yes I l the LCO/TRM information listed ~above the liner RO question l I No Can the question be answered solely by knowing Yes I the TS safety limits? _I RO question l I No Does the question involve one or more of the fol'°1A,*ing for the TS, TRM, or ODCM:

• application of required actions (TS Section 3) and SRs (TS Section 4) in accordance with rules of application requirements (TS Section 1)
• application of generic LCO requirements (LCO 3.0.1 through Yes I--,,. SRO-only question 3.0.7 and SR 4.0.1 through 4.0.4)
• knowledge of TS bases that is required to analyze Ts-required actions and terminology I No Ir Question might not be linked to 10 CFR 55.43{b}{2) for SRO-only Page 4 of 6

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 23 Points: 1.00 Given:

• Unit 2 is at 4% Reactor Power and stable At time 10:00:00
• A valid Reactor Trip signal on 21 SG LO-LO Level is generated but the Reactor does NOT trip
• The crew enters 2-EOP-TRIP-1 (Reactor Trip or Safety Injection)
• ALL attempts to trip the Reactor from the Control Room fail In accordance with 2-EOP-TRIP-1, which ONE of the following completes the statements below?

The crew will _(1 ) _ and _(2)_. NOTE:

• 2-EOP-FRSM-1 (Response to Nuclear Power Generation)

(1) (2) A. MANUALLY insert control rods continue in 2-EOP-TRIP-1 B. MANUALLY insert control rods go to 2-EOP-FRSM-1 C. allow control rods to insert AUTOMATICALLY continue in 2-EOP-TRIP-1 D. allow control rods to insert AUTOMATICALLY go to 2-EOP-FRSM-1 Answer: B Page 1 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) Answer Explanation DISTRACTOR ANALYSIS: A. Incorrect but plausible. Part 1 is correct. For Part 2, the candidate could incorrectly conclude that entry into 2-EOP-FRSM-1 is NOT required since reactor power is less than 5%.

8. Correct. For Part 1, 2-EOP-TRIP-1 and 2-EOP-TRIP-1 Basis Document require rods to be inserted. The basis document allows rods to insert in AUTOMATIC if the RCS Temperature error is such that rods step in > 48 steps/ minute. Since the plant is at 4%

(turbine is not on line), rods will not insert automatically greater than 48 steps / minute. Consequently, the rods will be inserted manually. For Part 2, IAW 2-EOP-TRIP-1, since the reactor is not tripped, the crew will go to 2-EOP-FRSM-1 Reactor Trip is confinned by .all of the follo,,*ing. at the time EOP-TRIP-1 step 2 is read by the NSS:

• Power rnnge NI indication less than 5~'o. A~TI
• Intermediate range NI indication dropping. A."\JD
• Intermediate range ">."1 startup rate indication negative C. Incorrect but plausible. For Part 1, 2-EOP-TRIP-1 Basis Document allows rods to be left in automatic if certain conditions are met. Consequently, the candidate could incorrectly conclude that allowing the rods to insert automatically is preferred. For Part 2, the candidate could incorrectly conclude that entry into 2-EOP-FRSM-1 is NOT required since reactor power is less than 5%.

D. Incorrect but plausible. For Part 1, 2-EOP-TRIP-1 Basis Document allows rods to be left in automatic if certain conditions are met. Consequently, the candidate could incorrectly conclude that allowing the rods to insert automatically is preferred. Part 2 is correct. Question Number: 23 Tier: 3 Group KIA: G2.4.21 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. Importance Rating: 4.6 Page 2 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) '0 CFR Part 55: 41 .7 / 43. 5 / 45. 12 10 CFR 55.43.b 5 KIA Match: K/A is matched because the candidate must assess plant conditions and determine if the Shutdown Margin (Subcriticality) safety function is met. SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to analyze plant parameters and perform an assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed). Technical 2-EOP-TRIP-1

References:

Proposed references to be provided: Learning Objective: Cognitive Level: Higher X Lower Question Source New - - Modified Bank - - Bank X Question History: Bank Question modified from January 2017 ILOT Exam SRO Q3 Comments: Page 3 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRG Exam - (T-75 SUBMITTAL) )uestion 23 References ES-401 8 Attachment 2 Figure 2-2 Screening for SRO-Only linked to 10 CFR 55.43(b}(5} (Assessment and Selection of Procedures) Can the question be answered solely by knowing "systems knowledge~ (i.e., how the system works, flowpath. logic, component location)? Yes

                                                                            ' -: RO question  I
                        ~

Can the question be answered solely by knowing immediate operator actions? Yes I-! RO question I

                        ~

Can lie question be an.red lfOlely bY falOWinO. entry condilons for AON c,r pbmt parameters that requn dfrKt entry iRtO majOr EOPs'? Yes 1 _: RO question I

                        ~

Can the question be answered solely by knowing the purpose. overall sequence of events, or overall mitigative strategy of a procedure? Yes

                                                                            ' -: RO question  I
                        ~

Does the question require one or more of the following:

• assessment of plant con(lilicJns (normal, abnormal, or emergency) andthen~ofa~arsection ot a procedure to milgate or recover, or With Which to proceed
• knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps

                                                                                  !Yes   I -_.SRO-only (IUeSIOn

• knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emergency contingency procedures
• knowledge of administrative procedures that specify hierarchy, implementation, ancl/or coordination of plant normal, abnormal, and emergency procedures

                        ~

Question might not be finked to 10 CFR 55.43(b)(5) for SRO-only Page 4 of 8

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRe Exam - (T-75 SUBMITTAL) 24 Points: 1.00 Given:

• The eRS is reviewing a release permit for a released from 21 eves Monitor Tank
• 2R18 (Waste Disposal Liquid Rad Monitor) has failed its source check In accordance with S2.0P-SO.WL-0001 (Release Of Radioactive Liquid Waste From 21 eves Monitor Tank), which ONE of the following completes the statement below?

The eRS _(1 ) _ approve the release permit _(2)_. A. (1) can (2) provided a second sample was drawn, analyzed, and calculations were second verified prior to the release

8. (1) can (2) provided continuous effluent sampling is conducted throughout the liquid waste discharge

e. (1) can NOT (2) until ONLY the 2R18 is repaired and returned to service D. (1) can NOT (2) until 2R18 is repaired and returned to service or until the Unit 1 R18 can be source checked and aligned to monitor the release Answer: A Page 1 of 5

It EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam - (T-75 SUBMITTAL) 1 Answer Explanation DISTRACTOR ANALYSIS: A. Correct. IAW S2.0P-SO.WL-0001, if 2R18 is inoperable, then the CRS can approve the release permit provided a second sample was drawn, analyzed, and calculations were second verified prior to the release. B. Incorrect but plausible. Part 1 is correct. For Part 2, since 2R18 provides continuous monitoring during the release, the candidate could incorrectly conclude that the effluent must be continuously sampled during the discharge. C. Incorrect but plausible. The candidate could incorrectly conclude that the release permit can not be approved until ONLY the 2R18 is repaired and returned to service. D. Incorrect but plausible. Since the 21 CVCS Monitor Tank can be discharged into the Unit 1 CW system, the candidate could incorrectly conclude that the Unit 1 R18 can be aligned to monitor the 21 eves Monitor Tank. Consequently, the candidate could then incorrectly determine that the release permit can not be approved until 2R18 is repaired and returned to service or until the Unit 1 R18 can be source checked and aligned to monitor the release.

'luestion Number:        24 Tier:      3     Group KIA:    G2.3.6 Ability to approve release permits Importance Rating:         3.8 10 CFR Part 55:            41.13 / 43.4 / 45.10 10 CFR 55.43.b             4 KIA Match:                 KIA is matched because the candidate must the requirements for approving a Liquid Waste Removal permit with 2R18 inoperable IAW S2.0P-SO.WL-0001 (Release Of Radioactive Liquid Waste From 21 eves Monitor Tank).

SRO Justification: The question meets the SRO requirements as described in NUREG 1021 ES-401 Attachment 2. The question is SRO Only because it requires the candidate to have knowledge of Radiation Hazards that may arise during Normal and Abnormal Situations, including Maintenance Activities and Various Contamination Conditions. Page 2 of 5

EXAMINATION ANSWER KEY Salem ILOT 16-01 SRO NRC Exam -(T-75 SUBMITTAL) Technical S2.0P-S0.WL-0001

References:

Proposed references None to be provided: Learning Objective: NOS05CAVENT-11 (CONTROL AREA VENTILATION SYSTEM)

10. Given a situation dealing with Control Area Ventilation System operability, examine the situation and apply the appropriate Technical Specification action.

Cognitive Level: Higher - - Lower X Question Source New - - Modified Bank - - Bank X Question History: Comments: Page 3 of S

SRO Question #25 not for public release.}}