ML090230038: Difference between revisions

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| number = ML090230038
| number = ML090230038
| issue date = 12/10/2008
| issue date = 12/10/2008
| title = 2008-301 Combined Final Ro/Sro Written Examination with Ka'S Answers and References
| title = 301 Combined Final Ro/Sro Written Examination with Ka'S Answers and References
| author name =  
| author name =  
| author affiliation = - No Known Affiliation
| author affiliation = - No Known Affiliation
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* 1FO-1, B/6 (PZR Hi Level RX Trip) is LIT and RED
* 1FO-1, B/6 (PZR Hi Level RX Trip) is LIT and RED
* ORPI indicates control bank position at 215 steps on Bank 0
* ORPI indicates control bank position at 215 steps on Bank 0
* Both RX TRIP BKR 1A and 1 B red lights are LIT. Which one of the following describes:  
* Both RX TRIP BKR 1A and 1 B red lights are LIT. Which one of the following describes:
: 1. The current condition of the plant and 2. The correct operator action to take for the above evolution?
: 1. The current condition of the plant and 2. The correct operator action to take for the above evolution?
A. 1. Anticipated Transient Without Scram (ATWS) 2. Manually trip the reactor B. 1. Anticipated Transient Without Scram (ATWS) 2. Perform a shutdown per OP/1/A/61 001003 (Controlling Procedure for Unit Operation)
A. 1. Anticipated Transient Without Scram (ATWS) 2. Manually trip the reactor B. 1. Anticipated Transient Without Scram (ATWS) 2. Perform a shutdown per OP/1/A/61 001003 (Controlling Procedure for Unit Operation)
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* The crew entered AP/1/A/5500/019 (Loss of Residual Heat Removal System) but actions to restore cooling have failed.
* The crew entered AP/1/A/5500/019 (Loss of Residual Heat Removal System) but actions to restore cooling have failed.
* The OSM has determined an immediate need to take an action per 10CFR50.54(X).
* The OSM has determined an immediate need to take an action per 10CFR50.54(X).
Per the requirements of OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines):  
Per the requirements of OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines):
: 1. Is notification to the NRC Operations Center required prior to taking the action? 2. How many additional SROs (if any) are required to agree with the OSM prior to the action being taken? A. 1. Yes 2. None B. 1. Yes 2. One additional SRO C. 1. No 2. None D. 1. No 2. One additional SRO Tuesday, November 18, 2008 Page 9 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination General Discussion  
: 1. Is notification to the NRC Operations Center required prior to taking the action? 2. How many additional SROs (if any) are required to agree with the OSM prior to the action being taken? A. 1. Yes 2. None B. 1. Yes 2. One additional SRO C. 1. No 2. None D. 1. No 2. One additional SRO Tuesday, November 18, 2008 Page 9 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination General Discussion  
--QUESTION 5 t--50.72 "The licensee shall activate the Emergency Response Data System (ERDS)4 as soon as possible but not later than one hour after declaring an Emergency Class of alert, site area emergency, or general emergency".
--QUESTION 5 t--50.72 "The licensee shall activate the Emergency Response Data System (ERDS)4 as soon as possible but not later than one hour after declaring an Emergency Class of alert, site area emergency, or general emergency".
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* One single steam generator tube fully shears on each unit
* One single steam generator tube fully shears on each unit
* The crews are responding per EP/1 (2)IAl5000/E-3 (Steam Generator Tube Rupture).
* The crews are responding per EP/1 (2)IAl5000/E-3 (Steam Generator Tube Rupture).
preparing to perform the initial reactor coolant system cooldown to the required core exit thermocouple temperature using steam dumps. Based on the differences between Unit 1 and Unit 2 steam generator design: 1. Which unit would have a lower primary system equilibrium pressure?  
preparing to perform the initial reactor coolant system cooldown to the required core exit thermocouple temperature using steam dumps. Based on the differences between Unit 1 and Unit 2 steam generator design: 1. Which unit would have a lower primary system equilibrium pressure?
: 2. Which unit will have a faster cooldown rate? (Assume identical cores and steam dump performance.)
: 2. Which unit will have a faster cooldown rate? (Assume identical cores and steam dump performance.)
A. Unit 1 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate. B. Unit 1 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate. c. Unit 2 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate. D. Unit 2 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate. Tuesday, November 18, 2008 Page 17 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 9 General Discussion Unit 1 has smaller tubes and larger surface area, therefore the leakage would be less on Unit 1 causing Unit 2 to have a larger pressure drop to equilibrium and assuming dumps are fully opened for the initial NC cooldown, Unit 1 would cooldown faster. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Cognitive Level QuestionType Comprehension BANK Developed Development References STMSGlO OPT Approved D OPS Approved NRC Approved QuestionBank  
A. Unit 1 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate. B. Unit 1 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate. c. Unit 2 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate. D. Unit 2 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate. Tuesday, November 18, 2008 Page 17 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 9 General Discussion Unit 1 has smaller tubes and larger surface area, therefore the leakage would be less on Unit 1 causing Unit 2 to have a larger pressure drop to equilibrium and assuming dumps are fully opened for the initial NC cooldown, Unit 1 would cooldown faster. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Cognitive Level QuestionType Comprehension BANK Developed Development References STMSGlO OPT Approved D OPS Approved NRC Approved QuestionBank  
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062AIG.03 Question does not meet KIA. The KIA asks for reasons for the following responses  
062AIG.03 Question does not meet KIA. The KIA asks for reasons for the following responses  
... The question as written does not address any reasons. Add reasons for actions to make question SAT. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 24 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 13 B QuestionBank  
... The question as written does not address any reasons. Add reasons for actions to make question SAT. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 24 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 13 B QuestionBank  
# IKA system IKA number I 519 I APE065 I AK3.03 I KA desc Knowledge of the reasons for the following responses as they apply to the Loss ofInstrument Air: (CFR 41.5,41.10/45.6/  
# IKA system IKA number I 519 I APE065 I AK3.03 I KA desc Knowledge of the reasons for the following responses as they apply to the Loss ofInstrument Air: (CFR 41.5,41.10/45.6/
: 45. 13) o Knowing effects on plant operation of isolating certain equipment from instrument air .....................................
: 45. 13) o Knowing effects on plant operation of isolating certain equipment from instrument air .....................................
Given the following:
Given the following:
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: 1. ECA-1.1 step 19 and Encl 5 -PROVIDED QuestionBank  
: 1. ECA-1.1 step 19 and Encl 5 -PROVIDED QuestionBank  
# IKA system IKA number I 521lWE04 IEKl.2 I KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the following:
# IKA system IKA number I 521lWE04 IEKl.2 I KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the following:
EP/1/A/5000IECA-1.1 (Step 19) EP/1/A/5000IECA-1.1 (Enclosure  
EP/1/A/5000IECA-1.1 (Step 19) EP/1/A/5000IECA-1.1 (Enclosure
: 5) (CFR: 41.7 /45. 7)DFacility*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.
: 5) (CFR: 41.7 /45. 7)DFacility*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.
401*9 Comments:
401*9 Comments:
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* S/G 1 D wide range level -28%
* S/G 1 D wide range level -28%
* The BOP has just secured all the NC pumps
* The BOP has just secured all the NC pumps
* The OATC notes NC system pressure is increasing  
* The OATC notes NC system pressure is increasing
: 1. Why have NC pumps been secured? 2. Why is NCS pressure increasing?
: 1. Why have NC pumps been secured? 2. Why is NCS pressure increasing?
A. 1. To begin NCS bleed and feed 2. Due to NC temperature increase B. 1. To minimize heat input 2. Due to letdown being secured C. 1. To begin NCS bleed and feed 2. Due to letdown being secured D. '1. To minimize heat input 2. Due to NC temperature.
A. 1. To begin NCS bleed and feed 2. Due to NC temperature increase B. 1. To minimize heat input 2. Due to letdown being secured C. 1. To begin NCS bleed and feed 2. Due to letdown being secured D. '1. To minimize heat input 2. Due to NC temperature.
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* 1AD-03, C/5 "SM ISOL TRN A" -LIT
* 1AD-03, C/5 "SM ISOL TRN A" -LIT
* 1AD-03, D/5 "SM ISOL TRN B" -LIT
* 1AD-03, D/5 "SM ISOL TRN B" -LIT
* 1AD-03, E/5 "SM ISOL VLVS NOTFULLY OPEN" -DARK 1. What additional action is taken per this procedure to attempt to close any MSIV? 2. If an MSIV can be closed, what plant parameter is monitored to determine when this procedure can be exited? A. 1. Maintenance is dispatched to isolate air to the MSIVs 2. NC loop T -hots B. 1. Both trains of Main Steam Isolation are manually initiated  
* 1AD-03, E/5 "SM ISOL VLVS NOTFULLY OPEN" -DARK 1. What additional action is taken per this procedure to attempt to close any MSIV? 2. If an MSIV can be closed, what plant parameter is monitored to determine when this procedure can be exited? A. 1. Maintenance is dispatched to isolate air to the MSIVs 2. NC loop T -hots B. 1. Both trains of Main Steam Isolation are manually initiated
: 2. NC loop T -hots C. 1. Maintenance is dispatched to isolate air to the MSIVs 2. S/G pressure D. 1. Both trains of Main Steam Isolation are manually initiated  
: 2. NC loop T -hots C. 1. Maintenance is dispatched to isolate air to the MSIVs 2. S/G pressure D. 1. Both trains of Main Steam Isolation are manually initiated
: 2. S/G pressure Tuesday, November 18, 2008 Page 35 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 18 c General Discussion To exit, one steam generator presure must be increasing and SII termination must not be in progress per ECA 2-1. NC Thots are monitored for other reasons in this procedure and they will increase once the MSIV is closed, but Enclsoure one specifies S/G Pressure.
: 2. S/G pressure Tuesday, November 18, 2008 Page 35 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 18 c General Discussion To exit, one steam generator presure must be increasing and SII termination must not be in progress per ECA 2-1. NC Thots are monitored for other reasons in this procedure and they will increase once the MSIV is closed, but Enclsoure one specifies S/G Pressure.
SM ISOL pushbuttons are depressed due to failed auto actions most likely during E-O in this scenario, but ECA-2.1 does not redo this action. It sends MAINT to isolate VI to the valves locally. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Memory NEW Development References EP/lI A/5000/ECA-2.1 QuestionBank  
SM ISOL pushbuttons are depressed due to failed auto actions most likely during E-O in this scenario, but ECA-2.1 does not redo this action. It sends MAINT to isolate VI to the valves locally. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Memory NEW Development References EP/lI A/5000/ECA-2.1 QuestionBank  
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* CRD BANK SELECT switch is in the "SBB" position.
* CRD BANK SELECT switch is in the "SBB" position.
* The OATC is withdrawing "B" Shutdown Bank control rods with the current bank position at 64 steps withdrawn.
* The OATC is withdrawing "B" Shutdown Bank control rods with the current bank position at 64 steps withdrawn.
* The OATC releases the ROD MOTION switch but "B" Shutdown Bank control rods continue to withdraw.  
* The OATC releases the ROD MOTION switch but "B" Shutdown Bank control rods continue to withdraw.
: 1. What is the current plant Mode of Operation?  
: 1. What is the current plant Mode of Operation?
: 2. Which of the following describes the first required action(s) for this situation per AP/1/A155001015 (Rod Control Malfunction)?
: 2. Which of the following describes the first required action(s) for this situation per AP/1/A155001015 (Rod Control Malfunction)?
A. 1. Mode 2 2. Immediately trip the reactor. B. 1. Mode 3 2. Immediately trip the reactor. C. 1. -Mode 2 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor. D. 1 Mode 3 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor. Tuesday, November 18, 2008 Page 37 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D General Discussion Per IRE lesson: '3.DAllows individual banks to be moved in bank select positions.
A. 1. Mode 2 2. Immediately trip the reactor. B. 1. Mode 3 2. Immediately trip the reactor. C. 1. -Mode 2 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor. D. 1 Mode 3 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor. Tuesday, November 18, 2008 Page 37 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D General Discussion Per IRE lesson: '3.DAllows individual banks to be moved in bank select positions.
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* Control Rod Bank D rod D4 indicates 216 steps withdrawn on DRPI.
* Control Rod Bank D rod D4 indicates 216 steps withdrawn on DRPI.
* All other Control Rod Bank D rods indicate 188 steps withdrawn on DRPI. 1. What is the first immediate action of the Abnormal Procedure that will address this issue? 2. What are the modes of applicability for the corresponding Technical Specification?
* All other Control Rod Bank D rods indicate 188 steps withdrawn on DRPI. 1. What is the first immediate action of the Abnormal Procedure that will address this issue? 2. What are the modes of applicability for the corresponding Technical Specification?
A. 1. Verify only one rod -MISALIGNED.  
A. 1. Verify only one rod -MISALIGNED.
: 2. MODE 1, MODE 2 with keff 1.0 B. 1. Verify only one rod -MISALIGNED.  
: 2. MODE 1, MODE 2 with keff 1.0 B. 1. Verify only one rod -MISALIGNED.
: 2. MODE 1, MODE 2 C. 1. Ensure "CRD BANK SELECT" switch -IN MANUAL. 2. MODE 1, MODE 2 with keff 1.0 D. 1. Ensure "CRD BANK SELECT" switch -IN MANUAL. 2. MODE 1, MODE 2 Tuesday, November 18, 2008 Page 39 of 200 B I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 B General Discussion One CR is misaligned by >24 asteps. And AP/14 would be appropriate for this situation.
: 2. MODE 1, MODE 2 C. 1. Ensure "CRD BANK SELECT" switch -IN MANUAL. 2. MODE 1, MODE 2 with keff 1.0 D. 1. Ensure "CRD BANK SELECT" switch -IN MANUAL. 2. MODE 1, MODE 2 Tuesday, November 18, 2008 Page 39 of 200 B I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 B General Discussion One CR is misaligned by >24 asteps. And AP/14 would be appropriate for this situation.
CRD bank select to manual is not an immedaite action but is the next action of this AP. It IS an immediate action of APIl5 for continuous rod movement.
CRD bank select to manual is not an immedaite action but is the next action of this AP. It IS an immediate action of APIl5 for continuous rod movement.
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45.6)ORCS water inventory  
45.6)ORCS water inventory  
..............................................
..............................................
S/G depressurization to atmospheric pressure has been performed in EP/1/A/5000/FR-C.1 (Response to Inadequate Core Cooling).  
S/G depressurization to atmospheric pressure has been performed in EP/1/A/5000/FR-C.1 (Response to Inadequate Core Cooling).
: 1. What are the NC temperature and RVLlS level limits that allow the crew to transition out of this procedure?  
: 1. What are the NC temperature and RVLlS level limits that allow the crew to transition out of this procedure?
: 2. Why are these conditions more restrictive than earlier transition conditions?
: 2. Why are these conditions more restrictive than earlier transition conditions?
A. 1. Two NC Thots less than 328 deg F, RVLlS level greater than 41 % 2. To ensure a hard bubble does not block natural circulation flow B. 1. Two NC Thots less than 328 deg F, RVLlS level. greater than 41 % 2. Due to the NC system being depressurized C. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 % 2. To ensure a hard bubble does not block natural circulation flow D. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 % 2. Due to the NC system being depressurized Tuesday, November 18, 2008 Page 47 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 24 General Discussion 350 and 61 are correct and NC depressurized is correct. 328 and hard bubble are both from S/G depress for CLA to prevent N2 injection.
A. 1. Two NC Thots less than 328 deg F, RVLlS level greater than 41 % 2. To ensure a hard bubble does not block natural circulation flow B. 1. Two NC Thots less than 328 deg F, RVLlS level. greater than 41 % 2. Due to the NC system being depressurized C. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 % 2. To ensure a hard bubble does not block natural circulation flow D. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 % 2. Due to the NC system being depressurized Tuesday, November 18, 2008 Page 47 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 24 General Discussion 350 and 61 are correct and NC depressurized is correct. 328 and hard bubble are both from S/G depress for CLA to prevent N2 injection.
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* 1RAD-3 D/2 "1EMF-17 REACTOR BLDG REFUEL BRIDGE" -LIT
* 1RAD-3 D/2 "1EMF-17 REACTOR BLDG REFUEL BRIDGE" -LIT
* The crew has implemented AP/1/Al55001025 (Damaged Spent Fuel). 1. Based on the above conditions, what was the status of the VP system when AP/11A15500/025 was entered? 2. What is the reason for establishing closure prior to VP being secured? A. 1. The VP system was running 2. To prevent an unmonitored release B. 1. The VP system was running 2. To prevent an excessive negative pressure in containment C. 1. The VP system has tripped 2. To prevent an unmonitored release D. 1. The VP system has tripped 2. To prevent an excessive negative pressure in containment Tuesday, November 18,2008 Page 49 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 25 General Discussion TIllS WAS A REPLACEMENT KA EMF39 secures VP using 2 separate signals one thru SSPS (Sh) and one directly from the EMF. With both trains ofSSPS in test, the Sh will not work, however VP will be secured by EMF 39 directly.
* The crew has implemented AP/1/Al55001025 (Damaged Spent Fuel). 1. Based on the above conditions, what was the status of the VP system when AP/11A15500/025 was entered? 2. What is the reason for establishing closure prior to VP being secured? A. 1. The VP system was running 2. To prevent an unmonitored release B. 1. The VP system was running 2. To prevent an excessive negative pressure in containment C. 1. The VP system has tripped 2. To prevent an unmonitored release D. 1. The VP system has tripped 2. To prevent an excessive negative pressure in containment Tuesday, November 18,2008 Page 49 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 25 General Discussion TIllS WAS A REPLACEMENT KA EMF39 secures VP using 2 separate signals one thru SSPS (Sh) and one directly from the EMF. With both trains ofSSPS in test, the Sh will not work, however VP will be secured by EMF 39 directly.
The status ofVP is checked per AP25. Answer A Discussion  
The status ofVP is checked per AP25. Answer A Discussion
[correct reason, wrong status Answer B Discussion  
[correct reason, wrong status Answer B Discussion
[both parts wrong Psychometric balance Answer C Discussion  
[both parts wrong Psychometric balance Answer C Discussion
[CORRECT Answer D Discussion  
[CORRECT Answer D Discussion
[wrong reason, corret status Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED 2004 NRC Q86 (Bank 386) Developed Development References Student References Provided AP/25 0 OPT Approved VQ 0 OPS Approved CNT VP NRC Approved QuestionBank  
[wrong reason, corret status Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED 2004 NRC Q86 (Bank 386) Developed Development References Student References Provided AP/25 0 OPT Approved VQ 0 OPS Approved CNT VP NRC Approved QuestionBank  
# IKA system IKA number J 531iAPE036 i AK3*03 J KA desc Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10 I 45.6 I 45. 13) DGuidance contained in EOP for fuel handling incident ................. . 401*9 Comments:
# IKA system IKA number J 531iAPE036 i AK3*03 J KA desc Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10 I 45.6 I 45. 13) DGuidance contained in EOP for fuel handling incident ................. . 401*9 Comments:
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* The crew entered EP/1/A/5000/ES-0.2 (Natural Circulation Cooldown).
* The crew entered EP/1/A/5000/ES-0.2 (Natural Circulation Cooldown).
* The OSM determined that a transition to EP/1/A/5000/ES-0.3 (Natural Circulation Cooldown With Steam Void in Vessel) was required.
* The OSM determined that a transition to EP/1/A/5000/ES-0.3 (Natural Circulation Cooldown With Steam Void in Vessel) was required.
* The crew has transitioned to ES-0.3 and is preparing to depressurize the NC system. 1. What condition would require stopping the depressurization of the NC system during this cooldown?  
* The crew has transitioned to ES-0.3 and is preparing to depressurize the NC system. 1. What condition would require stopping the depressurization of the NC system during this cooldown?
: 2. What is the basis for stopping the depressurization?
: 2. What is the basis for stopping the depressurization?
A. 1. PZR Level greater than 70% 2. To prevent loss of natural circulation B. 1. RVLlS level less than 73% 2. To prevent loss of natural circulation C. 1. PZR Level greater than 70% 2. To ensure normal pressurizer pressure control response D. 1. RVLlS level less than 73% 2. To ensure normal pressurizer pressure control response Tuesday, November 18, 2008 Page 53 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 27 B General Discussion 70% is the PZR Hi Level Alarm. The actual value is 90%. Thee reason is to prevent a los of natural circulation.
A. 1. PZR Level greater than 70% 2. To prevent loss of natural circulation B. 1. RVLlS level less than 73% 2. To prevent loss of natural circulation C. 1. PZR Level greater than 70% 2. To ensure normal pressurizer pressure control response D. 1. RVLlS level less than 73% 2. To ensure normal pressurizer pressure control response Tuesday, November 18, 2008 Page 53 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 27 B General Discussion 70% is the PZR Hi Level Alarm. The actual value is 90%. Thee reason is to prevent a los of natural circulation.
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* There is confirmed failed fuel on Unit 1.
* There is confirmed failed fuel on Unit 1.
* 1AD-07, F/3 "LETDN HX OUTLET HI TEMP" -LIT
* 1AD-07, F/3 "LETDN HX OUTLET HI TEMP" -LIT
* The BOP notes that letdown temperature has trended to 132°F and appears to have stabilized.  
* The BOP notes that letdown temperature has trended to 132°F and appears to have stabilized.
: 1. What minimum actions are required to reduce activity level per AP/1/A155001018 (High Activity in Reactor Coolant)?  
: 1. What minimum actions are required to reduce activity level per AP/1/A155001018 (High Activity in Reactor Coolant)?
: 2. What is the applicability of Tech Spec 3.4.16 (RCS Specific Activity)?
: 2. What is the applicability of Tech Spec 3.4.16 (RCS Specific Activity)?
A. 1. Ensure at least one mixed bed demineralizer in service only. 2. Modes 1, 2, and 3. B. 1. Ensure at least one mixed bed demineralizer in service only. 2. Modes 1 and 2, Mode 3 with Tavg 500°F. C. 1. Reduce letdown temperature to clear the alarm and then place additional demineralizers in service. 2. Modes 1, 2, and 3. D. 1. Reduce letdown temperature to clear the alarm and then place additional demineralizers in service. 2. Modes 1 and 2, Mode 3 with Tavg 500°F. Tuesday, November 18, 2008 Page 57 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 B General Discussion INV153A diverts to VCT (bypasses Demins) at 136 degrees. The alann comes in at 128 degrees. Placing additional demins in service could provide additional cleanup. Letdown does not need to have temeprature reduced, demins are still in service (but will isolate as 136F or greater) Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References OP/1/B/61001010H NV lesson TS 3.4.16 QuestionBank  
A. 1. Ensure at least one mixed bed demineralizer in service only. 2. Modes 1, 2, and 3. B. 1. Ensure at least one mixed bed demineralizer in service only. 2. Modes 1 and 2, Mode 3 with Tavg 500°F. C. 1. Reduce letdown temperature to clear the alarm and then place additional demineralizers in service. 2. Modes 1, 2, and 3. D. 1. Reduce letdown temperature to clear the alarm and then place additional demineralizers in service. 2. Modes 1 and 2, Mode 3 with Tavg 500°F. Tuesday, November 18, 2008 Page 57 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 B General Discussion INV153A diverts to VCT (bypasses Demins) at 136 degrees. The alann comes in at 128 degrees. Placing additional demins in service could provide additional cleanup. Letdown does not need to have temeprature reduced, demins are still in service (but will isolate as 136F or greater) Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References OP/1/B/61001010H NV lesson TS 3.4.16 QuestionBank  
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# IKA system IKA number I 537 I SYSOO5 I K4.11 I KA desc Knowledge of RHRS design feature( s) and! or interlock( s) which provide or the following: (CFR: 41.7) o Lineup for low head recirculation mode (external and internal)  
# IKA system IKA number I 537 I SYSOO5 I K4.11 I KA desc Knowledge of RHRS design feature( s) and! or interlock( s) which provide or the following: (CFR: 41.7) o Lineup for low head recirculation mode (external and internal)  
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1 NO-1 B (NO Pump 1A Suct Frm Loop B) and 1 NO-37 A (NO Pump 1 B Suct Frm Loop G) have been aligned to their alternate power supplies.  
1 NO-1 B (NO Pump 1A Suct Frm Loop B) and 1 NO-37 A (NO Pump 1 B Suct Frm Loop G) have been aligned to their alternate power supplies.
: 1. What impact (if any) will aligning the alternate power supply have on the interlocks associated with these valves? 2. How are these valves positioned electrically in the current alignment?
: 1. What impact (if any) will aligning the alternate power supply have on the interlocks associated with these valves? 2. How are these valves positioned electrically in the current alignment?
A. 1. Interlocks operate normally 2. From the main control boards B. 1. Interlocks operate normally 2. From the face of alternate MGG breaker G. 1. Interlocks are removed 2. From the main control boards O. 1. Interlocks are removed 2. From the face of alternate MGG breaker Tuesday, November 18, 2008 Page 61 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 31 General Discussion On alt power all interlocks are bypassed.
A. 1. Interlocks operate normally 2. From the main control boards B. 1. Interlocks operate normally 2. From the face of alternate MGG breaker G. 1. Interlocks are removed 2. From the main control boards O. 1. Interlocks are removed 2. From the face of alternate MGG breaker Tuesday, November 18, 2008 Page 61 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 31 General Discussion On alt power all interlocks are bypassed.
Line 602: Line 602:
Given the following conditions and sequence of events:
Given the following conditions and sequence of events:
* Unit 1 is manually tripped due to a loss of normal feedwater.
* Unit 1 is manually tripped due to a loss of normal feedwater.
* NLOs have manually isolated CA flow to 1 B S/G and level is noted to be 96% on NR level gauges. Which of the following consequences have increased risk for 1B S/G based on the current water level in that S/G? 1. Failure of S/G PORV to actuate 2. Failure of SM safety valves to reseat following an actuation  
* NLOs have manually isolated CA flow to 1 B S/G and level is noted to be 96% on NR level gauges. Which of the following consequences have increased risk for 1B S/G based on the current water level in that S/G? 1. Failure of S/G PORV to actuate 2. Failure of SM safety valves to reseat following an actuation
: 3. Water hammer upon initiation of steam flow 4. Mechanical failure of the main steam lines A. 1 and 2 only B. 3 and 4 only C. 1,2 and 3 D. 2,3 and 4 Tuesday, November 18, 2008 Page 87 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 44 General Discussion 2, 3 and 4 are all potential consequences of a SG overfill.
: 3. Water hammer upon initiation of steam flow 4. Mechanical failure of the main steam lines A. 1 and 2 only B. 3 and 4 only C. 1,2 and 3 D. 2,3 and 4 Tuesday, November 18, 2008 Page 87 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 44 General Discussion 2, 3 and 4 are all potential consequences of a SG overfill.
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided SMlesson 0 OPT Approved FR-H.3 Background 0 OPS Approved NRC Approved QuestionBank  
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided SMlesson 0 OPT Approved FR-H.3 Background 0 OPS Approved NRC Approved QuestionBank  
Line 632: Line 632:
==References:==
==References:==
: 1. OP-CN-ECCS-ISE page 21, 22, 23 QuestionBank  
: 1. OP-CN-ECCS-ISE page 21, 22, 23 QuestionBank  
# IKA system IKA number I 55l[SYS059  
# IKA system IKA number I 55l[SYS059
[A4.11 [ KA desc Question Source 2003 NRC Q55 (Bank 255) Old Bank Question:
[A4.11 [ KA desc Question Source 2003 NRC Q55 (Bank 255) Old Bank Question:
970BH Student References Provided Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8)DRecovery from automatic feedwater isolation 401-9 Comments:
970BH Student References Provided Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8)DRecovery from automatic feedwater isolation 401-9 Comments:
Line 655: Line 655:
This has no effect on Power Factor. This is OE from an NLO who was attempting to control PIP while operating isynchcronus.
This has no effect on Power Factor. This is OE from an NLO who was attempting to control PIP while operating isynchcronus.
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided DG3lesson D OPT Approved D OPS Approved NRC Approved QuestionBank  
Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided DG3lesson D OPT Approved D OPS Approved NRC Approved QuestionBank  
# IKA* system IKA number I 553[SYS062  
# IKA* system IKA number I 553[SYS062
[A3.01 [ KA desc Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7 I 45.5) o Vital ac bus amperage 401*9 Comments:
[A3.01 [ KA desc Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7 I 45.5) o Vital ac bus amperage 401*9 Comments:
062A3.01 Question appears to meet KIA. Change 2B Amps to 2B output amps. (field amps will decrease as voltage is lowered. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 94 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 c QuestionBank  
062A3.01 Question appears to meet KIA. Change 2B Amps to 2B output amps. (field amps will decrease as voltage is lowered. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 94 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 c QuestionBank  
Line 671: Line 671:
DIG will not start. Plausible:
DIG will not start. Plausible:
if student thinks that control power to the DIG is available thru V ADA. This is reversed, the DGCA supplies power thru V ADA to the sequencer.
if student thinks that control power to the DIG is available thru V ADA. This is reversed, the DGCA supplies power thru V ADA to the sequencer.
Answer C Discussion  
Answer C Discussion
:Incorrect:
:Incorrect:
DIG will not start. Plausible:
DIG will not start. Plausible:
Line 709: Line 709:
This is the FSAR requirement for the number of starts on a DIG Answer D Discussion Incorrect:
This is the FSAR requirement for the number of starts on a DIG Answer D Discussion Incorrect:
Can be started manually started Plausible:
Can be started manually started Plausible:
psychometric balance Job Level Cognitive Level QuestionType RO Comprehension BANK Developed Development References  
psychometric balance Job Level Cognitive Level QuestionType RO Comprehension BANK Developed Development References
: 1. DG 1 lesson D OPT Approved 2. Tech Spec Bases 3.8.3 El OPS Approved NRC Approved QuestionBank  
: 1. DG 1 lesson D OPT Approved 2. Tech Spec Bases 3.8.3 El OPS Approved NRC Approved QuestionBank  
# IKA system IKA number I 5571SYS064 IK6.07 I KA desc Question Source 2003 NRC Q64 (Bank 264) Student References Provided Knowledge ofthe effect ofa loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 I 45.7)DAir receivers 401-9 Comments:
# IKA system IKA number I 5571SYS064 IK6.07 I KA desc Question Source 2003 NRC Q64 (Bank 264) Student References Provided Knowledge ofthe effect ofa loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 I 45.7)DAir receivers 401-9 Comments:
Line 720: Line 720:
* A va release is in progress 1EMF-39L (CONTAINMENT GAS (LO RANGE>> detector fails causing a Trip 2 alarm
* A va release is in progress 1EMF-39L (CONTAINMENT GAS (LO RANGE>> detector fails causing a Trip 2 alarm
* 1RAD-1, Al2 "1EMF-39 CONTAINMENT GAS HI RAD" is LIT
* 1RAD-1, Al2 "1EMF-39 CONTAINMENT GAS HI RAD" is LIT
* 1 RAD-1, F/5 "CABINET 1-2 TROUBLE" is LIT 1. What is the status of the Unit 1 Containment Evacuation alarm? 2. What is/are the minimum action(s) required to reinitiate the air release from contain ment? A. 1. The Containment Evacuation alarm has actuated.  
* 1 RAD-1, F/5 "CABINET 1-2 TROUBLE" is LIT 1. What is the status of the Unit 1 Containment Evacuation alarm? 2. What is/are the minimum action(s) required to reinitiate the air release from contain ment? A. 1. The Containment Evacuation alarm has actuated.
: 2. Bypass the failed EMF detector per OP/0IAl65001080 (EMF RP86A Output Modules) and then RESET the safety signal per OPI1/B/61001010X (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) B. 1. The Containment Evacuation alarm has NOT actuated.  
: 2. Bypass the failed EMF detector per OP/0IAl65001080 (EMF RP86A Output Modules) and then RESET the safety signal per OPI1/B/61001010X (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) B. 1. The Containment Evacuation alarm has NOT actuated.
: 2. Bypass the failed EMF detector per OP/0IAl65001080 (EMF RP86A Output Modules) and then RESET the safety signal per OP/1/B/61001010X (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) C. 1. The Containment Evacuation alarm has actuated.  
: 2. Bypass the failed EMF detector per OP/0IAl65001080 (EMF RP86A Output Modules) and then RESET the safety signal per OP/1/B/61001010X (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) C. 1. The Containment Evacuation alarm has actuated.
: 2. RESET the safety signal only per OP/1/B/61 00101 OX per (Annunciator Response for Radiation Monitoring PaneI1RAD-1)
: 2. RESET the safety signal only per OP/1/B/61 00101 OX per (Annunciator Response for Radiation Monitoring PaneI1RAD-1)
D. 1. The Containment Evacuation alarm has NOT actuated.  
D. 1. The Containment Evacuation alarm has NOT actuated.
: 2. RESET the safety signal only per OP/1/B/61 00101 OX per (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) Tuesday, November 18, 2008 Page 103 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 52 General Discussion EMF 39 Trip2 will give an SH signal. This will isolate containment ventilation (VPNQ). To reset the SH the initiating signal must be cleared and the reset depressed unlike SP and ST which can be reset with the initiating signal present. The containment evacuation alarm sounds on this EMF in trip 2 below P-6 (Low in source range) the reactor is currently below P-l 0 (l0% power but well above P6) Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References OP/lIB1610010l0 X QuestionBank  
: 2. RESET the safety signal only per OP/1/B/61 00101 OX per (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) Tuesday, November 18, 2008 Page 103 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 52 General Discussion EMF 39 Trip2 will give an SH signal. This will isolate containment ventilation (VPNQ). To reset the SH the initiating signal must be cleared and the reset depressed unlike SP and ST which can be reset with the initiating signal present. The containment evacuation alarm sounds on this EMF in trip 2 below P-6 (Low in source range) the reactor is currently below P-l 0 (l0% power but well above P6) Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References OP/lIB1610010l0 X QuestionBank  
# IKA system IKA number I 558!SYS073 1 A2*02 I KA desc Question Source Student References Provided 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 cor-reet, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 I 45.3 I 45. 13) o Detector failure ................................................ . 401-9 Comments:
# IKA system IKA number I 558!SYS073 1 A2*02 I KA desc Question Source Student References Provided 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 cor-reet, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 I 45.3 I 45. 13) o Detector failure ................................................ . 401-9 Comments:
Line 788: Line 788:
A. S/G pressures are decreasing and T cold is at S/G saturation temperature.
A. S/G pressures are decreasing and T cold is at S/G saturation temperature.
B. S/G saturation temperatures are decreasing and REACTOR VESSEL U R LEVEL indication is greater than 100%. C. S/G pressures are decreasing and REACTOR VESSEL DIP indication is greater than 100%. D. S/G pressure is at saturation pressure for Tcold and REACTOR VESSEL DIP indication is greater than 100%. Tuesday, November 18, 2008 Page 117 0(200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 59 A General Discussion IBank Question:
B. S/G saturation temperatures are decreasing and REACTOR VESSEL U R LEVEL indication is greater than 100%. C. S/G pressures are decreasing and REACTOR VESSEL DIP indication is greater than 100%. D. S/G pressure is at saturation pressure for Tcold and REACTOR VESSEL DIP indication is greater than 100%. Tuesday, November 18, 2008 Page 117 0(200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 59 A General Discussion IBank Question:
911.1 Answer A Discussion Answer B Discussion  
911.1 Answer A Discussion Answer B Discussion
:Incorrect:
:Incorrect:
There is no indication of coupling between primary and secondary.
There is no indication of coupling between primary and secondary.
Line 818: Line 818:
Answer D Discussion Incorrect:
Answer D Discussion Incorrect:
HEP A filters do not remove radioactive Iodine Plausible:
HEP A filters do not remove radioactive Iodine Plausible:
REP A filter remove small particulates Job Level Cognitive Level Question Type RO Developed D OPT Approved D OPS Approved NRC Approved Memory BANK Development References  
REP A filter remove small particulates Job Level Cognitive Level Question Type RO Developed D OPT Approved D OPS Approved NRC Approved Memory BANK Development References
: 1. OP-CN-CNT-VE pages 5-6 QuestionBank  
: 1. OP-CN-CNT-VE pages 5-6 QuestionBank  
# IKA system IKA number I 5661SYS027 IKS.Ol I KA desc QUESTION 60 Question Source 2003 NRC Q41 (Bank 241) Student References Provided Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7 I 45.7)DPurpose of charcoal filters 401*9 Comments:
# IKA system IKA number I 5661SYS027 IKS.Ol I KA desc QUESTION 60 Question Source 2003 NRC Q41 (Bank 241) Student References Provided Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7 I 45.7)DPurpose of charcoal filters 401*9 Comments:
Line 840: Line 840:
035G2.i.40 Questions appears to match KIA. 2005 NRC exam. SAT BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 122 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 QuestionBank  
035G2.i.40 Questions appears to match KIA. 2005 NRC exam. SAT BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 122 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 QuestionBank  
# IKA system IKA number I 568 I SYS045 I A3.05 I KA desc Ability to monitor automatic operation of the MT/G system, including: (CPR: 4117 /
# IKA system IKA number I 568 I SYS045 I A3.05 I KA desc Ability to monitor automatic operation of the MT/G system, including: (CPR: 4117 /
control ................................... ...... Unit 1 is operating at 100% power. 1. H,?w is EHC Emergency Manual Mode selected?  
control ................................... ...... Unit 1 is operating at 100% power. 1. H,?w is EHC Emergency Manual Mode selected?
: 2. How do the control valves respond to a manual run back under the above conditions?
: 2. How do the control valves respond to a manual run back under the above conditions?
A. 1. automatically  
A. 1. automatically
: 2. the control valves will operate per the valve curves B. 1. automatically  
: 2. the control valves will operate per the valve curves B. 1. automatically
: 2. the control valves will NOT operate per the valve curves C. 1. manually 2. the control valves will operate per the valve curves D. 1. manually 2. the control valves will NOT operate per the valve curves Tuesday, November 18, 2008 Page 123 of 200 B FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 General Discussion Emerg manual mode cannot be manually selected.
: 2. the control valves will NOT operate per the valve curves C. 1. manually 2. the control valves will operate per the valve curves D. 1. manually 2. the control valves will NOT operate per the valve curves Tuesday, November 18, 2008 Page 123 of 200 B FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 General Discussion Emerg manual mode cannot be manually selected.
When the valves are operated (in manual using CV lower), all valves will stroke simultaneously without regard for the programmed valves curves Answer A Discussion lfirst part true second part false. Answer B Discussion Answer C Discussion Iboth parts false -psychometric balance Answer D Discussion lfirst part is wrong, second part is true Job Level Cognitive Level QuestionType Question Source RO Memory NEW B Developed Development References Student References Provided OPIl/B/6 I 00/0 lOB D OPT Approved EHC lesson D OPS Approved NRC Approved QuestionBank  
When the valves are operated (in manual using CV lower), all valves will stroke simultaneously without regard for the programmed valves curves Answer A Discussion lfirst part true second part false. Answer B Discussion Answer C Discussion Iboth parts false -psychometric balance Answer D Discussion lfirst part is wrong, second part is true Job Level Cognitive Level QuestionType Question Source RO Memory NEW B Developed Development References Student References Provided OPIl/B/6 I 00/0 lOB D OPT Approved EHC lesson D OPS Approved NRC Approved QuestionBank  
Line 876: Line 876:
* 2A DIG auto-started due to a blackout on 2ET A
* 2A DIG auto-started due to a blackout on 2ET A
* The control room crew notes all loads were sequenced on as required
* The control room crew notes all loads were sequenced on as required
* A fuel oil line leak occurs resulting in a major fire in the 2A DIG room Assuming no operator actions since the DIG auto-started:  
* A fuel oil line leak occurs resulting in a major fire in the 2A DIG room Assuming no operator actions since the DIG auto-started:
: 1. How long will it take for the Cardox system to discharge once the fire is detected?  
: 1. How long will it take for the Cardox system to discharge once the fire is detected?
: 2. What is the status of the 2A DIG emergency ventilation after the Cardox system discharges?
: 2. What is the status of the 2A DIG emergency ventilation after the Cardox system discharges?
A. 1. 6.5 minutes 2. Running due to sequencer actuation B. 1. 6.5 minutes 2. Secured due to Cardox actuation C. 1. 1.5 minutes 2. Running due to sequencer actuation D. 1. 1.5 minutes 2. Secured due to Cardox actuation Tuesday, November 18, 2008 Page 129 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE A ZOOS SRO NRC Examination QUESTION 65 General Discussion The DIG ventilation will start following the autostart after the B/O signal, since the sequencer has not been reset, they will continue to run. The cardox actuation would normally shutdown the ventialtion system. There is a 5.0 electronic time followed bya 1.5 min pneumatic timer. Were there a loss of power to the cardox system, the 5 min electronic timeer would not work and the cardox would dump at 1.5 minutes. Answer A Discussion Answer B Discussion Icorrect time, but fans run Answer C Discussion lincorrect time, fan status is correct Answer D Discussion IBoth incorrect pyschometric balance Job Level Cognitive Level Question Type Question Source RO Memory NEW Developed Development References Student References Provided RFY lesson 0 OPT Approved DG 1 lesson VD 0 OPS Approved NRC Approved QuestionBank  
A. 1. 6.5 minutes 2. Running due to sequencer actuation B. 1. 6.5 minutes 2. Secured due to Cardox actuation C. 1. 1.5 minutes 2. Running due to sequencer actuation D. 1. 1.5 minutes 2. Secured due to Cardox actuation Tuesday, November 18, 2008 Page 129 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE A ZOOS SRO NRC Examination QUESTION 65 General Discussion The DIG ventilation will start following the autostart after the B/O signal, since the sequencer has not been reset, they will continue to run. The cardox actuation would normally shutdown the ventialtion system. There is a 5.0 electronic time followed bya 1.5 min pneumatic timer. Were there a loss of power to the cardox system, the 5 min electronic timeer would not work and the cardox would dump at 1.5 minutes. Answer A Discussion Answer B Discussion Icorrect time, but fans run Answer C Discussion lincorrect time, fan status is correct Answer D Discussion IBoth incorrect pyschometric balance Job Level Cognitive Level Question Type Question Source RO Memory NEW Developed Development References Student References Provided RFY lesson 0 OPT Approved DG 1 lesson VD 0 OPS Approved NRC Approved QuestionBank  
Line 883: Line 883:
.................................... . 401-9 Comments:
.................................... . 401-9 Comments:
086K6.04 Question appears to match KIA. SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 130 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 66 D QuestionBank  
086K6.04 Question appears to match KIA. SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 130 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 66 D QuestionBank  
# IKA system IKA number I 572 I GEN2.1 I 2.1.45 I KA desc Conduct of Operations 0 Ability to identitY and interpret diverse indications to validate the response of another indication. (CFR: 41.7 /43.5 / 45.4) During a control board walkdown, the crew notes that over the last 10 minutes turbine load has decreased from 1209 MW to 1207 MW while reactor power has increased from 99.87% to 100.05%. They suspect a steam leak. Which set of the following indications could be used to confirm their suspicions?  
# IKA system IKA number I 572 I GEN2.1 I 2.1.45 I KA desc Conduct of Operations 0 Ability to identitY and interpret diverse indications to validate the response of another indication. (CFR: 41.7 /43.5 / 45.4) During a control board walkdown, the crew notes that over the last 10 minutes turbine load has decreased from 1209 MW to 1207 MW while reactor power has increased from 99.87% to 100.05%. They suspect a steam leak. Which set of the following indications could be used to confirm their suspicions?
: 1. % Steam flow 2. Steam pressure 3. Containment pressure 4. Containment humidity A. 1,2,3 B. 1,2,4 C. 1,3,4 D. 2,3,4 Tuesday, November 18, 2008 Page 131 of200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 66 General Discussion Based on simulator modelling, a steam leak of lE4 #1hI would cause MW and Rx power indications as shown. Containment pressure would increase as well as humidity.
: 1. % Steam flow 2. Steam pressure 3. Containment pressure 4. Containment humidity A. 1,2,3 B. 1,2,4 C. 1,3,4 D. 2,3,4 Tuesday, November 18, 2008 Page 131 of200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 66 General Discussion Based on simulator modelling, a steam leak of lE4 #1hI would cause MW and Rx power indications as shown. Containment pressure would increase as well as humidity.
This is less than 1I100th of 1 % steam flow to any given S/G (3.  
This is less than 1I100th of 1 % steam flow to any given S/G (3.  
Line 985: Line 985:
-GREEN
-GREEN
* NC Inventory  
* NC Inventory  
-YELLOW Per OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines):  
-YELLOW Per OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines):
: 1. Which control room crew position, by title, has primary responsibility for monitoring Critical Safety Function (CSF) status trees during EOP usage? 2. Based on current conditions how frequent should CSF status trees be monitored?
: 1. Which control room crew position, by title, has primary responsibility for monitoring Critical Safety Function (CSF) status trees during EOP usage? 2. Based on current conditions how frequent should CSF status trees be monitored?
A. 1. OSM 2. monitor every 10-20 minutes B. 1. OSM 2. monitor continuously C. 1. STA 2. monitor every 10-20 minutes D. 1. STA 2. monitor continuously Tuesday, November 18, 2008 Page 145 of 200 c I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 c General Discussion Per OMP 1-7, C is correct green or yellow only is every 10-20 minutes, any red or orange is continuously.
A. 1. OSM 2. monitor every 10-20 minutes B. 1. OSM 2. monitor continuously C. 1. STA 2. monitor every 10-20 minutes D. 1. STA 2. monitor continuously Tuesday, November 18, 2008 Page 145 of 200 c I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 c General Discussion Per OMP 1-7, C is correct green or yellow only is every 10-20 minutes, any red or orange is continuously.
Line 999: Line 999:
* is listed in the correct order per the CSF status trees from highest to lowest priority
* is listed in the correct order per the CSF status trees from highest to lowest priority
* forms the bases for protection of the fuel and fuel cladding?
* forms the bases for protection of the fuel and fuel cladding?
A. 1. Heat Sink 2. Core Cooling 3. Integrity B. 1 . Core Cooling 2. Heat Sink 3. NC Inventory C. 1. Heat Sink 2. Subcriticality  
A. 1. Heat Sink 2. Core Cooling 3. Integrity B. 1 . Core Cooling 2. Heat Sink 3. NC Inventory C. 1. Heat Sink 2. Subcriticality
: 3. NC Inventory D. 1. Subcriticality  
: 3. NC Inventory D. 1. Subcriticality
: 2. Heat Sink 3. Integrity Tuesday, November 18, 2008 Page 147 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 74 B General Discussion Answer A Discussion IIncorrect:
: 2. Heat Sink 3. Integrity Tuesday, November 18, 2008 Page 147 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 74 B General Discussion Answer A Discussion IIncorrect:
Wrong order, wrong functions.
Wrong order, wrong functions.
Line 1,009: Line 1,009:
G2.4.22 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 148 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 QuestionBank  
G2.4.22 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 148 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 QuestionBank  
# IKA system IKA number I 581 I GEN2.4 I 2.4.42 I KA desc Emergency Procedures  
# IKA system IKA number I 581 I GEN2.4 I 2.4.42 I KA desc Emergency Procedures  
/ PianO Knowledge of emergency response facilities. (CFR: 41.10 /45.11) An offsite release is occurring due to a stuck open SIG PORV on 2C SIG which has a significant tube leak. Which one of the following states: 1. The emergency facility that assumes responsibility for communications with offsite agencies including the NRC once it is activated?  
/ PianO Knowledge of emergency response facilities. (CFR: 41.10 /45.11) An offsite release is occurring due to a stuck open SIG PORV on 2C SIG which has a significant tube leak. Which one of the following states: 1. The emergency facility that assumes responsibility for communications with offsite agencies including the NRC once it is activated?
: 2. What is the lowest classification level that requires this facility's activation?
: 2. What is the lowest classification level that requires this facility's activation?
A. 1. Technical Support Center (TSC) 2. Alert B. 1. Technical Support Center (TSC) 2. Unusual Event C. 1. Operations Support Center (OSC) 2. Alert D. 1. Operations Support Center (OSC) 2. Unusual Event Tuesday, November 18, 2008 Page 149 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 A General Discussion Answer A Discussion Answer B Discussion Correct location, wrong classification.
A. 1. Technical Support Center (TSC) 2. Alert B. 1. Technical Support Center (TSC) 2. Unusual Event C. 1. Operations Support Center (OSC) 2. Alert D. 1. Operations Support Center (OSC) 2. Unusual Event Tuesday, November 18, 2008 Page 149 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 A General Discussion Answer A Discussion Answer B Discussion Correct location, wrong classification.
Line 1,027: Line 1,027:
* 1A NO and 1B NO loops operating in residual heat removal mode
* 1A NO and 1B NO loops operating in residual heat removal mode
* An NO pump suction relief has spuriously lifted and has not reseated
* An NO pump suction relief has spuriously lifted and has not reseated
* Both NO pumps have been secured per AP/1/A/55001027 (Shutdown LOCA) 1. What is the correct procedure flowpath for this situation?  
* Both NO pumps have been secured per AP/1/A/55001027 (Shutdown LOCA) 1. What is the correct procedure flowpath for this situation?
: 2. What is the limiting component that the current ECCS pump configuration is designed to protect from over-pressurization?
: 2. What is the limiting component that the current ECCS pump configuration is designed to protect from over-pressurization?
A. 1. Remain in AP/1/A/55001027 (Shutdown LOCA) 2. NC loop crossover pipe B. 1. Transition to AP/1/A/55001019 (Loss of Residual Heat Removal System) 2. NC loop crossover pipe C. 1. Remain in AP/1/A/55001027 (Shutdown LOCA) 2. Reactor vessel O. 1. Transition to AP/1 IA/55001019 (Loss of Residual Heat Removal System) 2. Reactor vessel Tuesday, November 18, 2008 Page 151 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 76 General Discussion this is Mode 4 LTOP condition.
A. 1. Remain in AP/1/A/55001027 (Shutdown LOCA) 2. NC loop crossover pipe B. 1. Transition to AP/1/A/55001019 (Loss of Residual Heat Removal System) 2. NC loop crossover pipe C. 1. Remain in AP/1/A/55001027 (Shutdown LOCA) 2. Reactor vessel O. 1. Transition to AP/1 IA/55001019 (Loss of Residual Heat Removal System) 2. Reactor vessel Tuesday, November 18, 2008 Page 151 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 76 General Discussion this is Mode 4 LTOP condition.
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QUESTION 77 QuestionBank  
QUESTION 77 QuestionBank  
# IKA system IKA number J 583 I EPEOII I 2.2.36 I KA desc EPEOII GENERIC 0 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status oflimiting conditions for operations. (CFR: 41.10/43.2/45.13)
# IKA system IKA number J 583 I EPEOII I 2.2.36 I KA desc EPEOII GENERIC 0 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status oflimiting conditions for operations. (CFR: 41.10/43.2/45.13)
Unit 2 is at 3% power. Given the following sequence of events: 12/01/08 1100 2A NI pump tagged to replace the motor cooler. 12/03/08 0500 2B DIG tripped on high vibration during performance of PT/2/A/43501002B (Diesel Generator 2B Operability Test). 12/03/08 0700 You complete turnover and take the position ofCRS. 1. What is the latest time that entry into Mode 3 is required per Technical Specifications assuming both components remain inoperable?  
Unit 2 is at 3% power. Given the following sequence of events: 12/01/08 1100 2A NI pump tagged to replace the motor cooler. 12/03/08 0500 2B DIG tripped on high vibration during performance of PT/2/A/43501002B (Diesel Generator 2B Operability Test). 12/03/08 0700 You complete turnover and take the position ofCRS. 1. What is the latest time that entry into Mode 3 is required per Technical Specifications assuming both components remain inoperable?
: 2. When you take shift duty at 0700, can the ECCS design criteria for a large break LOCA be assumed to be met? A. 1. 12/03/08 1200 2. Yes B. 1. 12/03/08 1200 2. No C. 1. 12/03/08 1600 2. Yes D. 1. 12/03/08 1600 2. No Tuesday, November 18, 2008 Reference provided Page 153 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 77 General Discussion This tests knowledge of the 4 hour additional time before redundant equipment is declared inoperable after the DIG is declared inoperable.
: 2. When you take shift duty at 0700, can the ECCS design criteria for a large break LOCA be assumed to be met? A. 1. 12/03/08 1200 2. Yes B. 1. 12/03/08 1200 2. No C. 1. 12/03/08 1600 2. Yes D. 1. 12/03/08 1600 2. No Tuesday, November 18, 2008 Reference provided Page 153 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 77 General Discussion This tests knowledge of the 4 hour additional time before redundant equipment is declared inoperable after the DIG is declared inoperable.
Until that time 3.0.3 does not apply to this situation after that, 3.0.3 is entered. Answer A Discussion this is the time for 3.0.3 without the 4 hours; second part correct Answer B Discussion this is the time for 3.0.3 without the 4 hours; still within the 4 hour window, therefore 2B NI is assumed to be operable.
Until that time 3.0.3 does not apply to this situation after that, 3.0.3 is entered. Answer A Discussion this is the time for 3.0.3 without the 4 hours; second part correct Answer B Discussion this is the time for 3.0.3 without the 4 hours; still within the 4 hour window, therefore 2B NI is assumed to be operable.
Answer C Discussion Icorrect Answer D Discussion correct time, still within the 4 hour window, therefore 2B NI is assumed to be operable.
Answer C Discussion Icorrect Answer D Discussion correct time, still within the 4 hour window, therefore 2B NI is assumed to be operable.
Co Job Level Cognitive Level QuestionType SRO Comprehension NEW Developed Development References T.S. 3.5.2 and basis 0 OPT Approved T.S. 3.8.1 and basis 0 OPS Approved NRC Approved QuestionBank  
Co Job Level Cognitive Level QuestionType SRO Comprehension NEW Developed Development References T.S. 3.5.2 and basis 0 OPT Approved T.S. 3.8.1 and basis 0 OPS Approved NRC Approved QuestionBank  
# IKA system IKA number I 5831EPEOli 1 2.2.36 I KA desc Question Source Student References Provided Technical Specification  
# IKA system IKA number I 5831EPEOli 1 2.2.36 I KA desc Question Source Student References Provided Technical Specification 3.5.2 Technical Specification 3.8.1 EPEOll GENERlCDAbility to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 I 43.2 145.13) 401*9 Comments:
 
====3.5.2 Technical====
 
Specification  
 
====3.8.1 EPEOll====
GENERlCDAbility to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 I 43.2 145.13) 401*9 Comments:
0IIEG2.2.36 Question appears to match the KIA. Reference for question 77 could help answer question 76. Appears to be SRO only. Stem Focus is also confusing.
0IIEG2.2.36 Question appears to match the KIA. Reference for question 77 could help answer question 76. Appears to be SRO only. Stem Focus is also confusing.
Try "assuming that components remain inoperable." Second question discussing ECCS Criteria.
Try "assuming that components remain inoperable." Second question discussing ECCS Criteria.
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# IKA system IKA number I 587 I APE077 I AA2.09 I KA desc Ability to detennine and interpret the. following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 /45.5, 45.7, and 45.8) 0 Operationar status of emergency diesel generators  
# IKA system IKA number I 587 I APE077 I AA2.09 I KA desc Ability to detennine and interpret the. following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 /45.5, 45.7, and 45.8) 0 Operationar status of emergency diesel generators  
........................
........................
Unit 1 is operating at 100% power. Unit 2 is in a refueling outage with 2EMXH aligned to Unit 1 power. Given the following conditions and sequence of events: 0530 1AD-11, G/6 "SWGR 1 ETA DEGRADED BUS VOLTAGE" is LIT 1 AD-11 , H/6 "SWGR 1 ETB DEGRADED B US VOLTAGE" is LIT 1AD-11, Kl6 "230KV SWITCHYARD VOLTAGE LO" is LIT 0535 The ST A notes by OAC trends that 1 ETA and 1 ETB minimum voltages were 3620V and 3637V respectively and are now increasing.  
Unit 1 is operating at 100% power. Unit 2 is in a refueling outage with 2EMXH aligned to Unit 1 power. Given the following conditions and sequence of events: 0530 1AD-11, G/6 "SWGR 1 ETA DEGRADED BUS VOLTAGE" is LIT 1 AD-11 , H/6 "SWGR 1 ETB DEGRADED B US VOLTAGE" is LIT 1AD-11, Kl6 "230KV SWITCHYARD VOLTAGE LO" is LIT 0535 The ST A notes by OAC trends that 1 ETA and 1 ETB minimum voltages were 3620V and 3637V respectively and are now increasing.
: 1. At 0530, what is the earliest time required for Unit 1 to enter Mode 3 per Technical Specifications?  
: 1. At 0530, what is the earliest time required for Unit 1 to enter Mode 3 per Technical Specifications?
: 2. At 0535, assuming no operator actions, what is the status of DIG 1A and DIG 1B? A. 7 hours due to TS 3.0.3; both running B. 7 hours due to TS 3.0.3; both secured C. 6 hours due to TS 3.7.5 (Auxiliary Feedwater (AFW) System); both running D. 6 hours due to TS 3.7.5 (Auxiliary Feedwater (AFW) System); both secured Tuesday, November 18, 2008 Page 161 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 81 B General Discussion At 90% voltage a 10 min timer starts to intiate aBO of the essential busses. This time is 5 seconds if a LOCA has occurred (in this case the DIGs would start and load). Also, if voltage decreases to approximately 84%
: 2. At 0535, assuming no operator actions, what is the status of DIG 1A and DIG 1B? A. 7 hours due to TS 3.0.3; both running B. 7 hours due to TS 3.0.3; both secured C. 6 hours due to TS 3.7.5 (Auxiliary Feedwater (AFW) System); both running D. 6 hours due to TS 3.7.5 (Auxiliary Feedwater (AFW) System); both secured Tuesday, November 18, 2008 Page 161 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 81 B General Discussion At 90% voltage a 10 min timer starts to intiate aBO of the essential busses. This time is 5 seconds if a LOCA has occurred (in this case the DIGs would start and load). Also, if voltage decreases to approximately 84%
the DIG would start and load. Neither of these situations occurred so the DIGs are not started. The annunciators imply a grid disturbance.
the DIG would start and load. Neither of these situations occurred so the DIGs are not started. The annunciators imply a grid disturbance.
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* 8/03/08 -89.00 0 F.
* 8/03/08 -89.00 0 F.
* 8/04/08 -89.75 0 F.
* 8/04/08 -89.75 0 F.
* 8/05/08 -90.50 0 F. 1. Assuming lake temperature continues to increase at a constant rate, on what date will Lake Wylie temperature first exceed the requirements of SLC 16.9-14 (Lake Wylie Water Temperature)?  
* 8/05/08 -90.50 0 F. 1. Assuming lake temperature continues to increase at a constant rate, on what date will Lake Wylie temperature first exceed the requirements of SLC 16.9-14 (Lake Wylie Water Temperature)?
: 2. What affect, if any, will this higher lake temperature have on the ability of the NS system to affect containment pressure following a large break LOCA? A. 1. 8/09/08 2. Minimal impact prior to ice melt, but significant impact later in the accident sequence when the ice has been depleted.
: 2. What affect, if any, will this higher lake temperature have on the ability of the NS system to affect containment pressure following a large break LOCA? A. 1. 8/09/08 2. Minimal impact prior to ice melt, but significant impact later in the accident sequence when the ice has been depleted.
B. 1. 8/09/08 2. Minimal impact during the entire accident sequence since lake temperature is still below the design basis accident assumptions.
B. 1. 8/09/08 2. Minimal impact during the entire accident sequence since lake temperature is still below the design basis accident assumptions.
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# IKA system IKA number I 5931SYS026 12.4.47 1 KA desc SYS026 GENERIC DAbility to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/45.12) 401*9 Comments:
# IKA system IKA number I 5931SYS026 12.4.47 1 KA desc SYS026 GENERIC DAbility to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/45.12) 401*9 Comments:
026G2.4.47 Question appears to match KJA. Appears to SRO only. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 174 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 88 D QuestionBank  
026G2.4.47 Question appears to match KJA. Appears to SRO only. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 174 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 88 D QuestionBank  
# IKA system IKA number I 594 I SYS039 I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/  
# IKA system IKA number I 594 I SYS039 I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/
: 45. 13) DDecrease in turbine load as it relates to steam escaping from relief valves . Given the following:
: 45. 13) DDecrease in turbine load as it relates to steam escaping from relief valves . Given the following:
* Rod control is in MANUAL.
* Rod control is in MANUAL.
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* 1A DIG was immediately secured by the control room crew.
* 1A DIG was immediately secured by the control room crew.
* All annunciators listed above continue to remain LIT.
* All annunciators listed above continue to remain LIT.
* The crew entered and took all actions per AP/O/A/55001030 (Plant Flooding) necessary to stop the flooding.  
* The crew entered and took all actions per AP/O/A/55001030 (Plant Flooding) necessary to stop the flooding.
: 1. At what RN header pressure do the annuciators first come into alarm? 2. What is the current overall status related to Tech Spec 3.7.8 (Nuclear Service Water System (NSWS))? A. 1. 40 psig decreasing  
: 1. At what RN header pressure do the annuciators first come into alarm? 2. What is the current overall status related to Tech Spec 3.7.8 (Nuclear Service Water System (NSWS))? A. 1. 40 psig decreasing
: 2. Unit 1 in a 72 hour action , Unit 2 operable B. 1. 40 psig decreasing  
: 2. Unit 1 in a 72 hour action , Unit 2 operable B. 1. 40 psig decreasing
: 2. Both units in a 72 hour action C. 1. 46 psig decreasing  
: 2. Both units in a 72 hour action C. 1. 46 psig decreasing
: 2. Unit 1 in a 72 hour action, Unit 2 operable D. 1. 46 psig decreasing  
: 2. Unit 1 in a 72 hour action, Unit 2 operable D. 1. 46 psig decreasing
: 2. Both units in a 72 hour action Tuesday, November 18, 2008 Page 179 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 90 General Discussion Rn low header pressure comes in at 46 pisg decreaing.
: 2. Both units in a 72 hour action Tuesday, November 18, 2008 Page 179 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 90 General Discussion Rn low header pressure comes in at 46 pisg decreaing.
With the lA DIG secured, RN232A would close. Since the conditions persist following shutdown, the leak must be between the DIG building wall and RN232A. The only way that this leak can be secured is to separate RN trains and secure all of A train RN which is what AP30 does. This makes both units enter a 72 action for RN. The 40 psig value is the RNIYV opearble light pressure setpoint.
With the lA DIG secured, RN232A would close. Since the conditions persist following shutdown, the leak must be between the DIG building wall and RN232A. The only way that this leak can be secured is to separate RN trains and secure all of A train RN which is what AP30 does. This makes both units enter a 72 action for RN. The 40 psig value is the RNIYV opearble light pressure setpoint.
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SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 180 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 91 QuestionBank  
SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 180 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 91 QuestionBank  
# IKA system IKA number I 597 I SYS033 I 2.2.22 I KA desc SYS033 GENERICDKnowledge oflimiting conditions for operations and safety limits. (CFR: 41.5 /43.2/45.,2)
# IKA system IKA number I 597 I SYS033 I 2.2.22 I KA desc SYS033 GENERICDKnowledge oflimiting conditions for operations and safety limits. (CFR: 41.5 /43.2/45.,2)
Unit 2 is in Mode 6 performing core unloading when Spent Fuel Pool level is noted at 22 feet above the fuel assemblies.  
Unit 2 is in Mode 6 performing core unloading when Spent Fuel Pool level is noted at 22 feet above the fuel assemblies.
: 1. Which one of the following is a required action for the above condition per T echn ical Specifications?  
: 1. Which one of the following is a required action for the above condition per T echn ical Specifications?
: 2. What is the basis for maintaining a minimum acceptable water level? A. 1. Immediately suspend movement of irradiated fuel assemblies  
: 2. What is the basis for maintaining a minimum acceptable water level? A. 1. Immediately suspend movement of irradiated fuel assemblies
: 2. Ensures shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident B. 1. Immediately suspend movement of irradiated fuel assemblies  
: 2. Ensures shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident B. 1. Immediately suspend movement of irradiated fuel assemblies
: 2. Ensures that there is a sufficient volume of water above the fuel assemblies to provide backup decay heat removal C. 1. Within 1 hour, initiate action to restore spent fuel pool level to within limits. 2. Ensures shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident D. 1. Within 1 hour, initiate action to restore spent fuel pool level to within limits. 2. Ensures that there is a sufficient volume of water above the fuel assemblies to provide backup decay heat removal Tuesday, November 18, 2008 Page 181 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 91 A General Discussion SFP Boron should be >2700 and level should be >23 feet. Both specs are not met. Action for boron out is to stop moving all fuel assemblies in the spent fuel pool and initiate action to get it back. Action for level out is to stop moving irradiated fuel. Correct answer states stop moving fuel assemblies.
: 2. Ensures that there is a sufficient volume of water above the fuel assemblies to provide backup decay heat removal C. 1. Within 1 hour, initiate action to restore spent fuel pool level to within limits. 2. Ensures shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident D. 1. Within 1 hour, initiate action to restore spent fuel pool level to within limits. 2. Ensures that there is a sufficient volume of water above the fuel assemblies to provide backup decay heat removal Tuesday, November 18, 2008 Page 181 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 91 A General Discussion SFP Boron should be >2700 and level should be >23 feet. Both specs are not met. Action for boron out is to stop moving all fuel assemblies in the spent fuel pool and initiate action to get it back. Action for level out is to stop moving irradiated fuel. Correct answer states stop moving fuel assemblies.
This encompasses both irradiated and none irradiated.
This encompasses both irradiated and none irradiated.
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Distractors B and D do not appear to be credible.
Distractors B and D do not appear to be credible.
NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 182 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 92 c QuestionBank  
NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 182 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 92 c QuestionBank  
# IKA system IKA number I 598 I syson I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/43.3/  
# IKA system IKA number I 598 I syson I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/43.3/
: 45. 13) DDetector failure .................................................
: 45. 13) DDetector failure .................................................
Given the following:
Given the following:
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* The crew has entered EP/21A15000/E-3 (Steam Generator Tube Rupture) due to 2EMF-10 (Steamline A) Trip 1 light being LIT.
* The crew has entered EP/21A15000/E-3 (Steam Generator Tube Rupture) due to 2EMF-10 (Steamline A) Trip 1 light being LIT.
* The BOP informs the OSM that 2RAD-3, F/3 (CABINET TROUBLE) is LIT
* The BOP informs the OSM that 2RAD-3, F/3 (CABINET TROUBLE) is LIT
* The OSM believes the EMF detector may have failed. 1. What method can the crew use to determine the validity of the EMF indication?  
* The OSM believes the EMF detector may have failed. 1. What method can the crew use to determine the validity of the EMF indication?
: 2. Once the indication is determined to be false, which of the following describes the correct procedure transition?
: 2. Once the indication is determined to be false, which of the following describes the correct procedure transition?
A. 1. Verify Trip 1 alarm on adjacent steamline EMF (2EMF-13 (Steamline 0)) is DARK 2. Transition to EP/2/A/5000/ES-0.0 (Rediagnosis)
A. 1. Verify Trip 1 alarm on adjacent steamline EMF (2EMF-13 (Steamline 0)) is DARK 2. Transition to EP/2/A/5000/ES-0.0 (Rediagnosis)
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* Reactor trip breakers are tagged open.
* Reactor trip breakers are tagged open.
* Maintenance determines that the MOV test data from the outage indicates that the torque switches for 1 NO-658 (NO TRAIN 18 HOT LEG INJ ISOL) have been set too low.
* Maintenance determines that the MOV test data from the outage indicates that the torque switches for 1 NO-658 (NO TRAIN 18 HOT LEG INJ ISOL) have been set too low.
* The SWM requests OSM approval to tag closed 1 NO-658 for repairs. Which one of the following statements correctly describes the operating restrictions and implications of tagging closed 1 NO-658? A. 1 NO-658 may be tagged closed for 72 hours if the steam generator in the running NC loop is operable.  
* The SWM requests OSM approval to tag closed 1 NO-658 for repairs. Which one of the following statements correctly describes the operating restrictions and implications of tagging closed 1 NO-658? A. 1 NO-658 may be tagged closed for 72 hours if the steam generator in the running NC loop is operable.
: 8. 1 NO-658 may not be tagged closed because this would make both trains of NO inoperable.
: 8. 1 NO-658 may not be tagged closed because this would make both trains of NO inoperable.
C. 1 NO-658 may not be tagged closed unless two NCPs are running with operable steam generators.
C. 1 NO-658 may not be tagged closed unless two NCPs are running with operable steam generators.
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* The crew has transitioned to EP/21A15000/ES-1.2 (Post LOCA Cool down and De pressu rizatio n)
* The crew has transitioned to EP/21A15000/ES-1.2 (Post LOCA Cool down and De pressu rizatio n)
* Containment pressure is 4.5 psig and decreasing slowly
* Containment pressure is 4.5 psig and decreasing slowly
* Present pressure indications are: o PZR PRESS Channel 1 -1815 psig o PZR PRESS Channel 2 -1795 psig o PZR PRESS Channel 3 -Failed High o PZR PRESS Channel 4 -Failed High o LOOP B HOT LEG W IR PRESS -1920 psig o LOOP C HOT LEG W/R PRESS -Failed Low 1. Which instrument(s) above will provide the most reliable indication of current primary system pressure?  
* Present pressure indications are: o PZR PRESS Channel 1 -1815 psig o PZR PRESS Channel 2 -1795 psig o PZR PRESS Channel 3 -Failed High o PZR PRESS Channel 4 -Failed High o LOOP B HOT LEG W IR PRESS -1920 psig o LOOP C HOT LEG W/R PRESS -Failed Low 1. Which instrument(s) above will provide the most reliable indication of current primary system pressure?
: 2. Based on the indications provided, is the LCO for Technical Specification 3.3.3 (PAM Instrumentation) met? A. 1. LOOP B HOT LEG W/R PRESS 2. No B. 1. PZR PRESS Channels 1 and 2 2. No C. 1. LOOP B HOT LEG W/R PRESS 2. Yes D. 1. PZR PRESS Channels 1 and 2 2. Yes Tuesday, November 18, 2008 Page 199 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 100 A General Discussion Per OMP 1-7, PAM isntruments provide the most relianble indication In ACC conditions.
: 2. Based on the indications provided, is the LCO for Technical Specification 3.3.3 (PAM Instrumentation) met? A. 1. LOOP B HOT LEG W/R PRESS 2. No B. 1. PZR PRESS Channels 1 and 2 2. No C. 1. LOOP B HOT LEG W/R PRESS 2. Yes D. 1. PZR PRESS Channels 1 and 2 2. Yes Tuesday, November 18, 2008 Page 199 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 100 A General Discussion Per OMP 1-7, PAM isntruments provide the most relianble indication In ACC conditions.
The basis of PAM instruments is for operator diagnosis of primary system parameters.
The basis of PAM instruments is for operator diagnosis of primary system parameters.

Revision as of 04:17, 12 July 2019

301 Combined Final Ro/Sro Written Examination with Ka'S Answers and References
ML090230038
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 12/10/2008
From:
- No Known Affiliation
To:
NRC/RGN-II
References
50-413/08-301, 50-414/08-301
Download: ML090230038 (202)
v • d • e


Text

Final Submittal (Blue Paper) CA=fmLeA ZC08 -301 Wr:tkA

\2../ /0 COMBINED RO/SRO WRITTEN EXAM WITH KAS, ANSWERS, REFERENCES, FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 1 QuestionBank

  1. IKA system IKA number I 507 I EPE007 I EK2.03 I KA desc Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7 / 45.7)DReactor trip status panel ..........................................

Unit 1 is at 100% reactor power. Four hours ago:

  • PZR Level Select Switch was in the 3-2 position
  • PZR level channel 1 failed HIGH
  • All actions required by Technical Specifications were completed to allow continued unit operation.

Following the receipt of several annunciators, the following items are noted:

  • 1 EOC has lost power
  • 1FO-1, B/6 (PZR Hi Level RX Trip) is LIT and RED
  • ORPI indicates control bank position at 215 steps on Bank 0
  • Both RX TRIP BKR 1A and 1 B red lights are LIT. Which one of the following describes:
1. The current condition of the plant and 2. The correct operator action to take for the above evolution?

A. 1. Anticipated Transient Without Scram (ATWS) 2. Manually trip the reactor B. 1. Anticipated Transient Without Scram (ATWS) 2. Perform a shutdown per OP/1/A/61 001003 (Controlling Procedure for Unit Operation)

C. 1. Reactor Protection System (RPS) failure 2. Manually trip the reactor O. 1. Reactor Protection System (RPS) failure 2. Perform a shutdown per OP/1/A/61 001003 (Controlling Procedure for Unit Operation)

Tuesday, November 18, 2008 Page 1 of 200 D FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 1 D General Discussion OMP 1-7 General Statements of Philosophy:

An ATWS (Anticipated Transient Without Scram) is defined in IOCFR50.62 as an anticipated operational occurrence followed by the failure of the reactor trip portion of the protective system. To have an ATWS there must be a transient followed by a failure of the reactor trip breakers.

Instrument failures, by themselves, are not necessarily transients.

For example, if one channel of Pressurizer Pressure was out of service for preventive maintenance (bistable in tripped condition) and another Pressurizer Pressure channel failed (not the controlling channel), a reactor trip signal would be generated.

If the reactor failed to trip, this would be a failure of the reactor trip breakers and the automatic trip features of the reactor protection system and not an ATWS event. (PPRB OPS-9283)

Since this is a transient condition, this would be an ATWS Answer A Discussion iCORRECT Answer B Discussion iFirst part correct Answer C Discussion iSecond part correct Answer D Discussion iBoth parts incorrect psychometric balance Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2006 NRC Q 1 (Bank 607) Developed Development References Student References Provided EPINTR013 0 OPT Approved OMP 1-7 0 OPS Approved TS 3.3.1 NRC Approved QuestionBank

  1. IKA system IKA number I 5071EPE007 IEK2.03 1 KA desc Knowledge of the interrelations between a reactor trip and the following: (CFR 41.7 /45. 7)DReactor trip status panel 401-9 Comments:

007 EK2.03 Borderline KIA match. Did not see where the reactor trip status panel was addressed.

Distractors B and C are not plausible.

If an A TWS had occurred the reactor would be tripped. If a failure of the Reactor Protection system occurred, and normal shutdown would be conducted.

Modified Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 2 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 2 QuestionBank

  1. IKA system IKA number I 508 I EPE009 I EA2.10 I KA desc Ability to determine or interpret the following as they apply to a small break: LOCA: (CFR 43.5 / 45. 13)DAirborne activity .................................................

Initial Conditions

  • Unit 1 was in Mode 3 cooling down for a refueling outage per OP/1/A/61 00/002 (Controlling Procedure for Unit Shutdown)
  • NC pressure is 1S00 psig
  • NC temperature is SOO°F and slowly decreasing Operators note the following:
  • 1RAD-1, B/3 "1EMF41 AUX BLDG VENT HI RAD" -LIT
  • 1AD-13, A/1 "ND & NS ROOMS SUMP LEVEL EMERG HI"-LIT * "SAFETY INJECTION ACTUATED" status light -LIT Which one of the following states the correct procedure flowpath that will address this event? A. AP/1/A/SSOO/027 (Shutdown LOCA) AP/1/A/SSOO/019 (Loss of Residual Heat Removal System) B. AP/1/A/SSOO/027 (Shutdown LOCA) AP/1/A/SSOO/010 (Reactor Coolant Leak) C. EP/1/A/SOOO/E-0 (Reactor Trip or Safety Injection)

EP/1/A/SOOO/E-1 (Loss of Reactor or Secondary Coolant) EP/1/A/SOOO/ES-1.2 (Post LOCA Cooldown and Depressurization) . D.* EP/1/A/SOOO/E-0 (Reactor Trip or Safety Injection)

EP/1/A/SOOO/E-1 (Loss of Reactor or Secondary Coolant) EP/1/A/SOOO/ECA-1.2 (LOCA Outside Containment)

Tuesday, November 18, 2008 Page 3 of 200 D FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 2 D General Discussion The EMF in alann is the key to a LOCA outside containment with the sump level providing confinnation.

Choices Band C are for LOCAs IN containment.

Choices A and B are for shutdown conditions as stated in AF/27 which do not apply to this situation based on the stem. Answer A Discussion He may interpret "shutdown" in the title as Mode 3. This is a common point of confusion.

When AF/27 is used, it does transition for this situation to AF/19 Answer B Discussion There is a transition to AFIlO, however he should realize it's a LOCA outside containment based on EMF-41 and NDINS sump roOm. Answer C Discussion This is a valid EP flowpath for a leak in the NCS. But not for a LOCA outside containment.

Answer D Discussion iCORRECT Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References OP/l/B/61001010X AF/1/Al55001027 EP/1/ Al5000/E-l EP/1/Al5000/ECA-1.2 QuestionBank

  1. IKA system IKA number I 50SiEPE009 i EA2.lO I KA desc Question Source Student References Provided Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 I 45.13}DAirbome activity 401-9 Comments:

009EA2.1 Question appears to match KIA. Distractors A and B may not be plausible.

Is there any time that Safety Injection Actuated light is lit that the operators would not go to E-O besides a loss of all AC? NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 4 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 3 D QuestionBank

  1. IKA system IKA number I 509 I EPEOll I 2.4.30 I KA desc EPE011 GENERICDKnowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 /43.5 /45.11) Given the following events:
  • A Large Break LOCA has occurred on Unit 2
  • All equipment functioned as designed
  • The OSM has declared an Alert
  • A signed Emergency Notification Sheet has been handed to you for transmittal Which of the following is a complete list of agencies required to be contacted within 15 minutes of the declaration of the Alert? A. State and county warning points and the NRC Operations Center B. County warning points and NRC Operations Center C. State warning points and NRC Operations Center D. State and county warning points Tuesday, November 18, 2008 Page 50(200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 3 D General Discussion 15 minute notifications do not include NRC, but are the state and county warning points. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2005 NRC Q75 (Bank 479) Developed Development References Student References Provided RP/O/A/5000/006A rev30 D OPT Approved RP/O/A/5000/001 rev 18 D OPS Approved NRC Approved QuestionBank
  1. IKA system IKA number I 5091EPEOll 1 2.4.30 1 KA desc EPEO 11 GENERlCDKnowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 I 43.5 I 45.11) 401*9 Comments:

401*9 Comments RESPONSE 0IlEG2.4.30 SAT BANK -2005 NRC exam. Tuesday, November 18, 2008 Page 6 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 4 A QuestionBank

  1. IKA system IKA number I 510 I APE022 I AKl.02 I KA desc Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8/41.10/

45.3)DRelationship of charging flow to pressure differential between charging and RCS .................................

Given the following initial conditions:

  • 1 NV-294 (NV Pmps A&B Disch Flow Ctrl) in MANUAL
  • 1NV-309 (Seal Water Injection Flow) in MANUAL
  • pressurizer pressure is 2235 psig
  • total seal water flow is 32 gpm
  • charging line flow is 89 gpm If pressurizer pressure is increased to 2300 psig, which one of the following sets of system parameter changes is correct? A. Charging line flow decreases and total seal water flow decreases B. Charging line flow decreases and total seal water flow remains the same C. Charging pump discharge header pressure increases and total seal water flow increases D. Charging pump discharge header pressure increases and total seal water flow remains the same Tuesday, November 18, 2008 Page 7 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 4 A General Discussion Centrifugal pump laws require that the discharge header pressure increases and flow decreases as system pressure increases.

Therefore charging line flow and total seal flow will decrease while charging line discharge pressure increases. . Answer A Discussion ICORRECT Answer B Discussion Incorrect:

total seal flow decreases.

May think higher discharge pressure = more seal flow.Incorrect:

total seal flow decreases because INV-309 is in manual. Answer C Discussion Incorrect:

total seal flow decreases.

May think higher discharge pressure = more seal flow. Answer D Discussion Incorrect:

total seal water flow decreases because INV-309 is in manual. Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2005 NRC Q6 (Bank 410) Developed Development References Student References Provided THFFF 12 thru THFFF15 D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 510lAPE022 IAKl.02 I KA desc Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8 /41.10 / 45.3)DRelationship of charging flow to pressure differential between charging and RCS ................................ . 401-9 Comments:

401-9 Comments RESPONSE 022AKl.02 Question kind of matches KIA. SAT. This question could be easily modified.

BANK -2005 NRC exam. Tuesday, November 18, 2008 Page 8 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 5 Jr QuestionBank

  1. IKA system IKA number I Quas.':'W a-511 I APE025 I 2.4.30 I KAdesc APE025 GENERIC 0 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.1 0 /43.5 /45.11) . Unit 1 was in Mode 5 preparing to enter Mode 6. Given the following:
  • Both trains of ND have been lost.
  • The crew entered AP/1/A/5500/019 (Loss of Residual Heat Removal System) but actions to restore cooling have failed.

Per the requirements of OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines):

1. Is notification to the NRC Operations Center required prior to taking the action? 2. How many additional SROs (if any) are required to agree with the OSM prior to the action being taken? A. 1. Yes 2. None B. 1. Yes 2. One additional SRO C. 1. No 2. None D. 1. No 2. One additional SRO Tuesday, November 18, 2008 Page 9 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination General Discussion

--QUESTION 5 t--50.72 "The licensee shall activate the Emergency Response Data System (ERDS)4 as soon as possible but not later than one hour after declaring an Emergency Class of alert, site area emergency, or general emergency".

OMP 1-7 3. The licensee shall notify the NRC Operations Center by ENS telephone of emergency circumstances requiring the licensee to take any protective action that departs from a license condition or technical specification as permitted by the preceding paragraphs.

When time permits, the notification must be made before the protective action is taken; otherwise, the notification must be made as soon as possible thereafter.

The Commission may require written statements from a licensee concerning its action. Also, the licensee should notify the Resident NRC Inspector as soon as practical.

Per 10cfr5054x, only one SRO is required to make the determination and take action per the CFR. OMP 1-7 says for situations not covered by procedure, 2 are required.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided OMP 1-7 D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA_number I 5111APE025 12.4.301 KA desc APE025 GENERIC o Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.1 0 / 43.5 / 45.11) 401-9 Comments:

025AG2.4.30 Question appears to match KIA. I think this was also on the 2007 exam will check to ensure. OMP 1-7 states two are required without a procedure.

This action will be outside the procedure, therefore someone could argue D is also correct (more conservative.

NEW? Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 10 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 6 A QuestionBank

  1. IKA system IKA number I 512 I APE026 I AA2.03 I KA desc Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 / 45.13)DThe valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition

..................

Unit 1 was operating at 100% with "A" Train KC in service. Given the following:

  • An 86N relay actuated on 1 ETB two minutes ago
  • A major KC system piping leak has occurred in the Auxiliary Building non-essential header
  • 1AD-10, Al1 "KC SURGE TANKA LO-LO LEVEL" -LIT
  • 1AD-10, Al2 "KC SURGE TANK B LO-LO LEVEL" -LIT
  • The crew has entered AP/1/A155001021 (Loss Of Component Cooling) Assuming all automatic actions have occurred, which one of the following correctly lists the major KC headers that are currently being cooled? A. KC Train A essential header only B. KC Train A essential header and the Reactor Building non-essential header C. KC Train A essential header and KC Train B essential header D. KC Train A essential header, KC Train B essential header and the Reactor Building non-essential header Tuesday, November 18, 2008 Page 11 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 6 A General Discussion An 86N locks out the essential bus, therefore, B train KC pumps are off and the B train header isolation vlaves will not close. The Reactor building header shares common piping with the AB non-ess header. Both non-essential headers are isolated based on low KC surge tank levels due to the piping rupture. Answer A Discussion Answer B Discussion If student thinks that the Rx Building header is not isolated since the leak is on the AB header. Although its diffvalves for purposes ofleak isoaltion they are identical.

Answer C Discussion IIf student thinks the DIG re-energizes 1 ETB Answer D Discussion IBoth B and C above for psychometric bal!p1ce.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Ii'] Developed Development References Student References Provided AP/1/A/5500/02l D OPT Approved PSSKC D OPS Approved Ii'] NRC Approved QuestionBank

  1. IKA system IKA number I 512IAPE026 1 AA2*03 I KA desc Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 I 45.13)DThe valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition

................. . 401*9 Comments:

026AA2.03 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 12 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 7 QuestionBank

  1. IKA system IKA number I 513 I APE027 I AAl.04 I KA desc Ability to operate and / or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7/45.5

/ 45.6}DPressure recovery, using emergency-only heaters .....................

Given the following:

  • The SSF has been manned due to a fire in the cable spreading room.
  • During the course of SSF operations a head vent stuck in the open position for a short period of time and then reclosed.
  • You have been directed to increase NC pressure using heaters. 1. Why is pressure recovery slower from the SSF than from the Control Room? 2. How are the heaters available from the SSF secured should Pzr level drop below 17%? A. 1. Only a portion of the D heaters are available from the SSF 2. Automatically B. 1. Only a portion of the D heaters are available from the SSF 2. Manually C. 1. Only A and B heaters are available from the SSF 2. Automatically D. 1. Only A and B heaters are available from the SSF 2. Manually Tuesday, November 18, 2008 Page 13 of 200 B FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 7 B General Discussion Only a portion ofD heaters are available from the SSF. The OP for SSF operations has numerous cautions about having to manually sercure those heaters should leve drop below 17%. A&B heaters are available from the ASP. Answer A Discussion lfirst part is correct. Answer B Discussion ICORRECT Answer C Discussion The A and B heaters would automatically secure but are available from the ASP not the SSF Answer D Discussion Isecond part is correct Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Memory NEW Development References OP/O/B/61 001013 PSILE QuestionBank
  1. IKA system IKA number I 513IAPE027 IAAl.04 I KA desc Question Source Student References Provided Ability to operate and I or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.7 145.5 I 45.6)DPressure recovery, using emergency-only heaters .................... . 401*9 Comments:

401*9 Comments RESPONSE 027AAl.04 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 Page 14 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 8 D QuestionBank

  1. IKA system IKA number I 514 I EPE029 I 2.4.34 I KA desc EPE029 GENERICDKnowledge ofRO tasks perfonned outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10 /43.5 /45.13) Which one of the following is a complete list of breakers directed to be opened per EP/1/A/SOOO/FR-S.1 (Response to Nuclear Power Generation/ATWS) to trip the reactor locally? 1. Reactor Trip Breakers RTA and RTB 2. Reactor Trip Bypass Breakers BY A and BYB 3. CRD/MG "Motor" Breakers 4. CRD/MG "Generator" Breakers A. 1 and 2 only B. 1,2, and 3 only C. 1,2, and 4 only D. 1, 2, 3, and 4 Tuesday, November 18, 2008 Page 15 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 8 General Discussion Nonnally the OSM will directed the non affected Units BOP to go open these breakers to minimize the time the Reactor stays critical.

RO's know it takes only opening one breaker to trip the reactor. Answer A Discussion Incorrect:

EP/1IA/500/FR-S.I requires opening all the breakers.

needs to be open to trip the reactor. Answer B Discussion Incorrect:

EP/1/A/500IFR-S.l requires opening all the breakers.

verify that Reactor Trip breakers and Reactor Trip Bypass Breakers are opened. Answer C Discussion Plausible:

Students knows only one breaker Plausible:

Immediate actions ofEP/1IA/5000/E-0 Incorrect:

EP/1IA/500/FR-S.l requires opening all the breakers.

Plausible:

If opening the Reactor Trip and Bypass reakers doesn't trip the Reactor then opening the MG set breakers will cause the rods to fall. Answer D Discussion ICorrect Job Level Cognitive Level Question Type RO Developed D OPT Approved D OPS Approved NRC Approved Memory NEW Development References FR-S.I QuestionBank

  1. IKA system IKA number I 514\EPE029

\2.4.34\ KA desc Question Source Student References Provided EPE029 GENERICDKnowledge ofRO tasks perfonned outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10 /43.5/45.13) 401*9 Comments:

029EG2.4.34 Question appears to match the KIA. Question needs some enhancements.

The operator need only know that the motor generator out put breaker needs to be opened and D is the answer. Change the distractors to be 1 and 2 only, 1,2, and 3 only 1, 2, and 4 only and 1, 2, 3, and 4. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 16 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 9 QuestionBank

  1. IKA system IKA number I 515 I EPE038 I EKl.02 I KA desc Knowledge of the operational implications of the following concepts as they apply to the SGTR: (CFR 41.8/41.10/

45.3)DLeakrate vs. pressure drop ........................................

Given the following:

  • Unit 1 and 2 are operating at 100%
  • The crews are responding per EP/1 (2)IAl5000/E-3 (Steam Generator Tube Rupture).

preparing to perform the initial reactor coolant system cooldown to the required core exit thermocouple temperature using steam dumps. Based on the differences between Unit 1 and Unit 2 steam generator design: 1. Which unit would have a lower primary system equilibrium pressure?

2. Which unit will have a faster cooldown rate? (Assume identical cores and steam dump performance.)

A. Unit 1 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate. B. Unit 1 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate. c. Unit 2 would have a lower equilibrium pressure and Unit 1 would have a faster cooldown rate. D. Unit 2 would have a lower equilibrium pressure and Unit 2 would have a faster cooldown rate. Tuesday, November 18, 2008 Page 17 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 9 General Discussion Unit 1 has smaller tubes and larger surface area, therefore the leakage would be less on Unit 1 causing Unit 2 to have a larger pressure drop to equilibrium and assuming dumps are fully opened for the initial NC cooldown, Unit 1 would cooldown faster. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Cognitive Level QuestionType Comprehension BANK Developed Development References STMSGlO OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system 515 EPE038 KA desc IKA number I IEKl.02 I Question Source 2005 NRC Q69 (Bank 473) Student References Provided Knowledge of the operational implications of the following concepts as they apply to the SGTR: (CFR 41.8/41.10/

45.3)DLeak rate vs. pressure drop ........................................

401-9 Comments:

038EKl.02 Question kind of matches KIA. BANK -2005 NRC exam Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 18 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 10 B QuestionBank

  1. IKA system IKA number I 516 I APE057 I AA2.13 I KA desc Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5 / 45.13)OVCT level and pressure indicators and recorders

......................

Unit 1 is operating at 100%. 1 ERPA is lost. What effect does this have on VCT auto makeup capability and VCT level indication in the control room? Auto Makeup Level Indication A. Available Available B. Unavailable Available C. Available Unavailable D. Unavailable Unavailable Tuesday, November 18, 2008 Page 19 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 10 General Discussion Vital has no effect on level indication.

Lost ofERP A will cause the Rx M/U pumps to not start in auto or manual. This makes auto makeup be lost. Answer A Discussion Incorrect for makeup but correct for indication Answer B Discussion ICORRECT Answer C Discussion lIn correct for makeup and for indication.

Answer D Discussion . Correct for makeup but incorrect for indication.

Job Level Cognitive Level QuestionType RO Memory NEW Developed Development References D OPT Approved D OPS Approved NRC Approved AP/11 Al5500/029 QuestionBank

  1. IKA_system IKA_number I 5161APE057 IAA2.13 I KA desc Question Source Student References Provided Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: (CFR: 43.5 I 45.13)OVCT level and pressure indicators and recorders

..................... . 401-9 Comments:

401-9 Comments RESPONSE 057AA2.13 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 Page 20 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 11 c QuestionBank

  1. IKA system IKA number I 517 I APE058 I AA1.02 J KA desc Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7/45.5

/ 45.6)DStatic inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector .............................

Given the following:

  • 1ERPD has been de-energized due to a blown fuse on inverter 1 EID.
  • The crew has implemented AP/1/A155001029 (Loss of Vital or Aux Control Power).
  • The fuse has been replaced and the CRS wishes to re-energize 1 ERPD from 1EID. Per OP/1/A/63501008 (125VDC/120VAC Vital Instrument and Control Power System), which one of the following correctly states the minimum acceptable wait time prior to inverter restart and the sequence for operation of inverter 1 EID DC input breaker and AC output breaker? A. 1. 5 seconds 2. Close the DC input breaker and then close the AC output breaker B. 1. 5 seconds 2. Close the AC output breaker and then close the DC input breaker C. 1. 60 seconds 2. Close the DC input breaker and then close the AC output breaker D. 1. 60 seconds 2. Close the AC output breaker and then close the DC input breaker Tuesday, November 18, 2008 Page 21 of200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 11 c General Discussion Per OP L&P 60 sec wait must occur. 5 seconds is the requried precharge time: Answer A Discussion ITime is incorrect.

Answer B Discussion IBoth time and order are incorrect.

Answer C Discussion Icorrect Answer D Discussion IThe order of the AC and DC breakers are reversed Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided EPL D OPT Approved AP/1/AJ5500/029 D OPS Approved OP/1/AJ6350/008 NRC Approved QuestionBank

  1. IKA system IKA number I 5171APE058 IAA1.02 I KA desc Ability to operate and / or monitor the following as they apply to the Loss of DC Power: (CFR 41.7/45.5/

45.6)DStatic inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector ............................ . 401-9 Comments:

058AA1.02 Question appears to match KIA. SAT (Is the time limit in accordance with a procedure?

If so, this should be stated). NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 22 of 200 I FOR REVIEW ONLY -DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 12 QuestionBank

  1. IKA system IKA number I 518 I APE062 I AK3.03 I KA desc Knowledge of the reasons for the following responses as they apply to the Loss ofNuc1ear Service Water: (CFR 41.4,41.8

/45.7 )DGuidance actions contained in EOP for Loss of nuclear service water .... Both units were at 100% with 2A RN Pump in service when the following annunciators were received:

  • 1AD-12, E/2 "RN PIT A SWAP TO SNSWP" -LIT
  • 2AD-12, E/2 "RN PIT A SWAP TO SNSWP" -LIT
  • 1AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL -LO" -LIT
  • 2AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL -LO" -LIT What is the minimum time the crew must wait following receipt of these annunciators prior to operating RN equipment per AP/0IN55001020 (Loss of Nuclear Service Water) and what is the reason for that time delay? A. 2 minutes; To allow sufficient time for all components to respond and allows the operator an opportunity to verify the signal is valid prior to any system realignments.

B. 2 minutes; To prevent an automatic swap to the pond if RN pit level can be restored within 2 minutes. C. 5 minutes; To allow sufficient time for all components to respond and allows the operator an opportunity to verify the signal is valid prior to any system realignments.

D. 5 minutes; To prevent an automatic swap to the pond if RN pit level can be restored within 5 minutes. Tuesday, November 18, 2008 Page 23 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 12 General Discussion AP/20 states that valves and pumps cannot be manipualted for 2 minutes following the autostart on pit level. (5 minutes is the time for the YV swap.) The purpose of the 2 minute wait is to allow components to reposition and for the operator to determine if the signal was valid prior to restoring.

Answer A Discussion ICORRECT Answer B Discussion ICorrect time, wrong reason Answer C Discussion IWrong time, correct reason Answer D Discussion iBoth incorrect

-for psychoimetric balance Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References AP/20 RNlesson QuestionBank

  1. IKA system IKA number I 518iAPE062 i AIG.03 i KA desc Question Source Student References Provided Knowledge of the reasons for the following responses as they apply to the Loss ofNuc1ear Service Water: (CFR 41.4,41.8 145.7 )DGuidance actions contained in EOP for Loss ofnuc1ear service water .... 401*9 Comments:

062AIG.03 Question does not meet KIA. The KIA asks for reasons for the following responses

... The question as written does not address any reasons. Add reasons for actions to make question SAT. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 24 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 13 B QuestionBank

  1. IKA system IKA number I 519 I APE065 I AK3.03 I KA desc Knowledge of the reasons for the following responses as they apply to the Loss ofInstrument Air: (CFR 41.5,41.10/45.6/
45. 13) o Knowing effects on plant operation of isolating certain equipment from instrument air .....................................

Given the following:

  • One RL turnaround valve is manually pinned in place for mantenance
  • The crew has entered AP/OIAl55001022 (Loss of Instrument Air)
  • Operators have determined that the leak can be isolated but doing so will result in all RL turnaround valves losing VI.
  • The CRS has directed that the leak be isolated . . Which one of the following correctly states the effect that this will have on the RL turnaround valves and the equipment cooled by RL. A. The unpinned RL turnaround valves will fail open resulting in more flow to the components supplied by RL. B. The unpinned RL turnaround valves will fail closed resulting in more flow to the components supplied by RL. C. The unpinned RL turnaround valves will fail open resulting in less flow to the components supplied by RL. D. The unpinned RL turnaround valves will fail closed resulting in less flow to the components supplied by RL. Tuesday, November 18, 2008 Page 25 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 13 B General Discussion The RL turnaround valves basically act as a false load to maintain header pressure.

The valves fail closed which cause header pressure to increase and forces more flow through the other components.

This is counterintuitive.

Answer A Discussion the valves fail closed. But logic would say that valves failing open woud result in > flow but not the case due to system design. Answer B Discussion ICORRECT Answer C Discussion ITrue if the valves DID fail open Answer D Discussion fail in right direction but the effect is reversed.

Job Level Cognitive Level QuestionType RO Comprehension NEW Developed Development References D OPT Approved D OPS Approved NRC Approved RL QuestionBank

  1. IKAsystem IKA number I 5191APE065 IAIG.03 I KA desc Question Source Student References Provided Knowledge of the reasons for the following responses as they apply to the Loss ofInstrument Air: (CFR 41.5,41.1 0 / 45.6 / 45. 13) o Knowing effects on plant operation of isolating certain equipment from instrument air .................................... . 401-9 Comments:

065AIG.03 Question appears to match KiA. I assume the crew entered AP /0/ Al5500/022 due to an air leak? You might need to say this. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 26 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 14 D QuestionBank

  1. [KA system [KA number I 520 I APE077 I AA1.01 I KA desc Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8 )DGrid frequency and voltage .........................................................

Given the following:

  • Unit 1 is at 100% power with power factor at 0.99 lagging.
  • Operators are controlling power factor in manual due to the auto voltage regulator not controlling properly.
  • A major grid disturbance causes power factor to increase to slightly leading. 1. Which button on the voltage regulator is operated to bring power factor back to its original value? 2. What part of the generator is susceptible to overheating should power factor be erroneously adjusted to 0.8 lagging? Reference provided A. 1. The "LOWER" button 2. The generator armature core end B. 1. The "RAISE" button 2. The generator armature core end C. 1. The "LOWER" button 2. The generator field D. 1. The "RAISE" button 2. The generator field Tuesday, November 18, 2008 Page 27 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 14 General Discussion The RAISE button will cause power factor to decrease froma leading value to a lagging value. If the generator voltage is adjusted to severley lagging (.8) then it will be past the AB line on the Generator capability curve and field heating is a concern. Answer A Discussion I.Both parts wrong, psychometric balance. Answer B Discussion Wwrong gneerator component.

This would be ifPF was severely LEADING. Answer C Discussion LOWER will cause PF to go more lagging but lower seems logical, Correct generator aea Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References Generator Capability Curve (DataBook Curve 43) RL QuestionBank

  1. IKA system IKA number I 5201APE077 IAA1.01 I KA desc Question Source Student References Provided Databook Figure 43 (Generator Capability Curve) Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 41.10 145.5, 45.7, and 45.8 )DGrid frequency and voltage ........................................................ . 401-9 Comments:

401-9 Comments RESPONSE 077 AAI.O 1 Question appears to match K/ A. This may be considered a direct look up. I will have another examiner review and comment. NEW Tuesday, November 18, 2008 Page 28 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 15 D QuestionBank

  1. IKA system IKA_number J 521 I WE04 I EK2.2 I KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the following: (CFR: 41.7 / 45.7)DFaCility*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.

Unit 1 was operating at 100%. Given the following events and conditions:

  • 0200 -reactor tripped due to a LOCA outside containment
  • 0210 -crew enters ECA-1.2, (LOCA Outside Containment)
  • 0220 -crew enters ECA-1.1, (Loss of Emergency Coolant Recirc)
  • 0240 -The crew is at the step in ECA-1.1 to determine NC subcooling
  • Current conditions:

o NCS pressure is 1100 psig o 1 B NC pump running o 1A, 1C, and 1D NC pumps secured o Reactor Vessel DIP is 20% o 1 NI pump running, indicating 220 gpm o 1 NV pump running, indicating 385 gpm o Both ND pumps off o No NS pumps running o Subcooling is 35°F Which one of the following statements correctly describes the minimum required flow and which pump can be secured? Reference provided A. 210 gpm, stop the running NV pump. B. 210 gpm, stop the running NI pump. C. 410 gpm, stop the running NI pump. D. 410 gpm, neither pump may be secured at this time. Tuesday, November 18, 2008 Page 29 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 15 D General Discussion Bank Question:

912.1 Time after trip is 40 minutes, graph starts at 10 minutes, flow required is 408 gpm Answer A Discussion Incorrect:

required flow is 408 gpm Plausible:

candidate misses the fact that the graph starts at 10 minutes; this is the 50 minute number Answer B Discussion Correct: required flow is 408 gpm, the NY pump is providing 410 gpm, and the NI pump may be stopped. Answer C Discussion Incorrect:

required flow is 408 gpm Plausible:

candidate uses 30 minutes to determine required flow (time since diagnosis ofLOCA outside containment)

Answer D Discussion Incorrect:

required flow is 408 gpm Plausible:

candidate uses 20 minutes to determine required flow (time since procedure entry) Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2004 NRC Q26 (Bank 326) Developed Development References Student References Provided D OPT Approved D OPS Approved NRC Approved Lesson Plan Objective:

EP-EP2 SEQ 29

References:

1. ECA-1.1 step 19 and Encl 5 -PROVIDED QuestionBank
  1. IKA system IKA number I 521lWE04 IEKl.2 I KA desc Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

EP/1/A/5000IECA-1.1 (Step 19) EP/1/A/5000IECA-1.1 (Enclosure

5) (CFR: 41.7 /45. 7)DFacility*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.

401*9 Comments:

W1E04EKl.2 Question appears to match KIA. Modified from 2004 NRC exam. SAT Modified.

Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 30 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 16 D QuestionBank

  1. IKA system IKA number I 522 I WE05 I EK3.1 I KA desc Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) (CFR: 41.5 / 41.1 0, 45.6, 45.13) 0 Facility operating characteristics during transient conditions, including 0 coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

A feedwater transient resulted in a reactor trip and the operating crew entered EP/1/N5000/FR-H.1 (Response to Loss of Secondary Heat Sink) when all Auxiliary Feedwater flow was lost. Given the following:

  • S/G 1A wide range level-31%
  • S/G 1 B wide range level -20%
  • S/G 1 C wide range level -23%
  • S/G 1 D wide range level -28%
  • The BOP has just secured all the NC pumps
  • The OATC notes NC system pressure is increasing
1. Why have NC pumps been secured? 2. Why is NCS pressure increasing?

A. 1. To begin NCS bleed and feed 2. Due to NC temperature increase B. 1. To minimize heat input 2. Due to letdown being secured C. 1. To begin NCS bleed and feed 2. Due to letdown being secured D. '1. To minimize heat input 2. Due to NC temperature.

increase Tuesday, November 18, 2008 Page 31 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 16 D General Discussion There are 2 times NC pumps are secured in HI. First after CA cannot be reinitiated, and second is prior to commencing feed and bleed. S/G wide range levels are above the FIB critera (3<24% WR to establish) unless ACC conditoions (36%). NCPs are secured to minimize heat input causing the water in the S/G to last longer. Pressure inceeases due to the temperature increase prior to the establishment of natural circulation.

Answer A Discussion FIB criteria are not met but would be for ACC numbers (correct part 2) Answer B Discussion Ipart 1 is correct, part 2 is not Answer C Discussion Iboth part incorrect

-psychometric baloance Answer D Discussion ICorrect Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References FR-h.l and basis E-l and basis QuestionBank

  1. IKA system IKA number I 5221WE05 IEIG.l I KA desc Question Source Student References Provided Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) (CFR: 41.5 /41.10, 45.6, 45. 13) o Facility operating characteristics during transient conditions, inc1udingDcoolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

401-9 Comments:

WIE05EK3.l Question matches KIA. SAT NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 32 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 17 c QuestionBank

  1. IKA system IKA number I 523 I WEll I EK2.1 I KA desc Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: (CFR: 4l. 7 / 45.7) 0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

The crew implemented EP/1/A/5000/ECA-1.2 (LOCA Outside Containment), determined the leak can not be isolated and transitioned to EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirculation).

Given the following:

  • FWST level is 55%
  • Subcooling is +rF. What actions, if any, are taken per EP/1/A/5000/ECA-1.1 to ensure the NV pumps maintain adequate suction until cold leg recirculation capability is restored?

A. Terminate safety injection and establish normal charging from the VCT. B. Remove power from 1NI-184B (ND Pump 1B Cont Sump Suct) and 1 NI-185A (ND Pump 1A Cont Sump Suct) C. Use "DEFEAT' buttons for "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A" and "C-LEG RECIR FWST TO CONT SUMP SWAP TRN B" D. None, a swap to the containment sump is blocked when sump level is less than 3.3 feet Tuesday, November 18, 2008 Page 33' of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 17 c General Discussion With FWST level at 55%, an attempt to swap hs not been made (37%). Answer A Discussion This can be done if Subcooling is > 50 degrees. Normal SII termination criteria is subcooling

>0 degrees. Swap to VCT is done in this procedure in that case. Answer B Discussion This is an action that could be done to prevent these valves from opening and is done when it is trying to open them manually.

Answer C Discussion ICORRECT Answer D Discussion The procedure mentions sump levels being both> 2.5 feet and > 3.3 feet in several locations.

The basis is to check for adequate suction source, but there are no actual interlocks to prevent the swapover at 37%. Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References ECA 1.1 QuestionBank

  1. IKA system IKA number I 5231WEll IEK2.1 1 KA desc Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:

Question Source Student References Provided (CFR: 4l.7 / 45.7) o Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

401*9 Comments:

W IE llEK2.IQuestion appears to match KIA. Are the defeat buttons in distractor C labeled correctly?

Otherwise question appears to be SAT. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 34 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 18 c QuestionBank

  1. IKA system IKA number I 524 I WEl2 I EK1.3 I KA desc Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators) (CFR: 41.8 /41.10/ 45.3) o Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

The crew entered EP/1/A/5000/ECA-2.1 (Uncontrolled Depressurization of All Steam Generators) following a unit trip. Given the following:

  • Attempts to close any MSIV using its individual valve control board pushbutton have failed.
  • Safety Injection has not been reset.
  • 1AD-03, E/5 "SM ISOL VLVS NOTFULLY OPEN" -DARK 1. What additional action is taken per this procedure to attempt to close any MSIV? 2. If an MSIV can be closed, what plant parameter is monitored to determine when this procedure can be exited? A. 1. Maintenance is dispatched to isolate air to the MSIVs 2. NC loop T -hots B. 1. Both trains of Main Steam Isolation are manually initiated
2. NC loop T -hots C. 1. Maintenance is dispatched to isolate air to the MSIVs 2. S/G pressure D. 1. Both trains of Main Steam Isolation are manually initiated
2. S/G pressure Tuesday, November 18, 2008 Page 35 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 18 c General Discussion To exit, one steam generator presure must be increasing and SII termination must not be in progress per ECA 2-1. NC Thots are monitored for other reasons in this procedure and they will increase once the MSIV is closed, but Enclsoure one specifies S/G Pressure.

SM ISOL pushbuttons are depressed due to failed auto actions most likely during E-O in this scenario, but ECA-2.1 does not redo this action. It sends MAINT to isolate VI to the valves locally. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Memory NEW Development References EP/lI A/5000/ECA-2.1 QuestionBank

  1. IKA system IKA_number I 5241WE12 IEK1.3 j KA desc Question Source Student References Provided Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators) (CFR: 41.8 I 41.10 I 45.3)DAnnunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

401*9 Comments:

401*9 Comments RESPONSE W1E12EK1.3 Question Kind of matches KIA. Is an annunciator received when the MSIVs are closed or a MSLI is received?

Using one of these indications would match the KIA better. NEW Tuesday, November 18, 2008 Page 36 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D QuestionBank

  1. IKA system IKA number I 525 I APEOOI I AA1.06 I KA desc Ability to operate and / or monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.7/45.5/

45.6)DRod transfer switches .............................................

Given the following events and conditions on Unit 1:

  • NC system is at full temperature and pressure.
  • CRD BANK SELECT switch is in the "SBB" position.
  • The OATC is withdrawing "B" Shutdown Bank control rods with the current bank position at 64 steps withdrawn.
  • The OATC releases the ROD MOTION switch but "B" Shutdown Bank control rods continue to withdraw.
1. What is the current plant Mode of Operation?
2. Which of the following describes the first required action(s) for this situation per AP/1/A155001015 (Rod Control Malfunction)?

A. 1. Mode 2 2. Immediately trip the reactor. B. 1. Mode 3 2. Immediately trip the reactor. C. 1. -Mode 2 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor. D. 1 Mode 3 2. Immediately place CRD BANK SELECT switch IN MANUAL; if rods continue to move then trip the reactor. Tuesday, November 18, 2008 Page 37 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 19 D General Discussion Per IRE lesson: '3.DAllows individual banks to be moved in bank select positions.

No prescribed sequencing exists and Bank Overlap is defeated.'

Immed action for AP/15. Mode 2 occurs when the first CONTROL BANK begins withdrawal.

Plant is currently in Mode 3 Answer A Discussion Iwrong mode, wrong action Answer B Discussion Iwrong action, right mode Answer C Discussion Iright action, wrong mode Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided AP/15 D OPT Approved IRE D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5251APEOOl IAA1.06 I KA desc Ability to operate and lor monitor the following as they apply to the Continuous Rod Withdrawal: (CFR 41.7 I 45.5 i 45.6)DRod transfer switches ............................................ . 401-9 Comments:

OOlAA1.06 Question does not really meet the KIA, however it is a good attempt, and the switch involved does transfer some control of the rods. The stem should state lAW whatever procedure is applicable for example lAW AP-15. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 38 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 QuestionBank

  1. IKA system IKA number I 526 I APE005 I 2.4.6' I KA desc APE005 GENERICDKnowledge ofEOP mitigation strategies. (CFR: 41.10 / 43.5 /45.13) Unit 1 was operating at 100% power with Control Rod Bank D at 216 steps withdrawn on DRPI when an OTDT runback occurred for approximately 30 seconds and cleared. When conditions stabilized, the following indications were noted:
  • Control Rod Bank D demand counters are indicating 190 steps.
  • Control Rod Bank D rod D4 indicates 216 steps withdrawn on DRPI.
  • All other Control Rod Bank D rods indicate 188 steps withdrawn on DRPI. 1. What is the first immediate action of the Abnormal Procedure that will address this issue? 2. What are the modes of applicability for the corresponding Technical Specification?

A. 1. Verify only one rod -MISALIGNED.

2. MODE 1, MODE 2 with keff 1.0 B. 1. Verify only one rod -MISALIGNED.
2. MODE 1, MODE 2 C. 1. Ensure "CRD BANK SELECT" switch -IN MANUAL. 2. MODE 1, MODE 2 with keff 1.0 D. 1. Ensure "CRD BANK SELECT" switch -IN MANUAL. 2. MODE 1, MODE 2 Tuesday, November 18, 2008 Page 39 of 200 B I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 20 B General Discussion One CR is misaligned by >24 asteps. And AP/14 would be appropriate for this situation.

CRD bank select to manual is not an immedaite action but is the next action of this AP. It IS an immediate action of APIl5 for continuous rod movement.

Tech spec 3.1.4 applied for Rod Group alignment Limits. 3.1.6 does not apply because the control rods are above insertion limits. Answer A Discussion Iwrong TS applicability Answer B Discussion ICORRECT Answer C Discussion IBoth wrong (for psychometric balance.)

Answer D Discussion IWrong action Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Memory QuestionBank

  1. KA system 526APE005 KA desc NEW Development References TS 3.1.6 APIl4 AP/15 TS3.1.4 KA number 2.4.6 Question Source Student References Provided APE005 GENERICDKnowledge ofEOP mitigation strategies. (CFR: 41.10 I 43.5 145.13) 401-9 Comments:

005AG2.4.6 Based on a previous discussion AP actions were determined to be acceptable to satisfY this KIA. Is there any occurrence of Mode 2 with Keff2:: 1.0? If not this may not be acceptable.

Will Discuss. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 40 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 21 c QuestionBank

  1. IKA system IKA number I 527 I APE024 I AKl.04 I KA desc Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8/41.10/

45.3}DLow temperature limits for born concentration

....................

Given the following:

  • Unit 1 is in Mode 5
  • BAT temperature is 60° F.
  • FWST temperature is 70° F. Assuming any required pumps are operable, which one of the following correctly states a combination of equipment which will satisfy the requirements of SLC 16.9-7 Boration System Flowpaths

-Shutdown?

A. BAT to NV Pump B. FWST to NI Pump via 2 cold leg lines C. FWST to NV Pump D. FWST to ND Pump via 2 cold leg lines Tuesday, November 18, 2008 Page 410(200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination General Discussion Bat is inoperable due to <65 deg F. FWST is operable.

NI Pump requires 4 flow paths not 2 ND can only be used in Mode 6. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Comprehension NEW Developed Development References TS 3.9.4 0 OPT Approved SLC 16.9-7 0 OPS Approved SLC 16.9-11 NRC Approved QuestionBank

  1. KA system IKA number I 527 APE024 IAKl.04 I KA desc QUESTION 21 Question Source Student References Provided Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8 / 41.1 0 /45.3)DLow temperature limits for born concentration

....................

401-9 Comments:

024AKl.04 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 42 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 22 A QuestionBank

  1. IKA system IKA number I 528 I APE033 I AK1.01 I KA desc Knowledge of the operational implications of the following concepts as they apply to Loss ofIntermediate Range Nuclear Instrumentation:

CFR 41.8/41.10/

45.3) 0 Effects of voltage changes on performance

...........................

Given the following conditions and sequence of events:

  • During the last calibration of N-35, an IAE technician improperly adjusted the compensating voltage to a value slightly lower than required by procedure.
  • N-36 failed 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago, the crew entered AP/1/A155001016 (Malfunction of Nuclear Instrumentation), Case III (Intermediate Range Malfunction).
  • All actions required by AP/1/A155001016 have been completed.
  • A feedwater transient occurs resulting in a reactor trip. How does this adjustment error affect the reading on N-35 and how will this condition affect when the source range instruments automatically energize?

A. N-35 will indicate higher than the actual value. The source ranges instruments will energize at a lower actual neutron flux. B. N-35 will indicate higher than the actual value. The source ranges instruments will energize at the same actual neutron flux. C. N-35 will indicate lower than the actual value. The source ranges instruments will energize at the same actual neutron flux. D. N-35 will indicate lower than the actual value. The source ranges instruments will energize at a higher actual neutron flux. Tuesday, November 18, 2008 Page 43 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 22 A General Discussion 2/2 IR instruments are required to clear P-6 and automatically energize the SR instruments.

Compensating voltage set, too low will cause IR indication to be higher than actual flux level, delaying automatic energizing of the SR. > P-lO removed SR voltage. If this is confuzed and student thinks that <polO will energize SR and with one IR already failed low, then "at the same time" is plausible.

Answer A Discussion Answer B Discussion indication is correct Answer C Discussion IPsychometric balance Answer D Discussion SR will energize at a lower value N35 will indicate higher. This would be corect if voltage was set higher Job Level Cognitive Level Question Type Question Source RO Comprehension NEW Developed Development References Student References Provided AP/1/A/5500/016 D OPT Approved ENB D OPS Approved NRC Approved QuestionBlink

  1. IKA system IKA number I 5281APE033 IAK1.01 I KA desc Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation:

CFR 41.8 141.101 45.3) D Effects of voltage changes on performance

.......................... . 401-9 Comments:

401-9 Comments RESPONSE 033AKl.OI Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 Page 44 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 23 D QuestionBank

  1. IKA system IKA number I 529 I APE037 I AA2.03 I KA desc Ability to detennine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 / 45.13)DThat the expected indication on main steam lines from the S/Gs should show increasing radiation levels ......................

Given the following:

  • Unit 1 is operating with a known 0.6 GPO S/G tube leak
  • 1A CF pump tripped and results in a plant runback.
  • The crew has stabilized the plant at the runback target per AP/1/A155001003 (Load Rejection)
  • The transient has caused the tube leak to increase to 12 GPO. Which one of the following indications will provide the best indication (most sensitive and timely) that the S/G tube leak has increased?

A. Observing 1EMF-26, 27,28 and 29 (Steamline 1A-10) B. Comparing S/G feed flow to steam flow mismatch C. Observing 1 EMF-33 (Condenser Air Ejector Exhaust) O. Observing 1EMF-71, 72,73,74 (S/G A-O leakage) Tuesday, November 18, 2008 Page 45 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 23 D General Discussion Bank Question:

605.1 nonnally, EMF-71-74 are the most sensitive monitors.

But these monitors detect N16 0 radiation that has a high energy (7 MeV) 0 that only is generated when the reactor is operating at power (requires a neutron flux). Answer A Discussion This would be true at low power level or in mode 3 where N16 is not present or at low concentrations Answer B Discussion Incorrect:

Not a sensitive method of comparison

-requires large gpm leak rates before this is noticeable.

Plausible:

This method will show gross SGTRs Answer C Discussion This EMF is not as senstive as the Stm line EMFs, also the Steam line EMF see the radiation first. Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2003 NRC Q32 (Bank 232) Developed Development References Student References Provided SM lesson 0 OPT Approved NSD513 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5291APE037 IAA2.03 I KA desc Ability to detennine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 / 45.13)DThat the expected indication on main steam lines from the S/Gs should show increasing radiation levels ..................... . 401-9 Comments:

037AA2.03 Question appears to match KIA. Need to add a specific power level for the Unit. 60% or so, some one could make the assumption that power had been reduced to a level where the N-16 monitors may not be the first indication.

Otherwise SAT. Modified from a 2003 NRC exam. Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 46 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 24 D QuestionBank

  1. IKA system IKA number I 530 I EPE074 I EA1.0I I KA desc Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41.7/45.5/

45.6)ORCS water inventory

..............................................

S/G depressurization to atmospheric pressure has been performed in EP/1/A/5000/FR-C.1 (Response to Inadequate Core Cooling).

1. What are the NC temperature and RVLlS level limits that allow the crew to transition out of this procedure?
2. Why are these conditions more restrictive than earlier transition conditions?

A. 1. Two NC Thots less than 328 deg F, RVLlS level greater than 41 % 2. To ensure a hard bubble does not block natural circulation flow B. 1. Two NC Thots less than 328 deg F, RVLlS level. greater than 41 % 2. Due to the NC system being depressurized C. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 % 2. To ensure a hard bubble does not block natural circulation flow D. 1. Two NC Thots less than 350 deg F, RVLlS level greater than 61 % 2. Due to the NC system being depressurized Tuesday, November 18, 2008 Page 47 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 24 General Discussion 350 and 61 are correct and NC depressurized is correct. 328 and hard bubble are both from S/G depress for CLA to prevent N2 injection.

41 % is the entry requirement and earlier kickout requirement.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References F-O FR-C.l and basis QuestionBank

  1. IKA system IKA number I 530lEPE074 IEA1.01 I KA desc Question Source Student References Provided Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: (CFR 41. 7 / 45.5 / 45.6)ORCS water inventory 401-9 Comments:

074EA1.01 Question kind of matches KIA. Change #2. to read: Why are these conditions more restrictive than earlier transition conditions Otherwise SAT. (Is this RO knowledge?)

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 48 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 25 QuestionBank

  1. IKA system IKA number I 531 I APE036 I AIG.03 I KA desc Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10

/ 45.6 /45.13)DGuidance contained in EOP for fuel handling incident ..................

Unit 1 was conducting refueling operations in mode 6. Given the following events and conditions:

  • The containment purge (VP) system is in operation in the REFUEL mode.
  • Both trains of SSPS are in "TEST".
  • The refueling crew dropped a fuel assembly into the refueling cavity.
  • The crew has implemented AP/1/Al55001025 (Damaged Spent Fuel). 1. Based on the above conditions, what was the status of the VP system when AP/11A15500/025 was entered? 2. What is the reason for establishing closure prior to VP being secured? A. 1. The VP system was running 2. To prevent an unmonitored release B. 1. The VP system was running 2. To prevent an excessive negative pressure in containment C. 1. The VP system has tripped 2. To prevent an unmonitored release D. 1. The VP system has tripped 2. To prevent an excessive negative pressure in containment Tuesday, November 18,2008 Page 49 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 25 General Discussion TIllS WAS A REPLACEMENT KA EMF39 secures VP using 2 separate signals one thru SSPS (Sh) and one directly from the EMF. With both trains ofSSPS in test, the Sh will not work, however VP will be secured by EMF 39 directly.

The status ofVP is checked per AP25. Answer A Discussion

[correct reason, wrong status Answer B Discussion

[both parts wrong Psychometric balance Answer C Discussion

[CORRECT Answer D Discussion

[wrong reason, corret status Job Level Cognitive Level QuestionType Question Source RO Memory MODIFIED 2004 NRC Q86 (Bank 386) Developed Development References Student References Provided AP/25 0 OPT Approved VQ 0 OPS Approved CNT VP NRC Approved QuestionBank

  1. IKA system IKA number J 531iAPE036 i AK3*03 J KA desc Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: (CFR 41.5,41.10 I 45.6 I 45. 13) DGuidance contained in EOP for fuel handling incident ................. . 401*9 Comments:

036AK3.03 Question does not match KIA. The KIA asks for reasons, none are included in the question.

Modified from 2004 NRC exam. Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 50 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 26 B QuestionBank

  1. IKA system IKA number I 532 I WE03 I EK2.1 I KA desc Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: (CFR: 41.7 / 45.7) 0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Unit 1 was operating at 100% power when a small break LOCA occurred.

Given the following events and conditions:

  • Cooldown and depressurization is in progress in ES-1.2 (Post Cooldown and Depressurization)
  • NC system pressure has stabilized at 410 psig
  • NC temperature has stabilized at 325°F
  • FWST level is 70% and slowly decreasing
  • The operators attempt to place 1A ND train in the RHR mode
  • 1ND-1B and 1 ND-2A (ND Pump 1A Suctfrom Loop B) will not open Which one of the following statements correctly describes why 1 ND-1B and 1 ND-2A will not open? A. ECCS has notbeen reset B. The NC system pressure is too high C. 1 NI-147B (NI Pumps Recirc to FWST Isol) is open D. 1 NI-185A (ND pump 1A Suct from CNMT Sump) is closed Tuesday, November 18, 2008 Page 51 of 200 FOR REVIEW ONLY DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 26 General Discussion IBank Question:

1167 Answer A Discussion Incorrect:

ECCS does not have to be reset for IND-IB and IND 2A to open Plausible:

Resetting ECCS is usually done as an operational matter before starting an ND train in RHR mode. Answer B Discussion Correct: IfNC system pressure is > 385 psig, these valves will not open Answer C Discussion Incorrect:

This is not a valve interlock with IND-IB and IND-2A Plausible:

lNI-147B being open is a valve interlock for ND-28A and NI-136B -if the candidate confuses the valve interlocks.

Answer D Discussion Incorrect:

NI-185A being closed will not prevent IND-lB and IND-2A from opening -the closed position makes up the interlock.

Plausible:

Reverse logic -If lNI-185A were open, it would prevent IND-IB and IND-2A from opening Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2004 NRC Q50 (Bank 350) B Developed Development References Student References Provided PS-ND9 0 OPT Approved NSD3.1.30 0 OPS Approved ND pages 8, 13 NRC Approved QuestionBank

  1. IKA system IKA number I 5321WE03 IEK2.1 I KA desc Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following: (CFR: 41.7 / 45.7) D Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

401-9 Comments:

WE03EK2.1 Question appears to match KiA. Need to add RCS temperature.

Used on the 2004 NRC exam under KiA 005K4.02 BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 52 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 27 B QuestionBank

  1. IKA system IKA number I 533 I WE09 I EK3.3 I KA desc Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations) (CFR: 41.5 /41.10, 45.6, 45. 13)DManipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

Given the following conditions and sequence of events:

  • One hour ago, a fault in the Unit 1 main generator resulted in a complete loss of offsite power.
  • The crew entered EP/1/A/5000/ES-0.2 (Natural Circulation Cooldown).
  • The OSM determined that a transition to EP/1/A/5000/ES-0.3 (Natural Circulation Cooldown With Steam Void in Vessel) was required.
  • The crew has transitioned to ES-0.3 and is preparing to depressurize the NC system. 1. What condition would require stopping the depressurization of the NC system during this cooldown?
2. What is the basis for stopping the depressurization?

A. 1. PZR Level greater than 70% 2. To prevent loss of natural circulation B. 1. RVLlS level less than 73% 2. To prevent loss of natural circulation C. 1. PZR Level greater than 70% 2. To ensure normal pressurizer pressure control response D. 1. RVLlS level less than 73% 2. To ensure normal pressurizer pressure control response Tuesday, November 18, 2008 Page 53 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 27 B General Discussion 70% is the PZR Hi Level Alarm. The actual value is 90%. Thee reason is to prevent a los of natural circulation.

Answer A Discussion IWrong level right reason Answer B Discussion ICORRECT Answer C Discussion IBoth Wrong Answer D Discussion Iwrong reason Job Level Cognitive Level Question Type Question Source RO Comprehension MODIFIED 2006R NRC Q65 (Bank 142) Developed Development References Student ReferenceS' Provided o OPT Approved OOPS Approved NRC Approved ES-0.3 SM QuestionBank

  1. IKA system IKA number I 5331WE09 IEIG.3 I KA desc Knowledge ofthe reasons for the following responses as they apply to the (Natural Circulation Operations) (CFR: 41.5/41.10, 45.6, 45. 13) D Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

401-9 Comments:

WE09EK3.3 Question does not meet KIA. The KIA asks for reasons. Why do they stop depressurization when RVLIS is less than 73%? From 2006 NRC exam. Modified Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 54 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 28 D QuestionBank

  1. IKA system IKA number I 534 I SYSOO3 I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5145.31 45113) o Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP ...................

Unit 1 is in the process of performing a reactor startup. Given the following conditions and sequence of events:

  • Control Bank "N' is at 28 steps withdrawn
  • The BOP validates that the 1 C NC Pump vibration level on the frame is at 6.5 mils using the NC Pump vibration monitor panel. Which one of the following selections is the list of the correct actions based on this situation?

A. Trip 1 C NC Pump. Go to AP/11A155001004 (Loss of Reactor Coolant Pump). B. Reinsert Control Bank "A" rods. Trip 1 C NC Pump. Go to AP/11A155001004 (Loss of Reactor Coolant Pump). C. Pump trip criteria is not yet met. Go To AP/1/A/55001008 (Reactor Coolant Pump Malfunction).

D. Trip the reactor. Trip 1 C NC Pump. Go to EP/11A15000/E-O (Reactor Trip or Safety Injection).

Tuesday, November 18, 2008 Page 55 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 28 D General Discussion The correct action is to trip the reactor (based on being in Mode 2), trip the reactor coolant pump, and enter E-O due to the reactor trip. Answer A Discussion Incorrect:

With the plant in mode 2, E-O is the correct procedure.

Answer B Discussion Plausible:

This would be correct response in Mode 3 with all control banks in. Answer C Discussion Incorrect:

The pump trip criteria is > 5 mils on the frame. Plausible:

If trip criteria were not met, this would be the correct response.

Answer D Discussion ICorrect:

Job Level Cognitive Level Question Type Question Source RO Memory BANK. 2004 NRC Q64 (Bank 364) Bank Question:

1183 Developed Development References Student References Provided PS-NCP 12 0 OPT Approved OP/1/B/6100/0lG 1AD-6 B/5 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5341SYS003 1 A2*02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45113) 0 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP " ................ . 401-9 Comments:

003A2.02 Question appears to match KIA. Very similar to question # 86 (SRO). The only difference is the initiating event. What procedure directs these actions? It seems to me that there is not a correct answer. AP-4 does direct the actions listed in choice C, but you would have to go to the procedure to perform them. Question symmetry does not look right. One of these needs to be changed. 2004 NRC exam BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 56 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 B QuestionBank

  1. IKA system IKA number I 535 I SYSOO4 I A1.01 I KA desc Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5/ 45.5)DActivity levels in primary system ...................................

Unit 1 is at 75% power and decreasing in preparation for entering a refueling outage. Given the following conditions and sequence of events:

  • There is confirmed failed fuel on Unit 1.
  • 1AD-07, F/3 "LETDN HX OUTLET HI TEMP" -LIT
  • The BOP notes that letdown temperature has trended to 132°F and appears to have stabilized.
1. What minimum actions are required to reduce activity level per AP/1/A155001018 (High Activity in Reactor Coolant)?
2. What is the applicability of Tech Spec 3.4.16 (RCS Specific Activity)?

A. 1. Ensure at least one mixed bed demineralizer in service only. 2. Modes 1, 2, and 3. B. 1. Ensure at least one mixed bed demineralizer in service only. 2. Modes 1 and 2, Mode 3 with Tavg 500°F. C. 1. Reduce letdown temperature to clear the alarm and then place additional demineralizers in service. 2. Modes 1, 2, and 3. D. 1. Reduce letdown temperature to clear the alarm and then place additional demineralizers in service. 2. Modes 1 and 2, Mode 3 with Tavg 500°F. Tuesday, November 18, 2008 Page 57 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 29 B General Discussion INV153A diverts to VCT (bypasses Demins) at 136 degrees. The alann comes in at 128 degrees. Placing additional demins in service could provide additional cleanup. Letdown does not need to have temeprature reduced, demins are still in service (but will isolate as 136F or greater) Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Comprehension NEW Development References OP/1/B/61001010H NV lesson TS 3.4.16 QuestionBank

  1. IKA system IKA number I 5351SYS004 IAl.Ol I KA desc Question Source Student References Provided Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: (CFR: 41.5 I 45.5) o Activity levels in primary system .................................. . 401*9 Comments:

401*9 Comments RESPONSE 004Al.Ol Question does not appear to match KIA, unless you are implying that the increase in letdown heat exchanger temperature is due to the increase activity in the RCS. (I do not believe that this would cause temperature to rise). The KIA is looking for the ability to predict and or monitor changes in parameters to prevent exceeding design limits associated with operating CVCS controls including activity levels in the primary system. It would be more in line with the KIA to state that Tuesday, November 18, 2008 Page 58 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 30 c QuestionBank

  1. JKA system IKA number I 536 I SYSOO4 I K1.34 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.91 45.7 to 45.8)DInterface between CVCS and reactor coolant drain tank; and PZR PCS .... Unit 1 is operating at 100%. Given the following initial conditions and sequence of events:
  • Excess letdown is in service to the VCT to repair a leak on the letdown line.
  • A PZR pressure channel failure causes 1 NC-32B (PZR PORV) and 1NC-36B (PZR PORV) to open.
  • 1 NC-36B does not re-close and the BOP closed its isolation valve.
  • Minimum NC pressure reached during the event was 1820 psig.
  • Current NC pressure is 2145 psig and increasing.

Assuming no operator actions other than isolating 1 NC-36B: 1. What tank other than the VCT can excess letdown be directed to by 1 NV-125B (Excess Letdn Hx Otlt Ctrl)? 2. Is excess letdown currently flowing to the VCT? A. PRT; no B. PRT; yes C. NCDT; no D. NCDT; yes Tuesday, November 18, 2008 Page 59 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 30 General Discussion The tanks that can receive input from lNV-125B are the VCT and the NCDT. Excess letdown cannot be aligned to the PRT, however, the PORVs in the stem will discharge to the PRT and the seal return (downstream of excess LID) goes to the PRT. The pressure drop stated in the stem results in a safety injection.

Excess letdown (lNV -124B) does not isolate on an SI signal however normal letdown does. The seal return isolations close on an St signal but if they think that it is an Sp singla then it would be flowing to the VCT still. Answer A Discussion IWrong tank, correct status. Answer B Discussion IWrong tank, and status (balance)

Answer C Discussion ICorrect Answer D Discussion ICorrect tank, wrong status Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided APIIO 0 OPT Approved NV 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 536[SYS004 i K 1.34 i KA desc Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)DInterface between CVCS and reactor coolant drain tank; and PZR PCS .... 401-9 Comments:

004K1.34 Question appears to match KIA. Need to place in the stem Excess letdown is in service and aligned to the YCT, or someone could make the assumption that excess letdown was aligned to the NCDT to begin with. Otherwise okay. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 60 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 31 D QuestionBank

  1. IKA system IKA number I 537 I SYSOO5 I K4.11 I KA desc Knowledge of RHRS design feature( s) and! or interlock( s) which provide or the following: (CFR: 41.7) o Lineup for low head recirculation mode (external and internal)

..........

1 NO-1 B (NO Pump 1A Suct Frm Loop B) and 1 NO-37 A (NO Pump 1 B Suct Frm Loop G) have been aligned to their alternate power supplies.

1. What impact (if any) will aligning the alternate power supply have on the interlocks associated with these valves? 2. How are these valves positioned electrically in the current alignment?

A. 1. Interlocks operate normally 2. From the main control boards B. 1. Interlocks operate normally 2. From the face of alternate MGG breaker G. 1. Interlocks are removed 2. From the main control boards O. 1. Interlocks are removed 2. From the face of alternate MGG breaker Tuesday, November 18, 2008 Page 61 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 31 General Discussion On alt power all interlocks are bypassed.

The reason is to allow ND to be aligned on a loss of one train of power. SSF power swaps are completed for items just not Interlocks are normal and would be desired but not available Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO NEW Developed Development References Student References Provided ND lesson 0 OPT Approved 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number S371SYSOOS IK4.11 I KA desc Knowledge ofRHRS design feature(s) and/or interlock(s) which provide or the following: (CFR: 41.7)OLineup for low head recirculation mode (external and internal)

......... . 401-9 Comments:

OOSK4.11 Question appears to match KIA. SAT this is a fundamental level question.

NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 62 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 32 c QuestionBank

  1. IKA system IKA number I 538 I SYSOO6 I AI.05 I KA desc Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR:

41.5/ 45.5)DCCW flow (establish flow to RHR heat exchanger prior to placing in service ................................................

At 1200, Unit 1 was addressing an NC system leak per AP 11 IA/5500101 0 (Reactor Coolant Leak) when the leak began to increase.

Given the following:

NC system pressure (psig) Containment pressure (psig) FWST level (%) Time 1200 2130 0.5 98. 1206 1950 1.3 97 1212 5 2.8 80 1218 5 4.2 60 What is the earliest time that KC flow is automatically aligned to the NO heat exchangers?

A. 1206 B. 1212 C. 1218 O. 1224 1224 5 2.5 35 Tuesday, November 18, 2008 Page 63 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 32 c General Discussion KC aligns to the ND Hx on an Sp signal (3 psig in cont) or on an Ss signal with 10 101 fwst level (37%) Answer A Discussion An Ss signal is present but FWST level is too high to align KC Answer B Discussion An Ss signal occurs on NCS pressure.

If student doesn not recognize Ss has already occurred on Cont pressure, this answer is plausible.

Answer C Discussion Answer D Discussion Ss with LoLo FWST is present, but KC was aligned on the SP at I21S. Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided KC lesson D OPT Approved D OPS Approved. NRC Approved QuestionBank

  1. IKA system IKA number I 53SISYSOO6 IAI.05 I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5 / 45.5)DCCW flow (establish flow to RHR heat exchanger prior to placing in service ............................................... . 401-9 Comments:

401-9 Comments RESPONSE 006Al.05Question appears to match KIA. Please add automatically to the stem. "What is the earliest time that KC flow is automatically aligned to the ND heat exchanger?" NEW Tuesday, November 18, 2008 Page 64 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 33 QuestionBank

  1. IKA system IKA number I 539 I SYS007 I 2.4.6 I KA dese SYS007 GENERICDKnowledge ofEOP mitigation strategies. (CFR: 41.10 /43.5/45.13)

The crew is performing actions of AP/11A1SS001010 (Reactor Coolant Leak) due to an increase in charging flow required to maintain pressurizer level. You have just completed an evaluation of PRT conditions and noted the following:

  • PRT pressure is 12 psig and slowly increasing
  • PRT temperature is 140°F and slowly increasing The CRS directs you to monitor inputs to the PRT per Enclosure 13 (Possible NC System Leakage Paths to PRT). Assuming a single valve is leaking by its seat, which valve could have caused the noted PRT indications?

A. 1 NC-S (Loop A Lo Point Orn) B. 1 NC-2S0A (Rx Head Vent Block) C. 1 NC-2SA (Rx Head Gasket Leakoff Isol) O. 1,NV-87 (NC Pumps Seal Return Hdr Inside Relief) Tuesday, November 18, 2008 Page 65 of 200 D I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 33 D General Discussion Answer A Discussion This goes to the NCDT and is monitored per Enclsoure 12 Answer B Discussion This goes to the PRT, however, another valve would have to leak by to compelte a flowpath.

Answer C Discussion This goes to the NCDT and is monitored per Enclsoure 12 Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Ii'l Developed Development References Student References Provided o OPT Approved OOPS Approved Ii'l NRC Approved QuestionBank

  1. KA system 539SYS007 KA desc APIlO KA number 2.4.6 SYS007 GENERlCDKnowledge ofEOP mitigation strategies. (CFR: 41.10 /43.5/45.13) 401-9 Comments:

007G2.4.6 Question Does not match KIA. The KIA system is Pressurizer Relief Tank and how EOP mitigating strategies relate. This question is an H.I question describing what constitutes a bleed and feed. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 66 of 200 FOR REVIEW ONLY'-DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 34 A QuestionBank

  1. IKA system IKA number I 540 I SYS008 I K3.03 I KA desc I Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:DRCP

...........................................................

I Unit 1 is in Mode 3 with all shutdown banks withdrawn in preparation for startup when the following occur:

  • 1AD-6 E/3 "NCP THERMAL BARRIER KC OUTLET HIILO FLOW" -LIT
  • OAC indicates KC flow to NCP 1C Thermal Barrier HX is 75 gpm. What effects will this have on NCP 1C and what action should be taken to address the alarm? A. NCP 1C seal cooling is being maintained.

Verify 1 KC-345A (NC Pump 1C Therm Bar Otlt) closes after a 30 second time delay. B. NCP 1C seal cooling is being maintained.

Verify 1 KC-345A (NC Pump 1C Therm Bar Otlt) closes immediately.

C. All seal cooling to NCP 1 C is lost. Open the #1 seal bypass valve to restore seal cooling. D. All seal cooling to NCP 1C is lost. Secure NCP 1 C to prevent further seal damage. Tuesday, November 18, 2008 Page 67 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 34 General Discussion The nonnal flow to the KC thennal barrier is 40 gpm per NCP. The high flow alarm is set at 60 gpm per NCP. Answer A Discussion Correct: NCP seal cooling is being maintained by NY. lKC-345A closes after a 30 second time delay. Answer B Discussion Incorrect:

1KC-345A does not close immediately.

Plausible:

This would be correct except the valve closes after a 30 second delay Answer C Discussion Incorrect:

All seal cooling is not lost. The seal bypass valve is on a common line from all 4 NCPs -not just the 1 C NCP. Plausible:

Ifhe thinks that seal cooling is lost, opening the seal bypass valve would enhance seal cooling to the NCP. Answer D Discussion Incorrect:

This would be correct if all seal cooling is lost in this mode. Plausible:

If the candidate does not understand that seal cooling is supplied by the NV with this alarm. Job Level Cognitive Level QuestionType Question Source A RO Comprehension BANK 2004 NRC Q53 (Bank 353) Bank Question:

1170 Developed o OPT Approved OOPS Approved NRC Approved QuestionBank

  1. KA system 540SYS008 KA desc Development References Student References Provided

References:

1. OP-CN-PSS-KC page 12 2. OP-CN-PS-NCP pages 15-19 KA number K3.03 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:DRCP 401*9 Comments:

008K3.03 Question appears to match the KIA. Change Distractor C to read ... Open the #1 seal bypass valve to restore seal cooling. Change distractor D to read All seal cooling to NCP1 C is lost. Secure NCP 1 C to prevent further seal damage. SAT 2004 NRC exam. BANK Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 68 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 35 A QuestionBank

  1. IKA system JKA number I 541 I SYSOO8 I K4.09 I KA desc Knowledge ofCCWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)DThe "standby" feature for the CCW pumps ............................

Unit 2 is in Mode 5 with alignment of the KC system for parallel operations per OP/1/A164001005 (Component Cooling System). Given the following conditions and events:

  • 2A1, 2B1, and 2B2 KC Pumps are in service.
  • Both 2ETA and 2ETB are aligned to Unit 1 offsite power
  • An 86S relay actuates on 2ETB
  • All systems respond appropriately in automatic.

Assuming no operator actions, which Unit 2 KC pumps are in service? A. 2A 1 KC pump only B. 2A 1 and 2A2 KC pumps only C. 2A1, 2B1, .and 2B2 KC pumps only D. 2A1, 2A2, 2B1 and 2B2 KC pumps Tuesday, November 18, 2008 Page 69 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 35 A General Discussion REPLACEMENT KIA An 86S relay causes 2ETB to lockout. The blackout signal will not be overridden by the blackout signal, however, a LOCA signal would override the 86S relay and attempt to load LOCA loads. Therefore neither B train pump will re-start.

On a normal LOCA or LOOP, both trains ofKC would actuate. Answer A Discussion ICORRECT Answer B Discussion If the student thinks that either train B/O causes both trains to start (could be confused with RN which causes both units pumps to start on either unit LOCA or B/O) 2A2 will not start. Answer C Discussion If student thinks that the B/O signal will override the 86S relay. This would be correct if a B train only were to occur. Answer D Discussion If the student thinks that either train B/O causes both trains to start (could be confused with RN which causes both units pumps to start on either unit LOCA orB/O) Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Memory MODIFIED Development References QuestionBank

  1. IKA system IKA number J 541lSYS008 IK4.09 I KA desc Question Source 2007 NRC Q36 (Bank 836) Student References Provided Knowledge ofCCWS design feature(s) andlor interlock(s) which provide for the following: (CFR: 41.7)DThe "standby" feature for the CCW pumps ........................... . 401-9 Comments:

008K4.09 Question appears to match the KIA. SAT 2007 NRC Exam Modified.

Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 70 of 200

FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 36 B QuestionBank

  1. IKA system IKA number I 542 I SYSOIO J 2.1.25 J KA desc I SYSOIO GENERIC DAbility to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.1 0 / 43.5 /45.12) I Given the following sequence of events and conditions:
  • A pressurizer PORV opens spuriously and will not close
  • 3 minutes after the PORV opens, the block valve is closed.
  • NC pressure is 1500 psig
  • NC temperature is 550 of
  • PRT pressure is 45 psig What is the approximate pressurizer PORV tailpipe temperature?

Reference provided B. 290 of C. 310 of D. 320 of Tuesday, November 18, 2008 Page 71 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 36 B General Discussion Tailpipe temperature will be saturation temperature for PRT pressure which is 45psig or 60 psia (psia used for steam tables) On the Mollier diagram, go to the -1500-psia point on the saturation line. Cross the constant enthalpy line (throttling is a constant enthalpy process) to the 60 psia line 45 psig + 15 psi atmospheric

= 60 psia). Follow that line up to the saturation curve. The constant temperature line that ends at that point on the curve establishes the temperature of the fluid. The temperature is approximately 290DF. (292 is temp for 60psia) Answer A Discussion This temperature would be based on correct graph usage but with 45 instead of the correct 60 psia Answer B Discussion Answer C Discussion this is the temperaure iifthe student uses correct pressure but goes straight up the graph (constant entropy) Answer D Discussion his is the temperaure iifthe student uses incorrect pressure and goes straight up the graph (constant entropy) Job Level Cognitive Level QuestionType RO Comprehension NEW Developed o OPT Approved OOPS Approved NRC Approved QuestionBank

  1. KA system 542 SYSOIO KA desc Development References KA number 2.1.25 Question Source Student References Provided ASME Steam Tables SYSOIO GENERIC DAbility to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.1 0 / 43.5 /45.12) 401-9 Comments:

401-9 Comments RESPONSE 010G2.1.25 Question appears to match the KJA. SAT NEW Tuesday, November 18, 2008 Page 72 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 37 D QuestionBank

  1. IKA system IKA number I 543 I SYSOl2 I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5

/45.3/ 45.5)DLoss of instrument power .........................................

Given the following conditions and sequence of events:

  • Unit 1 was operating at 100% power.
  • The crew has entered API1/A/55001016 (Malfunction of Nuclear Instrumentation System) due to N42 lower detector failing LOW
  • IAE has not yet placed the required bistables in the trip condition per AP/1/A/55001016.
  • A complete loss of 1 ERPD occurs What procedure takes priority for these conditions?

A. Continue in AP/11A155001016 B. Enter AP/11A155001029 (Loss of Vital or Aux Control Power) C. Enter AP/11A155001003 (Load Rejection)

D. Enter EP/11A15000/E-0 (Reactor Trip or Safety Injection)

Tuesday, November 18, 2008 Page 73 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 37 General Discussion With N-42 failed, OTDT picks up. Loss of a vital bus will cause that channels bistables to pick up (in general) including OTDT. This causes a 2/4 situation on the OTDT runback and reactor trip. Ran on simulator at BOL and EOL and confirmed that lower detector only failing low would cause OTDT bistable to switch state. Answer A Discussion

\This procedure will address the N42 failure but does not take priority.

Answer B Discussion This procdure will address ERPD failure but does not take priority.

Answer C Discussion There are 2/4 OTDT and if a reactor trip did not occur, a runback would. Answer D Discussion

\CORRECT.

Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided ENB lesson D OPT Approved EPL lesson D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 543ISYS012 1 A2*02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 1 45.5)DLoss of instrument power 401-9 Comments:

OI2A2.02 Question appears to match KJA. NEW Will the OTDT bistables be in if just the lower detector on N-42 failed low? Ifnot, and the bistables have not been placed in a tripped condition, the reactor may not trip, and C would be correct. Please explain. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 74 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 38 QuestionBank

  1. IKA system IKA number I 544 I SYSOl2 I KS.OI I KA desc Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5 /45.7)DDNB

...........................................................

Which one of the following selections correctly matches the reactor trip signals to their limiting accident/protection?

A. B. c. O. Reactor Trip Signal OPOT OTOT pzr High Level pzr Low Pressure OPOT OTOT Pzr High Level pzr Low Pressure o POT OTOT pzr High Level pzr Low Pressure o POT OTOT pzr High Level pzr Low Pressure Tuesday, November 18, 2008 Limiting Accident/Protection ONB Excessive fuel centerline temperature NC system integrity ONB Excessive fuel centerli ne temperature ONB ONB NC system integrity Excessive fuel centerline temperature ONB NC system integrity ONB NC System integrity Excessive fuel centerline temperature ONB ONB Page 75 of 200 c FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 38 c General Discussion Answer A Discussion IOPDT and OTDT are reversed Answer B Discussion Ipzr high and low pressure are reversed Answer C Discussion Icorrect Answer D Discussion Ipsychometric balance Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2007 Audit Exam #2 Q39 (Bank 39) !i'l Developed Development References Student References Provided TS 3.3.1 and bases 0 OPT Approved IPX 0 OPS Approved !i'l NRC Approved QuestionBank

  1. IKA system IKA number I 5441SYS012 IKS.Ol J KA desc Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5/ 45.7)ODNB 401*9 Comments:

012KS.Ol Question appears to match KIA. SAT BANK 2007 Audit Exam #2. Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 76 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 39 A QuestionBank

  1. IKA system IKA number I 545 I SYS013 I K6.01 I KA desc Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: (CFR: 41.7/45.5 to 45.8)0 Sensors and detectors

............................................

Initial Conditions:

  • Unit 1 was performing a heatup following a refueling outage
  • NC Temperature was 400 of
  • NC pressure was 1600 psig * "A" and "B" shutdown banks were withdrawn
  • Containment Pressure Channel II failed high Current Conditions:
  • 1 ERPD has lost power
  • Containment pressure channels read: o Channell:

0 psig o Channel II: +5 psig o Channel III: 0 psig o Channel IV: -5 psig Which of the following statements explains the impact on the Engineered Safeguards Features (ESF) system and expected operator actions? A. Only Train "A" safety injection actuates.

Implement AP/1/A/55001005, Reactor Trip or Inadvertent S/I Below P-1 B. Only Train "A" safety injection actuates.

Implement EP/1/A/5000/E-0, Reactor Trip or Safety Injection.

C. Train "A" and "B" safety injection actuates.

Implement AP/1/A/55001005, Reactor Trip or Inadvertent S/I Below P-11. D. Train "A" and "B" safety injection actuates.

Implement EP/1/A/5000/E-0, Reactor Trip or Safety Injection. Tuesday, November 18, 2008 Page 77 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 39 A General Discussion ESF AS information due to power failure: AP-29 Enclosure 17 Answer A Discussion ICorrect Answer B Discussion Incorrect:

Bistables for channels 2&4 are actuated and SSPS receives the input. Only A train actuates due to ERPD failure. Answer C Discussion Bistables for channels 2&4 are actuated and SSPS receives the input but only A train actuates .. Because the actuations were made in Mode 4, OS is the correct mitigation procedure path. Answer D Discussion Since both trains of input bay receive any signal from the process cabinets, he may assume that 2 press ch would satisfy both SSPS output bays. E-O is not used in M4, AP-OS transfers to E-O only on valid indication of high cont press >200 F in the NCS. Cognitive Level QuestionType Question Source Comprehension BANK 200S NRC Q36 (Bank 440) SIMILAR Developed D OPT Approved D OPS Approved NRC Approved Development References Lesson D OP-CN-ECCS-ISE ObjectivesD2 & 3 REFERENCESDAP/lIAlSSOO/029 Enclosure 17 (lERPD load list) rev 013 QuestionBank

  1. IKA system IKA number I S4SISYS013 IK6.01 I KA desc Student References Provided Knowledge of the effect ofa loss or malfunction on the following will have on the ESFAS: (CFR: 41.7 I 4S.S to 4S.8)DSensors and detectors 401-9 Comments:

013K6.01 Question appears to match KIA. SAT. 200S NRC Exam. BANK Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 78 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 40 D QuestionBank

  1. IKA system IKA number I 546 I SYS022 I I KA desc I Knowledge of power supplies to the following: (CFR: 41.7)DChillers

....................................................... . I Which one of the following is the type of power supplied to the YV Chillers?

A 600V unit power B. 4160 V essential power C. 4160 V blackout power D. 6900 V unit power Tuesday, November 18, 2008 Page 79 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 40 D General Discussion Answer A Discussion Iyvpumps Answer B Discussion lyC chillers get 4160 power (essential)

Answer C Discussion lyC chillers get 4160 power (essential)

Answer D Discussion ICorrect Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided RNlesson D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system KA number 546SYS022 K2.02 KA desc Knowledge of power supplies to the following: (CFR: 41.7)DChillers

....................................................... . 401-9 Comments:

022K2.02 Question does not meet KIA. All of the power supplies listed appears to be correct, and the answer is that there is not a swap. So what power supply to the chillers are we testing? NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 80 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 41 QuestionBank

  1. IKA system IKA number I 547 I SYS025 I A4.01 I KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) DIce condenser isolation valves ......................................

Given the following:

  • 1AO-13, 0/8 "GLYCOL EXPANSION TNK LO-LO LVL" -LIT
  • BOP notes that the Unit 1 NF containment isolation valves have closed Where does the bypass valve for pressure relief between the isolation valves relieve to and from what location may the Glycol Expansion Tank Lo-Lo Level interlock be bypassed?

A. Glycol Expansion Tank I local NF control panel B. Glycol Expansion Tank I main control room C. Glycol Mixing and Storage Tank I local NF control panel O. Glycol Mixing and Storage Tank I main control room Tuesday, November 18, 2008 Page 81 of 200 A FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 41 A General Discussion Bypass will allow excess pressure from within the pentration to excape INTO containment but not anything out of containment.

Interlock Bypass is a key switch on the local panel. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided NF lesson 0 OPT Approved 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5471SYS025 IA4.0l I KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)DIce condenser isolation valves 401-9 Comments:

025A4.0l Question appears to match KIA. Appears to be SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 82 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 42 c QuestionBank

  1. IKA system IKA number I 548 I SYS026 I A1.03 I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5/ 45.5) DContainment sump level ...........................................

Given the following:

  • A large break LOCA has occurred.
  • Containment pressure is 3.2 psig and slowly decreasing.
  • The crew has just transitioned to EP/1/A15000/ES-1.3 (Transfer to Cold Leg Recircu lation) What is the minimum containment sump level that will support operation of all ECCS pumps and the NS pumps? A. 0.5 ft B. 2.5ft C. 3.3 ft D. 5.0 ft Tuesday, November 18, 2008 Page 83 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 42 c General Discussion Per the anuciator response for Containemt sump levels on lAD20 & 21, 2.5 ft will support eccs operation, 3.3 ft will support eccs and NS operations.

All levels in distractors are levels mentioned in ES-l.3 which can be assumed entered for large break locas. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided ES 1.3 0 OPT Approved OP /11 Al61001007 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 54SlSYS026 IAl.03 I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associateg with operating the CSS controls including: (CFR: 41.5 I 45.5) 0 Containment sump level .......................................... . 401-9 Comments:

401-9 Comments RESPONSE 026Al.03 Question appears to match KJ A. SAT NEW Tuesday, November 18, 2008 Page 84 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 43 A QuestionBank

  1. IKA system IKA number I 549 I SYS026 I K1.01 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)OECCS

..........................................................

Given the following sequence of events: 1200 Unit 1 reactor tripped from 100% power due to a large break LOCA 1236 FWST level is 36% Containment pressure is 3.8 psig 1240 1NI-185A (NO Pump 1A Cant Sump Suet) is not open and efforts to open it from the control room have failed. 1241 1A NO pump is secured. 1245 NLOs have been dispatched to manually open 1NI-185A.

1300 NLOs report 1 NI-185A is fully open. 1301 1A NO pump is started. 1305 FWST level is 16% Containment pressure is 3.1 psig Which one of the following describes the status of the 1A NS pump at 1245 and what is the earliest time that NO Aux Spray can be placed in service? A. 1A NS pump was running; 1250 B. 1A NS pump was running; 1301 C. 1 A NS pump was off; 1250 O. 1A NS pump was off; 1301 Tuesday, November 18, 2008 Page 85 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 43 A General Discussion for ND Aux spray must have 50 min since trip and I train ofND in CLR mode. ND is secured if the cont sump valve does not open, but NS remains on till II % ifNS is required.

As long as NY SII and NT pump can be supplied from I train ofND alone, then after 50 minutes, can use ND aux spray from B train. Answer A Discussion Answer B Discussion INS status is correct, time is not Answer C Discussion ITime is corect status is now Answer D Discussion both incorrect

-psychomentric balance. Plausible because maybe think that NS is secured along with ND,and that both trains of CLR are needed to allow ND aux spay. Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided NS lesson 0 OPT Approved ES 1.3 0 OPS Approved ES 1.3 background NRC Approved QuestionBank

  1. IKA system IKA number I 5491SYS026 IK1.01 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8)DECCS

......................................................... . 401-9 Comments:

026KI.OI Question appears to matchKJA.

Very wordy. Attempt to get rid of most of the BOP reports. Actual stem needs some modification Which one of the following describes the status of the IA NS pump at 1245, and the earliest time that ND Aux spray can be placed in service? NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 86 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 44 D QuestionBank

  1. IKA system IKA number I 550 I SYS039 I K5.01 I KA desc Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5 / 45.7)DDefinition and causes of steam/water hammer ........................

Given the following conditions and sequence of events:

  • Unit 1 is manually tripped due to a loss of normal feedwater.
  • NLOs have manually isolated CA flow to 1 B S/G and level is noted to be 96% on NR level gauges. Which of the following consequences have increased risk for 1B S/G based on the current water level in that S/G? 1. Failure of S/G PORV to actuate 2. Failure of SM safety valves to reseat following an actuation
3. Water hammer upon initiation of steam flow 4. Mechanical failure of the main steam lines A. 1 and 2 only B. 3 and 4 only C. 1,2 and 3 D. 2,3 and 4 Tuesday, November 18, 2008 Page 87 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 44 General Discussion 2, 3 and 4 are all potential consequences of a SG overfill.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided SMlesson 0 OPT Approved FR-H.3 Background 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 55olSYS039 IKS.Ol 1 KA desc Knowledge of the operational implications of the following concepts as the apply to the MRSS: (CFR: 441.5/ 45.7)DDefinition and causes of steam/water hammer ....................... . 401-9 Comments:

039KS.Ol borderline KIA match. Definition of steam/water hammer is not really tested. Very wordy question.

This question actually test the consequences of a steam generator overfill event. Very little discriminating value. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 88 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 45 c QuestionBank

  1. IKA system IKA number I 551 I SYS059 I A4.11 I KA desc Ability to manually operate and monitor in the control room: (CFR: 41.7 / 45.5 to 45.8) o Recovery from automatic feedwater isolation

........................

Unit 1 is at 75% power when a plant trip occurs due to P-14 actuation.

Given the following events and conditions:

  • The plant is currently stable.
  • The steam dumps have just closed at no-load Tave.

What action must the operator take to reset CF isolation?

A. Lower the affected steam generator level, cycle the reactor trip breakers and depress the CF isolation reset pushbuttons.

B. Lower the affected steam generator level and cycle the reactor trip breakers.

C. Cycle the reactor trip breakers and depress the CF isolation reset pushbuttons.

D. Cycle the reactor trip breakers only. Tuesday, November 18, 2008 Page 89 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination General Discussion Answer A Discussion Incorrect:

no need to reduce S/G level Plausible:

would be true on unit 2. Answer B Discussion Incorrect:

not need to reduce S/G level on Unit I -must reset FWI QUESTION 45 Plausible:

partially correct -would be true on Unit 2 and Low TavelP-4 FWI had not occurred.

Answer C Discussion Correct: to clear the P-14, the trip breakers must be cycled. To clear the low tave/p-4 FWI, it must be reset. Answer D Discussion Incorrect:

must also depress FWI pushbuttons c Plausible:

would be true ifP-41L0w Tave FWI had not occurred.

Cycling Rx trip breakers does clear auto SII block following an S/!. Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Comprehension BANK Development References Lesson Plan Objective:

ISE Obj: 5

References:

1. OP-CN-ECCS-ISE page 21, 22, 23 QuestionBank
  1. IKA system IKA number I 55l[SYS059

[A4.11 [ KA desc Question Source 2003 NRC Q55 (Bank 255) Old Bank Question:

970BH Student References Provided Ability to manually operate and monitor in the control room: (CFR: 41.7/45.5 to 45.8)DRecovery from automatic feedwater isolation 401-9 Comments:

059A4.ll Question appears to meets KlA. SAT. 2003 NRC exam question.

BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 90 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 46 D QuestionBank

  1. IKA system IKA number I 552 I SYS06l I A3.03 I KA desc I Ability to monitor automatic operation of the AFW, including: (CFR: 41.7/ 45.5)OAFW S/G level control on automatic start ............................

1 Given the following:

  • Unit 2 was operating at 100% power.
  • 2A steamline ruptured inside containment resulting in containment pressure rapidly increasing to 3.7 psig.
  • Current containment pressure is 2.4 psig and slowly decreasing.
  • The crew has just verified that total CA flow is greater than 450 gpm per step 18.a of EP/2/A/5000/E-0 (reactor Trip or Safety Injection).

Within what operating band should the BOP be attempting to control S/G N/R levels? A. Between 11 % and 50% B. Between 29% and 50% C. Between 9% and 62% D. Between 21% and 62% Tuesday, November 18, 2008 Page 91 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC. Examination QUESTION 46 D General Discussion ACC values should be used since containment pressure exceeded 3 psig even though it has been redced below 3 psig. Answer A Discussion jUnit 1 non-ACC number Answer B Discussion IUnit 1 ACC numbers Answer C Discussion IUnit 2 non-ACC numbers Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided o OPT Approved OOPS Approved NRC Approved QuestionBank

  1. KA system 552 SYS061 KA desc E-O KA number A3.03 Ability to monitor automatic operation of the AFW, including: (CFR:

41.7/ 45.5)OAFW S/G level control on automatic start ........................... . 401-9 Comments:

061A3.03 Question appears to meets KIA. SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 92 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 47 QuestionBank

  1. IKA system IKA number I 553 I SYS062 I A3.01 I KA desc Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7/ 45.5)OVitaJ ac bus amperage .............................................

Given the following:

  • 2B DIG automatically started due to the incoming breaker to 2ETB spuriously opening.
  • While checking DIG operating parameters, the crew notes that DIG 2B 'VOLTS" is 4300 V.
  • At the direction of the CRS, the BOP adjusts voltage to normal. How will DIG 2B output "AMPS" and "P/F" indications respond to this adjustment?

AMPS P/F A. increase less lagging B. increase stay the same C. decrease less lagging D. decrease stay the same Tuesday, November 18, 2008 Page 93 of 200 B FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 47 B General Discussion Students must understand that the DIG is not in parallel and that voltage must be adjusted DOWN. When vlotage is reduced, DIG lETA amps increases.

This has no effect on Power Factor. This is OE from an NLO who was attempting to control PIP while operating isynchcronus.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided DG3lesson D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. IKA* system IKA number I 553[SYS062

[A3.01 [ KA desc Ability to monitor automatic operation of the ac distribution system, including: (CFR: 41.7 I 45.5) o Vital ac bus amperage 401*9 Comments:

062A3.01 Question appears to meet KIA. Change 2B Amps to 2B output amps. (field amps will decrease as voltage is lowered. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 94 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 c QuestionBank

  1. IKA system IKA number I 554 I SYS063 I K2.0l I KA desc I Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads ................................................ . I Which of the following receives power from 250VDC Auxiliary Power System? A. DIG Fuel Oil Booster Pump B. Reactor Trip Switchgear Control C. Unit 1 Turbine Emergency Bearing Oil Pump D. Power Operated Relief Valves Solenoids (both NC and SV systems) Tuesday, November 18, 2008 Page 95 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 48 c General Discussion All loads are DC loads, DIG booster pump comes from 1 DGDA. And rx: trip switchgear and PORV s come from l25VDC vital Answer A Discussion Answer B Discussion Answer C Discussion iCORRECT Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided D OPT Approved D OPS Approved NRC Approved QuestionBank
  1. KA system 554SYS063 KA desc EPL KA number K2.0l Knowledge of bus power supplies to the following: (CFR: 41.7)OMajor DC loads 401-9 Comments:

063K2.01 Question appears to meets KIA. There are no plausible distractors.

Only one power supply is DC @125 volts, and the correct answer (250V). Almost all emergency lube oil pumps in the industry are DC. Need to have more plausible distractors.

As written very little discriminatory value. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 96 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 49 D QuestionBank

  1. IKA system IKA number I 555 I SYS063 I K3.01 I KA desc Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7 145.6)DED/G

..........................................................

Unit 1 was operating at 10% power preparing to roll the turbine. Given the following sequence of events: 0200 -1 A DIG Battery Charger 1 DGCA fails. 0700 -DIG 1A Panel, E/5 "LOSS OF DC CONTROL POWER" -LIT 0900 -A tornado results in a complete loss of the switchyard.

Assuming no actions have been taken to address the failed charger, which one of the following statements correctly describes the operating status of the 1 A DIG and the reason for this status? A. The 1A DIG starts because the auto-start function is not dependent on DC control power. B. The 1A DIG starts because the control power is supplied from vital power through auctioneering diode 1VADA. C. The 1A DIG started but did not tie to the bus because the sequencer has lost all control power. D. The 1A DIG did not start because it has lost all control power. Tuesday, November 18, 2008 Page 97 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 49 D General Discussion ______________________________________________ Answer A Discussion Incorrect:

DIG will not start. DC control power is required for the DIG to start. Plausible:

If the candidate thinks that the battery will carry DC control power loads for> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Answer B Discussion Incorrect:

DIG will not start. Plausible:

if student thinks that control power to the DIG is available thru V ADA. This is reversed, the DGCA supplies power thru V ADA to the sequencer.

Answer C Discussion

Incorrect:

DIG will not start. Plausible:

The sequencer has normal power available thru lEDA (from vital power) Answer D Discussion ICorrect Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK 2004 NRC Q74 (Bank 374) OLD Bank Question:

1212 Developed Development References Student References Provided D OPT Approved D OPS Approved NRC Approved Lesson Plan Objective:

DG-DGl-14, 19

References:

1. OP-CN-DG-DGl pages 17-19,26 QuestionBank
  1. IKA system IKA number I 5551SYS063 IK3.01 I KA desc Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: (CFR: 41.7 1 45.6)OED/G 401*9 Comments:

063K3.01 Question appears to match KIA. Distractor B does not appear to be plausible.

Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 98 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 50 B QuestionBank

  1. IKA system IKA number I 556 I SYS064 I A3.07 I I Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7 / 45.5)DLoad sequencing

.................................................

I Given the following conditions and sequence of events:

  • Unit 2 was operating at 100% power when a LOCA occurred
  • Containment pressure peaked at 2.6 psig and is slowly decreasing
  • 1 A CA Pump failed to start * "A" train ECCS and DIG load sequencer was reset
  • 1 A CA Pump was manually started
  • A complete loss of switchyard occurs Assuming no operator actions since the loss of the switchyard, which of the following is a complete list of the ECCS pumps currently in service? A. 2A NV, 2A NI, 2A NO, 2B NV, 2B NI, 2B NO B. 2A NV, 2B NV, 2B NI, 2B NO C. 2B NV, 2B NI, 2B NO O. 2A NV, 2B NV Tuesday, November 18, 2008 Page 99 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 50 B General Discussion With sequencer reset, load groups 4 and 5 (N!, ND) will NOT start on a blackout.

This is the situation on "A" train. All will restart on B train since the LOCA signal is still present and it overrides the BO Answer A Discussion Ithis would be if neither train of ECCS/SEQ were reset Answer B Discussion Answer C Discussion This is plausibe if student thinks that all A train ECCS equipment does not restart on a blackout.

NV does ... Answer D Discussion IThis would occur ifBOTII trains were reset Job Level Cognitive Level QuestionType RO Comprehension NEW Developed D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system 556SYS064 KA desc Development References E-O and backgrnd doc EQB KA number A3.07 Question Source Student References Provided Ability to monitor automatic operation ofthe ED/G system, including: (CFR: 41.7 / 45.5)DLoad sequencing

................................................ . 401-9 Comments:

064A3.07 Question appears to match KlA.SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 100 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 51 A QuestionBank

  1. IKA system IKA number I 557 I SYS064 I K6.07 I KA desc Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7/ 45.7)OAir receivers

....................................................

Unit 1 is operating at 100% power. A plant operator reports the following:

  • DIG 1A Panel, B/8 "LOW VG AIR TANK PRESS" -LIT
  • VG receivers starting air pressure is stable at 149 psig Which one of the following statements correctly describes the state of readiness of the 1A DIG? A. The DIG can be manually started and is capable of one or two starts. B. The DIG can be automatically started and is capable of one or two starts. c. The DIG can be manually or automatically started and is capable of five starts. D. The DIG cannot be manually or automatically started until the VG receiver is repressurized . Tuesday, November 18, 2008 Page 101 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 51 A General Discussion Bank Question:

986 IfVG Pressure decreases to less than 150 psig, all automatic start signals are blocked. This conserves enough air for one or two manual start attempts after the cause of the start failure is corrected.

Answer A Discussion ICorrect:

Can be started manually one or two times Answer B Discussion Incorrect:

With starting air receiver pressure < 150 psig, auto starts are blocked. Plausible:

partially correct -capable of one or two manual starts. Answer C Discussion Incorrect:

Auto starts are blocked below 150 psig -can't make 5 starts at 150 psig. Plausible:

This is the FSAR requirement for the number of starts on a DIG Answer D Discussion Incorrect:

Can be started manually started Plausible:

psychometric balance Job Level Cognitive Level QuestionType RO Comprehension BANK Developed Development References

1. DG 1 lesson D OPT Approved 2. Tech Spec Bases 3.8.3 El OPS Approved NRC Approved QuestionBank
  1. IKA system IKA number I 5571SYS064 IK6.07 I KA desc Question Source 2003 NRC Q64 (Bank 264) Student References Provided Knowledge ofthe effect ofa loss or malfunction of the following will have on the ED/G system: (CFR: 41.7 I 45.7)DAir receivers 401-9 Comments:

064K6.07 Question appears to match KIA. SAT 2003 NRC exam question.

Add automatically and manually started to D. BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 102 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 52 B QuestionBank

  1. IKA system IKA number I 558 I SYS073 I A2.02 I KA desc 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 cor-rect, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/

45.13)DDetector failure .................................................

Given the following:

  • Unit 1 is operating at 8% power preparing to place the turbine online
  • A va release is in progress 1EMF-39L (CONTAINMENT GAS (LO RANGE>> detector fails causing a Trip 2 alarm
  • 1 RAD-1, F/5 "CABINET 1-2 TROUBLE" is LIT 1. What is the status of the Unit 1 Containment Evacuation alarm? 2. What is/are the minimum action(s) required to reinitiate the air release from contain ment? A. 1. The Containment Evacuation alarm has actuated.
2. Bypass the failed EMF detector per OP/0IAl65001080 (EMF RP86A Output Modules) and then RESET the safety signal per OPI1/B/61001010X (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) B. 1. The Containment Evacuation alarm has NOT actuated.
2. Bypass the failed EMF detector per OP/0IAl65001080 (EMF RP86A Output Modules) and then RESET the safety signal per OP/1/B/61001010X (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) C. 1. The Containment Evacuation alarm has actuated.
2. RESET the safety signal only per OP/1/B/61 00101 OX per (Annunciator Response for Radiation Monitoring PaneI1RAD-1)

D. 1. The Containment Evacuation alarm has NOT actuated.

2. RESET the safety signal only per OP/1/B/61 00101 OX per (Annunciator Response for Radiation Monitoring Panel 1 RAD-1) Tuesday, November 18, 2008 Page 103 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 52 General Discussion EMF 39 Trip2 will give an SH signal. This will isolate containment ventilation (VPNQ). To reset the SH the initiating signal must be cleared and the reset depressed unlike SP and ST which can be reset with the initiating signal present. The containment evacuation alarm sounds on this EMF in trip 2 below P-6 (Low in source range) the reactor is currently below P-l 0 (l0% power but well above P6) Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References OP/lIB1610010l0 X QuestionBank
  1. IKA system IKA number I 558!SYS073 1 A2*02 I KA desc Question Source Student References Provided 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 cor-reet, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 I 45.3 I 45. 13) o Detector failure ................................................ . 401-9 Comments:

073A2.02 Question kind of matches KIA. What procedure is used to mitigate the failure? The actions should be IA W a procedure.

It appears that Ctrnt. ventilation is isolated and must be restored.

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 104 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 53 A QuestionBank

  1. IKA system IKA number I 559 I SYS076 I K2.0l I KA desc I Knowledge of bus power supplies to the following: (CFR: 41.7)DService water ................................................... . I 1A RN pump is normally powered from: A. 4160V bus 1 ETA B. 4160V bus 1FTA C. 6900V bus 1TA long side D. 6900V bus 1TC long side Tuesday, NovemJJer 18, 2008 Page 105 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 53 A General Discussion These are all A train power supplies for large motors. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided D OPT Approved D OPS Approved NRC Approved QuestionBank
  1. KA system 559 SYS076 KA desc RN lesson EPC lesson KA number K2.01 Knowledge of bus power supplies to the following: (CFR: 41.7)0 Service water ................................................... . 401*9 Comments:

076K2.01 Question appears to match KIA. Do any of these busses supply lETA? If so it is also a correct answer. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 106 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 54 B QuestionBank

  1. IKA system IKA number I 560 I SYS078 I K3.02 I KA desc Knowledge of the effect that a loss or malfunction ofthe lAS will have on the following: (CPR: 41.7/ 45.6) D Systems having pneumatic valves and controls ........................

Unit 2 is in Mode 3 with charging and letdown in normalalignment.

What affect does a total loss of VI have on the NV system? A. Charging flow increases; letdown flow increases B. Charging flow increases; letdown flow decreases C. Charging flow decreases; letdown flow increases D. Charging flow decreases; letdown flow decreases Tuesday, November 18, 2008 Page 107 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 54 General Discussion 1NV294 and 1NV309 fail open, letdown orifice vlaves fail closed on loss of air. Letdown isolation valves 1NV-1A and 1NV-2A fail close on Loss of VI Answer A Discussion Ipartially correct. Answer B Discussion Answer C Discussion Ireversed

-psychometric balance Answer D Discussion Ipartially correct. Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided NV lesson D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 560lSYS078 IIG.02 I KA desc Knowledge of the effect that a loss or malfunction of the lAS will have on the following: (CPR: 41.7/ 45.6)DSystems having pneumatic valves and controls ....................... . 401-9 Comments:

078IG.02 Question appears to match KIA. Some of the information in the stem is window dressing.

SAT NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 108 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 55<t-QuestionBank

  1. IKA system IKA number I QuesT70n 561 I SYSI03 I K1.07 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8) D Containment vacuum system .......................................

Unit 1 is operating at 100% power with a routine containment air release in progress through 1VQ-10 (VQ Fans Disch To Unit Vent). 1. At what containment pressure will 1VQ-10 first receive a "CLOSE" signal? 2. What is the basis for closing 1VQ-10 at that pressure?

A. 1. -0.08 psig 2. Non-compliance with technical specification on containment pressure B. 1. -0.08 psig 2. Unexpected opening of ice condenser inlet doors C. 1. 0 psig 2. Non-compliance with technical specification on containment pressure D. 1. 0 psig 2. Unexpected opening of ice condenser inlet doors Tuesday, November 18, 2008 Page 109 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination General Discussion -QUES'FION IF VQ 10 fails to close based on pressure of 0 psig, it can conceivably draw pressure to negative 2.8 psig which violated TS limits, however, that's not enough to open lower ice cond doors. (0.5Ib/sqft)

-0.08 is the admin limit for containment pressure.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW [i'J Developed Development References Student References Provided 0 OPT Approved VQ lesson 0 OPS Approved [i'J NRC Approved QuestionBank

  1. IKA system IKA number I 561lSYSI03 IK1.07 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2to 41.9 145.7 to 45.8) 0 Containment vacuum system ...................................... . 401*9 Comments:

103K1.07 Question kind of matches KIA. What is the significance of the second part of the question?

Do you have a containment vacuum system? Which one of the following describes a condition that would automatically close I VQ-I 0, and what would the consequence be if the valve failed to close? Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 110 0(200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 56 QuestionBank

  1. IKA system IKA number I 562 I SYSOOI I K2.02 I KA desc Knowledge of bus power supplies to the following: (CFR: 41.7)OOne-line diagram of power supply to trip breakers .................... . Unit 1 was in Mode 3 with shutdown banks withdrawn in preparation for startup. Given the following:
  • 1TO short side incoming breaker trips
  • 1TO tie breaker does not automatically close Which MG set(s) haslhave a power supply available and what is the current status of the shutdown banks? A. Only 1A MG set; shutdown banks are inserted B. Only 1A MG set; shutdown banks are withdrawn C. 1A and 1 B MG sets; shutdown banks are inserted O. 1A and 1 B MG sets; shutdown banks are withdrawn Tuesday, November 18, 2008 Page 111 0(200 D I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 56 D General Discussion If 1 TD lshort side loses power, then lLXD and NCP D lose power. There is no reactor trip rewauierd either manually or auotmatically due to iNcp loss in this condition.

Therefor the shutdown banks would still be out. lLXC feeds MG set 1 and lLXD feeds MG set 2. lLXD gets backup power from 1 TXS assuming LXC is still powered (which it is). Therefore both MG sets still have power. Answer A Discussion plausible if they think that lLXD loses power. And NCP trip causes Rx trip Answer B Discussion Iplausible if they think that lLXD loses power. Answer C Discussion Iplausible if they think that ld NCP trip causes Rx trip Answer D Discussion ICORRECT Job Level Cognitive Level Question Type RO Developed D OPT Approved D OPS Approved NRC Approved Memory NEW Development References IPX EPB QuestionBank

  1. IKA system IKA number I 5621SYSOOl 1K2*02 I KA desc Question Source Student References Provided Knowledge of bus power supplies to the following: (CFR: 41.7)DOne-line diagram of power supply to trip breakers .................... . 401*9 Comments:

OOlK2.02 Does not match the KIA. This question really asks what happens ifboth bypass breaker are closed, not power supplies.

Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 112 of200 I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 57 D QuestionBank

  1. IKA system IKA number I 563 I SYSOll I Al.02 I KA desc Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5 / 45.5)DCharging and letdown flows ........................................

Initial conditions at 1300:

  • Unit 2 was at 50% power
  • Pressurizer level was at program level
  • 2NV-312A (Chrg Line Cont Isol) spuriously closed and could not be reopened
  • Operators have taken the following actions per AP/2/A/5500/012 (Loss of Charging or Letdown), Case I (Loss of Charging):

o Secured letdown o Total charging flow has been reduced to 32 gpm

  • Excess letdown can not be established At approximately what time will the pressurizer become inoperable per Tech Spec 3.4.9 (Pressurizer)?

Reference provided A. 1434 B. 1608 C. 1651 D. 1825 Tuesday, November 18, 2008 Page 113 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 57 D General Discussion With charging flow at 32 gpm and no letdown, a net of20 gpm is being added to the NC system. (Stating level is 40% based on 50% rx power) . Based on this and a conversion of -125gallons/%

level in the PZR, level will reach the hi level setpoint of70% at 1434 hrs (T+ 188 minutes).

This is plausible since it is an alarm setpoint associated with abnormally high pressurizer level. The actual inoperability level is 92% which will occur at -1825 hrs (T+325 minutes).

The othervalveus are based on level starting at 55% which is the normal PZR level at 100%. Answer A Discussion if assume 100% power level and 70% inoperable Answer B Discussion lif assume 50 power and 70% level Answer C Discussion lif assume 100power and 92 inoperable Answer D Discussion Job Level Cognitive Level QuestionType RO Comprehension MODIFIED Developed*

D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. IKA system 5631SYS011 KA desc Development References LessonDOP-CN-PS-ILE rev 23 REFERENCESDTS 3.4.9 PZR level to gallons graph (REF PROVIDED)

IKA number IA1.02 Question Source 2005 SRO Q77 (Bank 481) Student References Provided Pressurizer volume (gal) to level (%) graph Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: (CFR: 41.5 I 45.5) DCharging and letdown flows ........................................

401-9 Comments:

0llAl.02 Question kind of matches KIA. The question should be at approximately what time does charginglletdown have to be returned to service to prevent exceeding a TIS limit. 2005 NRC exam Modified.

Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 114 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 58 c QuestionBank

  1. IKA system IKA number I 564 I SYS016 I K1.12 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9/ 45.7 to 45.8)DS/G

............................................................

Unit 1 was operating at 70% when 1 C S/G MEDIAN SELECTED Wide Range (WR) Level output to the Digital Feedwater Control System (DFCS) fails low. How will the DFCS respond to this event? A. DFCS will switch 1C S/G CF reg valve and CF bypass reg valve to MANUAL. B. DFCS will substitute another S/G's WR level input into "C" loop. C. DFCS will generate a "DFCS TROUBLE" alarm only. D. DFCS will reduce S/G 1 C WR level to 50%. Tuesday, November 18, 2008 Page 115 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 58 c General Discussion WR level is only used at lower power <<25%) when it is used it it is median selected Answer A Discussion Would need additional failures to cause it to go to manual but since this is the output of a median selected signal it is plausible.

Answer B Discussion This would be true for CF temperature which substitutes another S/Gs value. Answer C Discussion ICORRECT Answer D Discussion this occurs on unit 2 when a CF pump is lost at >65% Job Level Cognitive Level QuestionType Question Source RO Comprehension BANK TASKMASTER IFE-002-A Developed Development References Student References Provided IFE lesson D OPT Approved ARP D OPS Approved NRC Approved QuestionBank

  1. IKA system KA number I 564!SYS016 K1.l2 I KA desc Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) 0 S/G ............................................................

401-9 Comments:

016K1.l2 Question appears to match KIA. Not sure if all of these are plausible.

Will discuss. BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 116 of200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 59 A QuestionBank

  1. IKA system IKA number I 565 I SYS017 I IG.Ol I KA desc Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7/ 45.6)DNatural circulation indications

.....................................

Unit 1 was operating at 100% power when a loss of offsite power caused a reactor trip. The crew has verified natural circulation in ES-D.1 (Reactor Trip Response).

Ten minutes later, the operator notes that the thermocouple input to both plasma displays is malfunctioning.

Which one of the following correctly describes a valid indication that natural circulation is continuing?

A. S/G pressures are decreasing and T cold is at S/G saturation temperature.

B. S/G saturation temperatures are decreasing and REACTOR VESSEL U R LEVEL indication is greater than 100%. C. S/G pressures are decreasing and REACTOR VESSEL DIP indication is greater than 100%. D. S/G pressure is at saturation pressure for Tcold and REACTOR VESSEL DIP indication is greater than 100%. Tuesday, November 18, 2008 Page 117 0(200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 59 A General Discussion IBank Question:

911.1 Answer A Discussion Answer B Discussion

Incorrect:

There is no indication of coupling between primary and secondary.

Plausible:

These are important indications during natural circulation.

Answer C Discussion Incorrect:

Reactor Vessel DIP is unavailable during natural circulation.

Plausible:

S/G pressure decreases during natural circulation and RVLIS is one of the other plasma display indications.

Answer D Discussion Incorrect:Reactor Vessel DIP is unavailable during natural circulation.

Plausible:

S/G pressure will remain close to saturation for Tco1d during natural circulation and RVLIS is one ofthe other plasma display indications.

Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2003 RO Q48 (Bank 248) Developed Development References Student References Provided HT D OPT Approved 1. ES-O.l page 15 D OPS Approved 2. ES-O.l Enclosure 3 page 1 NRC Approved QuestionBank

  1. IKA system IKA number I 5651SYS017 IK3.01 I KA desc Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: (CFR: 41.7/ 45.6)DNatura1 circulation indications

.................................... . 401*9 Comments:

017K3.01 Question appears to match KIA. SAT. 2003 NRC exam. BANK Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 118 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 60 c QuestionBank

  1. IKA system IKA number I 566 I SYS027 I KS.OI I KA desc Knowledge of the operational implications ofthe following concepts as they apply to the CIRS: (CPR: 41.7 / 45.7)OPurpose of charcoal filters ........................................

Unit 1 was operating at 100% when a design basis LOCA occurred.

Radiation monitoring teams at the site boundary report that Iodine 131 dose is 5 Rem. Which one of the following statements correctly describes the condition of the VE filters that would result in the dose readings noted at the site boundary?

A. 1 A VE train failed to start on the safety injection B. The prefilter/demisters are saturated C. The charcoal filters are saturated D. The HEPA filters are saturated Tuesday, November 18, 2008 Page 119 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination General Discussion IBank Question:

834 Answer A Discussion Incorrect:

Heaters are supposed to be energized.

Plausible:

If the candidate does not know the heater function.

Answer B Discussion Incorrect:

Prefilter/dernister do not remove Iodine. Plausible:

If the candidate does not know the prefilter function.

Answer C Discussion ICorrect:

Answer D Discussion Incorrect:

HEP A filters do not remove radioactive Iodine Plausible:

REP A filter remove small particulates Job Level Cognitive Level Question Type RO Developed D OPT Approved D OPS Approved NRC Approved Memory BANK Development References

1. OP-CN-CNT-VE pages 5-6 QuestionBank
  1. IKA system IKA number I 5661SYS027 IKS.Ol I KA desc QUESTION 60 Question Source 2003 NRC Q41 (Bank 241) Student References Provided Knowledge of the operational implications of the following concepts as they apply to the CIRS: (CFR: 41.7 I 45.7)DPurpose of charcoal filters 401*9 Comments:

027KS.Ol Question appears to match KJ A. Stem Focus -Radiation monitoring teams would measure actual dose not projected dose. Could we change distractor D to read heaters are de-energized?

2003 NRC exam. BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 120 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 61 QuestionBank

  1. IKA system IKA number I 567 I SYS035 I 2.2.40 I KA desc SYS035 GENERICDAbility to apply Technical Specifications for a system. (CFR: 41.10 /43.2 / 43.5/45.3)

Unit 1 is in Mode 5 following refueling.

All S/Gs were drained and have just been refilled with condensate water per Chemistry request. The following conditions existed during the filling operation and have been verified to be the current conditions:

Primary conditions:

  • 1A ND Hx inlet temperature 185 OF
  • 1 B ND Hx inlet temperature 185 OF
  • NC pressure 218 psig Secondary conditions:
  • S/G 1A CF inlet temperature 71°F
  • S/G 1B CF inlet temperature 72 OF
  • S/G 1 C CF inlet temperature 68 OF
  • S/G 1 D CF inlet temperature 71°F
  • All S/Gs pressures are 0 psig. Based on the reported conditions, what is the action required by Selected License Commitments?

A. Increase 1C S/G secondary temperature to greater than 70 OF within 30 minutes. B. Increase 1C S/G secondary temperature to greater than 70 OF within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. C. Reduce NC pressure to less than or equal to 200 psig within 30 minutes. D. Reduce NC pressure to less than or equal to 200 psig within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Tuesday, November 18,2008 Page 121 of 200 c I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 61 c General Discussion The correct action is to reduce NC pressure within 30 minutes to <200 psig. All ACTIONS MUST BE COMPLETE if the CONDITION is entered. Therefore, cannot increase temperature to get out of the action. mrs ONE NEEDS WORK Answer A Discussion Cannot increase temperature to revent having to do the actions. Correct time Answer B Discussion Cannot increase temperature to revent having to do the actions. Answer C Discussion Answer D Discussion IIncorrect:

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> will not meet the action. Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Memory QuestionBank

  1. KA system 567 SYS035 KA desc BANK Development References Lesson D OP-CN-CF-SG ObjectivesD25 REFERENCESDSLC 16.5-7 KA number 2.2.40 Question Source 2005 NRC Q86 (Bank 490) Student References Provided SYS035 GENERICDAbility to apply Technical Specifications for a system. (CFR: 41.10/43.2/43.5/45.3) 401-9 Comments:

035G2.i.40 Questions appears to match KIA. 2005 NRC exam. SAT BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 122 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 QuestionBank

  1. IKA system IKA number I 568 I SYS045 I A3.05 I KA desc Ability to monitor automatic operation of the MT/G system, including: (CPR: 4117 /

control ................................... ...... Unit 1 is operating at 100% power. 1. H,?w is EHC Emergency Manual Mode selected?

2. How do the control valves respond to a manual run back under the above conditions?

A. 1. automatically

2. the control valves will operate per the valve curves B. 1. automatically
2. the control valves will NOT operate per the valve curves C. 1. manually 2. the control valves will operate per the valve curves D. 1. manually 2. the control valves will NOT operate per the valve curves Tuesday, November 18, 2008 Page 123 of 200 B FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 62 General Discussion Emerg manual mode cannot be manually selected.

When the valves are operated (in manual using CV lower), all valves will stroke simultaneously without regard for the programmed valves curves Answer A Discussion lfirst part true second part false. Answer B Discussion Answer C Discussion Iboth parts false -psychometric balance Answer D Discussion lfirst part is wrong, second part is true Job Level Cognitive Level QuestionType Question Source RO Memory NEW B Developed Development References Student References Provided OPIl/B/6 I 00/0 lOB D OPT Approved EHC lesson D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5681SYS045 IA3.05 I KA desc Ability to monitor automatic operation of the MT/G system, including: (CFR: 4117 / 45.5)DElectrohydraulic control 401-9 Comments:

045A3.05 Question appears to match KIA. Distractors C and D are not plausible.

Is there such a thing as a manual runback? Are you talking about manually ramping load off of the turbine? This question needs some work. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 124 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 63 A QuestionBank

  1. IKA system IKA number I 569 I SYS071 I K4.01 I KA desc Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)DPressure capability of the waste gas decay tank .......................

Which one of the following Shutdown Waste Gas Decay Tanks (SWGDTs) is maintained at a low pressure per the limits and precautions of OP/0/A/6500/003A (Gaseous Waste System (Normal Operations))

and what maximum pressure does it specify? A. SWGDT A; less than 5 psig B. SWGDT A; less than 30 psig C. SWGDT B; less than 5 psig D. SWGDT B; less than 30 psig Tuesday, November 18, 2008 Page 125 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 63 General Discussion A WGDT pressure is normally limited to 5 psig per the OP to allow it to receive relief from other tanks. B tank has a different function-it is used to store nitrogen for shutdown.

The hydrogen recombiner operation limit and precaution requires 30 pisg minimum for proper operation.

Answer A Discussion ICORRECT Answer B Discussion IRight tank , wrong pressure Answer C Discussion IWrong tank, correct pressure Answer D Discussion IBoth wrong, psychometric balance. Job Level Cognitive Level QuestionType RO Developed o OPT Approved OOPS Approved NRC Approved Memory NEW Development References WG lesson plan page 6 OP/0/A/6500/003 B LIP OP/0/A/6500/003 A LIP QuestionBank

  1. IKA system IKA number I 5691SYS071 IK4.01 I KA desc Question Source Student References Provided Knowledge of design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)DPressure capability of the waste gas decay tank ...................... . 401-9 Comments:

071K4.01 Question does not really meet the KIA. At what pressure do the relief valves lift? I did not see this in your lesson plan. Add a statement to the end of each choice "to allow room for pressure relief when the tank pressure reaches : ... NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 126 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 64 QuestionBank

  1. [KA system [KA number I 570 I SYS079 I A4.01 I KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8) DCross-tie valves with lAS ..........................................

VI system pressure is 98 psig. Which one of the following statements correctly describes the sequence and position of VI system valves in response to a loss of VI header pressure as presl?ure continues to decrease?

A. VS-78 (VS supply to VI) opens at 80 psig VI-SOO (VI supply to VS) opens at 76 psig B. VS-78 (VS supply to VI) closes at 80 psig VI-SOO (VI supply to VS) opens at 76 psig C. VI-SOO (VI supply to VS) closes at 80 psig VS-78 (VS supply to VI) opens at 76 psig D. VI-SOO (VI supply to VS) closes at 80 psig VS-78 (VS supply to VI) closes at 76 psig Tuesday, November 18, 2008 Page 127 of 200 c FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination General Discussion IBank Question:

282.2 Answer A Discussion Incorrect:

VI-500 closes -not opens Plausible:

partially correct -VS-78 opens Answer B Discussion Incorrect:

valve operations are reversed Plausible:

psychometric balance Answer C Discussion Answer D Discussion Incorrect:

VS-78 opens -does not close Plausible:

partially correct -VI-500 closes. Job Level Cognitive Level RO Memory Question Type MODIFIED QUESTION 64 Question Source 2003 NRC Q7 (Bank 207) c Developed Development References Student References Provided o OPT Approved OOPS Approved NRC Approved OP-CN-SS-VI page 21 Lesson Plan Objective:

VI Obj: 5, 8, 28, 30 AP-22 QuestionBank

  1. IKA system IKA number I 570lSYS079 IA4.01 I KA desc Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)DCross-tie valves with lAS 401-9 Comments:

079A4.01 Question kind of matches KIA. There is no sequence in the distractors, they are all in the same order. At what pressure dQ the valves perform the swap? How can an operator monitor them with out knowing the pressure that should operate? Not very discriminating.

2003 NRC exam question.

BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 128 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 65 A QuestionBank

  1. IKA system IKA number I 571 I SYS086 I K6.04 I KA desc Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7/ 45.7)DFire, smoke, and heat detectors

.....................................

Given the following conditions and sequence of events:

  • 2A DIG auto-started due to a blackout on 2ET A
  • The control room crew notes all loads were sequenced on as required
  • A fuel oil line leak occurs resulting in a major fire in the 2A DIG room Assuming no operator actions since the DIG auto-started:
1. How long will it take for the Cardox system to discharge once the fire is detected?
2. What is the status of the 2A DIG emergency ventilation after the Cardox system discharges?

A. 1. 6.5 minutes 2. Running due to sequencer actuation B. 1. 6.5 minutes 2. Secured due to Cardox actuation C. 1. 1.5 minutes 2. Running due to sequencer actuation D. 1. 1.5 minutes 2. Secured due to Cardox actuation Tuesday, November 18, 2008 Page 129 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE A ZOOS SRO NRC Examination QUESTION 65 General Discussion The DIG ventilation will start following the autostart after the B/O signal, since the sequencer has not been reset, they will continue to run. The cardox actuation would normally shutdown the ventialtion system. There is a 5.0 electronic time followed bya 1.5 min pneumatic timer. Were there a loss of power to the cardox system, the 5 min electronic timeer would not work and the cardox would dump at 1.5 minutes. Answer A Discussion Answer B Discussion Icorrect time, but fans run Answer C Discussion lincorrect time, fan status is correct Answer D Discussion IBoth incorrect pyschometric balance Job Level Cognitive Level Question Type Question Source RO Memory NEW Developed Development References Student References Provided RFY lesson 0 OPT Approved DG 1 lesson VD 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 571lSYS086 IK6.04 I KA desc Knowledge of the effect ofa loss or malfunction on the Fire Protection System following will have on the: (CFR: 41.7 I 45.7) o Fire, smoke, and heat detectors

.................................... . 401-9 Comments:

086K6.04 Question appears to match KIA. SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 130 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 66 D QuestionBank

  1. IKA system IKA number I 572 I GEN2.1 I 2.1.45 I KA desc Conduct of Operations 0 Ability to identitY and interpret diverse indications to validate the response of another indication. (CFR: 41.7 /43.5 / 45.4) During a control board walkdown, the crew notes that over the last 10 minutes turbine load has decreased from 1209 MW to 1207 MW while reactor power has increased from 99.87% to 100.05%. They suspect a steam leak. Which set of the following indications could be used to confirm their suspicions?
1. % Steam flow 2. Steam pressure 3. Containment pressure 4. Containment humidity A. 1,2,3 B. 1,2,4 C. 1,3,4 D. 2,3,4 Tuesday, November 18, 2008 Page 131 of200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 66 General Discussion Based on simulator modelling, a steam leak of lE4 #1hI would cause MW and Rx power indications as shown. Containment pressure would increase as well as humidity.

This is less than 1I100th of 1 % steam flow to any given S/G (3.

  1. /hr) and would not be useful in diagnosing a steam leak. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType RO Comprehension NEW Developed OPT Approved D OPS Approved NRC Approved QuestionBank
  1. IKA system 572IGEN2.1 KA desc Development References AP/28 IKA number I 1 2.1.45 1 Question Source Student References Provided Conduct of Operations D Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 I 43.5 I 45.4) 401-9 Comments:

G2.1.45 Question appears to match KIA. Do you have a % steam flow indicator?

I don't think so? Need another name for #1. Otherwise it is not plausible.

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 132 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 67 I 573 I GEN2.1 I 2.1.8 I KA desc Conduct of Operations D Ability to coordinate personnel activities outside the control room. (CPR: 41.1 0 /45.5 / 45.12 / 45.13) Terrorists have broken through the security fence and set both Unit 1 main transformers on fire. Security has notified the operating crew that several terrorists are enroute to the control room. What instructions are provided to the NLO dispatched to the 1 ETA switchgear room and which procedure provides that guidance?

A. Perform a partial transfer to the SSF per AP/11A155001017 (Loss of Control Room) B. Transfer control to the SSF per API1/A/55001017 (Loss of Control Room) C. Perform a partial transfer to the SSF per AP/OIAl55001045 (Plant Fire) D. Transfer control to the SSF per AP/O/A/55001045 (Plant Fire) Tuesday, November 18, 2008 Page 133 of 200 B I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 67 B General Discussion API17 is used due to being a security event. A full transfer is done for a security event. Answer A Discussion Partial transfer is done in AP/45 for plant fires but not per AP/17 Answer B Discussion Answer C Discussion Partial transfers are done per AP/45 when fires exist in certain vital area (this is not) and there is a fire, however the security event takes priority.

Answer D Discussion IFull control is not transferred to the SSF in AP/45. Job Level Cognitive Level QuestionType RO Developed D OPT Approved D OPS Approved NRC Approved Memory QuestionBank

  1. KA system 573GEN2.1 KA desc NEW Development References AP/17 ENCL 11 AP/45 AP/17 Symptoms AP/17 step Sc KA number 2.1.S Question Source Student References Provided Conduct of Operations D Ability to coordinate personnel activities outside the control room. (CFR: 41.10 145.5 145.12 I 45.13) 401*9 Comments:.

G2.l.S Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 134 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 68 D QuestionBank

  1. IKA system IKA number I 574 I GEN2.2 I 2.2.2 I KA desc Equipment ControlDAbility to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2)

During a power increase to 100% power per OP/1/A161 001003 (Controlling Procedure for Unit Operation), the "C" Heater Drain Pumps are placed in service at a minimum power level of . The purpose of this is to prevent the potential for ___ _ A. 50% I excessive main feedwater pump discharge pressure B. 70% I excessive main feedwater pump discharge pressure C. 50% I deadheading of hotwell and booster pumps D. 70% I deadheading of hotwell and booster pumps Tuesday, November 18, 2008 Page 135 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 68 General Discussion C Heater drain pumps are placed in service at >70% to prevent the possibility of deadheading the hotwell and CBPs under certain transient conditions.

Since the C heater drain pumps pump to the suction of the CFPs, the student may think that the increases suction pressure might increase discharge pressure too high. The second CFP is placed in serivice at 50% Answer A Discussion Iboth parts false, psychometric balance Answer B Discussion lfirst part is true Answer C Discussion Isecond part is true Answer D Discussion Job Level Cognitive Level Question Type Question Source RO Memory NEW Developed Development References Student References Provided D OPT Approved CM Lesson plan OP/1/A/6100/003 D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5741GEN2.2 1 2.2.2 1 KA desc Equipment ControlDAbility to manipulate the console controls as required to operate the facility between shutdown and designated power levels. (CFR: 41.6/41.7/45.2) 401-9 Comments:

G2.2.2 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 136 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 69 A QuestionBank

  1. IKA system IKA number I 575 I GEN2.2 I 2.2.39 I KA desc Equipment ControlDKnow1edge ofless than or equal to one hour Technical Specification action statements for systems. (CFR: 41. 7 / 41.10/ 43.2 / 45.13) Unit 1 is at 4% power, conducting a plant startup. Given the following events and conditions: .
  • One control bank "A" rod drops fully into the core
  • NCS temperature decreases to 550°F Which one of the following statements correctly describes an action that is required within 30 minutes by Technical Specifications?

A. Be in mode 2 with Keff less than 1.0. B. Restore rod group within alignment limits. C. Verify shutdown margins within the limits specified in the COLR. D. Adjust power range Nils to increase reactor power so that reactor power and thermal power best estimate are equal. Tuesday, November 18, 2008 Page 137 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 69 General Discussion Answer A Discussion ICORRECT Answer B Discussion IRequired per 3.1.4 but not within 30 minutes Answer C Discussion IRequired per 3.1.6 but not within 30 minutes Answer D Discussion Thermal power would indicate lower not higher due to increased thermalization of the neutrons.

While NI adjustment is a problem, this action does not comply with action 3.4.2. Job Level Cognitive Level QuestionType Question Source RO Comprehension MODIFIED 2003 NRC Q30 (Bank 230) Bank Question:

600 Developed Development References Student References Provided D OPT Approved Lesson Plan Objective:

NC SEQ 10

References:

D OPS Approved 1. OP-CN-PS-NC page 33 2. Tech Spec 3.4.2 page 1 NRC Approved TS 3.1.4, 3.1.6 QuestionBank

  1. IKA system IKA number I 5751GEN2.2 12.2.39 I KA desc Equipment ControlDKnowledge ofless than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2/45.13) 401-9 Comments:

G2.2.39 Question appears to match KIA. SAT 2003 NRC Exam. Modified Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 138 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 QuestionBank

  1. IKA system IKA number I 576 I GEN2.31 2.3.11 I KA desc Radiation ControlDAbility to control radiation releases. (CFR: 41.11/43.4

/45.10) A Unit 1 containment purge is in progress using OP/11A16450/015.

Given the following events and conditions:

  • 1 EMF-39(L) (CONTAINMENT GAS (LO RANGE)) spiked to a Trip 2 condition then cleared Which one of the following statements correctly describes the action required?

A. The VP release may not be reinitiated until RP draws a new containment air activity sample. B. The VP release may be reinitiated after the spike clears. If 1 EMF-39 spikes a second time, the release may also be reinitiated.

C. The VP release may be reinitiated after the spike clears. If 1 EMF-39 spikes a second time, the release cannot be reinitiated without RP sampling containment air for activity.

D. The VP release may be reinitiated if grab samples are taken of Unit Vent activity during subsequent reinitiation.

Tuesday, November 18, 2008 Page 139 of 200 B I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 70 General Discussion Answer A Discussion Incorrect:

the OP allows the VP release to be reset twice if due to EMF spike. Plausible:

This is a conservative answer. Answer B Discussion Correct: the OP allows the VP release to be reset twice if due to EMF spike. Answer C Discussion Incorrect:

the OP allows the VP release to be reset twice if due to EMF spike. Plausible:

a new sample may be required if the EMF actuates prior to initiating the release. Answer D Discussion Incorrect:

the OP allows the VP release to be reset twice if due to EMF spike. Plausible:

grab samples are required ifEMF-39 is inoperable when the release occurs. Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2003 NRC Q54 (Bank 254) Bank Question:

968.3 B Developed Development References Student References Provided D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system 576GEN2.3 KA desc Lesson Plan Objective:

VP Obj: 8,9

References:

1. OP/I/A/6450/015, limits and precautions page 2 rev44 2. OP-CN-CNT-VP page 15 KA number 2.3.11 Radiation ControlDAbility to control radiation releases. (CFR: 41.11 143.4 I 45.10) 401-9 Comments:

401-9 Comments RESPONSE G2.3.11 Question appears to match KIA. SAT 2003 NRC Exam BANK Tuesday, November 18, 2008 Page 140 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 71 QuestionBank

  1. IKA system IKA number I 577 I GEN2.3 I 2.3.4 I KA desc Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 /43.4 /45.10) While performing a valve lineup in the boric acid mixing room, an air line failure caused a severe airborne beta contamination problem. A worker received both internal and external contamination that was detected upon attempting to exit the RCA. Which one of the exposures would exceed the 1 OCFR20 limit for the worker's annual shallow dose equivalent (SDE) exposure?

A. 55 Rem external dose to the lens of the eye. B. 55 Rem external dose to the leg below the knee. C. 17 Rem internal dose equivalent to the lens of the eye. D. 17 Rem internal dose to the right forearm. Tuesday, November 18, 2008 Page 141 of 200 B I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 71 General Discussion Answer A Discussion Incorrect:

skin dose equivalent Plausible:

50 Rem is correct limit for SDE -may confuse with LDE eye dose Answer B Discussion Correct: 50 Rem SDE limit to the extremities (below foreann and below knee) or skin. Answer C Discussion Incorrect:

SDE is an external skin or extremity dose not an internal dose Plausible:

this is the correct LDE limit (lens of the eye). Answer D Discussion Incorrect:

SDE is an external dose not an internal dose Plausible:

the right foreann is the correct part of the anatomy for an SDE -based on confusion of external/internal Job Level Cognitive Level QuestionType Question Source RO Memory BANK 2004 NRC Q 16 (Bank 316) B Developed Development References Student References Provided o OPT Approved OOPS Approved NRC Approved QuestionBank

  1. KA system 577GEN2.3 KA desc HP lesson KA number 2.3.4 Radiation ControlDKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 /43.4 / 45.10) 401-9 Comments:

G2.3.4 Question appears to match KIA. SAT 2004 NRC exam. BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 142 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE QUESTION 72 B 2008 SRO NRC Examination I 578 I GEN2.3 I 2.3.7 I KA desc I Radiation ControlDAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10) I A radiation worker is repairing a valve in a contaminated area, which has the following radiological characteristics:

  • The worker's present exposure is 1938 mrem for the year
  • The RWP states: o General area dose rate = 30 mrem/hr o Airborne contamination concentration

= 10.0 DAC The job will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the worker wears a full-face respirator.

It will only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the \NOrker does not wear the respirator.

If the RP Manager grants all applicable dose extensions, which one of the following choices for completing this job would maintain the worker's exposure within the station administrative requirements?

A. The worker should not wear the respirator.

The dose received wearing a respirator will exceed site annual personnel dose limits. B. The worker should not wear the respirator.

The calculated TEDE dose received will be less than if he does wear one. C. The worker should wear the respirator.

The calculated TEDE dose received will be less than if he does not wear one. D. The worker should wear the respirator.

He could exceed DAC limits. Tuesday, November 18, 2008 Page 143 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 72 B General Discussion Radiation exposure comparison:

Without respirator DDE = 30 mremlhr x 1 hr = 30 mrem From airborne contamination:

CEDE = 10 DAC 1 hr x 2.5 mremlDAC-hr

= 25 mrem TEDE = 30 + 25 = 55 mrem from job Total exposure for year = 1938 + 55 = 1993 mrem With respirator DDE = 30 mremlhr x 2 hr = 60 mrem CEDE = 0 TEDE = 60 mrem Total exposure for year = 1938 + 60 = 1998 mrem (With respirator) (Without respirator)

TEDE = 60 mrem > 55 mrem = do not use a respirator Answer A Discussion Incorrect:

the dose will not exceed the 2000 mrem limit based on calculation.

Plausible:

If the candidate miscalculates the dose Answer B Discussion ICorrect answer Answer CDiscussion Incorrect:

The calculated exposure will be greater if you wear the respirator.

Plausible:

If the candidate incorrectly computes the exposure -this was the correct answer on a previous exam Answer D Discussion Incorrect:

DAC limits are not direct ALARA controls.

Plausible:

If the candidate does not understand the concept of derived airborne concentrations.

Job Level Cognitive Level QuestionType RO Comprehension BANK Developed D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system 578GEN2.3 KA desc Development References Lesson Plan Objective:

HP Obj: 2,4 1. OP-CN-RAD-HP pages 14-15 KA number 2.3.7 Question Source 2003 NRC Qll (Bank 211) Bank Question:

353.3 Student References Provided Radiation ControlDAbility to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10) 401-9 Comments:

G2.3.7 Question appears to match KIA. 2003 NRC exam. BANK This question can be easily modified to be some what different than the bank question.

BANK Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 144 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 QuestionBank

  1. IKA system IKA number I 579 I GEN2.4 I 2.4.13 I KA desc Emergency Procedures

/ Plan 0 Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.1 0 /45.12) The crew is responding to a spurious safety injection.

Given the following validated CSF status tree indications:

  • Subcriticality

-GREEN

  • Core Cooling -GREEN
  • Heat Sink -GREEN
  • NC Integrity

-GREEN

  • Containment

-GREEN

  • NC Inventory

-YELLOW Per OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines):

1. Which control room crew position, by title, has primary responsibility for monitoring Critical Safety Function (CSF) status trees during EOP usage? 2. Based on current conditions how frequent should CSF status trees be monitored?

A. 1. OSM 2. monitor every 10-20 minutes B. 1. OSM 2. monitor continuously C. 1. STA 2. monitor every 10-20 minutes D. 1. STA 2. monitor continuously Tuesday, November 18, 2008 Page 145 of 200 c I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 73 c General Discussion Per OMP 1-7, C is correct green or yellow only is every 10-20 minutes, any red or orange is continuously.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system 579GEN2.4 KA desc OMP 1-7 OMP 1-8 KA number 2.4.13 Emergency Procedures

/ PlanO Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10/45.12) 401-9 Comments:

G2.4.13 Question appears to match KIA. Distractors B and D are not plausible.

Everyone with a license is responsible for CSFs. So why would a procedure not allow someone else with a license to be given the task of monitoring CSFs. Need better distractors.

NEW . Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 146 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 74 B QuestionBank

  1. IKA system IKA number I 580 I GEN2.4 I 2.4.22 I KA desc Emergency Procedures

/ Plan 0 Knowledge of the bases. for prioritizing safety functions during abnormal/emergem;yoperations. (CFR: 41.7 / 41.10/43.5

/45.12) Which one of the following sets of critical safety functions (CSFs):

  • is listed in the correct order per the CSF status trees from highest to lowest priority

A. 1. Heat Sink 2. Core Cooling 3. Integrity B. 1 . Core Cooling 2. Heat Sink 3. NC Inventory C. 1. Heat Sink 2. Subcriticality

3. NC Inventory D. 1. Subcriticality
2. Heat Sink 3. Integrity Tuesday, November 18, 2008 Page 147 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 74 B General Discussion Answer A Discussion IIncorrect:

Wrong order, wrong functions.

Answer B Discussion ICORRECT Answer C Discussion lright functions wrong order Answer D Discussion Iwrong functions, right order Job Level Cognitive Level QuestionType Question Source RO Comprehension NEW Developed Development References Student References Provided LessonDOP-CN-EP-CSF ObjectivesD2 D OPT Approved D OPS Approved NRC Approved REFERENCESDLesson plan information page 10 QuestionBank

  1. IKA system IKA number I 5801GEN2.4 1 2.4.22 I KA desc Emergency Procedures

/ PlanDKnowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CFR: 41.7 / 41.10/43.5

/45.12) 401*9 Comments:

G2.4.22 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 148 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 QuestionBank

  1. IKA system IKA number I 581 I GEN2.4 I 2.4.42 I KA desc Emergency Procedures

/ PianO Knowledge of emergency response facilities. (CFR: 41.10 /45.11) An offsite release is occurring due to a stuck open SIG PORV on 2C SIG which has a significant tube leak. Which one of the following states: 1. The emergency facility that assumes responsibility for communications with offsite agencies including the NRC once it is activated?

2. What is the lowest classification level that requires this facility's activation?

A. 1. Technical Support Center (TSC) 2. Alert B. 1. Technical Support Center (TSC) 2. Unusual Event C. 1. Operations Support Center (OSC) 2. Alert D. 1. Operations Support Center (OSC) 2. Unusual Event Tuesday, November 18, 2008 Page 149 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 75 A General Discussion Answer A Discussion Answer B Discussion Correct location, wrong classification.

The TSC can be activated at this level, but it is not REQUIRED.

Answer C Discussion Right level, wrong location.

This is the center in Charlotte.

The NRC and offsiote agency communications go thru the TSC Answer D Discussion IBoth wrong -psychometric balance. Job Level Cognitive Level QuestionType Question Source RO Memory NEW Developed Development References Student References Provided o OPT Approved OOPS Approved NRC Approved QuestionBank

  1. KA system 581 GEN2.4 KA desc SEP lesson KA number 2.4.42 Emergency Procedures

/ PlanDKnowledge of emergency response facilities. (CFR: 41.1 0 /45.11) 401-9 Comments:

G2.4.42 Question appears to match KIA. SAT NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 150 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 76 D QuestionBank

  1. IKA system IKA number I 582 I EPEOO9 I 2.2.25 I KA desc EPE009 GENERIC DKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 1 41.7/43.2)

Given the following Unit 1 conditions and sequence of events:

  • NC system temperature is 208 OF
  • NC system pressure is 350 psig
  • 1A NV pump is red tagged to replace its 1 ETA breaker
  • 1B NI pump is white tagged
  • An NO pump suction relief has spuriously lifted and has not reseated
  • Both NO pumps have been secured per AP/1/A/55001027 (Shutdown LOCA) 1. What is the correct procedure flowpath for this situation?
2. What is the limiting component that the current ECCS pump configuration is designed to protect from over-pressurization?

A. 1. Remain in AP/1/A/55001027 (Shutdown LOCA) 2. NC loop crossover pipe B. 1. Transition to AP/1/A/55001019 (Loss of Residual Heat Removal System) 2. NC loop crossover pipe C. 1. Remain in AP/1/A/55001027 (Shutdown LOCA) 2. Reactor vessel O. 1. Transition to AP/1 IA/55001019 (Loss of Residual Heat Removal System) 2. Reactor vessel Tuesday, November 18, 2008 Page 151 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 76 General Discussion this is Mode 4 LTOP condition.

AP/27 secured ND pumps and thenn transition is made to AP/19 for additiional actions. Or AP/l9 can be entered directly.

Second part isd the basis for LTOP to make SRO. Answer A Discussion Iboth parts incorrect

-psychometric balance Answer B Discussion ICORRECT Answer C Discussion lfirst part correct Answer D Discussion Isecond part correct Job Level Cognitive Level QuestionType SRO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References TS 3.5.2 Bases AM lesson QuestionBank

  1. IKA system IKA number I 5821EPE009 12.2.25 1 KA desc Question Source Student References Provided EPE009 GENERlCOKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 I 41.7 I 43.2) 401-9 Comments:

009EG2.2.25.

Question appears to match the KIA. Does not appear to be SRO only. While the question does address some items from the TIS basis, the ECCS acceptance criteria and what pumps are required during an event are RO knowledge.

Stem Focus is also somewhat confusing. (Large small break LOCA) (Which ECCS pumps are credited for this event) The question appears to be asking "what are the ECCS acceptance criteria for fuel clad temperature?" 4700 degrees F is not a plausible Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 152 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination.

QUESTION 77 QuestionBank

  1. IKA system IKA number J 583 I EPEOII I 2.2.36 I KA desc EPEOII GENERIC 0 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status oflimiting conditions for operations. (CFR: 41.10/43.2/45.13)

Unit 2 is at 3% power. Given the following sequence of events: 12/01/08 1100 2A NI pump tagged to replace the motor cooler. 12/03/08 0500 2B DIG tripped on high vibration during performance of PT/2/A/43501002B (Diesel Generator 2B Operability Test). 12/03/08 0700 You complete turnover and take the position ofCRS. 1. What is the latest time that entry into Mode 3 is required per Technical Specifications assuming both components remain inoperable?

2. When you take shift duty at 0700, can the ECCS design criteria for a large break LOCA be assumed to be met? A. 1. 12/03/08 1200 2. Yes B. 1. 12/03/08 1200 2. No C. 1. 12/03/08 1600 2. Yes D. 1. 12/03/08 1600 2. No Tuesday, November 18, 2008 Reference provided Page 153 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 77 General Discussion This tests knowledge of the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> additional time before redundant equipment is declared inoperable after the DIG is declared inoperable.

Until that time 3.0.3 does not apply to this situation after that, 3.0.3 is entered. Answer A Discussion this is the time for 3.0.3 without the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; second part correct Answer B Discussion this is the time for 3.0.3 without the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; still within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> window, therefore 2B NI is assumed to be operable.

Answer C Discussion Icorrect Answer D Discussion correct time, still within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> window, therefore 2B NI is assumed to be operable.

Co Job Level Cognitive Level QuestionType SRO Comprehension NEW Developed Development References T.S. 3.5.2 and basis 0 OPT Approved T.S. 3.8.1 and basis 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5831EPEOli 1 2.2.36 I KA desc Question Source Student References Provided Technical Specification 3.5.2 Technical Specification 3.8.1 EPEOll GENERlCDAbility to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 I 43.2 145.13) 401*9 Comments:

0IIEG2.2.36 Question appears to match the KIA. Reference for question 77 could help answer question 76. Appears to be SRO only. Stem Focus is also confusing.

Try "assuming that components remain inoperable." Second question discussing ECCS Criteria.

Enhancements needed. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 154 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 78 B QuestionBank

  1. IKA system IKA number I 584 I APE026 I AA2.05 I KA desc Ability to detennine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 / 45.13)OThe nonnal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS ........................

Unit 2 is at 100% power when an NLO reports the breaker for 2KC-56A (KC To NO Hx 2A Sup Isol) looks damaged. Upon investigation, the crew determines that 2KC-56A (KC To NO Hx 2A Sup Isol) will not open. What is the minimum flow required through this valve when aligned for cold leg recirculation and for the situation above, what system is required to be declared inoperable?

A. 5000 gpm / 2A Train of KC B. 5000 gpm / 2A Train of NO C. 5700 gpm / 2A Train of NO O. 5700 gpm / 2A Train of KC Tuesday, November 18, 2008 Page 155 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 78 General Discussion KC SR is modified by a Note indicating that the isolation of the CCW flow to individual components may render those components inoperable but does not affect the OPERABILITY of the CCW System. Per EPIES-1.3, 5000 per train is required.

5700 gpm is the miniflow given in ARP. Answer A Discussion ICorrect flow with incorrect TS. Answer B Discussion Answer C Discussion IIncorrect flow but correct TS Answer D Discussion IIncorrect flow and TS Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Developed Development References Student References Provided TSB 3.7.7 0 OPT Approved ES 1.3 0 OPS Approved OP/1/A/6100/010J KC56ADBD NRC Approved QuestionBank

  1. IKA system IKA number I 5841APE026 IAA2.05 I KA desc Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR: 43.5 / 45.13)DThe normal values for CCW -header flow rate and the flow rates to the components cooled by the CCWS .........*..............

401-9 Comments:

026AA2.05 Question Kind of matches KIA. There is not really a loss of the CCW system, but it is a loss of a control function of the system that effects CCW flow to the ND system. Stem Focus, second part of stem should read and what system is required to be declared inoperable?

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 156 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 79 B QuestionBank

  1. IKA system IKA number I 585 I APE057 I 2.4.21 I KA desc APE057 GENERICDKnowledge 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. (CFR: 41.7 /43.5 /45.12) Unit 1 is at 12% power following a refueling outage. Given the following conditions and sequence of events: 1200 1 NCPS880 (NC Loop 1B Cold Leg Temp) failed low 120S Unit 1 separated from the grid; the main turbine is carrying all in-house loads 1210 The crew has tripped the reactor, safety injected and entered EP/1/A1S000/E-0 (Reactor Trip or Safety Injection) based on the following indications:

o Charging flow is 12S gpm with letdown isolated o PZR level is decreasing as a rate of O.S% 1m in ute 1213 1 EDA loses all power due to a fault 1220 The crew is preparing to kick out of EP/1/A/SOOO/E-0 and notes the following indications:

o Containment pressure is stable at 0.08 psig o All S/G pressures are stable at 1100 psig o 1 EMF-33 (Condenser Air Ejector Exhaust) Trip 2 is LIT o Off-normal Critical Safety Function status as follows:

  • Containment is MAGENTA
  • Core Cooling is ORANGE
  • Heat Sink is YELLOW
  • NC Integrity is RED
  • NC Inventory is YELLOW What is the next procedure to be entered? A. Enter EP/1/A/SOOO/E-1 (Loss of Reactor or Secondary Coolant) B. Enter EP/1/A/SOOO/E-3 (Steam Generator Tube Rupture) C. Enter EP/1/A/SOOO/FR-C.2 (Response to Degraded Core Cooling) D. Enter EP/1/A/SOOO/FR-P.1 (Response to Imminent Pressurized Thermal Shock) Tuesday, November 18, 2008 Page 157 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 79 B General Discussion Based on plant conditions the student should be able to determine that a tube rupture is the most likely accident.

P.1 and C.2 are invalid due to the Tcold failure and loss of power to EDA respectively.

A is correct. E3 is correct because there are indications of some type ofNC inventory loss, however, since containment conditions are noraml, it should be deduced that it is a S/G tube leak along with the indications that EMF 33 is in alarm. Answer A Discussion some indications ofLOCA outside containment, but containment conditions are nominal. Answer B Discussion ICORRECT Answer C Discussion If red path is invalid and orange path is valid, then this would be the correct answer. Answer D Discussion lif red path wer valid this would be correct. Job Level Cognitive Level QuestionType SRO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References TS 3.3.2 basis AP29 QuestionBank

  1. IKA system IKA number I 5851APE057 12.4.21 1 KA desc Question Source Student References Provided APE057 GENERICDKnowledge 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. (CFR: 41.7/43.5/45.12) 401-9 Comments:

057AG2.4.21 Question Kind ofrnatches KIA. Not SRO knowledge.

This questions tests whether the containment spray bistables are energize to actuate, or de-energize to actuate and why. Both of these are systems knowledge.

Distractors A and C are not plausible.

Why would a Bistable lit prevent actuation of a safety system? NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 158 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 80 QuestionBank

  1. IKA system IKA number I 586 I APE058 I AA2.03 I KA desc Ability to detennine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 / 45.13)ODC loads lost; impact on ability to operate and monitor plant systems .... Given the following:
  • Unit 2 was operating at 100%.
  • At 1000, charger 2ECA output breaker opened due to an overvoltage condition.
  • The 2EDA tie breaker to 2EDC can not be closed.
  • At 1130, battery 2EBA voltage dropped below the voltage required per Technical Specifications.

Which one of the following describes the latest time that bus 2EDA can be restored to prevent entering a shutdown action and which procedure will be entered initially to respond to this failure? A. 1200; EP/2IAl5500/E-O (Reactor Trip or Safety Injection)

B. 1200; AP/21A155001029 (Loss of Vital or Aux Control Power) C. 1330; EP/21A15500/E-0 (Reactor Trip or Safety Injection)

D. 1330; AP/21A155001029 (Loss of Vital or Aux Control Power) Tuesday, November 18, 2008 Page 159 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 80 General Discussion Loss of EPA causes Reactor Trip but this does not occur until batteries are used up. EP /E-O would take precedence over AP 129 once a trip occurs and AP 129 would be used after crew exits E-O and enters ES-O 1. However in this case, the reactor does not trip sinc abttery will carry load for some time period. Correct action is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for DC. EDA does not become inoperable until the battery voltage drops below TS limits per the basis ofTS 3.8.9 Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType SRO Developed OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References TS 3.8.9 EPL lesson QuestionBank

  1. IKA system IKA number I 5861APE058 IAA2.03 I KA desc Question Source Student References Provided Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 1 45.13)ODC loads lost; impact on ability to operate and monitor plant systems .... 401-9 Comments:

058AA2.03 Question does not really meet the KIA. What DC loads were lost? I am sure that if the unit trips that some loads were lost. I also realize that the entering ofE-O implies that the loss of dc (impact) caused the reactor to trip. Question was also marked as a memory level question.

A reference is also provided.

If this is a memory level question then a reference should not be required.

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 160 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 81 B QuestionBank

  1. IKA system IKA number I 587 I APE077 I AA2.09 I KA desc Ability to detennine and interpret the. following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 /45.5, 45.7, and 45.8) 0 Operationar status of emergency diesel generators

........................

Unit 1 is operating at 100% power. Unit 2 is in a refueling outage with 2EMXH aligned to Unit 1 power. Given the following conditions and sequence of events: 0530 1AD-11, G/6 "SWGR 1 ETA DEGRADED BUS VOLTAGE" is LIT 1 AD-11 , H/6 "SWGR 1 ETB DEGRADED B US VOLTAGE" is LIT 1AD-11, Kl6 "230KV SWITCHYARD VOLTAGE LO" is LIT 0535 The ST A notes by OAC trends that 1 ETA and 1 ETB minimum voltages were 3620V and 3637V respectively and are now increasing.

1. At 0530, what is the earliest time required for Unit 1 to enter Mode 3 per Technical Specifications?
2. At 0535, assuming no operator actions, what is the status of DIG 1A and DIG 1B? A. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to TS 3.0.3; both running B. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to TS 3.0.3; both secured C. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to TS 3.7.5 (Auxiliary Feedwater (AFW) System); both running D. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to TS 3.7.5 (Auxiliary Feedwater (AFW) System); both secured Tuesday, November 18, 2008 Page 161 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 81 B General Discussion At 90% voltage a 10 min timer starts to intiate aBO of the essential busses. This time is 5 seconds if a LOCA has occurred (in this case the DIGs would start and load). Also, if voltage decreases to approximately 84%

the DIG would start and load. Neither of these situations occurred so the DIGs are not started. The annunciators imply a grid disturbance.

With degraded bus voltage shared systems VA, RN and VCYC are in 3.0.3. The RN procedure refers to RN, VCYC and CA when various protions ofRN are inoperable thereby making CA a valid distractor.

Answer A Discussion I Wrong DIG status Answer B Discussion ICORRECT Answer C Discussion IBoth parts wrong -psychometric balance Answer D Discussion Iwrong TS acton Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Developed Development References Student References Provided D OPT Approved EQB lesson EPA lesson D OPS Approved OP/1/B/61001010L 1AD-ll Annun resp NRC Approved QuestionBank

  1. IKA system IKA number I 5871APE077 IAA2.09 I KA desc Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (GFR: 41.5 and 43.5 145.5, 45.7, and 45.8) DOperational status of emergency diesel generators

....................... . 401-9 Comments:

077 AA2.09 Question appears to match KJ A. May not be SRO only. Determining if the DIGs will be running based on voltage is RO knowledge.

TIS entry conditions are also RO knowledge.

This question is somewhat convoluted.

Need to understand why this is SRO knowledge at CNS. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 162 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 82 B QuestionBank

  1. IKA system IKA number I 588 I APE024 I 2.2.39 I KA desc APE024 GENERIC o Knowledge ofless than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/

43.2/45.13)

Unit 1 is in Mode 1. 1. With a Boric Acid Tank (BAT) temperature of 63°F, what is the most limiting required Technical Specification/Selected License Commitment action time? 2. What plant event requires emergency boration using 1 NV-236B (Boric Acid to NV Pumps Suct)? A. 1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2. In response to an ATWS B. 1. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2. In response to an ATWS C. 1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2. When control rods are below the Lo-Lo insertion limits D. 1. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2. When control rods are below the Lo-Lo insertion limits Tuesday, November 18, 2008 Page 163 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 82 B General Discussion Both procedures direct use of emergency boration but must be in Mode 3 to use it in API O. FWST level is a one hour action, BAT is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> BAT is the suction source for emerg boration.

Answer A Discussion lright procedure, wrong time Answer B Discussion ICORRECT Answer C Discussion Iboth wrong, psychometric balanc Ariswer D Discussion Iwrong procedure, right time Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Developed Development References Student References Provided TS 3.5.4 and basis 0 OPT Approved 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5881APE024 1 2.2.39 1 KA desc APE024 GENERlCDKnowledge ofless than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7/41.10/

43.2 /45.13) 401-9 Comments:

024AG2.2.39 Does not really meet KIA. Not SRO only, this is system knowledge for ROs. There does not appear to be a need for an emergency boration, this meets the generic application, but the not the emergency boration abnormal?

Question as written is Unsat. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 164 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 83 D QuestionBank

  1. IKA system IKA number I 589 I APE068 I 2.4.21 I KA desc APE068 GENERICDKnuwledge 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. (CFR: 41.7 /43.5 /45.12) Unit 1 is operating at 100% power. Unit 2 is in No Mode. The control room has, become uninhabitable due to chlorine gas intrusion and control has been shifted to the Auxiliary Shutdown Complex per AP/1/A/55001017 (loss of Control Room). 1. How is adequate primary side inventory assured? 2. For the situation above, which one of the following sets of valves would require a temporary modification to prevent them from automatically aligning should a safety injection occur? A. 1. Automatic swap of NV pump suctions to the FWST 2. 1 NI-9A (NV Pmp C/l Inj Isol) and 1 NI-1 OB (NV Pmp C/l Inj Isol) B. 1. Automatic swap of NV pump suctions to the FWST 2. 1 NO-26 (NO Hx 1 A Outlet Ctrl) and 1 NO-60 (NO Hx 1 B Outlet Ctrl) C. 1. Manual swap of NV pump suctions to the FWST 2. 1 NI-9A (NV Pmp C/l Inj Isol) and 1 NI-1 OB (NV Pmp C/l Inj Isol) O. 1. Manual swap of NV pump suctions to the FWST 2. 1 NO-26 (NO Hx 1A Outlet Ctrl) and 1 NO-60 (NO Hx 1B Outlet Ctrl) Tuesday, November 18, 2008 Page 165 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 83 General Discussion The design basis for the ASP does not allow for a DBA concurrent with its operation.

When swapped to the ASP the interlock for automatic swap ofNV pump suctions is defeated and manually is perfromed by procedure at 23% VCT level. 4% is the correct swap setpoint for autoswap.

The ASP Complex consists of a variety of panels and is capable of attaining and maintaining mode 5 conditions.

The ND HX BYPASS valves are controlled via manual loader outside the NDINS pump room Ni9 and 10 do not need to be jumpered .. Valve NI9A will close when control is transferred to Auxiliary Shutdown Panel (ASP) A. Interlocks are installed in the valve control circuit so that the valve can not be opened, either from the Control Room or by the Solid State Protection System, when control is transferred to the ASP A. Valve NIlOB will close when control is transferred to Auxiliary Shutdown Panel (ASP) B. Interlocks are installed in the valve control circuit so that the valve can not be opened, either from the Control Room or by the Solid State Protection System, when control is transferred to the ASP B. ND valves fail open on a SI when at the ASP. Answer A Discussion IBoth wrong Answer B Discussion lfirst part wrong, second part right Answer C Discussion Isecond part wrong, first part right Answer D Discussion ICORRECT Job Level Cognitive Level Question Type Question Source SRO Memory NEW Developed Development References Student References Provided API17 and basis OPT Approved D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5891APE068 12.4.21 1 KA desc APE068 GENERIC 0 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, contaimnent conditions, radioactivity release control, etc. (CFR: 41.7 /43.5 /45.12) 401*9 Comments:

068AG2.4.21 Question appears to meet the KJA. Not SRO only. The question has two parts, how is primary side inventory assured from the ASP, and will the ASP combat a Design Basis Accident.

Both of these items are basic system functions (what is the ASP designed to do) and are RO knowledge.

NEW* Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 166 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 84 A QuestionBank

  1. IKA system IKA number I 590 I APE069* I AA2.01 I KA desc Ability to detennine and interpret the following as they apply to the Loss ofContainrnent Integrity: (CPR: 43.5 / 45. 13) D Loss of containment integrity

......................................

Assuming no additional actions, which one of the following situations will result in a required Technical Specification shutdown within the next 30 days? A. 1 VI-77B (VI Cont Isol) fails in an intermediate position B. Both lower personnel airlock doors closed and locked with both seals deflated on the outer door only C. Both upper personnel airlock doors closed and locked with the airlock door interlock mechanism inoperable D. 1VQ-15B (ContAir Add Cont Isol) fails in an intermediate position and 1 VQ-16A (Cont Air Add Cont Isol) is closed and de-activated Tuesday, November 18, 2008 Page 167 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 84 A General Discussion Answer A Discussion ICORRECT (not in compliance with 3.6.3 (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to take action and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to shutdown.

Answer B Discussion TS 3.6.2 is being complied with, no shutdown required . . Answer C Discussion TS 3.6.2 is being complied with, no shutdown required.

Answer D Discussion TS 3.6.3 is being complied with, no shutdown required.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Developed Development References Student References Provided D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 59olAPE069 1 AA2*Ol I KA desc Ability to determirie and interpret the following as they apply to the Loss of Containment Integrity: (CFR: 43.5 / 45.13) DLoss of containment integrity

..................................... . 401-9 Comments:

401-9 Comments RESPONSE 069AA2.01 Question does not meet KIA. This question is written for WE 14 High Containment Pressure EA2.l. The APE for containment integrity in concerned with integrity as is applies to normal at power operation.

What would be considered a loss of containment integrity at 100% power etc. The question as written is also not SRO only. CSF entry conditions and major notes and cautions in procedure are RO knowledge.

NEW Tuesday, November 18, 2008 Page 168 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 85 QuestionBank

  1. IKA system IKA number I 591 I WE16 I EA2.1 I KA desc Ability to detennine and interpret the following as they apply to the (High Containment Radiation) (CFR: 43.5/ 45.13)DFacility conditions and selection of appropriate procedures during abnonnal and emergency operations.

Regarding the use of EP/1/A/5000/FR-Z.3 (Response To High Containment Radiation

): 1. At what minimum reading on 1 EMF 53A (Containment High Range) is the YELLOW path for Containment High Radiation valid? 2. What mitigative strategy does this procedure direct to reduce activity in the containment atmosphere?

A. 1. 35 R/hr 2. Start Containment Auxiliary Charcoal Filter Units. B. 1.15Rlhr 2. Start Containment Auxiliary Charcoal Filter Units. C. 1. 35 Rlhr 2. Ensure the VE system is in service and vent containment to the annulus using the VY system. D. 1. 15 Rlhr 2. Ensure the VE system is in service and vent containment to the annulus using the VY system. Tuesday, November 18, 2008 Page 169 of200 A FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 85 A General Discussion H2 removal is plausible because the VB filters will get saturated with H2 ifH2 Purge is used. 15 R is eye lens dose equivalent.

No other dose RATEs were available.

Answer A Discussion ICORRECT Answer B Discussion Iwrong dose rate Answer C Discussion Iwrong system Answer D Discussion Iboth wrong Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Developed Development References Student References Provided VV lesson D OPT Approved F-O D OPS Approved RP-O.l NRC Approved QuestionBank

  1. IKA system IKA number I 5911WE16 IEA2.1 I KA desc Ability to determine and interpret the following as they apply to the (High Containment Radiation) (CFR: 43.5/ 45.13)DFacility conditions and selection of appropriate procedures during abnormal and emergency operations.

401-9 Comments:

WE 16EA2.1 Question does not totally meet the K/ A. There is no procedure selection.

The applicant is given what procedure is to be implemented in the Stem. However, there is some value in the setpoint that requires entry into the procedure, this is RO knowledge.

The basis statements are really the function of a charcoal filter. This is also RO (radiation worker knowledge).

Therefore the question is not SRO only. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 170 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 86 B QuestionBank

  1. [KA system [KA number [ 592 I SYSOO3 I A2.01 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45/13)DProblems with RCP seals, especially rates of seal leak-off ..............

Unit 2 is in preparations for startup with the shutdown banks withdrawn and the control banks inserted.

Given the following:

  • 2AD-7 C/1 NCP #1 "SEAL LEAKOFF HI FLOW" is LIT
  • 2B NCP sealleakoff is 6.5 gpm
  • 2B NCP Seal Outlet temperature is slowly increasing
  • The crew enters AP/2/A/55001008 (Malfunction of Reactor Coolant Pump) What is the maximum time 2B NCP can remain in service and what procedure does AP/21A155001008 direct the crew to enter once the pump is tripped? A. 5 minutes; EP/2/A/5000/E-O (Reactor Trip or Safety Injection)

B. 5 minutes; AP/2IAl55001004 (Loss of Reactor Coolant Pump) C. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; OP/21A161001002 (Controlling Procedure For Unit Shutdown)

D. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; AP/21A155001004 (Loss of Reactor Coolant Pump) Tuesday, November 18, 2008 Page 171 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 86 General Discussion A "normal" value requiring a 5 minute SID is greater than or equal to 7.5. The 6.5 would normally cause an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> SID however, in this case the temperature is slowly increasing.

Since the plant is in MODE 3 tripping the reactor is not required and AP/04 will be entered not E-O. The 10 minute time is the time for loss of seal cooling from KC and NY (SSF) causing seal failure. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType SRO D Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References OP/1/B/6100/010H lAD07 AP/1/A/5500/004 AP/1/A/5500/008 QuestionBank

  1. IKA system IKA number I 592ISYS003 1 A2*OI I KA desc Question Source Student References Provided Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.31 45/13)DProb1ems with RCP seals, especially rates of seal leak-off ............. . 401-9 Comments:

003A2.01 Question appears to match KIA. Appears to be SRO only. What makes the procedure selection in C plausible?

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 172 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination -QUESTION 87 --QuestionBank

  1. IKA system IKA number I h.9_ r 593 I SYS026 I 2.4.47 I KA desc SYS026 GENERICDAbility to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5

/45.12) The night shift surveillance readings for Lake Wylie temperature over the past several days are as follows:

  • 8/01/08 -87.50 0 F.
  • 8/02/08 -88.25 0 F.
  • 8/03/08 -89.00 0 F.
  • 8/04/08 -89.75 0 F.
  • 8/05/08 -90.50 0 F. 1. Assuming lake temperature continues to increase at a constant rate, on what date will Lake Wylie temperature first exceed the requirements of SLC 16.9-14 (Lake Wylie Water Temperature)?
2. What affect, if any, will this higher lake temperature have on the ability of the NS system to affect containment pressure following a large break LOCA? A. 1. 8/09/08 2. Minimal impact prior to ice melt, but significant impact later in the accident sequence when the ice has been depleted.

B. 1. 8/09/08 2. Minimal impact during the entire accident sequence since lake temperature is still below the design basis accident assumptions.

C. 1. 8/12/08 2. Minimal affect prior to ice melt, but significant affect later in the accident sequence when the ice has been depleted.

D. 1. 8/12/08 2. Minimal impact during the entire accident sequence since lake temperature is still below the design basis accident assumptions.

Tuesday, November 18, 2008 Page 173 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination General Discussion QUESTION 87 QvesTio-AJ 1{2 SLC requirement is 95.5 degrees which would be exceeded on 8/12/08. 08/09/08 is the time which would require one train ofRN to be aligned to the pond during ES 1.3. and is the same action as the sIc. Answer A Discussion jWrong date; 2 is incorrect Answer B Discussion jWrongdate Answer C Discussion jCORRECT Answer D Discussion j2 is incorrect Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Developed*

Development References Student References Provided SLC 16.9-14 D OPT Approved ES1.3 D OPS Approved TSB3.7.9 NRC Approved QuestionBank

  1. IKA system IKA number I 5931SYS026 12.4.47 1 KA desc SYS026 GENERIC DAbility to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/45.12) 401*9 Comments:

026G2.4.47 Question appears to match KJA. Appears to SRO only. SAT NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 174 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 88 D QuestionBank

  1. IKA system IKA number I 594 I SYS039 I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/
45. 13) DDecrease in turbine load as it relates to steam escaping from relief valves . Given the following:
  • Rod control is in MANUAL.
  • Turbine power has decreased from 1227 MW to 1214 MW and stabilized.
  • The crew has just entered AP/1/A/5500/028 (Secondary Steam Leak). What single steam relief valve passing 20% of its full flow would produce the conditions noted and what actions will be directed per AP/1/A/5500/028 based on the above conditions?

A. A steam line safety; trip the reactor and go to EP/1/A/5000/E-O (Reactor Trip or Safety Injection.

B. A S/G PORV; trip the reactor and go to EP/1/A/5000/E-0 (Reactor Trip or Safety Injection.

C. A S/G PORV; initiate a unit shutdown per AP/1/A/5500/009 (Rapid Down power) D. A steam line safety; initiate a unit shutdown per AP/1/A/5500/009 (Rapid Down power) Tuesday, November 18, 2008 Page 175 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 88 General Discussion A PORVis about 2.5% steam flow and a safety is about 5%. This turbine MW represents a a safety valve 20% open (-12-13 MW) Therefore it is a PORV. AP/28 directs tripping the reactor and entering E-O if steam leak is >5%. Otherwise a load reduction is performed per AP/09 (or the OP which is not an answer choice) Rx. Trip is required per Enc 1 if cant make up sufficent to losses of condensate water. Full open porv is -900 gpm. Max makeup is -400 gpm ifRO units are bypassed.

Therefore, if the leak greater than 50% open, would meet criteria ofEncll to trip Rx. Answer A Discussion Iright valve, wrong action Answer B Discussion Iwrong valve wrong action Answer C Discussion Iwrong vavle right action Answer D Discussion ICORRECT Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Ii'] Developed Development References Student References Provided AP/28 0 OPT Approved SM 0 OPS Approved Ii'] NRC Approved QuestionBank

  1. IKA system IKA number I 5941SYS039 1 A2*02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 I 45. 13) o Decrease in turbine load as it relates to steam escaping from relief valves . 401-9 Comments:

039A2.02 Question appears to match KIA. Stem Focus-stem is confusing.

Not sure that this is SRO only knowledge.

This may be procedure entry requirements.

Will Discuss. Not sure that distractor A or B is plausible.

Trip the reactor for an 8 MW. Change? NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 176 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE -B-2008 SRO NRC Examination 89 .Lb QuestionBank

  1. IKA system IKA number I 595 I SYS062 I 2.1.20 I KA desc SYS062 GENERICDAbility to interpret and execute procedure steps. (CFR: 41.10/43.5/45.12)

Unit 1 is operating at 100% power. Given the following:

  • 1A DIG was manually started by NLOs for monthly surveillance testing
  • A grid instability and relay failures caused all Unit 1 Switchyard PCBs to open
  • 1 B DIG failed to start
  • The ensuing transient resulted in a 1 B S/G tube rupture Which procedure will be used to isolate the ruptured S/G in this situation, and what procedural guidance is given regarding isolation of the ruptured steam generator?

A. EP/11A15000/E-3 (Steam Generator Tube Rupture) is used to isolate the ruptured S/G as soon as it is identified.

B. EP/11A15000/E-3 (Steam Generator Tube Rupture) is used to isolate the ruptured S/G only if S/G NR level is greater than 11 %. C. EP/11A15000/ECA-0.0 (Loss of All AC Power) is used to isolate the ruptured S/G as soon as it is identified.

D. EP/11A15000/ECA-0.0 (Loss of All AC Power) is used to isolate the ruptured S/G only if S/G NR level is greater than 11%. Tuesday, November 18, 2008 Page 177 of 200 I I FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination General Discussion Setup is that the only source of power may (or may not) be 1A DIG. The 10 lube oil setpoint will trip the DIG for manual starts, however, the loca seq will cause the non-emergency trips to be blocked, hence 1A DIG will be available so entry into ECA 0.0 is not required.

E3 guidance is to maintian > 11 % NR level Answer A Discussion This is the correct guidnace per ECAO.O for isolation of a ruptured S/G. But E3 is the proper procedure.

Answer B Discussion ICORRECT Answer C Discussion This would be correct if this was a loss of all AC (A DIG not available)

Answer D Discussion IThis is the proper guidance (per E-3) but not the correct procedure.

Job Level Cognitive Level Question Type SRO Comprehension NEW Developed D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system 595 SYS062 KA desc Development References DIG 1A Annun RESP ECAO.O E-3 DG3 KA number 2.1.20 Question Source Student References Provided SYS062 GENERlCDAbility to interpret and execute procedure steps. (CFR: 41.10 I 43.5 145.12) 401-9 Comments:

062G2.1.20 Question appears to match KIA. As written all answers are correct, all of these procedures will isolate the S/G. Stem is not focused properly.

A is also not totally correct. Ifleve1 is greater than 11 %, the S/G will be isolated.

This question needs some rewording.

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 178 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 90 D QuestionBank

  1. IKA system IKA number I 596 I SYS076 I A2.02 I KA desc 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: (CFR: 41.5/43.5/45/3/

45/13) 0 Service water header pressure ......................................

Both units were operating at 100% power with 1A RN pump in service. 1A DIG was operating in parallel for surveillance testing when the following conditions and sequence of events occurred:

  • 1AD-12, Al2 "RN ESSENTIAL HDR A PRESSURE -LO" -LIT
  • 2AD-12, Al2 "RN ESSENTIAL HDR A PRESSURE -LO" -LIT
  • 1AD-12, Al5 "RN ESSENTIAL HDR B PRESSURE -LO" -LIT
  • 2AD-12, Al5 "RN ESSENTIAL HDR B PRESSURE -LO" -LIT
  • NLO reported that he evacuated the 1 A DIG room due to flooding.
  • 1A DIG was immediately secured by the control room crew.
  • The crew entered and took all actions per AP/O/A/55001030 (Plant Flooding) necessary to stop the flooding.
1. At what RN header pressure do the annuciators first come into alarm? 2. What is the current overall status related to Tech Spec 3.7.8 (Nuclear Service Water System (NSWS))? A. 1. 40 psig decreasing
2. Unit 1 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action , Unit 2 operable B. 1. 40 psig decreasing
2. Both units in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action C. 1. 46 psig decreasing
2. Unit 1 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action, Unit 2 operable D. 1. 46 psig decreasing
2. Both units in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action Tuesday, November 18, 2008 Page 179 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 90 General Discussion Rn low header pressure comes in at 46 pisg decreaing.

With the lA DIG secured, RN232A would close. Since the conditions persist following shutdown, the leak must be between the DIG building wall and RN232A. The only way that this leak can be secured is to separate RN trains and secure all of A train RN which is what AP30 does. This makes both units enter a 72 action for RN. The 40 psig value is the RNIYV opearble light pressure setpoint.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level Question Type Question Source SRO Comprehension NEW Developed Development References Student References Provided AP30 0 OPT Approved RNlesson 0 OPS Approved TS 3.7.8 NRC Approved QuestionBank

  1. IKA system IKA number I 5961SYS076 1 A2*02 I KA desc 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: (CFR: 41.5 143.5 14513 I 45/13)DService water header pressure ..................................... . 401-9 Comments:

076A2.02 Question appears to match KIA. Appears to be SRO knowledge.

SAT. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 180 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 91 QuestionBank

  1. IKA system IKA number I 597 I SYS033 I 2.2.22 I KA desc SYS033 GENERICDKnowledge oflimiting conditions for operations and safety limits. (CFR: 41.5 /43.2/45.,2)

Unit 2 is in Mode 6 performing core unloading when Spent Fuel Pool level is noted at 22 feet above the fuel assemblies.

1. Which one of the following is a required action for the above condition per T echn ical Specifications?
2. What is the basis for maintaining a minimum acceptable water level? A. 1. Immediately suspend movement of irradiated fuel assemblies
2. Ensures shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident B. 1. Immediately suspend movement of irradiated fuel assemblies
2. Ensures that there is a sufficient volume of water above the fuel assemblies to provide backup decay heat removal C. 1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate action to restore spent fuel pool level to within limits. 2. Ensures shielding during fuel movement and to meet the assumptions for iodine decontamination factors following a fuel handling accident D. 1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate action to restore spent fuel pool level to within limits. 2. Ensures that there is a sufficient volume of water above the fuel assemblies to provide backup decay heat removal Tuesday, November 18, 2008 Page 181 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 91 A General Discussion SFP Boron should be >2700 and level should be >23 feet. Both specs are not met. Action for boron out is to stop moving all fuel assemblies in the spent fuel pool and initiate action to get it back. Action for level out is to stop moving irradiated fuel. Correct answer states stop moving fuel assemblies.

This encompasses both irradiated and none irradiated.

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> basis is from the SSF and the SFP level requirements.

Basis for boron: Calculations show that the soluble boron concentrations needed to maintain the spent fuel pool keffbelow 0.95 for the postulated accidents related to fuel assembly movement are far less than the minimum amount available in the spent fuel pools (per the LCO for TS 3 .. 7.15). Level basis is: The specified water level shields and minimizes the general area dose when the storage racks are filled to their maximum capacity.

Answer A Discussion Answer B Discussion ICorrect action with correct basis Answer C Discussion IIncorrect action with correct basis Answer D Discussion IIncorrect action with incorrect basis Job Level Cognitive Level QuestionType SRO Comprehension NEW Developed D OPT Approved D OPS Approved NRC Approved QuestionBank

  1. KA system 597SYS033 KA desc Development References COLR TS3.7.14 and basis TS3.7.15 and basis SLC16.7-9 KA number 2.2.22 Question Source Student References Provided SYS033 GENERICDKnowledge oflimiting conditions for operations and safety limits. (CFR: 41.5 /43.2 / 45.2) 401-9 Comments:

033G2.2.22 Question appears to match KIA. General discussion does not make sense. It talks about boron, and the basis for boron, however boron is not mentioned in the question.

Distractors B and D do not appear to be credible.

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 182 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 92 c QuestionBank

  1. IKA system IKA number I 598 I syson I A2.02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/43.3/
45. 13) DDetector failure .................................................

Given the following:

  • Unit 2 has experienced a Safety Injection.
  • All S/G pressures are 1000 psig and stable.
  • The crew has entered EP/21A15000/E-3 (Steam Generator Tube Rupture) due to 2EMF-10 (Steamline A) Trip 1 light being LIT.
  • The BOP informs the OSM that 2RAD-3, F/3 (CABINET TROUBLE) is LIT
  • The OSM believes the EMF detector may have failed. 1. What method can the crew use to determine the validity of the EMF indication?
2. Once the indication is determined to be false, which of the following describes the correct procedure transition?

A. 1. Verify Trip 1 alarm on adjacent steamline EMF (2EMF-13 (Steamline 0)) is DARK 2. Transition to EP/2/A/5000/ES-0.0 (Rediagnosis)

B. 1. Verify Trip 1 alarm on adjacent steamline EMF (2EMF-13 (Steamline 0)) is DARK 2. Evaluate tape flags in EP/2/A/5000/E-3 and then transition to EP/2/Al5000/E-1 (Loss of Reactor or Secondary Coolant) C. 1. Request that RP frisk cation columns 2. Transition to EP/2/A/5000/ES-0.0 (Rediagnosis)

D. 1. Request that RP frisk cation columns 2. Evaluate tape flags in EP/2/A/5000/E-3 and then transition to EP/2/Al5000/E-1 (Loss of Reactor or Secondary Coolant) Tuesday, November 18, 2008 Page 183 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 92 General Discussion Entry into ES-O.O may be made at anytime. Adjacent steamline EMFs can be used to diagnose a SGTR if the actual S/G EMF is broken. However those are the N16 monitors and these are not (plausible).

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level Question Type Question Source SRO Comprehension NEW Developed Development References Student References Provided E-l 0 OPT Approved E-3 0 OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 598ISYS072 1 A2*02 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/43.3/

45.13)DDetector failure ................................................ . 401*9 Comments:

072Aio2 Not sure the question meets the KJA. The KJA refers to a failed detector, and there is nothing in the question that tests this. The question does state that the OSM believes the EMF indication to be false. I am not sure that this means the same thing. What procedure directs the operator to have RP frisk the cation columns? Not sure it is SRO only (procedure entry requirements)

NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 184 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 93 D QuestionBank

  1. IKA system IKA number I 599 I SYS086 I A2.01 I KA desc Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3

/45.13)DManual shutdown of the FPS .......................................

Given the following:

  • Unit 1 is at 100% power.
  • Unit 2 is in No Mode.
  • NLOs were running the SSF DIG per PT/0/A/42001017 (Standby Shutdown Facility Diesel Test) when a fuel oil leak resulted in a fire.
  • The SSF sprinkler system failed to actuate which resulted in damage to the SSF DIG.
  • The Plant Fire Brigade extinguished the fire 20 minutes later. What is the current emergency classification and what procedure will be used to . address this situation?

Reference provided A. Unusual Event; AP/1/A/55001017 (Loss of Control Room) Case 2, "Loss of Plant Control Due to Fire or Security Event" B. Unusual Event; AP/0/A/5500/045 (Plant Fire) C. Alert; AP/1/A155001017 (Loss of Control Room) Case 2, "Loss of Plant Control Due to Fire or Security Evenf' D. Alert; AP/0IAl55001045 (Plant Fire) Tuesday, November 18, 2008 Page 185 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE D 2008 SRO NRC Examination QUESTION 93 General Discussion Unusual event is fire extinguished after 15 min or greater. Alert is visible damage to certain equipment (of which the SSF is one) regardless of length of fire. AP/l7 is used if there is a fire in the ASP affecting both trains of control. If the ASP is confused with the SSF this is plausible.

Answer A Discussion IWrong classification, wrong procedure Answer B Discussion Iwomg classification,.

Right procedure Answer CDiscussion Iright classification, wrong procedure Answer D Discussion ICORRECT Job Level Cognitive Level Question Type SRO Comprehension NEW Developed Development References RP/OI D OPT Approved RFY D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 5991SYS086 i A2*Ol i KA desc Question Source Student References Provided RP/O/A/5000100l Classification of Emergency Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 I 45. 13) D Manual shutdown of the FPS ...................................... . 401*9 Comments:

086A2.01 Kind of matches KIA. What procedure was used to correct control or mitigate the consequences of manual operation?

I realize that the classification is an attempt to make it SRO only. Distractor .analysis not correct. NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 186 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 94 A QuestionBank

  1. IKA system IKA number I 600 I GEN2.1 I 2.1.14 I KA desc Conduct of Operations 0 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CPR: 41.10/43.5/45.12)

Unit 1 is at 100% with 1A CA pump tagged for preventative maintenance.

Given the following conditions and sequence of events:

  • 1 B CA Pump is found to have no indicating lights and no discharge pressure or flow indicated
  • NLO reports 1B CA Pump control power is unavailable
  • CAPT was successfully reset and restarted
  • Current S/G parameters are: 1A 1B 1C 10 I N/R level 10% 7% 9% 10% I CAflow 105 gpm 105 gpm 115 gpm 110 gpm Which one of the following is the correct Emergency Action Level and the first required notification to plant personnel for this current conditions?

Reference provided A. Enter a General Emergency and notify all plant personnel to perform a site assembly B. Enter a General Emergency and notify non-essential plant personnel to perform a site evacuation C. Enter a Site Area Emergency and notify all plant personnel to perform a site assembly o. Enter a Site Area Emergency and notify non-essential plant personnel to perform a site evacuation Tuesday, November 18, 2008 Page 187 of 200 FOR REVIEW ONLY DO NOT DISTRIBUTE A 2008 SRO NRC Examination QUESTION 94 General Discussion Turbine trip should have resulted in a reactor trip but didn't and rx had to be tripped locally. Based on S/G conditions, Heat Sink is in RED due to S/G levels <11 % with total feed flow <450gpm. This loss of heat sink will cause entry into the fission product barrier matrix ofRP/Ol as Site Area Emergency, however it is a general emergency based on A TWS requiring local trip AND HEAT SINK in red. A site evacuation is always precluded by a site assembly, and never done directly.

Answer A Discussion Answer B Discussion ICorrect classification wrong action Answer C Discussion Wrong classification and action (but a correct action if the classification was true). Answer D Discussion IIncorrect classification and action Job Level Cognitive Level QuestionType SRO Comprehension MODIFIED Developed Development References

References:

D OPT Approved 1. RP/OI D OPS Approved 2. TS 3.7.5 OP-CN-EP-SEP14 D NRC Approved QuestionBank

  1. IKA system IKA number I 6001GEN2.1 1 2.1.14 1 KA desc Question Source 2006 NRC Q90 (Bank 696) Student References Provided RP/O/A/5000/001 Classification of Emergency Conduct of Operations 0 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CFR: 41.10 I 43.5 145.12) 401-9 Comments:

G2.1.14 Question appears to match KIA. Do not see how this is a general emergency.

If a site evacuation is always precluded by a site assembly, why would anyone choose B or D. There is not a release etc. Question needs some work. Modified Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 188 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 95 QuestionBank

  1. IKA system IKA number I 601 I GEN2.1 I 2.1.36 I KA desc Conduct of Operations 0 Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10 / 43.6 / 45.7) Given the following:
  • Core reload is in progress with 1 A NO train in service.
  • The fuel handling SRO requests 1A NO train be secured to allow a fuel assembly to be placed near the cold leg nozzle. 1. What is the maximum time 1A NO train can remain shutdown per Technical Specification 3.9.4 (Residual Heat Removal (RHR) and Coolant Circulation-High Water Level) 2. Why is boron concentration of any NC System make-up strictly limited with all NO loops shutdown?

A. 1. 30 minutes 2. Lack of adequate NC System temperature monitoring B. 1. 30 minutes 2. Lack of adequate mixing of NC System water C. 1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2. Lack of adequate NC System temperature monitoring O. 1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2. Lack of adequate mixing of NC System water Tuesday, November 18, 2008 Page 189 of 200 D I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 95 General Discussion TS says 'The required RHR loop may be removed from operation for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided no operations are permitted that would cause introduction of coolant into the Reactor Coolant System with boron concentration less than required to meet the minimum required D boron concentration ofLCO 3.9.1." The 30 minutes is the completion time for AFD and several other TS and Safety limits. It ensures the correct answer of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is not telegraphed by having a greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action and not giving the TS as a reference.

Additions must be >COLR limit since there is no mixing with no ND in service. An ND loop in service provides heat removal, mixing, and temperature indication.

Lack of temperature monitoring is a reason for only having 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, but is not the reason boron concentration is limited. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType SRO Comprehension NEW Developed o OPT Approved OOPS Approved NRC Approved QuestionBank

  1. KA system 601 GEN2.1 KA desc Development References TS 3.9.4 and basis TS 3.2.3 KA number 2.1.36 Question Source Student References Provided Conduct of Operations o Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10 I 43.6 I 45.7) 401-9 Comments:

G2.1.36 If these are precautions and limitations, then the question appears to match the KJ A. This appears to be just TIS requirements while refueling.

Does not appear to be SRO only. All of these items are RO knowledge.

NEW Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 190 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 96 B QuestionBank

  1. IKA system IKA number I 602 I GEN2.2 I 2.2.15 I KA desc Equipment ControlDAbility to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.10/43.3

/45.13) Unit 1 is operating in Mode 3 preparing for a reactor startup following a refueling outage. Given the following events and conditions:

  • NC Pump 1C is running.
  • Maintenance determines that the MOV test data from the outage indicates that the torque switches for 1 NO-658 (NO TRAIN 18 HOT LEG INJ ISOL) have been set too low.
  • The SWM requests OSM approval to tag closed 1 NO-658 for repairs. Which one of the following statements correctly describes the operating restrictions and implications of tagging closed 1 NO-658? A. 1 NO-658 may be tagged closed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the steam generator in the running NC loop is operable.
8. 1 NO-658 may not be tagged closed because this would make both trains of NO inoperable.

C. 1 NO-658 may not be tagged closed unless two NCPs are running with operable steam generators.

O. 1 NO-658 may be tagged closed if 1 NO-658 is restored to operation prior to transitioning to mode 2. Tuesday, November 18, 2008 Page 191 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 96 B General Discussion IBank Question:

096.1 Answer A Discussion Incorrect:

Both trains ofND will be inoperable.

Plausible:

If the candidate assumes 1 S/G and the A ND loop. Answer B Discussion ICorrect:

ND-65 prevents ND flow to all 4 loops. Answer C Discussion Incorrect:

Both trains ofND will be inoperable.

Plausible:

If the candidate focuses only on decay heat removal. Answer D Discussion Incorrect:

Both trains ofND will be inoperable.

Plausible:

If the candidate assumes that one ND train is sufficient in mode 3. Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK 2003 NRC Q76 (Bank 276) Developed Development References Student References Provided OPT Approved OPS Approved NRC Approved Lesson Plan Objective:

PS-ND SEQ 11

References:

1. OP-CN-PS-ND pages 12. 18 2. Tech Spec & Bases 3.4.5 -3. Tech Spec & Bases 3.4.6 -4. Tech Spec & Bases 3.5.2 -QuestionBank
  1. IKA system IKA number I 6021GEN2.2 12.2.15 1 KA desc Equipment ControlDAbility to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR: 41.10 / 43.3/45.13) 401-9 Comments:

401-9 Comments RESPONSE G2.2.15 Question appears to match KIA. Is there a block for the WCCSRO to sign the BCNF? Is the WCCSRO a required Technical Specification position? Is all this done without the Control Room Supervisors knowledge/permission?

Not sure this is SRO only. Any individual responsible for hanging Red Tags would require this knowledge to ensure the boundary change was approved.

NEW Tuesday, November 18, 2008 Page 192 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 97 B QuestionBank

  1. IKA system lKA number I 603 I GEN2.2 I 2.2.3 I KA desc Equipment ControlD(multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5 /41.6/ 41.7/41.10/45.12)

Which unit has a lower setpoint for P-14, and what is the basis for limiting maximum water level in the S/Gs? A. Unit 1 / Limit energy release into containment following a steam line break B. Unit 2/ Limit energy release into containment following a steam line break C. Unit 1 / Maintain offsite dose within assumed limits following a SGTR D. Unit 2/ Maintain offsite dose within assumed limits following a SGTR Tuesday, November 18, 2008 Page 193 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE B 2008 SRO NRC Examination QUESTION 97 General Discussion Unit 1 P-l4 -84%, Unit 2 -77%. Basis for P-l4 is"to prevent damage to the turbine due to water in the steam lines, stop the excessive flow of feedwater into the SGs, and to limit the energy released into containment" Reason that SAl and 4 are closed on S/G TR with loss of VI (which invovles hi S/G level as well) incorrect basis of "This signal provides protection against excessive cooldown, which could subsequently introduce a positive reactivity excursion after a plant trip" CF ISOL-GLD] Answer A Discussion IWrongunit Answer B Discussion Answer C Discussion IBoth wrong -psychometric balance. Answer D Discussion IWrong reason Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Developed Development References Student References Provided TS3.3.2 and basis D OPT Approved EPINTRO D OPS Approved NRC Approved QuestionBank

  1. IKA system IKA number I 6031GEN2.2 12.2.3 I KA desc Equipment ControlD(multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5 /41.6/ 41.7/41.10/45.12) 401-9 Comments:

G2.2.3 Question appears to match KIA. Not sure it is SRO only. An RO is required to know the S/G high level trips, and what they are based on. I did not find it in any of your lesson plans. C and D are not credible with the reason as stated. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 194 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 98 c QuestionBank

  1. IKA system IKA number I 604 I GEN2.3 I 2.3.13 I KA desc Radiation ControlDKnow1edge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor ahirms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 / 43.4 / 45.9/45.10)

Unit 2 is operating at 100% power. Maintenance has requested entry into the lower airlock. The work will require propping open the airlock vestibule door (eAD door) and the outer airlock door. The inner airlock door will remain closed. For this situation, per Site Directive 3.1.2 (Access to Reactor Building And Areas Having High Pressure Steam Relief Devices) whose permission is required to issue the access keys to this area and what is inoperable based on Technical Specifications?

A. wee SRO and Radiation Protection; the Annulus Ventilation System B. wee SRO only; the Annulus Ventilation System e. wee SRO and Radiation Protection; the Reactor Building D. wee SRO only; the Reactor Building Tuesday, November 18, 2008 Page 195 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination QUESTION 98 General Discussion Per SD 3.1.2 sect 4.2 if inner airlock door is not opened then not a containment entry and RB/Annulus entry requirements are needed. Sect 5.1.4 says approval from RP and WCC. RP mananger and station manager are need if enter lower containment at >5% RTP Sect 5.1.4.2 tells that if door open for reasons other than normal transit -RB inop. Not VE. See CNT lesson for that info too. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Developed Development References Student References Provided TS 3.6.l0 D OPT Approved TS3.6.16 D OPS Approved SD3.1.2 TS 5.7 NRC Approved RPManual QuestionBank

  1. IKA system IKA number I 604I GEN2.3 12.3.13 1 KA desc Radiation ControlDKnowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 I 43.4 I 45.9 I 45.10) 401*9 Comments:

G2.3.l3 Borderline KJ A match. May not be SRO only. This question is more of a containment integrity question.

ROs should know whose permission to get, and this is a TIS entry knowledge.

Distractors B and D do not appear to be credible (Station Manager)?

Memory level question.

NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 196 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 99 c QuestionBank

  1. IKA system IKA number I 605 I GEN2.3 I 2.3.14 I KA desc Radiation ControlDKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12/43.4

/45.10) A contract worker is performing a task in an area with 5000 dpm/100 cm 2 (beta, gamma) contamination.

His coworkers have reported he is acting erratically and believe he is "on" something.

While waiting for supervision and security to arrive the individual falls and is injured. The individual is contaminated and must be transported offsite for medical treatment.

What is the correct posting for the work area and what is the first required NRC notification time for this event? A. Contaminated Area; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. Highly Contaminated Area; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. Contaminated Area; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. Highly Contaminated Area; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Tuesday, November 18, 2008 Page 197 of200 FOR REVIEW ONLY -DO NOT DISTRIBUTE c 2008 SRO NRC Examination General Discussion FFD issue is a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification.

>50,000 is Highly. Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType SRO Developed D OPT Approved D OPS Approved NRC Approved Comprehension NEW Development References RP/13 NSD507 QuestionBank

  1. IKA system IKA number I 605!GEN2.3 12.3.14 1 KA desc QUESTION 99 Question Source Student References Provided Radiation ControlDKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12/43.4

/ 45.10) 401-9 Comments:

G2.3.l4 Question appears to match KIA. Appears to be SRO only. Both ofthe Notifications are required.

Need to change to soonest required notification, or something similar. NEW Tuesday, November 18, 2008 401-9 Comments RESPONSE Page 198 of 200 FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 100 QuestionBank

  1. IKA system IKA number I 606 I GEN2.4 I 2.4.3 I KA desc Emergency Procedures

/ P1anDAbility to identifY post-accident instrumentation. (CFR: 41.6 /45.4) Given the following conditions:

  • Unit 2 has experienced a small break LOCA
  • The crew has transitioned to EP/21A15000/ES-1.2 (Post LOCA Cool down and De pressu rizatio n)
  • Containment pressure is 4.5 psig and decreasing slowly
  • Present pressure indications are: o PZR PRESS Channel 1 -1815 psig o PZR PRESS Channel 2 -1795 psig o PZR PRESS Channel 3 -Failed High o PZR PRESS Channel 4 -Failed High o LOOP B HOT LEG W IR PRESS -1920 psig o LOOP C HOT LEG W/R PRESS -Failed Low 1. Which instrument(s) above will provide the most reliable indication of current primary system pressure?
2. Based on the indications provided, is the LCO for Technical Specification 3.3.3 (PAM Instrumentation) met? A. 1. LOOP B HOT LEG W/R PRESS 2. No B. 1. PZR PRESS Channels 1 and 2 2. No C. 1. LOOP B HOT LEG W/R PRESS 2. Yes D. 1. PZR PRESS Channels 1 and 2 2. Yes Tuesday, November 18, 2008 Page 199 of 200 A I I FOR REVIEW ONLY -DO NOT DISTRIBUTE 2008 SRO NRC Examination QUESTION 100 A General Discussion Per OMP 1-7, PAM isntruments provide the most relianble indication In ACC conditions.

The basis of PAM instruments is for operator diagnosis of primary system parameters.

W!R pressure does not initiate auto actions associated with accidents, but does provide input to LTOP circuitry.

PZR pressure channels input ESF AS but are not PAM instruments.

Answer A Discussion Answer B Discussion Answer C Discussion Answer D Discussion Job Level Cognitive Level QuestionType SRO Developed D OPT Approved D OPS Approved NRC Approved Memory QuestionBank

  1. KA system 606GEN2.4 KA desc NEW Development References TS3.3.3 and basis OMPI-7 KA number 2.4.3 Question Source Student References Provided Emergency Procedures

/ Plan D Ability to identify post-accident instrumentation. (CFR: 41.6 /45.4) 401*9 Comments:

G2.4.3 Question appears to match KIA. Not SRO only knowledge.

All operators are required to know PAM indicators and the why is obvious. Tuesday, November 18, 2008 401*9 Comments RESPONSE Page 200 of 200

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