Text

Final Written Examination with Answer Key (401-5 Format) (Folder 3)
	ML102920669
Person / Time
Site:	Limerick
Issue date:	09/29/2010
From:	Caruso J G; Operations Branch I
To:	; Exelon Nuclear Generation Corp
	Hansell S
Shared Package
ML100560247	List: IR 05000352/2010302; ML101650598; ML102720677; ML102870021; ML102920654; ML102920658; ML102920661; ML102920664; ML102920667; ML102920669; ML102920673; ML102920676; ML103080887;
References
	TAC U01767
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{{#Wiki_filter:RO ILT09-1

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TEST RECORD Firmware PART 1 Ver.3.3+ PART 2 TOTAL c8::J c8::1 c9::J 1:9:::1 (F) 51 cA::J ... cC::J co::J cE::J 52 cA::J cB::J 1411 co::J cE:::l 53 cA:::l cB::J cC:::l cE::! 54 !!iIIIIIII cB::J cC:::l co:::l cE:::l 55 cA::J cB::J ... cD::! cE:::l 56 ..... cB::! cC:::l co::J cE:::l 57 cA::J .... cC:::l cD::! cE::! 58 cA:::l cB:::l cC::! a8&I cE::J 59,-.. cB::! cC::! cD::! cE::! 60....,. cB::J c:C::! co::J cE::J 61 cA::! cB::J .... cD::! cE::J 62 ... cB::! cC::! cO::! cE:::l 63 cA::J cB::! cC:::l cE::J... 64 cA:::l cB:::l ... co::J cE::::I 65 cA::J cB::! ..... co::J cE::J 66 cA::J cB::J -em co::J cE::l 67 cA::l cB::! cC::J cE::J... 68 .. cB::J cC::J co::l cE::! 69 cA::J cB::J ... cD::! cE::! 70 cA::J co::J cE::l 71 cA::! cB::! ... co::J cE::! 72 cA::l ... cC::J cD::!

cE::! 73 cA::! cB::! cC::! t!!9!!!I cE::! 74 cA::J c8::! cC::! 118m cE::! 75 cA::! cB::! cC:::J II8e cE::::I 76 ..... c8::! c::C::! co::J cE::::I 77 cA::J cB::! c::C::l e8e cE::I 78 ... cB::! cC::! cD::! cE::I cB::! cC::! cD::! cE::J 80 cA::! r4I8 cC::! cD::! cE::! 81 aIIJIIIIIl c:B::! cC::! cO::! cE::! 82--" cB::! cC::J cD::! cE::! 83 cA::l cB::! cC::l CJ9IB cE::! cB::J cC::J co::J cE::J 85 cA::! ... cC::! cO::J cE::! 86"-cB::! cC::J cD::! cE::! 87 ..... cB::! cC::J cD::! cE::! 88 cA::! cC::J cD::! cE::J 89 cA::! ... cC::! cD::! cE::J 90 cA::J cB::J l'!J8IIt co::l cE::! 91 __ cB::! cC::J cO::J cE::! 92 cA::J cB::! cC::l cE::J... 93 cA::! cB::! cC::J ..., cE::l 94 cA::J cB::J cC::l cE::!... 95 cA::! cB::! cC::J tI&a cE::l 96 cA::J cB::J ... co::l cE::J 97 cA::l c B::! cC::! cE::! 98 cA::J cB::J cC:::J .... cE::J 99 cA::J r::B::J r::C::J .... cE::J 00 cA::J cB::J cO::J cE::J NAME .. KeY (taoI) (Fif1l) . . ;:::cg:a:;' SlIBJEC1:' INSTRUCTOR .. DATE PERIOD ptOf e.. ::D REORDER m <iD (J)AccuScan'" (J) 0 0 0 Advantage'" 0 ::D ::D F'lease AecyClt! m m 1 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Unit 2 plant conditions are as follows: -Main Turbine is -Reactor power is WHICH ONE of the following describes the required RPV pressure control strategy per T-101, RPV Control, and the reason for it? Stabilize RPV pressure with Safety Relief Valves to minimize power fluctuations Stabilize RPV pressure with HPCI to minimize heat input into the Suppression Pool Reduce RPV pressure with HPCI to minimize operation of Safety Relief Valves Reduce RPV pressure with Turbine Bypass Valves to minimize heat input into the Suppression Pool Answer: A Answer Explanation: ANSWER Stabilize RPV pressure with SRVs to minimize power fluctuations: Per T -101 , RPV pressure is stabilized at a value below the high RPV pressure scram set point (1096 psig) to avoid safety relief valve (SRV) actuation and to permit the scram logic to be reset (barring the existence of other scram signals). No minimum value is specified since the RPV pressure at which the TRIP procedures are entered cannot be pre-defined and the instruction must provide appropriate guidance for all events. The use of the term "Stabilize" means to hold RPV pressure as constant as possible within the constraints imposed by the nature of the event, the degree of control afforded by the systems used, and the availability of personnel to perform manual control functions. The intent is that RPV pressure be held as constant as practicable. The specific actions required and the degree to which the idea! of a constant pressure can be approached will vary according to these constraints. For example: During failure-to-scram events, stabilizing RPV pressure is of greater importance, but is likewise more difficult to accomplish. If significant reactor power is

being generated, it may be expected that RPV pressure will vary at a faster rate and over a wider band than under non-ATWS conditions.

EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Stabilize RPV pressure with HPCI to minimize heat . input into the Suppresskon Pool: See Explanation above -Above The HPCI system exhausts directly to the Suppression Pool which in turn has a tendency to pressurize primary containment. HPCI is used in some situations to depressurize or maintain pressure, however it will NOT minimize heat input to the Suppression Pool. The use of the term "Stabilize" means to hold RPV pressure as constant as possible within the constraints imposed by the nature of the event, the degree of control afforded by the systems used, and the availability of personnel to perform manual control functions. Reduce RPV pressure with HPCI to operation of SRVs: See Explanation above -Per RPV pressure is stabilized at a value below the high pressure scram set point (1096 psig) to avoid safety valve (SRV) actuation and to permit the scram logic to reset (barring the existence of other scram Reduce RPV pressure with turbine Bypass Valves minimize heat input into the Suppression Pool: Explanation above -Per T-101, RPV pressure is at a value below the high RPV pressure scram (1096 psig) to avoid safety relief valve and I or valve operation and to permit (SRV) actuation any heat distribution can be dissipated from Suppression ! Question 1 Info Question Type: Multiple Choice *Status: Active !Always select on test? No *Authorized for No Points: 1.00 Time to Complete: 3 i 2.00 System 8771 User-Defined 10: 8771 *Cross Reference Number: LLOT1560.05 OT-102, Reactor HI pressure trip with RPS lites not iTopic: extinguished Qer Num Field 1: Num Field 2: Text Field: 295037 I GerlCI ell Data Technical Reference with T-101 Revision Number: Cognitive Level H EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Justification for Non SRO 55.41 (b) 8 CFR Link: PRA: (i.e. Yes or No or #) Y 1 OCFR 55.43 (N/A for ROj N/A Question History: (I.e. LGS NRC 02 NRC-05, OYS CERT-04) Question Source: (I.e. New, Bank Bank, Modified) Revision History: Revision Bank History: (i.e. Modified distractor "b" to make plausible based on OTPS review) Ref {Iif appropriate) none 2 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8773 Points: 1.00 Unit 1 Reactor startup is in progress. The "1 Btl Recirc pump Field Breaker trips, plant conditions are as follows: -Reactor power is 50% -"1A" Recirc pump speed is 55 0/0 -PMS computer is unavailable -Core plate DP indication XR-042-1 R613 indication is 1.2 psid LGS Power Flow Operation Map OPRM Operable -ALL Feedwater Heaters In Service 120 110 100 90 i 80 '" C &. 60 ) 50 40 30 20 10 20 30 40 WHICH ONE of the following is a required action for the given conditions? A. Manually scram the reactor B. Stabilize Power at current value C. Insert control rods to exit RESTRICTED REGION D. Restart the "1 B" Recirc pump and Raise Core Flow Answer: C Answer Explanation: EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Insert control rods to exit RESTRICTED REGION: Correct because 50% power and Core plate dP of 1.2, places plant in the restricted region Per T-112. IF while executing the remainder of this procedure, RESTRICTED REGION of Power/Flow Map is entered, THEN immediately EXIT region by inserting control rods OR raising core flow. The RESTRICTED REGION of the Power/Flow Map encompasses regions where there is an increased potential for core THI. If entered, direction is provided to immediately exit the RESTRICTED REGION of the Power/Flow Map to minimize the potential for core THI. Manually scram the reactor: This is incorrect as conditions do not require a Reactor Scram. IF a second recire pump tripped, OR if Core Plate dP indication on was not available. Prior to OPRM System activation, a scram was required at LGS following entry into natural circulation based on commitments made to NRC Bulletin 88-07 Supplement 1, and was part of the Interim Corrective Actions (I CAs). The basis for the scram was to prevent the occurrence of core THI. Once OPRM System activation occurred, however, LGSs was no longer committed to the ICAs. Even though Technical Specification 3.4.1.1 permits continued plant operation of up to 12 hours0.5 days 0.0714 weeks 0.0164 months following a dual Recirc Pump trip, Exelon has decided, on a fleet-wide basis, to continue to direct that a manual scram be performed any time the plant enters the natural circulation mode, based primarily on the reactivity effects of starting a Recirc Pump while operating in this condition. Stabilize Power at current value: This is incorrect. If an incorrect diagnosis of the Core Flow Map is assumed it may be assumed that it is conservative to stabilize power at the present value. As 50% power and Core plate dP of 1.2, places plant in the Restricted Region Per OT -112 requiring action as described in ANSWER. IF while executing the remainder of this procedure, RESTRICTED REGION of Power/Flow Map is entered, THEN immediately EXIT region by inserting control rods OR raising core flow. EXAM BANK COMPUTER TEST Page: 5 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Restart 1 B Recirc Pump, and Raise Core Flow: This is incorrect Per OT-112, Restarting a Recirc Pump is not an acceptable means of raising flow as indicated in OT-112 CAUTION Restarting a Recirc Pump is not an acceptable means of raising flow. Because raising core flow is an option to exit the Restricted Region an incorrect assumption would be to start an idle pump and then raise core flow, but OT-112 specifically warns against this method of raising core flow. OT-112 states, I F while executing the remainder of this procedure, RESTRICTED REGION of Power/Flow Map is entered, THEN immediately EXIT region by inserting control rods OR raising core flow. Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 13 Difficulty: 3.00 System ID: 8773 User-Defined ID: 8773 Cross Reference Number: LLOT1540.05 Topic: OT-112, Partial loss offorced core flow Num Field 1: 3.3 Num Field 2: 3.5 Text Field: 295001 AK1.02 Comments: General Data Technical Reference with OT-112, Recirc Pump trip Revision Number: LOT-1540.05 COQnitive Level H Justification for I\lon SRO 5S.41(b) 6 CFR Link: PRA: (Le. Yes or No or #) N 10CFR 55.43 (N/A for RO) N/A Question Histmy: (Le. LGS New NRC-05, OYS CERT-04) Question Source: (Le. New, New Bank, Modified) Revision History: Revision N/A .1 History: (i.e. Modified distracter "b" to make plausible based on OTPS i review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) EXAM BANK COMPUTER TEST Page: 6 of 12 October 2010 II EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Excluded

Reference:

(Le. OT-112 Ensure ON-## not provided)

Low KA Justification (if N/A required): Question 2 Table-Item Links NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.2 General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and coolant flow. CFR: 41.3 Mechanical components and design features of the reactor primary system. CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics. CFR: 41.6 Design, components, and functions of reactivity control mechanisms and instrumentation. CFR: 41.8 Components, capacity, and functions of emergency systems. 10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 45.7 Safely operate the facility's heat removal systems, including primary coolant, emergency coolant, and decay heat removal systems, and identify the relations of the proper operation of these systems to the operation of the facility. CFR: 45.8 Safely operate the facility's auxiliary and emergency systems, including operation of those controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment. General Question Data Higher Initial Limerick RO SRO EXAM BANK COMPUTER TEST Page: 7 of 206 12 October 2010 3 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8780 Points: 1.00 Unit 2 plant conditions are as follows: Unit 2 was operating at 100% when a scram signal occurred One (1) minute later, the following conditions are noted: -Reactor Power is <4-Reactor Pressure is 960 psig and -Rod 26-11, 50-31, 22-51 are at position -All other control rods are at WHICH ONE of the following describes a new set of control rod positions and Standby Liquid Control (SLC) Status at which an "ATWS" is no longer in progress? ROD 26-11 ROD 50-31 ROD 22-51 A. "02" "02" "48" NOT Started B. "02" "02" "04" Injecting C. "00" "04" "04" Injecting D. "02" "02" "02" NOT Started Answer: 0 Answer Explanation: EXAM BANK COMPUTER TEST Page: 8 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ROD 26-11 at "02" ROD 50-31 at "02" ROD 22-51 at "02" SLC Status NOT Started: Correct, refer to LGS TRIP NOTE #14 reminds operators of the definition of the term "ATWS". In general, any time operators have positive confirmation that the reactor is, and will remain, shutdown under all conditions without boron, an ATWS is not in progress. This determination is best obtained by determining that no control rod is withdrawn beyond the Maximum Subcritical Banked Withdrawal Position (MSBWP, position 02). However, other criteria can also be used to demonstrate that the reactor will remain shutdown under all conditions without boron. Possibilities include the existence of the core design basis shutdown margin with the single strongest control rod fully withdrawn and all other control rods fully inserted and compliance with Technical Specification requirements governing control rod position and the allowable number of inoperable control rods. In some cases, the control room operating crew may be able to make this determination themselves. In most cases, however, it is expected that this determination will be made by a Reactor Engineer or other member of the Technical Support Staff. The definition of "ATWS" does not imply that either of the two conditions cannot be met if boron has been injected, but that credit cannot be taken for the negative reactivity contributed by i the boron. ROD 26-11 at "02" ROD 50-31 at "02" ROD 22-51 at "48" SLC Status NOT Started: Incorrect due to the definition of the term "ATWS" . In general, any time operators have positive con'firmation that the reactor is, and will remain, shutdown under all conditions without boron, an ATWS is not in progress. This determination is best obtained by determining that no control rod is withdrawn beyond the Maximum Subcritical Banked Withdrawal Position (MSBWP, position 02). However, other criteria can also be used to demonstrate that the reactor will remain shutdown under all conditions without boron. . ROD 26-11 at "02" ROD 50-31 at "02" ROD 22-51 at "04" SLC Status Injecting: Incorrect again due to the definition of the term "ATWS" and the fact that boron is or has been injected. ROD 26-11 at "00" ROD 50-31 at i'04" ROD 22-51 at "04" SLC Status Injecting: Incorrect due to the definition of the term "ATWS" . In general, any time operators have positive confirmation that the reactor is, and will remain, shutdown under all conditions without boron, an ATWS is not in progress, This determination is best obtained by determining that no control rod is withdrawn beyond the Maximum Subcritical Banked Withdrawal Position (MSBWP, position 02). However. other criteria can also be used to demonstrate that the reactor will remain shutdown under all conditions without boron. 2=-C O--=6 .--... EXAM BANK COMPUTER TEST* --EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 3 Info J Question TJlPe: Mllitinll'> Qbpice_ Status: Active I Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 8780 User-Defined ID: 8780 I Cross Reference Number: LIMERICK LOT 6740 ATWS in progress -Reactor Power is 6% -Suppression Topic: Pool temperature. is 1090F The Operator has ma Num Field 1: 3.7 Num Field 2: 4.0 Text Field: 295006 AK1.03 Comments: General Data ..Technical Reference with T-101 I Revisio Revision Number: n#: Level L Justification for Non SRO 55.41(b) 8 CFR Link: Question History: (i.e. LGS 02 NRC-05, OYS CERT-04) Question Source: (i.e. New, Bank Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision N/A History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (I.e. ABN-##) Excluded

Reference:

(I.e. N/A Ensure ON-## not provided)

LORT -. PRA: (I.e. Yes or No or #) Y LORT Question Section: A (I.e, A-Systems or B-Procedures) --------- 2::":00-;-10* EXAM -BANK COMPUTER TEST Page: 10 of206 4 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: -MCR has been evacuated due to Toxic Gas -SE-1, Remote Shutdown, was entered and all remote shutdown transfer switches are in "Emergency" r.,., IL , -f-:." While the Control Room is being evacuated reactor level drops to -40" fx:::-rv.' ifJC. Operators have only completed the Immediate Operator Actions required ,S'L 't/-z..tt before exiting the MCR 'I No other actions were taken at the RSP .,${.1.-,1 _, . .' Reactor Level goes up to + 60", {[It' is ... WHICH ONE of the following describes the expected response of HPCI and U d RCIC A. Shutdown B. Running C. Running Shutdown D. Running Running Answer: B Answer Explanation: HPCI Tripped and RCIC Running: Correct due to HPCI will trip as designed at 54" RPV level. SE-1 section 4.3.3 describes placing RCIC in service for manual control of level. RCIC as well as HPCI will normally automatically cycle to maintain level, however when RSP switches are placed in EMERGENCY, the high +54" trip !or RFiC is bypassed and shutdown of RCIC must be manually controlled. SE-1 NOTE for section 4.3A describes HPCI spurious operation that may require Emergency Shutdown. This is due to a fire induced problem with HPCI controls. In this case evacuation of the MCR was due to a Toxic Gas problem not a fire induced problem . . HPCI Tripped and RCIC Shutdown: Incorrect due to HPCI will trip as designed at 54" RPV level. There is no manual control capability for HPCI at the RSP except for the HPCI Emergency Shutdown using HS-56-*62 at the RSP. (fire induced problem). RCIC will require operation due to RSP switches are placed in EMERGENCY, the high +54" trip for RCIC is bypassed and shutdown of RCIC must be manually controlled. EXAMINATION ANSWER ILT09-1 RO questions in sample plan order HPCI Running and RCIC Shutdown: Incorrect due not understanding HPCI will trip as designed at 54" RPV level and assuming HPCI will mquire being manually secured from the RSP, whereas only RCIC manual operation is required at the RSP. There is no manual control capability for HPCI at the RSP except for the HPCI Emergency Shutdown using HS-56-*62 at the RSP. (fire induced problem. RCIC remains running as RPV level increases to >54" until being manually secured. HPCI Running and RCIC Running: Incorrect again due not understanding HPCI will trip as designed at 54" RPV level and assuming HPCI will require being manually secured from the RSP, whereas only RCIC manual operation is required at RSP. There is no manual control capability for HPCI at the RSP except for the HPCI Emergency Shutdown using HS-56-*62 at the RSP. (fire induced problem. RCIC remains running as RPV level increases to >54" until being manually secured. I Question 4 Info Question Type: Multiple Choice Active Always select on test? Yes Authorized for practice? No 1.00 Time to Complete: 2 3.00 System ID: 8794 User-Defined ID: 8794 Cross Reference Number: LLOT0735.02 Topic: Remote Shutdown Panel (RSP operation Num Field 1: R04.4 Num Field 2: SR04.5 Text Field: 295016 AK2.01 Comments: General Data Technical Reference with SE-1 Remote j Revisio Revision Number: Shutdown n #: i Cognitive Level L Justification for Non SRO 55.41 (b) 7 CFR Link: Question History: (i.e. LGS Bank i NRC-05, OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified) Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 12 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Revision History: Revision N/A History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If none appropriate): (Le. ABN-##) Excluded

Reference:

(Le. SE-1 Ensure ON-## not provided)

LORT PRA: (Le. Yes or No or #) Y LORT Question Section: B (Le, A-Systems or B-Procedures) EXAM BANK COMPUTER Page: 13 of 206 12 October 2010 5 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is 78% -Reactor pressure is 1022 psig -Both Instrument Air header low pressure annunciators have alarmed -Scram pilot air header low pressure (108-D-5) has alarmed Local air header pressure (47-1 N652 at 10C613) indicates 45 psig and trending down WHICH ONE of the following describes the expected response of the Main Steam Isolation Valves (MSIVs) as Instrument Air pressure continues lowering? A. Inboard MSIVs will fast close B. Outboard MSIVs will fast close C. Inboard MSIVs will drift closed D. Outboard MSIVs will drift closed Answer: B Answer Explanation: Outboard MSIVs will fast close: Correct due to ON-119 NOTE block prior to step 2.6.2 explaining that MSIVs may begin to drift closed and procedure steps direct closing MSIVs after all control rods are inserted and Recirculation Pumps are tripped. Although the accumulator on outboard MSIVs will not prevent closure the slow depressurization of the air header supplied to the operating piston will eventually be overcome by spring pressure. Inboard MSIVs will drift close: Incorrect due to pneumatic supply normally from Instrument Gas (Nitrogen) that is not affected by the loss of IA pressure. Inboard MSIV's are not affected by a loss of IA. If it is assumed that a loss of IA affects the INBD MSIV's the INBD MSIVs would drift closed, just as they will drift closed on a loss of PCIG. The INBD MSIV's configuration for pneumatics is different from the OUTBD MSIVs whereas the OUTBD MSIVs will fast close on a loss of IA. EXAM BANK COMPUTER TEST Page: 14 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Inboard MSIVs will fast close: Incorrect due pneumatic supply normally from Instrument (Nitrogen) that is not affected by the loss of IA Additionally, the Inboard MSIVs are maintained open an accumulator supply to the operating piston that protected by a check valve. For the INBD MSIVs location of the check valve supports maintaining MSIVs open by accumulator pressure, whereas for OUTBD MSIVs the location of the check valve fast closure of the OUTBO Outboard MSIVs will drift close: Incorrect due to plant conditions stated with depressurization of Instrument Air Headers allowing plant control per The OUTBD MSIV's will fast close due to an control modification whereas as Instrument Air continues deplete the control box will reverse closing Instrument from the valve and with the check valve being upstream the control box it will use accumulator pressure to close the OUTBO MSIV's fast as though power were to the solenoid controlled box which would have the Question 5 Info Question Type: Multiple Status: Always select on test? i Authorized for practice? No *1.00 Time to Complete: 3 Difficulty: 3.00 System 8774 *User-Defined 10: 8774 Cross Reference Number: LLOT1550.02 Topic: ON-119, Loss or partial loss of Instrument Num Field 1: Num Field 2: Text Field: 29S019 General Data Technical Reference with ON-119. Loss of Revision Number: Instrument air Cognitive Level L Justification for Non SRO 5S.41(b) 6 CFR Link: PRA: (i.e. Yes or No or #) Y 10CFR 55.43 {N/A for RO) N/A Question History: (I.e. LGS New NRC-05, OYS CERT-04) Question SourGe: (I.e. New, New Bank, Modified) EXAM BANK COMPUTER TEST Page: 15 of 12 October 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision N/A History: (Le. Modified distracter "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

Reference:

(Le. ON-119 Ensure ON-## not provided)

Low KA Justification (if N/A required): Question 5 Table-Item Links NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.7 Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. 10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION General Question Data Continuing Higher Limerick RO SRO ILT review 6 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Unit 2 plant conditions are as follows: -Reactor was manually scrammed -Reactor level lowered to -10" and recovered -Digital Feedwater is in startup level control with reactor level at + 35" -HPCI starts on a valid initiation signal WHICH ONE of the following describes the status of Reactor Enclosure Ventilation and Drywell Chilled Water systems? RE OW Chilled Water A. RE HVAC OW Chilled Water isolates B. RE HVAC does NOT isolate OW Chilled Water isolates C. RE HVAC OW Chilled Water does NOT isolate D. RE HVAC does NOT isolate OW Chilled Water does NOT isolate Answer: A Answer Explanation: REACTOR ENCLOSURE ISOLATION SIGNALS SIGNAL DIVISION 1 DIVISION 2 SETPOINT

MANUAL HS76-*78A HS76-*78B Arm & Depress . EXH.HI RAD A and B Inst. C and 0 Inst. 1.35 mRlHr
Low RPV A and B Inst. C and 0 Inst. -38", 1.68# level/High OW Pressure
SGTS Damper HV76-*96 HV76-*97 Not full Open closed
Low Zone DP A -0.1" WG for 50 minutes (still a vacuum, but not enough vacuum)

EXAMINATION ANSWER ILT09-1 RO questions in sample plan order RE HVAC isolates; OW Chilled Water isolates: Correct answer with referemce to ARC-MCR-113 H-4 (Div 1) and GP-8.1 U/2 for signal "H" High Drywell Pressure is 1.68 psig which is the initiation signal for a HPCI automatic start. HPCI started on drywell high pressure whereas RPV level dropped to 10" with the RPV low level HPCI aytomatic start is -38". RPV level for an auto HPCI start was not reached. The condition pressure of 2.1 psig is above the isolation setpoint of 1.68 psig stated in the ARC. The high pressure Signal will isolate both REHVAC as well as DWCW. For DWCW, the loop valves (PCIVs) to the drywell will isolate on a high drywell pressure signal, indicative of a problem in the drywell, and isolating the drywell as a possible source i of the high drywell pressure. I I OISTRACTOR RE HVAC does NOT isolate; OW Chilled Water I isolates: Incorrect, REHVAC will isolate as indicated on the RE isolation chart (provided) RE HVAC isolates; OW Chilled Water does isolate: Incorrect, DWCW will isolate as indicated RE HVAC does NOT isolate; OW Chilled Water does NOT isolate: Incorrect, see Justification above Question 6 Info Question Always select on Authorized for Time to

System User-Defined Cross Reference Topic: Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8789 8789 LLOT022.03 Secondary Containment and DWCW response to a high drywell signal 3.3 3.4 295024 EK2.18 General Data Technical Reference with GP-8 I Revisio Revision Number: GP-8.1 n #: Cognitive level High EXAM BANK COMPUTER TEST Page: 18 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Justification for Non SRO 55.41 (b) 7 CFR Link: Question History: (Le. LGS New NRC-OS, OYS CERT-04) Question Source: (Le. New, New Bank, Modified)

Low KA Justification (if N/A required): Revision History: Revision New History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE i Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) N LORT Question Section: N/A (Le, A-Systems or B-Procedures) EXAM BANK COMPUTER TEST Page: 19 of 206 12 October 2010 I 7 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: Points: 1.00 Unit 1 Plant conditions are as follows: -SRVs are being used to control Reactor during an A TWS -Suppression Pool Level is 21' 5" -Suppression Pool Temperature is 160°F -The CRS determines Suppression Pool Temperature CANNOT be maintained on the safe side of the Heat Capacity Temperature Curve. THE CRS directs the PRO to lower Reactor Pressure to remain on the safe side of the curve. WHICH ONE of the following describes why Reactor pressure is lowered to remain on the safe side of the curve? Minimize SRV cycling to prolong SRV availibility Ensure Boron Injection Initiation Temperature (BIIT) is maintained. Support prolonged availability of HPCI and RCIC. Maintain conditions to preclude a failure of the primary containment or a loss of equipment necessary for the safe shutdown of the plant. Answer: D Answer Explanation: Maintain conditions to preclude a failure of the primary containment or a loss of equipment necessary for the safe shutdown of the plan: Correct per T-102 Bases section SPIT-8 which states LGS TRIP step directs actions to control RPV pressure below the Heat Capacity Temperature Limit (HCTL, CURVE SPIT -1) when the action to control suppression pool temperture below the curve have proven unsuccessful. "If the actions being taken to limit the suppression pool temperature rise are inadequate or not effective, RPV pressure must be reduced in order to remain on the safe side of the HCTL. RPV pressure control actions have, therefore, been added to the suppression pool temperature (SPIT) control flowpath to accommodate these requirements. Failure to do so could lead to a failure of the primary containment or a loss of equipment necessary for the safe shutdown of the plant. Minimize SRV cycling to prolong SRV availability: Incorrect due to SRV cycling in progress for pressure control adding reactor heat to the Suppression Pool. This distracter is plausible if chosen to minimize SRV cycling rather than adding heat to the Suppression Pool which is the primary concern during an ATWS. EXAM BANK COMPUTER TEST Page: 20 of 12 October 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR Ensure Boron Injection Initiation Temperature (BIIT): Incorrect due to BIIT defined as 110 degrees. The HCTL curve is well above this. This distracter is plausible as suppression pool temperature is a basis for requirement of boron injection. The candidate may believe lowering reactor pressure is to support maintaining sp temp as a function of boron injection. DISTRACTOR Support prolonged availibility of HPCI and RCIC Incorrect due to action taken actually raises the Suppression Pool Temperature instead of lowering. This distracter is plausible as sp temp can required shutdown of HPCI and RCIC, both of which can be used for high pressure ATWS level control. Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8795 User-Defined 10: 8795 Cross Reference Number: LLOT1560.05 Suppression Pool high temperature requiring lowering Topic: Reactor pressure Num Field 1: 3.8 Num Field 2: 4.1 Text Field: 295026 EK3.01 Comments: GENERAL DATA Technical Reference with T-102, Primary Containment Revision Number: Control Cognitive Level L PRA: (I.e. Yes or No or #) Y 1 OCFR 55.43 (N/A for R055.41 (b)5 RO) Question History: (Le. NEW LGS NRC-05, OYS CERT-04) Question Source: (I.e. New

New, Bank, Modified)

Revision History: Revision N/A History: (i.e. Modified distractor "b" to make plausible based on OTPS review} Supplied Ref (If NONE appropriate): (I.e. ##) EXAM BANK COMPUTER TEST Page: 21 of 206 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

Low KA Justification (if N/A reJjuired): EXAM BANK COMPUTER TEST Page: 22 of 206 12 October 2010 8 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Plant conditions are as follows: -Reactor power is 80% -Power ascension is in progress A malfunctioning level controller on the 1B1 Moisture Separator causes the following: 106 MAIN STEAM F-2, B1 Moisture Separator Drain Tank HI Level 106 MAIN STEAM E-1. Moisture Separator HI Level Trip WHICH ONE of the following is the expected response and the reason for that response? Moisture Separator BTY Valve Response fjjgh Level Trip Logic On a Turbine Trip 1 out of 2 high level (LSH) BTY's close required for a turbine trip 2 out of 3 high level (LSH) BTY's close required for a turbine trip 1 out of 2 high level (LSH) BTV's open required for a turbine trip 2 out of 3 high level (LSH) BTY's open required for a turbine trip Answer: B Answer Explanation: EXAM BANK COMPUTER TEST Page: 23 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Moisture Separator High Level Trip Logic 2 out of 3 high level (LSH) required for a turbine trip: BTV Valve Response on a Turbine Trip -BTV's close Correct due to design of the (6) Moisture Separators. The moisture separators are vertical, cylindrical pressure vessels, whose purpose is to remove moisture from the exhaust steam leaving the H.P. turbine. Each of the six H.P. turbine exhaust lines is connected to its own moisture separator. the steam enters the moisture separator, it must pass through a flow diffuser, which evenly distributes the steam to the separator vanes. The steam then passes through the chevron-shaped vanes, where it is forced to repeatedly make quick changes in direction. The steam makes these direction changes easily, but the moisture is unable to change direction fast enough, and is removed by the vanes. The dry steam that exits the vanes flows around an outlet baffle to the moisture separator outlet, then through the cross-around piping to the low-pressure turbines. The moisture removed by the vanes is directed to the bottom of the moisture separator, then into a drain tank attached to the bottom of the moisture separator. The level in the moisture separator drain tank is controlled by level switches to prevent water from backing up into the moisture separator, and also to maintain a steam/water interface in the drain tank. Water in the drain tank is normally directed to one of the three 4th feedwater heaters. In the event that the 4th feedwater heaters are not in service, or if level cannot be maintained using only the drain to the feedwater heaters, then a second drain valve (dump valve) will open, which sends water directly to the condenser. If the level in the drain tank cannot be maintained below the level of the bottom of the moisture separator (top of the drain tank), then the main turbine will trip. This prevents damaging the low-pressure turbine due to excessive water induction into the turbine. Each moisture separator drain tank has three level switches to sense Hi-Hi level. If 2 out of 3 see Hi-Hi level (102.5 inches above the bottom of the drain tank) on anyone drain tank for at least 10 seconds, then the turbine will trip and a Turbine Trip at greater than -30% power will result in a Reactor Scram. If the level in the drain tank reaches the Hi level setpoint (50.5 inches above the bottom of the drain tank), then the A1 (B1, C1, A2, B2, C2) MOISTURE SEPARATOR DRAIN TANK HI LEVEL alarm will annunciate in the MCR. If the level in the drain tank lowers to the Lo level setpoint (15.5 inches above the bottom of the drain tank), then the A1 (B1, C1, A2, B2, C2) MOISTURE SEPARATOR DRAIN TANK LO LEVEL alarm will annunciate in the MCR. BTV valve response on a turbine trip is air is isolated ! from the BTV due to the EHC extraction relay dump . valve actuation (removes downstream air supply) to a I I number of valves, BTV's included. With the air supply EXAM BANK COMPUTER TEST Page: 24 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR DISTRACTOR DISTRACTOR Question 8 Info Question Type: Status: Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text EXAM BANK COMPUTER TEST isolated the STY's will close as extraction steam attempts to flow in reverse back to the turbines. Therefore the STY's prevent reverse flow (overspeed) of the turbines. Moisture Separator High Level Trip Logic 1 out of 2 high level (LSH) required for a turbine trip: BTV Valve Response on a Turbine Trip -BTV's close Incorrect, See discussion above If 2 out of 3 see Hi-Hi level (102.5 inches above the bottom of the drain tank) on anyone drain tank for at least 10 seconds, then the turbine will trip and a Turbine Trip at greater than -30% power will result in a Reaetor Scram. 'Moisture Separator High Level Trip Logic 1 out of 2 high level (LSH) required for a turbine trip: BTV Valve Response on a Turbine Trip* BTV's open Incorrect, See discussion above If 2 out of 3 see Hi-Hi level (102.5 inches above the bottom of the drain tank) on anyone drain tank for at least 10 seconds, then the turbine will trip and a Turbine Trip at greater than -30% power will result in a Reactor Scram. STY valve response on a turbine trip is air is isolated from the STV due to the EHC extraction relay dump valve actuation (removes downstream air supply) to a number of valves, STY's included. With the air supply isolated the STY's will close as extraction steam attempts to flow n reverse back to the turbines. Therefore the STY's prevent reverse flow (overspeed) of the turbines. Moisture Separator High Level Trip Logic 2 out of 3 high level (LSH) required for a turbine trip: BTV Valve Response on a Turbine Trip* BTV's open Incorrect, See discussion above Multiple 3.00 LGSOPS0001 With main generator is loaded on the grid the drain valve 2.5 2.6 295005 AK3.05 II General Data I Page: 25 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Technical Reference with Revision Number: Justification for Non SRO CFR Link: Cognitive Level Question History: (Le. LGS NRC-05, OYS CERT-04) Question Source: (Le. New, Bank, Modified) Low KA Justification (if required): Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (Le. ABN-##) Excluded

Reference:

(Le. Ensure ON-##. not provided)

Revisio LGSOPSOOO1 n #: B 55.41 (b) 5 L New New N/A N/A None LGSOPS0001 B ARC-MCR-1 06-F2 JE1 ) LORT PRA: (i.e. Yes or No or #) Y LORT Question Section: A (i.e, A-Systems or B-Procedures) High-High level in anyone moisture separator will cause the main turbine to trip. A turbine trip at greater that 30% power will result in a full scram KiA 295005 AK3.05 EXAM BANK COMPUTER TEST Page: 26 of 206 12 October 2010 I 9 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Unit 2 plant conditions are as follows: -Reactor power is -"2A" Recirculation Pump has -"2B" Recirculation Pump remains in -"2B" and "2C" RWCU pumps are in The running "2A" RECW pump trips, and the standby "2B" RECW pump fails to start WHICH ONE of the following identifies required action and basis for the action? Trip "2B" Reactor Recirculation pump within 1 0 minutes to minimize damage to motor windings Isolate tripped RWCU pumps to minimize erosion across pump seals Lower "2B" Reactor Recirculation pump speed, and maintain at low speed setting to prevent seal cavity failures Isolate tripped RWCU pumps to minimize pump pedestal heating, to maintain pump-motor alignment Answer: B Answer Explanation: Isolate tripped RWCU pumps to minimize erosion across pump seals: Correct per ON-113 Step 2.14 IF RWCU Pumps trip due to loss of RECW flow, THEN manually ISOLATE RWCU Pumps per S44.2.B, RWCU Recirculation Pump Shutdown. BASIS: The time RWCU Recirc Pump(s) are idle and lined up to system pressure must be minimized. This will minimize erosionlleakage across seals due to system pressure. Trip Reactor Recirculation pumps within 10 minutes to minimize damage to motor windings: Incorrect due ON-113 CAUTIONS IF RECW flow is not restored to Reactor Recirculation (Recirc) Pump seals (not windings) within 10 minutes. THEN U-cup damage AND seal failure may result. Pump manufacturer's recommendations for protection of Recirc Pump seal components. Extended operation of the Recire Pumps beyond the manufacturer's recommendations of ten minutes without seal cooling may cause increased thermal stress and checking of the seal carbon faces, and thermal damage to U-eups. Pump tripping is based upon a time basis because seal cavity temperatures may not reflect individual component temperature during transient conditions. EXAM BANK COMPUTER TEST Page: 27 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Lower Reactor Recirculation pumps speed, and maintain at low speed setting to prevent seal cavity failures: Incorrect, but plausible. It is NOT the manufactures recommendation per the ON-113, Loss of RECW, procedure. Pump manufacturer's recommendations for protection of Recirc Pump seal components. Isolate tripped RWCU pump to minimize pump pedestal heating, to maintain pump-motor alignment: Incorrect due to the "B" and "c" Rwcu pumps being in service. If the "A"RWCU pump was in service and a loss of CRD flow was established this distractor may apply. However, the makeup of the "B' and "C" RWCU pumps makes this distractor incorrect. J Question 9 Info Question Type: Multiple Choice i Status: Active Always select on test? No Authorized for practice? No I Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8778 User-Defined /0: 8778 Cross Reference Number: LLOT1550.02 Unit 2 is operating at 100% power when the following Topic: transient occurs: -"2A" RECW Pump trips on a Num Field 1: 3.1 Num Field 2: 3.3 Text Field: 295018 AK3.03 Comments: General Data J Technical Reference with On-113, Loss of RECW I Revision Number: Cognitive Level L PRA: (Le. Yes or No or #) Y 10CFR 55.43 (N/A for RO) 55.41 (b) 5 Question History: (i.e. LGS New NRC-05, OYS CERT -04) Question Source: (i.e. New, New

Bank, Modified)

Revision History: Revision N/A History: (i.e. Modified distracter "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE i appropriate): (Le. ABN-##) .1 EXAM BANK COMPUTER TEST Page: 28 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Excluded

Reference:

(Le. ON-113 Ensure ON-## not provided)

Low KA Justification (if N/A required): Question 9 Table-Item Links NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.5 Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics. 10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 45.6 Perform control manipulations required to obtain desired operating results during normal, abnormal, and emergency situations. General Question Data Continuing Higher Limerick RO SRO EXAM BANK COMPUTER TEST Page: 29 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8779 Points: 1.00 A refueling Outage is in progress on Unit 2, with plant conditions as follows: Fuel Shuffle is in progress -'JJA" ADHR is in service -ANN Panel20C222 "Refuel Bellow Leak Detect" Alarm is received -Refuel Floor Personnel report Lowering Fuel Pool Level WHICH ONE of the following describes the level to which the Reactor Vessel and Spent Fuel Pool will drain if no operator action is taken? Reactor Vessel Fuel Pool Will Drain to: Will Drain to: A. Cavity Weir Plates Bottom of the Transfer Canal B. Cavity Weir Plates Fuel Pool Weir Plates C. Vessel Bottom of the Transfer Canal D. Vessel Fuel Pool Weir Plates Answer: C Answer Explanation: Vessel Flange; Bottom of the Transfer Canal: Correct because refuel bellows is connected to the reactor at the bottom of the reactor cavity. A leak in the bellows, without makeup will result in water level dropping to the top of the vessel flange. Additionally, as fuel shuffle is in progress, the fuel pool gates are removed, and water in the fuel pool will drain to the bottom of the transfer canal. ADHR is in service which takes a suction from the fuel pool skimmer surge tanks. When level drops below the top of the skimmer surge tanks weir overflow the skimmer surge

tank level rapidly lowers c.ausing RHR pump vortex with ultimately water return to the vessel lost. Vessel level drops only to the vessel flange level and Spent Fuel Pool
level drops only to the top of the transfer canal.

Cavity Weir Plates; Bottom of the Transfer Canal: Incorrect due to water will continue to drain below weir plates as noted above Cavity Weir Plates; Fuel Pool Weir Plates: Incorrect due to water will continue to drain below weir plates as noted above. Additionally, water will stop draining from the fuel pool at the bottom of the transfer canal, which is above the top of the fuel storage racks EXAM BANK COMPUTER TEST Page: 30 of 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Vessel Flange; Fuel Pool Weir Plates: Incorrect due to Same as above Question 10 Info Question : Always select on Authorized for Time to $ystem User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No 3 3.00 8779 8779 LLOT0750.10 Refuel bellow leak impact on cavity and fuel pool level 2.9 3.2 295023 AA2.02 General Data , Technical Reference with ON-120 Revisio

Revision Number: S53.0.A n #: :1 2GP6.1 ! Justification for Non SRO 55.41 (b)7 CFR Link:
Cognitive Level H Question History: (I.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (I.e. New, NEW Bank, Modified)

Low KA Justification (if N/A required): Revision History: Revision NEW History: (I.e. lVIodified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If N/A appropriate): (I.e. ABN-##) Excluded

Reference:

(I.e. N/A Ensure ON-## not provided)

EXAM BANK COMPUTER TEST Page: 31 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8790 Points: 1.00 Plant conditions are as follows: -Unit 1 Reactor Enclosure HVAC is in service -Unit 1 Refuel Floor HVAC is in service -Refuel Floor Secondary Containment integrity is established (SGD-206-3, is OPEN) -Fuel Pool cleanout is in progress using a portable vacuum cleaner The vacuum cleaner filter breaks open during movement, resulting in a Refuel Floor high airborne contamination condition and 3.0 mRlhr on the Refuel Floor Exhaust rad monitors WHICH ONE of the following monitoring points is expected to show a valid measure of the offsite release five (5) minutes later? A. Unit 1 Reactor Enclosure Exhaust rad monitors B. Unit 1 Refuel Floor Exhaust rad monitors C. North Stack Wide Range Accident monitor D. Unit 1 South Stack Effluent rad monitor Answer: C Answer Explanation: North Stack Wide Range Accident monitor: Correct because Refueling Area ventilation exhaust isolates at 2.0 mr/hr and if aligned SBGT will initiate and align to the Refuel Floor. SBGT exhausts at the North Stack and therefore, the North Stack Wide Range Accident Monitor in conjunction with the North Stack radiation monitor will be used to measure the offsite release. Unit 1 Reactor Enclosure Exhaust rad monitors: Incorrect due to Refuel Floor secondary containment being established. SGD-206-3 is open which allows the Refuel Floor to align to SBGT should an Refuel Floor isolation occur.(vs the SGD being closed, ie. Refuel Floor does not align th SBGT) During this evolution 3.0 mr as sensed by Refuel Floor Exhaust is an isolation. This tests an understanding if an isolation occurs. Unit 1 Reactor Enclosure exhaust rad monitors are in service, however there is no indication of zone 1 and zone 3 tied together which ties Unit 1 Reactor Enclosure to the Refuel Floor. If the SGD were closed, SBGT would not align to the Refuel Floor and logic isolation of either Unit 1 and Unit 2 Ventilation flowpaths would not be indicated in the North Stack during an radiation isolation. EXAM BANK COMPUTER TEST Page: 32 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Unit 1 Refuel Floor Exhaust rad monitors: Incorrect due to Refuel Floor isolation logic isolation of both Unit 1 and/or Unit 2 Refuel Floor ventilation flowpaths on a valid isolation signal from either unit exhaust radiation monitors. Initially, the Refuel Floor exhaust rad monitors sensed radiation on the Refuel Floor, however Refuel Floor ventilation isolates on a sensed high radiation signal, and the radiation signal would dissipate. Unit 1 South Stack Effluent rad monitor: Incorrect to Refuel Floor isolation logic isolation of both Unit 1 Unit 2 Ventilation flowpaths on a valid isolation signal either unit exhaust radiation monitors. Flow from Refuel Floor to the South Stack is isolated. However to the SGD open Refuel Floor is ventilated to the Stack. All other normal ventilation that normally through the South Stack remain in service. The Stack rad monitor would only see the offsile release if Refuel Floor ventilation remained in service either due the SGD not open or the actual radiation signal sufficient to isolate the HVAC J Question 11 Info Question Type: Multiple : Active I* select on test? No j Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 8790 User-Defined ID: 8790 Cross Reference Number: LGSOPS0026.04 Identify the location of measured offsite release point Topic: following 3.0 mr/hr on Refuel Num Field 1: Num Field 2: Text Field: 295038 General Data Technical Reference with P&ID M-76 Revisio Revision Number: ARC 003 RAD n#: E-1, C-5 ARC 004 VENT E-3 ! Cognitive Level H Justification for Non SRO 55.41 (b) 7 CFR Link: Question History: (i.e. LGS NRC-05. OYS CERT-04) EXAM BANK COMPUTER TEST Page: 33 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question Source: (Le. New, Bank, Modified) Low KA Justification (if required): Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) Modified N/A Modified to include RE HVAC and RE HVAC rad monitors into stem and distracters. Also eliminated U#1 RF FLR HVAC from directly sensinQ the isolation ILT Supplied Ref (If appropriate): (i.e. Excluded

Reference:

(Le. Ensure ON-## not LORT PRA: (Le. Yes or No or #) N LORT Question Section: A (Le, A-Systems or B-Procedures)

KIA 295038 EA1.04 RO 2.8 SRO 3.2 EXAM BANK COMPUTER TEST Page: 34 of 206 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8796 Points: 1.00 Plant conditions are as follows: -LOCA is in progress -The steam leak causes the Drywell and Suppression Pool temperature and pressure to increase The CRS verifies drywell temperature and pressure are on the SAFE side of the DRYWELL SPRAY INITIATION LIMIT curve, per T-102, PRIMARY CONTAINMENT CONTROL, and directs the PRO to Spray the Drywell WHICH ONE of the following identifies the purpose of verifying the Drywell parameters prior to spraying the Drywell? Prevent Containment damage due to excessive pressure drop upon spray initiation Ensure sufficient DP between Drywell and Suppression Pool for adequate condensation Ensure temperature is low enough to prevent Suppression Chamber "chugging" when sprays are initiated Prevent covering Suppression Chamber to Drywell Vacuum Breakers and hindering their operation Answer: A Answer Explanation: EXAM BANK COMPUTER TEST Page: 35 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Prevent Containment damage due to excessive pressure drop upon spray initiation: Correct because T-102 Bases section DW/T-8 is a continue re-checking step and indicates that Drywell sprays should be initiated prior to temperature reaching 340 degrees if on the safe side of Curve DW/T-3 and Suppression Pool level is below 38.7 feet. Drywell spray operation effects a drywell pressure and temperature reduction through the combined effects of evaporative cooling and convective cooling. Evaporative cooling refers to spray droplet heat and mass transfer which occurs when water is sprayed into a superheated atmosphere. This process results in an immediate, rapid and large reduction in drywell pressure at a rate much faster than can be compensated for by the primary containment vacuum relief system. Unrestricted operation of drywell sprays could thus result in a negative drywell-to-suppression pool differential pressure large enough to cause a loss of primary containment integrity. Considering the pressure drop concerns described above, the Drywell Spray Initiation Limit (DSIL) Curve is defined to be the highest drywell temperature at which initiation of drywell sprays will not result in an evaporative cooling pressure drop to below either: The drywell-below-suppression pool differential pressure capability, or The high drywell pressure scram setpoint. Ensure sufficient DP between Drywell and Suppression Pool for adequate condensation: Incorrect due to oppOSite of actual concern for evaporative cooling. Drywell spray operation effects a drywell pressure and temperature reduction through the combined effects of evaporative cooling and convective cooling. This process results in an immediate, rapid and large reduction in drywell pressure at a rate much faster than can be compensated for by the primary containment vacuum relief system. Unrestricted operation of drywell sprays could thus result in a negative suppression pool differential pressure large enough to cause a loss of primary containment integrity. Ensure temperature is low enough to prevent Suppression Chamber "chugging" when sprays are initiated: Incorrect due to expected equalization of Drywell Pressure with Suppression Pool as Vacuum Breakers actuate on Drywell Spray initiation. Only by unrestricted operation of drywell sprays could thus result in a negative drywell-to-suppression pool differential pressure large enough to cause a loss of primary containment integrity. EXAM BANK COMPUTER TEST Page: 36 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Prevent covering Suppression Chamber to Vacuum Breakers and hindering their Incorrect due to initiation limit of 38.7 feet to prevent covering the vacuum breakers and inhibiting equalization on Evaporative cooling. Drywell spray operation effects a drywell pressure and temperature reduction through the combined effects of evaporative cooling and convective cooling. Evaporative cooling refers to spray droplet heat and mass transfer which occurs when water is sprayed into a superheated atmosphere. This process results in an immediate, rapid and large reduction in drywell pressure at a rate much faster than can be compensated for by the primary containment vacuum relief system. Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8796 User-Defined 10: 8796 Cross Reference Number: LIMERICK LOT 3696 identifies the purpose of ensuring parameters are on the Topic: SAFE side of the DRYWELL SPRAY INITIATION Num Field 1: R03.8 Num Field 2: SRO 3.9 Text Field: 295028 EA 1.01 Comments: General Data Technical Reference with T-102 Bases I Revisio Revision Number: n#: Cognitive Level L Justification for Non SRO 55.41 (b) 7 CFR Link: Question History: (I.e. LGS Bank NRC-05, OYS CERT-04) Question Source: (I.e. New, Bank Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision Bank History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT I Supplied Ref (If none I appropriate): (I.e. ABN-##) EXAM BANK COMPUTER TEST Page: 37 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Excluded

Reference:

(Le. none Ensure ON-## not provided)

LORT PRA: (Le. Yes or No or #) Y LORT Question Section: AlB (i.e. A-Systems or B-Procedures)

Reference:

T-102 EXAM BANK COMPUTER TEST Page: 38 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 13 ID: 8776 Points: 1.00 Unit 1 plant conditions are as follows: -OPCON 3 -Reactor water temperature is 275 deg.F and steady -"1A" RHR loop is in Shutdown Cooling -HV-51-1F003A ("A" RHR HX Outlet) is closed -HIC-51-103A ("A" RHR HX Outlet Bypass) is 30% open -Drywell temperature is 126 deg.F The instrument air line to HV-C-103A ruptures S' GSB-HT WHICH ONE of the following describes the effect on actual reactor water temperature and temperature indicated at TE-51-1 N004A ("A" RHR HX Inlet Temp) ten (10) minutes later without operator action? Actual Reactor Water Temperature TE-51-1N004A Indication A. rises rises B. rises lowers C. lowers rises D. lowers lowers Answer: B EXAM BANK COMPUTER TEST Page: 39 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Answer Explanation: rises; lowers: Correct because actual reactor water temperature will rise due to loss of cooling. The loss of instrument air to HV-C-103A will result in the valve failing closed. This will result in a loss of flow through the RHR heat exchanger and a loss of cooling. TE-51-2N004A indicated temperature will lower due to inadequate flow and ambient cooling in that section of piping. As the heat exchanger outlet valve bypass closes, more water bypasses the heat exchanger and therefore reactor water temperature will increase. With flow through the heat exchanger isolated temperature in the heat exchanger i piping will tend to decrease. i rises; rises: Incorrect due to actual reactor water temperature will rise due to loss of cooling. 2N004A indicated temperature will lower due to inadequate flow and ambient cooling. lowers; rises: Incorrect due to actual reactor water temperature will rise due to loss of cooling. 2N004A indicated temperature will lower due to inadequate flow and ambient cooling. DISTRACTOR lowers; lowers: Incorrect due to actual reactor water i temperature will rise due to loss of cooling. i 2N004A indicated temperature will lower due to I inadequate flow and ambient cooling. Question 13 Info !Question Type: Multiple ChoicB Status: Active select on test? No Authorized for practice? No 1.00 i Time to Complete: 3 Difficulty: 3.00 System 10: 8776 User-Defined 10: 8776 Cross Reference Number: ON-121, Loss of Shutdown temperature indication Num Field 1: 13.6 Num Field 2: Text Field: Comments: General Data Technical Reference with I ON-121, ST-6-107-640-2 Revision Number: EXAM BANK COMPUTER TEST Page: 40 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Cognitive Level H Justification for Non SRO 55.4'1 (b) 6 CFR Link: PRA: (i.e. Yes or No or #) Y 10CFR 55.43 (N/A for RO) N/A Question History: (Le. LGS IL T Cert Exam 2005 NRC-05, OYS CERT -04) Question Source: (Le. New, Bank Bank, Modified) Revision History: Revision N/A History: (Le. Modified distractor "b" to make . plausible based on OTPS review) ILT Supplied Ref (If appropriate): (Le. ABN-##) NONE i Excluded

Reference:

(Le. ON-121, Loss of Ensure ON-## notprovidedj Shutdown cooling Low KA Justification (if N/A) reguired}:

13 Table-Item links NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility. 10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. CFR: 45.13 Demonstrate the applicant's ability to function within the control room team as appropriate to the aSSigned position, in such a way that the facility licensee's procedures are adhered to and that the limitations in its license and amendments are not violated. General Question Data Continuing Higher Initial Limerick RO SRO EXAM BANK COMPUTER TEST Page: 41 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8792 Points: 1.00 Unit 1 plant conditions are as follows: -OPCON 1 -"1A" RHR in Suppression Pool Cooling with "OA" RHRSW pump -"1A" CRD Pump is in service -DIV 3 DC bus is de-energized due to ground fault 5 minutes later a LOCA occurs results in reactor level lowering to -130". 30 seconds following the LOCA signal, DIV 2 DC bus is deenergized WHICH ONE of the following identifies pumps that will be running 1 minute following the LOCA signal WITHOUT operator action? A. "1A" CRD and "1C" RHR B. "OA" RHRSW and "1 CIt RHR C. "1A" RHR" and "1A" CRD and "18" RHR D. "1A" RHR and "OA" RHRSW and "1B" RHR Answer: C Answer Explanation: "iA" RHR" and "1A" CRD and "1S" RHR: Correct because: "1A" RHR is unaffected by the loss of Div 3 or Div 2 DC Loss of Div 3 DC will result in 1 A CRD continuing to operate during the LOCA (will not load shed) "18" RHR will have already started following the LOCA prior to the loss of Div 2 DC "iA" CRO and "1C" RHR: Incorrect due to: Partially Correct: Loss of Div III DC will result in 1A CRD continuing to operate during the LOCA (will not load shed) Incorrect: "1 C RHR" will not start on the LOCA due to loss of DIV 3 DC "iA" RHR and "OA" RHRSW and "1S" RHR: Incorrect due to: Partially Correct"1 A" RHR is unaffected by the loss of Div 3 or Div 2 DC Incorrect: "OA" RHRSW will trip on the LOCA signal, and will not start without operator action Partially Correct"1 B" RHR will have already started following the LOCA prior to the loss of Div 2 DC. EXAM BANK COMPUTER TEST Page: 42 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order DISTRACTOR "OA" RHRSW and "1C" RHR: Incorrect due to: Incorrect: "OA" RHRSW will trip on the LOCA signal, and will not start without operator action Incorrect: "1C RHR" will not start on the LOCa due to loss of DIV 3 DC Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 6 i 4.00 System ID: User-Defined ID: *Cross Reference Number: Division 3 DC bus de-energized due "1 A" CRD Pump is in Topic: service; No Num Field 1: Num Field 2: Text Field: 295004 General Data Technical Reference with E-1FC Revision Number: S92.1.A S92.1.D Cognitive Level H . Justification for Non SRO 55.41 (b) 10 CFR link: Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS . review) I ILT Supplied Ref (If NONE (Le. ABN-##J Excluded

Reference:

(Le. E-1FC Ensure ON-## not provided)

S92.1.A I S92.1.D I LORT I PRAJLe. Yes or No or #) Y LORT Question Section: A (Le, A-Systems or B-Procedures) EXAM BANK COMPUTER TEST Page: 43 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order \IL-____----L-__---..JI\ EXAM BANK COMPUTER TEST Page: 44 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 15 10: 8783 Points: 1.00 Unit 1 is operating at 85% power when a Digital Feedwater Control System malfunction causes a rise in reactor level with the following: -The reactor scrams at -Reactor level continues to rise to -Reactor pressure is 1070 psig and -The Main Steam Isolation Valves (MSIV's) are manually The CRS directs RPV pressure control using SRV's per OT-110, REACTOR HIGH LEVEL WHICH ONE of the following identifies how reactor pressure will be controlled? A. Manual operation of a single SRV repeatedly B. Manual operation rotating among ALL SRV's C. Allow SRV's to cycle automatically on pressure D. Manual operation rotating among the ADS SRV's ONLY Answer: A Answer Explanation: EXAM BANK COMPUTER TEST Page: 45 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Manual operation of a single SRV repeatedly: Correct because in OT-110 for the situation where Main Steam lines are flooded there are three scenarios. The first case is addressed with RPV pressure below 700 pSig, the Operator is directed to maintain RPV pressure below 700 psig utilizing B, C or ,I SRV. It is desirable to manually open an SRV at a lower RPV pressure (Le., earlier in the event), rather than later (at a higher RPV pressure). The SRV discharge loads will be greater at higher RPV pressure. In this situation, manually opening either the B, C, or J SRV is desirable. These are the only SRVs in each unit with straight runs of discharge piping (no elbows) in the Suppression Pool (from Drywell slab down to the quencher). This will even further minimize the potential for a line break in the Suppression Pool airspace. The second case (step 3.15) addresses the situation where RPV pressure reaches 1096 psig with multiple automatic SRV operation expected on further RPV pressure rise. The Operator is directed to manually open B, C or J SRV to reduce and maintain RPV pressure below 700 psig. This action is prescribed to limit SRV discharge in the shaded region of ATTACHMENT 1 to a single SRV, thus minimizing the adverse affects on the plant (Le. limit any possible damage to a single SRV and tailpipe). SRV operation, with the Main Steam lines flooded, should be limited to a single SRV (B, C or J) if possible/practical. This action will limit any possible adverse consequence, due to higher than normal loads, to a single SRV. The decision to use multiple SRVs may be required due to other considerations such as local Suppression Pool temperatures and individual SRV performance. The final case is the situation where RPV pressure is above 700 psjg and the Operator is able to lower RPV level to below the Main Steam lines prior to reaching 1096 psig. Manual operation rotating among ALL SRV's: Incorrect due to contradiction with above statement. The Operator is directed to manually open B, Cor J SRV to reduce and maintain RPV pressure below 700 psig. This action is prescribed to limit SRV discharge in the shaded region of ATTACHMENT 1 to a single SRV, thus minimizing the adverse affects on the plant (Le. limit any possible damage to a single SRV and tailpipe). Allow SRV's to cycle automatically on pressure: Incorrect due to contradiction with above statement: The Operator is directed to manually open B, Cor J SRV to reduce and maintain RPV pressure below 700 psig. This action is prescribed to limit SRV discharge in the shaded region of ATTACHMENT 1 to a single SRV, thus minimizing the adverse affects on the plant (Le. limit any possible damage to a single SRV and tailpipe). EXAM BANK COMPUTER TEST Page: 46 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Manual operation rotating among the ADS SRV's ONLY: Incorrect due to contradiction with above statementThe Operator is directed to manually open Bf C or J SRV to reduce and maintain RPV pressure below 700 psig. The ADS valves S,H,M,E,and K are not specifically used for high RPV level situations. This action is prescribed to limit SRV discharge in the shaded region of ATTACHMENT 1 to a single SRV, thus minimizing the adverse affects on the plant (Le. limit any possible damage to a single SRV and tailpipe). Question 15 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: 3 3.00 System 8783 User-Defined 10: 8783 Cross Reference Number: Unit 1 is operating at 85% power when a Digital Feedwater Topic: Control System malfunction causes a rise Num Field 1: 3.7 l\Ium Field 2: 3.8 Text Field: 295025 EA2.06 Comments: General Data Technical Reference with OT-110, RPV Revisio Revision Number: high level n#: LOT1540.04 Cognitive Level L Justification for Non SRO 55.41 (b) 10 CFR Link: Question History: (Le. LGS Bank NRC-05, OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision Bank History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If None appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. OT-110 Ensure ON-## not provided)

EXAM BANK COMPUTER TEST Page: 47 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order LORT PRA: (i.e. Yes or No or #) Y LORT Question Section: B (i.e, A-Systems or B-Procedures) EXAM BANK COMPUTER TEST Page: 48 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8797 Points: 1.00 A Drywell leak has caused the following plant conditions: -Reactor pressure is 900 psig -Reactor level is -65" and slowly increasing -Suppression Pool temperature is 130 deg F -Suppression Pool level is 17.9' and steady -HPCI and RCIC automatically started and aligned to the reactor -Both "A" and "B" loops of Suppression Pool cooling are in service WHICH ONE of the following procedures are required for the given plant conditions? A. S49.2.A, RCIC Shutdown From Automatic or Manual Initiation B. S55.2.A, HPCI Shutdown from Automatic or Manual initiation C. S51.B.A, Suppression Pool Cooling operation and level control D. S51.B.K, RHR Full flow test and Suppression Pool level control Answer: B Answer Explanation: S55.2.A, HPCI Shutdown from Automatic or Manual initiation: Correct because T-102, Primary Containment Control, requires HPCI to be secured if Suppression Pool level cannot be maintained above 18 ft. When it is determined that SP level will not be able to be maintained above the elevation of the HPCI turbine discharge (18 ft), HPCI is required to be taken out-of-service. Operation of HPCI system with its exhaust disscharge device not submerged will directly pressurize the suppression pool. HPCI system operation is therefore secured as required to preclude the occurance off this condition. The consequences of not doing so may extend to failure of the primary containment from overpressurization, and thus HPCI system must be secured regardless of adequate core cooling concerns. S49.2.A, RCIC Shutdown From Automatic or Manual Initiation: Incorrect due to T-102, Primary Containment Control, doe not require RCIC to be secured if Suppression Pool level cannot be maintained above 18 ft S51.8.A, Suppression Pool Cooling operation and level control: Incorrect due to the purpose of this procedure is for startup/shutdown SP cooling mode of RHR and to provide a method to lower SP level whereas SP level is <18' already EXAMINATION ANSWER IL T09-1 RO questions in sample plan order SS1.8.K, RHR Full flow test and Suppression Pool level control: Incorrect due to the purpose of this procedure is to place RHR in full flow test and/or to provide a method to lower SP level whereas SP level is < 18' already Question 16 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: 3 3.00 System ID: 8797 User-Defined ID: 8797 Cross Reference Number: Execute plant procedures with Suppression Pool low level Num Field 1: R04.3 Num Field 2: SR04.4 Text Field: 295030 B2.1.23 Comments: General Data Technical Reference with T -102, Primary Revision Number: Containment Control LOT0340.03 Cognitive Level H PRA: (Le. Yes or No or #) Y t}Q9=R 55.43 (N/A for RO) 55.41 (b) 10 Question History: (Le. LGS New NRC-05, OYS CERT-04) Question Source: (Le. New, New Bank, Modified) Revision History: Revision N/A History: (i.e. Modified distracter "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) ! Excluded

Reference:

(Le. T-102 bases Ensure ON-## not provided)

Low KA Justification (if N/A required): KIA 295030 B2.1.23 RO 4.3 SRO 4.4 EXAM BANK COMPUTER TEST Page: 50 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 17 10: 8787 Points: 1.00 Plant conditions are as follows: -Main control room has been evacuated -1 01-D23, and 201-D23 4.16 KV safeguard feeder breakers are open -D23 Emergency Diesel Generator (EDG) breaker is closed -Differential pressure across the D23 EDG heat exchanger indicates NO ESW flow WHICH ONE of the following describes controls available to initiate ESW flow to the D23 EDG? A. OA ESW pump can be started from the Unit 2 Remote Shutdown Panel ONLY. B. OC ESW pump can be started from the Unit 1 Remote Shutdown Panel ONLY. C. OC ESW pump can be started from the Unit 2 Remote Shutdown Panel ONLY. D. OA ESW pump can be started from the Unit 1 Remote Shutdown Panel ONLY. Answer: D Answer Explanation: EXAM BANK COMPUTER TEST Page: 51 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order OA ESW pump can be started from the Unit 1 Remote Shutdown Panel ONLY: Correct because OA ESW pump controls are located on the Unit 1 Remote Shutdown Panel (RSP) ONLY. There are NO ESW pump controls located on the Unit 2 Remote Shutdown Panel. The OA ESW pump is also the only ESW pump controlled from the Remote Shutdown Panel. From SE-1, Remote Shutdown: OBSERVE bus power available lights AND breaker indicating lights to determine that the following are energized: -D*1 Safeguard -D*2 Safeguard -D*3 Safeguard PERFORM the following for any running diesel generator: VERIFY ESW is available by observing dP across DG heat exchangers (ESW supply PI-11-*07A(B,C,D) indicates higher pressure than ESW return PI-11-*OSA(B,C,D>>. PERFORM hourly checks per S92.9.N, Routine Inspection of Diesel Generators, until diesel is shutdown. IF A ESW pump is not running, THEN PERFORM the following: START OAP54S, "A ESW Pump" (PUMP A). VERIFY OAP54S, PUMP A, running. OA ESW pump can be started from the Unit 2 Remote Shutdown Panel ONLY: Incorrect due to contradiction with above information: OA ESW pump controls are located on the Unit 1 Remote Shutdown Panel (RSP) ONLY. There are NO ESW pump controls located on the Unit 2 Remote Shutdown Panel. OC ESW pump can be started from the Unit 1 Remote Shutdown Panel ONLY: Incorrect due to contradiction with above information: OA ESW pump controls are located on the Unit 1 Remote Shutdown Panel (RSP) ONLY. There are NO ESW pump controls located on the Unit 2 Remote Shutdown Panel. OC ESW pump can be started from the Unit 2 Remote Shutdown Panel ONLY: Incorrect due to contradiction with above information: OA ESW pump controls are located on the Unit 1 Remote Shutdown Panel (RSP) ONLY. There are NO ESVV pump controls located on the Unit 2 Remote Shutdown Panel. EXAM BANK COMPUTER TEST Page: 52 of 12 October 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 17 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8787 8787 LLOT0735.02 Control board actions with a partial loss of AC power 3.6 3.6 295003 B2.2.4 General Technical Reference with Revision Cognitive Leve! Justification for Non SRO 55.41 (b) CFR Question History: (I.e. LGS NRC-05, OYS Question Source: (I.e. New, Bank, Low KA Justification (if Revision History: Revision History: (Le. distractor "b" to plausible based on Supplied Ref (If appropriate): (I.e. Excluded

Reference:

(I.e. Ensure ON-## not PRA: (I.e. Yes or No or #) LORT Question Section: (i.e, A-Systems or EXAM BANK COMPUTER TEST Page: 53 of 206 12 October 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8793 Points: 1.00 Plant conditions are as follows: -The MCR has become uninhabitable due to smoke while at 100% power -Operators only had sufficient time to complete the Immediate Operator Actions required before exiting the MCR WHICH ONE of the following describes the status of RPV pressure control and RPV Injection while the operators are relocating to the RSP based on the above conditions?

RPV Pressure RPV Injection A. Turbine bypass valves in automatic RCIC due to manual initiation B. Turbine bypass valves in automatic Control Rod Drive pumps C. SRVs RCtC due to manual initiation D. SRVs Control Rod Drive pumps Answer: D Answer Explanation: SRVs only; Control Rod Drive pumps: Correct because of reference to SE-1 and FSSG-3020 Notes and Cautions. SE-1 Immediate Operator Actions include Manually SCRAM both unit Reactors Placing Mode Switches in SHUTDOWN Tripping the Main Turbines and ClOSing the MSIVs. Without an automatic initiation signal to HPCI and/or RCtC at -38 inches in RPV, the SRVs will be the only pressure control Per T-101, until control transfers to the RSPs. Although SE-1 section 4.1.2.2 has manual start of RCtC, this is not an Immediate Operator Action. The Feedwater pumps will be eliminated due to closing the MSIVs and the . CRD pumps will be the only remaining source of High Pressure Injection maintaining level per T-101. i Turbine bypass valves in automatic; RCIC due to manual initiation: Incorrect due to Turbine Bypass valves not available with MSIVs closed and RelC not available due to not starting as an Immediate Operator Action. Plausible do to the Turbine Bypass Valves normally control reactor pressure during shutdown, however the MSIVs are closed which renders the Turbine Bypass Valves not available. EXAM BANK COMPUTER TEST Page: 54 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Turbine bypass valves in automatic; Control Rod Drive pumps: Incorrect due to Turbine Bypass Valves not available with MSIVs closed. (Partially Correct for CRD pumps) SRVs only; RCIC due to manual initiation: Incorrect due to RCIC not manually started as an Immediate Operator Action. (Partially Correct for SRVs) RCIC will be placed in service at the RSP f however it is not placed in service as an lOA for SE-1. Plausible, due to RCIC could be placed in service in the MCR assuming time permitted. RCIC is a follow up action in SE-1. Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 8793 User-Defined 10: 8793 Cross Reference Number: LLOT1563.01 , LLOT1563.02 Topic: SE-1 Pressure and level control while relocating Num Field 1: R03.8 Num Field 2: SR04.5 Text Field: 600000 B2.4.8 Comments: General Data Technical Reference with FSSG-3020 Revisio Revision Number: Fire Area 020 n #: guide I Cognitive Level H I Justification for Non SRO 55.41 (b) 10 CFR Link: Question History: (Le. LGS Bank NRC-05, OYS CERT -04) Question Source: (Le. New, Bank Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If None appropriate): (Le. ABN-##) I EXAM BANK COMPUTER TEST Page: 55 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Excluded

Reference:

(Le. FSSG-3020 Fire Area , Ensure ON-## notprovided) 020jJuide LORT PRA: {Le. Ves or No or #} V LORT Question Section: B (i.e, A-Systems or B-Procedures)

EXAM BANK COMPUTER TEST Page: 56 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ID: 8798 Points: 1.00 Plant conditions are as follows: -PJM has initiated a "Voltage Reduction Curtailment Action" -E-5, GRID EMERGENCY has been entered Unit 1 Main Generator current conditions are as follows: -230 MVAR's -"1 GEN HYDROGEN AND SEAL OIL SYS TROUBLE ALARM" annunciates at 125 GEN and an EO reports that generator hydrogen pressure is 60 psig and steady at PI-028-103 on panel 10C120 WHICH ONE of the following identifies the required action? A. Raise hydrogen pressure to 65 psig B. Reduce generator output below 1125 MWe. C. Reduce reactive load to 110 MVAR's lagging. D. Maintain current generator output due to Voltage Reduction Curtailment Action Answer: B Answer Explanation: Reduce generator output below 1125 MWe: Correct because This would move in response to the noted "Max Emergency Generation Action" in response to grid voltage. The "Generator Capability Curve" or the table in attachment 2, provides direction to maintain the generator/exciter in a safe condition while responding to MVAR needs requested by PSD (SysOps). The "Generator Capability Curve" table enhances the curve for clear direction on maximum MVAR values in relation to MWe where interpretation of the "Generator Capability Curve" may be difficult. Other plant heating problems may dictate being more restrictive on MVAR loading (i.e. service water to the generator hydrogen coolers, stator water cooling, Alterer cooling). Performance of S32.3.A, Main Generator Inspection During Heavy Grid Load, and referencing the "Generator Capability Curve" will better define plant MEGAWATT and MEGAVAR output capability by monitoring all applicable data paints. EXAM BANK COMPUTER TEST Page: 57 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Raise hydrogen pressure to 65 psig: Incorrect due to raising hydrogen pressure to 65 psig will via the Generator Capacity Curve will be insufficient to maintain the MVARIMWE load on the Main Generator. Either real/true power or reactive power must be reduced or the Main

Generator will overheat and possibly fail during the Grid Emergency.

Reduce reactive load to 100 MVAR's: Incorrect due to personnel are expected to COMPL Y with PSD request for VAR generation OR immediately NOTIFY the PSD of inability to provide the requested VARs. Due to low voltage or grid concerns, maintaining LGS units on-line (producing MVARS) is essential because any load picked up by a startup source could cause grid voltage to drop further, thus increasing the probability of tripping the entire grid. By ensuring procedure compliance and minimizes the risk of inadvertently tripping a risk significant system that may cause a reduction in electrical generation and reactor power, which will increase the risk of a loss of oftsite power or station blackout. The PSD is the designated operating authority for the PECO transmission system. The PSD request may be to raise or lower WATTNAR production depending on grid conditions. VAR generation is important to the PSD in order to maintain grid stability. Therefore, the PSD may request that WATT production be lowered in order to raise VAR production. In this instance, the PSD will normally request a WATT reduction that can be performed by varying Recirc Pump flow only, followed by a request to reduce power further if necessary. Maintain current generator output due to Reduction Curtailment Action: Incorrect the generator cannot maintain stability without increasing generator cooling either by increasing hydrogen pressure or by reducing generator heat (MWE or MVARS) The PSD request may be to raise or lower WATTNAR production depending on grid conditions. VAR generation is important to the PSD in order to maintain grid stability. Therefore, the PSD may request that WATT production be lowered in order to raise VAR production. In this instance, the PSD will normally request a WATT reduction that can be performed by varying Recirc Pump flow only, followed by a request to reduce power further if necessary. EXAM BANK COMPUTER TEST Page: 58 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 19 Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 4.00 Grid disturbance causing voltage and frequency SRO 700000 General Data Technical Reference with E-5, Grid Emergency Revision Number: S32.3.A, Main Generator Inspection During Heavy Grid Cognitive Leve! PRA: (Le. Yes or No or #) 10CFR 55.43 (N/A for RO) 55.41 (b) Question History: (i.e. LGS NRC-05, OYS Question Source: (Le. New, I Bank, Revision History: History: (i.e. distracter "b" to plausible based on ILT Supplied Ref (If E-5 Attachment 2 page 1. appropriate): (Le. ABN-##) S32.3.A Excluded

Reference:

(Le. N/A Ensure ON-## not provided)

Low KA Justification (if N/A required):

KIA 700000 AA 1.01 RO 3.6 SRO 3.7 EXAM BANK COMPUTER TEST Page: 59 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8821 Points: 1.00 Unit 1 Conditions are a follows: T=O -Reactor Water Level is -130", down -Drywell pressure is 1.70 psig, up -Reactor Pressure is 670 psig. down WHICH ONE of the following identifies when ADS will initiate, and the Reactor Pressure at which the designated ECCS pump will inject into the RPV? ADS initiation ECCS Pump Injection Pressure A. 105 sec CS@455psig B. 105 sec RHR @ 250 psig C. 420 sec RH R @ 250 psig D. 420 sec CS @455psig Answer: B Answer Explanation: 105 sec; RHR @ 250 psig: Correct because the stated plant conditions indicate LOCA with all available ECCS pumps started and completion of the ADS actuation logic seal-in for Divisions I and III to start the ADS timers. The logic timer for blowdown is 105 seconds per the MCR-110-C4 Operator Actions. Of the choices given. the RHR pump design flow rate is established at about 250 psig with the Injection logic enabled with < 74 psid from pump discharge pressure to the RPV pressure.

Although the Core Spray injection logic is enabled at 455 psig. there will not be any flow until RPV pressure is reduced below the discharge pressure of the CS pump at about 330 psig. 105 sec; CS @ 455 psig: Incorrect due to RPV pressure above discharge pressure of CS pump. If an incorrect assumption of either the ADS timer or the selected ECCS pump discharge pressure required for injection is made the wrong selection will be made. 420 sec; RHR @ 250 psig: Incorrect due to wrong logic timer for ADS initiation. The 420 sec timer for LOCA outside of the Primary Containment is not required due to DW pressure condition stated> 1.68 psig. If an incorrect assumption of either the ADS timer or the selected ECCS pump discharge pressure required for injection is made the wrong selection will be made. j . EXAM BANK COMPUTER TEST Page: 60 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 420 sec; CS @ 455 psig: Incorrect due to wrong timer and too high an RPV pressure as stated above. If an incorrect assumption of either the ADS timer or the selected ECCS pump discharge pressure required for injection is made the wrong selection will be made. Question 20 Info Question Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: 3 3.00 System 8821 User-Defined ID: 8821 Cross Reference Number: LLOT0330.03 Reactor low level and effects as 2ressure drops Num Field 1: R03.8 Num Field 2: SRO 3.9 Text Field: 295031 EK2.02 Comments: General Data Technical Reference with ARC 110 C-4 Revision Number: ARC 113 F-3, E-3 Cognitive Level H PRA: (Le. Yes or No or #) Y 1 OCFR 55.43 (N/A for RO) 55.41 (b)7 Question History: (Le. LGS New NRC-05, OYS CERT-04) Question Source: (i.e. New, New Bank, Modified) Revision History: Revision N/A History: (Le. Modified distractor <lb" to make plausible based on OTPS , review) ILT Supplied Ref (If none appropriate): (i.*l. ABN-##) i Excluded

Reference:

(Le. if appropriate or NONE

Ensure ON-## not providedl Low KA Justification (if required):

i ! I J I EXAM BANK COMPUTER TEST Page: 61 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8846 Points: 1.00 Unit 2 plant conditions are as foflows: -Reactor power is 100%. -Control Room Emergency Fresh Air Supply (CREFAS) is in normal alignment with "A" CREFAS in "AUTO". A high radiation condition occurs at the outside air intake to the Main Control Room (MCR) Ventilation System WHICH ONE of the following describes the CREFAS fan response and expected MCR ventilation alignment? Ventilation alignment A. One fan Outside air and recirculated air B. Two fans Outside air and recirculated air C. One fan Recirculated air ONLY D. Two fans Recirculated air ONLY Answer: A Answer Explanation: One fan starts, Outside air and recirculated air: Correct because In the event of radiation isolation, the CREFAS fan in AUTO (A or B) will start immediately. If a radiation isolation Signal is generated by all four radiation detectors, then a complete isolation will occur, which results in the following: The main Control Room air is recirculated using the normal supply and return fans, while the CREFAS fan draws in some recirculation air as well as some outside air through the CREFAS filter, supplying the suction of the normal supply fan. Allowing some outside air into the CREFAS system ensures a positive pressure is maintained in the MCR which will protect MCR personnel from gaseous and particulate intrusion into the MCR. Two fans start, Outside air and recirculated air: Incorrect due to In the event of radiation isolation, the CREFAS fan in AUTO (A or B) will start immediately. EXAM BANK COMPUTER TEST Page: 62 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order One fan starts, Recirculated air ONLY: Incorrect due to In the event of radiation isolation, the CREFAS fan in AUTO (A or B) will start immediately Two fans start, Recirculated air ONLY, Incorrect due to In the event of radiation isolation, the CREFAS fan in AUTO (A or B) will start immediately. The design of the CREFAS system is to limit radiation exposure of MCR staff: Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8846 User-Defined 10: 8846 Cross Reference Number: LGSOPS0078.1L4 Topic: RO QUESTION 59 Num Field 1: 3.9 Num Field 2: 4.2 Text Field: 295033 EK1.02 Comments: General Data Technical with LGS UFSAR, CHAPTER Revision Number: 09,9.4-6 REV. 14 Cognitive Level H PRA: (i.e. Yes or No or #) NO 10CFR 55.43 (NJA for RO) 55.41 (b) 8 Question History: (i.e. LGS Bank NRC-OS, OYS CERT-04) Question Source: (I.e. New, Modified 560493 Bank, Modified) Revision History: Revision Modified answer and History: (i.e. Modified distractors to include distractor "b" to make reason for MCR plausible based on OTPS ventilation alignment to review) more closely align question with KIA. Edited question stem for clarity. Changed order of distractors. Changed correct answer from B to A. ILT Suppl1ed Ref (If NONE appropriate): (i.e. ABN-##) I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Excluded

Reference:

(Le. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 64 of 206 12 October 2010 EXAMINATION ANSWER RO questions in sample plan order 10: 8847 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is HPCI System Full Flow Functional Test in progress per The following Annunciators are received: 117 HPCI, HPCI Steam Line Hi Flow -002 VENT, Reac Encl St Fldg Dmpr Pnl10C234 Trouble -107 REACTOR, Div 2 Steam Leak Det Sys Hi Temp -107 REACTOR, 1-5, Div 4 Steam Leak Det Sys Hi Temp -004 VENT, A-3, B Reac Encl HVAC Pnl1BC208 Trouble -ODS FIRE, F-2-U, Reac 1 EI. 177 HPCI Pump Attempts to isolate HPCI Steam Supply valves HV-55-1 F002 and HV-55-1 F003 fail Security reports "a steam plume" is visible above the Diesel Generators WHICH ONE of the following identifies the condition of HPCI Pump Room Ventilation and the status of secondary containment integrity?

HPCI PUMP ROOM SEC. CONT.INTEGRITY A. Maintained B. NOT Maintained C. Lined up to Maintained D. Lined up to NOT Maintained Answer: B Answer Explanation: Isolated; NOT Maintained: Correct because plant conditions statement and Annunciators indicate a HPCI steam line break that should have isolated HPCI. The Annunciator for Reac Ene! St Fldg Dmpr Pnl actuation with Security report of steam visible above the Diesel Generator indicates that the HPCI room floor panel has lifted to pressurize the safeguard piping room that relieves to the outside above the diesels. The for Steam Flooding Damper Panel actuation directs entry into T-103 for Secondary Containment Control and directs communication to Health Physics to assess offsite dose consequences. The S7S.0.A is also referenced for evaluating the Secondary Containment Steam Flooding Damper actuation. EXAM BANK COMPUTER TEST Page: 65 of 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Isolated; Maintained: Incorrect due to indications Secondary Containment Blowout Panel actuation Steam Flooding Damper actuation to isolate the Pump Room. (Partially correct for HPCI Pump Room Lined up to RERS; Maintained: Incorrect due Isolation from Secondary Containment with Flooding Damper actuation and indication of outside of Secondary Containment indicating that Containment Integrity is NOT Maintained. Lined up to RERS; NOT Maintained: Incorrect due reason stated above. (Partially correct for Containment Integrity NOT I Question 22 Info Question Type: Multiple Choice i Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 3.00 System ID: User-Defined ID: Cross Reference Number: Topic: HPCI Num Field 1: Num Field 2: Text Field: 295035 General Data Technical Reference with ARC-MCR-117-C1 Revision Number: ARC-MCR-107-GS ARC-MRC-107-IS ARC-MCR-002-F5 ARC-MCR-004-A3 ON-111, BASES 1-103, BASES Cognitive Level H PRA: (Le. Yes or No or NO 10CFR 55.43 (N/A for 5S.41 (b) 7 Question History: (Le. LGS Bank, NRC-05, OYS CERT-04) Question Source: (Le. New, Bank, Bank, Modified) I EXAM BANK COMPUTER TEST Page: 66 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order II Revision History: Revision History: (Le. Modified . distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (i.e. ABN-##) Excluded

Reference:

(Le. Ensure ON-## not provided)

Low KA Justification (if required): Bank, LIMERICK LOT 0603. Modified answer and distractors to include reason for blowout panel operation to more closely align Question with KIA. Edited question stem for clarity. Changed order of distractors. Changed correct answer from D to B. Still catagorized a bank NONE NONE N/A EXAM BANK COMPUTER TEST Page: 67 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 5920 Points: 1.00 Unit 2 plant conditions are as follows: -100% power -Both reactor recirculation pumps are running at 80% speed The "2B" Reactor Feedwater Pump trips, and RPV level lowers to +25 inches. WHICH ONE of the following describes the plant response, and the reason for this response? Recirc Pump Reason for Response Pumps Runback to 28% Speed Reduces power to restore level by reducing steam load Pumps Runback to 42% Speed Reduces power to restore level by reducing steam load Pumps run back to 28% Speed Reduces power to ensure adequate NPSH to Recirc Pumps Pumps runback to 42% Speed Reduces power to ensure adequate NPSH to Recirc Pumps Answer: B Answer Explanation: Pumps Runback to 42% Speed; Reduces power to restore level by reducing steam load: Correct because S43.0.B NOTE block in section 4.2 Resetting High Limit Runback states the conditions for High Limit Runback as any reactor feed pump flow less than 18.8% and RPV water level less than 27.5 inches. These conditions are established in the plant conditions statement. The basis for the runback is anticipation of inadequate feed pump injection to maintain adequate core cooling. The reason for the response is to reduce power by reducing recirculation flow which will reduce the steam demand to within capacity of remaining feedwater injection and to allow the mechanism of swell to restore RPV level to the nominal control band. Pumps Runback to 28% Speed; Reduces power to restore level by reducing steam load: Incorrect due to conditions not met for Low Limit Runback per S43.0.B NOTE block in section 4.3. (Partially correct for Reason for the Response although the Recirc Pump Response is incorrect for plant conditions given) EXAM BANK COMPUTER TEST Page: 68 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR Pumps runback to 28% Speed; Reduces power to ensure adequate NPSH to Recirc Pumps: Incorrect due to stating Low Level Runback and wrong reason for the power reduction. Although ensuring adequate NPSH is correct for Low Level Runback, this is not correct for the conditions stated. DISTRACTOR Pumps runback to 42% Speed; Reduces power to ensure adequate NPSH to Recirc Pumps: Incorrect due to wrong reason for the Runback response as stated above. (Partially correct for Recirc Pump Response to High Level Runback) EXAM BANK COMPUTER TEST Page: 69 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 3.00 System ID: 5920 User-Defined ID: 5920 Cross Reference Number: LLOT0040.04 100% power Both reactor recirculation pumps are running Topic: at 80% speed The "2B" Reactor Feedwater Pu Num Field 1: 3.2 Num Field 2: 3.3 Text Field: 295009 AK3.01 Comments: General Data Technical Reference with I Revisio Revision Number: n #: Cqgnitive Level L Justification for Non SRO 55.41 (b) 5 CFR Link: Question History: (Le. LGS ILT NRC Exam 2005 NRC-05, OYS CERT-04) Question Source: (i.e. New, Bank Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision N/A History: (Le. Modified distractor "bit to make plausible based on OTPS review) ILT Supplied Ref (If None appropriate): (Le. ABN-##) Excluded

Reference:

(i.e. None Ensure ON-## not provided)

Question 23 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 70 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8848 Points: 1.00 Unit 1 was operating at 100% power when an earthquake occurred resulting in Primary Systems discharging into the Reactor Enclosure. The following annunciators are in alarm: -109 RAD, 8-4, Reactor Encl Area Hi Radiation -003 RAD, C-1, Radwaste Encl Exh Rad Mon Hi-Hi Iinop -003 RAD, A-1, Radwaste Equip Room Vent Exh Rad Mon Hi-Hi !Inop -127 OFF GAS 1, H-4, Reactor Enc Floor Drain Sump Pump HI-HI Water Level T-103, Secondary Containment Control, is being executed to mitigate abnormally high secondary containment temperatures and radiation levels. WHICH ONE of the following list of actions is correct per T-236, TRANSFERRING REACTOR ENCLOSURE FLOOR DRAIN SUMP TO SUPPRESSION POOL VIA CORE SPRAY SYSTEM, to minimize offsite release from the Radwaste Enclosure HVAC System? Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'NORMAL' to enable Sump Pump high radiation trip. Closely monitor North Stack Release Rate. Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'HI-HI RAD' to defeat Sump Pump high radiation trip. Closely monitor North Stack Release Rate. Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'NORMAL' to enable Sump Pump high radiation trip. Transfer Reactor Enclosure Floor Drain Sump to Suppression Pool. Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'HI-HI RAD' to defeat Sump Pump high radiation trip. Transfer Reactor Enclosure Floor Drain Sump to Suppression Pool. Answer: D Answer Explanation: EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'HI-HI RAD' to defeat Sump Pump high radiation trip. Transfer Reactor Enclosure Floor Drain Sump to Suppression Pool: Correct because plant conditions indicate Secondary Containment control per T-103 due to high Radiation conditions steam release, Step SCC/RAD-8 states to Consider pumping RE sump to Supp Pool per T-236, The purpose of this procedure is Transfer Reactor Enclosure Floor Drain Sump to Suppression Pool via Core Spray system to minimize offsite release from the radwaste Enclosure HV AC system, Procedure step 4.2 and preceding note directs Positioning the Rx Encl Floor Drain Sump Pumps Selector Switch to "HI-HI RAD" in order to accomplish this procedure, Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'NORMAL' to enable Sump Pump high radiation trip. Closely monitor North Stack Release Rate: Incorrect due to improper operation of Floor Drain Sump Pumps Selector Switch to allow transfer to Suppression Pool per T-103, An incorrect assumption of what occurs when the switch is placed in the Normal position may lead to selecting the wrong position for the stated conditions, Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'HI-HI RAD' to defeat Sump Pump high radiation trip. Closely monitor North Stack Release Rate: Incorrect due to lack of action to transfer Floor Drain Sump to Suppression Pool to minimize release, Radwaste Enclosure discharges to the South Stack therefore monitoring the North Stack would be performed if the assumption were made that Radwaste Enclosure discharges to the North Stack, Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'NORMAL' to enable Sump Pump high radiation trip. Transfer Reactor Enclosure Floor Drain Sump to Suppression Pool: Incorrect due to improper operation of Floor Drain Sump Pumps Selector Switch to allow transfer to Suppression Pool per T-103, This position will not allow transfer of Floor Drains to Suppression Pool per T-236 due to Post-LOCA Radiation Monitor Interlock trip, EXAM BANK COMPUTER TEST Page: 72 of 13 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 24 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active Yes No 1.00 4 4.00 8848 8848 LGSOPS1560.IL5, LGSOPS1561.1L 1 T-103 High Rad in Reactor Enclosure 2.8 3.0 295036 EA 1.03 General Data Technical Reference with T-103 basis Rev Revision Number: T-236, Rev 14 Cognitive Level H PRA: (i.e. Yes or No or #) NO 10CFR 55.43 (!\ItA for RO) 55.41 (b) 7 Question History: (i.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (I.e. New, NEW Bank, Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. NONE Ensure ON-## not provided)

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 73 of 206 13 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8849 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor shutdown -Loss of Coolant Accident -T-1 02 in progress -Drywell Pressure (Red Pen) indicates 18 PSIG on PR57-101 -Suppression Pool Pressure (Blue Pen) is 51 PSIG ON PR 57-101 CURVE PC.lP-1 Pi'll emiT PRESS LIMIT 100 El2.0 p8rl; 10 &0 50 palg 5Q o 40 +-+-+-+-+-+-+:-+-+-+-+-t--f!II Q 30 20 to +-+-+-+-+-+-+-+-+--1-+-+-II1II PRI I:DIIfT WATER LEVEL 1FT) CONTAINMENT LEVEL IN FEET ___ PSrG SUPP POOL PRESS ON PR!H-ilQl lBLUE PEN) MINUS H ___ PSI{) PRI CONT PRESS ON PR5T-ilOl (RED PEN) EQUALS (=1 --=-=-_ A PSIG TIMES co 2.3 FT/PSIG EOUALS (=1 ---FT PLUS (+) 26,8 Fl" EQUALS (=) ---FT COtHAINMENT LEVEL WHICH ONE of the following describes the Primary Containment Water Level? A. 75.9 feet B. 102.7 feet C. 117.3 feet D. 144.1 feet Answer: B Answer Explanation: 102.7 feet, Correct (51 -18 = 33) 33 x 2.3 + 26.8 =102.7 feet EXAM BANK COMPUTER TEST Page: 74 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR 144.1 feet, 51 x 2.3 + 26.8 = 144.1feet DISTRACTOR 75.9 feet, 33 x 2.3 = 75.9 feet I DISTRACTOR 117.3 feet, 51 x 2.3 = 117.3 feet PRIMARY CONTAINMENT PRESSURE LIMIT "A" (PCPL-A) CURVE PCPL-A is defined as the lesser of either: The pressure capability of the Primary Containment The maximum Primary Containment pressure at which vent valves sized to reject all decay heat from the Primary Containment can be opened and closed The maximum Primary Containment pressure at which SRVs can be opened and will remain open The maximum Primary Containment pressure at which RPV vent valves sized to reject all decay heat from the Primary Containment can be opened and closed 60 psig is the maximum drywell pressure where ADS valves will function using pneumatic pressure from the PCIG System at 85 psig. The curve allows SuppreSSion Pool pressure to be higher at a rate of 1 psig per 2.3 feet once the Suppression Pool pressure instrument tap is covered at a Primary Containment water level of 50 feet. The allowed pressure stops riSing at a Primary Containment water level of 101 feet because the ADS SRV solenoids are covered with water. A constant pressure limit above 101 feet ensures the total pressure against the ADS SRV diaphragms remains constant. Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 5 . Difficul!y: 3.00 System ID: 8849 User-Defined 10: 8849 i Cross Reference Number: LGSOPS1560.IL4 ! . Topic: PC/P curve determination Num Field 1: 3.4 Num Field 2: 3.5 Text Field: 295029 EA2.03 Comments: General Data Technical Reference with T-102 Rev 23 Revision Number: CO-.9nitive Level H PRA: {Le. Yes or No or #) NO : 1 OCFR 55.43 (N/A for RO) 55.41 (b) 10 Question History: (Le. LGS NEW NRC-OS, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified) EXAM BANK COMPUTER TEST Page: 75 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order , Revision History: Revision History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. Ensure ON-## not provided)

Low KA Justification (if required):

NEW T-102 Rev 23, Curve PC/P-1 NONE N/A EXAM BANK COMPUTER TEST Page: 76 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 26 10: 8850 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor STARTUP in progress -Reactor power is 19% Control Rod 02-19 has drifted to position 48, when Control Rod 58-23 begins to drift out WHICH ONE of the following describes the required operator action? ISOLATE the effected Control Rod Drive Mechanisms from their HCUs. Apply a continuous Control Rod insert signals to both Control Rods until fully inserted. Direct single rod scrams by placing both "NORM-TEST-SRI" toggle switches at the HCUs to "TEST' for BOTH CONTROL RODS. Manually SCRAM the reactor and place the Mode Switch in "SHUTDOWN".

Answer: D Answer Explanation: Manually SCRAM the reactor and place the Mode Switch in "SHUTDOWN": Correct because indications are that both rods are drifting out above 10% power requiring manual reactor scram because multiple drifting rods could be indicative of .9 generic issue resulting in inadvertent positive reactivity initiation. Apply a continuous control rod insert signals to both control rods until fully inserted: Incorrect due to while the basis for this action in ON-104 is correct; however, answer is incorrect because manual scram is required with multiple drifting rods. Direct single rod scrams by placing both TEST -SRI" toggle switches at the HCUs to "TEST" for BOTH CONTROL RODS: Incorrect due to While applying scram signals to the rods may free the CRD collet fingers, and the basis for this action in ON-104 is correct; however, answer is incorrect because manual scram is required with multiple drifting rods. EXAM BANK COMPUTER TEST Page: 77 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ISOLATE the effected Control Rod Drive Mechanisms from their HCUs: Incorrect due to while isolation of the CRDs from their HCUs will either terminate the drifting or verify that the drifting is being caused by stuck CRD collets, amd the basis for this action in ON-104 is correct; however, answer is incorrect because manual scram is required with multiple drifting rods. Question 26 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No ! 1.00 Time to Complete: !3 3.00 System 8850 User-Defined ID: 8850 Cross Reference Number: LGSOPS1550.IL 1 AND IL2 ! Inadvertent Reactivity Addition Num Field 1: !4.4 Num Field 2: 4.7 Text Field: 295014 2.1.7 Comments: General Data Technical Reference with ! ON-104, Bases, Rev 53a Revision Number: Cognitive Level L PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 10 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 78 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8851 Points: 1.00 LGS TRIP procedure Primary Containment Control, directs actions to rapidly shutdown the reactor when drywell temperature cannot be maintained below 340"F. WHICH ONE of the following describes the reason a rapid shutdown of the reactor is required? To maintain operability of ADS solenoid valves. Because the reactor must be shutdown to initiate Drywell Spray. Because Drywell temperature adversely affects reactor level indication. To maintain Suppression Pool temperature below ECCS suction temperature limits. Answer: A Answer Explanation: To maintain operability of ADS solenoid valves:: Correct because T -102 Bases for Step DW IT-11 states that when drywell temperature cannot otherwise be maintained below 340 degrees (Le., the maximum temperature at which ADS is qualified and drywell design temperature), further release of energy from the RPV to the drywell will be directed in the drywell temperature (DWIT) control flowpath to terminate, or reduce as much as possible, any continued rise in drywell temperature by rapidly depressurizing the RPV. Because the reactor must be shutdown to initiate drywell spray: Incorrect due to step DWIT-8 requirement for evaluating DW IT-3 and spraying the drywell if Supp Pool level is below 38.7 feet prior to DW temp reaching 340 degrees. If DW temperature exceeds 340 deg T-102 directs the reactor be shutdown, DWIT-10, due to the requirements of T-225, Startup And Operation Of Suppression Pool And Drywell Spray Operation. The Recirculation Pumps and Drywell fans must be secured. These actions are appropriate to prevent damage to the recirculation pumps and drywell cooling fans, because they are not designed to be operated in a spray environment. EXAM BANK COMPUTER TEST Page: 79 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Because drywell temperature adversely affects reactor level indication: Incorrect due to no link between T-102 expected level effects evaluated per T-291 and DWIT-1 RPV level validation curve and Shutdown req uirement. T -102 CAUTION warns operators of the possible effects of elevated drywell temperatures on RPV level instrument indications. This CAUTION, along with Step DW IT-1, define the conditions under which RPV level indications must be considered invalid due to the effects of RPV pressure, primary containment temperatures, and/or Reactor Enclosure temperatures. RPV level instruments are calibrated to provide accurate indication under expected operating conditions. Indicated RPV level will be inaccurate if primary containment temperature, Reactor Enclosure temperature, or RPV pressure vary from the calibrated conditions of the associated instrument. To maintain Suppression Pool temperature below ECCS suction temperature limits: Incorrect, Plausible because T-102 CAUTION reminds operators to remain aware of the net positive suction head (NPSH) and vortex limits for Residual Heat Removal (RHR) pumps when they are taking a suction on the suppression pool. NPSH and vortex limits are addressed within this CAUTION for the following reasons: It is difficult to define in advance exactly when the limits should be observed and when pumps should be operated irrespective of the limits. Pumps to which the limits apply are used in more than one flowpath. For example, RHR pumps are used in flowpaths in both T -101, RPV Control, and T-102, Primary Containment Control. Authorizing operation of the pumps "regardless of NPSH and vortex limits .. in one flowpath may conflict with instructions in another flowpath where flow would normally be controlled below the limits. Pump characteristics, and the shape of NPSH and vortex limit curves, vary widely. If a limit is relatively flat, throttling pump flow will be of little benefit; operators can only choose whether or not to operate the pump. Immediate and catastrophic failure is not expected if a pump is operated beyond its respective NPSH or vortex limit. NPSH limits are defined to be the highest suppression pool temperature values which provide adequate NPSH for the pumps which take a suction on the suppression pool. The NPSH limits are functions of pump flow and suppression pool over pressure (airspace pressure plus the hydrostatic head of water over the pump suction), and are utilized to preclude pump damage from I cavitation. EXAM BANK COMPUTER TEST Page: 80 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 27 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8851 8851 I LGSOPS1560.lL5 ! T-102 requirements for 340 deg in drywell 3.1 3.2 295012 AK1.02 General Technical Reference with T-102 bases, Rev Revision Cognitive Level

PRA: (Le. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41Jb) 8 Question History: (Le. LGS NEW NRC-05. OYS CERT-04) Question Source: (Le. New. NEW Bank. Modified)

Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If none appropriate): (Le. ABN-##) I Excluded

Reference:

(Le. T-102 bases Ensure ON-## not provided)

I Low KA Justification (if N/A required): I EXAM BANK COMPUTER TEST Page: 81 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8803 Points: 1.00 Unit 1 plant conditions are as follows: -100% power -ANN 114 ISOL D-2, "Main Steam Line Hi Flow" is received -"1 D" Main Steam Line (MSL), "A" and "D" Flow Transmiters Trip Upscale WHICH ONE of the following describes the expected status of MSIVs 30 seconds later? Inboard MSIVs Outboard MSIVs A. Open B. Closed C. Open D. Closed Answer: D Answer Explanation: Inboard closed and Outboard closed: Correct because High Main Steam Line flow is detected by differential pressure transmitters (4/steamline) that will activate at 140% steam line flow (122.1 psid) and input to NSSSS. If any steam line A OR C AND B OR D channels occur concurrently THEN Group 1A isolation will occur. This will isolate ALL Inboard and Outboard steam line MSIVs. NOTE: this logic arrangement is unique to MSIVs, other NSSSS logic arrangements consist of one logic system for all inboard isolation valves, one for all outboard isolation valves. Inboard closed and Outboard open: Incorrect due to Group I isolation logic satisfied (A or C) and (8 or Q) to complete the isolation for both Inboard and Outboard MSIVs Inboard open and Outboard closed: Incorrect due to same isolation logic used to control isolation of all (4) steam lines. No logic failures would cause isolation of a single MSIV. If any steam line A OR C AND B OR D channels occur concurrently THEN Group 1 A isolation will occur. This will isolate ALL Inboard and Outboard steam line MSIVs. EXAM BANK COMPUTER TEST Page: 82 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Inboard open and Outboard open: Incorrect due to same transmitters used to control logic contacts in both the Inboard and Outboard logic trains. If any steam line A OR C ANO B OR D channels occur concurrently THEN Group 1A isolation will occur. This will isolate ALL Inboard and Outboard steam line MSIVs. i i Question 28 Info *Question Type: Choice rstatus: Active I *Always select on No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 .Sy:stem 10: 8803 I User-Defined 10: 8803 Cross Reference Number: LLOT0180.6G Topic: NS4 MSL Num Field 1: Num Field 2: Text Field: 223002 i General Data I Technical Reference with GP-8.1, Rev. . Revision Number: ARC 114 D-2 i C()gnitive Level L IPRA: O.e. Yes or No or #) NO i 10CFR 55.43 (N/A for RO) 55.41 (b) 3 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make II plausible based on OTPS review) i ILT r-..--.... Supplied Ref NONE I i appropriate): (Le. ABN-##) Excluded

Reference:

(i.e. NONE Ensure ON-## n()t provided)

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 83 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8804 Points: 1.00 Unit 2 plant conditions are as follows: -Reactor power is 100% -The D-24 Emergency Diesel Generator (EDG) Fuel Oil Transfer Pump is inoperable undergoing mechanical repair -All Unit 2 EDG Fuel Oil Day Tanks have been verified filled to capacity (:<: 103.5 inches Day Tank level) A grid disturbance results in a complete loss of offsite power (LOOP) to both units -All four Unit 2 EDGs have automatically started -The D-24 EDG has been loaded to 1850 KW and load is stable WHICH ONE of the following describes the approximate time the D-24 EDG can be operated WITHOUT additional operator action? A. UP t01 hour. B. UP to 7 days. C. MORE than 3 hours0.125 days 0.0179 weeks 0.00411 months D. MORE than 7 days. Answer: C Answer Explanation: MORE than 3 hours0.125 days 0.0179 weeks 0.00411 months : Correct because the EDG fuel oil day tanks were verified as being filled to capacity prior to the LOOP, which provides enough fuel for a minimum of 3;;2 hours0.0833 days 0.0119 weeks 0.00274 months of continuous EDG operation at full load with an inoperable Fuel Oil Transfer Pump. UP to1 hour: Incorrect due to the EDG day tank Tech. Spec. minimum level is 200 gallons, which provides enough fuel oil for one hour of continuous operation. The answer is incorrect because the EDG fuel oil day tanks were verified as being filled to capacity prior to the LOOP, providing enough fuel oil for 3;;2 hours0.0833 days 0.0119 weeks 0.00274 months of continuous operation AT RATED LOAD. UP to 7 days: Incorrect due to the EDG Fuel Oil Storage tanks provide enough fuel oil for 7 days of continuous operation AT RATED LOAD (2850 KW). The answer is incorrect because the D-24 EDG Fuel Oil Transfer Pump is unavailable, preventing the addition of fuel oil to the Day Tank from the Fuel Oil Storage tank. The answer is also incorrect because the D-24 EDG is being operated at less . than rated load (1850 KW). i EXAM BANK COMPUTER TEST Page: 84 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order MORE than 7 days: Incorrect due to the EOG Fuel Oil Storage tanks provide enough fuel oil for 7 days of continuous operation AT RATED LOAD (2850 KW). Because the 0-24 EDG is being operated at less than rated load (1850 KW). the 0-24 EDG could be operated for MORE than seven days if the EOG Fuel Oil Transfer Pump were available; however. the answer is incorrect because the D-24 EDG Fuel Oil Transfer Pump is unavailable. Question 29 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 *Time to Complete: 3 Difficulty: 3.00 System 10: 8804 User-Defined 10: 8804 Cross Reference Number: LGSOPS009292B.3A OG operation, fuel oil supply Num Field 1: 3.2 Num Field 2: 3.3 Text Field: 264000 K1.05 Comments: General Data Technical Reference with P&IO M-20, sheet 9 Revision Number: Tech. Specs. 3.8.1.1 LGS UFSAR Chapter 9, pages 9.5-28 and 9.5-32 Cognitive Level L PRA: (Le. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b)8 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified) Revision History: Revision NEW History: (i.e. Modified . distractor "b" to make I plausible based on OTPS . review) i ILT Supplied Ref (If appropriate): (Le. Excluded

Reference:

(Le. Ensure ON-## not Low KA Justification (if

! i EXAM BANK COMPUTER TEST Page: 85 of 12 October 2010 i I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order EXAM BANK COMPUTER TEST--Page: 86 of EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8802 Points: 1.00 Unit 1 plant conditions are as follows: -OPCON 3 -RPV pressure is 40 pslg -D114 Safeguard Load Center has been removed from service for repair RPV level rapidly drops to -130 inches WHICH ONE of the following describes the automatic response of the RHR LPCIIN,IECTION valves? HV-51-F017A, 178, 17C, and 17D will OPEN. HV-51-F0178, 17C, and 17D will OPEN. HV-51-F017A remains CLOSED. HV-51-F017A, 17B, and 17D will OPEN. HV-51-F017C remains CLOSED. HV-51-F017B and HV-51-F017D will OPEN. HV-51-F017A and HV-51-F017C remain CLOSED. Answer: B Answer Explanation: HV-S1-F017B, 17C, and 17D will OPEN. HV-51*F017 A remains CLOSED: All four LPCI IN..IECTION valves I receive a Signal to open; however, HV-51-F017A will remain closed because it is powered from MCC D114-R-C, which is removed from service. HV-51-F017A, 17B, 17C, and 17D will OPEN: All four ! LPCI INJECTION valves receive a Signal to open; however, answer is incorrect because HV-51-F017A is powered from MCC D114-R-C, which is removed from service; therefore, HV-51-F017A will remain closed. HV-S1-F017A, 17B, and 17D will OPEN. HV-51-F017C remains CLOSED: HV-51-F017A is powered from MCC D114-R-C, which is removed from service; therefore, 51-F017A will remain closed. Also incorrect because 51-F017C receives a Signal to open and has power available to open. HV-51-F017B and HV-51-F017D will OPEN. F017A and HV-51-F017C remain CLOSED: HV-51-F017A will remain closed because it is powered from MCC R-C, which is removed from service; however, answer is incorrect because HV-51-F017C receives a signal to open and has power available to open. i EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 30 Info Question Type: i Always select on Authorized for Time to System User-Defined Cross Reference Topic: . Num Field 1: Num Field 2: Text Field: Comments: Multiple Choice Active No No 1.00 3 ! ! 8802 8802 RHR LPCI injection permissive 2.5 2.7 203000 K2.02 General Data Technical Reference with LGS Electrical Drawings: Revision Number: E-2B, E-58 sheet 1 and 4. General Electric Drawings: E11-1030 F001, F002 LGSOPS0051.1 L 16a Cognitive Level H PRA: (i.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b)7

Question History: (Le. NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified)

Revision History: Revision N/A History: (Le. Modified distractor "b" to make plausible based on OTPS review) I Supplied Ref (If ILT NONE I , appropriate): (i.e. ABN-##) I Excluded

Reference:

(i.e. NONE i Ensure ON-## not provided)

I Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 88 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8806 Points: 1.00 Unit 1 plant conditions are as follows: -RPV level lowers rapidly resulting in a LOCA signal. -M..u :r P.J..5. -The D134 Load Center Breaker trips tv--tL (. 0 t.J 1>' WHICH ONE of the following describes the expected status of the Instrument Air Compressors after shunt trips have been reset per SE-10-1, BREAKER RESETS FOLLOWING A LOCA? A. 1A 18 Compressors running. 8. 1A 18 Compressors NOT running. C. 1A Compressor running. 18 Compressor NOT running D. 1A Compressor NOT running. 18 Compressor running. Answer: D Answer Explanation: 1A Compressor NOT running. 1B Compressor running: The 1A and 18 Instrument Air Compressors are both SHUNT tripped on a LOCA signal. The 1A Instrument Air Compressor is powered from D134-R-H and will not restart. The LOCA SHUNT trips are reset not less than 10 minutes following the LOCA signal, restoring the 1 B Instrument Air Compressor to service. 1A and 1B Compressors running: The 1A and 1B Instrument Air Compressors are both SHUNT tripped on a LOCA signal. Normally, the LOCA SHUNT trips are reset not less than 10 minutes following the LOCA signal, restoring both Instrument Air Compressors to service; however, the answer is incorrect because the 1A Instrument Air Compressor is powered from D134-R-H and will not be running. 1A and 1 B Compressors NOT running: The 1 A and 1 B Instrument Air Compressors are both SHUNT tripped on a LOCA signal. The 1A Instrument Air Compressor is powered from D134-R-H and will not restart; however. the answer is incorrect because the LOCA SHUNT trips are reset not less than 10 minutes following the LOCA signal, restoring the 1 B Instrument Air Compressor to service. EXAM BANK COMPUTER TEST Page: 89 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR 1A Compressor running. 1 B Compressor NOT running: The 1 A and 1 B Instrument Air Compressors are both SHUNT tripped on a LOCA signal. The 1A Instrument Air Compressor is powered from D134-R-H and will not restart. The answer is also incorrect because the LOCA SHUNT trips are reset not less than 10 minutes following the LOCA signal, restoring the 1 B Instrument Air Compressor to service. Question 31 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 4.00 System 10: 8806 User-Defined 10: 8806 Cross Reference Number: Topic: Air Compressor start requirements

Num Field 1: 2.8 Num Field 2: 2.8 Text Field: 300000 K2.01 Comments:

General Data Technical Reference with SE-10-1, Rev. 44, Page 1 Revision Number: LGSOPS0015.1 L 16A Cqgnitive Level H PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (i.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS . review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##)

Excluded

Reference:

(I.e. NONE Ensure ON-## not provided)

Low KA Justification (if N/A I EXAM BANK COMPUTER TEST Page: 90 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8807 Points: 1.00 Unit 1 plant conditions are as follows: -The Reactor was shutdown 8 hours0.333 days 0.0476 weeks 0.011 months ago to support refueling outage, following 2 years of -OPCON -RPV level is + 86 inches on Upset -Reactor pressure is 40 -"1 B" RHR is in Shutdown Cooling Reactor level drops to + 0 inches WHICH ONE of the following describes the affect on reactor pressure WITHOUT operator action? Reactor pressure will remain at 40 psig INDEFINITELY. Reactor pressure will NOT immediately rise; however, pressure WILL eventually rise as reactor coolant temperature continues to rise. Reactor pressure will begin rising IMMEDIATELY, however pressure will stabilize as natural circulation develops. Reactor pressure will begin rising IMMEDIATELY, and continuously as reactor coolant temperature rises. Answer: D Answer Explanation: Reactor pressure will begin rising IMMEOIATEL Y and continuously as reactor coolant temperature rises: Correct with the plant is in OPCON 3; at 40 psig (54 psia) therefore, bulk reactor coolant temperature is @268 deg. At 268 deg and 40 pSig, reactor pressure will rise immediately on a loss of Shutdown Cooling, and pressure will rise continuously until saturation and then reactor temperature will rise without operator action to establish core circulation. Reactor pressure will remain at 40 psig INOEFINITEL Y: The answer is incorrect because with the plant in OPCON 3 after a 2 year run the decay heat buildup will cause, bulk reactor coolant temperature starting at @ 268 deg; therefore, rector pressure cannot remain at 40 psig with bulk reactor coolant temperature> 212°F; reactor pressure WILL begin to rise on a loss of Shutdown Cooling. This choice is plausible if misunderstood that 40 psig reactor pressure and reactor has been in operation for 2 years with 6-7% decay heat. Reactor pressure will NOT immediately rise, however, pressure WILL eventually rise as reactor coolant temperature continues to rise: Incorrect because the plant is in OPCON 3: therefore, bulk reactor coolant temperature is >200°F. At 40 pSig, reactor pressure will rise immediately on a loss of Shutdown Cooling. This choice is plausible if misunderstood that 40 psig reactor pressure equates to > 212 deg I EXAMINATION ANSWER I L T09-'1 RO questions in sample plan order Reactor pressure will begin rising IMMEDIATELY; however, pressure will stabilize as natural circulation develops: Incorrect because reactor level must be greater than 60" on Shutdown Range or greater than 78" on Upset Range to establish natural circulation. Also, at 40 psig, reactor pressure will begin to rise with bulk reactor coolant temperature reaches >212°F. Also, when reactor level is below those levels, the moisture separator drains are uncovered and the water inside the shroud is not coupled with the water outside the shroud preventing natural circulation. Question 32 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: 3 3.00 System 8807 User-Defined ID: 8807 Cross Reference Number: Reactor shutdown with decay heat Num Field 1: 3.3 Num Field 2: 3.3 Text Field: 205000 K3.01 Comments: General Data Technical Reference with GP-6.2, Rev. 42, Page 2 Revision Number: Technical. Specifications. Table 1.2, Operational Conditions LGSOPS0051 Rev001_2, pages 24 and 25 I Cognitive Level H PRA: JLe. Yes or No or #} NO 1 OCFR 55.43 (N/A for RO) 55.41 (b) 5 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified) Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on i review) ILT Supplied Ref (If Steam Tables appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE Ensure ON-## not I

BANK COMPUTER TEST Page: 92 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order EXAM BANK COMPUTER TEST Page: 93 of 206 12 October EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8808 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is -Power ascension is in -Normal electrical The RO has selected Control Rod 30-31 and is preparing to withdraw the Control Rod A loss of power to 1AY185, "1A APRM UPS Inverter" occurred WHICH ONE of the following identifies the APRM indic:ations, and RPS I Control Rod Block actuations, due to the failed power supply? RPS I Rod Block APRM indications A. Half Failed downscale

8. Control Rod Block Indicate actual power C. Half Indicate actual power D. Control Rod Block Failed downscale Answer: C Answer Explanation: Half scram; Indicate actual power -This is the correct answer because loss of 1 AY185 power supply will cause a loss of LVPS input to the APRMs. Although the LVPS is auctioneered with the 1 BY185 input to the LPRM and APRM chassis, it will deenergize the 2/4 Logic Modules for RPS A 1 and A2 logic inputs resulting in an 'A' side half scram. The APRMs continue to indicate normally due to the auctioneered LVPS inputs to the chassis.

Half scram; Failed downscale -This is partially correct due to identifying a Half scram but an incorrect answer because the APRM and LPRM chassis have auctioneered LVPS inputs for maintaining indication. Control Rod Block; Indicate actual power This is partially correct due to identifying that APRMs will indicate actual power but an incorrect answer because loss of 1 A Y185 power supply does not affect any Rod Blocks per S73.0.8. EXAM BANK COMPUTER TEST Page: 94 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Control Rod Block; Failed downscale -This is an incorrect answer because loss of 1AY185 power supply will not affect any rod blocks per S73.o.B and due to the auctioneered LVPS input from 1BY185 power supply all APRM and LPRM chassis as well as RBM chassis "A" and "B"w Question 33 Info Question Type: Choice Status: Active select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8808 User-Defined 10: 8808 Cross Reference Number: iTopic: RPS response on APRM Failure Num Field 1: 4.0 Num Field 2: 4.0 Text Field: 215005 K3.01 Comments: Question Info Question Type: Multiple Choice Status: Inactive I Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System 10: 8808 User-Defined 10: 8808 Cross Reference NEW Number: Num Field 1: Num Field 2: Text Comments: General TIS 3.3.1 Reference with Revision Number: , I I I J I I I I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Justification for Non SRO CFR Link: Cognitive Level Question History: (Le. LGS 05, OYS 04) Question Source: (Le. New, Bank, Modified) LowKA Justification (if reguired): Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) I".T Supplied Ref (If appropriate): (i.e. i ABN-##) Excluded

Reference:

(i.e. Ensure ON-## not provided) 55.41 (b) 7 H New New N/A New none 3.3.1 UllRT EXAM BANK COMPUTER TEST Page: 96 of 206 12 October 2010 EXAMINATION ANSWER IL RO questions in sample plan order 10: 8809 Points: 1.00 Unit 2 plant conditions are as follows: OPCON 2 with a reactor startup in

-RPS NI shorting links are -All I RMs are on Range SRM indications: -"1A" 0.8 x 10 5 -"1 B" 2.5 x 10 5 -"1C" 2.1 x 10 5 -"1D" 1.5x10 5 WHICH ONE of the following describes the plant response? Rod Block Half scram Full scram A. yes yes yes B. yes yes no C. yes no no D. no no no Answer: C Answer Explanation: yes; no; no -This is the correct answer because an SRM upscale condition will cause a control rod withdraw block if any channel is above 1 x 10 5 cps, and with the RPS NI shorting links installed, exceeding the RPS set pOint of 2 x 10 5 cps will not cause a reactor scram or half-scram. If the RPS NI shorting links had been removed, anyone SRM channel exceeding the RPS set point of 2 x 10 5 cps would have resulted in a full scram. yes; yes; yes -This is a partially correct answer because an SRM upscale condition will cause a control rod withdraw block if any channel is above 1 x 10 5 cps but the answer is incorrect because with the RPS Shorting Links installed as in the condition given, SRM level above 2 x 10 5 cps will no result in either a Half or Full Scram. If the RPS NI shorting links had been removed, anyone SRM channel exceeding the RPS set point of 2 x 10 5 cps would have resulted in a FULL scram. EXAM BANK COMPUTER TEST Page: 97 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order yes; yes; no -This is a partially correct answer because an SRM upscale condition will cause a control rod withdraw block if any channel is above 1 x 10 5 cps but the answer is incorrect because with the RPS Shorting Links installed as in the condition given, SRM level above 2 x 10 5 cps will no result in either a Half or Full Scram. If the RPS NI shorting links had been removed, anyone SRM channel exceeding the RPS set point of 2 x 10 5 cps would have resulted in a FULL scram. no; no; no -This is a partially correct answer for identifying that the condition will not result in either a Half or Full Scram with the RPS NI shorting links installed but is incorrect for failing to identify that a rod withdraw block will result if any channel is above 1 x 10 5 cps. Question 34 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: User-Defined ID: Cross Reference SRM indication on Startup Num Field 1: 3.4 i Num Field 2: 3.5 i Text Field: 215004 K4.02 Comments: General Data Technical Reference with ST-2-074-624-1, Rev 04, Revision Number: page 3 Tech Spec Table 3.3.6-1 LGSOPS0074.6 Cognitive Level H PRA: (Le. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (Le. LGS MODIFIED NRC-05, OYS CERT-04) Question Source: (Le. New, BANK: 562180 i Bank, Modified) EXAM BANK COMPUTER TEST Page: 98 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) i ILT Supplied Ref (If appropriate): (Le. ABN-##) Excluded

Reference:

(Le. Ensure ON-'##-not provided)

I Low KA Justification (if required): Modified, Changed to Unit 2. Changed values of all 4 SRM readings. Changed the channels indicating above the rod block and scram set points. Also, question 562180 has a half-scram occurring and if the RPS shorting links are removed. and SRM above the Hi Hi trip set point will result in a full scram; therefore, added a third column labeled full scram to make question distractors more plausible and require differentiation of SRM response from IRM and APRM response .. Changed the correct answer from "B" to "C". NONE NONE N/A EXAM BANK COMPUTER TEST Page: 99 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8810 Points: 1.00 Preparations are in progress to synchronize the Unit 2 Main Generator, with the following indications: -335 Breaker Synch Selector Switch ON -Voltage Regulator is in AUTO -INCOMING VOLTAGE is 121 -RUNNING VOLTAGE is 124 -SYNCHROSCOPE is rotating slowly in the SLOW direction WHICH ONE of the following is required prior to closing the 335 (OUTPUT) Breaker? A. Raise Speed AND Lower Incoming Voltage B. Raise Speed AND Raise Incoming Voltage C. Lower Speed AND Raise Incoming Voltage D. Lower Speed AND Lower Incoming Voltage Answer: B Answer Explanation: Raise Speed AND Raise Incoming Voltage -This answer is correct because generator speed must be raised until the synchroscope is rotating slowly in the FAST (clockwise) direction with synchronizing lights flashing. Generator voltage must be 0 to 3 volts higher than running voltage before the generator breaker (535) is closed so raising incoming voltage to meet this condition is correct. These stated conditions are consistent with operator procedure steps in S32.1.A for Synchronizing Main Generator to Grid. Raise Speed AND Lower Incoming Voltage -This answer is partially correct because generator speed must be raised until the synchroscope is rotating slowly in the FAST (clockwise) direction with synchronizing lights flashing. This answer is incorrect because generator voltage is already 3 volts lower than the grid voltage and further lowering would be improper for closing the generator breaker (535). This is per operator procedure steps in S32.1.A for Synchronizing Main Generator to Grid. I EXAM BANK COMPUTER TEST Page: 100 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Lower Speed AND Raise Incoming Voltage This answer is partially correct due to recognizing the requirement that Generator voltage must be 0 to 3 volts higher than running voltage before the generator breaker (535) is closed so raising incoming voltage to meet this condition is correct. This answer is incorrect because generator speed must be raised until the synchroscope is rotating slowly in the FAST (clockwise) direction with synchronizing lights flashing and lowering the speed would result in synchroscope rotating faster in the fast direction. If the generator breaker (535) were closed in this condition it would not be able to pick up real load and would become motorized from the grid. This is per operator procedure steps in S32.1.A for Synchronizing Main Generator to Grid. Lower Speed AND Lower Incoming Voltage -This answer is incorrect because generator voltage is already 3 volts lower than the grid voltage and further lowering would be improper for closing the generator breaker (535). Additionally, generator speed must be raised until the synchroscope is rotating slowly in the FAST (clockwise) direction with synchronizing lights flashing and lowering the speed would result in synchroscope rotating faster in the fast direction. If the generator breaker (535) were closed in this condition it would not be able to pick up real load and would become motorized from the grid. This is per operator procedure steps in S32.1.A for Synchronizing Main Generator to Grid. !Question 35 Info Question Type: Status: Always select on test? Authorized for practice?

Points: Time to Complete:
Difficulty:

System User -Defined I Cross Reference Num Field 3.00 8810 8810 Generator synch reguirements 3.4 Num Field Text Field: Comments: General Data Technical Reference Revision Cognitive PRA: (Le. Yes or No or 1 OCFR 55.43 (N/A for S32.1.A, Rev. 25, pages 7 and 8 LGSOPSOO32.iL7 H NO 55.41 (b) 7 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order i! Question History: (i.e. LGS BANK NRC-OS, OYS CERT-04) Question Source: (Le. New, BANK: 556938 Bank, Modified) Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE Ensure ON-## not provided]

Low KA Justification (if N/A i requiredj: EXAM BANK COMPUTER TEST Page: 102 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8811 Points: 1.00 Unit 1 plant conditions are as follows: -RCIC is in operation for pressure -HV-49-1 F022, RC1C Full Flow Test valve is initially adjusted to obtain a -RCIC pump discharge pressure of 600 psig at 600 -Reactor pressure is 350 psig and HV-49-1 F022 is throttled in the close direction to raise RCtC pump discharge pressure to 900 psig, and RCtC system flowrate is observed to lower WHICH ONE of the following describes the status of the RCIC system? A. RCIC FLOW CONTROLLER is in AUTO. RCIC turbine speed has risen. B. RCIC FLOW CONTROLLER is in AUTO. RCIC turbine speed is constant. C. RCIC FLOW CONTROLLER is in MANUAl. RCIC turbine speed has lowered. D. RCIC FLOW CONTROLLER is in MANUAl. RCIC turbine speed is constant. Answer: D Answer Explanation: RCIC FLOW CONTROLLER is in MANUAL. RCIC turbine speed is constant: With the RCtC FLOW CONTROLLER in MANUAL, RCIC turbine speed remains constant. RCIC system head loss goes up as HV-49-1 F022 is throttled closed, and RCIC system flowrate lowers. RCIC FLOW CONTROLLER is in AUTO. RCIC turbine speed has risen: RCIC system head loss goes up as 1 F022 is throttled closed. If the RCIC FLOW CONTROLLER were in AUTO, RCIC turbine speed would automatically rise to maintain a constant f10wrate to the CST; however, indications are that RCIC flowrate has lowered; therefore, the answer is incorrect. RCIC FLOW CONTROLLER is in AUTO. RCIC turbine speed is constant: If the RCIC turbine speed were constant with rising RCIC system head loss, RCIC system flowrate would lower. However, when the RCIC FLOW CONTROLLER is in AUTO, RCIC turbine speed automatically varies to maintain a constant flowrate to the CST; therefore, the answer is incorrect. RCIC FLOW CONTROLLER is in MANUAL. RCIC turbine speed has lowered: If RCIC turbine speed had lowered, RCIC system flowrate would lower; however, the answer is incorrect because RCIC turbine speed remains constant when the RCIC FLOW CONTROLLER in MANUAl. EXAM BANK COMPUTER TEST Page: 103 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 36 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text I Multiple Choice Active No No 1.00 3 3.00 8811 8811 LLOT0380.8A RCIC flow requirements 3.1 3.1 217000 K5.02 General Technical Reference with S49.7.A, Rev Revision Number: Cognitive Level PRA: (Le. Yes or No or #) 1 OCFR 55.43 (N/A for RO) 55.41 (b) Question History: (Le. LGS NRC-05, OYS Question Source: (Le. New, Bank, Revision History: Revision History: (Le. distractor "b" to plausible based on ! ILT . Supplied Ref(lf NONE i appropriate): (Le. Excluded

Reference:

(Le. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 104 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8812 Points: 1.00 Unit 1 plant conditions are as follows: -SLC Tank chemical mixing is underway in accordance with S48.3.C " Chemical and Demineralized Water Makeup for Standby Control Storage Tank" -TIS-48-1R002, SLC Tank Temperature indicates 92°F. WHICH ONE of the following describes the required status of the SLC Tank Heater Control switch and the SLC Heater Banks? Switch Position Heater "A" Heater "B" A. OFF OFF B. ON OFF C. ON OFF D. ON ON Answer: D Answer Explanation: ON, ON, ON: During Tank mixing, the Heater Control switch is placed in ON whenever SLC Tank temperature is below 95°F, energizing BOTH heater banks. SLC Tank temperature must be maintained greater than gO°F to prevent Sodium Pentaborate from crystallizing during mixing.

AUTO, OFF, OFF: During normal operation, the SLC Tank Heater Control switch is in AUTO, and SLC Heater Bank "A" can cycle to maintain SLC Tank temperature between 75°F and 105°F, making it is possible for both Heater Banks to be OFF; however, during Tank mixing, the Heater Control switch is placed in ON whenever SLC Tank temperature is below 95°F, energizing BOTH heater banks, preventing Sodium Penta borate from crystallizing during mixing. AUTO, ON, OFF: During normal operation, the SLC Tank Heater Control switch is in AUTO, and SLC Heater Bank "A" can cycle to maintain SLC Tank temperature between 75°F and 105°F, making it is possible for Heater Bank "A" ONLY to be ON; however, during Tank mixing, the Heater Control switch is placed in ON whenever SLC Tank temperature is below 95°F, energizing BOTH heater banks, preventing Sodium Pentaborate from crystallizing during mixing. EXAM BANK COMPUTER TEST Page: 105 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ON, ON, OFF: During Tank mixing, the Heater Control switch is placed in ON whenever SLC Tank temperature is below 95°F, which energizes BOTH heater banks. Question 37 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8812 8812 LGSOPS0048.1L2B SBLC Heater Operation 2.7

2.9 211000

K5.07 General Data Technical Reference Revision Cognitive PRA: (Le. Yes or No or 1 OCFR 55.43 {N/A for Question History: (Le. NRC-05, OYS Question Source: (i.e. Bank, Revision History: History: (i.e. distractor "b" to plausible based on ILT Supplied Ref <If appropriate): (Le. ABN-##) Excluded

Reference:

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Low KA Justification (if required): S48.1.A, Rev 15, page 9 S48.1.B, Rev 17, page 6 L NO 55.41 (b) 5 NEW NEW NEW NONE NONE N/A EXAM BANK COMPUTER TEST Page: 106 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8813 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor is -HPCI is operating for pressure control in accordance with The following occurs: -115 CLEANUP, E-5, Excess Flow Check Valve Operated Panel C218 alarms due to an instrument line break -115 COOL B. E-3, Div 2 Reactor LO-LO-LO Level alarms -114 ISOL, C-2, Reactor LO-LO Level alarms -Emergency Diesel D 12 auto starts -HPCI initiation (white) SEAL IN lamp illuminates on 10C647 WHICH ONE of the following describes the expected response of the HPCI system due to the current conditions? The HPCI system continues to operate in pressure control mode. The HPCI system CST flowpath isolates. HPCI CANNOT be returned to the pressure control mode. The HPCI system CST flowpath isolates. HPCI CAN be returned to the pressure control mode IMMEDIATL Y. The HPCI system CST flowpath isolates. HPCI CAN be returned to the pressure control mode AFTER depressing the "Seal In" Reset Pushbutton Answer: B Answer Explanation: The HPCI system CST flowpath isolates. HPCI CANNOT be returned to the pressure control mode: The HPCI CST flowpath isolates when HPCI is initiated. Regardless of actual vessel level, the division 2 level instruments affected by the sensing line failure will continue to "see" low-low vessel level; therefore, the HPCI initiation signal cannot be reset, and HPCI cannot be returned to the pressure control mode regardless of actual vessel level. The HPCI system continues to operate in the pressure control mode: Indications are that the division 2 level instruments affected by the sensing line failure "sees" low-low vessel level resulting in a continuous HPCI initiation signal. The HPCI CST flowpath isolates when HPCI is initiated. EXAM BANK COMPUTER TEST Page: 107 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR DISTRACTOR

Question 38 Info I Question Type: . Status: *Always select on test? Authorized for practice?

Points: Time to COITiplete: Difficulty: System User-Defined Cross Reference Num Field 0--... Num Field Text The HPCI system CST flowpath isolates. HPCI CAN be returned to the pressure control mode IMMEDIATELY: The HPCI CST flowpath iSQlates when HPCI is initiated. The answer is incorrect because the division 2 level instruments affected by the sensing line failure will continue to "see" low-low level regardless of actual vessel level; therefore, HPCI cannot be returned to the pressure control mode, immediately or otherwise. The HPCI system CST flowpath isolates. HPCI CAN be returned to the pressure control mode ONLY AFTER the initiation signal is reset: The HPCI CST flowpath isolates when HPCI is initiated. The answer is incorrect because the division 2 level instruments affected by the sensing line failure will continue to "see" lOW-low level regardless of actual vessel level; therefore, the initiation signal cannot be reset, and HPCI cannot be returned to the pressure control mode. Multiple 3.00 18813 8813 LLOT0340.12B Excess flow check valve indications

3.6 206000

General Data Technical Reference with Revision Number: c-(;ognitive Level PRA: (I.e. Yes or No or #) 1 OCFR 55.43 (N/A for RO) Question History: (i.e. LGS NRC-05, OYS CERT-04) r-=..... Question Source: (i.e. Bank, Revision History: . History: (I.e. Modified distractor "b" to make plausible based on OTPS review) S55.7.A, Rev. 8 E-41-1 040-E-021, sheet 001, Rev. 12 55.41 (b) NEW

NEW I ILT EXAM BANK COMPUTER TEST Page: 108 of 12 October 2010 I i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Supplied Ref (If appropriate): (I.e. Excluded

Reference:

(I.e. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 109 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order ID: 8814 Points: 1.00 Unit 1 plant conditions are as follows: -The 480 VAC MCC supply breaker for the 1A2D103 Battery Charger has tripped -120 -D11 G-1, UN IT DIV 1 SFGD BATTERY CHARGERS TROUBLE alarms WHICH ONE of the following is carrying the Division I DC loads? A. 1 A2 Battery and 1 A 10103 Battery Charger B. 1 A 1 D1 03 Battery Charger ONLY C. 1A1 and 1A2 Batteries D. 1A2 Battery ONLY Answer: A Answer Explanation: 1A2 Battery and 1A1D103 Battery Charger: The Division I DC Distribution system has 2 batteries and each battery has a battery charger. The battery chargers are the normal source of power for the DC system. With a trip of 480 VAC MCC supply breaker for one of the battery chargers, the associated battery will begin to discharge.

The second battery charger will continue to supply the DC bus. 1A1D103 Battery Charger only: With a trip of 480 VAC MCC supply breaker for one of the battery chargers, the second battery charger will continue to supply the DC bus; however, the associated battery will also begin to discharge. 1A1 and 1A2 Batteries: The Division I DC Distribution system has 2 batteries and each battery has a battery charger. The battery chargers are the normal source of power for the DC system. With a trip of 480 VAC MCC supply breaker for one of the battery chargers, the associated battery will begin to discharge. The second battery charger will continue to supply the DC bus. 1A2 Battery only: With a trip of 480 VAC MCC supply breaker for one of the battery chargers, the associated battery will begin to discharge; however, the second battery charger will also continue to supply the DC bus. EXAM BANK COMPUTER TEST Page: 110 of 12 October 201 0 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 39 Info f i Question Type: Multiple Choice I Status: Active , Always select on test? No i Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 8814 , User-Defined ID: 8814 Cross Reference Number: LGSOPS0095.1L 7 Topic: Battery charger loss Num Field 1: 3.2 Num Field 2: 3.5 Text Field: 263000 K6.01 Comments: General Data Technical Reference with ARC-MCR-120 G-1, REV Revision Number: 3 E-33, sh1, Rev 44 E-55, sh1, Rev 51 Cognitive Level L PRA: (Le. Yes or No or #) YES 10CFR 55.43 (N/A for RO) 55.41 (b)7 Question History: (i.e. LGS BANK NRC-05, OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified) Revision History: Revision Modified. Changed stem History: (Le. Modified to remove direct distractor "b" to make statement that the plausible based on OTPS charger would trip on a review) loss of the 480 VAC MCC supply breaker. Changed the effected charger to 1A2D103 from 1A1D103. Changed the order of the distractors. Changed the correct answer to A from D. ILT Supplied Ref {If E-33, Sh 1, Rev 51 {Le. ABN-##J Excluded

Reference:

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I[ Low KA Justification (if N/A required): I EXAM BANK COMPUTER TEST Page: 111 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8815 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is -Mode Switch is in -All IRMs are fully -"0" IRM recorder reads The following IRM indicating lamps are illuminated on the 10C603 benchboard. -"O"IRM UPSC -"0" IRM UPSC TR or INOP -"H" IRM UPSC TR or INOP -"A" IRM UPSC TR or INOP WHICH ONE of the following describes the affect of the IRM system on the RPS system? A. NO "An or "B" Side half-scram B. "A" side half-scram ONLY C. "B" side half-scram ONLY O. FULL scram Answer: A Answer Explanation: NO "A" or "8" Side half-scram: A scram signal is generated when an IRM is UPSCALE or INOP. One IRM in RPS trip system "An -IRM A, C, E, or G must be tripped to generate an "A" side half-scram, ANO one IRM in RPS trip system "B" -IHM B, 0, F, or H must be tripped to generate a "B" side half-scram. However, when the Reactor Mode switch is in RUN, alllRM generated scrams signals are bypassed; therefore, even though the IRM indicating lamps on 10C603 show that conditions have been met for a full scram, RPS remains energized. FULL scram: A scram is generated when an IRM is UPSCALE or INOP. One IRM in RPS trip system "An -IRM A, C, E, or G must be tripped, ANO one IRM in RPS trip system "B" IRM B, 0, F, or H must be tripped for a full RPS trip to occur. The IRM indicating lamps on 10C603 show that conditions have been met for a full scram; however, the answer is incorrect because the Reactor Mode switch is in RUN bypassing all IRM generated scrams signals. EXAM BANK COMPUTER TEST Page: 112 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order "A" side half-scram ONLY: A scram signal is generated when an IRM is UPSCALE or INOP. One IRM in RPS trip system "N' -IRM A, C, E, or G must be tripped, OR one IRM in RPS trip system "B" -IRM B, 0, F, or H must be tripped for an RPS half-scram to occur. The IRM indicating lamps on 10C603 show that conditions have been met for an "An side half-scram to occur; however, the answer is incorrect because the Reactor Mode switch is in RUN bypassing alllRM generated scrams signals. "B" side half-scram ONLY: A scram signal is generated when an IRM is UPSCALE or INOP. One IRM in RPS trip system "N' -IRM A, C, E, or G must be tripped, OR one IRM in RPS trip system "8" -IRM B, D, F, or H must be tripped for an RPS half-scram to occur. The IRM indicating lamps on 10C603 show that conditions have been met for a "B" side half-scram to occur; however, the answer is incorrect because the Reactor Mode switch is in RUN bypassing all IRM generated scrams signals. Question 40 Question Always select on Authorized for Time to System Jser-Defined Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8815 8815 LGSOPS0074.IL20A Neutron Indications on Startup 3.3 3.2 215003 A 1.06 General Data Technical Reference Revision Cognitive PRA: (Le. Yes or No or 10CFR 55.43 (N/A for Question History: (Le. NRC-05, OYS Question Source: (Le. Bank, M-1-C71-1020-E-006, 007,009 H NO 55.41 (b) 5 Bank EXAM BANK COMPUTER TEST Page: 113 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision Modified question to test History: (i.e. Modified knowledge of IRM distractor "b" to make Benchboard indications plausible based on OTPS and ability to predict review) affects on RPS. Changed APRM status in question stem to IRM indications. Added status of IRM indicating lamps. Changed answer from A to D. ILT Supplied Ref (If NONE appropriate): (Le. ABN-Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

Low KA Justification (if N/A required):

c P;:;:-a-g-e:-c 1 ,-;-14-:--:of:-:::2c::-

-----....... --------:1 7 2-=O-:ct,....,ob:--e-r 06 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8816 Points: 1.00 Unit 1 plant conditions are as follows: -"A" SGTS fan is Inoperable RE HVAC isolates on High Rad -"B" SGTS fan -The liB" SGTS fan bypass damper is fully WHICH ONE of the following describes the expected steady state Reactor Enclosure differential pressure?

A. 0.00 to -0.15 psid B. 0.00 to +0.15 psid C. -0.25 psid or lower (more negative) D. +0.25 psid or greater (more positive) Answer: C Answer Explanation: -0.25 psid or lower (more negative): Standby Gas Treatment (SGTS) draws suction on RERS downstream of the RERS filters. or directly on the refuel floor. and maintains the zone(s) pressure -.25" H 2 0. The SGTS fan f10wrate is controlled by the combined modulation of the fan inlet, outlet and bypass dampers. When running. a SGTS fan will be regulated by the bypass damper (PD-C-339A.B) to maintain the zone with the highest static pressure (least negative) at 0.25 WG. The failed closed bypass damper, 339B, will reduce the amount of air bypassing the SBGT fan. however the inlet and outlet damper will continue to regulate to maintain >-0.25" H 2 O. 0.00 to -0.15 psid: Standby Gas Treatment (SGTS) draws suction on RERS downstream of the RERS filters or directly on the refuel floor. and maintains the zone(s) pressure -.25" H 2 O. 0.00 to +0.15 psid: Standby Gas Treatment (SGTS) draws suction on RERS downstream of the RERS filters or directly on the refuel floor. and maintains the zone(s) pressure -.25" H 2 O. +0.25 psid or greater (more positive): Standby Gas Treatment (SGTS) draws suction on RERS downstream of the RERS filters or directly on the refuel floor, and maintains the zone(s) pressure -.25" H 2 O. EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 41 Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8816 8816 LLOT0200.5E SGTS requirements 3.0 3.3 261000 A1.04 General Data Technical Reference with P&ID M-76. Rev 20 Revision Number: Cognitive Level H PRA: (Le. Yes or No or #) NO

10CFR 55.43 (N/A for RO) 55.41 (b)5 Question History: (i.e. LGS NRC-05, OYS CERT-04) Question Source: (Le. New. Bank,561042 Bank, Modified)

Revision History: Revision Changed answer from 0 History: (Le. Modified to C. Changed distractor distractor "b" to make C to A; changed distractor I plausible based on OTPS A to B, and changed review) distractor B to D.

ILT i Supplied Ref (If NONE appropriate): (Le. Excluded

Reference:

(Le.

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Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 116 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8817 Points: 1.00 Unit 1 plant conditions are as follows: -100% power -SPOTMOS indicates Suppression Pool temperature is 90°F and stable STEAM 110, B-1, SRV/HEAD VENT VALVE LEAKING alarms: -XI-036-101 on 10C614 confirms rising Safety Relief Valve (SRV) Tailpipe Temperature for PSV41-1F013S. -All Amber "SRV HAS LIFTED" lamps on 10C626 are NOT Lit. -All Red "SRV OPEN" lamps on 1 OC626 are NOT Lit. -All Green "SRV CLOSED" lamps on 1 OC626 are Lit. -All White "SRV SOLENOID ENERGIZED" lamps on on 1 OC626 are NOT Lit -SPOTMOS indicates Suppression Pool temperature is 92°F and slowly RISING. WHICH ONE of the following describes the condition of the "S" SRV and the required operator action? SRV Leaking Place One loop of Suppression Pool Cooling in service per S51.8.A . SRV Leaking. Place Two loops of Suppression Pool Cooling in service per OT-114 SRV FULLY Open Place One loop of Suppression Pool Cooling in service per S51.8.A SRV FULLY Open Place Two loops of Suppression Pool Cooling in service per OT-114 Answer: A Answer Explanation: SRV Leaking, Place One loop of Suppression Pool Cooling in service per S51.B.A: This answer is correct because an SRV/HEAD VENT VALVE LEAKING alarm with slowly rising Suppression Pool temperature and riSing SRV tailpipe temperature indicates a leaking SRV. Appropriate action is to place one loop of suppression pool cooling in operation per S51.8A Two loops of RHRSW may be aligned in anticipation of further need for removing heat from the Suppression Pool if temperature reaches 95 deg. F and T-102 entry is required. EXAM BANK COMPUTER TEST Page: 117 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR DISTRACTOR DISTRACTOR Question 42 Info Question Type: Status: SRV Place One loop of Suppression Pool Cooling in service per This answer is only partially correct due to the assessment of an Leaking but is not correct because OT-114 is only entered for a open SRV. Additionally. OT-114 directs placing two loops of Pool Cooling in service. The follow-up actions in OT-114 give indications for an SRV stuck open and these do not match with exception of rising SP and Tail Pipe SRV FULLY Place One loop of Suppression Pool Cooling in service per This answer is only partially correct. Based on the indications given. Annunciator for SRV/Head Vent Leaking alarms at 205 deg. F and open SRV would have a Tail Pipe temperature of about 330 deg. Indications do not support that an SRV is open. Additionally. If an SRV open OT-114 should be entered. OT-114 directs placing two loops Suppression Pool Cooling in SRV FULLY Place One loop of Suppression Pool Cooling in service per OTThis answer is incorrect because indications do not support that SRV open and OT-114 directs placing two loops of Suppression Pool in Always select on Authorized for Time to Ity: stem ID: User-Defined ID: Cross Reference Number: Num Field Num Field Text Multiple Choice Active No No 3.00 SPOTMOS indications

3.1 239002

General Data Technical Reference Revision Cognitive PRA: (i.e. Yes or No or 10CFR 55.43 (N/A for Question History: (i.e. NRC-05, OYS Question Source: (Le. Bank, S51.B.A OT-114 BASES Rev. 255 T-102. LGSOPS1540.1,2, and 5 H YES 55.41 (b) 7 NEW NEW EXAM BANK COMPUTER TEST Page: 118 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 119 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8818 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor Pressure 200 psig and lowering -Drywell Pressure 1 .0 psig and steady -Div 3 DC is de-energized Reactor level -165" down slow Given the following procedures: -E-1 FC, Loss of Division 3 Safeguard 125V DC Bus -S52.7.B, Core Spray Injection with a single pump running WHICH ONE of the following identifies the "1A" Core Spray (CS) pump loop operation and procedural actions required? "1A" loop Core Spra!i (CS) Procedural actions pump operation required A. 1 CS pump running, and Start CS pump per E-1 FC B. 1 CS pump running, and Operate CS per S52.7.B 1 CS pump running, NO injection Start CS pump and open Injection Valve per E-1 FC 1 CS pump running, NO injection Operate CS, and open Injection Valve per S52.7.B Answer: B Answer Explanation: 1 CS pump running, and injecting; Operate CS per S52.7.B This answer is correct because with the conditions given a LOCA signal is present due to < -129 inches and an Injection Signal is present with RPV pressure < 455 psig. With the loss of Division 3 Safeguard DC power the 1 C CS pump will not start but the Division 1 LOCA logic will start the 1A CS pump and align the A Loops CS Injection valves. The Core Spray loop must be operated under the controls and conditions of S52.7.B to prevent damage and unavailability of the 1A Core Spray pump due to potential run-out with a single pump running. 1 CS pump running, and injecting; Start CS pump per E-1 Fe This answer is partially correct due to the assessment of 1 CS pump running and injecting with the Div I LOCA logic and Injection logic enabled but is incorrect because there is no capability for starting the 1 C Core Spray pump with no divisional DC control power to the 4KV breaker control circuit EXAM BANK COMPUTER TEST Page: 120 of 12 October 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 1 CS pump running, NO injection; Start CS pump and open Injection Valve per E-1FC -This answer is incorrect because the 1A Core Spray pump will be running and injecting with the current plant conditions of LOCA due to < -129 inches and injecting due to RPV pressure < 455 psig. Additionally, this answer is incorrect due to the statement for starting and aligning injection with the 'E' procedure for loss of Div III Safeguard DC power. 1 CS pump running, NO injection; Operate CS, and open Injection Valve per S52.7.B -This answer is partially correct for assessment of the procedure for controlling injection with a single Core Spray pump in a loop but incorrect because it does not recognize that the Core Spray pump is expected to be running and injecting with the given plant conditions. Question 43 Info Question Type: Multiple Choice Active Always select on test? No Authorized for No 1.00 Time to Complete: 3 3.00 System ID: 8818 User-Defined ID: 8818 Cross Reference Number: LLOT0350.3D Core Spray requirements Num Field 1: 2.9 Num Field 2: 3.0 i Text Field: 209001 A2.04 Comments: General Data I Technical Reference with T-111 Bases I Revision Number: Cognitive Level H PRA: (Le. Yes or No or #) YES i 10CFR 55.43 (N/A for RO) 55.41 (b) 5 Question History: (Le. LGS NEW NRC-05, OYS CERT-04J Question Source: (Le. New, NEW Bank, Modified) Revision History: Revision NEW History: (Le. Modified I distractor "b" to make i plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##} Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

I EXAMINATION ANSWER KEY I L T09-1 RO questions in sample plan order Low KA Justification (if I N/A required): --EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8819 Points: 1.00 Unit 1 plant conditions are as -Unit 1 plant is at 100% reactor -107 REACTOR, H-1, REACTOR WATER BELOW LEVEL 3 TRIP The "B" Scram Status lamps on 1 OC-603 are NOT illuminated. The "A" Scram Status lamps on 10C-603 ARE illuminated. WHICH ONE of the following identifies Reactor Level Switches that could have caused these 10C-603 Scram Status light Reactor Level 3 Level Switch A. lISL-42-1N680A or 1N680C tripped B. lISL-42-1N680B or 1N6800 tripped C. lISL-42-1 N680A and 1 N680B tripped O. lISL-42-1 N680S and 1 N680C tripped Answer: B Answer Explanation: LlSL-42-1 N680B or 1 N6800 tripped: A "S" or "0" Reactor Level trip unit failing downscale de-energizes the S 1 or S2 RPS relay logic resulting in a half scram on the "S" side, extinguishing the "S" RPS Scram Status lights. LlSL-42-1 N680A or 1 N680C tripped: The answer is incorrect because an "A" or "C" Reactor Level trip unit failing downscale would de-energizes the A 1 or A2 RPS relay logic resulting in a half scram on the "A" side, extinguishing the "An RPS Scram Status lights. LlSL-42-1 N680A and 1 N680B tripped: The answer is incorrect because 1 N680A and 1 N680B Reactor Level trip units failing downscale would de-energizes the A1 and B1 RPS relay logics resulting in a full scram, extinguishing both the "An and "S" RPS Scram Status lights. LlSL-42-1N680C and 1N680D tripped: The answer is incorrect because 1 N680C and 1 N6800 Reactor Level trip units failing downscale would de-energizes the A2 and S2 RPS relay logics resulting in a full scram, extinguishing both the "An and "S" RPS Scram Status lights. EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 44 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8819 8819 LGSOPS0071.7A RPS scram condition 3.2 3.0 212000 A3.02 General Data Technical Reference with ARC 107 REACTOR, H-Revision Number: 1, rev 0 C71-1020-E-020, sh 7A, Rev 3, sh 9, Rev 5, and sh 10, Rev 5 Cognitive Level H PRA: (i.e. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (i.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, BANK, MODIFIED Bank, Modified) Revision History: Revision Modified bank question History: (i.e. Modified 562290. Changed stem of distractor "b" to make question to test the ability plausible based on OTPS to monitor the operation review) of specific system relays inputting to RPS utilizing only the available control room indications. Supplied Ref (If appropriate): (i .8. Excluded

Reference:

(i.e. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 124 of 206 12 Oc;tober 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8825 Points: 1.00 Unit 1 plant conditions are as follows: -"1A" RECW pump is in "AUTO" after -"1 B" RECW pump is in "AUTO" after RPV level drops to -150" WHICH ONE of the following describes the "1A" and "1 B" RECW pumps response as RPV level drops without operator action? "1A" RECW "1 B" RECW pump "1A" pump will trip and "1 B" pump will auto start remains shutdown after 0144 is reenergized "1A" pump will trip and auto "1 B" pump will auto start restart after 0134 is reenergized after 0 144 is reenergized "1 A" pump will trip and "1 B" pump will remain shutdown remains shutdown "1 A" pump will trip and auto "1 B" pump will remain shutdown restart after 0134 is reenergized Answer: C Answer Explanation:

i"1A" pump will trip and remains shutdown; "1 B" pump will remain shutdown -This answer is correct because of the LOCA Load Shed trips for the RECW pumps Oiv III for *A pump trip and Oiv IV for *B pump Also during the LOCA, the LC breaker is cycled open for 3 seconds. After the 0134 and 0144 Load Centers are reenergized, the SE-1O procedure step 4.6 controls the restart of RECW when greater than 10 minutes have elapsed following a design basis LOCAILOOP. In order to restart the RECW pump the pump control would need to be restarted with the hand switch or the Divisional LOCA signal would be reset. The restart following a LOCA is per S13.1.A. "1A" pump will trip and remains shutdown; "1B" pump will auto start after 0144 is reenergized -This answer is partially correct due to the 1A RECW pump response to a Div III LOCA signal but incorrect because the 1 B RECW pump will not restart in AUTO following a LOCA. It must be manually started. "1A" pump will trip and auto restart after 0134 is reenergized; "'I B" pump will auto start after 0144 is reenergized -This answer is incorrect because neither 1 A or 1 B RECW pump will restart unless the Div III or Div IV LOCA signals are restart or the pump is restarted from the hand switch. EXAM BANK COMPUTER TEST Page: 125 of 12 October 2010 EXAMINATION ANSWER Il T09-1 RO questions in sample plan order "1A" pump will trip and auto restart after 0134 is reenergized; "1 B" pump will remain shutdown -This answer is partially correct because 1 B RECW pump will remain shutdown but is incorrect because the 1A RECW pump will not auto restart after 0134 is reenergized. Either a manual start or reset of lOCA divisional logic is required. Question 45 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Question 45 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8825 User-Defined 10: 8825 Cross Reference Number: lGSOPS0013.ll4A Topic: RECW pump start requirements Num Field 1: 3.0 Num Field 2: 3.0 Text Field: 400000 A3.01 Comments: General Data Technical Reference wth ARC 118 SERVICES, H-Revision Number: 3, REAC ENCL COOLING WATER HTX OUT LO PRESS. P&ID 8031-M-13, Rev 41 Bechtel Electrical drawing E-565, Rev 10 Cognitive Level L PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review)I EXAM BANK COMPUTER TEST Page: 126 of 12 October 2010 i I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

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Low KA Justification (if N/A required): EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8826 Points: 1.00 The following occurred on Unit 2: -Reactor level dropped to -150 -All Low pressure ECCS pumps -Both divisions of ADS actuated -All ADS SRVs Current Unit 2 conditions are as follows: -Reactor pressure is 250 psig and -Drywell pressure is 15 psig and -Reactor level has recovered to +20" and is ADS Reset Pushbuttons S3A and S3C, DIW PRESS HIGH RX LEVEL LOW are depressed and released. WHICH ONE of the following describes the expected affect on the ADS SRVs? A. ADS SRVs will close initially but will re-open after 525 seconds. B. ADS SRVs will close initially but will re-open after 105 seconds. C. ADS SRVs will close and remain closed. D. ADS SRVs will remain open. Answer: C Answer Explanation: ADS SRVs will close and remain closed: With Reactor Level restored above -129" and ADS logic reset, the ADS SRVs will close and remain closed. With the existing high drywell pressure condition (15 psig), ADS will not re-initiate unless vessel level again remains below -129 inches for 105 seconds. ADS SRVs will close initially but will re-open after 525 seconds: With Reactor Level restored above -129" and ADS logic reset, the ADS SRVs will close and remain closed. Without the existing high drywell pressure condition, ADS would not re-initiate until vessel level again remains below -129 inches for a total of 525 seconds. However, with the existing high drywell pressure condition (15 psig), ADS would re-initiate if vessel level remained below -129 inches for 105 seconds. I ADS SRVs will close initially but will re-open after 105 seconds: With Reactor Level restored above -129" and ADS logic reset, the ADS will close and remain closed. With the existing high drywell pressure condition, ADS will not re-initiate unless vessel level again ! remains below -129 "-'VIIU; ! J EXAM BANK COMPUTER TEST Page: 128 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR ADS SRVs will remain open: With Reactor Level restored above 129" and ADS logic reset, the ADS will close. Question 46 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 8826 User-Defined ID: 8826 Cross Reference Number: LGSOPS0050.lL7B I I VlJlv. ADS initiation requirement Num Field 1: 4.2 Num Field 2: 4.2 Text Field: 218000 A4.03 Comments: General Data Technical Reference with Revision Number: F.003.17 003, sh1, Rev 15 004, sh1, Rev 14 005, sh1, Rev 13 Cognitive Level H PRA: (Le. Yes or No or #) NO

10CFR 55.43 (N/A for RO) 55.41 (b) 7
Question History: (Le. LGS BANK NRC-05, OYS CERT-04) . Question Source: (i.e. New, BANK. LIMERICK LOT Bank, Modified) 2558 Revision History: Revision Edited stem for clarity. History: (i.e. Modified Changed order of distractor "b" to make distractors.

Changed plausible based on OTPS answer from B to C. review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

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Low KA Justification (if N/A required):

EXAM BANK COMPUTER TEST Page: 129 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8827 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is 41 % and steady -RPV level is -70 inches and steady -"1A" and "1 C" RFPs are tripped HS-006-149B.

"1 B" RFPT Speed Cont Switch (MSC). has the following indications -"MSC SELECT" light is -"MIA SELECT" light is T = 0 seconds RPV pressure rises to 1150 psig. WHICH ONE of the following identifies the "1 B" RFP indicators that are illuminated at the specified times? T = 30 T = 90 seconds A. MSC MSC SELECT B. MIA MSC SELECT C. MIA MIA SELECT D. MSC MIA SELECT Answer: B Answer Explanation: MIA SELECT; MSC SELECT: Correct because "MIA SELECT" light is illuminated during the runback, and the "MSC SELECT" light is illuminated at the completion of the run back. RRCS FW runback will override all MIA permissives and place the RFP in MIA control during a runback. At the completion of the run back, the RFP will automatically swap back to MSC control. Ref. RRCS logic OP-AID in CRIB. Refer to GP-18 Attachment 3 for setpoint for FW Runback > 1149 psig. MSC SELECT; MSC SELECT: Incorrect due to not identifying Feedpump control transfer to MIA and running back to minimum speed during the runback signal. See above discussion. (Partial correct T=90 for MSC Select) MIA SELECT; MIA SELECT: Incorrect due to not identifying return to pre-runback modeof MSC select after the completion of the feedback runback. See above discussion. (Partial correc T=30 for MIA Select) EXAM BANK COMPUTER TEST Page: 130 of 12 October 2010 EXAMINATION ANSWER IL1 RO questions in sample plan order MSC SELECT; MIA SELECT: Incorrect due to not identifying Feed pump control transfer to MIA and running . back to minimum speed during the runback signal and return to mode of MSC select after the completion of the feedback runback. i Question 47 Info Question Type: Multiple Choice Status: Active i Always select on test? No *Authorized for practice? No Points: 1.00 i Time to Complete: 3

3.00 System ID: 18827 iUser-Defined ID: Cross Number: LLOT0550.05 Topic: RFP Num Field 1: Num Field 2: Text Field: 259002 I General Data Technical Reference with Revision Number: Cognitive Level H PRA: (I.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) I 55.41 (b) 7 Question History: (i.e. LGS BANK 367916 NRC-05, OYS CERT-04) Question Source: (i.e. New, BANK Bank, Modified)
Revision History:

NONE History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

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Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 131 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8828 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is -"1A" RPS output breaker trips on under The CRS enters E-1AY160, "Loss of 1A RPS UPS Power", and directs performance of actions to bypass and restore affected systems WHICH ONE of the following identifies Technical Specifications LCO's that must be entered as a result of the loss of "1A" RPS UPS and the actions taken per E-1AY160? Isolation Actuation Instrumentation (3.3.2) ONLY Primary Containment Isolation Valves (3.6.3) ONLY Isolation Actuation Instrumentation Primary Containment Isolation Valves Primary Containment Isolation Valves (3.6.3) AND Reactor Enclosure Secondary Containment Integrity (3.6.5.1.1) Answer: C Answer Explanation: Isolation Actuation Instrumentation (3.3.2) AND Primary Containment Isolation Valves (3.6.3) This answer is correct because procedure E-1AY160 directs actions for restoring systems that have had in inadvertent isolation due to loss of logic power. These systems are RECW, DWCW, PCIG and Bypass Barrier Blocks and Vents which are Primary Containment Isolation Systems with valves controlled by NSSSS isolation logic. In order to restore the systems, the inadvertent isolation signals are removed with Keylock bypass switches and the Primary Containment Isolation Valves (PCIV) are returned to in service in a bypassed inoperable condition. Since the Instrumentation that controls the automatic isolation will no longer function the Limiting Conditions for Operation (LCO) and action statements for compliance with T.S. 3.3.2, Isolation Actuation Instrumentation must be met. Additionally, since these valves are PCIVs and will not longer isolate on an instrument detected condition the LCO and action statements for compliance with T.S. 3.6.3, Primary Containment Isolation Valves must be met. Both of these Tech Specs are required and referenced in E-1AY160. EXAM BANK COMPUTER TEST Page: 132 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DESTRACTOR DESTRACTOR DISTRACTOR Question 48 Info Question Type: Status: Isolation Actuation Instrumentation (3.3.2) ONLY This answer is partially correct due to Isolation Actuation Instrumentation (3.3.2) but is incorrect because ONLY excludes the Primary Containment Isolation Valves (3.6.3) required Tech Spec Actions. Primary Containment Isolation Valves (3.6.3) ONLY This answer is partially correct due to Primary Containment Isolation Valves (3.6.3) but is incorrect because ONL Y excludes the Isolation Actuation Instrumentation (3.3.2 required Tech Spec Actions. Primary Containment Isolation Valves (3.6.3) AND Reactor Enclosure Secondary Containment Integrity (3.6.5.1.1 ) This answer is partially correct due to Primary Containment Isolation Valves (3.6.3) but is incorrect because it adds the Reactor Enclosure Secondary Containment Integrity (3.6.5.1.1) which, although partial isolated by loss of 1AY160, Tech Spec Actions are met for Secondary Containment Integrity by the expected function of SGTS to maintain a negative pressure. Always select on test? i Authorized for practice? Points: Time to Complete: Difficulty:

System ID: User-Defined ID: Cross Reference Number: Num Field Num Field Text i I Multiple Choice Active No No 1.00 3 3.00 8828 8828 LGSOPS0071.1L'l3 RPS feed breaker loss 4.0 4.7 262002 2.2.22 General Data Technical Reference Revision Cognitive PRA: (i.e. Yes or No or 10CFR 55.43 (N/A for Question History: (Le. NRC-OS, OYS Question Source: (i.e. Bank, TECH SPEC 3.8.4.3 L NO 55.41 (b) 5 NEW NEW I : I EXAM BANK COMPUTER TEST Page: 133 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

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Low KA Justification (if N/A EXAM BANK COMPUTER TEST Page: 134 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8829 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor STARTUP is in progress -Reactor power is 20% During the startup the following alarms on MCR PNL 122 annunciate: -1 B RPS & UPS STATIC INVERTER TROUBLE -1DB-1 250 VDC MCC UNDERVOLTAGE -1 DB-2 250 VDC MCC UNDERVOL TAGE An EO verifies "1B" RPS/UPS, 10NAX160 "Inverter AC Feed Switch" is aligned to Secondary Alternate All RPS white status lights are WHICH ONE of the following identifies the source currently providing power to "1 B" A. TSC UPS Inverter bypassing the RPS/UPS B. TSC UPS Inverter not bypassing the RPS/UPS Inverter C. 480VAC Non-Safeguard bypassing the RPS/UPS inverter D. 480VAC Non-Safeguard not bypassing the RPS/UPS inverter Answer: D Answer Explanation: 480VAC Non-Safeguard not bypassing the RPS/UPS Inverter -This is the correct answer because the DC supply is the normal preferred source from 1 DB-1 250 VDC MCC. The primary alternate supply is from the TSC UPS Inverter (144D-C-F) and the Secondary Alternate supply is from Non Safeguard 480 VAC MCC 124A-G-F for the 1B Inverter. Per the conditions stated, The secondary alternate is selected on the Inverter AC Feed Selector Switch and the RPS inverter static switch will auto swap to the selected supply which in this case is the secondary alternate supply. In this stated condition the AC supply is not bypassing the RPS inverter, but is going through the inverter. TSC UPS Inverter not bypassing the RPS/UPS Inverter-This answer is incorrect because the conditions do not state that the Inverter is bypassed. The conditions also state that the Secondary Alternate Supply is selected which is not the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch. EXAM BANK COMPUTER TEST Page: 135 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order TSC UPS Inverter bypassing the RPS/UPS Inverter-This answer is incorrect because the conditions do not state that the Inverter is bypassed. The conditions also state that the Secondary Alternate Supply is selected which is not the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch. 480VAC Non-Safeguard bypassing the RPS/UPS Inverter -This answer is partially correct by identifying the correct Secondary Alternate AC supply but is incorrect because the inverter is not Manually bypassed using the maintenance BYPASS switch. Question 49 Info QUestion Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8829 8829 LGSOPS0071.1L2A, 2B, AND 2C RPS/UPS static inverter 4.1 4.1 262002 2.1.28 General Data Technical Reference Revision Cognitive PRA: (i.e. Yes or No or 1 OCFR 55.43 (N/A for Question History: (i.e. NRC-05, OYS Question Source: (I.e. Bank, Revision History: History: (I.e. distractor "bit to plausible based on ILT Supplied Ref (If appropriate): (i.e. ABN-##) Excluded

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Page: 136 of 206 E-32, 33 Sh 1, Rev 56 S94.1.A, Rev. 17 L NO 55.41 (b) 7 NEW 2008 exam Modified the Alternate supply is selected versus the primary supply as in original question, this changes the stem and correct answer NONE NONE 12 October 2010 EXAM BANK COMPUTER TEST EXAMINATION ANSWER KEY ILT09-1 RO questions in sample plan order __ ____________.!eqUlred): ..EXAM BANK COMPUTER TEST Page: 137 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8830 Points: 1.00 Unit 1 and 2 plant conditions are as follows: Loss of Offsite Power (LOOP) has -E-10/20, "Loss of Offsite Power" has been -All Unit 2 Emergency Diesel Generators (EDGs) have -Unit 1 EDGs have NOT -The D21 and D11 4KV Safeguard Buses have been cross-tied, D21 EDG supplying both 021and D11Safeguard -D21 EDG is currently operating at 1295 The CRS directs "1 A" RHR be placed in Suppression Pool Cooling per S51 .B.A . .. SUPPRESSION POOL COOLING OPERATION (STARTUP AND SHUTDOWN) AND LEVEL CONTROL" E-10/20. Alternate Power Supply for any 4KV Safeguard Bus Using any Diesel Generator BUS LOAD RATED KW LOAD CENTERS RATEDKW RHR Pump 950 -0114 525 Core Spray Pump 450 -D124 425 MCRChilier 400 -D134 650 ESW Pump 375 -D144 BOO RHRSW Pump 525 -D214 350 CRD Pump 200 D224 325 0234 BOO -D244 300 WHICH ONE of the following describes the ability to place "1A" RHR in Suppression Pool Cooling while maintaining Diesel Generator load per E-10/20 and S51.B.A? "1 A" RHR can NOT be placed in Suppression Pool Cooling CAN be placed in Suppression Pool Cooling for an indefinite period at the current Diesel Generator loading. CAN NOT be placed in Suppression Pool Cooling UNTIL Diesel Generator load is reduced by 300KW "1A" RHR CAN be placed in Suppression Pool Cooling but operation is limited to 2 hours0.0833 days 0.0119 weeks 0.00274 months in any 24 hour period Answer: C Answer Explanation: EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ANSWER DISTRACTOR DISTRACTOR DlSTRACTOR Question 50 Info Question Type: Status: Always select on Authorized for Time to System ID: i User-Defined ID: Cross Reference Number: Num Field Num Field Text CAN NOT be placed in Suppression Pool Cooling UNTIL Diesel Generator load is reduced by 300KW -This is the correct answer due to S51.8.A performance step 1.3 which states that "If the EDG is carrying the respective Bus, then ensure the EDG load must be below 1000 Kw prior to starting an RHR pump, to prevent loss of the other EDG loads. Conditions stated indicate EDG load of 1295 Kw which requires removal of 300 Kw load prior to starting the RHR pump. The other loading requirements for total KW 2850 continuously or 3135 KW for 2 hours0.0833 days 0.0119 weeks 0.00274 months in 24 hours1 days 0.143 weeks 0.0329 months are met. "1A" RHR can NOT be placed in Suppression Pool Cooling -This answer is incorrect because the initial loading can be reduced to support start of the RHR pump per S51.8.A. Distractor is plausible if not understood to reduce bus loading prior to RHR pump start. CAN be placed in Suppression Pool Cooling for an indefinite period at the current Diesel Generator loading -This answer is incorrect due to the starting bus load requirements of S51.8.A as discussed above. Distractor is plausible if the S51.8.A starting limit is not understood. "1A" RHR CAN be placed in Suppression Pool Cooling but operation is limited to 2 hours0.0833 days 0.0119 weeks 0.00274 months in any 24 hour period -This answer is incorrect due to E-10/20 information that indicates continuous loading limit of 2850 Kw and 3135 Kw for 2 hours0.0833 days 0.0119 weeks 0.00274 months in 24 hours1 days 0.143 weeks 0.0329 months . The current D21 load of 1295 Kw would be reduced for RHR pump start with expected total load after restoring secured loads of 2245 Kw which is < 2850 Kw. Operation would not be limited to 2 hours0.0833 days 0.0119 weeks 0.00274 months . Multiple Choice Active No No 1.00 3 3.00 8830 8830 LGSOPS0092A.3A. LGSOPS0092B.10 E 10/20 loss of offsite power 3.9 4.3 262001 A2.03 General Technical Reference with E-10/20, Attachment Revision Number: Rev E-12, sh1. Rev 14 E-13. sh1. Rev 14 Cognitive Level PRA: (i.e. Yes or No or #) 10CFR 55.43 (N/A for RO) 55.41 (b) EXAM BANK COMPUTER TEST ... Page: 139 of 206 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question History: (Le. LGS NRC-05, OYS CERT -04) Question Source: (Le. New, Bank, Modified) Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (Le. ABN-##) Excluded

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Low KA Justification (if required): i NEW NEW NEW E-10/20, Alternate Power Supply for any 4KV Safeguard Bus Using any Diesel Generator NONE N/A EXAM BANK COMPUTER TEST Page: 140 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8831 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is 100% -"1A" SBLC pump inadvertently starts -113 COOL A, B-5, CORE SPRAY LINE INTERNAL BREAK alarms WHICH ONE of the following describes the impact on the ability to detect a "1 A" or "1 B" Core Spray Loop line break inside the vessel but outside the shroud? 1A and 1B Core Spray Loops internal line break detection are BOTH functional. 1 A and 1 B Core Spray Loops internal line break detection are BOTH masked. 1 A Core Spray Loop internal line break detection is masked, 1 B Core Spray Loop internal line break detection is functional. 1A Core Spray Loop internal line break detection is functional, 1 B Core Spray Loop internal line break detection is masked. Answer: B Answer Explanation: 1A and 1 B Core Spray Loops internal line break detection are BOTH masked: This is the correct answer because there is a single Core Spray internal line break alarm to annunciate in the event of a failure of Core Spray system piping between the vessel penetration and the core shroud penetration. Excessive differential pressure between A and B Core Spray loops indicate such a failure. SLC injects to the vessel via the B COfe Spray sparger; therefore, when SLC inadvertently initiates, pressure in the B Core Spray header would be higher than pressure in the A Core Spray header, resulting in the Core Spray line internal line break alarm, masking an actual failure of Core Spray loop piping for either Core Spray system. 1A and 1B Core Spray Loops internal line break detection are BOTH functional: This is an incorrect answer because when SLC inadvertently initiates, pressure in the B Core Spray header would be higher than pressure in the A Core Spray header, resulting in high differential pressure and the Core Spray line internal line break alarm, masking an actual failure of Core Spray loop piping for either Core Spray system. 1A Core Spray Loop internal line break detection is masked. 1B Core Spray Loop internal line break detection is functional: This is an incorrect answer because when SLC inadvertently initiates, pressure in the B Core Spray header would be higher than pressure in the A Core Spray header, resulting in high differential pressure and the Core Spray line internal line break alarm, masking an actual failure of Core Spray loop piping for either Core Spray system. EXAM BANK COMPUTER TEST Page: 141 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 1B Core Spray Loop internal line break detection is masked. 1A Core Spray Loop internal line break detection is masked: This is an incorrect answer because SLC injects to the vessel via the B Core Spray sparger; therefore, when SLC inadvertently initiates, pressure in the B Core Spray header would be higher than pressure in the A Core Spray header; however. there is only a single Core Spray internal line break alarm, masking an actual failure of Core Spray loop piping for either Core Spray system. Question 51 Question Type: Multiple Status: Always select on test? Authorized for Time to Complete: 3 Difficulty: 3.00 System ID: 8831 User-Defined ID: 8831 Cross Reference Number: LGSOPS0048.1L4 Core Spray system requirements Num Field 1: 3.0

3.2 Field

211000 K3.02 Comments: General Data Technical Reference with ARC 113 COOL A, B-5 Revision Number: 8031-M-48. Rev 30 8031-M-52. Rev 50 Cognitive Level L PRA: (i.e. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank. Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

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Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 142 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order EXAM BANK COMPUTER TEST Page: 143 of 206 12 October EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8832 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is 75% -All systems in normal alignment -"1 A" Reactor Enclosure Vent Exhaust Duct Radiation Monitor is in a tripped condition The "1 B" Reactor Enclosure Vent Exhaust Duct Radiation Monitor fails Upscale. WHICH ONE of the following describes the status of Reactor Enclosure HVAC (RE HVAC) and Standby Gas treatment (SGTS)? RE SGTS A. Operating Initiated B. Operating Standby C. Isolated Initiated D. Isolated Standby Answer: C Answer Explanation: Isolated; Initiated -This is the correct answer because the REHVAC isolation logic is for channels A and B for Inboard Isolation Logic and channels C and D for Outboard Isolation Logic. With 1A RE Vent Exhaust Duct Radiation Monitor in tripped condition and 1 B RE Vent Exhaust Duct Radiation Monitor failed upscale, the logic is satisfied for the Inboard REHVAC isolation logic. The fans will trip on Low Flow due to the closure of the Inboard Series damper. The OA SGTS Fan will start with the Inboard Logic. Operating; Initiated -This is an Incorrect answer due to the information above. There are no conditions that the REHVAC would be operating with the SGTS Initiated. When the Inboard designated parallel damper opens, this causes an isolation command to the REHVAC Inboard logic. . Operating; Standby -This is an Incorrect answer due to the information above. Isolated; Standby -This is an Incorrect answer due to the information above. EXAM BANK COMPUTER TEST Page: 144 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ,-_.... , Question 52 Info I Question Type: , Status: Always select on test? Authorized for practice? i Points: Time to Complete: Difficulty: System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8832 8832 LGSOPS0048.1L4 REHV AC and 12.8 3.1 261000 K1.08 General Data I Technical Reference with M-1-B21-1090-E-023, , Revision Number: sh1, Rev 42 ! i Cognitive Level L PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 7 i Question History: (Le. LGS BANK Modified NRC-05, OYS CERT-04) Question Source: (i.e. New, BANK 560361 Bank, Modified) Revision History: Revision Bank Modified. Changed I! History: (Le. Modified stem conditions which distractor "b" to make , changed correct answer.

plausible based on OTPS !review) i ILT Supplied Ref (If NONE appropriate): (Le. ABN-##)
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I' Low KA Justification (if N/A required): EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8833 Points: 1.00 Unit 1 plant conditions are as follows: -Core axial flux is peaked at notch 24 A central Local Power Range Monitor (LPRM) detector at "C" elevation fails from a reading of 70 to a reading of 6 following selection of an adjacent Control Rod. WHICH ONE of the following describes the impact on APRM and RBM readings? APRM ODA RBM readings A. Unchanged B. Flux indicates Lower than Unchanged C. Lower Than Actual D. Flux indicates Lower than Lower Than Actual Answer: D Answer Explanation: Flux indicates Lower than Actual; Lower Than Actual: This is the correct answer because if an LPRM detector fails downscale, the affected APRM channel indication is lowered by an amount depending upon the initial LPRM detector reading. The "c" LPRM detector failed whereas the "A" LPRM detector failing will have no change due to its location in the core. The RBM channels will automatically remove any LPRM detector input signal from its local average neutron flux calculation when the input signal from that LPRM detector drops below 3%. In this case, the output fell to 6% and would be averaged, lowering the RBM output. INOP; Unchanged: This answer is Incorrect due to the APRM indication actually lowering due to discussion above and the RBM indication actually lowering due to the discussion above. There is no indication of a condition causing an INOP to Flux indicates Lower than Actual; Unchanged: This answer is partially correct due to the APRM response but incorrect due to RBM actually lowering as discussed above. INOP; Lower than actual: This answer is partially correct due to the RBM indication actually lowering but incorrect due to no indication of a condition causing an INOP to APRM. EXAM BANK COMPUTER TEST Page: 146 of 12 October 2010 EXAMINATION ANSWER IL RO questions in sample plan order Question 53 Info i Question Type: Multiple Choice Status: Active Always select on test? No i Authorized for practice? No Points: 1.00 i Time to Complete: 3 I Difficulty:- 3.00 iSystem ID: *8833 I User-Defined ID: 8833 i Cross Reference Number: LGSOPS0074A.lL7A iTopic: APRM determinations Num Field 1: 2.9 Num Field 2: 3.1 Text Field: 215005 K5.()4 Comments: General Data Technical Reference with LPRM -UFSAR Revision Number: 7.6.1.4.4.1.1.b APRM -UFSAR 7.6.1.4.5.1.1 RBM -UFSAR 7.7.1.6.2.1.1 i Lgggnitive Level L PR.A: (i.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 5 Question History: (i.e. LGS BANK NRC-05,OYSCERT-04) Question Source: (I.e. New, BANK, 556253 Bank, Modified) Revision History: Revision Bank,556253.Changed History: (I.e. Modified the order of the I distractor "b n to make distractors. Changed plausible based on OTPS correct answer from A to i review} C. ILT I! Supplied Ref (If NONE I {I.e. ABN-##) i Excluded

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Low KA Justification (if N/A I required): EXAM BANK COMPUTER TEST Page: 147 of 206 12 October 2010 I I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8834 Points: 1.00 Unit 1 plant conditions are as follows: -75% Reactor -Control Rod withdraws are in WHICH ONE of the following describes when the "B" RBM applies gain to its LPRM input signals? When a control rod is SELECTED, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%. During control rod WITHDRAWAL, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%. If the local LPRM detector signals average to a value LESS THAN the present STP from APRM 1, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%. If the local LPRM detector signals average to a value GREATER THAN the present STP from APRM 2, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%. Answer: A Answer Explanation: When a control rod is selected, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%: When a control rod is selected, the RBM calculates the average of the related LPRM detectors and calculates a gain factor that will adjust the RBM channel average to 100. The calculated value for the gain remains in effect until another control rod is selected. During control rod withdrawal, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%: The RBM calculates the average of the related LPRM detectors and calculates a gain factor that will adjust the RBM channel average to 100. However the answer is incorrect because gain is applied when a control rod is selected, and the calculated value for the gain remains in effect until another control rod is selected. EXAM BANK COMPUTER TEST Page: 148 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order If the local LPRM detector signals average to a value GREATER THAN the present STP from APRM 1, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%: For conservatism, the gain adjustment value will never be less than 1; therefore, if the LPRM input signals average to a value greater than the present simulated thermal power (STP) from the reference APRM, the RBM channel average flux is NOT scaled down but is maintained at the higher value. The answer is also incorrect because APRM 1 is the primary reference APRM for RBM channel A. If the local LPRM detector signals average to a value GREATER THAN the present STP from APRM 2, gain is applied to the average of the LPRM detector inputs until the RBM channel average is equal to 100%: APRM 2 is the primary reference APRM for RBM channel B. APRM 2 is bypassed, so the first alternate APRM provides STP to the B RBM. APRM 4 is the first alternate reference APRM for RBM channel B. If the LPRM input signals average to a value greater than the present simulated thermal power (STP) from the reference APRM, the RBM channel average flux is NOT scaled down but is maintained at the higher value. Question 54 Question Type: Multiple Status: . Always select on test? Authorized for practice? Points: Time to Complete: Difficulty: System 10: User-Defined 10: Cross Reference Number: Topic: LPRM input to Num Field 1: Num Field 2: Text Field: 215002 General Data Technical Reference with LPRM -UFSAR Revision Number: 7.6.1.4.4.1.1.b RBM UFSAR 7.7.1.6.2.1.1 I

Cognitive L PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for ROJ 55.411b) 6
Question History: (Le. LGS Bank i NRC-05, OYS CERT-04) I Question Source: (Le. New, Bank Bank, Modified)

L-. EXAM BANK COMPUTER TEST Page: 149 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (Le. ABN-##J Excluded

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Low KA Justification (if required): Bank. 556253. Changed the order of the distractors. Changed correct answer from D to A. Modified stem and distractors extensively to improve clarity and discrimination. NONE NONE N/A EXAM BANK COMPUTER TEST Page: 150 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8835 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is -A "A2." RPS solenoid power supply fuse has -Group "A2" indicating light on 1 OC603 is RPS UPS panel 1 BYi60 is inadvertently de-energized as a result of an under frequency condition WHICH ONE of the following identifies the status of the Control Rods and Scram Discharge Volume (SDV) Vent and Drain valves ten (10) seconds after 1 BY160 de-energizes? Control Rods SDV Vents and Drains A. All Control Rods Open B. 45 Control Rods Closed C. 45 Control Rods Open D. AU Control Rods Closed Answer: C Answer Explanation: 45 Control Rods scram and SOV vents and drains remain open: RPS UPS panel 1 BY160 powers the 'B' scram solenoids and the 'B' side RPS logic. The RPS logic and scram solenoid vales are de-energized to operate. When 1 BYi60 is de-energized, the 'B" RPS scram solenoids are de-energized. With the RPS "A2." blown fuse 1/4 of the "A" RPS scram solenoids are also de-energized. With 1/4 of the scram valves for "A" RPS de-energized and all 4 "B" RPS channel scram solenoids deenergizing due to the loss of 1BYi60, 47 Control Rods have a "A" and "B" RPS loss of power, and will scram. 45 Control Rods scram and SOV vents and drains close: Same RPS concept as described in Answer. The SDV vent and drains are fail closed on a loss of RPS power supply. The 1 BYi60 power supply is lost, however the "A" RPS has only one half of a loss of power which will not affect the vent and drain valves. To close the SDV vent and drain valves will require a loss of either "Ai" or "A3" power supply. This will be a loss of both channels of RPS which will scram all control rods and close the SDV vent and drains. All Control Rods scram and SOV vent and drains close: When iBYi60 is de-energized, the 'B" RPS scram solenoids are de-energized; however, iAY160 powers the 'A' scram solenoids and RPS logic With the RPS "A2." blown fuse 1/4 of the "A" RPS scram solenoids are also de-energized. With 1/4 of the scram valves for "A" RPS de-energized. To insert all control rods both RPS "A" and "B" must be deenergized. EXAM BANK COMPUTER TEST Page: 151 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order All Control Rods scram and SDV vent and drains remain open:: When 1 BY160 is de-energized, the 'B" RPS scram solenoids are energized. The answer is also incorrect because RPS UPS panel 1AY160 powers the 'A' scram solenoids and RPS logic, which remain energized. With the RPS "K2" blown fuse 1/4 of the "A" RPS scram solenoids are also de-energized. With 1/4 of the scram valves for "A" RPS de-energized. To insert ali control rods both RPS "A" and "B" must be deenergized. Question 55 Info Question Type: Multiple Choice . Status: Active Always select on test? No i Authorized for practice? No Points: 1.00 i Time to Complete: 3 Difficulty: 3.00 i . System ID: 8835 User-Defined ID: 8835 Cross Reference Number: LGSOPS0071.2D Control Rod effect with partial RPS power loss with 1 BY 160 Topic: deenergized Num Field 1: 3.6 Num Field 2: 3.7 Text Field: 201001 K2.02 Comments: General Data Technical Reference with E-1BY160, Rev. 18 Revision Number: E-32, Sh 1, Rev 56 Cognitive Level L PRA: (i.e. Yes or No or #) NO

10CFR 55.43 (N/A for 55.41 (b) 7 Question History: (i.e. LGS NEW NRC-OS, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified)

Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

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Low KA Justification (if N/A required): J . EXAM BANK COMPUTER TEST Page: 152 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8768 Points: 1.00 WHICH ONE of the following describes a component malfunction that could result in an automatic initiation of the Fire Protection System, and the Potential Hazard? Fire Protection System Malfunction Potential Hazard Failed Sprinkler Head, Water spraying on energized Aux Boiler Enclosure electrical equipment Wetpipe System Failed Heat Detector, C02 will displace Oxygen Cable Spreading Room Cardox System Failed Sprinkler Head, Water spraying on energized D12 Diesel Generator electrical equipment Pre-action Sprinkler System Failed Heat Detector, Halon will displace Oxygen Remote Shutdown Panel Halon System Answer: A Answer Explanation: Failed Sprinkler Head, Aux Boiler Enclosure Wetpipe System; Water spraying on energized electrical equipment: Correct because sprinkler head failure with Wetpipe system will cause water flow with hazard caused for adjacent energized electrical panels. Failed Heat Detector, Cable Spreading Room Cardox System; C02 will displace Oxygen: Incorrect due to failed heat detector will not actuate Cardox. (Partial correct for C02 displace Oxygen) Failed Sprinkler Head, 012 Diesel Generator Pre-action Sprinkler; Water spraying on energized electrical equipment: Incorrect due to failed Sprinkler head will not result in a Pre-action system actuation. A heat detector would also be needed to actuate the pre-action system. EXAM BANK COMPUTER TEST Page: 154 of 12 October 2010

EXAMINATION ANSWER IL T09-1 RO questions in sample plan order r--______ Failed Heat Detector, Remote Shutdown Panel System; Halon will displace Oxygen: Incorrect due to single failed heat detector will not initiate suppression. (Partial correct for Halon will Question 56 Info Question MllltinlF! Status: IAlways select on test? ,.e.uthorized for eractice? No Points: 1.00 3 Difficulty: __2.00 System 8768 -------User-Defined 10: 8768 . Cross Reference Number: LGSOPS022.05 Topic: Fire Potection Num Field 1: Num Field 2: General Data Technical Reference with -M-22 Revision Number: S22.1.B S22.1.C Cognitive Level L PRA: {I.e. Yes or No orJ!.L. N {N/A--.Jor RoT-55.41 (h)Question History: (I.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (I.e. New, NEW Revision History: Revision N/A History: (i.e. Modified distractor "b" to make plausible based on OTPS Supplied Ref (If NONE {i.e. ABN-##) __ Excluded

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(i.e. NONE Ensure Low KA Justification (if N/A EXAM BANK COMPUTER TEST Page: 155 of -12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8836 Points: 1.00 Unit 1 plant conditions are as follows: -SGO-206-1 (Unit 1 RE) is -SGO-506-2 (Unit 2 RE) is -SGO-206-3 (Refuel Floor) is -Unit 2 RF Ventilation is in -Zones 1 and 3 HVAC Isolation Interlocks are WHICH ONE of the conditions will cause an isolation of Unit 1 RE HVAC and Unit 1 RF HVAC? A. Unit 1 Refuel Floor Vent Exhaust Rad level at 1.8 mr/hr B. Unit 2 Refuel Floor Vent Exhaust Rad level at 2.2 mr/hr C. Unit 1 Reactor Enclosure Vent Exhaust Rad level at 1.2 mr/hr O. Unit 2 Reactor Enclosure Vent Exhaust Rad level at 2.4 mr/hr Answer: B Answer Explanation: Unit 2 Refuel Floor Vent Exhaust Rad level at 2.2 mr/hr: Correct because rad level is above the isolation setpoint of 2.0 mrfhr and an isolation condition on either U/1 or U/2 Refuel Floor will cause an Isolation of RF ventilation on both units. With the SGOs open and the Zone Isolation Interlocks cross-tied between Zone 1 and Zone 3, this will also Isolate the Unit 1 Reactor Enclosure HVAC. I-:::-___

__--_i Unit 1 Refuel Floor Vent Exhaust Rad level at 1.8 mr/hr: Incorrect due to Rad level condition below the isolation setpoint for Refuel Floor. Unit 1 Reactor Enclosure Vent Exhaust Rad level at 1.2 mr/hr: Incorrect due to Rad level below the isolation setpoing of 1.35 mr/hr for Reactor Enclosure. 2.4 mr/hr: Incorrect due to no cross-tie to either Refuel Floor or Unit 1 Reactor Enclosure Vent zones although the Rad level is above the setpoint. L.....___* ______.___._.*.____.*._____***__._________* EXAM BANK COMPUTER Page: 156 of 206 . EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 57 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8836 8836 LGSOPS0078.IL3 REHVAC operations 3.7 3.8 288000 K4.02 General Data Technical Reference with M-1-B21-1090-E-023, Revision Number: sh1, Rev 42 P&ID M-76 Cognitive Level L PRA: (i.e. Yes or No or #) NO 10CFR 55.43 (I'J/A for RO) 55.41 (b) 7 Question History: (i.e. LGS BANK NRC-05, OYS CERT-04) Question Source: (i.e. New, Bank,557532 Bank, Modified) Revision History: Revision Changed sequence of History: (i.e. Modified distractors. Changed distractor "b" to make answer from A to B. plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

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Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 157 of 206 12 October 2010 58 10: 8837 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is 90% -EHC Load Set is 105% -EHC Load Limit is 105% -Max Combined Flow is 115% -Pressure Set is 960 psig The output of PT-001-101A (A EHC MAIN STEAM PRESSURE) fails to 993 psig EHC LOGIC SlUM Lt.::\Load_CIf MOT ...dR....R.......'--_-j '-----..., I--=:W_w.:'!i .cp WHICH ONE of the following identifies the Control and Bypass valve .cONTROL VALVE BYPASS A. 100% steam flow 3% steam flow B. 100% steam flow 10% steam flow C. 105% steam flow 3% steam flow D. 105% steam flow 5% steam flow Answer: 0 Answer Explanation: EXAM BANK COMPUTER TEST Page: 1 of 3 13 October 2010 105% steam flow; 5% steam flow -This answer is correct because sensed Steam Pressure fails up to 993 psig on the Pressure Controller is in control, the total steam pressure signal goes up by a multiplying of 3.33 times or to 110%. The EHC Load Set is at 105%> so that this is maximum amount allowed to pass through the Control valves. remaining 5% must pass through the Bypass Valves as long as the Combined Flow Limit is not 100% steam flow; 3% steam flow -This answer is incorrect because the pressure input failure causes a demand for flow greater than 100%. Typically, 990 psig corresponds to 100% and 993 psig corresponds to 110% due to the 3.33%/psig scaling. The remaining steam flow demand would have to pass through the Bypass Valves up to the Max Combined flow Limit. The distractor is plausible if the candidate believes that the pressure signal in excess of 990 psig would be converted to Bypass Valve percent directly. 100% steam flow; 10% steam flow This answer is incorrect even though the correct scaling of excess pressure to %f1ow is used, steam flow was not controlled through the Control valves up to the Load Set 105% steam flow; 3% steam flow This answer is incorrect because percent steam flow to pressure scaling factor is not accounted for regards to BPV position. The distractor is plausible if the believes that the excess pressure directly converts to excess steam directly to the Question 1 Info Question Type: Multiple I.."nOlce Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: 3 4.00 System 10: User-Defined 10: Cross Reference Number: LGSOPS003'1 EHC operation Num Field 1: 3.8 Num Field 2: 3.7 Text 241000 A1.07 Comments: General Data a ! Technical Reference with I OP AID S-95-008 Revision Number: ! P&ID 8031-M-1, sh1, Rev 56 I ! Cognitive Level H '-PRA: (i.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.4jJ.b) 5 Question History: (I.e. LGS New NRC-05, OYS CERT-04) Question Source: (I.e. New, New Bank, Modified) EXAM BANK COMPUTER TEST Page: 2 of 13 October 2010 I I Revision History: Revision History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (i.e. ABN-##) Excluded

Reference:

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Low KA Justification (if required): Associated objective(s): 2010 IL T QUESTION HOLDER New Attached EHC simplified diagram NONE N/A EXAM BANK COMPUTER TEST Page: 3 of 3 13 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8839 Points: 1.00 Unit 1 plant conditions are as follows: -LOCA is in progress -Drywell temperature is 260°F -"1A" Loop of RHR is in Suppression Pool Cooling -"'18" Loop of RHR is in Drywell Spray -"1A" and "18" Loop of RHRSW is in service -Suppression Pool temperature is 105°F and dropping slowly -Drywell pressure 14.6 psig and dropping quickly The "8" RHRSW Radiation monitor fails, resulting in an INOP trip WHICH ONE of the following describes the impact on Suppression Pool temperature and Drywell pressure? Drywell Pressure A. Continues Continues dropping 8. Continues Will stabilize or rise C. Will stabilize or Continues dropping D. Will stabilize or Will stabilize or rise Answer: A Answer Explanation: Continues droppingl Continues dropping: A trip of the 18 RHRSW process radiation monitor trips the "8" RHRSW pumps, resulting in a loss of "8" RHRSW ONLY. The "An loop of RHR is unaffected. The effectiveness of drywell spray is maintained due to the significance impact of evaporative cooling. Continues droppingl Will stabilize or rise: A trip of the 18 RHRSW process radiation monitor results in a loss of "8" RHRSW OI\lL Y. RHRSW is lost to the "8" RHR loop; however, the effectiveness of drywell spray is maintained due to the significance impact of evaporative cooling. Will stabilize or rise, Continues dropping: If the "An RHRSW pumps had tripped, suppression pool cooling would be negatively impacted by the loss of RHRSW; however, a trip of the 18 RHRSW process radiation monitor results in a loss of "8" RHRSW ONLY, and the "An loop of RHR is unaffected. RHRSW is lost to the "8" RHR loop; however, the effectiveness of drywell spray is maintained due to the significance impact of evaporative cooling. EXAM BANK COMPUTER TEST Page: 161 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Will stabilize or rise; Continues dropping: A trip of the 1 B RHRSW process radiation monitor results in a loss of "B" RHRSW ONLY and the "A" loop of RHR is unaffected. RHRSW is lost to the "B" RHR loop; however, the effectiveness of drywell spray is maintained due to the significant impact of evaporative cooling. Question 59 Info Question Type: Multiple Status: Always select on test? Authorized for practice? Points: Time to Complete: Difficulty: System ID: User-Defined ID: Cross Reference Number: Topic: DW and SP spray without Num Field Num Field ¥a Text Field: 226001 K6.11 Comments: General Data Technical Refel with T-102 BASES, Rev. 22. Revision Number: Step PC/P-9 i Cognitive Level H PRA: (I.e. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (I.e. LGS Bank. Modified NRC-OS, OYS CERT-04) Question Source: (I.e. New. Bank, LIMERICK LOT Bank, Modified) 6714 Revision History: Revision Modified stem and History: (I.e. Modified distractors significantly to distractor "b" to make align question with KIA. plausible based on OTPS Changed sequence of review) distractors. Changed wording of answer and distractors to add clarity. Changed answer from B to A. ILT Supplied Ref (If NONE appropriate): (I.e. ABN-##) Excluded

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Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 162 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8840 Points: 1.00 Unit 1 plant condition are as follows: -Reactor power is 100% -Control Rod 22-37 is a position 48 -Rod select key is in the "No Rod Select" position -The SCRAM outlet valve for control rod 22-37 fails open WHICH ONE of the following identifies the response of Control Rod 22-37 and impact on SOV level? Control Rod SOV level A. Control Rod drifts fun SOV level remain unchanged B. Control Rod drifts full SOV level goes up C. Control Rod Remains at position 48 SOV level remain unchanged O. Control Rod Remains at position 48 SOV level goes up Answer: A Answer Explanation: Control Rod drifts full in; SOV level remain unchanged -This answer is correct because of the pressure differential from the Reactor to the SOV (vented) causing flow and movement of the CROM piston with the Scram Outlet valve failed open. There is no Scram signal so the SOV vents and drains remain open with the flow bypassing secondary containment to the Rad Waste Equipment Drain Tank. Control Rod drifts full in; SOV level goes up -This answer is partially correct due to Control Rod drifting full in with flow path for CRDM piston but incorrect because of no isolation on the SDV that would allow the leakage path to increase SOV level. Control Rod Remains at position 48; SOV level remain unchanged This answer is partially correct due to the SOV level indication however is incorrect because with the Scram Outlet valve failed open, about a 1000 psig dP will initiate Control Rod inward motion and flow to the SDV (vented). Control Rod Remains at position 48; SOV level goes up -This answer is totally incorrect due to discussion of dP causing Control Rod Motion and flow into the SOV and due to the drain path to Radwaste as discussed above. EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 60 Info I I Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8840 8840 LGSOPS0047.1L7 CRD Impact on power 2.6 2.7 201003 K5.01 General Data Technical Reference Revision Cognitive Level PRA: (I.e. Yes or No or #) 10CFR 55.43 (N/A for RO) Question History: (I.e. LGS NRC-05, OYS CERT-04) Question Source: (I.e. New, Bank, Modified) Revision History: Revision History: (i.e. Modified distractor "b" to make plausible based on OTPS . review) ILT Supplied Ref (If appropriate): (I.e. ABN-##) Excluded

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Low KA Justification (if required): ON-104 BASES, Rev. 41 L NO 55.41 (b}5 NEW NEW NEW NONE NONE N/A .. EXAM BANK COMPUTER TEST Page: 165 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order ID: 8841 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is 100%. -An Equipment Operator reports that Hydrogen Injection System H2 flow is elevated to five times normal levels. WHICH ONE of the following describes the expected plant response and lists the procedure the operator must enter? A rise in Offgas System temperatures ONLY: Enter ON-103, CONTROL OF SUSTAINED COMBUSTION IN THE OFFGAS SYSTEM. A rise in Offgas System hydrogen concentration ONLY: Enter ON-103, CONTROL OF SUSTAINED COMBUSTION IN THE OFFGAS SYSTEM. A rise in Main Steam Line radiation ONLY: Enter ON-102, AIR EJECTOR DISCHARGE OR MAIN STEM/I HIGH RADIATION. A rise in Reactor Water Conductivity ONLY: Enter ON-116, HIGH REACTOR WATER CONDUCTIVITY. Answer: C Answer Explanation: A rise in Main Steam Line radiation ONLY: Enter ON-102, AIR EJECTOR DISCHARGE OR MAIN STEAM HIGH RADIATION.: The primary mechanism by which H2 injection causes a temporary rise in MSL & consequently SJAE radiation monitor levels is the transition from oxidizing to reducing conditions in the reactor which cause a temporary reverse in the transport of N 13, affecting the radiation monitors. This transition occurs between 5 and 20 SCFM of H2.lf a Hydrogen Water Chemistry System malfunction exists, ON-102 directs tripping of the HWC Injection System. After HWC flow rates stabilize the SJAE radiation levels should return to normal levels or lower in approximately 20 minutes. A rise in Offgas System temperatures ONLY: Enter ON-103, CONTROL OF SUSTAINED COMBUSTION IN THE OFFGAS SYSTEM: Combustion in the Offgas System is indicated by a sudden drop in Offgas System hydrogen concentration. A rise in Offgas System hydrogen concentration ONLY: Enter 103, CONTROL OF SUSTAINED COMBUSTION IN THE OFFGAS SYSTEM: The volume of Hydrogen injected via the HWC Injection System is insignificant in comparison with the volume of hydrogen and Oxygen generated in the reactor and evacuated from the Main Condenser via the SJAEs. EXAM BANK COMPUTER TEST Page: 166 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order A rise in Reactor Water Conductivity: Enter ON*116, HIGH REACTOR WATER CONDUCTIVITY. Conductivity would only rise due to activated resin or other organic breakdown products passing through the reactor. Question 61 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: 3 3.00 System 10: 8841 User-Defined 10: 8841 Cross Reference Number: LGSOPS1550.IL 1 Hydrogen concentration effect

Num Field 1: 2.6 . Num Field 2: 2.8 Text Field: 272000 A2.07 Comments:

General Data Technical Reference with ON*102 BASES, Rev. 29 Revision Number: Cognitive Level H PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 5 Question History: (I.e. LGS NEW NRC-OS, OYS CERT-04) Question Source: (I.e. New, NEW Bank, Modified) Revision History: Revision NEW History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE . appropriatel:iLe. ABN-##) Excluded

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Low KA Justification (if N/A required): I EXAM BANK COMPUTER TEST Page: 167 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8842 Points: 1.00 Unit 1 plant conditions are as follows: -Drywell pressure is 8.5 psig and rising slowly -RPV pressure is 470 psig and lowering -RPV level lowered to a minimum of -65 inches, before recovering to current level of +35 inches. -"1A" RHR is in Suppression Pool Spray per T-225 -Pressure upstream of HV-51-1 F017A is 285 psig WHICH ONE of the following describes the response of the RHR Suppression Pool Spray Valve (HV-51-1 F027A) and LPCllnjection Valve (HV-51-1F017A) as pressure continues to lower? HV-51-1F017A A. Closes at 455 psig Opens at 359 psig B. Closes at 359 psig Opens at 359 psig C. Closes at 359 psig Opens at 455 psig D. Closes at 455 psig Opens at 455 psig Answer: A Answer Explanation: Closes at 455 psig; Opens at 359 psig -This is the correct answer because LPCI Initiation signal is 1.68 psig drywell pressure and::; 455 psig reactor pressure. This will control HV-51-'1 F027A (and HV-51-1 F024A) to auto close in response to the LOCA signal. As RPV pressure continues to lower, HV-51-1F017A will auto open in response to a LPCI initiation signal when the differential pressure across the valve is < 74 psid. This would be at a minimum pressure of 359 psig but probably higher due to the higher pump head without SP spray flow. Closes at 359 psig; Opens at 359 psig -This answer is partially correct due to the approximate opening pressure of the HV-51-1 F017 A valve at 74 psid but incorrect due to the wrong LOCA response for OW pressure> 1.68 psig and RPV pressure < 455 psig. EXAM BANK COMPUTER TEST Page: 168 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order DISTRACTOR DISTRACTOR Question 62 Info Question Type: Status: Closes at 359 psig; Opens at 455 psig -This answer is totally incorrect due to wrong LOCA Initiation signal and wrong pressure to satisfy the LPCI Injection interlock. The LOCA is 1.68 psig drywell pressure and :s; 455 psig reactor pressure which closes the HV-51-1 F027A (and HV-51-1 F024A) valve and the LPCI injection valve initiation signal. HV-51-1 F017A will auto open in response to a LOCA initiation signal and the differential pressure across the valve is < 74 psid or a minimum pressure of 359 psig based on the conditions given. See discussion above for the answer. Closes at 455 psig; Opens at 455 psig -This answer is partially correct due to the LOCA signal response when OW Pressure is 1.68 psig and RPV pressure is :s; 455 psig but incorrect due to the response of the LPCI injection valve that responds to a LOCA signal and 74 psid across the HV-51-1 F017 A valve to initiate flow. The highest expected pressure for the LPCI injection to open with the RHR pump running on Min flow is about 395 psig. Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8842 8842 LGSOPS0051.IL8F RHR valve initiation requirements 3.4 3.3 230000 A3.01 General Data Technical Reference Revision Cognitive PRA: (i.e. Yes or No or 1 OCFR 55.43 (I\I/A for Question History: (i.e. NRC-05, OYS Page: 169 of 206 8031-M-1-E11-1040-005, sh1, Rev 25 8031-M-1-E11-1040-015, sh1, Rev 34 8031-M-1-E11-1040-016, sh1, Rev 33 H NO 55.41 (b) 7 BANK 12 October 2010 EXAM BANK COMPUTER TEST EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question Source: (Le. New, BANK Bank, Modified) Revision History: Revision BANK. History: (Le. Modified distractor ubI! to make plausible based on OTPS I review) I ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

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Low KA Justification (if N/A

required):

EXAM BANK COMPUTER TEST Page: 170 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8843 Points: 1.00 Plant conditions are as follows: -Both CREFAS subsystems are OPERABLE -"A" CREFAS fan hand-switch is in AUTO -"B" CREFAS fan hand-switch is in STBY A manual chlorine isolation has been initiated on all four channels per S78.B.A, MANUAL INITIATION OF CONTROL ROOM RADIATION OR CHLORINEITOXIC CHEMICAL ISOLATION. -The "CIt chlorine isolation channel failed to trip WHICH ONE of the following describes the status of the "A" and liB" CREFAS fans two (2) minutes later based on the above conditions? 'A' CREFAS 'B' CREFAS FAN A. Not running B. Not Not running C. Running D. Not Running Answer: D Answer Explanation: Not running; Running -This is the correct answer because the CREFAS initiation logic for the Chlorine Isolation requires both channels A and C for the A subsystem and the Fan only starts off of the C Channel actuation logic. The conditions stated were for the Channel C Isolation Channel failure. This prevents the OA CREFAS fan from starting on Chlorine. Because there were no indications of failures on the B subsystem the OB CREFAS fan in Standby would start after a time delay sensing the Auto fan not running. Running; Not running -This answer is incorrect due to the conditions given with the failure of the C channel preventing start of the OA CREFAS fan from the A Subsystem logic. The OB CREFAS fan would be expected to start after time delay in Standby sensing the OA fan low flow (not running). Not running; Not running -Th answer is partially I DISTRACTDR correct due to identifying that the OA CREFAS fan will not

start with a failure of the C channel logic but incorrect due to information above for Standby OB CREFAS fan start. I EXAM BANK COMPUTER TEST Page: 171 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Running; Running -This answer would be correct for identifying that the OB CREFAS fan would in Standby on Manual Chlorine Isolation logic but due to indicating the OA CREFAS fan running with failed channel isolation logic. With one fan in Auto and the in Standby there is no condition that would cause fans to run at the same Question 63 Info Question Type: Multiple Choice . Status: Active *Always select on No Authorized for practice?

No Points: 1.00 Time to Complete: 3 --::::--=-"" 3.00 System 10: User-Defined 10: Cross Reference Number: Topic: Num Field 1: Num Field 2: Text Field: 290003 I General Data . Technical Reference with Bechtel Drawing, E-495, Revision sh1, Rev 18 E-496 sh 1 & 4 ARC-MCR-002-A-2 S78.8.A Cognitive Level H PRA: (I.e. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b)7 Question History: (I.e. LGS BANK NRC-05, OYS CERT-04) Question Source: (I.e. New, BANK, 561566 , Bank, Modified) Revision History: Revision BANK, 561566. Changed History; (i.e. Modified order of distractors. distractor "b" to make Changed answer from B plausible based on OTPS to D. review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

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I Low KA Justification (if N/A required): , EXAM BANK COMPUTER TEST Page: 172 of 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order EXAM BANK COMPUTER TEST Page: 173 of 206 12 October EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8844 Points: 1.00 LGS Unit 2 plant conditions are as follows: -OPCON 5 -Fuel Shuffle is in progress for Unit 2 -Fuel Pool Cooling (FPC) is in service with "1 A" and "1C" FPC pumps running The following Annunciators are received: -212 Cleanup K-5, Fuel Pool Cooling Pumps -212 Cleanup 1-5, Fuel Storage Pool Hi/Low EO reports Both Fuel Pool Coaling pumps have tripped, and confirms lowering Fuel Pool Level WHICH ONE of the following correctly describes the procedures required to be entered for the above conditions? ON-125, Loss of Fuel Pool Cooling ONLY ON-120, Fuel Handling Problems AND ON-111, Loss of Secondary Containment ONLY ON-125, Loss of Fuel Pool Cooling AND ON-120, Fuel Handling Problems ONLY ON-125, Loss of Fuel Pool Cooling AND ON-120, Fuel Handling Problems AND ON-111, Loss of Secondary Containment Answer: C Answer Explanation: ON-125, Loss of Fuel Pool Cooling AND ON-120, Fuel Handling Problems ONLY: Correct because ON-125 is entered on Indication of loss of capability to maintain Fuel Pool temperature, which is appropriate due to loss of FPC pumps. ON-120 is entered due to UnantiCipated reduction of Spent Fuel Pool Water Level. ON-125, Loss of Fuel Pool Cooling ONLY: Incorrect due to being partially correct. ON-125 is entered, BUT ON-120 entry is also required. ON-120, Fuel Handling Problems AND ON-111, Loss of Secondary Containment ONLY: Incorrect due to being is partially correct, BUT lowering level in the fuel pool does not impact Secondary Containment. ! i EXAM BANK COMPUTER TEST Page: 174 of 12 October 2010 --EXAMINATION ANSWER IL T09-1 RO questions in sample plan order ON-125, Loss of Fuel Pool Cooling AND ON-120, Fuel Handling Problems AND ON-111, Loss of Secondary Containment: Incorrect due to being partially correct, see above. Question 64 Info Question Type: Multiple Choice Status: Active select on test? No Authorized for practice? No *Points: 1.00 i Time to 3 !Difficult:r:: 3.00 iSystem 10: 8844 I User-Defined 10: 8844 Cross Reference Number: LGSOPS0053.IL5 Fuel Pool Cooling, Abnormal procedure entry INUm Field 1: 3.6 Num Field 2: 4.6 Text Field: 233000 2.4.4 Comments: General Data Technical Reference with ON-120, Revision Number: ON-125 Cognitive Level L PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 10 Question History: (Le. LGS . NEW NRC-05, OYS CERT-04) . Question Source: (Le. New, NEW Bank, Modified) Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS reviewl ILT . Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 175 of 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8845 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is -127 OFF GAS 1, A-2, 1 Unit HEPA Filters Trouble alarms on differential pressure.

-Charcoal Adsorber Outlet flow on FR69-115 on 10C673 indicates 0 SCFM. -Off-Gas System pressure on PR69-115 on 10C673 is rising. WHICH ONE of the following describes the expected response of PCV-141A, RECIRC TO COND, and the expected impact on Main Condenser vacuum? Main Condenser Vacuum Opens Stabilizes at a lower value (less vacuum), Main Turbine remains on line Closes Stabilizes at a lower value (less vacuum) Main Turbine remains on line Opens Continues to degrade until the Main Turbine trips on low Condenser vacuum Closes Continues to degrade until the Main Turbine trips on low Condenser vacuum Answer: C Answer Explanation: Opens; Continues to Degrade Until the Main Turbine trips on low Condenser vacuum -This is the correct answer because PIC-07-141A in Auto is normally expected to open to Recirc pressure to the condenser at 7.0 psig (70% open). At higher backpressures PCI-07 -141A would be full open. Indications are that the Off Gas HEPA filter is fouled and off gas flow has gone to zero. There is no flowpath so over time, non-condensable gasses will accumulate in the main condenser, and vacuum will degrade (lowering vacuum). Eventually, the First Stage Air Ejector Condenser will become air bound and the Steam Jets will stall. Without the ability to remove non-condensable gasses from the condenser, the absolute pressure will rise until eventually the Main Turbine trips on High Back Pressure (lOW condenser vacuum). Opens; Stabilizes at a lower value (less vacuum), Main Turbine remains on line -This answer is partially correct for the response of the PIC*07 -141 A valve to fully open in Auto due to high back pressure but incorrect for assessment of the Main Turbine to remain on line with no Condenser Air Removal. EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Closes; Stabilizes at a lower value (less vacuum), Main Turbine remains on line -This answer is totally incorrect due to indicating that the PIC-07 -141 A recirculation valve closing on high back pressure and for assessing that the Main Turbine would remain on line with no Condenser Air Removal. Closes; Continues to Degrade Until the Main Turbine trips on low Condenser vacuum -This answer is partially correct for assessing the Main Turbine trip on degrading vacuum condition but incorrect due to indicating that the PIC-O?-141 A recirculation valve closing on high back pressure. Question 65 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: 3 3.00 System 8845 User-Defined ID: 8845 Cross Reference Number: LGSOPS0069.7 A Main Condenser vacuum loss Num Field 1: 3.5 Num Field 2: 3.5 Text Field: 271000 K3.01 Comments: General Data Technical Reference with P&ID M-69, sh 1, Rev 48 Revision Number: P&ID M-70, sh 2, Rev 32 P&ID M-07, sh 1, Rev 47 Cognitive Level H PRA: (Le. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (i.e. LGS Bank NRC-05, OYS CERT-04) Question Source: (Le. New, Bank,561322 Bank, Modified) EXAM BANK COMPUTER TEST Page: 177 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision Modified stem to indicate History: (Le. Modified HEPA filter blockage distractor "b" to make sufficient to result in a plausible based on OTPS loss of ability to evacuate review) non-condensable gasses from the main condenser, ultimately resulting in degrading condenser vacuum. Modified stem and distractors to require interpretation of 141 A status as a result of rising Off gas pressure. I Changed correct answer ! I from D to C. ILT Supplied Ref (If ! NONE appropriate): (Le. ABN-##) Excluded

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Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 178 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8852 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor startup in progress -Rods are being withdrawn per S73.1.A, "Normal Operation of the Reactor Manual Control System" -Control Rod 30-31 is at position 30 and is being continuously withdrawn to position 44. WHICH ONE of the following identifies the earliest indicated notch position at which the continuous withdrawal signal is REQUIRED TO BE REMOVED per S73.1.A to ensure that the Control Rod stops at the target position? A. 44 B. 42 C. 40 D. 36 Answer: C Answer Explanation: 40: Correct because per S73.1.A NOTE number 3 in section 4.3, Continuous Withdraw (Non Channel Distortion Rod), the withdraw signal is removed two notches before its target position. Single notch withdraw(s) are then performed to place the control rod in its target position. Starting at position 30 with target position 44, the required stop point is at notch position 40. 44: Incorrect due to contrary to procedure and per information above. 42: Incorrect due to contrary to procedure and per information above. 36: Incorrect due to a lower position than the required position for stopping continuous withdrawal. EXAM BANK COMPUTER TEST Page: 179 of 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 66 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8852 8852 LGSOPSOO73A.lL4B Control Rod movement 4.6 4.6 2.1.20 General Data Technical Reference with S73.1.A, Rev 47 Revision Number: Cognitive Level L PRA: (I.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 6 Question History: (I.e. LGS Bank NRC-05, OYS CERT-04) Question Source: (I.e. New, Bank, 55460 Bank, Modified) Revision History: Revision Bank, 55460. Changed History: (I.e. Modified order of distractors. distractor "b" to make Changed correct answer plausible based on OTPS from B to A. review) Supplied Ref (If appropriate): (I.e. Excluded

Reference:

(I.e. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 180 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 67 10: 8853 Points: 1.00 Plant conditions are as follows: -MCR has been

-Cooldown has commenced on both -Unit 1 RPV pressure is 665 psig at the -Unit 1 RPV water level indicates +30 inches at the Unit 1 RPV water level is held constant and cooldown rate established at the MAXIMUM allowed (100 0 FI hr) SE-1 ATTACHMENT 3 100 'E/Hr COOLOOWN RATE NOMINAL COOLDO\I\IN RATE NOTE SLOPE OF COOLDO\I\IN RATE CANNOT BE STEEPER T HAN TYPICAL LNE SHO\I\IN. oK 50 <:10CoFklrT >10 °FJhr RPVCOOLD()\.'\.4\l RATE E M 40P (OF) --c---r-r-----r 30 0 SHUTDOV\tNCOOLING } PERMISSIBLE 20 0 o 1 2 3 TIME (hours) WHICH ONE of the following identifies the EARLIEST time Shutdown Cooling can be initiated? SOC Initiation A. 2.5 hours0.208 days 0.0298 weeks 0.00685 months from now B. 2.25 hours1.042 days 0.149 weeks 0.0342 months from now C. 2.0 hours0 days 0 weeks 0 months from now O. 1.75 hours3.125 days 0.446 weeks 0.103 months from now Answer: 0 Answer Explanation: EXAM BANK COMPUTER TEST Page: 181 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 1.75 hours3.125 days 0.446 weeks 0.103 months from now: 665 psig corresponds to 679 pSia. From steam tables, 679 psia is approximately 500°F. From Attachment 3, a line starting at 500°F with the same slope as the "Normal Cooldown Rate" would intersect the "Shutdown Cooling Permissible" line at the 1.75 hour point

2.0 hours0 days 0 weeks 0 months

from now: From Attachment 3, a line starting at 500°F intersecting the "Shutdown Cooling Permissible" line at the 2.0 hour pOint would have a slope less steep than the "Normal Cooldown Rate." DISTRACTOR 2.25 hours1.042 days 0.149 weeks 0.0342 months from now: From Attachment 3, a line starting at 500°F ! intersecting the "Shutdown Cooling Permissible" line at the 2.25 hour point would have a slope less steep than the "Normal Cooldown Rate."

2.5 hours0.208 days 0.0298 weeks 0.00685 months

from now: From Attachment 3, a line starting at 500°F intersecting the "Shutdown Cooling Permissible" line at the 2.5 hour point would have a slope much less steep than the "Normal Cooldown Rate." Question 67 Question Type: Multiple Status: Always select on test? Authorized for practice? Points: Time to Complete: Difficulty: System ID: User-Defined ID: Cross Reference Number: Topic: SE-1 MCR Num Field 1: Num Field 2: Text Field: General Data Technical Reference with SE-1, Section 4.8, Rev Revision Number: 63, Attachment 3 Cognitive Level H PRA: (Le. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b) 10 Question History: (Le. LGS Bank NRC-05, OYS CERT-04) Question Source: (i.e. New, Bank, Modified, Bank, Modified) LIMERICK LOT 0582 EXAM BANK COMPUTER TEST Page: 182 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (i.e. ABN-##) Excluded

Reference:

(Le. Ensure ON-## not provided)

Low KA Justification (if required): Modified starting pressure in question stem. Modified stem to directly test application of SE-1, Attachment

3. Modified all distractors so that each offers a different final pressure.

Changed correct answer from C to A. Steam Tables NONE N/A EXAM BANK COMPUTER TEST Page: 183 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8855 Points: 1.00 ST-6-092-931-1 "011 DIESEL GENERATOR GOVERNOR AND VOLTAGE REGULATOR POST MAINTENANCE TESTING" is in progress following governor replacement. -The measured Bus Voltage is NOT within the acceptance criteria contained in an asterisked step. Engineering has determined that an error was introduced into the procedure during the WHICH ONE of the following describes an acceptable action to be taken by the Reactor Operator performing the test? Stop ST performance. Report the discrepancy to Shift Supervision, document the measured bus voltage in the ST additional Action/test comments section, and mark the test cover sheet "ABORTED". Stop ST performance. Revise the acceptance criteria using the process for Temporary Changes to Approved Documents and Partial Procedure Use, resume ST performance. Continue ST performance. Upon ST completion, document the measured Bus Voltage in the ST Additional Action I Test Comments section, mark the ST cover sheet as "Satisfactory". Continue ST performance. Upon ST completion, revise the Bus Voltage acceptance criteria using the process for Temporary Changes to Approved Documents and Partial Procedure Use, mark the ST cover sheet as "Satisfactory". Answer: A Answer Explanation: Per HU-AA-104-101 PROCEDURE USE AND ADHERANCE and 430, SURVEILLANCE TESTING PROGRAM users shall STOP upon obtaining unexpected results, OR if continuation would result in an unsafe condition or an unexpected condition. Voltage data outside of the specified acceptance criteria would fall into these categories. If a test cannot or should not be continued due to the unexpected condition, then test is ABORTED and the reason for aborting shall be documented on the test. Per AD-LG-101-1002 Temporary Changes to Approved Documents and Partial Procedure Use, changes to technical specification or other regulatory related acceptance criteria are a CHANGE OF INTENT and may NOT be revised using the Temporary Change process. ._-. " . Testing shall stop upon unexpected results. Per WC-LG-430, SURVEILLANCE TESTING PROGRAM, signature on a SATISFACTORY test shall mean all asterisk, "I", URn, black box or other steps denoted in the acceptance criteria or on the cover page are within required limits. _. EXAM BANK COMPUTER TEST Page: 184 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Testing shall stop upon unexpected results. Per AD-LG-101-1002, changes to technical specification or other regulatory related acceptance criteria are a CHANGE OF INTENT and may NOT be revised using the Temporary Changes to Approved Documents and Partial Procedure Use process. Per WC-LG-430, SURVEILLANCE TESTING PROGRAM, signature on a SATISFACTORY test shall mean all asterisk, "I", "R", black box or other steps denoted in the acceptance criteria or on the cover page are within required limits. Question 68 Info 1 Question Type: Multiple Choice Status: Active ! Always select on test? No Authorized for practice? No : Points: 1.00 Time to Complete: 3 Difficulty: 13.00 System 10: 8855 User-Defined 10: 8855 Cross Reference Number: LGSOPS2010.IL Topic: Procedure actions taken Num Field 1: 4.1 Num Field 2: 4.4 Text Field: 2.1.2 Comments: General Data Technical Reference with AD-LG-1 01-1 002, Revision Number: Temporary Changes to Approved Documents WC-LG-430, Surveilance Testing Program HU-AA-104-101, Human Performance Compliance OP-AA-1 02-1 04 Cognitive Level L PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 10 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified) Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS review) 1 ILT Supplied Ref (If NONE approQriatel: (i.e. ABN-##) Excluded

Reference:

(Le. OP-AA-102-104 Ensure ON-## not provided)

EXAM BANK COMPUTER TEST Page: 185 of 12 October 2010 I EXAMINATION ANSWER KEY ILT09-1 RO questions in sample plan order II L.OW KA Justification (if I N/.A .____ ________' EXAM BANK COMPUTER TEST Page: 186 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order ID: 8854 Points: 1.00 Unit 1 plant conditions are as follows: -ST-6-1 07-450-1 , ECCS AND RCIC LINEUP VERIFICATION -OPCONS 1,2, AND 3, is being performed -The MCR handswitch for valve HV-055-1 F002, HPCI Steam Line Inboard Isolation Vlv (INBOARD), has a blue tag applied stating that the valve is back seated WHICH ONE of the following describes the correct reference documentation regarding the valve's current position? A. P&ID 8031-M-0055 B. ST/RT Status Log (Short Duration Time Clock Log) C. Abnormal Component Position Sheet (ACPS) D. An ACTIVE clearance that includes a tag for the HV-055-1 F002 handswitch Answer: C Answer Explanation: Abnormal Component Position Sheet (ACPS): The ACPS is used to document approvals, positioning and restoration of component(s). The EST(s) identify the temporary status of the equipment positions at the point of control. Blue Equipment Status Tags are controlled per OP-AA-108-101 CONTROL OF EQUIPMENT AND SYSTEM STATUS. EST(s) direct attention to any special condition of an operating system such as outstanding PMT or non-preferred equipment use. The procedure also specifies personnel shall "utilize EST(s) in conjunction with the ACPS to flag the component(s) left in an abnormal position. I P&ID 8031-M-0055: P&IDs are updated via ECR process for permanent changes vs. temporary abnormal positioning. ST/RT Status Log (Short Duration Time Clock Log): ST/RT Status Log is used to document in progress Surveillance, Routine, or System operating procedures that cause short duration entry into TS LCO or TRM action statements. An ACTIVE clearance that includes a tag for the HV-055-1FOO2 handswitch: The Clearance and Tagging process is used for equipment and worker safety, and utilize INFO, DANGER, and SCT tags vs EST(s). EXAM BANK COMPUTER TEST Page: 187 of 13 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order I Question 69 Info Question Type: Multiple Status: Always select on test? Authorized for practice? I Points: 1.00 Time to Complete: 3 Difficul!1': 3.00 . System ID: 8854 User-Defined ID: 8854 I Cross Reference Number: LGSOPS2010.lL Topic: Procedure requirements I Num Field 1: 3.9 Num Field 2: 4.3 Text Field: 2.2.15 I General I Technical Reference with , OP-AA-108-101 I Revision Number: Level L I PRA: (Le. Yes or No or #) NO ToCFR 55.43(N/A for RO) 55.41 (b) 10 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) -J Excluded

Reference:

(i.e. NONE Ensure ON-## not provided)

Low KA Justification (if N/A I = EXAM BANK COMPUTER TEST Page: 188 of 206 13 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 5193 Points: 1.00 WHICH ONE of the following situations is controlled with a Troubleshooting, Rework & Testing (TRT) Form? Mod Acceptance Testing the "B" RWCU Pump following installation of a new design pump seal Manually throttling RHRSW flow through the RHR Heat Exchangers for baseline flow determinations Station Work Order requiring removal of a fuel injector from the D11 DIG for use on the D13 DIG D14 LOCAILOOP Plant Evolution/Special Test (PEST) Answer: B Answer Explanation: Manually throttling RHRSW flow through the RHR Heat Exchanger for baseline flow determinations: Correct because MA-M-716-004. establishes a standard systematic approach for performing Troubleshooting on new and long-standing equipment problems including failures, abnormal operating conditions, negative performance trends and recurring events. The problems may be identified from varying sources, such as in response to another department's request (phone. written, or in person), during a system walkdown, a Work Request (WR) I Action Request (AR), or assigned through an Issue Report (IR). 1.3. This procedure provides guidance for a broad spectrum of conditions ranging from simple troubleshooting with a component isolated from service to complex cases that could involve multiple work groups and equipment that remains in operation with potential impact on other equipment. 1.7. A troubleshooting plan that requires discovery of information prior to the development of the next step, does not constitute a requirement for transition from simple to a complex troubleshooting plan. Simple troubleshooting may address several failure modes or activities due to the type and quantity of information that needs to be obtained to narrow the troubleshooting scope. Mod Acceptance testing the "8" RWCU Pump following installation of a new design pump seal: Incorrect due to A-C-29, or MOD-C-5, Mod acceptance testing covers Mod acceptances. EXAM BANK COMPUTER TEST Page: 189 of 12 October 2010 --EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Station Work Order requiring removal of a injector from the 0-11 DIG for use on the 013 Incorrect due to the station work order process clearance application for personnel safety would required for this 014 LOCAl LOOP Plant Evolution/Special Test (PEST): Incorrect due to A-C-29, or MOD-C-5, Mod acceptance I testing covers PESTs. I Question 70 Info i Question Type: Choice . Status: Active i Always select on test? No I Authorized for practice? No I Points: 1.00 I Time to Complete: 13 D ifficu 4.00 System ID: 5193 User-Defined ID: 5193 . Cross Reference Number: LLOT1570.06 Identify the condition is controlled with a Troubleshooting, Topic: Rework &Testing (TRT} Num Field 1: ll'Jum Field 2: 3.6 13.8 Text Field: 2.2.7 12.2.20 Comments: r--General Data I Technical Reference with MA-AA-716-004 Revision Number: 1 Cognitive Level L Justification for Non SRO 55.41 (b) 10 CFR Link: Question History: (i.e. LGS BANK *NRC-05, OYS CERT -04) ..

Question Source: (I.e. BANK Bank, Modified)

Low KA Justification (if NIA required): Revision History: Revision BANK History: (I.e. Modified distractor "b" to make

plausible based on OTPS review) ILT ._.-_, Supplied Ref (If None appropriate): (i.e. ABN-##) f-.. Excluded

Reference:

(i.e. MA-AA-716-004

Ensure ON-## not Qrovided)

II LORT II PRA: (I.e. Yes or No or #) No EXAM BANK COMPUTER TEST Page: 190 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order LORT Question Section: A (Le, A-Systems or B-Procedures) I Question 70 Table-Item Links NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility. 10 CFR 55.41 RO WRITTEN EXAMINATION 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 43.3 Facility licensee procedures required to obtain authority for design and operating changes in the facility. CFR: 43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. CFR: 45.13 Demonstrate the applicant's ability to function within the control room team as appropriate to the assigned position, in such a way that the facility licensee's procedures are adhered to and that the limitations in its license and amendments are not violated. General Question Data EXAM BANK COMPUTER TEST Page: 191 of 206 12 October 2010

* * * *
EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8856 Points: 1.00 Unit 1 plant conditions are as follows: -Plant is in OPCON 5 -Fuel is being loaded into the core -"1 A" SRM count rate is 4 cps and has a signal-to-noise ratio of 3.5 -"1 B" SRM was declared inoperable last shift due to spiking -"1 C" SRM count rate is 2.6 cps and has a signal-to-noise ratio of 2.5 -"10" SRM count rate is 2 cps and has a signal-to-noise ratio of 1.6 -i I I I 1.' I .. M I ,I I I I I I II.' I I I I t t 2\ I , I I I I I I I I .0 I I .1 \ \ 1 ., f I '1. I I I J I I \! , I" . I I r.;-* D ." J ,f r , .I I I
_.... 1. CIIIIf lID ...&tall. 'II __ Ut.1IIO nat s..J.t-. WHICH ONE of the following describes the impact on FUEL LOADING into the core? A. Fuel may be loaded into "A", "C", or "0" core quadrants ONLY. B. Fuel may be loaded into "An or "c" core quadrants ONLY. C. All fuel loading must be suspended IMMEDIATELY.

D. Fuel loading may CONTINUE in any quadrant. EXAM BANK COMPUTER TEST Page: 192 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Answer: C Answer Explanation: ANSWER I OISTRACTOR OISTRACTOR DISTRACTOR Question 71 Question Always select on . Authorized for practice? I Points: . Time to System User-Defined Cross Reference i Num Field Num Field Text i I All fuel loading must be suspended IMMEOIATEL Y: "0" SRM is inoperable since it does not have at least 3 cps, and does not have adequate signal-to-noise ratio per TS figure 3.3.6-1. With "S" and "0" SRMs inoperable. fuel movement cannot be performed in any quadrant. since LCO 3.9.2 requires an SRM operable in the quadrant where fuel is being moved. and in an adjacent quadrant. Fuel may be loaded into "A". "C". or "0" core quadrants ONL Y: See Above Fuel may be loaded into "A" or "C" core quadrants ONLY: See Above Fuel loading may CONTINUE in any quadrant: See Above Choice Active No No 1.00 3 3.00 8856 8856 LGSOPS0074.10A SRM indications in the MCR 3.4 4.7 2.2.40 General Data Technical Reference with Revision Number: , Cognitive Level (i.e. Yes or No or #) 10CFR 55.43 (N/A for RO) i Question History: (i.e. LGS , NRC-05. OYS CERT -04) Question Source: (i.e. New. Sank. Modified) Tech Spec TS figure 55.41 . SANK, LIMERICK LOT i 7306 Page: 193 of 12 October 2010 EXAMINATION ANSWER ILT09*1 RO questions in sample plan order Revision History: Revision History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (i.e. ABN*##) Excluded

Reference:

(i.e. Ensure ON-## not providedJ Low KA Justification (if required):

Modified to edit stem to maintain consistent formatting. Changed order of distractors. Changed correct answer from B to C. NONE NONE N/A EXAM BANK COMPUTER TEST Page: 194 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 3312 Points: 1.00 Unit 2 plant conditions are as follows: -Reactor power is 100% -TIPs are in operation per S74.0.A "Operation of Traversing In-Core Probe System" to support APRM calibration -The Reactor Enclosure Duty Equipment Operator reports workers are observed on the Tip Room roof WHICH ONE of the following shall be immediately performed? A. Direct Equipment Operator to enter posted area and evacuate workers B. Stop operation of TIP mechanisms, Inform Shift Supervision C. Immediately withdraw TIPs into shields, Inform Shift Supervision D. Direct Security to enter area and evacuate workers Answer: B Answer Explanation: Stop operation of TIP mechanisms, Inform Shift Supervision -This answer is correct because of the WARNING in S74.0.A procedure, "TIP detectors shall not be moved from their chamber shields until Health Physics has taken appropriate actions for TIP system operation." With the conditions stated, either the required postings and Announcements per S74.0.A sections 4.2 and 4.3 are not completed or personnel have violated a posted radiation boundary. This action prevents moving the irradiated TIP detector from in-Core through the area that would cause higher dose to the workers on the TIP room roof. These actions are consistent with RP-LG-301*2001 Attachment 9, TIP Run Coverage and Posting and 460, TIP Area Access Controls. Direct Equipment Operator to enter posted area and evacuate workers -This answer is incorrect because this action would violate a posted Rad Boundary and lead to potential uncontrolled dose. __ Immediately withdraw TIPs into shields, Inform Shift Supervision -This answer is incorrect because moving the irradiated TIP detector from in-Core through the TIP room to the chamber shields would raise the dose rate in the vicinity of the workers on the TIP room roof. EXAM BANK COMPUTER Page: 195 of 206 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order [DISTRACTO_R--l._D_i_re_c_t _security to enter area and evacuate workers This answer is incorrect because this action would violate a posted Rad Boundary and lead to potential uncontrolled dose. 1 Question 72 Info I Question Type: MultiEle . Status: ..Alway_s select on test? No Authorized for practice? No t-=-:-:-.. Points: i Time to : Difficult:t: I i Sl'stem 10: I User-Defined 10: Cross Reference Number: A Locked High Radiation Area is found uncontrolled and Topic: accessible. shall be immediatel:t Qerformed? i Num Field 1: Num Field 2: Text Field: Comments: General Data Technical Reference with RP-AA-460, RP-AA-376, Revision Number: RP-LG-460-1 060, I Cogn itive level L l10CFR55 10CFR55.41 (b) 12 I Question History: (I.e. LGS NEW NRC-05, OYS CERT-04l Question Source: (I.e. New, NEW Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS I. ILT I Supplied Ref (If NONE aeproeriate): liYBN-##) Excluded

Reference:

(i.e. Ensure ON-## not provide..<=!) LORT PRA (i.e. Yes or No or #) LORT Question (I.e, A-Systems or II EXAM BANK COMPUTER TEST i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 72 Table-Item Links LO Question Category 97 C Question System (Old TEGRS questions)

HP General Question Data EXAM BANK COMPUTER TEST Page: 197 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 73 10: 4985 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor Power is -Hydrogen Water Chemistry in Main Steam Rad Monitor readings (RR-41-1R603) are as follows: -1A 3574 -1B 1770 -1C 1750 -10 1780 Unit 1 Main Steam Line RAD Monitor I MS Monitor Background HWC Factor 1.5 (x) HWC Factor of 1 x Background = with HWC in-service t 1A 1153 MRlhr 1.0 1729 MRlHr 1B 1164 MRlhr 1.0 1746 MRlHr 1C 1159 MRlhr 1.0 1738 MRlHr 10 1153 MRlhr 1.0 1792 MRlHr (Operator Aid S-01-014) WHICH ONE of the following descibes the Expected Annuciators for the above conditions? A. 109 Rad F-1, Main Steam Line DIV I Rad Monitor HI/Downscale ONLY B. 109 Rad F-1, Main Steam Line DIV I Rad Monitor HI/Downscale AND 109 Rad F-2, Main Steam Line DIV II Rad Monitor HI/Downscale ONLY C. 109 Rad F-1, Main Steam Line DIV I Rad Monitor HI/Downscale AND 107 Reactor 1-1, Main Steam Line HI-HI Radiation ONLY D. 109 Rad F-1. Main Steam Line DIV I Rad Monitor HllDownscale AND 109 Rad F-2, Main Steam Line DIV II Rad Monitor HI/Downscale AND 107 Reactor 1-1! Main Steam Line HI-HI Radiation Answer: 0 Answer Explanation: EXAM BANK COMPUTER TEST Page: 198 of 206 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 109 Rad F-1, Main Steam Line DIV I Rad HI/Downscale: Correct because this ANN is received to 1.5 x NFPB, on RISH 411 K603A, B. A & B both exceed this value 109 Rad F-2, Main Steam Line DIV II Rad HI/Downscale: Correct because this ANN is received to 1.5 x NFPB, on RISH 411K603C, D. C & D Exceeds this value 107 Reactor 1-1, Main Steam Line HI-HI Correct because this ANN is received due to 3 x NFPB. Any RISH 411K603A. B, C, D. The 'A' Channel this 109 Rad F*1, Main Steam Line DIV I Rad HI/Downscale ONLY: Incorrect due to reasoning Additional 109 Rad F*1, Main Steam Line DIV I Rad HI/Downscale 109 Rad F-2, Main Steam Line DIV II Rad HI/Downscale ONLY: Incorrect due to reasoning Additional 109 Rad F*1, Main Steam Line DIV I Rad Monitor HI/Downscale AND 107 Reactor 1*1, Main Steam Line HI*HI Radiation ONL Y: Incorrect due to reasoning above. Additional annunciator Question 73 Question Type: Multiple Status: Always select on test? Authorized for practice? Points: Time to Com plete: .4.00 System ID: User-Defined ID: Cross Reference Number: LLU-'IJ f Topic: MSL Hi Num Field 1: _M___ Num Field 2: Text Field: General Data II Technical Reference with ARC 109 F-1, F-2 Revision Number: Cognitive Level H Justification for Non SRO 55.41 (b) 11 CFR Link: EXAM BANK COMPUTER TEST Page: 199 of 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified) Low KA Justification (if N/A reguired): Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A-Systems or B-Procedures) I I Question 73 Table-Item Links NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.11 Purpose and operation of radiation monitoring systems, including and survey CFR: 41.12 Radiological safety principles and 10 CFR 55.41 RO WRITTEN 10 CFR 55.43 SRO WRITTEN CFR: 43.4 Radiation hazards that may arise during normal and abnormal including maintenance activities and various contamination CFR: 45.9 Demonstrate or describe the use and function of the facility's monitoring systems, including fixed radiation monitors and alarms, portable instruments, and personnel monitoring General Question Data EXAM BANK COMPUTER TEST Page: 200 of 206 12 October 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 5998 Points: 1.00 Unit 1 initial plant conditions are as -Reactor power is -RPV pressure is 1027 "1 B" Outboard MSIV has failed closed. Current conditions are: -Reactor power is 81 % -107 REACTOR G-2, "REACTOR HI PRESS" has alarmed, and will not clear -One bypass valve is 40% open WHICH ONE of the following describes the required immediate operator action? Place the Reactor Mode Selector Switch to "SHUTDOWN" Raise EHC Pressure Set until one Bypass Valves is fully open Depress Bypass Valve jack "OPEN" pushbutton to fully open one Bypass Valves Reduce Reactor power until RPV pressure is below "REACTOR HI PRESS" setpoint Answer: D Answer Explanation: Reduce Reactor power until RPV pressure is below "REACTOR HI PRESS" setpoint: Correct because Annunciator response directs OT-102 entry after verifying high pressure on PI-42-1 R605 on 10C603 panel. Per the OT -102 entry conditions the Immediate Operator Actions are required per section 2.1, Reduce Reactor power in accordance with GP-5, Steady State Operations and RMSI to maintain Reactor pressure less than 1053 psig. Per the ARC, the alarm setpoint for Reactor Hi Press is 1053 pSig with a reset of 1051 psig. The second Immediate Operator Action per section 2.2, Control Reactor Pressure below 1053 psig with bypass valves using the jack or by reducing pressure set. This would . require "opening" the BPVs. Place the Reactor Mode Selector Switch to "SHUTDOWN": Incorrect due to no indication of exceeding an RPS scram setpoint for Reactor Hi Pressure Trip and no procedure direction in OT-102. Raise EHC Pressure Set until one Bypass Valves is fully open: Incorrect due to wrong direction of operation to open Bypass Valves. Procedure direction is for pressure to lower pressure below 1053 psig. EXAM BANK COMPUTER TEST Page: 201 of 12 October 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Depress Bypass Valve jack "OPEN" pushbutton to fully open one Bypass Valves: Incorrect due to no specific procedure direction to fully open a Bypass Valve. OT-102 only requires controlling Reactor pressure below 1053 psig following the power reduction. Opening a BPV without regard to pressure would not be correct. I Question 74 Info ! Question Type: Multiple Choice !Status: Active Always select on test? No Authorized for No Points: 1.00 Time to 3 3.00 System ID: 5998 User-Defined ID: 5998 Cross Reference Number: LLOT1540.02 Unit 1 initial Reactor power is 80% RPV pressure is 1027 Topic: MSIV has failed closed Num Field 1: r---4.0 Num Field 2: 4.0 Text Field: G2.4.49 Comments: General Data Technical Reference with ARC 107 G-2,

Revision Number: OT-102 Level H 10CFR55 55.41(b} 10
Question History: (Le. LGS Bank, IL T NRC Exam i NRC-05, OYS CERT-04) 2005 Question Source: (I.e. New, Bank, Modified)

Low KA Justification (if Bank N/A required): Revision History: Revision Bank History: {I.e. Modified distractor "b" to make plausible based on OTPS i Supplied Ref (If i None {Le. ABN-##}

Excluded

Reference:

(I.e. ARC 107 G-2 i Ensure ON-## not provided)

_. . LORT PRA: (Le. Yes or No or #) Y LORT Question Section: A (Le, A-Systems or B-i Procedures 2 I i EXAM BANK COMPUTER TEST Page: 202 of 12 October 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 74 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 203 of 206 12 October 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 5857 Points: 1.00 Unit 1 is at 100% power when the following occurs: -"1 S" Condensate Pump trips -RPV level drops to +18 inches, then recovers to normal level -No half or full scram signals are generated WHICH ONE of the following sets of procedures are required to be performed? OT-104, "Unexpected/Unexplained Positive or Negative Reactivity Insertion," ONLY OT-100, "Reactor Low Level," ONLY OT-100, "Reactor Low Level," OT -112, "Recirculation Pump OT-100, "Reactor Low Level," AND OT-104, "Unexpected/Unexplained Positive or Negative Reactivity Insertion" Answer: D Answer Explanation: OT-104, Unexpected/Unexplained Positive or Negative Reactivity Insertion and OT-100, Reactor Low Level: Correct, Conditions are met with trip of condensate pump and Total Feedwater flow> 80.3%. for a High Level Recirculation pump runback, causing power to decrease, which is an entry into OT-104. A Reactor Low Level Alarm < 30" requires an entry into OT-100. OT-104, Unexpected/Unexplained Positive or Negative Reactivity Insertion ONLY: Partially correct, as conditions are met with trip of condensate pump and Total Feedwater flow> 80.3%. for a High Level Recirculation pump runback, causing power to decrease, which is an entry into OT-104. Incorrect as condfiions are also met for entry into OTass described above. DISTRACTOR OT-100, Reactor Low Level and OT-112, Recirculation . Pump Trip: Incorrect due to no indication of Recirc Pump

trip, (Partial correct answer for OT-100 entry)

OT -100, Reactor Low Level, Partially correct, as conditions are met for entry into OT -100 as described above, Incorrect, as conditions are also met for entry into OT-112 ass described

above, EXAM BANK COMPUTER TEST Page: 204 of 12 October 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order I Question 75 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?

No Points: 1.00 Time to Comr:1Jete: 3 Difficulty: 3.00 System ID: 5857 User-Defined ID: 5857 , Cross Reference Number: LLOT1540.02 '----. "1 B" Condensa!e pump trips RPV level drops li'!um Field 1: 4.0 I Num Field 2: 4.3 Text Field: 295014 G2.4.4 Comments: General Data Technical Reference with OT-104, Reactivity Revision Number: Addition OT-112, Recirc Pump Trip OT-100, RPV low level Cognitive Level L 10CFR55 55.41 (b) 10 Question History: (i.e. LGS Bank NRC-05, OYS CERT-041 Question Source: (Le. New, Bank Bank, Modifiedl I Low KA Justification (if N/A Revision History: Revision Bank History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If None (i.e. ABN-##) Excluded

Reference:

(I.e. OT-104, OT-100, OT-Ensure ON-## not provided) 112 LORT PRA: (I.e. Yes or No or #) Y LORT Question Section: A (i.e, A-Systems or B-Procedures) EXAM BANK COMPUTER TEST Page: 205 of 206 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 75 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 206 of 206 12 October 201 0 SRO ILT09-1 1 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: Points: 1.00 T-111, Steam Cooling, is in progress with the following conditions:

-Reactor level is -No injection systems available to the WHICH ONE of the following describes the status of the fuel? Adeguate Core Cooling Peak Clad A. 1800 deg. F B. 2200 deg. F C. 1800 deg. F D. 2200 deg. F Answer: A Answer Explanation: Adequate Core Cooling _. Yes; Expected Peak Clad Temp -1800 deg. F: This combination answer is correct. With the initial conditions of -196" and no injection systems available to the vessel the T-111 Stearn Cooling Strategy is followed. Per the T-111 Bases, the steam cooling section of T-111 directs actions to stabilize RPV pressure while efforts to restore RPV injection sources are continued. With no injection into the RPV, adequate core cooling is defined to exist as long as peak clad temperature remains below 1800 deg. F, the threshold for significant metal-water reaction. As the core begins to uncover and PCT begins to rise, boil-off continues and the steam produced by decay heat in the covered portion of the core provides some cooling to the uncovered portion through convective heat transfer. At the Minimum Injection RPV Water Level (MZIRWL) the steam generated by the covered portion of the core is exactly sufficient to remove the heat generated in the uncovered region with PCT at 1800 deg. F. The MZIRWL is -205 inches and since the conditions show level above this, the PCT is expected to not exceed 1800 deg. F. Adequate Core Cooling -Yes; Expected Peak Clad Temp -2200 deg. F: This combination is incorrect because although the given conditions support adequate core cooling, the PCT is not expected to reach the 2200 deg. F threshold. This temperature value is plausible because it is a number associated with accelerated zirconium water reactions. .. --.. __,_=_=____,.-::_::_c_c_ EXAM BANK COMPUTER TEST Page: 1 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order ..__.. DISTRACTOR Adequate Core Cooling -No; Expected Peak Clad 1800 deg. F: This combination is incorrect because the current conditions stated indicate steam cooling will continue to remove heat from the fuel and maintain the PCT below 1800 deg. F. thus maintaining adequate core cooling. DISTRACTOR Adequate Core Cooling -No; Expected Peak Clad 2200 deg. F: This combination is incorrect because with the given plant conditions of RPV level above MZIRWL adequate core cooling is expected to be maintained and PCT is

expected to not exceed 1800 deg. F. I I Question 1 Info '-_. Question Type: Multiple Choice Active Always select on test? No I Authorized for practice?

No *' 1.00 Time to 5 Difficulty: 4.20 System 10: 14946 User-Defined ID: . 4946 Cross Reference Number: 6315 T-111, Steam Cooling, is in progress ! Num Field 1: 4.6 (4.6) Num Field 2: 4.7 (4.8) Text Field: 295031 EA2.04 Comments: General Data Technical Reference with TRIP BASES I Revisio Revision Number: n #: , Cognitive Level H Justification for Non SRO 55.43 (b) 5 CFR Link: Question History: (Le. LGS BANK NRC-05, OYS CERT-04) Question Source: (i.e. New, BANK Bank, Modified) Low KA Justification (if N/A _________________Revision History: Revision N/A History: (i.e. Modified distractor ub" to make plausible based on OTPS review) .. __ c==== ____ __, Ref (If none * (i.e. 1 Ensure ON-4I# LORT EXAM BANK COMPUTER TEST Page: 2 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order LORT Question Section: B (Le, A-Systems or B-Procedures) Question 1 Table-Item Links NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.7 Design. components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. CFR: 41.8 Components, capacity, and functions of emergency systems. CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility. 10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. CFR: 45.6 Perform control manipulations required to obtain desired operating results during normal, abnormal, and emergency situations. CFR: 45.8 Safely operate the facility's auxiliary and emergency systems, including operation of those controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment. CFR: 45.13 Demonstrate the applicant's ability to function within the control room team as appropriate to the assigned position, in such a way that the facility licensee's procedures are adhered to and that the limitations in its license and amendments are not violated. General Question Data Higher Limerick SRO 2 10: Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is -Reactor pressure is 750 psig down -Reactor level indications are as -Narrow Range Indications are indicating upscale -HPCI high level trip light is lit -Reference leg boiling on PMS is YES -"A" Fuel Zone level indicates -145" down slow -Suppression Pool temperature is -2 SRVs are WHICH ONE of the following describes the earliest condition at which injection into the RPV is directed? A. When 5 SRVs are open, restore injection B. When level drops below -161", restore injection C. When reactor pressure is 390 psig, restore injection. D. When reactor pressure is 590 psig, restore injection. Answer: D Answer Explanation: When reactor pressure is 590 psi restore injection -This is the correct answer because as long as RPV pressure remains above the Minimum Alternate RPV Flooding Pressure (MARFP, 230 psig with 5 SRVs open) the core is adequately cooled by a combination of submergence and steam cooling regardless of whether any water is being injected into the RPV or the reactor is at power. The MARFP is defined to be the lowest RPV pressure at which steam flow through open SRVs is sufficient to preclude any clad temperature from exceeding 1500 F, even if the core is not completely covered. The MARFP with only 2 SRVs open is 600 psig for initiating injection. When RPV pressure drops to the MARFP or at lease 2 ADS/SRVs cannot be opened, injection into the RPV must be re-established to maintain adequate core cooling and to ultimately flood the RPV. When five SRVs are opened, restore injection -This is an incorrect answer since MARFP (core cooling) is ensured until RPV pressure reaches 230 psjg with 5 SRVs open. Immediate restoration of injection is not required. When level drops below -161", restore injection -This is an incorrect answer since MARFP (core cooling) is ensured until RPV pressure reaches 230 psig. If RPV Level is unknown, then T-111 directs to enter T-116. EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order DISTRACTOR When level drops below -161", restore injection -This is incorrect answer since MARFP (core cooling) is ensured RPV pressure reaches 230 psig. If RPV Level is then T -111 directs to enter T When reactor pressure is 390 psig, restore injection. is an incorrect answer since MARFP (core cooling) is until RPV pressure reaches 230 psig. Since only 2 SRVs open, the MARFP is 600 psig. The value of 390 psig would correct if only 3 SRVs are open. This would not be earliest conditions at which RPV injection is -Question 2 Question Type: Multiple Status: I Always select on test? Yes *Authorized for practice? No Points: 1.00 !Time to C()mplete: 3 ! Difficulty: 3.00 System ID: User-Defined ID: Cross Reference Number: Topic: Interperet RX pressure during Num Field 1: Num Field 2: Text Field: Gern:;1 ell Data Technical Reference with T-116 Revision Number: Cognitive Level H PRA Y 10CFR 55.43 55.43 (b) 5 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified) Low KA Justification (if N/A

Revision History:

NEW History: (Le. Modified distractor "b" to make plausible based on OTPS ! review) ILT , Supplied Ref (If T-116 sheets 1 and 2 ! appropriate): (Le. ABN-##) T-117 I Excluded

Reference:

(Le. N/A Ensure ON-## not

! 3 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: -OPCON 2 during plant -RPV pressure is 600 -Heat-up in Fire Protection Group reports that one of three fire suppression heat sensors in the RCIC room are inoperable WHICH ONE of the following describes the required actions, if any, based on the above conditions? Establish an hourly fire watch within the next hour No actions required provided the other two heat detectors and both smoke detectors are operable No action required provided RPV pressure is lowered below 200 psig within the next hour Restore the instrument to operable within 14 days or establish an hourly fire watch within the next hour Answer: A Answer Explanation: Establish an hourly fire watch within the next hour -This is the correct answer per TRM 3.3.7.9-1, Table 3.3.7.9-1, Fire Zone 33, Requires 3 Function B (Activation of Fire Suppression System and Early Warning Notification) instruments for HEAT. The TRM requires: With the number of OPERABLE fire detection instruments in one or more zones: One less than the Total Number of instruments shown in Table 3.3.7.9-1 for Function B within 1 hour establish a fire watch patrol to inspect the zone(s) with the inoperable instrument at least once per hour, unless the instruments is located inside an inaccessible zone, then inspect the area surrounding the inaccessible zone at least once per hour. This TRM applies when the component to be serviced by fire detection is required. In this case, RCIC is required when steam dome pressure is greater than 150 psig. No actions required provided the other two heat detectors and both smoke detectors are operable -This is an incorrect answer because the requirements of TRM 3.3.7.9-1 do not allow substitution of smoke detectors for fire detectors. The action for the failed heat sensor is to take the action specified in the LCO. EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order No action required provided RPV pressure is lowered below 200 psig within the next hour -This is an incorrect answer because per TRM 3.3.7.9-1 applicability for this condition is whenever equipment protected by the fire detection instrument is required to be OPERABLE. Per TS 3.3.5 RCIC is required to be OPERABLE in OPCON 1, 2 and 3 with reactor steam dome pressure greater than 150 psig.Heat-up in progress indicates pressure is rising due to plant conditions. Restore the instrument to operable within 14 days or establish an hourly fire watch within the next hour* This is an incorrect answer because per TRM 3.3.7.9-1 this action would be required for Function A devices, and the conditions state the inoperability of the fire suppression heat sensor for a Function B device. Question 3 Info Question Type: Multiple Choice Active Always select on test? No Authorized for practice? No 1.00 3 3.00 System 10: 5409 User-Defined 10: 5409 Cross Reference Number: LLOT0733.09 Heatup in progress Fire Protection Group Num Field 1: Num Field 2: SRO 3.4 Text Field: 600000 AA2.15 Comments: General Data II Technical Reference with TRM 3.3.7.9 I Revisio Revision Number: n #: 27 Cognitive Level H Justification for Non SRO 55.43 (b) 5 CFR Link: Question History: (I.e. LGS NRC-02 NRC-05, OYS CERT-04) Question Source: (i.e. New, Bank Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision N/A History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Supplied Ref (If (i.e. ABN-##) i Excluded

Reference:

(Le. , Ensure ON-## not LORT PRA: (Le. Yes or No or #) LORT Question Section: (i.e, A-Systems or B-Procedures)

Question 3 Table-Item Links General Question Data Limerick RO TRM 3.3.7.9 N/A N A EXAM BANK COMPUTER TEST Page: 9 of 77 12 October 2010 4 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: -Loss of Coolant Accident (LOCA) and steam leak in the OB MSIV room -Reactor pressure is 700 psig and slowly lowering -Drywell Temperature is 240 degrees -Drywell Pressure is 24 PSIG -HPCI and RCIC are controlling RPV level -Area 11/12 OB MSIV Room temperature is 350 degrees The Reactor Operator reports the following RPV level indications: -Narrow Range (1 R606C) +2 -Wide Range (1 R623B) -115 -Fuel Zone (1R610) -125 -Shutdown Range (1 R605) -21 WHICH ONE of the following RPV level indicating ranges are usable to maintain RPV level with HPCI and RCIC? A. Wide Range and Fuel Zone Range B. Narrow Range and Wide Range C. Fuel Zone Range and Shutdown Range D. Narrow Range and Fuel Zone Range Answer: A Answer Explanation: Wide Range and Fuel Zone Range: This is the correct answer because with the OB MSIV Room (Room 407) Area 11/12 given at 350 degrees and RPV level at -115" I Wide Range (XR-42-1 R623B) indication temperature would be > than MRT (181°) but level is > than MIL (-124"). Per T-291 if an indication is either < MRT or > MIL the indication is usable. For the Fuel Zone Indication (LI-42-1 R6i 0) temperature would be > than MRT (i2T) but> than MIL (-303"). Per T-291 if an indication is either < MRT or > MIL the EXAM BANK COMPUTER TEST Page: 10 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Narrow Range and Wide Range: This is only partially correct due to the OB MSIV Room (Room 407) Area 11/12 greater than 350 degrees and RPV level at +2", Narrow Range (U-42-1 R606B) indication temperature would be > than MRT (304°) and also < than MIL (+3"). Per T-291 if an indication is > MRT and < MIL the indication is not usable. Wide Range (XR-42-1 R623B) indication temperature would be> than MRT (181°) but level is > than MIL (-124"). Per T-291 if an indication is either < MRT or > MIL the indication is usable. Fuel Zone Range and Shutdown Range: This is only partially correct due to the Fuel Zone Indication 1 R61 0) tem perature would be > than M RT (12r) but> than MIL (-303"). Per T-291 if an indication is either < MRT or > MIL the indication is usable. Shutdown (U-42-1 R605) indication if run temperature is < 350°F (DIW & Reactor Enclosure) and indicated level> 49" then the indication is usable. With conditions of 350° in the Drywell and RPV level at -21" the indication is not usable. Narrow range and Fuel Zone Range: This is only partially correct due to the OB MSIV Room (Room 407) Area 11/12 greater than 350 degrees and RPV level at +2", Narrow Range (U-42-1 R606B) indication temperature would be > than MRT (304°) and also < than MIL (+3"). Per T-291 if an indication is > MRT and < MIL the indication is not usable For the Fuel Zone Indication (U-42-1 R610) temperature would be > than MRT (127°) but> than MIL (-303"). Per 291 if an indication is either < MRT or > MIL the indication is

usable. Question 4 Info No No 1.00 Time to Com lete: 5 I Difficulty:

4.00 Reference Number: EXAM BANK COMPUTER TEST Page: 11 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order General Data Technical Reference Revision Cognitive PRA: (i.e. Yes or No or 10CFR 55.43 (N/A for Question History: (i.e. NRC-05, OYS Question Source: (i.e. Bank, Revision History: History: (i.e. distractor "b" to plausible based on ILT Supplied Ref (If appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. Ensure ON-## not provided)

Low KA Justification (if required): T-291 , Rev. 16 H NO 55.43 (b) 5 NEW NEW NEW T-291 , Temperature Effects on Reactor Level Instrumentation NONE N/A EXAM BANK COMPUTER TEST Page: 12 of 77 12 October 2010 5 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is 100% An MSIV AUTO closure occurs: -RPS failed to SCRAM the Reactor -Control Rods were inserted by RRCS -SRV's failed to AUTO open, and had to be MANUALLY opened -Reactor pressure went up to 1330 psig -Reactor level dropped to -130" WHICH ONE of the following is the most limiting action and reportability requirements to the NRC Operations Center for the above conditions? REPORT TO NRC LIMITING CONDITION CENTER WITHIN A. Reactor vessel Safety Limit 24 hours1 days 0.143 weeks 0.0329 months B. Reactor vessel Safety Limit 1 hour C. ECCS system actuation with injection to the vessel 24 hours1 days 0.143 weeks 0.0329 months D. ECCS system actuation with injection to the vessel 1 hour Answer: B Answer Explanation: Reactor vessel Safety limit violation* 1 hour -This is the correct answer because Safety Limit 2.1.3 states in OPCON 1, 2, 3, 4 the reactor coolant system pressure, as measured in the reactor vessel steam done, shall not exceeded 1325 psig. With the reactor coolant system pressure above 1325 psig, be in at least HOT SHUTDOWN with the reactor coolant system pressure less than or equal to 1325 psig within 2 hours0.0833 days 0.0119 weeks 0.00274 months and comply with the requirements of Specification

6.7.1 which

requires the NRC Operations Center be notified as soon as possible and in all cases within 1 hours0.0417 days 0.00595 weeks 0.00137 months of a safety limit violation. Reactor vessel Safety limit violation* 24 hours1 days 0.143 weeks 0.0329 months -This is an incorrect answer because Tech Spec 6.7.1 requires the NRC Operations Center be notified as soon as possible and in all

cases within 1 hours0.0417 days 0.00595 weeks 0.00137 months of a safety limit violation.

EXAM BANK COMPUTER TEST Page: 13 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order DISTRACTOR DISTRACTOR Question 5 Info Question Type: Status: ECCS system actuation with injection to the vessel-24 hours1 days 0.143 weeks 0.0329 months -This is an incorrect answer because per Tech Spec 3.5.1 ACTION f. in the event of an ECCS system is actuated and injects water into the Reactor Coolant System, a special report shall be prepared and submitted to the Commission pursuant to Specification

6.9.3 within

90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The distractor specifies 24 hour notification. The Reporatability Reference Manual requires that an ECCS activation be reported within 4 hours0.167 days 0.0238 weeks 0.00548 months (LS-AA-1020) SAF 1.5 ECCS system actuation with injection to the vessel* 1 hour* This is an incorrect answer because per Tech Spec 3.5.1 ACTION f. in the event of an ECCS system is actuated and injects water into the Reactor Coolant System, a special report shall be prepared and submitted to the Commission pursuant to Specification

6.9.3 within

90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The distractor specifies 1 hour notification. The Reporatability Reference Manual requires that an ECCS activation be reported within 4 hours0.167 days 0.0238 weeks 0.00548 months (LS-AA*1020) SAF 1.5 Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8838 8838 LGSOPS1800.07 Safety Limit violation and reportability requirement

4.1 295025

2.4.30 General Data Technical Reference with Safety Limit 2.1.3, Tech Revision Number: Spec 3.5.1 ACTION f Cognitive Level L PRA: (i.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.43 (b) 5 Question NRC-05, OYS Question Source: (Le. New. Bank. EXAM BANK COMPUTER TEST Page: 14 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Revision History: Revision Modified History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If none appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 150f77 12 October 2010 6 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: -OPCON -A fuel bundle 43-20 is being seated in the The RO reports that SRM 'C' count rate has changed from 70 to 290 cps. -All other SRMs remain at 70 cps or less, WHICH ONE of the following describes the required actions and the basis for those actions? Required Basis for Required Action Raise fuel bundle 43-20 Raising the fuel assembly will return the until it clears the top guide. core to a sub-critical configuration. Evacuate the fuel floor and Evacuation of Fuel Floor is necessary for ensure all insertable control safety of personnel. Inserting insertable rods are inserted. rods ensures that the core is made as critical as possible, Notify shift supervision and Shift Supervision should be aware of any verify normal ventilation is problems associated with reactivity, A leak isolated and SGTS is resistant boundary must be restored within initiated, an hour of an accident in the refueling area, Control and monitor HVAC systems which exhaust to the south releases from Refuel Floor stack are unfiltered but capable of being ensuring NORMAL refuel monitored to allow for dose reduction floor ventilation and rad, techniques, monitoring in service, Answer: A Answer Explanation: Raise fuel bundle 43-20 until it clears the top guide. Raising the fuel assembly will return the core to a sub* critical configuration: Since the control rods would have to be withdrawn for maintenance for the criticality to occur, they would be blocked out of service, Thus, they would not insert when high flux causes a scram signal. If the control room operator observes SRM count rate increasing due to sub-critical multiplication, stopping insertion of the fuel assembly may prevent criticality. Raising the fuel assembly will return the core to a sub-critical configuration. EXAM BANK COMPUTER TEST Page: 16 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Evacuate the fuel floor and ensure all insertable control rods are inserted. Evacuation of Fuel Floor is necessary for safety of personnel. Inserting insertable rods ensures that the core is made as sub-critical as possible: Evacuation of Fuel Floor is necessary for safety of personnel only if a criticality occurs. Additionally, the first action taken if count rate doubles with a fuel assembly grappled is to raise the fuel assembly returning the core to a sub-critical configuration. DISTRACTOR Notify shift supervision and verify normal ventilation is isolated and SGTS is initiated. Shift Supervision should be aware of any problems associated with reactivity control. A leak resistant boundary must be restored within an hour of an accident in the refueling area: Shift supervision must be notified; however, the answer is incorrect because action to isolate normal ventilation and initiate SBGT is required per ON-120 in the event an irradiated fuel bundle is dropped or damaged, NOT in the event of count rate doubling. When ON-120 is entered, only that section which corresponds to the i present symptom is required to be performed. Control and monitor releases from Refuel Floor ensuring normal refuel floor ventilation and associated radiation monitoring in service. HVAC systems which exhaust to the south stack are unfiltered but capable of being monitored to allow for dose reduction techniques: When ON-120 is entered, only that section which corresponds to the present symptom is required to be performed. Action to verify normal ventilation is required per ON-120 in the event an irradiated fuel bundle is dropped or damaged and refuel floor secondary containment is NOT established, The answer is incorrect because this action is NOT required in the event of count rate doubling. EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 6 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8862 8862 LGSOPS1550.IL 1, AND IL2 OPCON 5 with SRM counts high 4.0 4.2 295023, 2.4.11 General Data Technical Reference with ON-120 BASES, Rev. 17 Revision Number: Cognitive Level PRA: (I.e. Yes 10CFR 55.43 (N/A for RO) Question History: (Le. LGS NRC-05, OYS CERT-04) Question Source: (Le. New, Bank, Modified) Revision History: Revision History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (I.e. l\ Excluded

Reference:

(I.e. Ensure ON-## not provided)

BANK Modified Modified stem to indicate count rate doubling WITHOUT a continuous increase which would have confirmed criticality. Also modified stem to indicate the fuel bundle was still grappled. These changes changed the correct answer from "Evacuate the floor and insert all insertable rods" to "Raise the fuel bundle until it clears the top guide. Added requirement to choose action and basis for required action to better align the question with the KIA: Knowledge of abnormal conditions procedures. NONE NONE EXAMINATION ANSWER KEY ILT09-1 SRO questions in sample plan order ___ __________.. '. 7 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: Points: 1.00 A radiological emergency was declared 1 hour ago due to a loss of annunciators concurrent with a steam leak in the Unit 2 Reactor Enclosure. All available methods to isolate the leak have been attempted without success. The following 00-Z559 "MCR RMDS Workstation" indications exist: WIDE RANGE MON ITOR RE2B07B-4

2.224E+02 UC/S -WIDE RANGE MONITOR RE2B076-2

1.136E-06 UC/ML -NORTH STACK VENT RE26075A-1

== 2.992E+07 UC/ML -NORTH STACK VENT RE26075B-1 == 2.927E+07 UC/ML -SOUTH STACK VENT RE26285A-3

3.584E-02 UC/ML -SOUTH STACK VENT RE26285B-3

== 3.182E-02 UC/ML Table R1 --Effluent Monitor Thresholds General Emeruency I Site Area Emergency I Alert I Unusual Event 1.92 E+08 ,ICi/sec I 1.92 E+07 I 2.20 E+06 IICi/sec 2.20 E+04 North (WR Monitor: -.. 2.71 E-D1 "Cifcc I 2.71 E-02 uCilcc I 3.09 E-03 I 3.09 E-05 South Stack (Unit 1: RY26-185A-$' RY26-185-B-3 or Unit 2: RY26*285A-$ f RY26.285-B-3) WHICH ONE of the following is correct regarding the source of the offsite release and required procedure to mitigate the release South Stack Ventilation Enter and execute T-104 Radiological South Stack Ventilation Exhaust, Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination North Stack Ventilation Enter and execute T-104 Radiological North Stack Ventilation Exhaust, Perform ST-B-104-880-0, Gaseous Effluent Dose Rate Determination Answer: A Answer Explanation: ISouth Stack Ventilation Exhaust, Enter and execute T -104 Radiological Release: Correct, The Unit 2 South Stack Noble Gas (-3) channel is above the ALERT threshold of table R-1, therefore meeting 104 entry condition of ALERT or higher offsite release. EXAM BANK COMPUTER TEST Page: 20 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order DISTRACTOR DISTRACTOR DISTRACTOR Question 7 Info Question Type: Status: Always select on Authorized for Time to -Defined ID: s Reference Number: !Topic: Num Field 1: Num Field 2: Text Field: Comments: trlD South Stack Ventilation Perform ST 104-880-0, Gaseous Effluent Dose Determination: Incorrect, Release point correct, 104-880-0 directed ONL Y due to North or South Stack Hi Alarms (no annunciators North Stack Ventilation Enter and execute T -104 Radiological Incorrect, The Unit 2 South Stack Noble Gas (-3) is above the ALERT threshold of table R-1, procedure North Stack Ventilation Perform ST 104-880-0, Gaseous Effluent Dose Determination: Incorrect, Release point incorrect, ST 104-880-0 directed ONLY due to North or South Stack Hi Alarms (no annunciators Multiple Choice Active No No 1.00 3 3.00 8860 8860 LLOT-1790 OBJ 4 T -104 entry on high stack rad 2.5 3.3 295038 EA2.04 General Data Technical Reference Revision Cognitive PRA: (Le. Yes or No or 10CFR 55.43 (N/A for Question History: (Le. NRC-05, OYS Question Source: (Le. Bank, T -104, Rad ioactivity Release Control and AA-1008 Radiological Emergency Plan Annex for LGS L NO 55.43 (b) 5 New New EXAM BANK COMPUTER TEST Page: 21 of 77 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Revision History: Revision New I History: (i.e. Modified distractor "b" to make ! plausible based on OTPS review) I ! Supplied Ref (If (Le. i Excluded

Reference:

(Le. Tech Spec . Ensure ON-## not  KA Justification (if i EXAM BANK COMPUTER TEST Page: 22 of 77 12 October 2010 8 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: -100% reactor power -Secondary Containment Ventilation is in a normal alignment

-Secondary Containment -.3 inches WG One of the running Reactor Enclosure Exhaust Fans trips and the "AUTO" Fan fails to start resulting in the following conditions: -Reactor Enclosure indicate downscale (high -ANN 004 VENT B-3, "REAC ENLC LOW Delta PI LOSS OF POWER I -NO operator actions are WHICH ONE of the following identifies Secondary Containment 5 minutes later and the required action? Secondary Required Action -.25 inches WG Initiate a Low dIp Secondary Containment Isolation per S76.8.B, INITIATION OF REACTOR ENCLOSURE OR REFUELING FLOOR SECONDARY CONTAINMENT B. Greater than -.25 inches Shutdown Reactor Enclosure Supply (more Fans per S76.2.B, SHUTDOWN OF REACTOR ENCLOSURE HVAC -.25 inches WG Secure SGTS Fans per S76.8.A, MANUAL STARTUP AND SHUTDOWN OF SGTS D. Greater than -.25 inches Initiate a Low dip Secondary (more Containment Isolation per S76.8.B, INITIATION OF REACTOR ENCLOSURE OR REFUELING FLOOR SECONDARY CONTAINMENT Answer: D Answer Explanation: EXAM BANK COMPUTER TEST Page: 23 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Greater than -.25 inches WG (more positive); Initiate a Low dip Secondary Containment Isolation per S76.8.B, INITIATION OF REACTOR ENCLOSURE OR REFUELING FLOOR SECONDARY CONTAINMENT. This is correct because when the reactor enclosure exhaust fan trips and the standby fan fails to start, Reactor enclosure configuration will be aligned with 2 supply fans and 1 exhaust fan. This configuration will result in pressurizing the RE. When reactor enclosure pressure reaches +3.5" H20, the reactor enclosure supply and exhaust fans will trip on interlock. Per ARC 004 VENT 3, REAC ENCL LOW DELTA PI LOSS of POWER IINOP, If Reactor Enclosure Delta P is -0.1" H20 for more than 50 minutes, THEN RE and Primary Containment groups VIA and VIB isolate. It will take 50 minutes for the automatic isolation to occur and standby gas to initiate. The question asks the status of Reactor Enclosure HVAC delta pressure 5 minutes later. RE delta P will still be positive. ARC 004 VENT B-3, step directs IF DELTA P is off scale positive, THEN consider initiating a low delta P secondary containment isolation per S76.8.B. The RX ENCLlOutside . DIV A (PDI 76-198A) is offscale positive at +.05 inches wg. -.25 inches WG; Initiate a Low dIp Secondary Containment Isolation per S76.8.B, INITIATION OF REACTOR ENCLOSURE OR REFUELING FLOOR SECONDARY CONTAINMENT. This is incorrect because SGTS will not be in-service at this time. The question stem specifies 5 minutes after the failure of the fan to i start. SGTS will auto start 50 minutes after a loss of Delta , P therefore -.25 delta p cannot be obtained. 1-====--::-:::-=-=---+-=----,-,. ---=-::-::--::-.-:-::-:--:::-::---- --.. ----j Greater than -.25 inches WG (more positive); Shutdown Reactor Enclosure Supply Fans per S76.2.B, SHUTDOWN OF REACTOR ENCLOSURE HVAC. This is incorrect because the ARC directs S76.8.B for initiating an isolation signal. -.25 inches WG; Secure SGTS Fans per S76.8.A, MANUAL STARTUP AND SHUTDOWN OF SGTS. This is incorrect because SGTS will not be in-service at this time. The question stem specifies 5 minutes after the failure of the fan to start. SGTS will auto start 50 minutes after a loss of Delta P therefore -.25 delta p cannot be I obtained. Additionally, the wrong procedure is referenced WII!.... '.:;lll the isolation and starting SGTS (should be EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 8 Info *Question Type: Multiple Choice *Active i Always select on test? No Authorized for practice? No *1.00 Time to Complete: 4 ,QLfficu It}'.: 4.00 !System ID: User-Defined ID: f-=-.... Cross Reference Number: LLOT0200.03 , 8, 9 Unit 1 100% reactor power Secondary Containment . Topic: Ventilation is in a normal alignment Secondary Num Field 1: Num Field 2: Text Field: 295035 General Data Technical Reference with ANN-004 B-3, Revision Number: ON-111, S76.8.B Cognitive Level H Justification for Non SRO 55.43 (b) 5 CFR Link: Question History: (I.e. LGS IL T Cert Exam 2005 NRC-05, OYS CERT-04) .. Question Source: (I.e. New, Bank Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision Bank History: (I.e. Modified distractor "b" to make plausible based on OTPS

review) I ILT I Supplied Ref (If None
appropriate): (I.e. ABN-#ft) Excluded

Reference:

(i.e. N/A Ensure ON-## not LORT PRA: (I.e. Yes or No or #) N LORT Question Section: A (I.e, A-Systems or B-Procedures) i i EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 8 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 26 of 77 12 October 2010 9 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 1 was operating at full power when a loss of EHC caused a Main Turbine trip, and an Anticipated Transient Without Scram (ATWS) with the following:

-Reactor power is 15% -Reactor level is maintained by T -117, LEVEL/POWER CONTROL -Reactor pressure is maintained between 800 -900 with SRV's -Suppression Pool temperature is 167°F and rising slowly -Suppression Pool level is 20 ft. WHICH ONE of the following identifies the required action for the given conditions? A. Lower Reactor pressure to below 700 psig S. T-112, EMERGENCY SLOWDOWN, is required C. Restore Reactor pressure in band between 990 and 1096 psig D. Restore Reactor pressure in band between 900 and 1000 psig Answer: A Answer Explanation: Lower Reactor pressure to below 700 psig This is correct because with the conditions given above the Suppression Pool temperature is 167 degrees and rising slowly, Suppression Pool level is 20 ft with reactor pressure of 800 to 900, it can be determine that the operating point is currently still on the safe side of the curve but cannot be maintained there. Sprr-8 states If Supp Pool temp Cannot be maintained on the safe side of Curve SPIT -1, Then maintain RPV press on the safe side ! of Curve Sprr-1. Reducing reactor pressure to below 700 psig will provide operating point margin by shifting to the next lower pressure curve. T-112, EMERGENCY BLOWDOWN, is required -This is incorrect because with the conditions given above Suppression Pool temperature is 167 degrees and rising slowly, Suppression Pool level is 20 ft with reactor pressure of 800 to 900, it can be determine that the operating point is currently still on the safe side of the curve but cannot be maintained there due to rising suppression pool temperature. Action must be taken to prevent an operating point on the unsafe side of the curve. Conditions of sprr-9 Stop Sign are not yet met requiring T-112 Emergency Slowdown. EXAM BANK COMPUTER TEST Page: 27 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Restore Reactor pressure in band between 990 1096 psig -This is incorrect because with the given above Suppression Pool temperature is 167 and rising slowly, Suppression Pool level is 20 ft reactor pressure of 800 to 900, it can be determine the operating point is currently still on the safe side of curve but cannot be maintained there. Raising Pressure above 990 psig would result in the use of pressure curve that would result in an operating pOint the unsafe region of the curve adding additional heat to the

Suppression Pool and reducing Heat Capacity.

Restore Reactor pressure in band between 900 1000 psig -This is incorrect because with the given above Suppression Pool temperature is 167 and rising slowly, Suppression Pool level is 20 ft reactor pressure of 800 to 900, it can be determine the operating point is currently still on the safe side of curve but cannot be maintained there. Raising Pressure above 901 psig would result in the use of pressure curve that would result in an operating point the unsafe region of the Question 9 Info *Question Type: Multi(lle Choice

Active Always on test? No Authorized for practice?

No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 ... 6180 *User-Defined 6180 Cross Reference Number: LGSOPS 1560.1 L6 ATTACHMENT: HEAT CAPACITY TEMPERATURE LIMIT I Topic: CURVE, is required Unit 1 was operating at full power i Num Field 1: 3.9 Num Field 2: 4.2 1-=--. Text Field: 2950132.1.25 Comments: General Data . Technical Reference with T-102 I Revisio Revision Number: n#: H Justification for Non SRO 55.43 (b) 5 CFR Link: I I

Question History: (i.e. Bank NRC-05, OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified)

Low KA Justification (if required): EXAM BANK COMPUTER TEST Page: 28 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Revision History: Revision Changed question stem, History: (Le. Modified one distractor, and distractor "b" to make answer to acoutn for plausible based on OTPS changes in curve

review) h IU
Supplied Ref (If HCTL curve rE0pr;ate): (i.e. ABN-##) Excluded

Reference:

(Le. T-102

Ensure ON-## not provided)

,.-' .... LORT PRA: (Le. Yes or No or #) Y LORT Question Section: A (Le, A-Systems or Procedures) Question 9 Table-Item links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 29 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8864 Points: 1.00 Unit 2 plant conditions are as follows: -An ATWS is in -MSIVs are -Reactor pressure maintained 990 to 1096 using -SLC pumps have injected to a tank level of 1,000 -Reactor Enclosure (RE) is -Reactor water level was intentionally lowered to lower reactor -Level reaches -150" at which time all APRMs are WHICH ONE of the following describes systems available for injection and actions necessary prior to injection? Systems available Action necessary prior to injection HPCIONLY T-251 , HPCIINJECTION TO EO lifts lead in AER HPCI and RCIC T-251, TO EO lifts lead in AER RCIC ONLY T-247 , BYPASS RCIC LOW PRESSURE ISOLATION -EO lifts leads in AER HPCI and RCIC T-247, BYPASS RCIC LOW PRESSURE ISOLATION -EO lifts leads in AER Answer: B Answer Explanation: HPCI and RCIC, T -251, HPCllnjection to Feedwater EO lifts lead in AER -This is the correct answer due to the appropriate systems for maintaining level during an ATWS are those which inject outside the core shroud, mixing the relatively cold injected water with the warmer water in the lower plenum prior to it reaching the core, limiting the addition of positive reactivity. T-251, HPCI Injection to Feedwater, ensures HPCI injects to the "An Feedwater line only, eliminating injection to the "B" Core Spray header which is inside the shroud. RCIC injects to the "B" Feedwater line, also outside the shroud. EXAM BANK COMPUTER TEST Page: 30 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order HPCI ONLY, T -251, HPCllnjection to Feedwater -EO lifts lead in AER -This is an incorrect answer due to the appropriate systems for maintaining level during an ATWS are those which inject outside the core shroud mixing the relatively cold injected water with the warmer water in the lower plenum prior to it reaching the core, limiting the addition of positive reactivity. T-251 , HPCI Injection to Feedwater, ensures HPCI injects to the "A" Feedwater line only, eliminating injection inside the shroud; however, RCIC also injects to the "8" Feedwater line, outside the shroud, and is also available for injection and is not included. RCIC ONLY, T -247, Bypass RCIC Low Pressure Isolation -EO lifts leads in AER -This is an incorrect answer due to RCIC injecting to the "8" Feedwater line, outside the shroud; however, bypassing the RCIC low pressure isolation is unnecessary prior to injection. Answer is also incorrect because HPCI is also available. T-251 , HPCllnjection to Feedwater, ensures HPCI injects to the "A" Feedwater line only, eliminating injection to the "8" Core Spray header which is inside the shroud. RCIC and HPCI, T-247, Bypass RCIC Low Pressure Isolation -EO lifts leads in AER -This is an incorrect answer due to the appropriate systems for maintaining level during an ATWS are those which inject outside the core shroud mixing the relatively cold injected water with the warmer water in the lower plenum prior to it reaching the core, limiting the addition of positive reactivity. RCIC injects to the "8" Feedwater line, outside the shroud; however, answer is incorrect because bypassing the RCIC low pressure isolation in unnecessary prior to injection and because T-251 , HPCllnjection to Feedwater, ensures HPCI injects to the "An Feedwater line only, eliminating injection to the "8" Core Spray header which is inside the shroud. EXAM BANK COMPUTER TEST Page: 31 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 10 Info ! Question Type: Multiple Choice Status: Active ! select on test? No

Authorized for practice?

No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8864 . User-Defined tD: 8864 i Cross Reference Number: LGSOPS2003.IL4 Topic: HPCI RCIC T-200s Num Field 1: 3.8 Num Field 2: 4.0 Text Field: 295014,2.4.35 Comments: k=... .General Data

Technical Reference with Revision Number: Cognitive Level H PRA: (I.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.43 (b) 5 Question History: (I.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (I.e. New, NEW Bank, Modified)

Revision History: Revision NEW History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (I.e. ABN-##) r Excluded

Reference:

(I.e. NONE Ensure ON-## not provided) i I Low KA Justification (if N/A

required}:

'--______...__ .. "-1___________________

' I EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: 8859 Points: 1.00 Unit 2 plant conditions are as follows: -GP-2, Normal Reactor STARTUP in progress -Reactor power is 45% -Total Feedwater flow is 6.8 mlbm/hr -Annunciator GEN STATOR COOLANT TROUBLE. (MCR-125 GEN-1) alarms The EO investigations reveals the following:

214A Load Center tripped due to an electrical fault causing a trip of the "2A" Stator Water Cooling pump with a failure of the "2B" Stator Water Cooling pump to start WHICH ONE of the following identifies the expected Reactor Recirculation Pump response and procedural requirements for the given conditions? Recirc Pump Procedural requirements "2A" Pump tripped, only Enter ON-114, LOSS OF STATOR WATER COOLING, and Insert Control Rods per RMSI "2A" & "2B" Pumps tripped Enter ON-114, LOSS OF STATOR WATER COOLING, and Insert Control Rods per RMSI "2A" Pump tripped, only Enter OT-112, RECIRCULATION PUMP TRIP, and manually scram the reactor "2A" & "2B" Pumps tripped Enter OT-112, RECIRCULATION PUMP TRIP, and manually scram the reactor Answer: A Answer Explanation: EXAM BANK COMPUTER TEST Page: 33 of 12 October 2010 EXAMINATION ANSWER ANSWER ILT09-1 SRO questions in sample plan order "2A" Pump tripped, only -Enter ON-114, Loss of Stator Water Cooling and Insert Control Rods per RMSI IF Feedwater (FW) flow is maintained >44% of rated, THEN *A Recirc Pump trips after a 9 second time delay, AND *8 Recirc Pump trips after an 18 second time delay. Normal feedwater flow at 100% power is 14.8 mlbm/hr. 6.8 mlbm/hr thus relates to @ 46% power / 46% feedflow. As the "2A" Recirc pump trips on loss of Stator Cooling, total feedflow decreases below 44 % and thus the "28" Recirc pump does not trip. The plant experiences a single Recirc pump trip due to loss of Stator cooling, but does not experience a dual Recirc Pump trip which would require a manual scram. IF FW flow is maintained >44% of rated, THEN VERIFY both Recirc Pumps have tripped AND manually SCRAM Rx AND PLACE Reactor Mode Switch in "SHUTDOWN" AND ENTER T-100, Scram/Scram Recovery OR T-101, RPV Control, as applicable. IF one Recirc Pump tripped THEN immediately ENTER OT-112, Recirculation Pump Trip AND PERFORM the following concurrently.

1. VERIFY EHC Load Set is running back. (EHC Set Runback begins after an 8 second time 2. INSERT control rods per Rx Maneuvering Instructions as required to maintain an adequate margin AND to remain within capacity of Main Bypass 3. REDUCE Main Generator reactive load to ZERO MVAR) to minimize Main Generator Stator OT-112, Recirc Pump Trip IF while executing the remainder of this procedure, Recirc Pumps trip, THEN immediately manually Rx AND PLACE Reactor Mode Switch in AND ENTER T-100, Scram/Scram Recovery OR RPV Control, as applicable. (Ref. I EXAM BANK COMPUTER TEST Page: 34 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order DISTRACTOR DISTRACTOR DISTRACTOR Question 11 Info I Question

Status: "2A" & "2B" Pumps tripped -Enter ON-114, L oss of Stator Water Cooling and Insert Control Rods per RMSI: Incorrect due to IF Feedwater (FW) flow is maintained

>44% of rated, THEN *A Recirc Pump trips after a 9 second time delay, AND *8 Recire Pump trips after an 18 second time delay. Normal feedwater flow at 100% power is 14.8 mlbm/hr. 6.8 mlbm/hr thus r elates to @ 46% power I 46% feedflow. As the "2A" Recirc pump trips on loss of Stator Cooling, total feedflow decr eases below 44% and thus the "2B" Recirc pump does not trip. The plant experiences a single Recirc pump trip due to loss of Stator cooling, but does not experience a dual Recirc Pump trip which would require a manual s cram. Answer is plausible if feedwater flow> 44% not understood to cause second Recirc Pump trip. "2A" & "2B" Pump tripped, Enter OT-112, Recirculation Pump Trip, and manually scram the reactor: Incorrect due to IF Feedwater (FW) flow is maintained >44% of rated, THEN *A Recirc Pum p trips after a 9 second time delay, AND *8 Recirc Pump trips after an 18 second time delay. The plant experien cesa Single Recirc Pump trip due to loss of Stator cooli ng, but does not experience a dual Recirc Pump trip whic h would require a manual scram and entry into OT-112. "2A" Pump tripped, only Enter OT-112, Recirc ulation Pump Trip. and manually scram the reactor: I ncorrect due to The plant experiences a single Recirc Pu mp trip due to loss of Stator cooling, but does not experie nce a dual Recirc Pump trip which would require a man ual scram and entry into OT-112. Multiple Always select on test? Authorized for practice? Points: ---. I Time to 3 !Difficulty: 4.00 System 10: I User-Defined 10: Cross Reference Number: .. Topic: Single Recirculation Pump trie and erocedural requirements I Num Field 1: R03.6 *Num Field SRO 3.7 Text Field: 202001 A2.03 Comments: General Data II EXAM BANK COMPUTER TEST Page: 35 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Technical Reference with Revision Number: lCognitive , PRA: {Le. Yes or No or ! 10CFR 55.43 (N/A for Question History: (i.e. LGS I\IRC-05, OYS CERT-04) Question Source: (i.e, New, Bank, Modified) Revision History: Revision History: (Le. Modified distracter "bit to make plausible based on OTPS ILT Supplied Ref (If appropriate): (i.e. ABN-##) . Excluded

Reference:

(Le. Ensure ON-## not provided)

Low KA Justification (if required}: ON-114, Loss of Stator Water Cooling and 112, Recirc Pump Trip H Y 55.43 (b) 5 New New N/A NONE ON-114, Loss of Stator Water Cooling and 112, Recirc N/A I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 12 10: 8865 Points: 1.00 Unit 1 plant conditions are as follows: -OPCON 2 -GP-2, Plant Startup is in progress -AlllRMs are on Range 2 107 REACTOR, H-4, "SRM Upscale/Inoperative" alarms, with the following indicated: -All four UPSCALEIINOP ALARM LAMPS illuminate on 10C603 -All four SRM recorders indicate and REMAIN full downscale WHICH ONE of the following describes the required operator response? Enter ON-109, TOTAL LOSS OF THE SRM, IRM, OR APRM SYSTEMS and immediately perform a Rapid Plant Silutdown per GP-4. Verify automatic scram, place mode switch in shutdown, Enter T-101 or T-100 Suspend Power Ascension per GP-2 and return SRMs to operable status as soon as possible. Enter ON-109, TOTAL LOSS OF SRM, IRM. OR APRM SYSTEMS and commence a Normal Plant Shutdown per GP-3. Answer: A Answer Explanation: Enter ON-109, TOTAL LOSS OF SRM, IRM. OR APRM SYSTEMS and immediately perform a Rapid Plant Shutdown per GP-4: This is correct because SRMIIRM overlap is performed with the IRMs below Range 3, and SRMs are required in the Startup mode with the IRMs below Range 3. If a Neutron Monitoring System becomes inoperable while that system is required to monitor/control neutron flux, then ON-109, Total Loss of SRM, IRM, OR . APRM Systems, directs a rapid plant shutdown per GP-4. ..--...--.-----:-::- ExAM BANK COMPUTER TEST Page: 37 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Verify automatic scram, place mode switch in shutdown, Enter T-101 or T -100: If the number of operable SRM channels is two or more less than required by the Minimum operable Channels per Trip Function requirement of Tech. Spec Table 3.3.6.1, Tech Specs requires that the inoperable channel be placed in the tripped condition within 1 hour. There is no indication in the question stem that the RPS shorting links are removed to enable SRM scram function. The answer is incorrect because all SRM channels are INOP, and ON-109, Total Loss of SRM, IRM. OR APRM Systems, directs a rapid plant shutdown per GP-4 when a Neutron Monitoring System becomes completely inoperable while that system is required to monitor/control neutron flux. Suspend Power Ascension per GP-2 and return SRMs to operable status as soon as possible: If a Neutron Monitoring System becomes inoperative while that system is NOT required to monitor/control neutron flux, then 109, Total Loss of SRM, IRM, OR APRM Systems, directs the return that system to operation as soon as possible. The answer is incorrect because SRM -IRM overlap is performed with the IRMs below Range 3, and SRMs are required in the Startup mode with the IRMs below Range 3. Enter ON-109, TOTAL LOSS OF SRM, IRM, OR APRM SYSTEMS and commence a Normal Plant Shutdown per GP-3: If the number of operable SRM channels is one less than required by the Minimum OPERABLE Channels per Trip Function requirement of Tech. Spec Table 3.3.6.1, Tech Specs requires that the inoperable channel be returned to operable status within 12 hours0.5 days 0.0714 weeks 0.0164 months or the Inoperable channel must be placed in the tripped condition. The answer is incorrect because all SRM channels are INOP and because ON-109, Total Loss of SRM, IRM, OR APRM Systems, directs a rapid plant shutdown per GP-4 when a Neutron Monitoring System becomes completely inoperable while that system is required to monitor/control neutron flux. EXAMINATION ANSWER Il T09-1 SRO questions in sample plan order i Question 12 Info i Question Type: Multiple Choice I Status: Active l6[W8YS select on test? No *Authorized for I=lractice? No 1.00Time to Coml=llete: 3 L Difficultl': 4.00 *Sl'stem 10: 8865 User-Defined 10: 8865 Cross Reference Number: lGSOPS0074.1L 1 AND Il2 Topic: GP-2 Startup with neutron Num Field 1: Num Field 2: Text Field: 215004, General Data I Technical Reference with Tech Spec Table 3.3.6-1 Revision Number: ON-109, Rev 5 Cognitive Level H PRA: (i.e. Yes or No or#) NO 1 OCFR 55.43 (N/A for RO) 55.43 (b) 5 Question History: (Le. LGS NEW NRC-OS, OYS CERT-04) Question Source: (Le. New, NEW 8ank, Modified) Revision History: Revision NEW History: (i.e. Modified , distractor "b" to make plausible based on OTPS review) I ILT --=--": Supplied Ref (If ! NONE A8N-##) I Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

LOW" KA Justification (if N/A required): If EXAM BANK COMPUTER TEST Page: 39 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8866 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor power is -Attempts to inject SLC -RPV Pressure is 990 psig, controlled with Bypass -RPV level is being maintained between -186" and -161" with -No other high pressure injection systems are A steam leak occurs in the RCIC room, with room temp 118°F and rising (T-103, Secondary Containment, MNO temperature is 114°F deg.) Given the following: -T-249, HPCI/RCIC HIGH AREA TEMPERATURE ISOLATION BYPASS -T-250, REMOTE MANUAL PRIMARY CONTAINMENT ISOLATIONS -T-112, EMERGENCY BLOWDOWN WHICH ONE of the following describes the ability to continue to operate RCIC, AND the TRIP or T-200 procedure that describes the reason for the action? Ability to Reason for Action RCIC can continue to operate Perform T-249 to bypass RCIC high temperature isolation RCIC can continue to operate Perform T-112 If RCIC automatically isolates on High Temperature RCIC can continue to operate Perform T-112 prior to reaching RCIC MSO Temperature RCIC must be isolated Perform T -250 for RCIC due to MNO temperate being exceeded Answer: B Answer Explanation: RCIC can continue to operate Perform T-112IF RCIC automatically isolates on High Temperature -This is correct because if RCIC automatically isolated, then RPV level can no longer be restored and maintained above -186 inches, emergency RPV depressurization is required for the purpose of maximizing injection flow from high head pumps and to permit injection from low head pumps. EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order DISTRACTOR DISTRACTOR DISTRACTOR Question 13 Info Question Type: Status: Always select on Authorized for Time to User-Defined Cross Reference Num Field Num Field Text RCIC can continue to operate, Perform T to bypass RCIC high temperature isolation This is incorrect because defeating RCIC System high area temperature isolation interlocks permits continued use of these systems following loss of area coolers or ventilation, such as might occur during a station blackout. If a leak does exist, T-249 cannot be performed. RCIC can continue to operate Perform T-112 if RCIC MSO Temperature is reached -This is incorrect because if Reactor Enclosure temperatures continue to rise and exceed the maximum safe operating (MSO) value in two or more areas, the RPV must be depressurized to preclude further temperature rises. The leak identified ib the Stem is only in one ares, therefore T-112 is not required per T-103. Additionally. RCIC MSO temperature is below the isolation setpoint, so RCIC will continue to operate. and maintain level. RCIC must be isolated Perform T -250 for RCIC due to MNO temperate being exceeded -This is incorrect because LGS TRIP Step SCC/T-5 directs actions to isolate all systems discharging into Reactor Enclosure utilizing 250 unless the system(s} is(are} required for either fire suppression or to accomplish steps directed in the TRIP procedures. Multiple Choice Active No No 1.00 3 4.00 8866 8866 LGSOPS2010.IL Steam leak in RCIC room 3.5 4.4 217000.2.4.16 r-General Data I Technical Reference with

Revision Number: Cognitive Level '--""" PRA: (i.e. Yes or No or #) 10CFR 55.43 (N/A for 1=(0) Question History: (Le. LGS NRC-05, OYS CERT-04) T-103 BASES, Rev. 2023 T-117 BASES, Rev. 2023 55.43 (b) 5
NEW

--I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question Source: (Le. New. NEW Bank. Modified) Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If none appropriate): (Le. ABN:##) Excluded

Reference:

(Le. NONE Ensure ON-## not provided)

Low KA Justification (if N/A re uired):_. EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8867 Points: 1.00 Unit 1 was operating at 100% power with conditions as follows: The following Safety Relief Valve (SRV) failures have been identified: -"1S" SRV deenergized (fuses removed) due to failed solenoid(s) -"1 A" SRV Bellows is confirmed failed -"1 L" SRV Bellows is confirmed failed -All other systems are operable WHICH ONE of the following LCO actions is the most limiting, if any, due to the status of the SRV's? No Tech Spec Actions required Restore required SRV(s) within 14 days, or be in OPCON 3 within next 12 hrs Be in OPCON 3 within 12 hrs. and OPCON 4 within 24 hrs Be in OPCON 3 within 12 hrs. and steam dome pressure <100 psig within 24 hrs Answer: B Answer Explanation: Restore required SRV(s) within 14 days, or be in OPCON 3 within next 12 hrs: Ensures capability to shutdown the plant during adverse conditions The third SRV (1S) is an ADS valve. Although this valve can perform the function of Safety/Relief it will not function in an ADS capability. TECH SPEC 3.5.1.d requires that all five ADS SRVs be functional or the LCO action must be taken. No Tech Spec Actions required: This is incorrect because even though T.S. 3.4.2 is met for a designed MSIV failure with 12 of 14 valves capable of performing their safety function, T.S. 3.5.1.d would still apply with the '1 S' ADS SRV unable to operate in the ADS function of ECCS. Be in OPCON 3 within 12 hrs. and OPCON 4 within 24 hrs: This is incorrect because this action is required for Insufficient SRVs available during a designed MSIV failure << 12 operate on Safety Lift Function) per T.S. 3.4.2. The conditions stated only indicate that '1A' and '1L' SRV will fail to operate on the Safety Lift Function. EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Be in OPCON 3 within 12 hrs. and steam dome pressure <100 psig within 24 hrs: This is incorrect because this action would be appropriate only for the case where 2 of the required ADS SRVs were inoperable per T.S. 3.5.1.d and the conditions stated only indicate '1 S' ADS SRV inoperable. Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 8867 User-Defined ID: 8867 Cross Reference Number: LLOT0330.09 Topic: SRV failures with appropriate LCO's Num Field 1: 3.4 Num Field 2: 4.7 Text Field: 2180002.2.40 Comments: General Data Technical Reference with T.S. 3.4.2, 3.5.1, 3.5.3, Revision Number: 3.3.7.4 i Cognitive Level L 10CFR 55.43 (N/A for RO) 55.43 (b) 2 I Question History: (i.e. LGS Bank NRC-05, OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified) Revision History: Revision Bank History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If T.S 3.3.3, 3.4.2. 3.3.7.4 (I.e. ABN-##) (p-1 only) and 3.5.1 Excluded

Reference:

(I.e. NONE Ensure ON-## not provided)

Low KA Justification (if N/A required): EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order DISTRACT A and C only; Verify Automatic Scram and enter T -101 or T-100 This is incorrect due to reasons above for power loss to IRMs and correct procedure for required actions. Queslio f1 15lnfo **. .__...Question Type: Multiple Choice Status: Active I Always select on test? No . Authorized for practice? No I Points: . 1.00 j Time to ComQlete: -_..__j 3.00 I .. i System ID_:_ 8858 *User-Defined ID: 8858 : Cross Reference Number: LOT0250.10 h=opic: Loss of IRM Qower sUQ[)ly and erocedural reguirements Num Field 1: R02.8 Num Field 2: SRO 3.2 Text Field: 215003 Comments: General Data Technical Reference with ARC 1 A RPS & UPS Dist Revision Number: Pnl120 F-5 and 1A-Y160, Loss of 1A RPS UPS Power I Cognitive Level H PRA: (i.e. Yes or No or #) Y 10CFR 55.43 (N/A for RO) 55.43 (b) S

Question History: (i.e. LGS New NRC-OS, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)

Revision History: Revision N/A History: (Le. Modified distractor "b" to make plausible based on OTPS review) I ILT Supplied Ref (If NONE (i.e. ABN-##) I

Excluded

Reference:

1A-Y160 I Ensure ON-## not provided) ! Low KA Justification (if N/A required): KIA 215003 A2.01 RO 2.8 SRO 3.2 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order EXAM BANK COMPUTER TEST Page: 48 of 77 12 October EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: 8858 Points: 1.00 Unit 1 plant conditions are as follows; -Reactor STARTUP in progress -Neutron Monitoring Overlap Surveillance Test has been completed -Source Range Monitor (SRM) detectors are being withdrawn -Intermediate Range Monitor (IRM) status is as follows: IRM Channel IRM Range switch 4 B C D E F G H Annunciator "1A RPS & UPS DIST PNL TROUBLE" alarm at (120 D11, F-5) alarmed, and investigation revealed the "1A" RPS/UPS inverter 120VAC output breaker(s) trip on undervoltage WHICH ONE of the following identifies the IRMs that lose their power supply and the required action? IRM power supply Required Actions Aand CONLY Perform S94.9.A, Routine Inspection of "An RPS/UPS Inverter A, C, E and G Verify Automatic Scram and enter T-1 01 or T-100 A, C, E and G Perform S94.9.A, Routine Inspection of "A" RPS/UPS Inverter Aand CONLY Verify Automatic Scram and enter T-101 or T-100 Answer: C Answer Explanation: EXAM BANK COMPUTER TEST Page: 45 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order A, C, E and G; Perform S94.9.A, Routine Inspection of "Au RPS/UPS Inverter -This answer is correct because ARC MCR 120 F-5 1A RPS & UPS Distribution trouble alarm identifies a loss of power to panel 1 AC248 which causes a loss of the loads listed on E-32 Sheet 1 with the following OPERATOR ACTIONS: 1. Refer to E-1AY160, "Loss of 1A RPS UPS Power". 2. Dispatch Operator to locally determine the problem with 1AY160 distribution panel source via S94.9.A (Routine Inspection of *A RPS UPS Static Inverter).

3. Consider reportability and Tech Spec implications.

CAUSES: 1. Loss of 125 VDC from Panel1AD102 CKT 17 or 1CD102 CKT 04. 2. Overvoltage, undervoltage or under-frequency condition at RPS breaker Panel 1 AC248 to 1A RPS UPS Distribution Pane11AY160. DEVICE(S}:

81-AY24801 (CY24801)
27-AY24801 (CY24801)
59-AY24801 (CY24801)

E-i AYi60 Procedure step 1.22 identifies loss of AlC SRMs and AlC/E/G IRMs. A GP-2, Normal Plant Startup cannot continue due to a 1/2 scram signal due to a loss of power supply to the 1AY160 panel as referenced by the associated "E" procedure E-1AY160 indicating a 1/2 scram on a loss of the power supply. Also a RMCS control rod block occurs due to the loss of the power supply. Therefore, power operation cannot continue. TECH SPECs require, during a reactor STARTUP (OPCON 2), a minimum of 3 IRMs per trip system to be OPERABLE, or to be in HOT SHUTDOWN within 12 hours0.5 days 0.0714 weeks 0.0164 months . The STARTUP cannot continue until this is corrected. A and C only; Perform S94.9.A, Routine Inspection of "An RPS/UPS Inverter -This is incorrect due to only indicating loss of A and C IRMs contrary to E-1AY160 procedure. The actions of S94.9.A are partially correct. A, C, E and G; Verify Automatic Scram and enter T 101 or T-100 -This is incorrect even though listing the correct IRMs with power loss. There is no indication in the conditions stated for an Automatic Scram requiring entry into either T-101 or T-100. EXAM BANK COMPUTER TEST . Page: 46 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 16 10: 8868 Points: 1.00 Unit 1 plant conditions are as follows: -100% Reactor power 1 B Reactor Recirc MG-Set trips and the following alarms are noted concurrently: -126 AUX BUS 1, A-4, 12 Unit Aux Bus Neg. Phase Sequence -126 AUX BUS 1, B-4, 12 Unit Aux Bus Undervoltage -125 GEN 1, F-4, 12 Bus Breaker Trip WHICH ONE of the following describes the expected impact on the Feedwater system and the appropriate procedural response? Feedwater System Response Enter and Direct Action from All RFPs remain in service GP-5 Appendix 3, Unintentional Drop with speed limited to 78% in Power C RFP trips. A &B remain in OT-110, Reactor High Level service. Speed limited to 78% B & C RFPs trip. A RFP remains in OT-100, Reactor Low Level service with speed limited to 78% All RFPs trip. T-101, RPV Control Answer: A Answer Explanation: All RFPs remain in service with speed limited to 78%; GP 5 Appendix 3, Unintentional Drop in Power -This is correct due to loss of the 12 Aux Bus tripping the 1 B Condensate pump and the 1 B Reactor Recirc MG-Set; additionally, with feed flow initially> 80%, there is a 62% run back of the recirculation system preventing a reactor scram. All Reactor Feed Pumps remain in service, and GP-5 is entered for the unintentional drop in power. C RFP trips. A & B remain in service. Speed limited to 78%; OT-110, Reactor High Level This is incorrect due to plant response on Condensate Pump Trip to reduce power within capacity of remaining two condensate pumps. The partially correct second half of the response is due to the level swell as power is reduced. B & C RFPs trip. A RFP remains in service with speed limited to 78%; OT-100, Reactor Low Level-This is incorrect due to no basis for RFP trips and incorrect reactor level response as power is reduced by 1 A Recirc Pump Trip on loss of 12 Aux bus. L EXAM BANK COMPUTER TEST Page: 49 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order All RFPs trip; T -101, RPV Control -This is incorrect to no expectation for RFP trip on loss of a Condensate Pump. The High Limit runback is designed prevent RFP trips due to low suction pressure resulting from Condensate pump Question 16 Info Question Type: Multi[:>le Choice Status: Active ..--.. Always select on test? No Authorized for practice? No ! Points: 1.00 I Time to Complete: 3 ! Difficulty: 3.00 *System 10: 8868 IUser-Defined 10: 8868 : Cross Reference Number: LGSOPSOO05.IL8C IRFP response to los§ of power i Num Field 1: 3.6 Num Field 2: 3.7 Text Field: 259001, A2.03 Comments: General Data Technical Reference with ARC-MCR-104 F2 Rev 0 Revision Number: Cognitive Level H PRA: (I.e. Yes or No or #) NO 10CFR 55.43(N/A for RO) 55.43 (b) 5 Question History: (I.e. LGS NEW NRC-05, OYS CERT -04) Question Source: (I.e. New, NEW Bank, Modified) i Revision History: Revision NEW History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE (I.e. ABN-##) Excluded

Reference:

(I.e. NONE Ensure ON-## not provided)

Low KA Justification (if I N/A I required): i EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8869 Points: 1.00 An Equipment Operator performing rounds reports that leakage is occurring through PSV-044-208 "REACTOR WATER CLEANUP REGENERATIVE HEAT EXCHANGER". -The RWEO reports Equipment Drain Collection Tank input has risen sharply by 75 gpm. WHICH ONE of the following describes the CRS direction to mitigate the leak, and the applicable surveillance requirement? Direct RO to shutdown RWCU per S44.2.A, perform Drywell Floor Drain Sump I Equipment Drain Tank Surveillance. Direct RO to shutdown RWCU per S44.2.A, direct Shift Chemist to commence Reactor Coolant Conductivity Monitoring. Direct RO to isolate RWCU by closing HV-044-2F004 and HV-044-2F105, perform Drywell Floor Drain Sump I Equipment Drain Tank Surveillance. Direct RO to isolate RWCU by closing HV-044-2F004 and HV-044-2F105, direct Shift Chemist to commence Reactor Coolant Conductivity Monitoring. Answer: D Answer Explanation: Direct RO to isolate RWCU by closing HV-044-2F004 and HV-044-2F105, direct Shift Chemist to commence Reactor Coolant Conductivity Monitoring: Correct answer because Isolation of RWCU should have autom.atically occurred but did not occur due to failure of the differential flow isolation instrumentation. Isolation via 2F004 and 2F105 is directed by ARC-MCR-212-1-3 upon failure to automatically isolate during a high differential flow condition. Conductivity monitoring is required by Chemistry due to loss of flow at normal conductivity sample point per TRM 4.4.4.c.1 within 4 hours0.167 days 0.0238 weeks 0.00548 months . Direct RO to shutdown RWCU per S44.2.A, direct Shift Chemist to commence Reactor Coolant Conductivity Monitoring: Incorrect answer because Shutdown per S44.2.A is not directed by Hi differential flow timer ARC and will not correct the lifted PSV. The second part of the answer is Correct direction to perform conductivity surveillance due to loss of flow at normal conductivity sample point per TRIVl4.4.4.c.1 within 4 hours0.167 days 0.0238 weeks 0.00548 months . EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Direct RO to isolate RWCU by closing and HV-044-2F105, and perform Drywell Floor Sump I Equipment Drain Tank Surveillance: answer because although Isolation direction is correct isolate the PSV per the ARC for RWCU Hi Flow Isolation timer but the Drywell equipment drain surveillance is incorrect because this is not the tank receives PSV discharge flow (Goes to RE Floor Direct RO to shutdown RWCU per S44.2.A, perform Drywell Floor Drain Sump I Equipment Tank Surveillance: Incorrect answer because direction is incorrect for isolating a lifted RWCU PSV the Drywell equipment drain tank surveillance is because this is not the tank that receives PSV I Question 17 Info Question Type: Multiple Status: *Always select on test? No i Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 4.00 System 10: User-Defined 10: Cross Reference Number: Topic: Radwaste leakage identified with appropriate Num Field 1: Num Field 2: Text Field: 204000, General Data Technical Reference with S44.2.A Revision Number: TRM 4.4.4.c.1 i Cognitive Level H PRA: (i.e. Yes or No or #) NO

10CFR 55.43 (N/A for RO) 55.43 (b) 5
Question History: (i.e. LGS NEW
NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified)
Revision History:

NEW History: (Le. Modified

distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If None appropriate): (i.e. ABN-##) I EXAM BANK COMPUTER TEST Page: 52 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: 8870 Points: 1.00 Unit 2 plant conditions are as follows: -OPCON -Monthly ONE ROD OUT INTERLOCK VERIFICATION

TEST, is in progress -A centrally located control rod has been withdrawn to position 02 -The Refuel Bridge is moving from the spent fuel pool through the cattle chute with the main hoist full up and UNLOADED.

WHICH ONE of the following describes the expected refueling equipment response? All control rod motion is blocked as the refuel bridge moves over the core. The Refuel Bridge will automatically stop as the refuel bridge moves over the core. Outward control rod motion ONLY is blocked as the refuel bridge moves over the core. When a fuel bundle is grappled and raised, hoist movement is IMMEDIATELY blocked. Answer: 0 Answer Explanation: .-----. When a fuel bundle is grappled and raised, hoist movement is IMMEOIATEL Y blocked: Main Hoist inoperative when bridge near or over core and any rod not full in with main hoist fuel loaded. All control rod motion is blocked as the refuel bridge moves over the core: Rod block requires bridge near or over core and any hoist fuel loaded. Incorrect because hoist is unloaded. Also incorrect because only outward rod motion is blocked. The Refuel Bridge will automatically stop as the refuel bridge moves over the core: No Bridge motion when bridge near or over core and any hoist fuel loaded with any rod not full in. Incorrect because hoist is unloaded. Outward control rod motion ONL Y is blocked as the refuel bridge moves over the core: Rod block requires bridge near or over core and any hoist fuel loaded. Incorrect because hoist is unloaded. .. **--*----*-*------1C":2....,O,...c-to..,-.-ber 2010 EXAM BANK COMPUTER Page: 54 of 77 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 18 Info Question Type: Status: select on test? Authorized for practice? Points: Time to Comple!e: Difficulty: 10: User-Defined 10: Cross Reference Number: Topic: *Num Field 1: _Num Field 2: .. Text Field: Comments: Multiple Choice Active No No 1.00 3 3.00 8870 8870 LLOT0760.5B Control Rod motion while in Refuel 3.3 4.1 234000, K4.01 General Data I .\ Technical Reference with S97.0.M, Rev. 20

Revision Number: I Level ". L
PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.43 (b) 7 Question History: (Le. LGS NEW NRC-05, OYS CERT-041 Question Source: (Le. New, NEW Bank, Modified)

Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on aTPS review}ILT Supplied Ref (If NONE apQroQriate): {Le. ABN-##l Excluded

Reference:

(Le. NONE Ensure ON-## not provided)_.. N/A Low KA Justification (if EXAM BANK COMPUTER TEST Page: 55 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8876 Points: 1.00 Unit 1 was operation at 100% power when a main generator fault resulted in the following conditions:

-Main Turbine Trip -Automatic Reactor Scram -A" control rods failed to insert -Reactor power 38% -The Full Core Display has the following indications for all control rods: Red Rod Drift Lights ON Orange Scram Accumulator Lights ON Blue Scram Lights ON Red Rod Full Out Indication OFF An SRO is executing the RC/Q leg of T-101 WHICH ONE of the following procedures should the CRS direct personnel to perform? T-213, Individual Control Rod Scram/Solenoid De-energization T-215, De-enerization of Scram Solenoids T -216, Manual Isolation and Vent of Scram Air Header T-217, RPS/ARI Reset and Backup Method of Draining Scram Discharge Volume Answer: D Answer Explanation: T-217, RPS/ARI Reset and Backup Method of Draining Scram Discharge Volume -This is the correct answer because analyzing the information in the stem it can be determined that RPS actuated as indicated by all Blue Scram Lights being lit and Scram Accumulator Lights lit, some control rod movement occurred, Red Rod Full Out Indication not lit and Rod Drift lights lit. This is not a failure of RPS but rather an hydraulic problem preventing the Rods from inserting. Of the T-200 procedures provided, only T-217 is a viable option. T-213, T-215 and T-216 are contingencies for a RPS failure. T-217 is the only contingency that addresses Scram Discharge blockage. T -213, Individual Control Rod Scram/Solenoid energization -This is incorrect because the Blue Scram Lights lit and Accumulator Orange Light lit indicates that RPS Scram Pilot Solenoid Valves have already energized to allow the pneumatic scram valves to open. T-213 would not provide any benefit since RPS has already de-energized : EXAM BANK COMPUTER TEST Page: 56 of 12 OctOber 2010

EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order r-::-:-:=::::-:c-=-::::::-::-::=----

T -215, De-energization of Scram Solenoids -This incorrect for the same reasons as above. T -215 would provide any benefit since RPS has already T-216, Manual Isolation and Vent of Scram Air -This is incorrect for the same reason as above since Blue Scram Lights lit indicate that the Scram Air already been depressurized. T-216 would not provide benefit since RPS had actuated and the Scram Air is already -Question 19 Info . Multiple vnOlce Status: Active Always select on test? No for practice? No 1.00'litre to Complete: 2 . . Sy-stem 10: 18876 User-Defined ID: 8876 Cross Reference Number: illOT0760.5B Topic: TRIP execution with Control Rod Num Field 1: r--c--------. --f----.--.-Num Field 2 Text Field: Comments: -=--_ General Data Technical Reference with T-102, Primary Revision Number: Containment Control Level _____ J::L ____ PRA: (i.e. Yes or f\J()_or #) NO ,..1QfFR 55.43 (N/A for Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS _______ ILT f------.--------.------------------------Supplied Ref (If NONE ABN-##} Excluded

Reference:

(Le. NONE Ensure ON-## not provided) r-cow KA Justification (if N/A requiredt I Page: 57 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 5013 Points: 1.00 Unit 1 plant conditions are as follows: -ST-6-092-364-1.

D14 DIESEL GENERATOR OPERABILITY VERIFICATION, is in progress: -The EO working locally at the EDG reports that the procedure directs operation of LOCAL-REMOTE SELECTOR SWITCH "43-DG207" -The EO verifies that this switch number should be "43-DG501" WHICH ONE of the following describes the actions necessary to complete this ST? Complete the ST. then submit a PPIS for the change per HU-AA-104-101, Procedure Use and Adherence Complete the ST. then submit a TC for the change. AD-LG-101-1002 Temporary Changes To Approved Documents and Partial Procedure Use Stop the ST. process a PPIS for the change per HU-AA-1 04-1 01, Procedure Use and Adherence. then continue Stop the ST. process a TC for the change per AD-LG-101-1002 Temporary Changes To Approved Documents and Partial Procedure Use. then continue Answer: D Answer Explanation: Stop the ST, process a TC for the change per AD*LG*101* 1002 Temporary Changes To Approved Documents and Partial Procedure Use, then continue This is correct because Temporary Changes (TC) to procedures or T&RMs should be issued when the existing document is in error. Per procedure step 4.2.2. errors in eqUipment numbers. eqUipment condition (on/off, open/closed). numerical values. and sample calculations are to be considered TCs and NOT PPISs. Per HU-AA-101-104, when procedural errors are identified. STOP AND NOTIFY supervision, initiate appropriate changes prior to continuing or attempting again. EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Complete the ST, then submit a PPIS for the change per HU-AA-104-101, Procedure Use and Adherence -This is incorrect because the switch designation in the procedure is incorrect and the procedure can not be performed as written. The Procedure Performance Improvement System is designed for enhancements that do not need to be corrected prior to continuing.

,

.. Complete the ST, then submit a TC for the change, LG-101-1002 Temporary Changes To Approved Documents and Partial Procedure Use -This is incorrect because the procedure cannot be performed as written. AA-1 04-1 01 paragraph 3.1.8.2 says, "STOP whenever the procedure cannot be performed as written ... and continues to direct notifying Job Supervisor. This is repeated in paragraph 4.1.6. Stop the ST, process a PPIS for the change per 104-101, Procedure Use and Adherence, then This is incorrect because the Procedure Performance Improvement System (PPIS) is designed for enhancements that do not need to be corrected prior to continuing. .. Q uestion 20 Info Q uestion T:tQe: S tatus: A Iways select on test? A for P oints: T 2 D ifficultt 3.00 S iystem ID--.: ___5013 ....1U ser-Defined 10: 5013 C ross Reference Number: I T 0 Procedural compliance with EDG oQe!ability N um Field 1: i3.0 N um Field 2: T ext .2.2.6 C omments: General Data Technical Reference with HU-AA-104-Revisio Revision Number: 101 n #: .. ---. r 1002 L PRA: N--..10CFR 55.43 55.43 {bP .. Question History: (i.e. LGS BANK . NRC-05, OYS CERT-04) ..-Question Source: (i.e. New, BANK Bank, Modified) EXAM BANK COMPUTER TEST Page: 60 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Low KA Justification (if N/A Revision History: Revision Added procedure History: (Le. Modified references, still distractor "b" to make considered bank Q plausible based on OTPS ILT 3 Supplied Ref (If NONE (Le. ABN-##__ . Excluded

Reference:

(Le. AD-LG-101-1002 Ensure ON-## not provided HU-AA-104-101 . NRC EXAM -10 CFR 55 Operators' Licenses CFR: 41.10 Administrative, normal, abnormal, and emergency operating procedures for the facility.

10 CFR 55.43 SRO WRITTEN EXAMINATION CFR: 43.2 Facility operating limitations in the technical specifications and their bases. CFR: 43.3 Facility licensee procedures required to obtain authority for design and operating changes in the facility. CFR: 45.13 Demonstrate the applicant's ability to function within the control room team as appropriate to the assigned position, in such a way that the facility licensee's procedures are adhered to and that the limitations in its license and amendments are not violated. Higher Limerick SRO EXAM BANK COMPUTER TEST Page: 61 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8891 Points: 1.00 Unit 1 plant conditions are as follows: -GP-4, Rapid Plant Shutdown was performed due to a loss of Drywell Cooling -Drywell pressure is 1.9 psig up slow -'A' and 'B' SBGT fans both failed to start -Due to a fuel cladding failure, elevated radiation levels exist in the Main Steam and HPCI Steam Supply piping -Radiation levels in the Outboard MSIV Room and HPCI Pump Room are above Max Normal Operating (MNO) Values Due to NO operating HVAC, Outboard MSIV room temperatures are approaching MNO WHICH ONE of the following actions shall be directed to mitigate degrading plant conditions? T-250 REMOTE MANUAL PRIMARY CONTAINMENT ISOLATIONS. to isolate HPCI prior to radiation level exceeding the Max Safe Operating (MSO) value ST 076-360-1. RX ENCL SEC CNTMT INTEGRITY VERIFICATION. to verify that penetrations/access paths into the RX ENCL SEC CNTMT are closed and sealed T-227 BYPASS OF REACTOR ENCLOSURE HVAC HIGH DRYWELL PRESSURE / LOW RPV WATER LEVEL / LOW DP ISOLATION, to restore Reactor Enclosure Temperatures and Pressure to normal T-112 EMERGENCY BLOWDOWN. to depressurize the Reactor when MSO Radiation levels in the HPCI and OBMSIV rooms are exceeded Answer: C Answer Explanation: EXAM BANK COMPUTER TEST Page: 62 of 12 October 2010 EXAMINATION ANSWER I L T09-1 SRO questions in sample plan order T-227 BYPASS OF REACTOR ENCLOSURE HIGH DRYWELL PRESSURE /LOW RPV LEVEL/LOW DP ISOLATION, to restore Enclosure Temperatures and Pressure to Correct because due to the loss of Secondary Containment as Reactor Enclosure HVAC (REHVAC) isolates with drywell pressure exceeding 1.68 psig, and with Standby Gas (SGBT) unable to maintain Secondary Containment their exists no ventilation in the Secondary Containment. Maximum normal operating (MNO) value are approached as Reactor Enclosure temperatures continue to increase, the continued operability of equipment needed to carry out TRIP procedure actions may be compromised. High Reactor Enclosure area temperatures also present a danger to personnel, a consideration of significance since access to the The Reactor Enclosure HVAC System is the system normally used to maintain Reactor Enclosure temperature and differential pressure within operational limits. If isolated, it is appropriate to re-start the Reactor Enclosure HVAC System and use it to restore and maintain control of Reactor Enclosure temperature and pressure once it has been confirmed that re-start will not result in an excessive release of radioactivity to the environment. Defeating high drywell pressure, low RPV level, and low differential pressure isolation interlocks is appropriate, if needed, since application of these isolations to the Reactor Enclosure HVAC System is for the sole purpose of limiting radioactivity release to the environment. Once assurance is provided that excessive release of radioactivity will not occur, these three isolation interlocks

become dispensable.

T-250 REMOTE MANUAL PRIMARY ISOLATIONS, to isolate HPCI prior to radialion exceeding the Max Safe Operating (MSO) T-250, Remote Manual Primary Containment Isolations, provides guidance on isolating possible leakage sources which are contributing to existing Reactor Enclosure high temperature, radiation, and or water level conditions. No system is currently leaking into the RE Enclosure, the elevated temperatures are due to no ventilation. Continued operation of damage control systems required to protect personnel, plant structures, or essential equipment is permitted since these objectives generally , take precedence over control of secondary containment '---_____.1 area temperatu_re_s_,__ EXAM BANK COMPUTER TEST Page: 63 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order ST *6*076*360-1, RX ENCL SEC CNTMT INTEGRITY VERIFICATION, to verify that penetrations/access paths into the RX ENCL SEC CNTMT are closed and sealed ST-6-076-360-1. RX ENCL SEC CNTMT INTEGRITY VERIFICATION. to verify that penetrations/access paths into the RX ENCL SEC CNTMT are closed and sealed Confirming isolation of the Reactor Enclosure HVAC System subsequent to receipt of a high radiation isolation signal terminates any further release of radioactivity to the environment from the Reactor Enclosure HVAC System. The Standby Gas Treatment System (SBGT) is the normal mechanism employed under post-transient conditions to maintain Reactor Enclosure pressure negative with respect to the atmosphere since the exhaust from the SBGT is processed and directed to an elevated release point before being discharged to the environment. SBGT is required per the procedure in the event of an isolation, however SSGT failed to maintain Secondary Containment. T*112 EMERGENCY BLOWDOWN, to depressurize the Reactor when MSO Radiation levels in the HPCI and OBMSIV rooms are exceeded: Incorrect due to when it has been determined that a primary system discharge is discharging into the Reactor Enclosure. operators are directed to shutdown and depressurize the reactor. As mentioned previously. when Reactor Enclosure radiation levels have risen in two areas. the RPV must be depressurized. MSO temperatures or radiation levels must be due to a primary system leaking for the operator to perform a Emergency Slowdown. RPV depressurization places the primary system in its lowest possible energy state, rejects heat to the suppression pool in preference to outside the primary containment. and reduces the driving head and flow of primary systems that are unisolated and discharging into the Reactor Enclosure. EXAM BANK COMPUTER TEST Page: 64 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 21 Info No No Points: 1 Time to Com lete: Difficulty: 3.00 I=s==st=e=m:::=I=O=: User-Defined 10: C Rf ross e erence um er: -i Topic: T-103 temperatures and steam leak reguiring REHVAC Num Field 1: R03.4 Num Field 2: SRO 3.8 Text Field: 2.3.14 Comments: General Data Technical Reference with T -227, Bypass of Reactor Revision Number: Enclosure HVAC High Orywell Pressure I Low RPV Water Level I Low OP Isolation T -103, Secondary Containment Control Cognitive Level. H PRA: (i.e. Yes or No or #) Y 10CFR 55.43 (N/A for RO) 55.43 (b) 5 Question History: (i.e. LGS New NRC-05, OYS CERT-04) Question Source: (I.e. New, New Bank, Modified) Revision History: Revision New History: (I.e. Modified distractor "b" to make plausible based on OTPS reviewt ILT Supplied Ref (If I NONE appropriate}: {i.e. Excluded

Reference:

(I.e. T-103, ON-iii Ensure ON-## not provided)

I Low KA Justification (if N/A I EXAM BANK COMPUTER TEST Page: 65 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8877 Points: 1.00 Unit 2 Plant conditions are as follows: A large break LOCA has occurred -RPV Level dropped to -310" is stable at -207" -DIW Pressure reached at 18 PSIG then rapidly dropped to 3 PSIG when the seal on the drywell equipment hatch -MET Data indicates wind is from 88 degrees at 5 -A General Emergency has been Which ONE of the following protective action recommendation should be taken? Evacuation Downwind Sectors A. Evacuate 2 Mile Radius I 5 Mile Downwind ENEI E I ESE B. Evacuate 2 Mile Radius I 5 Mile Downwind WSW/W/WNW C. Evacuate 5 Mile Radius I 10 Mile Downwind ENE/E/ESE D. Evacuate 5 Mile Radius 110 Mile Downwind WSW/W/WNW Answer: D Answer Explanation: Evacuate 5 Mile Radius 110 Mile Downwind WSW I W I WNW This is correct because RPV level at <-186", results it a Fuel Clad Barrier LOSS and a Reactor Coolant System Barrier LOSS. The rapid drop in Drywell Pressure would result in a Primary Containment Barrier LOSS per EP-AA-1008. These conditions would result in a declaration on a General Emergency due to a LOSS or Potential Loss of all three fission product barriers. In evaluating the PAR per EP-AA-111-F-08, a loss of three fission product barriers would result in evacuation of 5-Mile Radius and 10-Mile downwind Sectors. Since the wind was from 88 degrees, WSW I W I WNW downwind sectors would be affected. Evacuate 2 Mile Radius I 5 Mile Downwind ENE I E I Incorrect due to this evacuation is based on loss of 2 of three fission barriers Evacuate 2 Mile Radius I 5 Mile Downwind WSW I W I WNW -Incorrect due to this evacuation is based on loss 2 of three fission barriers and an incorrect assumption on

downwind sectors affected (Le. wrong direction) I EXAM BANK COMPUTER TEST Page: 66 of 12 October 2010 Question 1 Info i Multiple Choice Status: Active Always select on test? No Authorized for practice?

No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 8877 User-Defined ID: 8877 Cross Reference Number: LLOT0760.5B Topic: PAR requirement on a EP call Num Field 1: 4.2 Num Field 2: 4.4 Text Field: 2.4.44 Comments: General Data Technical Reference with EP-AA-1008 Rev 17 Revision Number: EP-AA-111-F-08, Rev D Cognitive Level H PRA: (I.e. Yes or No or #) NO . 10CFR 55.43 (N/A for RO) 55.43Jb) 5 Question History: (I.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (I.e. New, NEW r Bank, Modified) Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If EP-AA-111-F-08 appropriate): (I.e. ABN-##) Excluded

Reference:

(I.e. NONE .' Ensure ON-## not provided) r Low KA Justification (if N/A required):

I Associated objective(s): 2010 IL T QUESTION HOLDER EXAM BANK COMPUTER TEST Page: 2 of 2 13 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: 8879 Points: 1.00 Unit 1 Plant conditions are as follows: -Reactor power is -I & C determines that the following Transmitters are failed - - WHICH ONE of the following identifies the status of the Instrumentation LCOs listed below? TS LCO TS LCO 3.3.5 A. Satisfied B. Not Satisfied. C. Not Satisfied D. Not Not Satisfied Answer: D Answer Explanation: Not Satisfied; Not Satisfied -This answer is correct because from M-0042 Sheet 1, the affected instruments would be L T -1 N095A (ECCS -ADS Level 3 Permissive) L T -1 N097 A (RCIC level 2, 8). From M-0042 Sheet 2 table 1 "Water level Instrumentation Utilization", the function and level trip point for each level transmitter can be found in the last two columns of the table. Based on the information, LCO 3.3.3 is not met since the ADS Level 3 Permissive requires a minimum of 1 operable channel (1/trip system; two trip systems with 1 channel per trip system). LCO 3.3.5 is not met since RCIC Level 2 and Level 8 trips require a minimum of 4 operable channels (4 per trip function). Satisfied; Not Satisfied -This answer is incorrect but plausible if the applicant dosen't know how many level

channels are actually available for ADS actuation logic.

Not Satisfied; Satisfied -This answer is incorrect but plausible if the applicant dosen't know how many level channels are actually available for the RCIC initiation and trip logic circuits or believes that the High Level Trip function is met due to the transmitter being in a tripped condition. EXAM BANK COMPUTER TEST Page: 68 of 12 October 2010 i EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Satisfied; Satisfied This answer is incorrect but plausible since only two channels (1/subsystem) provide Signals for the ADS level 3 permissive. If the applicant dosen't notice the (***) note at the bottom of the page concerning the "Minimum Operable Channels per Trip function" is per subsystem then this choice appears to be the correct answer and the applicant dosen't know how many level channels are actually available for RCIC initiation and trip circuits or believes that the High Level Trip function is met due to the transmitter being in a tripped condition. EXAM BANK COMPUTER TEST Page: 69 of 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 23 Info i LQuestion Type: Multiple Choice I ! Status: Active i Always select on test? No I Authorized for practice? No i Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: 8879 User-Defined 10: 8879 Cross Reference Number: LLOT0760.5B I Topic: T.S & M-42 for Num Field 1: Num Field 2: Text Field: General Data I Technical Reference with TECH SPECS and P&ID I Revision Number: M-42 I Cognitive Level H PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.43 (b) 2 Question History: (Le. LGS Bank NRC-05, OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified) Revision History: Revision N/A History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If T.S. Sections 3.3.3 appropriate): (Le. ABN-##) (instrumentation), and 3.3.5 (RCIC) M-42-sheet 1 & 2 Excluded

Reference:

(Le. NONE Ensure ON-## nQ!j>rovided)

Low KA Justification (if N/A required):

I .Question 23 Table-Item Links NRC EXAM -10 CFR 55 Operators' Licenses 10 CFR 55.43 SRO WRITTEN EXAMINATION EXAM BANK COMPUTER TEST Page: 70 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 5401 Points: 1.00 Unit 2 plant conditions are as follows: -Drywell venting to REECE is in progress for containment pressure control per OT-101, HIGH DRYWELL PRESSURE During the venting operation, a steam leak in the drywell is indicated on the containment leak detectors and the SOUTH STACK HI HI RAD alarm is received WHICH ONE of the following describes the plant response and required actions, if any, based on the above conditions? Automatic Group 6B isolation will terminate the release. Ensure isolation of 2 inch vents and start of SGTS Automatic Group 6B isolation will terminate the release and SGTS will remain in standby. Ensure isolation of 2 inch vents. Alarm only. Manually isolate 2 inch vents and ensure at least one SGTS fan and filter is running in AUTO until normal release rates restored Alarm only. Manually isolate 2 inch vents and ensure drywell cooling is maximized Answer: D Answer Explanation: Alarm only. Manually isolate 2 inch vents and ensure drywell cooling is maximized-This answer is correct per OT-101 High Drywell Pressure, Step 3.16.1, "IF Primary Containment Steam Leak is detected or South Stack HI/HI radiation alarm (003-F-1) is received while venting Drywell then close the following valves: HV-57-211, INBD and 217 OUTBOARD.

An OT-101 immediate operator action is to Maximize Drywell cooling (Step 2.1). Per ARC-MCR-003 RAD F-1, this annunciator has no automatic actions that occur. Automatic Group 6B isolation will terminate the release. Ensure isolation of 2 inch vents and start of SGTS -This answer is incorrect because a South Stack Hi-Hi radiation signal will not initiate a 6B isolation (see GP-8, pg 6, 8-9). No isolations will automatically occur. Automatic Group 6B isolation will terminate the release and SGTS will remain in standby. Ensure isolation of 2 inch vents This answer is incorrect because a South Stack Hi-Hi radiation signal will not initiate a 68 isolation (see GP-8, pg 6, 8-9). No isolations will automatically occur. This response is partially correct because SGTS will remain in standby and isolations would be manually required. I EXAM BANK COMPUTER TEST Page: 71 of 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Alarm only_ Manually isolate 2 inch vents and ensure at least one SGTS fan and filter is running in AUTO until normal release rates restored -This answer is incorrect because there is no automatic start of SGTS although this response is partially correct due to Alarm Only and Manually isolate 2 inch vents. EXAM BANK COMPUTER TEST Page: 72 of 12 October 2010 --EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 24 Info Question Type: MI MinlA Status: /,-Iways select on test? No Authorized fO!2ractice? No Time to Complete: Difficulty: 1-=--. __5401 User-Defined 10: 5401 Cross Reference Number: LLOT1540.02 Corlldllllilent pressure \JVlIlIVI per OT-101, HIGH Topic: Num Field 1: Num Field 2: SRO 1-:=--:---. Text Field: Comments: General Data Technical Reference with OT-101, Drywell high Revision Number: pressure Cognitive Level H 10CFR55.43 .-.--. Question History: (Le. LGS 02NRC OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified) .. KA Justification (if Bank reguired}: Revision History: Revision Bank History: (Le. Modified distractor "b" to make plausible based on OTPS ILT Supplied Ref (If none {Le. ABN-##J Excluded

Reference:

(Le. OT-101 I Ensure ON-## not provided)

II LORT (Le. Yes or No or #) No LORT Question Section: A (Le, A-Systems or E!ocedures) I ===J Qyestion24 Table-Item Links Limerick RO EXAM BANK COMPUTER TEST Page: 73 of 77 12 October 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8874 Points: 1.00 Unit 1 plant conditions are as follows: -Plant cooldown in progress for forced outage -Shutdown Cooling was lost on 18 loop RHR due to pump trip while in OPCON 4 -Shutdown Cooling was restored 1 hour ago with 1A RHR Loop -RPV Water level is + 65 inches on Shutdown level indication -RPV Pressure is 6 psig and up slow -1 A RHR flow is 11,500 GPM -1 A RHR HX RHR inlet temperature is 150 deg F 1A RHR HX RHR outlet temperature is 120 deg F WHICH ONE of the following describes the heat removal from the core and the required actions? Heat removal is Reduce RHR flow to below 11, 000 Heat removal is Raise level to 80 inches on Shutdown Heat removal is INADEQUATE with indications of core bypass; Declare OPCON 3 and verify lineup Heat removal is INADEQUATE due to insufficient RPV water level; Declare OPCON 3 and raise RPV water level to 80 inches on Shutdown level Answer: C Answer Explanation: Heat removal is INADEQUATE with indications of core bypass; Declare OPCON 3 and verify lineup -This answer is correct because per S51.8.8 precaution 3.13, Operating RHR in Shutdown Cooling Mode and Recirc in that loop is out of service with both Recirculation Pump valve *F023A(8) SUCTION and HV-43-*F031A(8), discharge open will create a Shutdown Cooling 8ypass Leakage path and could result in an unexpected OPCON Mode change due to decreased Shutdown Cooling capability. The conditions shown with loop swap from 18 to 1 A and RPV pressure at 6 psig with RHR HX inlet and outlet temperatures indicating bypass flow all indicate this condition with inadvertent OPCON change. Heat removal is ADEQUATE; Reduce RHR flow to below 11, 000 gpm -This answer is incorrect because heat removal is not adequate even though the RHR flow rate through the Heat Exchanger is exceeding the limit of 11,000 gpm. '---_._____....L-..______*. ____.. EXAM BANK COMPUTER TEST Page: 75 of 77 12 October 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Heat removal is ADEQUATE; Raise level to 80 inches Shutdown level -This answer is incorrect because removal is not adequate. The condition stated for RPV 65 inches on Shutdown range meets the S51.8.B for> 60 inches on LI-42-*R601 on *OC602 in precaution Heat removal is INADEQUATE due to insufficient water level; Declare OPCON 3 and raise RPV water to 80 inches on Shutdown level-This answer is because RPV level in the condition is stated for RPV level inches on Shutdown range which meets the requirement for> 60 inches on LI-42-*R601 on *OC602 precaution 3.4. Heat removal is inadequate as evidenced RPV pressure 6 psig and abnormal RHR HX inlet and temperatures indicating no forward flow through the I Question 25 Info : Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Comtllete: 3 3.00 System ID: User-Defined ID: Cross Reference Number: Topic: Heat removal from the core with loss of shutdown Num Field 1: Num Field 2: Text Field: ! General Data Technical Reference with Trip Bases, Revision Number: T-101 Cognitive Level H PRA: (Le. Yes or No or #) YES 55.43 (N/A for RO) 55.43 (b) 5 Question History: (i.e. LGS NEW NRC-05. OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified) Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If I NONE appropriate): (Le. ABN-##) EXAM BANK COMPUTER TEST Page: 76 of 12 October 2010 I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Excluded

Reference:

(Le. Ensure ON-## not provided)

Low KA Justification (if i required): NONE N/A -EXAM BANK COMPUTER Page: 77 of 77 *--*--120ctober 2010}}

v t e Letter Sequence Acceptance Review
TAC:U01767, (Open)
Initiation Acceptance Administration Questions Answers Results Approval... Other: ML102920667, ML102920673, ML102920676, ML103080887
MONTHYEAR2010-08-20 [Table View]

ML102920669

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2.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br />

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