ML102920664

Limerick - Draft Written Exam (Folder 2)

ML102920664
Person / Time
Site:	Limerick
Issue date:	08/20/2010
From:	Caruso J G Operations Branch I
To:	Goff C B Exelon Generation Co, Exelon Nuclear
Hansell S
Shared Package
ML100560247	List: IR 05000352/2010302 ML101650598 ML102720677 ML102870021 ML102920654 ML102920658 ML102920661 ML102920664 ML102920667 ML102920669 ML102920673 ML102920676 ML103080887
References
TAC U01767
Download: ML102920664 (258)

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{{#Wiki_filter:Limerick License Exam RO 1 EXAMINATION ANSWER IL T09-1 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: 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 setpoint (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 ideal 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. EXAM BANK COMPUTER TEST Page: 1 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Stabilize RPV pressure with HPCI to minimize heat input into the Suppression Pool: See Explanation above -Above capacity of HPCl Reduce RPV pressure with HPCI to minimize operation of SRVs: See Explanation above -Above capacity of HPCI Reduce RPV pressure with turbine Bypass Valves to minimize heat input into the Suppression Pool: See Explanation above -Above capacity of BPVs EXAM BANK COMPUTER TEST Page: 2 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 1 Info Question Multiple Choice Status: Active Always select on test? No ! Authorized for practice? No Points: 1.00 Time to Complete: 3 ! 2.00 System ID: User-Defined ID: Cross Reference Number: OT-102, Reactor HI pressure trip with RPS lites not !Topic: extinguished per Num Field 1: Num Field 2: Text Field: 295037 EK1.Q1 11 LJ /J .... ':... ... r('._ lJe,.....JL {f w r-A /'.Vi/V" I'V -L1 J,A. v /2)c. f P1General Data Technical Reference with T-101 Revision Number: Level H i PRA: (Le. Yes or No or #) Y

• 10CFR 55.43 (N/A for 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) Supplied Ref (If appropriate) none I i EXAM BANK COMPUTER TEST Page: 3 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8773 Points: 1.00 2 Unit 1 plant conditions are as follows: -Reactor startup is in progress when the "1 B" Recirc pump Field Breaker trips -Reactor power is 50% r _ "iAn Recirc pump speed is J t -PMS computer is II 0 -Core plate DP indication XR-042-1 R613 indication is 1.2 psid LGS Power Flow Operation Map-1. I: __ 0".0,."""" ..""...'" 'mOo. 00 ! 80 /l '0 70! .0 I J 50 40 30 10 20 30 50 &i 70 80 00 1W 110 1:;;0 dP Core Flow (% of Ratea) 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 "1B" Recirc pump and Raise Core Flow Answer: C Answer Explanation: ANSWER 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 Page: 4 of 195 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order r-DiSTRACTOR-- Manually scram the reactor:Thlsisjncorrect as conditions do not require a Reactor Scram. IF a second recirc pump tripped, OR if Core Plate dP indication on was not available Stabilize Power at current value: This is incorrect 50% power and Core plate dP of 1.2, places plant in restricted region Per T-112 requiring 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 f1ow-112 Question 2 Info General Data Technical Reference with OT-112, Recirc Pump trip Revision Number: LOT-1540.05 __ ____ _______---l H PRA: (i.e. Yes or No or #) N 10CFR 55.43 (N/A for -t-cN:-:/_A ________ Question History: (I.e. LGS New

---

1 Question Source: (i.e. New, New

__________ --j Revision History: Revision N/A History: (I.e. Modified distracter "b" to make plausible based on OTPS revieI/VL__________

-:-::::--

________ ILT EXAM BANK COMPUTER TEST Page: 5 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order CFR: 41.2 General design features of the core, including core structure, elements, control rods, core instrumentation, and coolant 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 3 EXAMINATION ANSWER IL T09-1 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 is at position Rod 50-31 is at position -Rod 22-51 is at position "48" -All other control rods are at "00" -No Boron has been injected WHICH ONE of the following describes a new set of control rod positions at which an "ATWS" is no longer in progress? BOD 26-11 ROD 50-31 ROD 22-51 A. "02" "48" "48" B. "00" "48" "48" C. "02" "04" D. "00" "00" "48" Answer: 0 Answer Explanation: EXAM BANK COMPUTER TEST Page: 7 of 195 20 August 2010 EXAMINATION ANSWER RO questions in sample plan order ROD 26-11 at "00" ROD 50-31 at "00" ROD 22-51 at "48": 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 the boron. ROD 26-11 at "02" ROD 50-31 at "48" ROD 22-51 at "48": Incorrect due to two additional rods beyond position "02" ROD 26-11 at "00" ROD 50-31 at "48" ROD 22-51 at "48": Incorrect due to more than one rod beyond position "02" ROD 26-11 at "02" ROD 50-31 at "04" ROD 22-51 at "04": Incorrect due to two additional rods beyond position "02" I EXAM BANK COMPUTER TEST Page: 8 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order I Question 3 Info , Question Type: Choice Status: Active Always select on test? No Authorized for.practice? No Points: 1.00 Time to Complete: 0 : SY':>LI:":I 8780 User-Definea ID: Cross Reference Number: LIMERICK LOT 6740 - is 6% -Suppression Topic: Pool t lperat 1090 he Operator has Num Field 1: 3.7 ! !1 tlI.l. Num Field 2: 4.1 ,/ \T'< '. vv'iJ Text Field: 295046 EKf.04 \ , I I J Vi Comments: <:::""'IJ J...J..If. '/4.-...P K J I C/' General Data' I' F..,;ftt(;LI(,r sr I Technical Reference with T-101 [ Revisio 11_ Revisic)1l Number: n #: 510 Cognitive Level L II Justification for Non SRO 10CFR41b.8 CFR Link: Question History: (I.e. LGS 02 NRC-05, OYS CERT-04) r--Question Source: (I.e. New, Bank i 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 Lreview) II ILT II Supplied Ref (If NONE {i.e. ABN-##l __ Excluded

Reference:

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

LORT 1--=PRA: (I.e. Yes or No or #) Y LORT Question Section: A (I.e, A-Systems or B-Procedures) EXAM BANK COMPUTER TEST Page: 9 of 20 August 2010 i 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 The reactor was manually Scrammed! Rx Mode switch is in Shutdown Main Turbine is tripped MSIV's are closed RCIC was manually initiated SE-1, Remote Shutdown, was entered and all remote shutdown transfer switches are in "Emergency" No other actions were t9.ten at the WHICH ONE of the following describes how HPCI and RCIC will function at the Remote Shutdown Panel? A. Manually controlled to maintain level Manually controlled to maintain level B. Automatically cycles to maintain level Manually controlled to maintain level C. Automatically cycles to maintain level Automatically cycles to maintain level D. Manually controlled to maintain level Automatically cycles to maintain level Answer: B Answer Explanation: Automatically cycles to maintain level; Manually controlled to maintain level: Correct because SE-1 NOTE for section 4.3.1 describes HPCI spurious operation that may require Emergency Shutdown and for section 4.3.3 describes placing RCIC in service for manual control of level. Manually controlled to maintain level; Manually controlled to maintain level: Incorrect due to no manual control capability for HPCI at the RSP except for the HPCI Emergency Shutdown using HS-56-*62 at the RSP. G OISTRACTOR Automatically cycles to maintain level; Automatically cycles to maintain level: Incorrect due to information above. EXAM BANK COMPUTER TEST Page: 20 August 2010 EXAMINATION ANSWER I L T09-1 RO questions in sample plan order Manually controlled to maintain level; Automatically cycles to maintain level: Incorrect due to information above. Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? Yes Authorized for practice? No Points: 1.00 Time to ComQlete: 2 Difficulty: 3.00 System 10: 8794 User-Defined 10: 8794 i 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 ('.AL 1W'l...tn.J hfl y -(J, f -I<Y -'1A.Jl. Comments: General Data I Technical Reference with Revision Number: SE-1 Remote Shutdown i Cognitive Level L Justification for Non SRO 55.41 (b)7 CFR Link: i Question History: (i.e. LGS Bank

• NRC-05, OYS CERT-04) Question Source: (I.e. l\lew, Bank i Bank, Modified) i Low KA Justification (if N/A
• required}:

Revision History: Revision N/A History: (Le. Modified distractor "b" to make plausible based on OTPS review) II ILT Supplied Ref (If none

• appropriate): (Le. ABN-##) Excluded

Reference:

(i.e. SE-1 Ensure ON-## not provided)

LORT

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

J I EXAM BANK COMPUTER TEST Page: 11 of 20 August 2010 5 EXAMINATION ANSWER ILT09-1 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 (47-1N652 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 drift close. B. Outboard MSIVs will drift close. C. Inboard MSIVs will immediately close. D. Outboard MSIVs will immediately close. Answer: B Answer Explanation: Outboard MSIVs will drift 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 i pressure I I DISTRACTOR 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 MSIVs will immediately close: Incorrect due to pneumatic supply normally from Instrument Gas (Nitrogen) that is not affected by the loss of fA pressure. Additionally, the Inboard MSIVs are maintained open by an accumulator supply to the operating piston that is protected by a check valve EXAM BANK COMPUTER TEST Page: 13 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Outboard MSIVs will immediately close: Incorrect due to the plant conditions stated with depressurization in Instrument Air Headers allowing plant control per ON-119 Inboard MSIVs pneumatics are suppled by instrument gas leaving then unaffected by a loss of instrument air. AL \:) "7 b \..,t-\1J7 \ Due to check valve arrangement on the MSIVs air supply lines, the Ir.+board MSIVs will close slowly as accumulator pressure leaks past check valve; the outboard MSIVs w"m -,Iiupon loss of afI; Question 5 Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text ,'\:.. 1 ,j wW <<Multiple (Active No No 3.00 8774 11 LLOT1550.02 I 1'1( l & 'q ON-119, Loss or partial loss of Instrument Air 3.4 l\ -r' 1\ () 295019 .u w J;,taJ5 ali\) tc111V't-oy\ PJ General Data Technical Refe. "'live; Revision Cognitive PRA: (i.e. Yes or No or 10CFR 55.43 (N/A for Question History: (i.e. i NRC-05, OYS CERT-04) Question Source: (I.e. New, Bank, Modified) Revision History: Revision History: (I.e. Modified distracter "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): ON-119, Loss of Instrument air L Y N/A New New N/A NONE ON-119 N/A EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 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 ILT EXAM BANK COMPUTER TEST Page: 15 of 195 20 August 2010 6 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: Points: 1.00 Unit 2 plant conditions are as follows: -GP-3 SHUTDOWN is in progress due to a steam leak in the Drywell -Unit 2 is in a normal HVAC alignment -Drywell pressure rises to 2.1 psig WHICH ONE of the following describes the impact on the Reactor Enclosure Ventilation and Drywell Chilled Water systems? RE DW Chilled Water A. RE HVAC DW Chilled Water isolates B. RE HVAC does NOT isolate DW Chilled Water isolates C. RE HVAC DW Chilled Water does NOT isolate D. RE HVAC does NOT isolate DW Chilled Water does NOT isolate Answer: A Answer Explanation: RE HVAC isolates; OW Chilled Water isolates: Correct answer with reference to ARC-MCR-113 H-4 (Div 1) and GP-8.1 U/2 for signal "HI! High Drywell Pressure. The condition pressure of 2.1 psig is above the isolation setpoint of 1.68 psig stated in the ARC. RE HVAC does NOT isolate; OW Chilled Water isolates: Incorrect, see Justification above RE HVAC isolates; OW Chilled Water does NOT isolate: Incorrect, see Justification above RE HVAC does NOT isolate; OW Chilled Water does NOT isolate: Incorrect, see Justification above EXAM BANK COMPUTER TEST Page: 16 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 6 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: 8789 User-Defined ID: 8789 Cross Reference Number: LLOT022.03 Secondary Containment and DWCW response to a high Topic: drywell signal Num Field 1: 3.3 Num Field 2: Text Field: 3.4 .'-Ii. ,/'0 295024 EK2.18 1J-<.J/..1) tJ 01-"\ Comments: V' I /' General Data Technical Reference with GP-8 I Revisio Revision Number: GP-8.1 n #: Cognitive level L Justification for Non SRO 55.41 (b) 7 CFR Link: 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. 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)

LORT PRA: (i.e. Yes or No or #) N LORT Question Section: N/A (i.e, A-Systems or B-Procedures) EXAM BANK COMPUTER TEST Page: 17 of 195 20 August 2010 7 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 -Reactor water level is Reactor Pressure is being maintained between 990 and 1096 psig with SRVs -Suppression Pool Level is 22' 6" -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 800 psig WHICH ONE of the following describes why Reactor pressure is lowered to remain on the safe side of the curve? A Minimize SRV cycling to prolong SRV availibility .(B) Maintain Suppression Pool Temperature to support Boron Injection Initiation Temperature (BIIT). Restore Suppression Pool Temperature below maximum suction temperature for HPCI and RCIC operation. 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 SP/T-8 which states LGS TRIP step directs actions to control RPV pressure below the Heat Capacity Temperature Limit (HCTL, CURVE SP/T-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." EXAMINATION ANSWER Il T09-1 RO questions in sample plan order Minimize SRV cycling to prolong SRV Incorrect due to SRV cycling in progress for control adding reactor heat to the Suppression Maintain Suppression Pool Temperature to support Boron Injection Initiation Temperature (BIIT): Incorrect due to BIIT defined as 110 degrees. The HCTl curve is well above this. Restore Suppression Pool Temperature maximum suction temperature for HPCI and operation: Incorrect due to action taken actually the Suppression Pool Temperature instead of Question 7 Info ! Question Type: Multiple Status: Always select on test? . Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 ID: 8795 User-Defined ID: 8795 i Cross Reference Number: LLOT1560.05 Suppression Pool high temperature requiring lowering Topic: Reactor Num Field 1: Num Field 2: 4.1 L'\ J Text Field: 295026 EK3.01 r t-tt.;"T""' P J 1/l11A n .n "I Comments: GENERAL DATA U Uf Technical Reference with T-102, Primary Revision Number:

• Cognitive level L ! I PRA: (Le. Yes or No or #) Y
• 1 OCFR 55.43 (N/A for RO 55.41 (b) 5 RO) Question History: (Le. NEW LGS NRC-05, OYS i CERT-04) Question Source: (Le. New New, Bank, Modified)

Revision History: Revision N/A History: (Le. Modified distractor "b n to make plausible based on OTPS I II EXAM BANK COMPUTER TEST Page: 20 August 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Supplied Ref (If NONE appropriate): (Le. ##) Excluded

Reference:

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

i Low KA Justification (if i EXAM BANK COMPUTER TEST Page: 20 of 195 20 August 2010 8 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Plant conditions are as follows: Reactor power is 95% The following annunciator windows have alarmed in the MCR. MAIN STEAM F-2 (B1 MOISTURE SEPARATOR DRAIN TANK HI LEVEL) MAIN STEAM E-1 (MOISTURE SEPARATOR HI LEVEL TRIP) WHICH ONE of the following is the expected response and the reason for that response? Expected response Reason for response Main Turbine trip, ONLY Prevent water intrusion into the Main Turbine Main Turbine trip Prevent water intrusion into the Main Turbine AND Reactor scram 'B l' Moisture Separator Prevents erosion of the 4th Feedwater dump vlv. ONLY opens Heater tubes and baffles 'B1' Moisture Separator Prevents erosion of the 4th Feedwater drain vlv. AND dump vlv. open Heater tubes and baffles Answer: B Answer Explanation: EXAM BANK COMPUTER TEST Page: 21 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order -ANSWER Main Turbine trip and Reactor scram; Prevent water intrusion into the Main Turbine: 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. Once 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 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 i '\ 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 La level setpoint (15.5 inches above the bottom of the drain tank), then the A1 (B1, C1, A2, 82, C2) MOISTURE SEPARATOR DRAIN TANK LO LEVEL alarm will annunciate in the MCR. EXAM BANK COMPUTER TEST Page: 22 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order I Main Turbine trip, ONLY; Prevent water intrusion into the Main Turbine: Incorrect, See discussion above 'B1' Moisture Separator dump vlv. ONLY Prevents erosion of the 4th Feedwater Heater and baffles: Incorrect, See discussion I 'B1' Moisture Separator drain vlv. and dump open; Prevents erosion of the 4th Feedwater I tubes and baffles: Incorrect, See discussion above I I Question 8 Question Type: Multiple Status: Always select on test? Authorized for practice? Points: Jime to ComQlete: 3 Difficulty: 3.00 System ID: User-Defined ID: Cross Reference Number: LGSOPS0001 With main generator is loaded on the grid the moisture Topic: drain valve Num Field 1: . . Num Field 2: /I' " A A k. I n I tZiXJ !II F' ! Text Field: 295005 AK3.05 I v V d-ur1.tYf..,*( Comments: General Data I Technical Reference with I Revision Number: LGSOPSOO01 n#. i 8 I Justification for Non SRO 55.41 (b) 5 CFR Link: i Cognitive Level L I Question History: (Le. LGS New NRC-05, OYS CERT-04) I Question Source: (Le. New, New Bank, Modified) Low KA Justification (if N/A required): Revision History: Revision N/A History: (Le. Modified distractor "b" to make plausible based on OTPS review)I ILT Supplied Ref (If None appropriate): (Le. ABN-##) I EXAM BANK COMPUTER TEST Page: 23 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order I' Excluded

Reference:

(Le. LGSOPS0001 B . Ensure ON-## not provided)

LORT PRA: (Le. Yes or No or #) Y LORT Question Section: A (Le, 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: 24 of 195 20 August 2010 i 9 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Unit 2 is operating at 100% power when a fault on 0134 Load Center causes the following: -"2A" RECW Pump trips -"2B" RECW Pump starts automatically, but cannot maintain system flow -RECW system temperatures are steadily rising ON-113, LOSS OF RECW, is being performed and directs the Reactor Water Cleanup (RWCU) Pumps be isolated if they trip from a loss of RECW. WHICH ONE of the following identifies the reason for isolating a tripped RWCU Pump? A. Prevent RWCU Filter-Oemineralizer resin damage B. Minimize erosion across RWCU Pump seals due to system pressure C. Prevent RWCU non-regen heat exchanger isolation on high temperature O. Minimize RWCU pump pedestal heating, to maintain pump-motor alignment Answer: B Answer Explanation: Minimize erosion across RWCU Pump seals due to I system pressure: 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 erosion/leakage across seals due to system pressure. Prevent RWCU Filter-Demineralizer resin damage: Incorrect due to system response with pump tripped is to place the filter on the hold pump automatically with no further system flow to cause resin damage from heat Prevent RWCU non-regen heat exchanger isolation on high temperature: Incorrect due to system temperature not expected to continue to rise with no pump flow to transfer heat from reactor to RWCU heat exchangers Minimize RWCU pump pedestal heating, to maintain pump-motor alignment: Incorrect due to no system flow to cause a temperature gradient accross pump pedestal EXAM BANK COMPUTER TEST Page: 25 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 9 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 8778 8778 LLOT1550.02 Unit 2 is operating at 100% power when the following transient occurs: -"2A" RECW Pump trips on 0 3.1 3.3 11 I 1 r 1.vJ 295018 AK3.03 '1I"LlJ / 1(', General Data ./ .... f)'\..0' ".Q Technical Reference with On-113, Loss of RECW ,4 Revision Cognitive Level L WVf'PRA: (i.e. Yes or No or #) 1 OCFR 55.43 (N/A for RO) 55.41 Question History: (i.e. LGS NRC-05, OYS Question Source: (i.e. New, Bank, Revision History: Revision History: (i.e. distracter "b" to plausible based on Supplied Ref (If appropriate): (i.e. Excluded

Reference:

(i.e. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 26 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 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 EXAM BANK COMPUTER TEST Page: 27 of 195 20 August 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 "1A" ADHR is in service ANN Panel 20C222 "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 Top of Fuel Storage Racks C. Vessel Bottom of the Transfer Canal D. Vessel Top of Fuel Storage Racks 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. AHDR 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 causing 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 EXAM BANK COMPUTER TEST Page: 28 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order DISTRACTOR Cavity Weir Plates; Top of Fuel Storage Racks: 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 Vessel Flange; Top of Fuel Storage Racks: Incorrect due to Same as above I Question 10 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: Refuel bellow leak impact on cavity and fuel pool level Num Field 1: 2.9 Num Field 2: 3.2 *11 n A D J /I ... Text Field: 295023 AA2.02 JlJ..f.....tk' - AliI. ""\.. """I Comments: o I General Data I Technical Reference with ON-120 I Revisio Revision Number: S53.0.A

• n#: I 2GP6.1 ! Justification for Non SRO 55.41 (b) 7 CFR Link: I Cognitive Level H ! Question History: (I.e. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, NEW Bank, Modified) i i Low KA Justification (if N/A required):

Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (if N/A appropriate): (i.e. ABN-##) EXAM BANK COMPUTER TEST Page: 29 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8790 Points: 1.00 Unit 2 plant conditions are as follows: Fuel Pool clean out is in progress using a portable vacuum Refuel Floor Containment integrity is established Unit 1 Refuel Floor HVAC is in service The vacuum cleaner filter breaks open during movement, resulting in a Refuel Floor high airborne contamination condition and 3.0 mRlhr on all Unit 1 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 2 Refuel Floor Exhaust rad monitors B. Unit 1 Refuel Floor Exhaust rad monitors C. North Stack Wide Range Accident monitor D. Unit 2 South Stack monitor Answer: C Answer Explanation: ANSWER -N-o-rt-h-S-t-ac-k-W-id-e"-R-a-ng-e-A-c-c-id-e-n-t-m-o--n-j-to-r-:-C-o-r-re-c-t---' 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 will measure the offsite release Unit 2 Refuel Floor Exhaust rad monitors: Incorrect due to Refuel Floor isolation logic isolation of both Unit 1 and Unit 2 Ventilation flowpaths on a valid isolation Signal from either unit exhaust radiation monitors Unit 1 Refuel Floor Exhaust rad monitors: Incorrect due to Refuel Floor isolation logic isolation of both Unit 1 and Unit 2 Ventilation flowpaths on a valid isolation signal from either unit exhaust radiation monitors Unit 2 South Stack monitor: Incorrect due to Refuel Floor isolation logic isolation of both Unit 1 and Unit 2 Ventilation flowpaths on a valid isolation signal from either unit exhaust radiation monitors. Flow to the South Stack is isolated EXAM BANK COMPUTER TEST Page: 31 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 11 Info Question Always select on Authorized for

• Points: Time to System User-Defined Cross Reference *Num Field 1: ! Num Field 2: Text Field: Comments:

Multiple Choice Active No No 1.00 3 3.00 8790 8790 LGSOPS0026.04 Identify the location of measured offsite release point following 3.0 mr/hr on Refuel Floor 2.8 3.9 295038 EA1.04 I I General Data Technical Reference Revision Cognitive Justification for Non

• CFR Link: 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)

P&ID M-76 Revisio ARC 003 RAD n#: E-1, C-5 ARC 004 VENT E-3 H 55.41 (b) 7 Bank N/A N/A none PRA: (Le. Yes or No or #) LORT Question Section: * (i.e, A-Systems or B--X;.. /Qw r I Procedures) 1\ A I I 1 )ilJ)P'It*; \(,\ KJA 295038 EA1.04 RO 2.8 SRO 3.2 c.. \r' EXAM BANK COMPUTER TEST Page: 32 of 195 010 I EXAMINATION ANSWER ILT09-1 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: 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 safet 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 I primary containment vacuum relief system. Unrestricted operation of drywell sprays could thus result in a negative drywell-to-suppression pool differential pressure large Ienough 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 Suppression Pool for adequate Incorrect due to opposite of actual concern for evaporative cooling Ensure temperature is low enough to Suppression Chamber "chugging" when sprays initiated: Incorrect due to expected equilization of Pressure with Suppression Pool as Vacuum actuate on Drywell Spray 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 equilization on Evaporative cooling I EXAM BANK COMPUTER TEST Page: 35 of 20 August 2010 EXAMINATION ANSWER ILT09--1 RO questions in sample plan order Question 12 Info Question *Always select on test? Authorized for practice? Points: Time to Complete: Difficulty: System User-Defined r-::--'Cross Reference Number: Topic: Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8796 8796 LIMERICK LOT 3696 identifies the purpose of ensuring parameters are on the SAFE side of the DRYWELL SPRAY INITIATION R03.8 /J .l,,," 1 r SRO 3.9 -.. \ J IlA'vi 295028 EA1.01 ,yl.V r I rQ/" V V f"'lVV"" J.--;-"\ f I\. r ")\ General Data I Technical Reference with T-102 Bases Revisio Revision Number: n #: I Cognitive Level L Justification for Non SRO 55.41 (b) 7 CFR Link: Question History: (i.e. LGS Bank NRC-05, OYS CERT-04) I Question Source: (I.e. New, Bank I Bank, Modified) i Low KA Justification (if N/A i required): Revision History: Revision Bank History: (i.e. Modified distractor "b" to make plausible based on OTPS review) i ILT Supplied Ref (If none appropriate): (i.e. ABN-##) Excluded

Reference:

(I.e. none ! . Ensure ON-## not provided) 

! LORT PRA: (I.e. Yes or No or #) LORT Question Section: (I.e, A-Systems or B-Procedures)

Reference:

T-102 EXAM BANK COMPUTER TEST Page: 36 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8776 Points: 1.00 Unit 2 plant conditions are as follows: -OPCON -Reactor water temperature is 275 deg.F and "2A" RHR loop is in Shutdown Cooling -HIC-51-203A ("A" RHR HX Outlet Bypass) is 30% open -Drywell temperature is 126 deg.F HIC-51-203A fails closed. WHICH ONE of the following describes the effect on actual reactor water temperature and temperature indicated at TE-51-2N004A ("An RHR HX Inlet Temp) ten (10) minutes later? Actual Reactor Water Temperature TE-51-2N004A Indication A. rises B. lowers C. rises D. lowers Answer: B Answer Explanation: rises; lowers: Correct because Actual reactor water temperature will rise due to 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 piping will tend to decrease. rises; rises: Incorrect due to actual reactor water temperature will rise due to loss of cooHng. 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 EXAM BANK COMPUTER TEST Page: 37 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order lowers; lowers: 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 Question 13 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: 8776 User-Defined 10: 8776 Cross Reference Number: LLOT2006.1 Topic: ON-121, Loss of Shutdown temperature indication Num Field 1: 3.6 Num Field 2: 3.6 () J f/ Text Field: 295021 AA2.04 )1.1> cvCJt., fy-Comments: V t '/.1 J /)'1'\ J;,;)(f\J,:/Iv'" '1'-...General Data Technical Reference with ON-121, ST-6-107-640-2 Revision Number: I Cognitive Level H PRA: (i.e. Yes or No or #) Y 10CFR 55.43 (N/A for RO) N/A Question History: (i.e. LGS ILT Cert Exam 2005 NRC-05, OYS CERT-04) Question Source: (I.e. New, Bank Bank, Modified) 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. ON-121, Loss of Ensure ON-## not provided)

Shutdown cooling Low KA Justification (if N/A) required): EXAM BANK COMPUTER TEST Page: 38 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 13 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 EXAM BANK COMPUTER TEST Page: 39 of 195 20 August 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 -"J,A:.Ell::IR in Suppression Pool Cooling with "OA n RHRSW pump -Pump is in DIV 3 DC bus is de-energized due to ground fault 5 minutes later a LOCA occurs results in reactor level n\A/.e>r.r.rl 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 S. "OAn RHRSW and "iC" RHR C. "iA" RHR" and "iA" CRD and is RHR D. "iA" RHR and "OA" RHRSW and "1 S" RHR Answer: C Answer Explanation: "1A" RHR" and "1A" CRD and "1B" RHR: Correct because: "1 A" 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) "1 S" 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 iA 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 EXAM BANK COMPUTER TEST Page: 40 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order "1A" RHR and "OA" RHRSW and "18" RHR: Incorrect due to: Partially Correct:"1A" 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. I DISTRACTOR

• OA" RHRSW and "1 C" RHR: Incorrect due to: Incorrect: "OA" RHRSW will trip on the LOCA signal, and will not start without operator action Incorrect:

"1 C RHR" will not start on the LOCa due L_..__to_I_O_S_S_O_f _D_IV_3_D_C __________ Question 14 Info Question ___-+-:-M_ultiple Choice Status: Active Alw9YS select on test? No %thorized for practice?:........._+.N'-'-'-o ___________________ --1 Points: 1.00 Time to Complete: __-+-"-6_______.___________ .__--1 . 4.00 I System ID: 8792 . User-Defined ID: ___t-=8=-::7-=9:=:2=-::-=-=-:-::---:o_:__- ...--------------l Cross Reference Number: LLOT0690.03 , 04 -. Division 3 DC bus de-energized due "1 A" CRD Pump is in __----t-=s::..:e::-rvice; No ECCS

• Num Field 1: 3.2 Num Field 2: 3.3 n j 11 /\ 111 () J r Field: 295004 AA2.04 V'1.4. \ r-;( O\.f .... Comments:

. ,;;};,: I General Data CIf Technical Reference with I E-1 FC n! Revision Number: . S92.1.A S92.1.o Cognitive Level H JUstification for Non SRO i 55.41 (b) 10 CFR Link: Question History: (Le. LGS NEW OYS CERT-O:..:.4.L.)

--4-----------1 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 L' !

---

ILT

---

;1 EXAM BANK COMPUTER TEST Page: 41 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

Reference:

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

S92.1.A S92.1.D LORT PRA:JLe. Yes or No or #) Y LORT Question Section: (Le, A-Systems or B-Procedures) i EXAM BANK COMPUTER TEST Page: 42 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 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 +50" / / -Reactor level continues to rise to Reactor pressure is 1070 psig and rising -The Main Steam Isolation Valves (MSIV's) are manually closed / The CRS directs RPV pressure control using SRV's per OT-110, REACTOR HIGH LEVEL WHICH ONE of how reactor pressure will be controlled? A. f'1. peration rotating among ALL SRV's ...... B. Allow SRV's to cycle automatically on pressure C. of a single SRV repeatedly D. rotating among the ADS SRV's Answer: '1 , EXAM BANK COMPUTER TEST Page: 43 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Prolonged 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 J 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. f-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 lim SRV discharge in the shaded region of ATTACHMENT 11 "{ 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 psig and the Operator is able to lower RPV level to below the Main Steam lines prior to reaching 1096 psig. DISTRACTOR I Allow operation rotating among ALL SRV's: Incorrect i

• due to contradiction with above statement Allow SRV's to cycle automatically on Incorrect due to contradiction with above Prolonged operation rotating among the ADS Incorrect due to contradiction with above I EXAM BANK COMPUTER TEST Page: 44 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 15 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: 8783 User-Defined ID: 8783 Cross Reference Number: LLOT1540.04 Unit 1 is operating at 85% power when a Digital Feedwater Topic: Control System malfunction causes a rise Num Field 1: 3.7 Num Field 2: 3.8 "'I n I) fJ s.-r L-k" Text 295025 EA2.06 \JAt\1\" V 11lA'l../ . CU" Comments: I J General D9(y .-.iI./ f AA4f'V (\ Technical Reference with OT-110 Y Revisic{ Revision Number: n #: 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. 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:

OT-110 Ensure ON-## not provided) LORT PRA: (i.e. Yes or No or #) Y LORT Question Sedion: B (i.e, A-Systems or B-Procedures) EXAM BANK COMPUTER TEST Page: 45 of 20 August 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 / -80th "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. S51.8.A. Suppression Pool Cooling operation and level control D. S51.8.K. RHR Full flow test and Suppression Pool level control .,..:;:> ./' Answer: 8 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 f1. 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 coo r Ing concerns. i 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 i 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 EXAM BANK COMPUTER TEST Page: 46 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order S51.8.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 Status: Always select on test? __+-N_o______________________________________Points: Time to Complete: Difficulty: 'System 10: User-Defined 10: Cross Reference Number: f-:'T.,.=0..L.:..:PiiC-:::: __________ +=Ex,-::e::....:c=:-=u:,-,te'--.Lplant procedures with Suppression Pool low Field 1: RO 4.3 Field 2: SRO 4.4 ,-... () n I J I Text Field: 295030 B2.1.23 I. .,rk'lr "::> t" X' O/f<Z: (;/. 1, Comments: 1&,...,1/. 71-..r. /) I General Data I v -) 'V ..... r "{ Technical Reference with T-102, Primary \ Revision Number: Containment Control' A :<-1 -f '-., u 14-j/Vh . Cognitive J PRA: (I.e. Yes or No or #) Y {TC1n:tG.fLj>L4 10CFR 55.43 (N/A for RO) 55.41 (b)14rr n V Question History: (I.e. LGS New NRC-05, OYS CERT-04) Question Source: (I.e. New, New . Bank, Modified) ________-+__________________-l Revision History: Revision N/A History: (i.e. Modified distracter "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): (I.e. Excluded

Reference:

(I.e. T-102 Ensure ON-## not Low KA Justification (if KIA 295030 B2.1.23 RO 4.3 SRO 4.4 EXAM BANK COMPUTER TEST Page: 47 of 20 August 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 tL-0234.16 KV safeguard feeder breakers are open "1 _"tC 023 Emergency Diesel Generator (EDG) is 023 safeguard bus -Differential pressure across the 023 EDG heat exchanger indicates NO ESW flow WHICH ONE of the following describes controls available to initiate ESW flow to the 023 EDG? A. OA ESW pump can be started from the Unit 2 Remote Shutdown Panel ONLY. B. DC 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: 0 Answer Explanation:

EXAM BANK COMPUTER TEST Page: 48 of 195 20 August 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 ONL V. There are no ESW pump controls located on the Unit 2 Remote Shutdown panel. The OA ESW pump is also the only ESW pump controllable 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: -0*1 Safeguard Bus -0*2 Safeguard Bus -D*3 Safeguard Bus PERFORM the following for any running diesel generator: VERIFY ESW is available by observing dP across OG heat exchangers (ESW supply PI-11-*07 A(B,C,D) indicates higher pressure than ESW return PI-11-*OBA(B,C,0).

2. 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:

1. START OAP54B, "A ESW Pump" (PUMP A). 2. VERIFY OAP54B, PUMP A, running.

OA ESW pump can be started from the Unit 2 Remote Shutdown Panel ONLY: Incorrect due to contradiction with above information OC ESW pump can be started from the Unit 1 Remote Shutdown Panel ONLY: Incorrect due to contradiction with above information OC ESW pump can be started from the Unit 2 Remote Shutdown Panel ONLY: Incorrect due to contradiction with above information EXAM BANK COMPUTER TEST Page: 49 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 17 Info I Question Type: Militinip. Status: IAlways select on test? Authorized for practice? Points: Time to Complete: Difficulti': System 10: 8787 User-Defined 10: Cross Reference Number: Topic: Control board actions with a partial loss of AC power Num Field 1: 3.6 . Num Field 2: 3.6 r. 1\ (f) ,I I I-A Text Field: 295003 B2.2.4 \Y..c Ino t .. Comments: 1 I Luf7AJ General Data-' v '/ r ...r/ -cJlX?--C 'i AI IJ f-.l.1. Reference with SE-1 ReVIsion Number: , ,.J-", <' Cognitive Level L y for Non SRO 55.41 (b) 6 ttCFR Question History: (Le. LGS New NRC-05. OYS Question Source: (Le. New, I 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. SE-1 Ensure ON-## not provided)

LORT r-PRA:Ji.e. Yes or No or #J Y LORT Question Section: N/A (Le, A-Systems or B-Procedures) I EXAM BANK COMPUTER TEST Page: so of 19S 20 August 2010 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 RCIC 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 RCIC 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 RCIC, 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. Turbine bypass valves in automatic; RCIC due to manual initiation: Incorrect due to Turbine Bypass valves not available with MSIVs closed and RCIC not available due to not starting as an Immediate Operator Action. 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) EXAM BANK COMPUTER TEST Page: 51 of 20 August 2010 EXAMINATION ANSWER KEY ILT09-1 RO questions in sample plan order [ SRVs only; RCIC due to manual initiation: due to RCIC not manually started as an Operator Action. (Partially Correct for Question 18 Question Type: Multiple Status: Always select on test? No Authorized for practice? . 1.00 !Time to Complete: Difficulty: 3.00 System 10: User-Defined 10: Cross Reference Number: LLOT1563.01 , Topic: FSSG provided; Determine actions for fire on 254 Num Field 1: i Num Field 2: SRO JnL l\n Text Field: 600000 B2.4.8 Ie f"(.! Comments: rI <<:'j'uA-t U¥'" General Data Technical Reference with LLOT-i Revisio!.1 Revision Number: 1565.04 n r;r, v Cognitive Level H Justification for Non SRO N/A CFR Question History: (Le. LGS Bank NRC-05, OYS CERT-04) (.. J )J fJ f¥,PJ Question Source: (i.e. 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) ! . IL T ..,-' .... ! Supplied Ref (If ( FSSG-3020 Fire Area) , appropriate): (i.e. ABN-##) 020 guide * ..A Excluded

Reference:

(Le. -..-/ Ensure ON-## notprovided) LORT PRA: (i.e. Yes or No or #) Y LORT Question Section: B (Le, A-Systems or B-i Procedures)

I I EXAM BANK COMPUTER TEST Page: 52 of 20 August 2010

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EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8798 Points: 1.00 -Reactor power is -Generator output is 1150 -450 MVARs -Voltage regulator in -Terminal voltage is 21.5 Whitpain 5030 line has tripped

• The Nuclear Duty Officer (NDO) has issued a "Max Emergency Generation Action" and requests LGS take action to ensure grid reliability per E-5, GRID EMERGENCY.

WHICH ONE of the following actions is required? A. Reduce generator reactive load. B. Verify Load Tap Changers are in "AUTO". C. Verify Stator Water Cooling temp. <82 deg C. D. Reduce generator field current to raise terminal voltage. Answer: B Answer Explanation: VERIFY load tap changers are in "AUTO": Correct because per 32.3.A , VERIFY load tap changers for the offsite source transformers are in service in "AUTO" as verified by counter movement within the last 7 days per equipment operator rounds in Auto Tour the computer rounds program. 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, Alterrex 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 points. EXAM BANK COMPUTER TEST Page: 54 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Reduce reactive load: Incorrect due to personnel are expected to COMPLY with PSD request for VAR generation OR immediately NOTIFY the PSD of inability to provide the requested VARs. Due to low voltage 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. Referencing WC-M-101 "Online Work Control Process" and WC-M-104 "Review and Screening for Production Risk", ensures 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 offsite power or station blackout. Reduce generator field current to raise generator voltage: Incorrect due to reducing generator field current will reduce generator loading which will tend to reduce generator output voltage and current, the opposite effect for grid instabilities due to low grid voltage concern. 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. Ensure stator cooling water temp <82 deg C: Incorrect due to these action are associated with Stator Water Cooling Runback, If a runback were in progress Personnel are directed to VERIFY the following as appropriate: Runback of EHC Stator current> 7,469 amps Load Set Loss of Stator Cooling is detected by any of the following: Inlet High Stator Water bulk outlet temperature (81°C) Bushing coolant flow <84 gpm. I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 14 Difficulty: 4.00 rc .. System ID: 8798 User-Defined ID: 8798 i Cross Reference Number: LLQI15§6.Q2 Topic: Grid disturbance causing.."oltage and Num Field 1: i Num Field 2: SRO 3.7 Text Field: 700000 AA 1.01 Comments: General Data Technical Reference with E-5, Grid Emergency Revision Number: S32.3.A, Main Generator Inspection During Heavy I Grid Load. Cognitive Level L PRA: (i.e. Yes or No or #) N 10CFR 55.43 (N/A for RO) 55.41 (b) 10 Question History: (I.e. LGS New NRC-05, OYS CERT-04J Question Source: (I.e. New, New Bank, Modified) Revision History: Revision History: (I.e. Modified distracter "b" to make plausible based on OTPS i review) ILy i (-" "" Supplied Ref (If \ appropriate): (I.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A i required}: KIA 700000 AA1.01 RO 3.6 SRO 3.7 EXAM BANK COMPUTER TEST Page: 56 of 195 20 August 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. 525 sec RH R @ 250 psig D. 525 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 . . OISTRACTOR k5 sec; CS @ 455psig: Incorrect due to RPV pressure I discharge pressure of CS pump. 525 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 to be added to the 105 sec timer due to DW pressure condition stated> 1.68 psig. EXAM BANK COMPUTER TEST Page: 57 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR 525 sec; CS @ 455 psig: Incorrect due to wrong timer I and too high an RPV pressure as stated above. * *Question 20 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 Number: Topic: Reactor low level and effects as pressure drops Num Field 1: R03.8 /\ Num Field 2: SRO 3.9 () t. () .I J

• fI l Text Field: 295031 EK2.02 I-JiW Comments:

il t.:tl P ,.. .tY Or , r<.r General Data Technical Reference with ARC 110 C-4 Revision Number: ARC 113 F-3, E-3 Cognitive Level H PRA: (I.e. Ves or No or #) V 1 OCFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (I.e. LGS New NRC-05, OVS CERT-04) Question Source: (I.e. New, New Bank, Modified) Revision History: Revision N/A History: (I.e. Modified distractor ub" to make plausible based on OTPS review) ILT Supplied Ref (If none (I.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if required): EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 21 10: 8846 Points: 1.00 Unit 2 plant conditions are as follows: Reactor power is 100%. A high radiation condition occurs at the outside air intake to the Main Control Room (MCR) Ventilation System. Control Room Emergency Fresh Air Supply (CREFAS) is in normal alignment with "A" CREFAS in "AUTO". WHICH ONE of the following describes the CREFAS fan response and expected MCR ventilation alignment? C ,L CREFAS fans alignment A. One fan starts Outside air and recirculated air B. Two fans start Outside air and recirculated air C. One fan starts Recirculated air ONLY D. Two fans start Recirculated air ONLY Answer: A Answer Explanation: ANSWER 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. DISTRACTOR Two fans start, Outside air and recirculated air: Incorrect due to In the event of radiation isolation, the CREFAS fan in AUTO (A or 8) will start immediately. EXAM BANK COMPUTER TEST Page: 59 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order One fan starts, Recirculated air ONL V: Incorrect due In the event of radiation isolation, the CREFAS fan AUTO (A or B) will start Two fans start, Recirculated air ONLY, Limit exposure of MCR staff: Incorrect due to In the event radiation isolation, the CREFAS fan in AUTO (A or B) start 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: User-Defined 10: Cross Reference Number: Topic: RO QUESTION 59 Num Field 1: 3.9 " Num Field 2: 4.2 I! '\ \ (l \ (;; I l/J n.-P n r. 11 I-::T::-=-ex-'-:t-=Fc:-'ie'='"'ld:--': ... I ;* 11 [':vI') JI.. ",. General Data V)V "or Technical Reference 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 (N/A for RO) 55.41 (b) 8 Question History: (i.e. LGS Bank, Modified NRC-05, OYS CERT-04) Question Source: (I.e. New, Bank, 560493 Bank, Modified) Revision History: Revision Bank, 560493. Modified History: (I.e. Modified answer and distractors to distractor "b" to make include 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 Supplied Ref (If NONE I appropriate): (i.e. ABN-##) EXAM BANK COMPUTER TEST Page: 60 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Excluded

Reference:

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

Low KA Justification (if N/A required): i I EXAM BANK COMPUTER TEST Page: 61 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 22 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 Annuciators are received: 117 HPCI, C-1, HPCI Steam Line Hi Flow 002 VENT, F-5, Reac Enel St Fldg Dmpr Pnl10C234 Trouble 107 REACTOR, G-5, 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 Reae Encl HVAC Pnl1 BC208 Trouble 006 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 steam 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 VENT. SEC. CONT.INTEGRITY A. Isolated Maintained B. Isolated NOT Maintained C. Lined up to RERS Maintained D. Lined up to RERS NOT Maintained Answer: Answer EXAM BANK COMPUTER TEST Page: 62 of 195 20 August 2010 EXAMINATION ANSWER IL RO questions in sample plan order ANSWER DISTRACTOR _ ... DISTRACTOR DISTRACTOR .--. 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 Encl St Fldg Dmpr Pnl actuation with Security report of steam visible above the Diesel Genertors indicates that the HPCt 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 S76.0.A is also referenced for evaluting the Secondary Containment Steam Flooding Damper actuation. Isolated; Maintained: Incorrect due to indications of Secondary Containment Blowout Panel actuation following Steam Flooding Damper actuation to isolate the HPCI Pump Room. (Partially correct for HPCI Pump Room Vent isolation) 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 , .... . ..Lined up to RERS; NOT Maintained: Incorrect due to reason stated above. (Partially correct for Secondary Containment Integrity NOT Maintained) Question 22 Info i Question Type: I Status: ... i Always select on test? Authorized for practice? , Points: Time to Complete: Difficulty: . System 10: i User-Defined ID: Cross Reference Number: ,Topic: . Num Field 1: MultiQle Choice Active No No 1.00 4 3.00 8847 8847 LLOT0190.lL6F RO QUESTION 60 3.3 i Num Field 2: 3.7 /"'. j n J ... II' !fl.I .D i Text Field: 295035 EK2.04 !1"-1../(f fr,Comments: " *,j.,h hll I General Data ft1 VIV\ v v h II EXAM BANK COM PUTERTEST Page: 63 of 195 20 August v EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Technical Reference with LGS UFSAR, CHAPTER Revision Number: 03,3.6-14, REV. 14 Cognitive Level H I 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 I NRC-05, OYS CERT-04) I! Question Source: (i.e. New, Bank, LIMERICK LOT I Bank, Modified) 0603 Revision History: Revision Bank, LIMERICK LOT History: (Le. Modified 0603. Modified answer distractor "b" to make and distractors to include plausible based on OTPS reason for blowout panel review) operation to more closely align question with KIA. Edited question stem for clarity. Changed order of distractors. Changed correct answer from D to B. ILT /' Supplied Ref (If NONE v appropriate): (Le. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A I required): I EXAM BANK COMPUTER TEST Page: 64 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 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 I nominal conlrol band. EXAM BANK COMPUTER TEST Page: 65 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Pumps Runback to 28% Speed; Reduces power restore level by reducing steam load: Incorrect due conditions not met for Low Limit Runback per NOTE block in section 4.3. (Partially correct for for the Response although the Recirc Pump Response incorrect for plant conditions Pumps runback to 28% Speed; Reduces power ensure adequate NPSH to Recirc Pumps: due to stating Low Level Runback and wrong reason the power reduction. Although ensuring adequate is correct for Low Level Runback, this is not correct for conditions I Pumps runback to 42% Speed; Reduces power ensure adequate NPSH to Recirc Pumps: due to wrong reason for the Runback response as above. (Partially correct for Recirc Pump Response High Level I I Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No ! Authorized for practice? No Points: 1.00 Time to Complete: 12 Difficulty: 3.00 C-c::. . System 10: User-Defined 10: : Cross Reference Number: LLOT0040.04 100% power Both reactor recirculation pumps are running Topic: at 80% speed The "2B" Reactor Feedwater Num Field 1: Num Field 2: 3.3 , (.J-t (, {'J A I fJ 4 Text Field: 295009 AK3.01 '''IY x.,v-z,.c. fjNU!JlJ"'1( Comments: /I 17 h 1?rt...General Data -n Technical Reference with . I Revisio Revision Number: n#: Cognitive Level L Justification for Non SRO 10CFR55.41 (b) 5 CFR Link: Question History: (i.e. LGS IL T NRC Exam 2005 NRC-05, OYS CERT -04) Question Source: (Le. New, IL T NRC Exam 2005 Bank, Modified) Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 66 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order .1 Revision History: Revision . History: (Le. Modified ! distractor "b" to make plausible based on OTPS II ILT Supplied Ref (If None appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. None Ensure ON-## notprovided)

I Question 23 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 67 of 195 20 August 2010 EXAMINATION ANSWER I L T09-1 RO questions in sample plan order 10: 8848 Points: 1.00 Unit 1 was operating at 100% power when an earthquake resulted in the following conditions: downscale A:fllS RCIC in service for level control High containment radiation levels are indicative of fuel failure Unisolable RWCU lioe break High Rad conditions ttl the RCIGpllmp-r6bm and at the RWCU Regenerative Heat Exchanger .-. Reactortnclosure HVAC isolated and SGTS initiated The following annunciators have alarmed: 109 RAD, B-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 Iinop 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 lists of a¢i9ns i correct to minimize offsite release from the Radwaste Enclosure HVAC System. 03> Ensure Reactor Drain Sump Pumps Selector Switch is in 'NORMAL' to eliabl& high ffldietion 9nr Closely monitor North Stack Release Rate. Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'HI-HI I2Ymp nigh radiatioFl trif>. I Closely monitor North Stack Release Rate. Ensure Reactor Enclosure Floor Drain Sump Pumps Selector Switch is in 'NORMALt'&-enabJ9 Pump bigR ftleiiatioFl tnI'. Transfer Reactor Enclosure Floor Drain Sump to Suppression Pool. Ensure Reactor Enclosure Floor Drain Sump Selector Switch is in 'HI-HI RAD' .to..Qefeet SOIIl!? PUiIiP rllgiliadietiol"! sf4( Transfer Reactor Enclosure Floor Drain Sump to Suppression Pool. Answer: D Answer Explanation: EXAM BANK COMPUTER TEST Page: 68 of 20 August 2010 EXAMINATION ANSWER IL T09-1 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 HVAC 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. 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. 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. I Page: 69 of 195-----*EXAM BANK COMPUTER 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order [QUestion 24 Info Question Type: *Status: *Always select on test? I Authorized for

• Points: *Time to Complete:

I Difficulty: System User-Defined *Cross Reference Number: Num Field Num Field Text MultiQle 1.00 LGSOPS1560.IL5, LGSOPS1561.1L RO QUESTION 62 2.8 ( n If' \' /l /; f7::.... [) 295036 EA1.03 ttL ,,'Y ,,'\...v it{14'.,"t)A l /11\, .*,,) tJ'T> 'DA iz_ General Da ... D alM I Technical Reference with T-03 basis Rev 'lrr;

• Revision Number: T-236, Rev 14 Level PRA: {Le. Yes or No or #} 10CFR 55.43 (N/A for RO) 55.41 Question History: (Le. LGS NRC-05, OYS Question Source: (Le. New, Bank,
• Revision History: History: (Le.

distractor "b" to plausible based on ILT

• Supplied Ref NONE appropriate): (i.e. Excluded

Reference:

(Le. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 70 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 25 10: 8849 Points: 1.00 Unit 1 plant conditions are as follows:

• Reactor shutdown
• Loss of Coolant Accident
• T -102 in progress
• Drywell Spray is required Drywell Spray suction source must be determined
• 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 PRI C:DNT PRESS LIMIT IDO 90 a BO til 10..., UJ DD GO paig"" "" 50...J <;;> CI.. 30 a.. a.. ::J 2Q Vl 10 0 Pi'll CDMT WATER LEVEL 1FT) CONTAINMENT LEVEL IN FEET ___ PSIG SUPP POOL PRESS ON PR57-ilQI IBLUE PEN) MINUS H ___ PSIG PRI CONT PRESS ON PR5i'-1I01 (RED PEN) EOUALS (=1 --::--::-_

t::. f'SIG TIMES (Xl --,=,2.=3_ FT/PSlG EIJUAlS (=J ---FT PLUS (+) 26.B FT EOUALS (=) ---FT LEVEL TABLE SUPP POOL/DW SPRAY SUCT CONDITION SUCT On safe side of Curve PC/P-l

• Internal (Supp
• External (RHRSW OR Fire Water) On unsafe side of Curve PC/P-l Internal (Supp Pool) ONLY WHICH ONE of the following describes the Primary Containment Water Level and the appropriate Drywell Spray Suction Source? Primary Containment Level Drywell Spray Suction Source A. 102.7 feet Internal Preferred B. 102.7 feet Internal Only C. 75.9 feet Internal Preferred EXAM BANK COMPUTER TEST Page: 71 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order D. 75.9 feet Answer: A Answer Explanation:

ANSWER DISTRACTOR DISTRACTOR DISTRACTOR Question 25 Question Always select on Authorized for Time to er-Defined 10: Cross Reference Number: Topic: Num Field 1: ! N, 1m Field 2: ield: Comments: Internal Only 102.7 feet, Internal Preferred: (51 -18 =33) 33 x 2.3 + 26.8 =102.7 feet Internal sources are preferred. 144.1 feet, Internal Only: 51 x 2.3 + 26.8 144.1; if Primary Containment Level were 144.1 feet, only internal sources would be used. 75.9 feet, Internal Preferred: 33 x 2.3 =75.9; if Primary Containment Level were 75.9 feet, only internal sources would be preferred. 117.3 feet, Internal Only: 51 x 2.3 =117.3; if Primary Containment Level were 117.3 feet, only internal sources would be used. I Choice No 1.00 5 3.00 8849 8849 LGSOPS1560.IL4 RO QUESTION 63 3.4 3.5 295029 EA2.03 General Data Technical Reference Revision Cognitive I PRA: (i.e. Yes or No 10CFR 55.43 (NtA fo Question History: (Le. LGS NRC-OS, OYS CERT-04) Question Source: (Le. New, Bank, Modified) Revision History: Revision History: (i.e. Modified distractor "b n to make plausible based on OTPS review) ILT Page: 72 of 195 T-102 Rev 23 H NO 55.41 (b) 10 NEW NEW NEW 20 August 2010 EXAM BANK COMPUTER TEST EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Supplied Ref (If T-102 Rev 23, Curve appropriate): (I.e. ABN-##) PC/P-1 T-102 Rev 23,Table PC/P-1 Excluded

Reference:

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

Low KA Justification (if N/A required): I EXAM BANK COMPUTER TEST Page: 73 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8850 Points: 1.00 Unit 1 plant conditions are as follows: Reactor startup in progress Reactor power is 19% 108 REACTOR, F-4, ROD DRIFT alarms One RED rod drift light illuminates for an edge rod on the Core Vertical Display 10C649. The rod drift reset button is depressed on 10C603 and the ROD DRIFT alarm is reset. 108 REACTOR, F-4, ROD DRIFT alarms a second time A RED rod drift light illuminates for a second edge rod on 10C649. When selected on the Rod Select Matrix, the Four Rod Display indicates both control rods are moving out at slower than normal speed. 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 a generic issue resulting in inadvertentjJositive 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-1 04 is correct; however, answer is incorrect because manual scram is required with multiple drifting rods. EXAM BANK COMPUTER TEST Page: 74 of 20 August 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 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. ISOLATE the effected Control Rod Drive Mechanisms from their HCUs: Incorrect due to while isolation of the CROs from their HCUs will either terminate the drifting or verify that the drifting is being caused by stuck CRO 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 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 8850 8850 LGSOPS1550.IL 1 AND IL2 Inadvertent Reactivity Addition 4.4 4.7 295014 2.1.7 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. i Bank, Modified) . Revision History: Revision History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ON-104, Bases, Rev 53a L ) 'Ne1 ... 55.41 (b) ILT Supplied Ref (If NONE appropriate): {i.e. ABN-##) EXAM BANK COMPUTER TEST Page: 75 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order II Excluded

Reference:

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

EXAM BANK COMPUTER TEST Page: 76 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8851 I Steps OW IT-10 and OW IT-11 of the LGS TRIP procedure T -102 dire actions to rapidly shutdown the reactor when drywell temperature cannot be maintai d below 340°F . .,.:::::..... (WHICH ONE of the following describes the reason steps OWIT-10 and OWIT-11 direct rapid shutdown of the reacto!? R'ecretOr'ShotdOWn is required because drywell spray will be initiated. ghl:ltQ9Wn is required because drywell temperature affects reactor level indication. si'lt:ltdewn is required to allow for normal depressurization, slowing the continued rise in drywell temperature. Reactor shutdown is required before1*Pv'depressurization is initiated. Vessel depressurization reduces or terminates the continued rise in drywell temperature. Answer: o Answer Explanation:

---

,Reactor shutdown is required before RPV depressurization is initiated.

Vessel depressurization reduces or terminates the continued rise in drywell temperature: Correct because T-102 Bases for Step OWIT-11 states that when drywell temperature cannot otherwise be maintained below 340 degrees (i.e" 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 (OW IT) control flowpath to terminate, or reduce as much as possible, any continued rise in drywell temperature by rapidly depressurizing the RPV. This action should be taken, however, only after the reactor has been shutdown. This ensures that. if possible, the reactor is scrammed and shutdown by control rod insertion before RPV depressurization is initiated. _ .. Reactor shutdown is required because drywell spray will be initiated: Incorrect due to step OW 1T-8 requirement for evaluating OWIT-3 and spraying the drywell if Supp Pool level is below 38.7 feet prior to OW temp reaching 340 degrees. -"-'-'-'-- Reactor shutdown is required because drywell temperature affects reactor level indication: Incorrect due to no link between T-102 expected level effects evaluated per T -291 and OW IT-1 RPV level validation curve and Shutdown requirement. EXAM BANK COMPUTER TEST Page: 77 of 195 20 August 2010 EXAMINATION ANSWER KEY IL T09-1 RO questions in sample plan order I DlSTRACTOR Reactor shutdown is required to allow for normal I depressurization, slowing the continued rise in . drywell temperature: Incorrect, Conditions require a I

• Blowdown, as opposed to a normal

..... "cm 27 Info Question Multiple Status select on test? Authorized for practice? . Points: Complete: I System 10: I User-Defined 10: Reference Number: Topic: RO QUESTION 65 Num Field 1: 3.1 Num Field 2 3.2 U 1 -;..,. r I. /) /' . I .c-tl lvv'Text Field: 295012 AK1.02 J/1.V(jIl'll I\JJt:tt-' (ft.A.If'L',.Jx Comments: V , '}rt4-Yt) 1,,-" General Data--- 'Y j' r-:rechnical Reference with T-102 basis, Rev 23 C!A Revision Number: lJ!oi Cognitive Level L ! PRA: (Le, Yes or No or #) NO 1 OCFR 55,43 (N/A for RO) 55.41J22.i3 I' Question History: (I.e. LGS NEW

• NRC-05, OYS I Question Source: (I.e. New, I Bank, Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS i reviewl ILT Supplied Ref (If tJ }\tr appropriate}:

{I.e. Excluded

Reference:

(I.e. T-102 )I Ensure ON-## not provided) 

"-" I ! Low KA Justification (if N/A required): _ I EXAM BANK COMPUTER TEST Page: 20 August 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, Main Steam Line Hi Flow is recieved -"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? All MSIVs remain OPEN ONLY "1 D" MSL Inboard and Outboard MS1Vs isolated ALL Inboard MSIVs are ALL Outboard MSIVs remain ALL Inboard and Outboard MSIVs are isolated Answer: D Answer Explanation: All Inboard and Outboard MSIVs are isolated: 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 1 A isolation will occur. This will isolate ALL Inboard and Outboard steam line MSIVs. NOTE: this logic arangement is unique to MSIVs, other NSSSS logic arrangements consist of one logic system for all inboard isolation valves, one for all outboard isolation valves. i All MSIVs are open: Incorrect due to Group I isolation logic satisfied (8, or C) and (B or .Q) to complete the isolation for both Inboard and Outboard MSIVs ONLY "10" MSL Inboard and Outboard MSIVs are

• isolated:

Incorrect due to same isolation logic used to control isolation of all (4) steam lines. No logic failures il\!Y r-' would cause isolation of a single . ALL Inboard MSIVs are isolatedl ALL Outboard MSIVs remain open: Incorrect due to same transmitters used to control logic contacts in both the Inboard and Outboard logic trains. EXAM BANK COMPUTER TEST Page: 79 of 20 August 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 28 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: 8803 User-Defined ID: 8803 Cross Reference Number: LLOT0180.6G Topic: NS4 MSL isolation Num Field 1: 3.8 Num Field 2: 3.9 0 ___,... f) A 11 V t'I..'-v Text Field: 223002 K1.01 !\.Il"- __ dVI \" Comments: General Data Technical Reference with GP-8.1, Rev. Revision Number: ARC 114 D-2 Cognitive Level L PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 3 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 appropriate): (I.e. Excluded

Reference:

(i.e. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 80 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8804 Points: 1.00 Unit 2 plant conditions are as follows: Reactor power is 100% The 0-24 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 The 0-24 EOG has been loaded to 1850 KW and load is WHICH ONE of the following describes the approximate time the 0-24 EDG can be operated WITHOUT additional operator action? A. UP t01 hour. B. UP to 7 days. C. MORE than 3 hours D. MORE than 7 days. Answer: C Answer Explanation: MORE than 3 hours: Correct because the EOG fuel oil day tanks were verified as being filled to capacity prior to the LOOP, which provides enough fuel for a minimum of 3% hours 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% hours of continuous

• operation AT RATED LOAD. EXAM BANK COMPUTER TEST Page: 81 of 20 August 2010 EXAMINATION ANSWER lL T09-1 RO questions in sample plan order 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).

MORE than 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). Because the D-24 EDG is being operated at less than rated load (1850 KW), the D-24 EDG could be operated for MORE than seven days if the EDG 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: Mult[ple Choice I Active Always select on test? No Authorized for practice? No 1.00 Time to Complete: i 3.00 System 8804 User-Defined ID: 8804 Cross Reference Number: LGSOPS009292B.3A DG operation, fuel oil sL!PPly Num Field 1: 3.2 Num Field 2: Text Field: Comments:

3.3 264000

K1.05 [ "" /) ,.,., V (' .A. f /J \ V-Gerfural Data Technical Reference with P&ID 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 (NJA for RO) 55.41 (b) 8 History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (Le. New, NEW Bank, Modified)

EXAM BANK COMPUTER TEST Page: 82 of 20 August 2010 EXAMINATION ANSWER KEY IL T09-1 RO questions in sample plan order Revision History: Revision NEW History: (i.e. Modified I distractor "b" to make plausible based on OTPS I* review} ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) i Excluded

Reference:

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

I Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 83 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order ID: 8802 Points: 1.00 Unit 1 plant conditions are as follows: OPCON 3 RPV pressure is 40 psig 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 LPCI INJECTION 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, 178, and 17D will OPEN. HV-51-F017C remains CLOSED. HV-51-F0178 and HV-51-F017D will OPEN. HV-51-F017A and HV-51-F017C remain CLOSED. Answer: 8 Answer Explanation: HV-51-F017B, 17C, and 17D will OPEN. HV-51-F017A remains CLOSED: All four LPCI INJECTION valves 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 FO 17 A will remain closed. HV-51-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 poweV' __ ____ 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 '---_______-1-a'-n"-'-d D.as power available to open. EXAM BANK COMPUTER TEST Page: 84 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 30 Info Question Type: Multiple Status: Always select on test? Authorized for practice? Points: . Time to Complete: 3 Difficulty: 3.00 System ID: 8802 User-Defined ID: 8802 I 1-='Cross Reference Number: LGSOPS0051.IL 16A /1 iTOPiC: RO QUESTION 3 / / I Num Field 1: 2.5 \ .f / /Num Field 2: 2.7 --",\JY '\"'Y' / Text Field: .-103000 K2.= \" . t=t .... \f&J'l 'f Comments: . . v.\, General Data v Technical Reference with LGS Electrical Drawings: Revision Number: E-28, E-58 sheet 1 and 4. General Electric Drawings: E11-1030 F001, F002 I Cognitive Level H I PRA: (i.e. Yes or No or #} NO J 1 OCFR 55.43 (N/A for RO) 55.41 (b) 7 I . 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: (i.e. Modified distractor "b" to make plausible based on OTPS i review) ILT II Supplied Ref (If NONE (i.e. ABN-##) .. Excluded

Reference:

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

Low KA Justification (if N/A . reguired}: EXAM BANK COMPUTER TEST Page: 85 of 195 20 August 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. The D134 Load Center Breaker trips open. 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. 1 A and 1 B Compressors running. B. 1A and 18 Compressors NOT running. C. 1A Compressor running. 1 B Compressor NOT running D. 1 A Compressor NOT running. 18 Compressor running. Answer: 0 Answer Explanation: 1A Compressor NOT running. 1 B Compressor running: The 1A 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 LOCA SHUNT trips are reset not less than 10 minutes following the LOCA signal, restoring the 18 Instrument Air Compressor to service. 1A and 1 B Compressors running: The 1A and 1 B 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. 1 A and 1 B Compressors NOT running: The 1 A and 1 B Instrument Air Compressors are both SHUNT tripped on a LOCA signal. The 1 A 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 18 Instrument Air Compressor to service. 1 A Compressor running. 1 B Compressor NOT running: The 1A 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 18 Instrument Air Compressor to service. EXAM BANK COMPUTER TEST Page: 86 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 31 Info lQuestion Type: i Status: Always select on Authorized for . Time to System User-Defined Cross Reference Num Field . Num Field 2: Text Field: Comments: Multiple Choice Active No No ! 4.00 8806 8806 LGSOPS0015.IL 16A RO QUESTION 4 / 2.8 I\: '" n* 1.1 N"'\ \ 300000 K2.01 1 M

• IJ General Data Technical Reference with SE-10-1, Rev. 44, Page 1 Revision Number: Cognitive Level H PRA: (I.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (I.e. LGS NRC-05, OYS Question Source: (I.e. New, Bank, Revision History: Revision History: (i.e.

distractor "b" to plausible based on i Supplied Ref (If NONE i (I.e. ABN-##) I Excluded

Reference:

(i.e. NONE i Ensure 01\1-## notprovided) i I Low KA Justification (if N/A i reguired):

EXAM BANK COMPUTER TEST Page: 87 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8807 Points: 1.00 Unit 1 plant conditions are as fsllows:

• OPCON4 tJo /UIA....--.
• RPV level is + 86 inches on Upset

-........ ,_.

• Reactor pressure is 0 pSig.
• 1B RHR is in Shutdown.Cooling (SDC) Reactor level drops to +57 inches on Upset WHICH ONE of the following describes the affect on reactor pressure WITHOUT operator action? Reactor pressure will remain at 0 psig INDEFINITELY. Reactor pressure will begin rising IMMEDIATELY and continuously as reactor coolant temperature rises. Reactor pressure will begin rising IMMEDIATELY; however, pressure will stabilize as natural circulation develops. Reactor pressure will NOT immediately rise; however, pressure WILL eventually rise as reactor coolant temperature continues to rise .. Answer: D Answer Explanation: Reactor pressure will NOT immediately rise; however, pressure WILL eventually rise as reactor coolant temperature continues to rise: The plant is in OPCON 4; therefore, bulk reactor coolant temperature is 200°F. At 0 psig, reactor pressure will NOT rise immediately; however, when bulk reactor coolant temperature reaches 212°F, reactor pressure will begin to rise and will rise continuously without operator action to establish core circulation.

Reactor pressure will remain at 0 psig INOEFINITEL Y: With the plant in OPCON 4, bulk reactor coolant temperature is 200°F; therefore, rector pressure will remain at 0 psig until bulk reactor coolant temperature reaches 212°F; however, the answer is incorrect because reactor pressure WILL begin to rise once bulk reactor coolant temperature reaches 212°F. Reactor pressure will begin rising IMMEOIATEL Y and continuously as reactor coolant temperature rises: The plant is in OPCON 4; therefore, bulk reactor coolant temperature is 20QoF. At 0 psig, reactor pressure Will not rise UNTIL bulk reactor coolant ! temperature reaches 212°F. EXAM BANK COMPUTER TEST Page: 88 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Reactor pressure will begin rising IMMEDIATELY; pressure will stabilize as natural circulation develops: At 0 reactor pressure will not begin to rise until bulk reactor temperature reaches 212°F. Also incorrect because reactor level be greater than 60" on Shutdown Range or greater than 78" on Range to establish natural circulation. When reactor level is those levels, the moisture separator drains are uncovered and water inside the shroud is not coupled with the water outside the ______ preventing natural circulation. ______________________________EXAM BANK COMPUTER TEST Page: 89 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 32 Info Question Type: Multiple Status: Always select on test? Authorized for practice? Points: i Time to 3 3.00 10: 8807 User-Defined 10: 8807 I . Cross Reference Number: LGSOPS0051.1L 13A I TOJ>ic: RO QUESTION Num Field 1: fI Num Field 2: 3.3 If! i 1\ 1. 11), Text Field: 205000 K3.01 LQ"'I-'l"' ']S I V V J l-..... Comments: 1 I' 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 COllnitive Level H PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b 5 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 n to make plausible based on OTPS reviewl ILT Supplied Ref (If ! NONE appropriate): (i.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 90 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 33 10: 8808 Points: 1.00 Unit 2 plant conditions are as follows: -Two Loop -Total Recirc Drive Flow is -Total Core Flow is 45 Reactor Power (Process Computer) is 1660 -Average APRIVI Reading is 51 WHICH ONE of the following represents the current APRM flow biased scram setpoint based on the conditions above? A. 90.8% B. 92.5% C. 96.5% D. 98.4% Answer: D Answer Explanation: ANSWER 98.4%: Correct because 0.66(54) + 62.8 =98.4% DISTRACTOR 90.8%: Incorrect due to above calculation DISTRACTOR 92.5%: Incorrect due to above calculation OISTRACTOR 96.5%: Incorrect due to above calculation EXAM BANK COMPUTER TEST Page: 91 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 33 Info Question Always select on Authorized for Time to I System User-Defined Cross Reference *Topic: Num Field Num Field Text Multiple Choice Active No No 1.00 3 3.00 8808 8808 LOT0275. 14, 15 Two Loop Operation -Total Recirc Drive Flow is 54% Total Core Flow is 45 Mlbm/hr -Reactor Pwr I 3.7 / /3.7 " 1\ ** / 215005 K4.07 WW f' .J\l1"" V '\ ':2/'Question Info I Question Type: MultiQle Choice I Status: Inactive Always select on I No test? I Authorized for No Points: Time 0 Difficulty: J System ID: 4660 . User-Defined ID: LIMERICK LOT 6021 Cross Reference NEW Number: Two Loop Operation -Total Topic: Drive Flow is 54% Total Core Flow 45 Mlbm/hr -Reactor Num Field 1: Num Field 2: Text Comments: General Data Technical TIS 3.3.1 Reference with Revision Number: Justification for 55.41 (b) 7 Non SRO CFR Link: Cognitive Level H Question History: Bank (i.e. LGS 05, OYS 04) Page: 92 of 20 August 2010 EXAM BANK COMPUTER TEST EXAMINATION ANSWER IL T09-1 RO questions in sample plan order i Question Source Bank (Le. New, Bank, Modified) LowKA N/A Justification (if required): Revision History: Bank Revision History: (Le. Modified distractor "b" to make plausible based on OTPS I review) I LT Supplied Ref (If appropriate): (Le. ABN-##) Excluded

Reference:

(Le. Ensure ON-## Qot provided)

L)RT I EXAM BANK COMPUTER TEST Page: 93 of 195 20 August 2010 EXAMINATION ANSWER ILT09-i 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 AlllRMs are on Range SRM indications: "iA" 0.8 x 10 5 "1B" 2.5 x 10 5 "1C" 2.1 x 10 5 "10" 1.5 x 10 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: An SRM upscale condition will cause a control rod withdraw block i channel is above 1 x 10 5 cps, and with the RPS NI shorting links installed, excee the RPS set paint of 2 x 10 5 cps will not cause a reactor scram or half-scram. If t RPS NI shorting links had been removed, anyone SRM channel exceeding the F set point of 2 x 10 5 cps would have resulted in a full scram. Yes, yes, yes: An SRM upscale condition will cause a control rod withdraw blocl channel is above 1 x 10 5 cps. In the case of the IRMs or APRMs, "C" and "B" ch, above their scram set paints would result in a full scram, but for the SRMs, excel the RPS set pOint of 2 x 10 5 cps will not cause a reactor SCRAM or a HALF-SCF with the RPS NI shorting links installed; therefore, the answer is incorrect. If the I NI shorting links had been removed, anyone SRM channel exceeding the RPS point of 2 x 10 5 cps would have resulted in a FULL scram. Yes, yes, no: An SRM upscale condition will cause a control rod withdraw block channel is above 1 x 10 5 cps. In the case of the IRMs or APRMs, either the "C" c channels above their scram set paints would result in HALF-SCRAM, but for the SRMs, because the RPS NI shorting links are installed, exceeding the RPS set 2 x 10 5 cps will not result in a scram signal; therefore, the answer is incorrect. Ab the RPS NI shorting links had been removed, anyone SRM channel exceeding t RPS set point of 2 x 10 5 cps would have resulted result in a full scram. No, no, no: With the RPS NI shorting links installed, exceeding the RPS set pair x 10 5 cps will not cause a reactor scram or half-scram; however, answer is incon because an SRM upscale condition will cause a control rod withdraw block if any channel is above 1 x 10 5 cps. EXAM BANK COMPUTER TEST Page: 94 of 20 August 2010 i EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 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: 8809 User-Defined ID: 8809 Cross Reference Number: LGSOPSOO74.6 Topic: RO QUESTION 7 Num Field 1: 3.4 Num Field 2: 3.5 n! \,," f"-d-Text Field: 215004 K4.02 1 fYY'"'Vho ) JL tf\ Comments: U V I. J J?Cf'" General Data "vr-v r Technical Reference with ST-2-074-624-1, Rev 04, Revision Number: page 3 Tech Spec Table 3.3.6-1 Cognitive Level H = PRA: (i.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 7 Question History: (i.e. LGS BANK, MODIFIED NRC-05, OYS CERT-04) Question Source: (i.e. New, BANK: 562180 Bank, l\IIodified) Revision History: Revision Changed to Unit 2. History: (i.e. Modified Changed values of all 4 distractor "b" to make SRM readings. Changed plausible based on OTPS the channels indicating review) 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". ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) EXAM BANK COMPUTER TEST Page: 95 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Excluded

Reference:

(Le. Ensure ON-## not Low KA Justification (if i EXAM BANK COMPUTER TEST Page: 96 of 195 20 August 2010  

--EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8810 Points: 1.00 Unit 1 plant conditions are as follows: Synchronization of the Main Generator is in progress Voltage Regulator is in AUTO Synch Check Relay Selector switch is in NORMAL 535 Breaker Synch Selector Switch ON INCOMING VOLTAGE is 124 RUNNING VOLTAGE is 121 /, SYNCHROSCOPE is stable at the 12 o'clock position. Synchronizing lamps are OUT. WHICH ONE of the following set of conditions should be met prior to closing the 535 (OUTPUT) breaker? A. Raise generator speed. Raise incoming voltage B. Raise generator speed. Incoming voltage is satisfactory C. Generator speed is satisfactory. Raise Incoming voltage D. Generator speed is satisfactory. Incoming voltage is satisfactory Answer: B Answer Explanation: Raise generator speed. Incoming voltage is satisfactory: 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; therefore, ______cc-_l__in--c'"'--oming voltage is satisfactory. Raise generator speed. Raise incoming voltage: Generator speed must be raised until the synchroscope is rotating slowly in the FAST (clockwise) direction with synchronizing lights flashing; however, the answer is incorrect because generator voltage is satisfactory for closing the generator breaker (535). Additionally, raising incoming voltage would make conditions UNSATISFACTORY for breaker closure. ..----------1 Generator speed is satisfactory. Raise Incoming voltage: Generator speed must be raised until the synchroscope is rotating slowly in the FAST (clockwise) direction with synchronizing lights flashing, and the answer is also incorrect because generator voltage is satisfactory for closing the generator breaker (535). Raising incoming voltage would make conditions UNSATISFACTORY for breaker closure .. 20 August 2010 __ EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ._.__.__._--_.__.__._..__._--_._.. Generator speed is satisfactory. Incoming voltage satisfactory: Generator voltage is satisfactory for the generator breaker (535); however, the answer incorrect because generator speed must be raised until synchroscope is rotating slowly in the FAST ____-'--direction with synchronizing lights flashilJ.9 ..______Question 35 Info Question Type: ______ ..L-_.----.-.-_----------.---.-_--.-.---.--1 Status: ..-.----.-_1 Always§.elect on test?_.--,I.c._:.c: __........... ___..._._.. _. ___.__.__...... _............... ___........_..__ ... --l __ ___,____.________._.______..________.__ Points:.---.-.----.-----+-:-------------------.----------.---.-----J Time to Complete:

---

If-'---.

S stem 10: User-Defined ID: ____.__..____+:,..:Rc..::O--=-=.;;;..:.. ..:..=...:. ..:...::..- ..-----..--------.----_-- __..__ ._._.---] Num Field 1: 3.4 ___---------.-.-.-.----_I Num Field 2: 3.6 -------------

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';on,Qr<>1 Data Technical Reference with S32.1.A, Rev. 25, pages Revision Number: 7 and 8 .--.--.--.. Cognitive LeveL . ......,-__. H .ERA: (I.e. Yes or N9_or!tL NO__________-J 10CFR 55.43 (f\j!A for RO) 55.41 (blL_______---I Question History: (I.e. LGS BANK, MODIFIED NRC-Q§, OYS CERT-04.L.) _+--_________ Question Source: (i.e. New, BANK: 556938 Bank, Modified) 20 August 2010 --EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Revision History: Revision Changed to Unit 1. History: (Le. Modified Modified stem adding distractor "b" to make additional information plausible based on OTPS status of Sync Check review) Selector switch and Synchronizing lamps. Also changed the status of the synchroscope to static at the 12 o'clock position and changed the values of incoming and running voltage. Changed correct answer from "raise speed and raise incoming voltage" to "raise generator speed, and "incoming voltage is satisfactory." Changed correct answer from up\' to H8". ILT Supplied Ref (If NONE Excluded

Reference:

(i.e. NONE Ensure ON-## not provided) -cow'KA Justification (if N/A required) 20 August 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, RCIC 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 RCIC pump discharge pressure to 900 psig, and RCIC 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 RCIC 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. RCtC turbine speed has risen: RCle 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 flowrate to the CST; however, indications are that RCIC f10wrate has lowered; therefore, the answer is incorrect. RCIC FLOW CONTROLLER is in AUTO. RCIC turbine speed is constant: If the RCle turbine speed were constant with rising RCIC system headloss, RCIC system flowrate would lower. However, when the RCIC FLOW CONTROLLER is in AUTO, RCIC turbine speed automatically varies to I . maintain a constant flowrate to the CST; therefore, the answer i is incorrect. RCIC FLOW CONTROLLER is in MANUAL. RCiC turbine speed has lowered: If RelC turbine speed had lowered, RCIC system f10wrate 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: 100 of 20 August 2010 EXAMINATION ANSWER Il T09-1 RO questions in sample plan order Question 36 Info Question Type: Multiple Choice i Status: Active Always select on test? No

• Authorized for practice?

No ! Points: 1.00

• Time to Complete:

3 Difficulty: 3.00 System ID: 8811 User-Defined ID: 8811

• Cross Reference Number: LlOT0380.8A Topic: RO QUESTION Num Field 1: " <::: Num Field 2: 3.1 !\ ( \) Text Field: 217000 K5.02 \LL\G \)1I Comments:

I General Data I Technical Reference with i S49.7.A, Rev 08 Revision Number: Cognitive level H PRA: (Le. Yes or No or #) NO 10CFR 55.43JN/A for ROJ 55.41 Jb) 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) 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: 101 of 195 20 August 2010 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? Position Heater A. OFF OFF B. ON G: C. ON 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 90°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 duringrnixing. 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. 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. EXAM BANK COMPUTER TEST Page: 102 of 20 August 2010 EXAMINATION ANSWER Il T09-1 RO questions in sample plan order Question 37 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field I Text Multiple 3.00 SBlC Heater Operation I 2.7 2.9 /J 211000 K5.07 -S I 011Ju'1.1A..J

• V General Technical Reference with S48.1 .A, Rev 15, page Revision Number: S48.1.B, Rev 17, page 6 I Cognitive Level l PRA: (i.e. 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: (Le. New. NEW Bank. Modified)

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

Reference:

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

IllOW KA Justification (if N/A EXAM BANK COMPUTER TEST Page: 103 of 195 20 August 2010 EXAMINATION ANSWER RO questions in sample plan order 10: 8813 Points: 1.00 Unit 1 plant conditions are as follows: Reactor HPCI is operating for pressure control in accordance with S55.7 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 D12 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 isola.tes. HPCI CANNOT be returned to the pressure control mode. . The HPCI system CST flowpath isolates. HPCI CAN be returned to the pressure control mode IMMEDIATLY. The HPCI system CST f10wpath 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. The HPCI system CST flowpath isolates. HPCI CAN be returned to the pressure control mode IMMEDIATL Y: 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, HPCI cannot be returned to the pressure control mode, immediately or otherwise. EXAM BANK COMPUTER TEST Page: 104 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order The HPCI system CST flow path 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. I Question 38 Info I Question Type: Multiple Choice Status: Active I select on test? No I Authorized for practice? No I Points: 1.00 I Time to 3 *].00 .S'y::;tbl ID: 8813 ID 8813 I Cross Reference Number: LLOT0340.12B !To[)ic: RO QUi::::> nQN 11 Num Field 1: 3.6 .1 Field 2: 3.7 1\ J ." Text Field: __.. 206000 K6.11 .A1'LL (T f1.v/r . /lJ v 1( f7\_. '-' U General Data Technical Reference with I S55.7.A, Rev. 8 Revision Number: E-41-1 040-E-021, sheet 001, Rev, 12 Cognitive Level H \-:: I PRA: (I.e. Yes or No or #) NO I 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, NEW Bank, Modified} Revision History: Revision NEW History: (I.e. Modified distractor "b" to make plausible based on OTPS ILT Supplied Ref (If I NONE {I.e. ABN-##) I Excluded

Reference:

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

Low KA Justification (if N/A I required): EXAM BANK COMPUTER TEST Page: 105 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 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, UNIT DIV 1 SFGD BA TIERY CHARGERS TROUBLE alarms. WHICH ONE of the following identifies A. B. C. 1A1 and 1A2 Batteries D. 1A2 Battery ONLY Answer: A Answer Explanation: -,:---=--== 1A2 Battery and 1A10103 Battery Charger: The Division I DC Distribution system has 2 batteries and each battery ha ttery charger. The battery charge 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. ,-=-_____ will continue to supply the DC bus. 1A1D103 Battery Oharger 8Aly. Witfi a tnp of Mec 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 __ _____________ f-OISTRACTOR 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_ . 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: 106 of 20 August 2010 --EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 39 Info , Question Type: Status: Always select on test? Authorized for practice? Points: Time to Complete: Difficulty: L§y;:, ll:: I II II::h User-Defined ID: Cross Rei 1::1 I::llvl:: Number: ____ Num Field 1: Num Field Comments: Multiple Choice Active INo No 3 13.00 1.881! ,8814 I BQ QUESTION 12 13.2 263000 ] =J : J , , General Data Technical Reference with Revision Number: Cognitive Level PRA: (I.e. No 10CFR 55.43 {N/A for RO} Question History: (Le. LGS I NRC-05, OYS CERT-04} Question Source: (i.e. New, j3ank, Modified) ___Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If appropriate): {Le. ABN-##) Excluded

Reference:

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

Low KA Justification (if ARC-MCR-120 G-1, REV 3 E-33, sh1, Rev 44 E-55, sh1, Rev 51 L YES (b) L BANK C 562594 Bank, Modified. Changed stem to remove direct statement that the charger would trip on a loss of the 480 V AC 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. E-55, Sh 1, Rev 51 NONE N/A EXAM BANK COMPUTER TEST Page: 107 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8815 Points: 1.00 Unit 1 plant conditions are as follows: Reactor power is 7% Mode Switch is in "RUN" All IRMs are fully inserted "D" IRM recorder reads 122/125th The following IRM indicating lamps are illuminated on the 10C603 benchboard. "D"IRM "D" IRM UPSC TR or "H" IRM UPSC TR or "A" IRM UPSC TR or WHICH ONE of the following describes the affect of the IRM system on the RPS system? A. NO "A" "S" Side half-scram S. "Au side half-scram ONLY C. "S" side half-scram ONLY D. 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 "Au -IRM A, C, E, or G must be tripped to generate an "A" side half-scram, AND one IRM in RPS trip system "S" -IRM S, D, F, or H must be tripped to generate a "S" side half-scram. However, when the Reactor Mode switch is in RUN, all IRM 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 signal is generated when an IRM is UPSCALE or INOP. One IRM in RPS trip system "Au -IRM A, C, E, or G must be tripped, AND one IRM in RPS trip system "S" -IRM 8, D, 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. "An side half-scram ONLY: A scram signal is generated when an IRM is UPSCALE or INOP. One IRM in RPS trip system "f:>.:' -IRM A, C, E, or G must be tripped, OR one IRM in RPS trip system "8" -IRM S, 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 an "A" side half-scram to occur; however, the answer is incorrect because the Reactor Mode switch is in RUN bypassing alllRM generated scrams signals. EXAM BANK COMPUTER Page: 108 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order "6" side half-scram ONLY: A scram signal is generated when an IRM is UPSCALE or INOP. One IRM in RPS trip system "A" -IRM A, C, E, or G must be tripped, OR one IRM in RPS trip system "8" -IRM 8, 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 "8" side scram to occur; however, the answer is incorrect because the Reactor '---_____----" Mode switch is in RUN bypassing all IRM generated scrams signals. EXAM BANK COMPUTER TEST Page: 109 of 20 August 2010 EXAMINATION ANSWER RO questions in sample plan order Question 40 Info ___ _______ ____Status: Always select on test? Authorized for practice? _______ .0...:;.0_________,____.._____.___..______, Time to Complete: 3 Difficulty: 3.00 I ______. ,: __ ______.. User-Defined ID: ----------- Cross Reference Number: LG§OPSo.Q74.IL£OAI Topic: RO QUESTION 13 Num Field 1: 3.3 Num Field 2: 3.2 .J.-,!) IJ Jt-.. J / Text Field: 215003 A1.06 *J--.rlU1i I}t- .. 6 J V..hl cA'\. f? . . General gata -<t VW""", \ i1 Technical Reference withl M-1-C71-1020-E-006, (A,/\ ) f . Revision Number: I 007, 009 . f\? . H' A r7..v " i PRA: (I.e. Yes or No qrJ!L_ NO 'r . 10CF_R for RO) 55.41 (b) 5 L. Question History: (Le. LGS !'!RC-05, OYS CERT-04) Question Source: (I.e. New, Bank, LIMERICK LOT Modified) .. 2_8:...7___9_____.___--1 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): (I.e. ABN-##) ...__._.__._ Excluded

Reference:

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______-I Low KA Justification (if N/A ______.______L..___._..________' EXAM BANK COMPUTER TEST 20 August 2010 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 "B" SGTS fan The "B" 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: 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 flowrate 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 mainJ<3J!1 >-0.25" H 2 0. _____ 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 0. ----_._-_.---_. D1STRACTOR 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 0. D1STRACTOR +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 I the zone(s} pressure -.25" H 2 0. . ..______.___-' EXAM BANK COMPUTER TEST Page: 111 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 41 Info Question Type: Multiple Status: Always select on test? Authorized for practice? Points: to Complete: 3 ulty: 3.00 !System ID: User-Defined ID: Cross Reference Number: Topic: RO QUESTION Num Field 1: Num Field 2: 3.3 Text Field: 261000 A1.04 .c.. fl.t> Ii l J-j rI.. -Itv..J .dj.... 7/U C;/ -'J I ---:-1 I..General Data y/ i 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: (Le. LGS NRC-05, OYS CERT-04) Question Source: (Le. New. Bank. 561042 Bank, Modified) Revision History: Revision Changed answer from D History: (I.e. Modified to C. Changed distractor distractor "b" to make C to A; changed distractor plausible based on OTPS A to B. and changed review) distractor B to D. ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A I reguired}: EXAM BANK COMPUTER TEST Page: 112 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8817 Points: 1.00 Unit 1 plant conditions are as follows: 100% power SPTOTMOS indicates Suppression Pool temperature is 90°F and stable STEAM 110, B-1, SRV/HEAO VENT VALVE LEAKING alarms: XI-036-101 on 10C614 confirms rising Safety Relief Valve (SRV) Temperature for All Amber "SRV HAS L1FTEO" lamps on 1 OC626 are All Red "SRV OPEN" lamps on 1 OC626 are All Green "SRV CLOSEO"lamps on 10C626 are All White "SRV SOLENOIO ENERGIZEO"lamps on on 10C626 are SPTOTMOS indicates Suppression Pool temperature is 92°F and slowly 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.B.A SRV Leaking. Place One loop of Suppression Pool Cooling in service per OT-114 SRV FULLY Open Place One loop of Suppression Pool Cooling in service per S51.B.A SRV FULLY Open Place One loop of Suppression Pool Cooling in service per OT -114 Answer: A Answer Explanation: ANSWER-lsRVLeakin g , . 9 Place One loop of Suppression Pool Cooling in service per S51.S.A: An SRV/HEAO VENT VALVE LEAKING alarm,slowly rising Suppression Pool temperature, and rising SRV tailpipe temperature predict the I presence a leaking SRV. Appropriate action is to place one loop of _____ I suppreion pool cooling in operation per S51.8.A.:.... _______ SRV Leaking, Place One loop of Suppression Pool Cooling in service per OT*114: OT-114 is only entered for a stuck open SRV, additionally, OT-114 ==--+-directs placing two Pool Cooling in __ SRV FULLY Open, Place One loop of Suppression Pool Cooling in service per S51.S.A: Indication do not support that SRv is open, Additionally, If an sRV is open OT-114 should be entered. OT-114 directs placing two loops of ___-L._S_-'up'-'p'-r_es_si()n Pool_goDling in_service. EXAM BANK COMPUTER TEST Page: 113 of 20 August2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order SRV FULLY Open, Place One loop of Suppression Pool Cooling in service per OT-114: Indication do not support that SRv is open, Additionally, OT-114 directs placing two loops of Suppression Pool Cooling in service.. Question 42 Info Question Always select on Authorized for ! Time to Complete: I System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active No j No I .00 3 I 8817 8817 LGSOPS1540.1, 2, AND 5 I RO QUESTION 15 /" 3.2 /'l I I /239002 A2.02 S/LI/ V 0 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, Revision History: History: (Le. distractor "b" to plausible based on S51.8.A OT-114 BASES Rev. 255 T-102, H YES 55.41 (b) 7 NEW l ! NEW NEW ILT Supplied Ref (If NONE I appropriate): (i.e. ABN-##) Excluded

Reference:

(Le. NONE Ensure ON-## not rovided) i Low KA Justification (if N/A I required):

EXAM BANK COMPUTER TEST Page: 114 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8818 Points: 1.00 Unit 2 plant conditions are as follows: Division 2 DC was de-energized due to a ground A Loss of Offsite Power (LOOP) occurs coincident with a small break 2A and 2C LPCI pumps have RCIC and all available CRD and SLC pumps are Reactor pressure is 700 Vessel level has lowered to -161 ordered emergency vessel depressurization in witt'i 1-1111md Pripr to opening thenSRVs, th Division f ,9.C bus ge,:elopS\a fault de-energizing the bus........... 12."<.. tdJl1. Q.£( WHIC a a . e ex STATUS of the Core Spray system arTd impm;rOn . . ing? 1=/1/ '7 f v One Core subsystem is a ilable. Emergencyaepressurization immediately proceed. Alternate injection subsystems must be lined up per 111. One Core Spray subsystem is available. Emergency depressurization CAN proceed per T -112. One Core Spray pump ONLY is available. Emergency depressurization CANNOT immediately proceed. Alternate injection subsystems must be lined up per T-111. One Core Spray pump ONLY is available. Emergency depressurization CAN proceed per T-112. Answer: B Answer Explanation: One Core Spray subsystem is available. Emergency depressurization CAN proceed: The Core Spray System comprises two "subsystems" each consisting of two pumps discharging into a common header. With division 1 and 3 DC available, the "A" and "C" Core spray pumps are available, constituting one Core Spray subsystem. The systems listed in T-101 have proven inadequate to maintain level > -161 inches; therefore, T-101 RC/L is exited; T-111 is entered, and with one Core Spray subsystem available, the vessel can be EXAM BANK COMPUTER TEST Page: 115 of 20 Augusl2010 EXAMINATION ANSWER IL T09-'1 RO questions in sample plan order --------- One Core Spray subsystem is available. Emergency depressurization CANNOT proceed: The Core Spray System comprises two "subsystems", each consisting of two pumps discharging into a common header. With division 1 and 3 DC available, the "A" and "C" Core spray pumps are available, constituting one Core Spray subsystem. The answer is incorrect because the systems listed in T -101 have proven inadequate to maintain level> -161 inches, and with one Core S ra subs stem available, the vessel must be depressurized. One Core Spray pump is available. Emergency depressurization CANNOT proceed: With division 1 and 3 DC available, the "A" and "C" Core spray pumps are both available, constituting one Core Spray subsystem; therefore the answer is incorrect. If only one Core Spray pump were available, the second half of the answer would be correct; however, the answer is incorrect because the systems listed in T-101 have proven inadequate to maintain level > -161 inches, and with one Core Spray subsystem available, the must be depressurized. ____________..__.. One Core Spray pump is available. Emergency depressurization CAN proceed: With division 1 and 3 DC available, the "A" and "C" Core spray pumps are both available. constituting one Core Spray subsystem; therefore the answer is incorrect. If only one Core Spray pump were available, the second half of the answer would be incorrect; however, the systems listed in T-101 have proven inadequate to maintain level> -161 inches, and with one Core L._______.___. ____--L_S... the vessel can be depressurized. _____ Question 43 Info .-----.--.-._---._------+---.:--::---- .._---,--------.- ..-----------._- .._--------1 Cross Reference To Num Field EXAM BANK COMPUTER TEST Page: 116 of 20 August 2010

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--EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Technical Reference with Revision Number: Level T-111 BASES, Rev. 12, step LR-6, lR-7, and 8. E21-1040-E-005,006, 007, and 008. E-360. sheet 2, 3, and 4. H YES 55.41 {b} 5 ..Question History: (Le. LGS _NRC-05, OYS CERT-04} Question Source: (i.e. New. Revision History: Revision History: (Le. Modified distractor "b" to make plausible based on OTPS ILT-. Supplied Ref (If appropriate): (LE:. ABN-##) Excluded

Reference:

(Le.

Low KA Justification (if ___.. NEW NEW NEW EXAM BANK COMPUTER TEST Page: 117 of 195 20 August 2010 44 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: Points: 1.00 Unit 1 plant conditions are as follows: Unit 1 plant is at 100% reactor power 107 REACTOR, H-1, REACTOR WATER BELOW LEVEL 3 TRIP alarms The "B" Scram Status tamps on 1 OC-603 are NOT illuminated. The "An Scram Status lamps on 1 OC-603 ARE illuminated. WHICH ONE of the following identifies Reactor Level Switches that could have caused these 10C-603 Scram Status light indications? Reactor Level 3 Level Switch status A. LISL-42-1 N680A or 1 N680C tripped B. LlSL-42-1 N680B or 1 N6800 tripped C. LlSL-42-1 N680A and 1 N680B tripped O. LlSL-42-1 N680B and 1 N680C tripped Answer: B Answer Explanation: LlSL-42-1 N680B or 1 N680D tripped: A "B" or "0" Reactor Level trip unit failing downscale de-energizes the B 1 or B2 RPS relay logic resulting in a half scram on the "B" side, extinguishing the "B" 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 A1 or A2 RPS relay logic resulting in a half scram on the "Au side, extinguishing the "A" 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 "N an<j "B" RPS Scram Status lights. LlSL-42-1 N680C and 1 N680D tripped: The answer is incorrect because 1 N680C and 1 N6800 Reactor Level trip units failing downscale would de-energizes the A2 and B2 RPS relay logics resulting in a full scram, extinguishing both the "A" and "B" RPS Scram Status lights. EXAM BANK COMPUTER TEST Page: 118 of 20 August 2010 I

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EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 44 Info Question Multiple Choice Status: iActive select on test? No Authorized for practice?

No Points: 1.00 TIme to Complete: 3 3.00

10. 8819 Bi319 Cross Rej",. ""'v'" Number: LGSOPS0071.7A

[Topic: RO QUESTION 17 1: 3.2 r fI Field 2: 3.0 U)")/\ l\ .IT , I l.-<' It, ltv 212000 A3.02 \ \!,v (jY\AV'!;'WV JJb Comments: J / 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 L PRA: (Le. Yes or No or #) NO 10CFR 55.43.lli!A for RO) 55.41 (b) 7 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (i.e. New, BANK, MODIFIED Bank, Modified} Revision History: Revision Modified bank question History: (Le. 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. __ILT Supplied Ref (If NONE (Le. ABN-##L Excluded

Reference:

(i.e.

Ensure ON-## not provided) Low KA Justification (if N/A required}: EXAM BANK COMPUTER TEST Page: 1190f195 20 August 2010 II LXMERICK GENERATXNG STATXON 107 REACTOR H-1 ACS03 36 I ALARM WORDING: REACTOR 2 WATER BELOW LEVEL 3 3 TRXP 4 5 A B C D E F G H I AU'l'OMATXC ACTXONS: 1. SCRAM. 2. ADS system permissive.

3. Group II isolation.

OPERATOR ACTXONS: 1. IF SCRAM, THEN enter T-IOL RPV Control. CAUSES: 1-Low level in Reactor Vessel. ANNUNCXATOR#:

• None SETPOINT:
• 12.5" DEVXCE(S):
• LIS-42-1N680A(B,C,D}

REFERENCES:

1. E-620 2. C71-1020 ARC-MCR-I07 HI, REV. 0 PAGE I OF 1 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8825 Points: 1.00 Unit 1 plant conditions are as follows: "1An RECW pump is running with its control switch in "AUTO" "1 B" RECW pump is NOT running. Its control switch is in "AUTO". A leak at the discharge of the "A" RECW heat exchanger results pressure dropping to 115 psig on PI-13-108 at 10C655, and the following annunciator alarms at 118 SERVICES.

H-3, REAC ENCL COOLING WATER HTX OUT LO PRESS. WHICH ONE of the following describes the expected RECW pump status? A. 1A" RECW pump allQ. "1 Btl RECW pump running. B. 1AtI RECW pump running. "1 B" RECW pump NOT running. C. 1B" RECW pump running. "1A" RECW pump NOT running. D. "1A" RECW pump NOT running. "1B" RECW pump NOT running. Answer: A Answer Explanation: ANSWER '1A" RECW pump and "1B" RECW pump running: When RECW heat exchanger outlet pressure is < 118.6 psig, the standby RECW pump auto starts if its control switch is in AUTO without the presence of a LOCA signal. There is no indication of an "An RECW pump trip; therefore, both RECW should be running. 1A" RECW pump running. "1B" RECW pump NOT running: There is no indication of an "An RECW pump trip, so the "An RECW pump should be running. The answer is incorrect because when RECW heat exchanger outlet pressure is < 118.6 psig. the standby RECW pump auto starts if its control switch is in AUTO without the presence of a LOCA signal; ___________ pUI!:l£ ____________ 1 B" RECW pump running. "1A" RECW pump NOT running: The answer is incorrect because when RECW heat exchanger outlet pressure is < 118.6 psig, the standby RECW pump auto starts if its control switch is in AUTO without the presence of a LOCA signal; therefore, the "B" RECW pump should be running. The answer is incorrect because there is no indication of an "An L _______.L:....R=ECW pump trip; therefore, 20 August 2010 EXAMINATION ANSWER Il T09-1 RO questions in sample plan order DISTRACTOR "1A" RECW pump NOT running. "18" RECW pump NOT running There is no indication of an "AU RECW pump trip; therefore, the "N' RECW pump should be running. The answer is also incorrect because when RECW heat exchanger outlet pressure is < 118.6 psig, the standby RECW pump auto starts if its control switch is in AUTO without the presence of a lOCA signal; RECW be __ EXAM BANK COMPUTER TEST Page: 121 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 45 Info Question Type: Multiple Status: Always select on test? *Authorized for No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 I System 10: User-Defined 10: Cross Reference Number: I BPic: RO QUESTION 18 Num Field 1: 3.0 .... , ? Num Field 2: 3.0 f\ , / r. \. i = Text Field: 40000 A3.01 '-4' I \ A 1Irv---Comments: _1.-\ V'1 General Data Technical Reference with ARC 118 SERVICES, H-Revision Number: 3, REAC ENCL COOLING WATER HTX OUT LO PRESS. P&ID 8031-M-13, Rev41 Bechtel Electrical drawing E-565, Rev 10 ! Cognitive Level L : PRA: (I.e. Yes or No or #) NO 10CFFfS5.43 (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 I distractor "b" to make I plausible based on OTPS . review) I ILT Supplied Ref (If NONE c-"!Q2ropriate): (I.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A reguired}: EXAM BANK COMPUTER TEST Page: 122 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8826 Points: 1.00 The following occured on Unit 2: Reactor level dropped to -150 inches All Low pressure ECCS pumps started Both divisions of ADS actuated automatically All ADS SRVs opened Current Unit 2 conditions are as follows: Reactor pressure is 250 psig and lowering Drywell pressure is 15 psig and rising Reactor level has recovered to +20" and is steady ADS Reset Push buttons 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. ADS SRVs will close initially but will re-open after 105 seconds: I DISTRACTOR 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 inches for 105 seconds. ADS SRVs will remain open: With Reactor Level restored 129" and ADS logic reset, the ADS will close. EXAM BANK COMPUTER TEST Page: 123 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 46 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiple Choice Active 1\10 No 1.00 3 3.00 8826 8826 LGSOPS0050.IL7B RO QUESTION 19 4.2 4.2 218000 A4.03 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: (i.e. Yes or No or #) NO 10CFR 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, 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): (i.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 124 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 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 "1 A" and "1 C" RFPs are tripped HS-006-149B, "1 B" RFPT Speed Cont Switch (MSC), has the following indications "MSC SELECT" light is illuminated "MIA SELECT" light is extinguished T=O 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 runback. RRCS FW runback will override all MIA permissives and place the RFP in MIA control'during a runback. At the completion of the runback, 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 run back. See above discussion. (Partial correc T=30 for MIA Select) EXAM BANK COMPUTER TEST Page: 125 of 20 August 2010 --EXAMINATION ANSWER KEY ILT09-1 RO questions in sample plan order MSC SELECT; MIA SELECT: Incorrect due to identifying Feedpump control transfer to MIA and back to minimum speed during the run back signal return to pre-runback modeof MSC select after completion of the feedback ..!Question 47 Info !Question Multiple Status: select on test? . Authorized for practice? No I Points: i Time to CompJete: 3 I IQ_:_. " :User-Defined 10: Reference I _.---: Topic: I RO QUESTION Num Field 1: ;-:-;--.. +Num Field 2: 3.6 ) Text Field: 259002 A4.03 .F T1.L1I1 ( i General ffY It-r f)/Ul-1V (Technical Reference with (Iii' Revision Number: r-----". Cognitive Level H PRA: (I.e. Yes or No or #) NO 1 OCFR 55.43 (NfA for RO) 55.41 (b) 7 r-.----.-. . Question History: (I.e. LGS . BANK 367916 -l " Question Source: (I.e. New, I BANK . Bank, Modified} Revision History: Revision NONE History: (I.e. Modified distractor "b" to make plausible based on OTPS review) ILT ---" " Supplied Ref (If NONE appropriate): (i.e. ABN-##) i Excluded

Reference:

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

-3 Low KA Justification (if N/A " " I I EXAM BANK COMPUTER TEST Page: 126 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8828 Points: 1.00 Unit 1 plant conditions are as follows: OPCON 5 Core Shuffle Part II in progress Both the "1 A" and "1 B" RPS/UPS inverters are in service Maintenance has requested to remove the "1 A" RPS/UPS Inverter Power Monitoring System from service to replace a degrading component. WHICH ONE of the following describes the action to be taken, if any and the reason for the action? An LCO should not be entered, entry is only required when in OPCONs 1,2 and 3 An LCO should be entered due to the removal of the inverter power monitoring system An LCO entry is only required when both inverter power monitoring systems are removed from service An LCO entry is not required since an alternate power supply is available Answer: B Answer Explanation: An LCO should be entered due to the removal of the inverter power monitoring system: Correct because Tech Spec 3.8.4.3 requires two RPS electric power monitoring channels for each in-service RPS inverter or alternate power supply shall be operable. Removing the

• power monitoring channel for the "1 An RPS inverter would require entry into the tech spec action.

An LCO should not be entered, entry is only required when in OPCONs 1,2 and 3: Incorrect because the Tech Spec applies to all OPCONs and is applicable at all times. An LCO entry is only required when both inverter power monitoring systems are removed from service: Incorrect because the Tech Spec applies to each inverter. The minimum criteria for the LCO is one inverter power monitoring system removed from service. EXAM BANK COMPUTER TEST Page: 127 of 20 August 2010 i EXAMINATION ANSWER ILT09-1 RO questions in sample plan order An LCO entry is not required since an alternate supply is available: Incorrect because the LCO is dependant on an alternate source being available. monitoring channel must be operable even if the source is in J Question 48 Info Question Type: Multiple Choice i Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System 10: User-Defined 10: Cross Reference Number: LGSOPS0071.IL 13 RO QUESTION 21 *Num Field 1: 4.0 f Num Field 2: 4.7 1'\ I , 1\ 1 f/l,,(jA. Text Field: 262002 2.2.22 I} II? q' n;Comments: General Data .....\lX; Technical Reference with \, Revision Number: Cognitive Level L 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-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) 

• 1 Low KA Justification (if N/A ! I required):

I EXAM BANK COMPUTER TEST Page: 128 of 20 August 2010 49 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: fffvQ.AJ Points: 1.00 WHICH ONE of the following describes the RPS/UPS static inverter power supplies? Div 1_250 YDC TSC UPS via 114D-C-F MCC 114A:G-F A. Normal Supply Secondary Alternate Primary Alternate B. Primary Alternate Secondary Alternate Normal Supply C. Normal Supply Primary Alternate Secondary Alternate D. Primary Alternate Normal Supply Secondary Alternate Answer: C Answer Explanation: ANSWER Normal Supply, Primary Alternate, Secondary Alternate: The DC supply is the normal preferred source. The primary alternate supplies are from the TSC UPS Inverter via MCC 144D-C-F, and the secondary alternate supply is from 480 VAC MCC114A-G-F for the 1A Inverter. OISTRACTOR Normal Supply, Secondary Alternate, Primary Alternate: The DC supply is the normal preferred source. The question is incorrect because the primary alternate supplies are from the TSC UPS Inverter via MCC 144D-C-F, and the secondary alternate supply is from 480 VAC MCC114A-G-F for the 1 A Inverter. OISTRACTOR Primary Alternate, Secondary Alternate, Normal Supply: The DC supply is the normal preferred source. The primary alternate supplies are from the TSC UPS Inverter via MCC 144D-C-F, and the secondary alternate supply is from 480 VAC MCC114A-G-F for the 1A Inverter. OISTRACTOR Primary Alternate, Normal Supply, Secondary Alternate: The secondary alternate supply is from 480 VAC MCC114A-G-F for the 1A Inverter. The DC supply is the normal preferred source, and the. The question is also incorrect because the primary alternate supplies are from the TSC UPS Inverter via MCC EXAM BANK COMPUTER TEST Page: 129 of 195 20 August 2010 EXAMINATION ANSWER I L T09-1 RO questions in sample plan order Question 49 Info .9tlesticm _______ ________________________________

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1 Status:

_ ___________________________/ Points: -------------_._ .. Time to Complete: _____S-stem 10: _______-Technical Reference Revision ------------------

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/

___________j'---L:c--------_-_---------------_j PRA: Le. Yes..2'".!'le>. or #L RQL Question History: (i.e. OYS Question Source: (Le. BanJ<.. Revision History: Revision History: (Le. distractor "b" to plausible based on review) ____________ILT \Excluded

Reference:

(Le. NONE Low KA Justification (if

____________ L _____________________ ____' -EXAM BANK COMPUTER TEST-------- Page: 130 of 195 20Augusl2010 EXAMINATION ANSWER IL T09-1 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, with D21 supplying both D21 and D11Safeguard D21 EDG is currently operating at 950KW The CRS directs "1 A" RHR be placed in Suppression Pool Cooling E-10/20, Alternate Power Supply for any 4KV Safeguard Bus Using any Diesel Generator BUS LOAD RATED KW LOAD CENTERS RATED KW --RHR Pump -D114 525 Core Spray Pump 450 -D124 425 MCR Chiller 400 -D134 650 ESW Pump 375 -D144 800 I-RHR SW Pump -D214 350 CRD Pump -D224 325 -D234 800 -D244 ,c( 7 00 , L ..WHICH ONE of the following descnbes the ability to place " 1A" RHR In Suppression Pool Cooling while maintaining Diesel Generator load per E-1 0/20? "1A" RHR can NOT be placed in Suppression Pool Cooling "1 A" RHR CAN be placed in Suppression Pool Cooling and for an indefinite period "1A" RHR CAN be placed in Suppression Pool Cooling ONLY AFTER reducing Diesel Generator Load by an additional 300KW "1A" RHR CAN be placed in Suppression Pool Cooling but operation is limited to 2 hours in any 24 hour period Answer: B Answer Explanation: 1A loop of RHR CAN be placed in suppression pool cooling: Action is required to reduce load on the D21 EDG if total KW exceeds 2850 continuously or if load exceeds 3135 KW for 2 hours in 24 hours. The total load on the D21 Emergency Diesel Generator is < 2850; therefore the 1A loop of RHR CAN be placed in suppression pool cooling IMMEDIATELY and for an indefinite period. EXAM BANK COMPUTER TEST Page: 131 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 1A loop of RHR CAN NOT be placed in suppression pool cooling: The answer is incorrect because the total load on the D21 Emergency Diesel Generator is < 2850; therefore the 1 A loop of RHR CAN be placed in suppression pool cooling. "1A" RHR CAN be placed in Suppression Pool Cooling ONLY reducing Diesel Generator Load by an additional While DG load is required to be maintained with the ratings prescribed in E-10/20 the current DG load of 950 KW is suficient to meet the requirements for placing suppresion pool cooling in service. ! 1A loop of RHR CAN be placed in suppression pool IMMEDIATELY if operation is limited to 2 hours in any 24 hour IF total load exceeds 3135 KW then EDG operation is limited to 2 hours in a 24 hour period. The answer is incorrect because the total load on the D21 Emergency Diesel Generator is < 2850. Question 50 Info Question Type: Multiple Choice Status: Active Always select on test? No i Authorized for practice? No : Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 8830 User-Defined ID: 8830 Cross Reference Number: LGSOPS0092A.3A , LGSOPS0092B.1 0 Topic: RO QUESTION 23 Num Field 1: 3.9 Num Field 2: 4.3 Text Field: 262001 A2.03 Comments: General Data Technical Reference with E-10/20, Attachment 3, Revision Number: Rev 44 E-l 2, sh 1, Rev 14 E-13, sh1, Rev 14 Cognitive Level H PRA: (i.e. Yes or No or #) NO 10CFR 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 OTPS review) ILT Supplied Ref (If appropriate): (Le. ABN-##) II EXAM BANK COMPUTER TEST Page: 132 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Excluded

Reference:

(Le. NONE Ensure Low KA Justification (if N/A i required): 

.--.--. EXAM BANK COMPUTER-TEST Page: 133 of 195 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% "A" 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 line break inside the vessel but outside the shroud? U;opg 1A and 1 B Core Spray internal line break detection are BOTH masked. #.... 1A and 1 B Core Spray internal line break detection are BOTH functional. P 1A Core Spray internal line break detection is masked. 1 B break is functional. f A. _'#j/.¢( 1 B Core Spray internal line break detection is masked. 1 Wreak detection is functional. '" Answer: A Answer Explanation: 1A and 1 B Core Spray internal line break detection are BOTH masked: 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 Core Spray sparger; therefore, when SLC inadvertently initiates, pressure in the B Core Spray header would be higher than pressure in the A Core header, resulting in the Core Spray line internal line break alarm, masking an actual failure of Core Spray for either Core Spray system. 1A and 1 B Core Spray internal line break detection are BOTH functional: 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 internal line break detection is masked. 1B break detection is functional: 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 SpraJ' s},stem. -... 1B Core Spray internal line break detection is masked. 1A break detection is functional: 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 $Q@}' system. EXAM BANK COMPUTER TEST Page: 134 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 51 Info Question Type: Multiple Choice *Active Always select on test? No Authorized for practice? No Points: 1.00 j i i Time to Complete: 3 i 3.00 i i System ID: 18831 User-Defined ID: .8831 Cross Reference Number: Topic: RO QUESTION Num Field 1: 3.0 I Num Field 2: 3.2 1. I 11 /)) Ii Text Field: 211000 K3.02 c,t"':J..f ./ a HIP 'J" r" , Comments: 0 /loA r//'1 C General Data -:;::::::: Technical Reference with ARC 113 COOL A, Revision Number: 8031-M-48, Rev 8031-M-52, Rev Cognitive Level L PRA: (Le. 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: (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): (i.e. ABN-##) I Excluded

Reference:

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

Low KA Justification (if N/A required): I EXAM BANK COMPUTER TEST Page: 135 of 20 August 2010 EXAMINATION ANSWER IL T09-1 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 The "B" Reactor Enclosure Vent Exhaust Duct Radiation Monitor fails downscale.

WHICH ONE of the following describes the status of Reactor Enclosure HVAC (RE HVAC) and Standby Gas treatment RE HVAC A. Operating Initiated B. Isolated Initiated C. Operating Standby D. Isolated Standby Answer: C Answer Explanation: Operating; Standby: Correct because REHVAC will not isolate on a single channel failure, and SGTS will not initiate on a single channel failure . .. OISTRACTOR Operating; Initiated: Incorrect due to same as above OISTRACTOR Isolated; Initiated: Incorrect due to same as above OISTRACTOR Isolated; Standby: Incorrect due to same as above EXAM BANK COMPUTER TEST Page: 136 of 20 August 2010

---

I EXAMINATION ANSWER KEY IL T09-1 RO questions in sample plan order 1 Question 52 Info c* . Question T:tee: Multiple Choice Status: Active on test? No I for:.e!:9ctice?

No @LPolnts. . 1.00 .. [Time to Complete: 3 I i 3.00 System ID 8832 User-Defined ID: 8832 I Cross Reference Number:--LGSOPS0048.IL4 RO QUESTION 25 ._. Num Field 1: Num Field 2: 3.1 ,.. fl " r Text Field: 261000 K1.08 UO/f.Jr AtWI,41,t.1, Comments: t>. 1) n\ " .4a General Data rw' Technical Reference with I M-1-B21-1090-E-023, Revision Number: sh1, Rev 42 I L.9ognitive Level L £RA: {Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) --auestion History: (Le. LGS BANK,560361 NRC-05, OYS CERT-04) . Question Source: (Le. New, BANK,560361 Bank, Modifiedt Revision History: Revision Bank, 560361. Changed History: (Le. Modified the order of the distractor "b" to make distractors. Changed plaUSIble based on OTPS correct answer from review) : C. -----ILT Supplied Ref (If NONE -J appropriate): {Le. ABN-##l Excluded

Reference:

(Le. NONE Ensure ON-## not provided) I Low KA Justification (if N/A I I I , EXAM BANK COMPUTER TEST Page: 137 of 195 20 August 2010 53 EXAMINATIO*N ANSWER ILT09-1 RO questions in sample plan order 10: 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 RBM readings A. Unchanged B. Lower Than Actual Unchanged C. Lower Than Actual D. Lower Than Actual Lower Than Actual Answer: D Answer Explanation: lower than actual; lower than actual: Correct 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 RBM channels will automatically remove any LPRM detector input signal from its local average neutron flux calculation I 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. higher than actual; lower than actual: Incorrect due to APRM indication actually lowering. (Partial correct for RBM reading lower than actual) higher than actual; higher than actual: Incorrect due to both APRM and RBM indication actually lowering as discussed above. lower than actual; higher than actual: Incorrect due to RBM indication actually lowering due to a lower average of inputs. (Partial correct for APRM reading lower than actual)

• EXAM BANK COMPUTER TEST Page: 138 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order I 53 Info Question Type: Multiple Choice I Status: Active . Always select on test? No [Authorized for practice?

No i Points: 1.00 Time to Complete: Difficulty: System ID: User-Defined ID: Cross Reference Number: LGSOPS007 4A.IL 7 ... Topic: RO QUESTION 26 Num Field 1: 2.9 Num Field 2: 3.1 nl i II /I Text Field: 215005 K5.04 I(.;V-' tl Comments: LfflA1 (At.JFmJ -:fill ;1;General Data ( Technical Reference with LPRM -UFSAR 81 1 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 Cognitive Level L PRA: (i.e. Yes or No or #) NO 10CFR 55:43 (N/A for RO) 55.41 (b) 5

• Question History: (i.e. BANK, 556253 NRC-05, OYS CERT-04) Question Source: (I.e. New, BANK, 556253 Bank, Modified)

Revision History: Revision Bank,556253.Changed History: {I.e. Modified the order of the (* distractor "b" to distractors. Changed plausible based on OTPS correct answer from A ,to (review) C. ILT ! Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

Reference:

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

I EXAM BANK COMPUTER TEST Page: 139 of 20 August 2010 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. If the 10callPRM 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 Qrima!}, reference APRM for RBM channel A. EXAM BANK COMPUTER TEST Page: 140 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 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 1000;.,: 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 Info f---c_--'-'- ____-I-"3_.1 215002-'51:02 Comments: __--I-Gene al 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 --.--.-.--------- Cognitive ______L__________________l PRA: (Le. N_O____________ 10CFR 55.43 (N/A for RO) 55.41 b __Question History: (Le. LGS Bank,555427 t-J_F3f-05, Question Source: (Le. New, Bank, Modified 555427 _______ Revision History: Revision Bank,556253.Changed History: (Le. Modified the order of the distractor "b" to make distractors. Changed plausible based on OTPS correct answer from D to review) A. Modified stem and distractors extensively to improve clarity and discrimination. ______________ ILT_____________ _ NONE EXAM BANK COMPUTER TEST Page: 141 of 195 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Excluded

Reference:

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

Low KA Justification (if N/A I reguired}: EXAM BANK COMPUTER TEST Page: 142 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8835 Points: 1.00 Unit 1 plant conditions are as follows:

• 100% reactor power
• Normal electrical lineup RPS UPS panel 1BY160 is inadvertently de-energized as a result of an under frequency condition.

WHICH ONE of the following identifies the status of the RPS solenoid valves? A. 'A' and 'B' RPS solenoid valves are energized. B. 'A' and 'B' RPS solenoid valves are de-energized. C. 'A' RPS solenoid valves energized. 'B' RPS solenoid valves de-energized. D. 'A' RPS solenoid valves de-energized. 'B' RPS solenoid valves energized. Answer: C Answer Explanation: 'B' RPS solenoid valves de-energized. 'A' RPS solenoid valves energized: RPS UPS panel1BY160 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. Because RPS UPS panel 1AY160 powers the 'A' scram solenoids and RPS logic, the 'A' and 'B' RPS solenoid valves also remain energized. 'A' and 'B' RPS solenoid valves are energized: If the failure had been to the 1 A RPS UPS inverter, RPS UPS panel 1 BYi60 would have remained energized by its primary alternate power supply. Because RPS UPS panel1AYi60 powers the 'A' scram solenoids and RPS logic, the 'A' and 'B' RPS solenoid valves would also remain energized. The answer is incorrect because 1BY160 is de-energized, de-energizing the 'B" RPS scram solenoids. 'A' and 'B' RPS solenoid valves are de-energized: When 1BYi60 is de-energized, the 'B" RPS scram solenoids are de-energized; however, RPS UPS panel1AY160 powers the 'A' scram solenoids and RPS logic; therefore, the 'A" RPS solenoids remain energized, making the answer incorrect. 'B' RPS solenoid valves energized. 'A' RPS solenoid valves de-energized: When 1BY160 is de-energized, the 'B" RPS scram solenoids are de-energized. The answer is also incorrect because RPS UPS panel1AY160 powers the 'A' scram solenoids and RPS logic, which remain energized. EXAM BANK COMPUTER TEST Page: 143 of 20 August 2010 EXAMINATION ANSWER Il T09-1 RO questions in sample plan order Question 55 Info i Question Type: Status: Always select on test? i Autborized for practice? Points: Time to Complete: Difficulty:

• System 10: *User-Defined 10: Cross Reference Number: Num Field Num Field Text

!\.1ultiQle 3.00 I RO QUESTION 28, I \ o ,..... /7 \ / 201001 K2.02 (-t?z,rL t Lo.M."AI hlt\A v III OAf' I.. " General i Technical Reference with E-1BY160, Rev. Revision Number: E-32, Sh 1, Rev Cognitive Level PRA: (I.e. Yes or No or #) 10CFR 55.43 (N/A for RO) 55.41 Question History: (I.e. LGS . NRC-05, OYS I n Source: (I.e. New, Bank, I Revision History: Revision

• History: (I.e. , distractor "b" to I plausible based on review) Supplied Ref (If appropriate): (I.e. Excluded

Reference:

(I.e. ... Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 144 of 195 20 August 2010 I EXAMINATION ANSWER IL T09-1 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 impact on Personnel Safety? Fire Protection Impact on System MalfYDction Personnel Failed Sr,:uinkler I::le.ad, Water spraying on energized Aux Boiler Enclosure electrical equipment Wetpipe System FCliled SmQ!5.e Detector, C02 will displace Oxygen Cable Spreading Room Cardox System Failed Heat Detector, Water spraying on energized 012 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 Smoke Detector, Cable Spreading Room Card ox System; C02 will displace Oxygen: Incorrect due to failed smoke detection not actuating Cardox. (Partial correct for C02 displace Oxygen) Failed Heat Detector, 012 Diesel Generator Pre-action Sprinkler; Water spraying on energized electrical equipment: Incorrect due to failed heat detector only actuating the pre-action system. An additional failure of a sprinkler head would be required for initiating flow. EXAM BANK COMPUTER TEST Page: 145 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Failed Heat Detector, Remote Shutdown Panel System; Halon will displace Oxygen: Incorrect due to single failed heat detector will not intiate suppression. (Partial correct for Halon will Question 56 Info ! Ouest ion Type: i Multiple Choice Always select on test? No Authorized for No Points: lime to Com[)lete: 3 3.00 10: 8768 User-Defined 10: 8768 Cross Reference Number: LGSOPS022.05 Topic: Fire system Num Field 1: Num Field 2: /1 of I 0' Text Field: 286000, K3.02 .;'";z4-i1[ , .. . Comments: L' 7 r I. General Data l1 Technical Reference with M-22 r-Revision Number: S22.1.B S22.1.C CO..9.nitive Level L PRA: (I.e. Yes or No or #) N 10CFR 55.43 (N/A for RO) RO 55.41 (bT7 Question History: (I.e. LGS NEW t'JRC-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) ILT Supplied Ref (If NONE {I.e. ABN-##} GExcluded

Reference:

(I.e. NONE Ensure ON-## not erovided}

i Low KA Justification (if l\ltA ..EXAM BANK COMPUTER TEST Page: 146 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8836 Points: 1.00 Unit 1 plant conditions are as follows: -8GO-206-1 (Unit 1 RE) is -8GO-506-2 (Unit 2 RE) is -8GO-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 mrfhr 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 mr/hr 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 8GOs 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 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. OISTRACTOR Unit 2 Reactor Enclosure Vent Exhaust Rad level at 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. EXAM BANK COMPUTER TEST Page: 147 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 57 Info Question Always select on . Authorized for practice? Points: Time to Complete: Difficulty: System User-Defined -c*** Cross Reference Number: *Topic: Num Field 1: Num Field 2: Text Field: Comments: Multiple Choice Active i No

• No 1.00 3 i 3.00 8836 8836 LGSOPS0078.IL3 RO QUESTION 30 3.7 / 3.8 /11 ./' J l D I , 288000 K4.02 \,' fiJI tvJ if j7JY'1 Iv"""'-, oj, () -:di t General Data 'i (,...N r1 II f-...:: 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 OTPS I review) . ILT Supplied Ref (If appropriate): (I.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if required): sh1, Rev 42 I P&IDM-76 L Ct NO 55.41 (b) 7 BANK Bank,557532 Changed sequence of distractors. Changed answer from A to B . NONE NONE N/A EXAM BANK COMPUTER TEST Page: 148 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 58 10: 8837 Points: 1.00 Unit 1 plant conditions are as follows: Reactor power is Pressure at the Pressure Averaging Manifold (PAM) is 990 EHC Load Set is Max Combined Flow is Load Limit is The Load Limit potentiometer is reduced to 94% SWorn ih_1e ___I .. Oil.' WHICH ONE of the following describes the status of the Control Valves and Turbine Inlet (PAM) Pressure? A. 85% steam flow 990 pSig B. 94% steam flow 990 psig C. 85% steam flow 885 psig EXAMINATION ANSWER ILT09-1 RO questions in sample plan order D. 94% steam flow 885 psig Answer: B Answer Explanation: 94% steam flow, 990 psig, 94% of rated load: Reducing Load Limit potentiometer by 6% closes control valves 6%, reducing turbine load proportionally. With reactor power constant, the bypass valves open by the same amount to maintain pressure at the Pressure Averaging manifold (PAM). The PAM is located upstream of the control valves and bypass valves; therefore, pressure will remain unchanged as the bypass valves open to compensate for control valve closure. 85% steam flow, 990 psig, 85% of rated load: Steam flow is reduced and pressure at the PAM is unchanged; however, the answer is incorrect because reducing Load Limit potentiometer by 6% closes control valves 6%, reducing turbine load proportionally. 85% steam flow, 885 psig, 85% of rated load: If reactor power had been reduced by 15%, the reduction in steam flow would have resulted in a PAM pressure reduction of 1 psig for every 3% reduction in steam flow as the control valves closed; however, with reactor power constant, if the control valves are closed by the Load Lim it potentiometer, the bypass valves will open by the same amount, maintaining pressure constant at the Pressure Averaging manifold (PAM). The answer is also incorrect because reducing the Load Limit potentiometer by 6% closes control valves 6%, reducing turbine load proportionally. 94% steam flow, 888 psig, 94% of rated load: Reducing Load Limit potentiometer by 6% closes control valves 6%, redUCing turbine load proportionally; additionally, if reactor power had been reduced by 6%, the reduction in steam flow would have resulted in a PAM pressure reduction of 1 psig for every 3% reduction in steam flow. The answer is incorrect because reactor power is constant and the control valves were closed by the Load Limit potentiometer; therefore, the bypass would valves will open to maintain pressure constant at the Pressure Averaging manifold (PAM). EXAM BANK COMPUTER TEST Page: 150 of 20 August 2010 _________ _ EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 58 Info Question Type: Status: Num Field Text Field: Comments: Revision P&ID 8031-M-1, sh1. Rev 56 _________-,-:---+__ _PRA: (i.e.

1. ) __________ __> Question History: (Le. Bank, Modified CERT-04)Question Source: (Le. New, Bank, LIMERICK LOT

_______ 2277 Revision History: Revision Modified stem and History: (Le. Modified distractor to align distractor "b" to make question more directly plausible based on OTPS with KIA. Changed review) sequence of distractors. Changed answer from A to B. ILT EXAM BANK COMPUTER Page: 151 of 195 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 Drywell temperature is "iA" Loop of RHR is in Suppression Pool "1 B" Loop of RHR is in Drywell "1 An and "1 B" Loop of RHRSW is in service Suppression Pool temperature is 105°F and dropping slowly Drywell pressure 14.6 psig and dropping quickly The "B" RHRSW Radiation monitor fails, resulting in an INOP trip. WHICH ONE of the following describes the impact on Suppression Pool temperature and Drywell pressure? fuillpression Pool Temperature Drywell Pressure A. Continues Continues dropping oJ-(i, /'>A B. Continues Will stabilize or rise . .J--" stlv 1\,:.C. Will stabilize or Continues dropping CI'1, D, Will stabilize or Will stabilize or rise Answer: A Answer Explanation: Continues droppingl Continues dropping: A trip of the 1 B RHRSW process radiation monitor trips the "B" RHRSW pumps, resulting in a loss of "B" RHRSW ONLY. The "A" loop of RHR is unaffected. The effectiveness of drywell spray is ! maintained due to the significance impact of evaporative cooling, OISTRACTOR Continues droppingl Will stablize or rise: A trip of the 'I B RHRSW process radiation monitor results in a loss of "B"

• RHRSW ONLY. RHRSW is lost to the "B" RHR loop; however, the effectiveness of drywell spray is maintained due to the evaporative cooling.

Will stablize or rise, Continues dropping: If the "AU RHRSW pumps had tripped, suppression pool cooling would be negatively impacted by the loss of RHRSW; however, a trip of the 1 B RHRSW process radiation monitor results in a loss of "B" RHRSW ONLY, and the "AU loop of RHR is unaffected. RHRSW is lost to the "B" RHR loop; however, the effectiveness of drywell spray is maintained due to the significance impact of evaporative coofing. EXAM BANK COMPUTER TEST Page: 152 of 20 August 2010

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EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Will stablize or rise, Continues dropping: A trip of the RHRSW process radiation monitor results in a loss of RHRSW ONLY, and the "An loop of RHR is RHRSW is lost to the "8" RHR loop; however, effectiveness of drywell spray is maintained due to '---______-'----s..,.i L.n_ifi_c_an_c_e impact of eV§.florative cooling. [Question

---

==1 Question Type: Multiple Choice -----------------i Status: Active 1 r------------.----

Always select on test? __+--I'J_O___________________ __ . AuJ-,!orized for practice? No --------------, I I Num Field 2: 2 8 l /'Text Field: /' Co-m-m-e-nt-s-: l Co nitive PRA: (Le.ves-o-r10CFR 55.43 (N/A for Question History: (Le. LGS Bank, OYS CERT-04 )'------+ ______Question Source: (i.e. New, Bank, LIMERICK Bank, Modified) ___ ___Revision History: Revision Modified stem History: (Le. Modified distractors significantly distractor "b" to make align question with plausible based on OTPS Changed sequence review) distractors. wording of answer and distractors to add clarity. Changed answer from B to A. ILT NONE =-r:"':"':=-=-==.i.--f--- ___________-j N/A EXAM BANK COMPUTER TEST Page: 153 of 20 August 2010 EXAMINATION ANSWER KEY IL T09-1 RO questions in sample plan order 10: 8840 Points: 1.00 Unit 2 plant conditions are as follows: GP-2, STARTUP is in progress A control rod at position 24 will NOT move per S73.1.A. Normal Operation of the Reactor Manual Control System (RMCS). No rod blocks exist RMCS is functioning normally . no c movement is attem . cordance with ON-104 PROBLEMS. WHICH ONE of the following indications can be used to CONFIRM the control rod is A. No change in nuclear instrumentation f'0 () "ILt,JL B. Elevated CRD drive water I C. ROD OVERTRA VEL alarm D. 4 gpm CRD drive water insert fr y{.r-,) Answer: OfJ Answer Explanation: No change in nuclear instrumentation: Stuck control rod may be ANSWER indicated by loss of expected nuclear instrumentation response during rod movement. Low CRO drive water pressure: Insufficient pressure might indicate a clogged CRD drive filter or a failed CRD flow control valve; however. it is not a direct indication that a control rod is stuck. ROD OVERTRAVEL alarm: Overtravel is an indication of an uncoupled control rod. 4 gpm CRD drive water insert flow: 4 gpm is the normal value for the insert of CRDs it does not direct indicate that a control rod is stuck. EXAM BANK COMPUTER TEST Page: 155 of 20 August 2010 EXAMINATION ANSWER I L T09-1 RO questions in sample plan order Question 60 Info Question Type: Status: i Alwavs select on test? ! Auth()rized for practice? Points: Time to COf"r'lplete: I Difficulty: System User-Defined Cross Reference Num Field Field Comments: Multiple 1.00 3 3.00 18840 8840 LGSOPS0047.IL7 CR,p on

3.7 201003

A General Data

• Technical Reference ON-l04 BASES, Revision Number: gognitive Level PRA: (I.e. Yes or No or #) 10CFR 55.43 (N/A for RO) 55.41 . Question History: (I.e. LGS NRC-05, OYS Question Source: (i.e. New, (3ank, Modified)

Revision History: Revision Bank, Modified two History: (i.e. Modified distractors to improve the distractor "b" to make discriminating value of the plausible based on OTPS question: Changed high review) CRD drive water flow to low flow, and changed low CRD pressure to high CRD pressure. Changed sequence of distractors. Changed answer from D to A. i Supplied Ref (If (I.e. Excluded

Reference:

(I.e. Ensure ON-## not

_ Low KA Justification (if N/A EXAM BANK COMPUTER TEST Page: 156 of 20 August 2010 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 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. ON!;.pf the following describes .the expected.plant response anQ.:tRe operator let...... Ph" t f. , A. A rise in Offgas System temperatures ONLY: ' '..er Enter ON-103, CONTROL OF SUSTAINED COMBUSTION IN THE I 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 STEAM HIGH RADIATION. A rise in Reactor Water Conductivity Enter ON-116, HIGH REACTOR WATER 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 & consequesntly SJAE radiation monitor levels is the transition from oxidizing to reducing conditions in the reactor which cause a temporary reverse in the transport of N13, 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 2!L ______ ...__________ . 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 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. -E-XA-MBANK Page: 157 of 195 --EXAMINATION ANSWER ILT09-1 RO questions in sample plan order r DISTRACTOR 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. . f 611 no ueslon f Question Tx:ee: Milltinip. Status: .. select on test? Authorized for Qractice? Points: 1.00 Time to Com[llete: 3 Difficulty: 3.00 -c::: §I_stem ID: 8841 User-Defined fD: 8841 -.Cross Reference Number: . LGSQE..S1550.IL 1 Topic: RO QUESTION 34 Num Field 1: 2.6 I Num Field 2: 2.8 . -f..di' I Text ?J200 0A2.JJL... '" --u(;t.v4':;;;;r . ,.. y r-.--.. . 4:, J ,4' (J A "n" ;;'1 .J tli i .... -v IV '-to --=--. .---. Technical Reference with ON-102 BASES, Rev. Revision Number: 29 '<;:ognitive Level __.... H PRA: (Le. Yes or No or #) NO_ 55.43 (NfA for RO) 55.41 (b)5 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-##) Excluded

Reference:

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

Low KA Justification (if 1\l/A required): I EXAM BANK COMPUTER TEST Page: 158 of 20 August 2010 I 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 7.5 psig and rising RPV pressure is 475 psig and RPV level lowered to a minimum of -65 inches, recovering to current level of +35 "1A" RHR is in suppression pool spray per Pressure upstream of HV-51-1 F017A is 285 Reactor pressure continues to lower steadily. WHICH ONE of the following describes the response of the RHR Full Flow Test Return Valve (HV-51-1 F024A) and RHR suppression pool spray valve (HV-51-1 F027A)? HV-51-1 HV-51-1F027A A. Closes at 359 psig Closes at 359 pSig B. Remains open Closes at 455 psig C. Closes at 455 psig Remains open D. Closes at 455 psig Closes at 455 pSig Answer: D Answer Explanation: Closes at 455 psig; Closes at 455 psig: Correct because LPCI Initiation signal is 2! 1.68 psig drywell pressure and S 455 psig reactor pressure. HV-51-1 F024A will auto close in response to a LPCI initiation signal. 51-1 F024A will auto close in response to a LPCI initiation signal. HV-51-1F017A will auto open in response to a LPCI initiation signal .fmd the differential pressure across the valve is < 78 psid. Closes at 359 psig; Closes at 359 psig: Incorrect due to LPC! Initiation signal is 2! 1.68 psig drywell pressure and S 455 psig reactor pressure. HV-51-1 F024A will auto close in response to a LPCI initiation signal. HV-51-1 F024A will auto close in response to a LPCI initiation signal. 1 F017 A will auto open in response to a LPCI initiation signal find the differential pressure across the valve is < 78 psid. 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Remains open; Closes at 455 psig: Incorrect due to LPGI Initiation signal is <:: 1.68 psig drywell pressure and ::; 455 psig reactor pressure. HV-51-1 F024A will auto close in response to a LPGI initiation signal. HV-51-1F024Awill auto close in response to a LPGI initiation signal. 1F017A will auto open in response to a LPGI initiation signal and the differential pressure across the valve is < 78 psid. Closes at 455 psig, Remains open: Incorrect due to LPGI Initiation signal is <:: 1.68 psig drywell pressure and ::; 455 psig reactor pressure, HV-51-1F024Awill auto close in response to a LPGI initiation signal. HV-51-1F024Awill auto close in response to a LPGI initiation signal. 1 FOi7 A will auto open in response to a LPGI initiation signal and the differential pressure across the valve is < To ic: Num Field--1-:

---

I-'::-'-::......;;;;:..::..:=c..:...c

. __________N-u-m-F-ie-ld-2-: Text Field: Gomments: c=-==------=--- Technical Reference with 8031-M-1-E Revision Number: 005, sh1, Rev 25 8031-M-1-E 015, sh1, Rev 34 016, sh1, Rev 33 NO (b) ___ Question History: (Le. LGS BANK OYS _____._____ Question Source: (Le. New, BANK, 558262 Bank, Modified Page: 160 of 20 August 2010 EXAMINATION ANSWER IL T09-1 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 Excluded

Reference:

(Le. Ensure ON-## n0..!.l>rovided)

Low KA Justification (if required): BANK, MODIFIED 558262. Changed drywell pressure and reactor pressure in the question stem. Added 1 F024A to question stem and distractors. Modified distractors and answer to include conditions where HV-51-1 F024A and 51-1F027A do not respond to a LPCI signal and instead remain open. Changed answer from A to D. NONE NONE N/A Page: 161 of 195 20August2010 EXAM BANK COMPUTER TEST 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 S7B.B.A, MANUAL INITIATION OF CONTROL ROOM RADIATION OR CHLORINEITOXIC CHEMICAL ISOLATION. The "C" chlorine isolation channel failed to trip WHICH ONE of the following describes the status of the "A" and "B" CREFAS fans two (2) minutes later based on the above conditions? 'A' CREFAS FAN CREFAS FAN A. Not running B. Not Not running C. Running D. Not Running Answer: D Answer Explanation: Not running; Running: Correct because The 'A' CREFAS fan will receive a start Signal from only the C isolation channel. The 'C' channel failed to trip; therefore, the 'A' CREFAS fan did not start. The 'B' CREFAS fan will receive a start signal from only the D isolation channel. The 'D' channel did trip; therefore, the ,B' CREFAS fan did start. Running; Not running: Incorrect due to information above Not running; Not running: Incorrect due to information above Running; Running: Incorrect due to information above EXAM BANK COMPUTER TEST Page: 162 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 63 Info Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Num Field Text Multiele Choice Active No i No 1.00 3 3.00 J 8843 8843 I LGSOPS0078.1L4 RO QUESTION 36 3.2 3.2 __ n (/I tI /, u./j .1' 290003 ftC--Cv(t"LV/ !ft'I"'J ./111 Aat .L..!_ ..ILJ I"}t.I-tX' istj;General ......".../ Technical Reference with Bechtel Drawing, Revision Number: sh1, Rev 18 l Cognitive Level H

• PRA: (I.e. Yes or No or NO 10CFR 55.43 {N/A for RO} (b) 7 Question History: (i.e. LGS-BANK NRC-05, OYS CERT-04) I 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. I review) Supplied Ref (If appropriate): (i.e. Excluded

Reference:

(i.e. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 163 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order ID: 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 "1A" and "1C" FPC pumps running The following Annuciators are 212 Cleanup K-5, Fuel Pool Cooling Pumps Trouble 212 Cleanup 1-5, Fuel Storage Pool Hi/Low Level EO reports Both Fuel Pool Cooling 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? 01\1-125, 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 i not impact Secondary Containment. I EXAM BANK COMPUTER TEST Page: 164 of 20 August 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 I Question Type: Multiple Choice i Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 _.

• 3.00 System 10: User-Defined 10: Cross Reference Number:

Topic: Fuel Pool Cooling. Abnormal pr()cedure Num Field 1: Num Field 2: b n Text Field: 233000 2.4.4 . .J ['-{"tiJ f.rt11Comments: £At bL ('.-/I ,'. lJ\ 11 General Dena ...... --TV r fJ Technical Reference with ON-120, Revision Number: ON-125 Cognitive Level L PRA: (i.e. Yes or No or #) 1\10 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)

Revision History: Revision NEW History: (i.e. Modified distractor UbI> to make plausible based on OTPS review) ILT I Supplied Ref (If NONE {Le. ABN-##) Excluded

Reference:

(Le. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 165 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ID: 8845 Points: 1.00 Unit 1 plant conditions are as follows: Reactor power is 100% 127 OFF GAS 1! A-2, 1 Unit HEPA Filters Trouble alarms on high differential . 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 status of PCV-141A, RECIRC TO COND, and the expected impact on Main Condenser vacuum? PCV-141A Main Condenser vacuum A. Full Open Improving (More vacuum) 8. Full Closed Improving (More vacuum) C. Full Open Degrading (Less vacuum) D. Full Closed Degrading (Less vacuum) Answer: C Answer Explanation: Full Open, Degrading (Less vacuum): The scale on Recirculation to condenser PIC-07-141A is 0-100%. This corresponds to a pressure setting of 0 10 psig. The normal Setpoint for PIC-07-141A(8) is 7.0 psig. At 10 psig demand, PCV-141A would be full open. Indications are that the Off Gas HEPA filter is fouled and off gas flow has gone to zero; therefore, over time, non-condensable gasses will accumulate in the main condenser, and vacuum will degrade (lowering I vacuum). DISTRACTOR Full Open, Improvi,,9 (More vacuum): See Above DISTRACTOR Full Closed, Improving (More vacuum): See Above DISTRACTOR Full Closed, Degrading (Less vacuum): See Above EXAM BANK COMPUTER TEST Page: 166 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order I Question 65 I Question i select on I Authorized for practice?

I Points: Time to CoITlplete: I S:tstem [9ser-Oefined I Cross Reference *Topic: Num Field 1: , Num Field 2: Text Field: Comments: Multiple Choice I Active No No 1.00 3 3.00 8845 8845 LGSOPS0069.7A RO QUE:STIQN38 3.5 3.5 271000 K3.01 General Data I Technical Reference with Revision Number: I 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 I {i.e. ABN-##) . Excluded

Reference:

(i.e. I Ensure ON-## not provided)  KA Justification (if I l . P&IO M-69, sh 1, Rev 48 I P&IO M-70, sh 2, Rev 32 P&IO M-07, sh 1, Rev 47 H NO I 55.41 {b} 7 I Bank,561322 Bank,561322 Modified stem to indicate HEPA filter blockage sufficient to result in a loss of ability to evacuate non-condensable gasses from the main condenser, ultimately resulting in degrading condenser vacuum. Modified stem and distractors to require interpretation of 141A status as a result of riSing Off gas pressure.

Changed correct answer I from 0 to C. NONE NONE N/A EXAM BANK COMPUTER TEST Page: 167 of 195 20 August 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 Control Rod 30-31 is at position 30 and is being continuously withdrawn to position WHICH ONE of the following identifies the earliest indicated notch position at which the continuous withdrawal signal is REQUIRED TO BE REMOVED to ensure that the control rod stops at the target position? A. 44 B. 42 C. 40 D. 36 Answer: Answer 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: 169 of 20 August 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 LGSOPS0073A.IL4B RO QUESTION 66 4.6 1/4.6 n ..l 1"\ A /"\ .. 2.1.20 I J II 'i/ General Data Technical Reference with Revision Number: Cognitive 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) 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

Reference:

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

Low KA Justification (if required): S73.1.A, Rev 47 L NO 55.41 (b) 6 Bank Bank,55460 Bank,55460.Changed order of distractors. Changed correct answer from B to A. NONE NONE N/A EXAM BANK COMPUTER TEST Page: 170 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 10: 8853 Points: 1.00 Plant conditions are as follows: MCR has been Cooldown has commenced on both Unit 1 RPV pressure is 685 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 the MAXIMUM allowed (100 0 FI SE-1 3 100 'FfHr COOLDOWN RATE NOMINAL COOLDOV\IN RATE SLOPE OF COOLDOV\IN RATE CANNOT BE STEEPER T HANTYPIC,a.L LINE SHOV\IN. I<<10( T >10 °F.1'lr RPV COOLDO\i\tN RATEI M 40 0 P (OF) 1--1----I--I--30 0 SHUT DQV\.II'IJ COOLING } PERMISSIBLE 20o 1 3 TIME (hours) WHICH ONE of the following identifies the EARLIEST time Shutdown Cooling can be initiated? A. 2.5 hours from now B. 2.25 hours from now C. 2.0 hours from now D. 1.75 hours from now Answer: D EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Answer Explanation: ANSWER 1.75 hours from now: 685 psig corresponds to 700 psia. From steam tables, 700 psia is approxim ately 500°F. From Attachment 3, a line starting at 500°F with the sa me slope as the "Normal Cooldown Rate" would intersect the "Shutdow n Cooling Permissible" line at the 1.75 hour rnSTRACTOR point.

2.0 hours

from now: From Attachment 3, a line starting at 500°F intersecting the "Shutdown C ooling Permissible" line at the 2.0 hour point would have a les s steep than the "Normal Cooldown Rate." DISTRACTOR 2.25 hours from now: From Attachment 3, a line starting at 500°F intersecting the "Shutdown C ooling Permissible" line at the 2.25 hour _point would have a slope les s than "Normal Cooldown Rate." DISTRACTOR Attachment 3, a line starting at 500°F 2.5 hours from now; From intersecting the "Shutdown C ooling Permissible" line at the 2.5 hour point would have a slope mu ch less steep than the "Normal Cooldown Rate." Question 67 Multiple Status: on test? No for practice? No 1.00 I Time to Complete: 3 ! 3.00 10: 8853. I User-Defined 10: 8853 I Cross Reference Number: LGSOPS2000.lL4 I Topic: _. RO QUESTION 67 Num Field 1: I _ Num Field 2: 4.4 fJ n ( Text Field: 2.1.23 . . t t1vft.-l . Comments: Iff) I ( eneral Data f-=--:---Technical Reference with SE-1, Section 4.8, Rev Revision Number: 63, Attachment 3 rcognitive Level H PRA: (I.e. Yes or No or #} NO 55::t3 (N/A for RO) 55.41 (b) 10 , Question History: (I.e. LGS Bank, Modified NRC-05, OYS CERT -04) Question Source: (I.e. New, Bank, Modified, .*-Bank, Modified) LIMERICK LOT 0582 EAAM BANK COMPUTER TEST Page: 172 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 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 ABN-ft.itl. Excluded

Reference:

(i.e. Ensure ON-## !lot Low KA Justification (if . required)I Bank, LIMERICK LOT 0582. 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. , t Steam Tables NONE NtA EXAM BANK COMPUTER TEST Page: 1730f 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8855 Points: 1.00 Unit 1 plant conditions are as follows: Plant is in an unscheduled shutdown, OPCON Preparations are underway to conduct unscheduled, testing of the Unit 1 LOCAILOOP A Special Test Director, an NRC licensed operator, has been to coordinate test preparations and direct test activities, interfacing Operations Shift Management, Work Control, and other departments as Test preparations §nd performance are expected take five full days to WHICH ONE of the following can be used to obtain specific operations management expectations and guidance on the authorities and responsibilities of operations personnel for the duration of this non-routine operating condition? A. Standing Orders B. Pre-Job Briefs C. Shift Training Briefs D. On-shift Just-in-time training Answer: A Answer Explanation: r-::-:-:-::::--:::=-*-----**- .Standing Orders are longer-term, written directions from Operations Management to Shift Crews which include but are not limited to: Non-routine station/unit operating condition, Temporary administrative requirements, Authorities and responsibilities not included in procedures. DlSTRACTOR --r-pre-Job Briefs is a format for verifying Procedure Prerequisites ____-+-a.::;.n..:..d,_Precautions are understood prior to commencin an evolution. DlSTRACTOR Shift Training Briefs are a method of quickly disseminating important information. The STB is mainly used when the time to ____________ information to the operators is limited. .--c:-----j On-shift Just-in-time training provides training to Operations personnel on topics that do not require a formal classroom or simulator setting. This facilitates more focused training in the formal programs and provides an opportunity for direct instruction in the plant. Typical on-shift training topics may include, but are not limited to, operation of new tools or equipment, performance of a '--_____._..__.._--'-_new task, and electrical safet . EXAM BANK COMPUTER TEST Page: 174 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 68 Info ______+-:..c=.-:.:J::c..=--::;-,. ___....___......_______..---1 Status: for practice?_-l---'- ___________ ._____.._______--/ Points:---.---.--- .. ____ __ Difficulty: .. tI*---------General Data ) Technical Reference withlOP-AA-102-104, A v Revision Number: Pertinent Information Program, Rev 1 I Cognitive Level L , PRA: (Le. Yes or.No or #) NO 10C£13 55.43 (N/A for RO ___.____ Question History: {i.e. LGS NRC-05, OYS Question Source: (i.e. New, i Bank, Modified Revision History: Revision History: (i.e. distractor "b" to plausible based on reviewL__..__ILT ._._.__. Supplied Ref (If NONE a ro riate): (i.e..: ABN-##L-+--:-:-::-:-_' __ __Excluded

Reference:

(Le.

Of'j.:.'f:!.# not Low KA Justification (if _____--,____ EXAM BANK COMPUTER TEST . Page: 175 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 8854 Points: 1.00 Unit 1 plant conditions are as follows: Plant is in OPCON 1. RT-6-055-380-1. HPCI Drain Pot Flow Orifice Test is in progress. An EO reports that he has found a normally LOCKED OPEN valve (55-1F036) that appears to have been manually backseated hot. A short section of string is attached to the valve hand-wheel; however, no tag can be located. WHICH ONE of the following describes means by which intentional backseating of 55-1 F036 could be verified? A. Check P&ID 8031-M-55. B. Check the Locked Valve Log. C. Check the Equipment Status Tag Log. D. Check for an open clearance on HPCI. Answer: C Answer Explanation: Check the Equipment Status Tag Log: Correct because perOP-LG-10B-101-1004 paragraph 2.6.2 any valve backseated while hot requires an Action Request with an associated Equipment Status Tag applied. --::=-;.--------r..: Check P&IO 8031-M-5S: Incorrect due to discussion above and no specific backseating requirements annotated. Check the Locked Valve Log: Incorrect due to no specific requirements for valve backs eating in the Locked Valve Log. . Check for an open clearance on HPCI: Incorrect due to no indication that a clearance would be in place on a component when perform the RT for Drain Pot Flow Orifice. EXAM BANK COMPUTER TEST Page: 176 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 69 Question Always select on Authorized for Time to System User-Defined Cross Reference Num Field Multiple Choice Active No No 1.00 3 3.00 8854 8854 LGSOPS2010.IL RO QUESTION 68 3.9 i-i N---"u10-, /,.,) I)m_FI'-'-.e---"ld'-'2=-: ____Text 2.2.15 W LVi L.. ct.J,J.".".. P .Jl.?'1I'1/V /.---) .J {I A A.A. D } "I-, Reference with

• ReVIsion Number: Cognitive Level PRA: (i.e. Yes or No or #) 10CFR 55.43 (N/A for RC>> Question History: (Le. LGS NRC-OS, OYS CERT-04) Question Source: (i.e. 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

Reference:

(Le. ! i Ensure ON-## not provided)

I Low KA Justification (if OP-AA-108-101 -f1I-,..;::;I::tJ L NO 55.41 (b) 10 NEW NEW NEW NONE NONE N/A /) G I . A.>J -(.py. L.@9.uired): ___---"-_________-1 EXAM BANK COMPUTER TEST Page: 177 of 20 August 2010 EXAMINATION ANSWER ILT09-1 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 D/G for use on the D13 D/G 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-AA-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 i and quantity of information that needs to be obtained to

• narrow the troubleshooting scor::pe::c.::-=-::-::-:-:

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. I EXAM BANK COMPUTER TEST Page: 178 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Station Work Order requiring removal of a fuel injector from the 0*11 DIG for use on the 013 DIG: Incorrect due to the station work order process and clearance application for personnel safety would be required for this evolution. D14lDCAllOOP Plant Evolution/Special Test (PEST): I Incorrect due to A-C-29, or MOD-C-5, Mod acceptance testing covers PESTs. '---_______"_"___"."__.__.__.______..JI \Question 70 Info I Question-T-y-p-e-'-M-ultiple Choice ---.--.-----------1

Status: ---. Active Always select on test? No : Authorized for practice?

No lime .to Complete: Difficulty: i -=c--" ___. ---"-------------------------1 User-Defined 10: Cross Reference Number: T \ Identify the condition is controlled with a Troubleshooting, OpIC. Rework & TestLQ9JTRT) Form? . ._..---; ___. {} I ___.__ .!j.Ym Field 2: 3.6 I 3.8 (I 11 -I--I j .[.11 Text Field: 2.2.7 12.2.20 m. ,/&/)/re-f/ IZ.t/"f'-1i..!r'7 Comments: U ) :/..___ ...:.> __ Technical Reference with MA-AA-716-004 -") ) Revision Number: -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. 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) ________-:-=L-.-__._.________ ILT Supplied Ref (If None appropriatel.il:.e"'-. __A_B-'-N"""C"---'-##-'l)'--+- ________i Excluded

Reference:

(I.e. MA-AA-716-004 Ensure ON-## not provided)

LORT PRA: (I.e. Yes or No or #) No EXAM BANK COMPUTER TEST Page: 179 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order LORT Question Section: (i.e, A-Systems or Procedures) 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: 180 of 195 20 August 2010

• * * * * * *
• EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 71 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 "1 D" SRM count rate is 2 cps and has a signal-to-noise ratio of 1.6. 3.0 1.' I-I I I I I I I . ., I I I I J I I I2.' " I 22L{1 I I I I j r I I I I J i I ., \ f 1 I t ., I If t I I § -1. \ I [\. f I I I I I j .J \ , t I'...... fl I t I I 1. I rt: o.iO. , f J f , I , , o , , *I I II 14 IttI&1. .... .out IAftO ... CIXIIII' JodI ..... hGI& to 'IDUI u:rm nGIJU ",1...1 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 "A" or "C" core quadrants ONLY. C. All fuel loading must be suspended IMMEDIATELY.

EXAM BANK COMPUTER TEST Page: 181 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order O. Fuel loading may CONTINUE in any quadrant. Answer: C Answer Explanation: All fuel loading must be suspended IMMEOIATEL Y: SRM is inoperable since it does not have at least 3 cps, does not have adequate signal-to-noise ratio per TS 3.3.6-1. With "B" and "0" SRMs inoperable, fuel cannot be performed in any quadrant, since LCO 3.9.2 an SRM operable in the quadrant where fuel is being and in an adjacent OISTRACTOR Fuel may be loaded into "Au, "C", or "0" core ONLY: See OISTRACTOR Fuel may be loaded into "An or "C" core quadrants See OISTRACTOR Fuel loading may CONTINUE in any quadrant: See Question 71 Info Question Type: Multiple Choice I Status: Active Always select on test? No Authorized forpractice? No Points: 1.00 Time to Complete: 3 o 3.00 10: 8856 User-Oefined 10: 8856 Cross Reference Number: LGSOPS0074.10A I Topic: RO QUESTION Num Field 1: Num Field 2: p Il J I J I I Text Field: ;<-2.2.40 ) WtJi.--(A '1-rr I Comments: / // J , v Oata Technical Reference with Tech Spec 3.9.2 Revision Number: TS figure 3.3.6-1 i Cognitive Level H PRA: (I.e. Yes or No or #) NO 1 OCFR 55.43 (N/A for RO) 55.41 (b)6 Question History: (I.e. LGS BANK, LIMERICK LOT NRC-05, OYS CERT-04) 7306 Question Source: (I.e. New, BANK, LIMERICK LOT Bank, Modified) 7306 Revision History: Revision Edited stem to maintain History: (i.e. Modified consistent formatting. distractor "b" to make Changed order of plausible based on OTPS distractors. Changed review) correct answer from B to C. EXAM BANK COMPUTER TEST Page: 182 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order ,I ILT i I Supplied Ref (If NONE . (Le. ABN-##) IExcluded

Reference:

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

• 1 Low KA Justification (if N/A required):

EXAM BANK COMPUTER TEST Page: 183 of 195 20 August 2010 EXAMINATION ANSWER Il T09-1 RO questions in sample plan order 10: 3312 Points: 1.00 Unit 2 plant conditions are as follows: Reactor power is 60% A security guard calls the control room and reports a door to the Main Condenser Area was found uncontrolled and accessible General Radiation in this area is 1500 mrem per hour WHICH ONE of the following shall be immediately performed? A. inform the Shift Manager and search the area for personnel B. inform RP Supervision and initiate access control of area C. inform Industrial Risk Management and evacuate area D. inform Security and initiate an audit of Level II Keys Answer: B Answer Explanation: Inform RP supervision and initiate access control of area: Correct because if an HRAllHRANHRA cannot be controlled by a barricade or locked door, then consistent with step 4.1.1.2. above, it may be controlled by direct surveillance of the boundary. However, in those situations, the area must still be posted in accordance with 376. Any individual who determines that an HRAlLHRANHRA is not being controlled adequately shall notify RP immediately (while maintaining positive control over the area to the extent possible during this notification period). After notifying RP, the individual shall return to the area and maintain positive HRAlLHRANHRA access control of the area, without personal endangerment. until an RP representative arrives. In addition. the incident shall be documented as part of the Corrective Action Program. inform Shift Manager and search the area for personnel: Incorrect due to required action to notify RP immediately and maintain positive control over the area ------- inform Industrial Risk Management and evacuate area: Incorrect due to required action to notify RP immediately and maintain positive control over the area EXAM BANK COMPUTER TEST Page: 184 of 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order DISTRACTOR inform Security and initiate an audit of Level II Keys: I Incorrect due to required action to notify RP immediately and maintain positive control over the area i 011 ...: II 72 Info I Ouestion Type: Multiple Choice Status: select on test? No i Authorized for practice? No Points: 1.00 I Time to Complete: 3 3.30 i System ID: 3312 User-Defined ID: :3312 Cross Reference Number: LOT1760.04 TMocked High Radiation Area is found uncontrolled and . Topic: I accessible. shall be immediately performed? . Num Field 1: 3.2 -----1 Num Field 2: ----... " Text Field: ____ ./ '") ...1=' / ________ -1'") _________ Comments:\. 1-=---:---:---:-=_-::-- __...cG;-:-;ec...n;..,:.e.;..;;ra:.:,I.:::,D.--:.;ata . ==l Technical Reference with RP-AA-460, RP-AA-376, I Revision Number: RP-LG-460-1060, 1-::----::-,--:-. Cognitive level L 10CFR55.41 Question History: (i.e. LGS BANK NRC-05, OYS CERT-04) Question Source: (Le. New, BANK Bank. Modified) Low KA Justification (if N/A requiredL__-=-.-c--c-_-+--c,..-,--:-:-:--:-- __.____--t Revision History: Revision BANK History: (i.e. Modified distractor UbI! to make plausible based on OTPS review) I Suppiied Ref (if J I (Le. ABN-##L I Excluded

Reference:

(Le. Ensure ON-## not provide<:j 

.----------1 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (Le, A-Systems or I Procedures) .. EXAM BANK COMPUTER TEST Page: 185 of 195 20 August 201 0 I EXAMINATION ANSWER ILT09-1 RO questions in sample plan order Question 72 Table-Item Links LO Question 97 C HP Page: 186 of 195 20 August 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 1A 3574 MRlhr 1 B 1770 MRlhr 1 C 1750 MRlhr 1 D 1780 MRlhr 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 i i 1A 1153 MR/hr 1.0 1729 MRlHr I 1B 1164 MRlhr 1.0 1746 MRlHr 1C 1159 MRlhr 1.0 1738 MRlHr I 1D 1153 MRlhr 1.0 1792 MRlHr (Operator Aid 8-01-014)

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 HI/Downscale 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: D Answer Explanation: EXAM BANK COMPUTER TEST Page: 187 of 195 20 August 2010 EXAMINATION ANSWER IL T09-1 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 411 K603C, D. C & 0 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 DISTRACTOR 109 Rad F-1, Main Steam Line DIV I Rad HI/Downscale ONLY: Incorrect due to reasoning , Additional I 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 HI/Downscale 107 Reactor 1-1, Main Steam Line HI-HI ONLY: Incorrect due to reasoning above. Question 73 Info Multiple Choice Status: Active select on test? No Authorized for practice? Points: Time to ComEllete: Difficulty: System 10: User-Defined 10: --.. . . Cross Reference Number: LLOT0720.02 i Topic: .-MSL Hi rad tr' Num Field 1: Num Field 2: J\O fL"f-.J AJ I II A I Text Field: B2.3.5 Comments: d , . r I General Data J I Technical Reference with ARC 109 F-1, F-2

• Revision Number: COJlnitive Level H Justification for Non SRO 55.41 (b) 11 CFR Link: EXAM BANK COMPUTER TEST Page: 188 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question History: (I.e. LGS NEW NRC-OS, QYS CERT-04) Question Source: (I.e. New, NEW Bank, Modified)

Low KA Justification (if N/A i reguired): Revision History: Revision NEW History: (I.e. Modified distractor "b" to make . plausible based on OTPS I review)I ILT I Supplied Ref (If appropriate): (i.e. ABN-##) NONE ! I I I 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) 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 Limerick Lower RO SRO EXAM BANK COMPUTER TEST Page: 189 of 195 20 August 2010 EXAMINATION ANSWER ILT09-1 RO questions in sample plan order 10: 5998 Points: 1.00 Unit 1 initial plant conditions are as follows: Reactor power is RPV pressure is 1027 "1 Bit 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. EXAM BANK COMPUTER TEST Page: 190 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order 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 controlling pressure to lower pressure below 1053 psig. -----1 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. Question 74 Info Type: ___ ______________________ --__1 _____.-+I=-=A<;futc.:..:..::e ___.__...___________ ._._________J Always select on test? No i for practi_c N-'-o _______---ii__ _______________. Points: 1.00 Complete: __-l--:::.3--:-: ______________________! 3.00 stem 10: 5998 User-Defined 10: 5998 I I \ /l LJ j) / J... Cross Reference Number: LLOT1540.02 I LA:. J f11,rTJ e.e4J.t.* Unit 1 initial Reattor power is 80% RPV pressure is 1027 A:c{5; Topic: -;-:-__._.____tJpc..;ls'::'ig"'--"1-.cB '-".Outboard MSIV has failed closed Num Field 1: 14.0 ---. Num Field 2: 14.0 ,,=:' . ____ . ________-I Comments: General Data :--=--;-._____c.::::.____..__._ Technical Reference with ARC 107 G-2, Revision Number: OT-102 . Cognitive Level L 10CFR55,_ 10CFR55.41 (b},::1:-0 __-; Question History: (I.e. LGS Bank, IL T NRC Exam i-NRC-05, OYS CERT -04) 2005 ________--; Question Source: (I.e. New, Bank Bank, Modified) Low KA Justification (if N/A riequired)_: ..___,_-+-______" _____1 Revision History: Revision Bank History: (I.e. Modified distractor "b" to make plausible based on OTPS i review) 1 _____ __ __-_ i I Supplied Ref (If None ! appropriate): __+-__________; Excluded

Reference:

(Le. ON-## not provided)

LORT EXAM BANK COMPUTER TEST Page: 191 of 20 August 2010 EXAMINATION ANSWER IL T09-1 RO questions in sample plan order PRA: (Le. Yes or No or #} LORT Question Section: (Le, A-Systems or ,-Erocedures} .Qyestion 74 Table-Item Links Limerick 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: "'I Bn 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 and OT-117, RPS Failure OT-100, Reactor Low Level and OT-112. Recirculation Pump Trip OT-112, Recirculation Pump Trip and OT-117, RPS Failure OT-104. Unexpected/Unexplained Positive or Negative Reactivity Insertion and OT-100, Reactor Low Level Answer: 0 Answer Explanation: 01-104, Unexpected/Unexplained Positive or Negative Reactivity Insertion 01-100, Reactor Low Level: Correct because per the S43.0.B procedure for resetting Recirculation pump runbacks. conditions are met with trip of condensate pump and Total Feedwater flow> 80.3%. With the given plant conditions ARC-MCR-107-H2 would be followed for Reactor Low Level Alarm < 30" and entry into OT-100. The Recirculation Runback to the High Level Runback would cause the Power decrease driving entry into OT-104. OT-104, Unexpected/Unexplained Positive or Negative Reactivity Insertion and 01-117, RPS Failure: Incorrect due to no indication of entry condition to OT -117, RPS Failure since no SCRAM setpoint is exceeded. (Partial correct answer for OT-104 entry) ! 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-112, Recirculation Pump Trip and 01-117, RPS Failure: Incorrect due to reasons stated above. EXAM BANK COMPUTER TEST Page: 193 of 20 August 2010 I EXAMINATION ANSWER IL T09-1 RO questions in sample plan order Question 75 Info Question *Always select on Authorized for Time to System User-Defined Cross Reference iTopic: Num Field 1: Num Field 2: Text Field: Comments: Multiple 1.00 ! 3.00 Unit 1 is at 100% power when the following occurs: "1 B" . Condensate pump trips RPV level drops to + 4.0 4.3 f) J J _ Ii. J.:=---j !'t A I r 295014 G2.4.4 ..,).1lAl...J. ILl J £"0 ftt{d p lA.,(0/;,. Genldal Data U/ 1\ i ... Technical Reference with OT-117, .r . 1'1.. 1-"f[ ; Revision Number: OT-100' Cognitive Level 10CFR55 10CFR55.41 (b) Question History: (i.e. LGS NRC-05, OYS Question Source: (Le. New, Bank,

Low KA Justification (if Revision History: Revision History: (Le.

distractor "b" to II plausible based on OTPS review) II ILT Supplied Ref (If None appropriate): (Le. ABN-##) Excluded

Reference:

(Le. Ensure ON-## not provided)

LORT PRA: {Le. Yes or No or #) LORT Question Section: (i.e, A-Systems or B-Procedures) -Question 75 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 194 of 20 August 2010 ILLicense Exam SRO 1 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 2 plant conditions are as follows: A reactor scram from full power has occurred due to a loss of offsite power Shortly after the scram, lit alarm windows on MCR annunciator panels 201 through 206, 210, 216, and 220 go out. WHICH ONE of the following identifies the cause of the loss of DC power indicated by this loss of annunciators? A. One 30 Amp fuse has failed in 2PP01 B. Two 30 Amp fuses have failed in 2PP02 C. One 250 Amp fuse has failed in Fuse Box 200115 O. One 500 Amp fuse has failed in Fuse Box 200114 Answer: C Answer Explanation: One 30 Amp. fuse has failed in 2PP01, A failure of two 30 amp fuses in 2PP01 could have resulted in the indications provided; however, a failure of one fuse would only result in a loss of either 201 through 206 or 210,216, and 220. Two 30 Amp fuses have failed in 2PP02, A failure of two 30 amp fuses in 2PP01 could have resulted in the indications provided; however, a failure of either fuse in ! 2PP02 would NOT result in a loss of any of the . annunciators indicated. One 250 Amp fuse has failed in Fuse Box 200115, SRO Are responsible to execute ON-122, ON-122 will a failure of one 250 amp fuse in fuse box 200115 would energize 2PP01 completely, resulting in the indications rovided. ---i-'-:- ---,-----i OISTRACTOR One 500 Amp fuse has failed in Fuse Box 200114, A failure of one 500 amp fuse in fuse box 200114 would energize 2PP01 through 2PP04, resulting in the loss of all annunciators. EXAM BANK COMPUTER TEST Page: 1 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 1 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 10: 8857 User-Defined 10: 8857 Cross Reference Number: LGSOPS1550.lL3 Topic: SRO QUESTION 1 Num Field 1: 3.6 Num Field 2: 4.3 Text Field: 295004 AA2.01 Comments: General Data Technical Reference with ON-122. Revision Number: E-34. sh3. Rev 30 I Cognitive Level H I PRA: (i.e. Yes or No or #) NO I 1 OCFR 55.43 (N/A for RO) 55.41 (b) 10. 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)c-ILT Supplied Ref (If ON-122. LOSS OF MAIN appropriate): (I.e. ABN-##) CONTROL ROOM ANNUNCIATORS E-34, sheet 1 through 3. Excluded

Reference:

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

I Low KA Justification (if N/A . EXAM BANK COMPUTER TEST Page: 2of70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8820 Points: 1.00 Unit 1 plant conditions are as follows: -Reactor Water Level cannot be -Reactor Power is -Reactor Pressure is 580 psig going down -5 SRVs are Suppression Pool Level is -Suppression Pool Pressure is 18 WHICH ONE of the following describes conditions at which injection into the RPV must begin to ensure adequate core cooling? Immediately restore injection. Continue depressurization, when reactor pressure is 590 psig, then restore injection. Continue depressurization, when reactor pressure is 280 psig, then restore injection. Continue depressurization, when reactor pressure is 220 psig, then restore injection. Answer: D Answer Explanation: Immediately restore injection. Since MARFP (core cooling) is ensured until RPV pressure reaches 230 psig. Immediate restoration of injection is not required. Continue depressurization, when reactor pressure is 590 pSig, then restore injection. This distractor is incorrect Since MARFP (core cooling) is ensured until RPV pressure reaches 230 psig. Since 5 SRVs are open, the MARFP is 230 psig. The value of 590 PSIG would be correct if only 2 SRV open. Continue depressurization, when reactor pressure is 280 psig, then restore injection. This distractor is incorrect Since MARFP (core cooling) is ensured until RPV pressure reaches 230 psig. Since 5 SRVs are open, the MARFP is 230 i psig. The value of 590 PSIG would be correct if only 4 SRV are open. I EXAM BANK COMPUTER TEST Page: 3 of 20 August 2010 EXAMINATION ANSWER ANSWER ILT09-1 SRO questions in sample plan order Continue depressurization, when reactor pressure is 220 psig, then restore injection. 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 reactors 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. When RPV pressure drops to the MARFP or 5 ADS/SRVs cannot be opened injection into the RPV must be re-established to maintain adequate core cooling and to ultimately flood the RPV EXAM BANK COMPUTER TEST Page: 4 of 70 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 2 Info QuestionType: Multiple Choice Status: Active l'-:.Iways select on test? Yes i Authorizt':}d for practice? No i Points: 1.00 *Time to 3 Difficulty: 3.00 System 8820 *User-Defined 8820 Cross Reference Number: LOT-1560.06 SRO ONLY, RX t!ressure during ATWS iNUrn Field 1: 4.0 Num Field 2: 4.1 Text Field: 295037,EA2.06 Comments: General Data Technical Reference with T-116 Revision Number: Cognitive Level H PRA Y 10CFR 55.43 43.5 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}: History: Revision NEW History: (I.e. Modified distractor "b" to make i plausible based on OTPS . review) ILT Supplied Ref (If T-116 sheets 1 and appropriate): (I.e. Excluded

Reference:

(I.e. Ensure ON-## not I EXAM BANK COMPUTER TEST Page: 20 August 2010 3 EXAMINATION ANSWER I L 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 Heatup 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 provided RPV pressure is lowered psig Restore the instrument to operable within 14 days or establish a continuous fire ..weter within the next hour Answer: A Answer Explanation: Establish an hourly fire watch within the next hour. Per TSM 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 TSM 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 hours, 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 be serviced by fire detection is required. In this case, RCle is required when steam dome pressure is greater than 150 No actions required provided the other two heat rSTRACTOlf detectors and both smoke detectors are operable. The requirements of TSM 3.3.7.9-1 do not allow SUbstitution of smoke detectors for fire detectors. The action for the failed I heat LCO_. No action provide RPV pressure is stabilized below 200 psig TSM 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 __._... ___..l.-d_o_m-'.e than 150 psig. ____________ _ EXAM BANK COMPUTER TEST Page: 20 August 2010 EXAMINATION ANSWER KEY ILT09-1 SRO questions in sample plan vJv establish continuous fire w er within the next hour. Per TSM 3.3.7.9-1 this action would be required for Function A devices. I able within 14 days or EXAM BANK COMPUTER TEST Page: 7of70 20 August 2010

---

EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question Question T pe: I Multiple Choice Active 3 Info _ _

Always select on test? II for practice? oln s: I Time to Complete: 3 3.00 10: 5409 ! User-Defined 10: 5409 !cross Reference Number: LLOT0733.09 i OPCON 2 during plant -RPVpressure is 600 Topic: Heatu2J!:!j.Jrogress Fire Protection * ,J:!um Field 1: Num Field 2: SRO 3.4 Text Field: KIA 286000 2.4.25 Comments: I General Data

• Technical Reference with TRM 3.3.7.9 I Revisio Number: n #: 27 I Cognitive Level . H
• Justification for Non 10CFR55.43 (b) 5 CFR Link: Question History: (i.e. LGS NRC-02 .NRC-05, OYS CERT-04) Question Source: (Le. New, Bank I , Bank, Modified)

I I Low KA Justification (if N/A . Revision History: Revision History: (i.e. Modified distractor "b" to make plausible based on OTPS r:: vieW } ILT ..I Ref (If . : TRM 3.3.7.9 a roe ria',,, (i.e. ABN-T* Excluded

Reference:

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

I I EXAM BANK COMPUTER TEST Page: 20 August 2010 I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 3 Table-Item Links General Question Data Limerick RO EXAM BANK COMPUTER TEST Page: 9 of 70 20 Augusl2010 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 -RPV Level is -100" The current RPV level band is -90 to -120 -Drywell Temperature is 240 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) +5 inches -Wide Range (1 R623B) -115 inches -Fuel Zone (1R610) -125 inches Shutdown Range (1 R605) -21 inches 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: With the OB MSIV Room (Room 407) Area 11/12 greater than 350 degrees and RPV level at -100", Wide Range (XR-42-1 R623B) Indication temperature would be > than MRT (181°) and> than MIL (-124") per T-291 if an indication is <MRT or > MIL the indiction is usable. For the Fuel Zone Indication (LI-42-1 R61 0) temperature would be > than MRT (127") and> than MIL (-303") per 291 if an indication is <MRT or > MIL the indiction is usable EXAM BANK COMPUTER TEST Page: 10 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Narrow Range and Wide Range: With the OB MSIV Room (Room 407) Area 11/12 greater than 350 degrees and RPV level at -100", Narrow Range (LI-42-1 R606B) Indication temperature would be > than MRT (304 0) and < than MIL (+3") per T-291 if an indication is <MRT or > MIL the indiction is Not usable. Wide Range (XR-42-1 R623B) Indication temperature would be > than MRT (181°) and> than MIL (-124") per 291 if an indication is <MRT or > MIL the indiction is usable. Fuel Zone Range and Shutdown Range: For the Fuel Zone Indication (LI-42-1R610) temperature would be > than MRT (12r) and> than MIL (-303") per T-291 if an indication is <MRT or > MIL the indiction is usable. Shutdown (LI-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 240 0 in the Drywell and RPV level at -100" the indication is not usable. Narrow range and Fuel Zone Range: Narrow Range 42-1R6068) Indication temperature would be> than MRT (304°) and < than MIL (+3") per T-291 if an indication is <MRT or > MIL the indiction is Not usable. For the Fuel Zone Indication (LI-42-1 R61 0) temperature would be > than MRT (12r) and> than MIL (-303") per 291 if an indication is <MRT or > MIL the indiction is usable. Question 4 Question Type: Multiple Status: Always select on test? Authorized for practice? Points: I Time to COJTlplete: , Difficulty: I System 8861 r User-Defined ID: i Cross Reference Number: SRO QUESTION r Num Field 1: *Num Field Text Field: 295028, iGeneral Data i Ii Technical Reference with T-291 , Rev. 16 Revision Number: I Gognitive Level H r PRA: (Le. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 7,55.43 (b) 5 i Question History: (Le. LGS NEW NRC-05, OYS CERT-04) EXAM BANK COMPUTER TEST Page: 11 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 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 T-291, Temperature appropriate): (i.e. ABN-##) Effects on Reactor Level Instrumentation Excluded

Reference:

(i.e. NONE Ensure Ol\j-## not provided)

Low KA Justification (if N/A required): 5 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order ID: 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 hours B. Reactor vessel Safety Limit 1 hour C. ECCS system actuation with injection to the vessel 24 hours D. ECCS system actuation with injection to the vessel 1 hour Answer: B Answer Explanation: Reactor vessel Safety Limit violation -24 hours -Specification

6.7.1 which

requires the NRC Operations Center be notified as soon as possible and in all cases within 1 hours of a safety limit violation. Reactor vessel Safety Limit violation -1 hour -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 hours 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 hours of a safety limit violation. ____.________EXAM BANK COMPUTER TEST Page: 13 of 20 August 2010 --EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order DISTRACTOR DISTRACTOR iciUestion 5 Info Question Tyee: i Status: Always select on test? Authorized for practice?

Time to I Difficulty: System 10: User-Defined ID: I Cross Reference Number: L= I Toe icI Num Field Num Field 2: Text Field: Comments:

---"' ECCS system actuation with injection to the vessel-24 hours -This distractor is incorrect. 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 hours (LS-AA-1020) SAF 1.5 ECCS system actuation with injection to the vessel -1 hour -This distractor is incorrect. 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 I ECCS activation be reported within 4 hours (LS-AA-1020) SAF 1.5 Multiele Choice Active No I fDa 3 i 8838 LGSOPS1800.07 '- violation and reeortability requirement . I'" I L r&<> l/J *I-.'t.}O .. ._--General Data Technical Reference with I Safety limit 2.1.3, Tech-Revision Number:

• Spec 3.5.1 ACTION f Cognitive PRA: (I.e. Yes or No or 10CFR 55.43 LN/A for Question History: (i.e. NRC-05, OYS Question Source: (i.e.

Modified} Revision History: Revision History: (I.e. Modified distractor "b" to make plausible based on OTPS review) L --'--' NO 55.41 (b17, 55.43 (b) Modified EXAM BANK COMPUTER TEST Page: 14 of 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order --" ILT Supplied Ref appropriate): (Le. Excluded

Reference:

(Le. Ensure ON-## not Low KA Justification (if EXAM BANK COMPUTER TEST Page: 15 of 70 20 August 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 5 A fuel bundle 43-20 is being seated in the Core 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? 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 an.!1 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 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 ____----,_a_s_s_e_m_b_l,,---w_il_1 r_e_tu_r_n_t_he_c_o __ EXAM BANK COMPUTER TEST . Page: 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Evacuate the fuel floor and ensure all control rods are inserted. Evacuation of Fuel Floor necessary for safety of personnel. Inserting rods ensures that the core is made as sub-critical possible: Evacuation of Fuel Floor is necessary for of personnel only if a criticality occurs. Additionally, first action taken if count rate doubles with a fuel grappled is to raise the fuel assembly returning the core ______-+ 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 S8GT 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 resent s tom is required to be performed. DISTRACTOR 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. _______ Question 6 Info Multiple Qhoice Status: Active 1----- select on test? No for practice? No I Points: 1.00 Time to Complete: 3 roifficulty:

• 3.00

_ .. .886£ User-Defined 10: 88g f-::--'-----Cross Reference Number: LGSOPS1550.IL 1 AND IL2 ,........ Topic: . SRO QUESTION Num Field 1: Num Field 2: -'--' ! 2.4.11 I Comments: General I Page: 17 of 70 ------------20 August 2010 EXAM BANK COMPUTER TEST I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Technical Reference with ON-120 BASES, Rev. 17 Revision Number: -----_. Cognitive Level L PRA: (i.e. Yes or ti0_or #L NQ for RO)_ (bTL Question History: (Le. LGS BANK CERT -04 L._ ............. -*..*........*......Question Source: (Le. New, BANK,7566 .Bank, Modified} .*..Revision History: Revision BANK. 7566. Modified History: (Le. Modified stem to indicate count distractor "b" to make rate doubling WITHOUT plausible based on OTPS a continuous increase review) 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. ILT .. Supplied Ref (If NONE appropriate): (Le. ABN-##) Excluded

Reference:

(Le. NONE provided) 

.._.... Low KA Justification (if N/A required): .-.-.. ..EXAM BANK COMPUTER TEST Page: 18 of70 7 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: Points: 1.00 Unit 1 was operating at 100% power when the following events occurred: A significant fuel defect occurs Radiation levels in the plant rising WHICH ONE of the followinQ.tls if the off-site release rate (the sum of the activities of the six noble is less than or equal to the Tech Spec limit of 330 millicuries/second? Isotopic Off-Gas analysis per ST-5-070-885-1 Offsite dose calculations per EP-MA-110-200. Gaseous Effluent Dose Rate Determination for the Sou Stack per 880-0. Gaseous Effluent Dose Rate Determination for the N 880-0. Answer: A Answer Explanation: Tech Spec 3.11.2.6 -W' the rate of the sum of the activities of the specifi (j noble gases at the recombiner after-condenser dis arge exceeding 330 milicuries/second restore the gross radioactivity rate to within its limit . in 72 hours or be in at least HOT SHUTDOW ithin the next 12 hours. ST-5-070-885-1, Isotopic Of as Analysis determines if release rate is > than 3.30 +05 contact SSV and take action per TS 3.11.2.6 ODCM 3.2.1 .1, Liquid Effluents requires immediately restore the concentration to within the limits or terminate the release. There is no requirement to enter a Tech Spec action. ODCM 3.2.2.3, Gaseous Effluents, requires generation an Issue Report that identifies the cause for exceeding the limit and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. There is no . ..,--------1 ST-6-104-880-0, Gaseous Effluent Dose Rate Determination, requires radiation protection to perform AA-110-200, Dose Assessment, to determine off site radiation exposure effects. There is no requirement to Tech S ec action. EXAM BANK COMPUTER TEST Page: 19 of 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order .... Question 7 Info Question Type: Multiple Choice . Status: Active fttways select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3

• Difficulty:

3.00 [System ID: 8860 . User-Defined ID: 8860 i Cross Reference Number: LLOT-1790 OBJ 4 Topic: SRO Question 7 Num Field 1: 2.5 Num Field 2: 3.3 Text Field: 295038 EA2.02 Comments: General Data -I Technical Reference with procedure. print etc used Revision Number: to answer question I Cognitive Level L £IRA: (i.e. Yes or No Of:f!) NO

• 1 OCFR 55.43 (N/A for RO) SRO 55.43 (b) 4 i I Question History: (i.e. LGS I 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) i ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. Tech Spec 3.11.2.6 Ensure ON-##-not provided)

Low KA Justification (if N/A required): i EXAM BANK COMPUTER TEST Page: 20 of 70 20 August 2010 8 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order ..Points: 1.00 Unit 1 plant conditions are as follows: 1 00% reactor Secondary Containment Ventilation is in a normal Secondary Containment L'lP -.3 inches One of the running Reactor Enclosure Exhaust Fans trips and the "AUTO" Fan fails to start resulting in Reactor Enclosure L'lP reaching +4 inches WG. All other automatic actions occur as designed. \

• WHICH ONE of identifies!Secondary Containment L'lP 5 minutes later-#.no operator action is taken required action? ;-I\. I) Secondary Containment Z )ReqUired Procedural Action -.25 inches WG Verify Reactor Enclosure Isolation Complete per S76.9.A Verification Of Reactor Enclosure or Refueling Floor Secondary Containment Isolation Greater WG Shutdown Reactor Enclosure Supply

'. Fans per S76.2.8, Shutdown of Reactor Enclosure HVAC -./) -.25 inches WG Secure SBGT Fans per S76.B.A, Manual Startup and Shutdown of SGTS D. Greater than -.25 inches Initiate a Low dIp Secondary Containment Isolation per S76.8.B, Initiation of Reactor Enclosure OR -Refueling Floor Secondary Containment Answer: D Answer Explanation: -.25 inches WG -Verify Reactor Enclosure Isolation Complete per S76.9.A Verification Of Reactor Enclosure or Refueling Floor Secondary Containment Isolation 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 cannot be obtained. EXAM BANK COMPUTER TEST Page: 21 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order DISTRACTOR DISTRACTOR ANSWER Question 8 Info Question Type: Status: Always select on Authorized for Time to

• System User-Defined Cross Reference Topic: Num Field Num Field Text EXAM BANK COMPUTER TEST Greater than -.25 inches WG (positive)
• Secure SBGT Fans per S76.8.A, Manual Startup and Shutdown of SGTS -See answer below, additionally, the ARC directs S78.8.B for initiating an isolation signal. -.25 inches WG -Secure SBGT Fans per S76.8.A, Manual Startup and Shutdown of SGTS SGTS will not be in-service at this time. The question stem specifies 5 minutes after the failure of the fan to start. SGT8 will auto start 50 minutes after a loss of Delta P therefore

-.25 delta p cannot be obtained. Greater than -.25 inches WG (positive) -Initiate a Low dIp Secondary Containment Isolation per S76.8.B, Initiation of Reactor Enclosure OR Refueling Floor Secondary Containment. When the reactor enclosure exhaust fan trips and the standby 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 I INOP, 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 p 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 876.8.B. The RX ENCLlOutside DIV A (POI 76-198A) is upscale at +.05 Multiple 4.00 5913 !5913 LLOT0200.03 , 8, 9 Unit 1 100% reactor power Secondary Ventilation is in a normal alignment Secondary 3.8 295035 General Technical Reference with ANN-004 Revision Number: S76.8.B Page: 22 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Cognitive Level H Justification for Non SRO 10CFR 55.41 (b) 5, 7 CFR Link: Question History: (i.e. LGS I L T Cert Exam 2005 NRC-05, OYS CERT-04) i Question Source: (i.e. New, Bank I* Bank, Modified) Low KA Justification (if N/A reguired}: Revision History: Revision Bank History: (I.e. Modified distractor "b" to make

• plausible based on OTPS i review) ILT I Supplied Ref (If None appropriate}: (I.e. ABN-##) I Excluded

Reference:

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

LORT PRA: (I.e. Yes or No or #) N LORT Question Section: (i.e, A-Systems or

• Procedures)

Question 8 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 23 of 70 20 August 2010 9 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 6180 Points: 1.00 Unit 1 was operating at full power when a loss of EHC caused Main Turbine trip, and an Anticipated Transient Without Scram (ATWS) with the following: -Reactor power is -Reactor level is maintained by T-117, LEVEL/POWER -Reactor pressure is maintained between 990-1090 with -Suppression Pool temperature is 155 degrees and rising -Suppression Pool level is 23 CURVE SP/T-I LEGEND CURVE SPIT-I HEAT TEMP LIMIT WHICH ONE of the following identifies the required action for the given conditions? A. T-112, EMERGENCY BLOWDOWN, is required B. The current Reactor pressure band is acceptable C. Reactor pressure must be maintained at or above 901 psig. D. Reactor pressure must be maintained at or below 900 psig. EXAM BANK COMPUTER TEST Page: 24 of 70 20 August 2010 EXAMINATION ANSWER Il T09-1 SRO questions in sample plan order Answer: D Answer Explanation: 1-112, EMERGENCY BLOWDOWN, is required -With the conditions given above Suppression Pool temperature is 155 degrees and rising slowly, Suppression Pool level is 23 ft with reactor pressure of 990. 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. The current Reactor pressure band is acceptable -Per T -102 Bases SP I T -8, if during the initial evaluation of the HCTl curve. the operating point is on the unsafe side of the HCTl. no action may be taken to restore and maintain the safe side of the HCTL. The heat capacity of the suppression pool has been lost and emergency RPV depressurization is required. With the conditions given above Suppression Pool temperature is 155 degrees and rising slowly, Suppression Pool level is 23 ft with reactor pressure of 990. it can be determine that the operating i point is currently still on the safe side of the curve but

• cannot be maintained there.

Reactor pressure must be maintained at or above 901 psig. With the conditions given above Suppression Pool temperature is 155 degrees and rising slowly. Suppression Pool level is 23 ft with reactor pressure of 990. it can be determine that the operating point is currently still on the safe side of the curve but cannot be maintained there. Maintaining Reactor Pressure above 901 psig would result in the use of a pressure curve that would result in an I operating point in the unsafe region of the curve. ANSWER Reactor pressure must be maintained at or below 900 psig. With the conditions given above Suppression Pool temperature is 155 degrees and riSing slowly. Suppression Pool level is 23 ft with reactor pressure of 990, it can be determine that the operating point is currently still on the safe side of the curve but cannot be maintained there. Direction is provided in SPIT-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 1. Reducing reactor pressure to below 900 psig will provide operating point margin by shifting to the next pressure curve EXAM BANK COMPUTER TEST Page: 25 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 9 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 6180 6180 LGSOPS1560.1 L6 ATTACHMENT: HEAT CAPACITY TEMPERATURE LIMIT CURVE, is required Unit 1 was operating at full power 3.9 4.2 295013 2.1.25 General Data Technical Reference with T-102 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 required): Revision History: Revision Changed question stem, I History: (i.e. Modified one distractor, and distractor "b" to make answer to acoutn for plausible based on OTPS changes in curve review) ILT Supplied Ref (If . appropriate): (Le. ABN-##) Excluded

Reference:

(i.e. HCTL Curve, imbedded Ensure ON-## not provided) in question LORT PRA: (Le. Yes or No or #) Y LORT Question Section: (Le, A-Systems or B-Procedures)

Question 9 Table-Item Links General Question Data Limerick EXAM BANK COMPUTER TEST Page: 26 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8864 Points: 1.00 Unit 2 plant conditions are as follows: An A TWS 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 , HPCllnjection to Feedwater -EO lifts lead in AER HPCI and RCIC T-251 , HPCllnjection to Feedwater -EO lifts lead in AER RCIC ONLY T-247, Bypass RCIC Low Pressure Isolation EO lifts leads in AER RCIC and HPCI T-247 , Bypass RCtC Low Pressure Isolation EO lifts leads in AER Answer: B Answer Explanation: HPCI ONLY, T -251, HPCllnjection to Feedwater -EO lifts lead in AER: Appropriate systems for maintaining level during an ATWAS 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 "/l\' Feedwater line only, eliminating injection inside the shroud; however, RC1C injects to the "B" Feedwater line, outside the shroud, and is also available for injection. EXAM BANK COMPUTER TEST Page: 28 of 20 August 2010 I EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order HPCI and RCIC, T -251, HPCllnjection to Feedwater EO lifts lead in AER: Appropriate systems for maintaining level during an ATWAS 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, 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 injects to the "8" Feedwater line, outside the shroud. RCIC ONLY, T-247, Bypass RCIC Low Pressure Isolation -EO lifts leads in AER: RCIC injects to the "8" Feedwater line, outside the shroud; however, bypassing the RCIC low pressure isolation in 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 HPCI, T-247, Bypass RCtC Low Isolation -EO lifts leads in AER: Appropriate for maintaining level during an ATWAS are those inject outside the core shroud mixing the relatively injected water with the warmer water in the lower prior to it reaching the core, limiting the addition of reactivity. RCIC injects to the "8" Feedwater line, the shroud; however, answer is incorrect bypassing the RCIC low pressure isolation in prior to injection and because T-251 , HPCllnjection Feedwater, ensures HPCI injects to the "A" Feedwater only, eliminating injection to the "8" Core Spray which is inside the Alwa s select on test? Cross Reference Number: - Topic: ______________________________________Num Field 1: ---.. Num Field 2: Comments: Technical -1 Revision Number:

---

i Co nitive Level i H EXAM BANK COMPUTER TEST Page: 29 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order PRA: {Le. Yes or No or #) NO '1OCFR 55.43 (N/A for RO) 55.41 (b) 10, 55.43 (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: (I.e. Modified distractor "b" to make ! plausible based on OTPS I 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 I required): I EXAM BANK COMPUTER TEST Page: 30 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 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 46% -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 "2AtI 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: 31 of 20 August 2010 EXAMINATION 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 Load Set Runback begins after an 8 second time delay) 2. INSERT control rods per Rx Maneuvering Shutdown Instructions as required to maintain an adequate scram margin AND to remain within capacity of Main Turbine Bypass Valves. 3. REDUCE Main Generator reactive load to ZERO (0 MVAR) to minimize Main Generator Stator Amps. OT-112. Recire Pumg Trig states: IF while executing the remainder of this procedure, both Recirc Pumps trip, THEN immediately manually SCRAM Rx AND PLACE! Reactor Mode Switch in "SHUTDOWN" AND ENTER T-100, Scram/Scram Recovery OR 101, RPV Control, as applicable. (Ref. 5.3.13)

"2An & "28" Pumps tripped -Enter ON-114, Loss of Stator Water Cooling and Insert Control Rods per RMSI Only the "2A" Recirculation Pump should trip "2A" Pump tripped, only Enter OT-112, Recirculation Pump Trip, and manually scram the reactor -Manual scram is not required EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: 8865 Points: 1.00 Unit 1 plant conditions are as follows: OPCON Normal Plant Startup is in progress per AlllRMs are on Range ANN 107 REACTOR, H-4, SRM Upscalellnoperative alarms, with the following indicated: All four UPSCALE/INOP 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 Shutdown per GP-4. Place at least one SRM channel in the tripped condition within one hour per Tech Spec 3.3.6.1. 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: Correct 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. 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 S stems, a rapid plant shutdown per GP-4 ___.___-I Place at least one SRM channel in the tripped condition within one hour: 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. 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 i System becomes completely inoperable while that system I is required to monitor/control _____ EXAM BANK COMPUTER TEST Page: 33 of 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order DISTRACTOR Suspend Power Ascension per GP-2 and return to operable status as soon as possible: If a Monitoring System becomes inoperative while that is NOT required to monitor/control neutron flux, then 109, Total Loss of SRM, IRM, OR APRM Systems, the return that system to operation as soon as The answer is incorrect because SRM -IRM overlap performed with the IRMs below Range 3, and SRMs

• required in the Startup mode with the IRMs below Range i 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 hours 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 I becomes completely inoperable while that system is ____________ ____________Question 12 Info

• Status: Always select on test? . Authorized for eractice?

!Points: Time to Complete:

• Difficult}':

I System I User-Defined I Cross Reference lNum Field Num Field Text .Itinl", Choice Active No No 1.00 3 4.00 8865 8865 LGSOPS0074.IL 1 AND IL2 SRO QUESTION 12 3.4 3.7 215004. A2.02 I General Data i I II Technical Reference with i Revision Number: i I Cognitive Level . PRA: (i.e. Yes or No or #) II 1 OCFR 55.43 (N/A for RO) i I Question History: (i.e. LGS i NRC-05, OYS CERT-04) II Question Source: (I.e. New, Bank, Modified) I Tech Spec Table 3.3.6-1

• ON-109, Rev 5 i H NO 55.41 (b} 5,55.43 (b) 6 NEW NEW i EXAM BANK COMPUTER TEST Page: 34 of 70 20 August 2010 I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Revision History: Revision NEW History: (i.e. Modified distractor "b" to make I plausible based on OTPS C ew ) ILT ..--. , Supplied Ref (If NONE appropriC:'lte): (i.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A I EXAM BANK COMPUTER TEST Page: 35 of 70 20 August 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 teak occurs in the RCIC room, with room temp 118°F and rising (T-103, Secondary Containment, MNO temperature is 114°F Given the following: T-249, HPCIIRCIC 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 RCtC, AND the TRIP or T -200 procedure that describes the reason for the action? Ability to Reason Operate RCte. fQr Action RCtC 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 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 -249 to bypass RCIC high temperature isolation: 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 . EXAM BANK COMPUTER Page: 36 of 70 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order ANSWER DlSTRACTOR DISTRACTOR Question 13 Info Question Type: Status: select on test? i Authorized for practice? Points: Time to Complete: Difficulty: 2Y.?tem ID: User-Defined ID: Cross Reference Number: !QpJc: .. RCIC can continue to operate Perform T *112 IF RCIC automatically isolates on High Temperature: 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. RCIC can continue to operate Perform T*112 if RCIC MSO Temperature is reached: 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: LGS TRIP Step SCC/T-5 directs actions to isolate all systems discharging into Reactor Enclosure utilizing T-250 unless the system(s) is(are) required for either fire suppression or to accomplish steps directed in the TRIP procedures. Multiple 4.00 I-SRO QUESTION 13 : I Ii

• Num Field 1: 3.5 Num Field 2: Text Field:

F: General Data Technical Reference with

• Revision Number: I 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, . T-103 BASES, Rev. 2023 T-117 BASES, Rev. 2023 L NO 55.411b) 10, NEW NEW EXAM BANK COMPUTER TEST Page: 37 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO 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 Imbed Table SCC-1 appropriate): (Le. ABN-##) Excluded

Reference:

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

! Low KA Justification (if N/A reguired}: EXAM BANK COMPUTER TEST Page: 38 of 70 20 August 2010 EXAMINATION ANSWER IL T09-i 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: -is SRV deenergized (fuses removed) due to failed solenoid(s) -"iAn 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, and the basis for that LCO? No Tech Spec Actions required: Sufficient SRV's are available during a designed MSIV failure 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 Be in OPCON 3 within 12 hrs. and OPCON 4 within 24 hrs: Insufficient SRV's available during a designed MSIV failure Be in OPCON 3 within 12 hrs. and steam dome pressure <100 psig within 24 hrs: There are insufficient SRV(s) to function during a LOCA Answer: B Answer Explanation: No Tech Spec Actions required: Sufficient SRV's are available during a designed MSIV failure TECH SPEC 3.4.2 requires the safety valve function of at least 12 of the following reactor coolant system safety/relief valves shall be OPERABLE. LGS has 14 SRVs, the question stem indicates that two (1A and 1 L) of the valves would not function in the safetylrelief mode with bellows failed. The third SRV (1 S) will operate in the Safety/Relief mode but will not function in the ADS mode. This valve is required I to function in the ADS function so Tech Spec 3.S.1.d 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 (is) 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 SRV be functional or the LCO action must be taken. Be in OPCON 3 within 12 hrs. and OPCON 4 within 24 hrs: Insufficient SRV's available during a designed I MSIV failure EXAM BANK COMPUTER TEST Page: 39 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Be in OPCON 3 within 12 hrs. and steam pressure <100 psig within 24 There are insufficient SRV(s) to function during '----______.,_.L LOCA @uestion 14 Info i Question Type: Multiple Choice Status: Active! I Always select on test? No Authorized for practice? No . Points: 1.00 Time to Complete: 3 I Difficult}': 3.00 User-DElfi.neaID: Cross ""I Iv"" Number: LLo-t !2Eic: SRO QUESTION 14 ._1 Num Field 1: Num Field 2: = Text General Data Technical Reference with T.S. 3.4.2, 3.5.1, 3.5.3, Revision Number: 3.3.7.4 Cognitive Level L 10CFR 55.43 (N/A for RO) 10CFR 55.43 (b) 5 Question History: (i.e. LGS Bank NRC-OS, OYS CERT-04) Question Source: (Le. New, Bank Bank, Modified) Revision History: Revision Bank History: (Le. Modified distractor UbI> to make plausible based on OTPS review) ILT Supplied Ref (If T.S 3.3.3 and 3.5.1 (i.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A _. EXAM BANK COMPUTER TEST Page: 40 of 20 August 2010 EXAMINATION ANSWER ILT09-1 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 Monitors (SRMs) detectors are being withdrawn -Intermediate Range Monitors (IRMs) status is as follows: IRM IRM Range switch 4 3 3 o E F G 4 Annunciator "1A RPS & UPS DIST PNL TROUBLE" alarm at (120011, 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 related procedural requirements? IRM power supply loss Required Procedural actions A, C, and G only Perform S94.9.A, Routine Inspection of "A" RPS/UPS Inverter A, C, E and G Continue control rod withdrawal per GP-2, Normal Plant Startup A, C, E and G Perform S94.9.A, Routine Inspection of "A" RPS/UPS Inverter A, C, and G only Continue control rod withdrawal per GP-2, Normal Plant Startup Answer: C Answer Explanation: I A, C. and G only -Perform S94.9.A. Routine Inspection of "A" RPS/UPS Inverter Any combinations other than as listed in the answer. See Answer A. C, E and G -Continue control rod withdrawal per GP-2, Normal Plant Startup Any combinations other than as listed in the answer. See Answer EXAM BANK COMPUTER TEST Page: 41 of 20 August 2010 EXAMINATION ANSWER I L T09-1 SRO questions in sample plan order A, C, E and G -Perform S94.9.A, Routine Inspection of "A" RPS/UPS Inverter -ARC MCR 120 F-5 1 A RPS & UPS Distribution trouble alarm identifies a loss of power to panel 1AC248 which causes a loss of the loads listed on E-32 Sheet 1. 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 Panel 1 AD 102 CKT 17 or 1 CD1 02 CKT 04. 2. Overvoltage, undervoltage or under-frequency condition at RPS breaker Panel 1 AC248 to 1A RPS UPS Distribution Panel1AY160. DEVICE(S): I 81-AY2480i (CY24801) I 27-A Y24801 (CY2480 1 )

• 59-AY24801 (CY24801)

A GP-2, Normal Plant Startup cannot continue due to a 1/2 scram signal due to a loss of power supply to the 1 A Yi60 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 hours. DISTRACTOR A, C, and G only -Continue control rod withdrawal per GP*2, Normal Plant Startup i Any combinations other than as listed in the answer. See Answer IEXAM BANK COMPUTER TEST Page: 42 of 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 15 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 8858 8858 LOT0250.10 Loss of IRM power supply and procedural requirements R02.8 SRO 3.2 215003 A2.01 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 Cognitive Level H PRA: (i.e. Yes or No or #) Y 1 OCFR 55.43 (N/A for RO) SRO 55.43 (b) 2 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 distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE appropriate): (i.e. ABN-##) Excluded

Reference:

(i.e. 1A-Y160 Ensure ON-## not provided)

Low KA Justification (if N/A required): KIA 215003 A2.01 RO 2.8 SRO 3.2 EXAM BANK COMPUTER TEST Page: 43 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 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 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? All RFPs remain in service GP 5 Appendix 3, Unintentional Drop in with speed limited to 78%. Power C RFP trips. A & B remain OT-110, Reactor High Level in service. Speed limited to 78%. B & C RFPs trip. A RFP OT-100, Reactor Low Level remains in 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: Loss of the 12 Aux Bus trips the B Condensate pump trip and the 1 B Reactor Recirc MG-Set; additionally, with feed flow initially> 80%, there is a 62% runback of the recirculation system preventing a reactor scram. All Reactor Feed Pumps remain in service, and GP-5 is entered for the .._____.__ C RFP trips. A & B remain in service. Speed limited to 78%. OT-110, Reactor High Level. OT-100, Reactor Low Level:-----=-=---+-::=.:: B & C RFPs trip. A RFP remains in service with speed limited to 78%: OISTRACTOR All RFPs trip. T -101, RPV Control: Loss of this bus will NOT result immediate reactor EXAM BANK COMPUTER TEST Page: 44 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Question 16 Question TYl2e: Status: .. --.. Always select on test? Authorized for practice? Points: *Time to Complete: 3 I 3.00 iSystem 10: 8868 i

• User-Defined 10: _a i i Cros!:) Reference Numb,ef: LGSOPSOOOQ.lLaq SRO QUESTIO'N.

16

• Num Field 1: I Y Num Field 2: \ ) J / Text Field: Comments:

I General I I Technical Reference with ARC-MCR-104 F2 Rev 0 i

• Revision Number: I Cognitive Level H I PRA: (I.e. Yes or No or #) INO 1 OCFR §5.4_3 (N/A for RO) I 55.41 (b) 5, 55.4? (b) 6 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 .. I I ILT i Supplied Ref (If NONE . ABN-##) I Excluded

Reference:

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

EXAM BANK COMPUTER TEST Page: 45 of 70 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: 8869 Points: 1.00 Unit 1 was operating at 100% power when the following events occur: Level Transmitter L T-1 N1081A fails upscale Reactor Water Clean up is in service and operating normally A Loss of Coolant accident results in the following indications Reactor Scram Drywell Pressure 16 PSIG Drywell Temperature is 210 0 F RPV Level being maintained by HPCI at -60" Reactor Pressure 650 PSIG and slowly lowering WHICH one of the following describes the position of the RWCU isolation valves five minutes after HPCI start with no operator actions taken? EQUIPMENT NAME CHANNEL BYPASS HV-44-1 F001 "RWCU Suct" A&B None (INBD) HV-44-1 F004 "RWCU Suet" C&D None (OUTBD) HV-44-1 F001 HV-44-1 F004 (OUTBOARD) A. Closes B. Remains Open C. Remains Closes D. Remains Remains Open Answer: C Answer Explanation: l T-1N1081A failing up scale will prevent isolation of HV-44-1 F001 valve. Logic for isolation requires both A & B NSSSS isolation signals. When RPV level drops to below -38 inches (level 2) all other NSSSS (1N1081B through 1N1080D) level 2 transmitters will actuate. logic for isolation of the HV-44-1 F004 requires both C & D NSSSS isolation signals. These signals do not come from the 1N1081A therefore the valve will isolate. A is incorrect due to l T-1 N1081A failing up scale will prevent isolation of HV-44-1 F001 valve. logic for isolation requires both A & B NSSSS isolation signals. EXAM BANK COMPUTER TEST Page: 46 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order DISTRACTOR B is incorrect due to L T -1 N 1 081 A failing up scale will prevent isolation of HV-44-1 F001 valve. Logic for isolation requires both A & B NSSSS isolation signals. Logic for isolation of the HV-44-1 F004 requires both C & D NSSSS isolation signals. These signals do not come from the 1 N 1 081 A therefore the valve will isolate. DISTRACTOR o is incorrect. Logic for isolation of the 44-1 F004 requires both C & 0 NSSSS isolation signals. These signals do not come from the 1 N1081A therefore the valve will isolate. Question 17 Info Status: select on test? Authorized for practice? Points: Time to Complete: i Difficulty: System User-Defined Cross Reference Num Field Num Field Text Multiple 1.00 .3 4.00 SRO QUESTION 17 4.6 4.6 Il 204000,2.1.20 General I Technical Reference with

• Revision Number: Cognitive PRA: (Le. Yes or No or
• 10CFR 55.43 (N/A for ROJ Question History: (Le. LGS NRC-05, OYS CERT-04} Question Source: (i.e. 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

Reference:

(i.e. Ensure ON-## notprovided)

Low KA Justification (if required): Page: 47 of 70 T-226, Rev. 1414 I T-11 6 I Rev 1 i I ! I 55.41 (b) 5,55.43 (b) 6 I NEW NEW NEW I P&IO M-42, Sheet 2 is required to answer this question. NONE N/A 20 August 2010 I EXAM BANK COMPUTER TEST EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 8870 Points: 1.00 Unit 2 plant conditions are as follows: OPCON 5 Monthly ONE ROD OUT INTERLOCK VERIFICATION TEST. ST-6-107-632-1. 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: __* __ _______ ____ _______ ____________________ 'DiSTRACTOR-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. OISTRACTOR--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 unloaded_ _ __________________ jWhen 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. . . . . . EXAM BANK COMPUTER TEST Page: 49 of 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 18 Info Question Type: Multiple Choice Status: Active i Always select on test? No *Authorized for No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: User-Defined ID: Cross Reference Number: SRO QUESTION 18 3.3 4.1 234000, General Data Technical Reference with S97.0.M, Rev. 20 Revision Number: Cognitive Level L PRA: (I.e. Yes or No or #) NO 10CFR 55.43 (N/A for RO) 55.41 (b) 7,55.43 (b) 7 Question History: (Le. LGS NEW NRC-05, OYS CERT-04) Question Source: (I.e. New, NEW Bank, Modified) , Revision History: Revision NEW I History: (i.e. Modified distractor "b" to make plausible based on OTPS

• revie vv} ILT Supplied Ref (If NONE §Qprc>priate): (i.e. ABN-##) Excluded

Reference:

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

Low KA Justification (if N/A required): EXAM BANK COMPUTER TEST Page: 50 of 20 August 2010 19 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order ID: 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 All 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: DISTRACTOR T-213, Individual Control Rod Scram/Solenoid energization T -213 would not provide any benefit since ___ de-energized DlSTRACTOR T-215, De-enerization of Scram Solenoids T-215 would not provide any benefit since RPS has already -c-__I---'-en'-e.:....r .....gc=iz-'-e(.L ____________________ _ DISTRACTOR T -216, Manual Isolation and Vent of Scram Air Header T-216 would not provide any benefit since RPS had actuated and the Scram Air Header is already EXAM BANK COMPUTER TEST Page: 51 of 20 August 2010 EXAMINATION ANSWER ANSWER IL T09-1 SRO questions in sample plan order T-217, RPS/ARI Reset and Backup Method of Draining Scram Discharge Volume -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 Green Rod Full Out Indication not lit and Rod Drift lights lit. In aggregate, analysis the indication would eliminate a failure of RPS to function as the cause of the ATWS and indicate that there is an issue with the Scram discharge volume. 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 blocka e. System ID_:______--I..-.-.. ___________._._____.___..___.___ ___i User-Defined 10: Cross Reference Number: fcc T..-o--j c'=:-: _+1 SRO QU.ESTION 19 holder ==-..Num Field 1: Num Field ...,Text Field: Comments: -General Data Technical Reference with S97.0.M, Rev. 20 Revision Number: .._Cognitive Level H r:RA: (i.e. Yes ()r No or!!) . NO 1" OCFR 55.4;UN/A for ROj 55.41 {b}10, 55.43 {b) 13 Question History: (I.e. LGS NEW _f'!f3.f-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 cleviewl 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: 52 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 10: 5013 Points: 1.00 Unit 1 plant conditions are as foillows: ST-6-092-364-1, 014 DIESEL GENERATOR OPERABILITY VERIFICATION, is in progress: The EO working locally at the EDG reports that the procedure directs operation of LOCAL-REMOT 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-104-101, 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: 0 Answer Explanation: DISTRACTOR I Complete the ST, then submit a PPIS for the change per HU-AA-104-101, Procedure Use and Adherence -see answer below DISTRACTOR I Complete the ST, then submit a TC for the change, LG-101-1002 Temporary Changes To Approved Documents and Partial Procedure Use -see answer below ---i----'-' Stop the ST, process a PPIS for the change per 104-101, Procedure Use and Adherence, then ___: see answer below EXAM BANK COMPUTER TEST Page: 54 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order Stop the ST, process a TC for the change per AD-LG-1 1002 Temporary Changes To Approved Documents and Partial Procedure Use, then continue Temporary Changes (TC) to procedures or T&RMs should be issued when the existing document is in error. Errors in equipment numbers, equipment condition (ontoff, open/closed), numerical values, and sample calculations are be considered TCs 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. '--__ ..__.1_____________________ _____'Question 20 I Question Type: Multiple ..Status: Always select on test? Authorized for Qractice? I Points: 1.00 ..I Time to Complete: 2 I Difficulty: 3.00 I Sy;:Ht:::r 10: User-Defined 10 Cross Reference Number: SRQ Question 20 ,..-;. . Num Field l' Num Field 2: Text Field: ..---.. General Data Technical 04-Revisio Revision Number: 101 n #: . 1002 Il I I Cognitive Level L IpRA: N 10CFR 55.43 55.43 (b) 3 Question History: (Le. LGS BANK NRC-05, OYS CERT-04) Question Source: (i.e. New, BANK Modified) I Low KA Justification (if N/A required): Revision History: Revision Added procedure History: (Le. Modified references, still . distractor "b" to make considered bank Q I plausible based on OTPS ILT Supplied Ref (If NONE appropriate): (Le. ABN-##) EXAM BANK COMPUTER TEST Page: 55 of 20 August 2010 EXAMINATION ANSWER IL SRO questions in sample plan order i Excluded

Reference:

(Le. ; Ensure ON-## not provide_dL-.1._H_U'--_AA_-1_0_4_-1_0_1.

___Question 20 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 55.43 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. General Question Data EXAM BANK COMPUTER TEST Page: 56 of 70 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order 10: 8872 Points: 1.00 Unit 1 plant conditions are as follows: OPCON COfe Shuffle Part I is During transfer of an irradiated fuel bundle from the core to the spent fuel pool, a catastrophic failure of the fuel handling grapple occurs and results in the following: The fuel bundle is laying on itl/side in the transfer canal The fuel bundle was not damaged WHICH ONE of the following workers would be at the greatest risk of radiation overexposure? LSRO on the refuel platform "UJ /l B. Shaw workers erecting scaffolding on Elevation 313 C. Maintenance mechanic working on "1A" Recirc Pump D. Instrument Maintenance Technician at the Standby Liquid Control Skid Answer: B Answer Explanation: LSRO on the refuel platform Incorrect, water level above the fuel bundle will act as shielding and change in radiation levels are expected on the refueling platform Shaw workers erecting scaffolding on Elevation 313: Correct, Per RP-LG-460-103, Upper Level Drywell Access Controls during Irradiated Core Component Movement, during movement of irradiated fuel, control rods, or LPRMs through the cattle chute, then restrict access to elevation 313" and inside the bioshield on 303' including N9 stub nozzle. This restriction is put into place due to high radiation levels that may result Maintenance mechanic working on Safety Relief Valves: Incorrect due to the location of the Reactor Recirc Pumps not being impacted by radiation levels around the fuel transfer canal. Instrument Maintenance Technician at the Standby Liquid Control Skid: Incorrect due to the Standby Liquid Control skid is located on Elevation 283' and is not affected by increased radiation levels on Elevation 313' EXAM BANK COMPUTER TEST Page: 57 of 20 August 2010 EXAMINATION ANSWER IL T09-1 SRO questions in sample plan order To ic: - .. Num Field 1: Text Field: Comments: -----. __ Q_at_a________ Technical Reference with RP-LG-460-103 Revision Number: Cognitive Level L PRA: or __________LOCFB 55.43 (N/A for ROJ 55.41 (b) 12. 55.43 b 4 Question History: (i.e. LGS NEW NRC-05, OYS CERT-04) Question Source: {i.e. New, NEW _ Revision History: Revision NEW History: (i.e. Modified distractor "b" to make plausible based on OTPS review) ILT Supplied Ref (If NONE (Le. ABN-##) . Excluded

Reference:

(Le. NONE Low KA Justification (if re --L__._. ..___ ____ __'--.....L__ ____._ EXAfvf BANK"COMPUTER TEST Page: 58 of 70 20 August 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" DfW Pressure reached at 18 PSIG then rapidly dropped to 3 PSIG when the seal on the drywell equipment hatch failed MET Data indicates wind is from 88 degrees at 5 mph A General Emergency has been declared LIMERICK I PEACH BOnOM PLANT BASED PAR FLOWCHART 

---

..

Classification is a Gel1eral No PARs Required Yes Dose Projecrion ,. 500-IlIRem TEDE AND No < 1 Rem TEDE and <: 5 Rem eDE Thyroid Yes* Consider Shelter 2-MII. Radius & 5.M iles Downwind,

• Recommend Klfor the General No Public in Sheltered Areas. loss 01 'FUEL CLAD' Barrier
• Advise the remainder of the EPZ to monitor [AS Messages, Yes

______________ -, Yes

• Evacuate 2-Mile Radius & 5-Mil",

__-. No Downwind or Shelter baS<><! on offsite loss of 'PRIMARY CONTAINMENT' Barrier impediments,

• Recomm end Kllor the General Public in Yes EVII<:u.ted Areas,
• Ad.ise the remeinderofthe EPZ 10
• Eva<:uate 5 Mile Radius & 10-Miles monitor EAS Downwind or Shelter based on off.it INOTE: Ensure dose based PARs a;e evaluated , evacuated areas.

a release 15 in progress, .-----.J* Recommend Kllor general Public in Advise the remainder of the EPZ monitor EA') Date: _____Time: __.,Wind Directions (From) l---OOW-nWind Sectors' Wind Directions (From) Downwind Sectors' __3:355:-;;.-C't0"-C0;;:;O",,5 __ SSW 17510 '185 . NNW IN ':",N-=N.:::E=-=--j -006 to 017 SSE {SI SSW I SW '18610 '197 NNW f N.' NNE / NE I 01810027 SISSW!SW '19810207 NINNE/NE 02810 03;<-9__+ __ _____ N! NNE I NE / ENE ____ .-J!1QJQ 050_____ SSW { SW {WSW 220 10 { ENE 051 to 062-SSWISW I WSW rv:r r----231to 242----NNE f NE' ENE I E ,_-. I WSW I W 243 to 252 NE I ENE I E 073 to 084 SW I WSW I W {WNW 25310264 NEI ENEI E I ESE '---08510095 WSW I W I WNW 26510275 ENE I E f ESE 096 to 107 WSW I W / WNW I NW 27610287 ENE I E I ESE I:.LJ '108 to '117 ---If---'-7 W f;'( WNW (NW 28810297 E ( ESE I SE i I WNW I NW (NNW---298 to 309 E I ESE I SE I 130 to '140--VJNW (NW I NNW 310 to 320 ESE / SEI SSE I NW (NNW I N 32110332 ESE I SE f SSE IS '153 to '162 NW f NNW IN 333 to 342 SE I SSE IS '163 to '174 NW/NNW/N/NNE 34310354 SE/SSEISISSW 'BOLD refers to afleeted se(tors. These sectors are based on a dOse model stability class"D and II'l some cases ;)11 extc;) sector was inCluded lor cOI1servatlSm EXAM BANK COMPUTER TEST Page: 59 of 20 August 2010 I EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Which ONE of the following protective action recommendation should be taken? ,!::vacuation Radius A. Evacuate 2 Mile Radius I 5 Mile Downwind ENE I E / ESE B. Evacuate 2 Mile Radius / 5 Mile Downwind WSW/W/WNW C. Evacuate 5 Mile Radius! 10 Mile Downwind ENE/E!ESE D. Evacuate 5 Mile Radius 110 Mile Downwind WSW/W/WNW Answer: D Answer Explanation: Evacuate 2 Mile Radius I 5 Mile Downwind ENE I E I ESE: I Incorrect due to this evacuation is based on loss 2 of fission barriers Evacuate 2 Mile Radius I 5 Mile Downwind WSW 1 WI WNW: Incorrect due to this evacuation is based on loss 2 of three fission barriers and an incorrect assumption on I downwind sectors affected (I.e. wrong direction) i Evacuate 5 Mile Radius 110 Mile Downwind ENE I E I ESE: Incorrect due to Downwind sector being wrong. If the assumption is made that the wind is blowing to 88 degrees these sectors would be correct. The affected sectors are based on the wind from direction. Evacuate 5 Mile Radius 110 Mile Downwind WSW I W I WNW 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-1 008. 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 / WNW downwind sectors would be c:ifft::vlt:::U I EXAM BANK COMPUTER TEST Page: 60 of 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question 22 Info Question _____ Status: To ic:

• Num Field 1:

Num Field RevIsion Number: EP-AA-l11-F-08, Rev 0 I ----------------f---: --' Level____ H --------i Question History: (Le. LGS NEW _N.I3C-05.J)YS Question Source: (Le. New, NEW ______________________Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS __________ _ ILT Supplied Ref (If EP-AA-111-F-08 a Qr:QP.Siate -##) Excluded

Reference:

(Le. NONE Ensure ON-## not rovided Low KA Justification (if N/A EXAM BANK COMPUTER TEST Page: 61 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 23 10: 8879 Points: 1.00 Unit 1 Plant conditions are as follows: Reactor power 100% power 1& C determines that the following Transmitters are failed upscale LT-42-1N095A LT-42-1 N097A WHICH ONE of the following identifies the status of the Instrumentation LCOs listed below? TS LCO 3.:t:t TSLC03.3.5 A. Satisfied Satisfied B. Satisfied Not Satisfied.

C. Not Satisfied Satisfied D. Not Satisfied Not Satisfied Answer: 0 Answer Explanation: EXAM BANK COMPUTER TEST Page: 62 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Satisfied -Satisfied /Incorrect but plausible since only channels (One I subsystems) provide signals for the Level 3 permissive. If the applicant doesn't notice the note at the bottom of the page concerning that the Operable Channels per Trip Function" is per subsystem this choice appears to be correct answer, and doesn't how many level channels are actually available for circuits, or believes High level rip function is met due to transmitter being in a trieQed Satisfied -Not Satisfied I Incorrect but plausible if the applicant doesn't know how many level channels are available for ADS Not Satisfied -Satisfied I Incorrect but plausible if applicant doesn't know how many level channels are available for the RCIC circuits, or believes High level function is met due to transmitter being in a Not Satisfied-Not Satisfied I From M-42 Sheet 1, affected instruments would be: L T-1 N095A (ECCS -Level 3 Permissive) LT-1N097A (RCIC Level 2, 8). Sheet 2, Table 1 "Water Level instrumentation the function and level trip point for each level transmitter be found in the last two columns of the table. Based on information, LCO 3.3.3 is not met since the ADS Level Permissive requires a minimum of 1 operable channel system; two trip systems with 1 channel per trip LCO 3.3.5 is not met since RCIC Level 2 and Level 8 require a minimum of 4 operable channels (4 per function). I i Question 23 Info i Question TYQe: I Multiple Choice I Status: Active Always select on test? No ..I Authorized for Qractice? No I 1.00 Time to Complete: 3 3.00 Sysier 10 8879 I User-Definea 10 8879 Cross qt;,,:'1 ClI,..,Cl Number: LLO'I ufou.5B Topic: T.S & M-42 for Num Field 1: Num Field 2: Text Field: .1 General Data I Technical Reference with I S97.0.M, Rev. 20 i Revision Number: ._-_._--_. EXAM BANK COMPUTER TEST Page: 63 of 20 August 2010 EXAMINATION ANSWER KEY IL T09-1 SRO questions in sample plan order Cognitive Level H I I PRA: (i.e. Yes or No or#t NO I i 1 OCFR 55.43 {N/A for RO) 55.43 {b}2 I [ Question History: (I.e. LGS 20081LT .. NRC-05. OYS CERT-04)

• Question Source: (I.e. New, . 20081LT Modified)

Revision History: Revision 20081LT History: (I.e. Modified

• distractor "b" to make plausible based on OTPS review) i i ILT Supplied Ref (If T.S. Sections 3.3 appropriate): (i.e. ABN-##) (instrumentation).

and 3.3.5 (RCIC) M-42-sheet 1 & 2 I Excluded

Reference:

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

II Low KA Justifii.;cHIVIl (if . N/A required): I '------_._-- I EXAM BANK COMPUTER TEST Page: 64 of 70 20 August 2010 EXAMINATION ANSWER IL T09-1 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: EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Automatic Group 6B isolation will terminate the release. Ensure isolation of 2 inch vents and start of SGTS. A south stack hi hi radiation signal will not initiate a 6B isolation (see GP-8 Pg. 6. 8-9). No isolations will ,_______ occur. ____.______.__-I Automatic Group 6B isolation will terminate the release and SGTS will remain in standby. Ensure isolation of 2 inch vents. A south stack hi hi radiation signal will not initiate a 6B isolation (see GP-8 Pg. No isolations will automatically ____ 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. SGTS will not automatically initiate. __._____--j Alarm only. Manually isolate 2 inch vents and ensure drywell cooling is maximized I OT-101 High Drywell Pressure. Step 3.16.6, IF Primary Containment steam leak is detected or South Stack HI/HI-HI Radiation alarm F-1) is received while venting Drywell then close the following valves HV 211, IN BD and HV -57. OUTBOARD. An OT-101 immediate operator action is to Maximize Drywell cooling (Step 2.1). Per ARC 003 RAD ______. __-L.F:....-....:1..!....

r.

.___ .., Status: Active

-_-+-N_o-'---

____ __._._________ _ .. ---_.-..... .. --l Points: 1.00 . Time to Comple!_e.:. ___--1!-:0____*___ _______.__._____I Difficulty: 0.00 System ID: 54...Q1 User-Defined ID: ----+-5::-.:..::.40t-'-1 .. Cross Reference Number: LLOT1540.02 Drywell venting to REECE is in progress for containment _.-.-._._-+- cOi"\trol ____: Num-F-ie-ld-2-:-"-' SRO 3.2 Text Field: KIA 2.3.11 Comments: ..-c_------- .. General Data .. .. Technical Reference with OT-101 Revision Number: --1 Ii 10CFR55.43 1 OCFR55.43 (b) Question NRC-05, OYS CERT-04) -EXAM BANK COMPUTER TEST Page: 66 of 20 August 2010 i EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order Question Source: (Le. New, Bank Bank, Modified) Low KA Justification (if Bank required): Revision History: Revision Bank History: (Le. Modified distractor "b" to make plausible based on OTPS review) . ILT none I Ref (If ropriate): (Le. ABN-##) Excluded

Reference:

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LORT PRA: (Le. Yes or No or #) LORT Question Section: (Le, A-Systems or B-Procedures) Question 24 Table-Item Links General Question Data Limerick RO EXAM BANK COMPUTER TEST Page: 67 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order 25 10: 8874 Points: 1.00 Unit 1 plant conditions are as follows: Reactor Scram Control Rod 06-39 is stuck at position 24 Four other control rods are stuck at position 02 No Boron has been injected IRMs are downscale on Range 1 SRMs are midscale and trending down (10E+3 CPS) WHICH ONE of the following describes the status of the Reactor based on the above conditions? ATWS in Progress Shutdown Status A. YES Reactor is Shutdown B. YES Reactor is NOT Shutdown C. NO Reactor is Shutdown D. NO Reactor is NOT Shutdown Answer: A Answer Explanation: EXAM BANK COMPUTER rEST Page: 68 of 70 20 August 2010 EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order ANSWER DISTRACTOR DISTRACTOR DISTRACTOR fQUestion 25 Info i Question Type: Status: I Alway"s select on test? i Authorized for practice? Points: Time to C0rYlplete: Difficulty: .Sy"sterYl 10: I User-Defined 10: Cross Reference Number: *Topic: Num Field 1: Num Field 2: Text Field: Comments: YES I Reactor is Shut Down: Per Trip Bases: An ATWS is defined as: all rods NOT inserted to OR beyond 02 AND the reactor has NOT been determined to be shutdown under all conditions without boron, As Control Rod 06-39 is stuck at position 24 the definition of ATWS is met. SHUTDOWN is defined as the reactor is subcritical with power below the heating range as defined by IRMs below range 6 OR SRMs below 50,000 cps. As IRMs are downscale on range 1 and SRMs are 10E+3 CPS the definition of shutdown is met. YESI Reactor is NOT Shut Down: See Above NO I Reactor is Shut Down: See Above NO I Reactor is NOT Shut Down: See Above Multiple Choice Active No No 1.00 3 3.00 8874 8874 LLOT-1560.06 SRO QUESTION 25 4.0 4.6 2.4.21 General Data Technical Reference with Revision Number: i -'" Cognitive PRA: (i.e. Yes or No or 10CFR 55.43 (N/A for Question History: (i.e. NRC-05, OYS CERT Question Source: (i.e. Bank. Trip Bases, T-101 H YES 55.41 (b) 7.55.43 (b) 5 NEW NEW EXAM BANK COMPUTER TEST Page: 69 of 70 20 August 2010 --EXAMINATION ANSWER ILT09-1 SRO questions in sample plan order .. Revision History: Revision NEW History: (Le. Modified distractor "b" to make plausible based on OTPS _________1______.___._.* Supplied Ref (If a r()Q!2Cite): (Le. Excluded

Reference:

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