Text

July/August 2002 Retake Exams 50-369 & 50-370/2002-302 Final Written SRO Exam
	ML022520008
Person / Time
Site:	Mcguire, McGuire
Issue date:	06/04/2002
From:	; NRC/RGN-II
To:	;
References
	50-369/02-302, 50-370/02-302
	Download: ML022520008 (151)
	v • d • e

Final Submittal (Blue Paper)

MCGUIRE AUGUST/SEPTEMBER 2002 50-369 & 50-37012002-302 FINAL WRITTEN SRO EXAM WITH ANSWERS & KAs Senior Operator Written Examination

The following questions will have reference material provided.

3 Tech Specs. 3.6.1 and 3.6.3

9 Data Book Curve 1.10B, E-1 and Steam Tables

31 Steam Tables

1011 E-1, Steam Tables and Data Book Curve 1.10B

Bank Question: 959 Answer: B I Pt(s) The NCPs are limited to 3 consecutive starts in any 2-hour period. There is an additional requirement of a minimum idle period of 30 minutes between restarts. What is the reason for these limitations? This restriction assures that the oil temperature will decrease to design specifications between restart attempt This restriction prevents overheating the motor windings due to high starting current This restriction allows the NCP seals to fully reseat between NCP oil lift pump cycle This restriction ensures that natural circulation is reestablished between starts to prevent a cold-water addition acciden Distracter Analysis: Incorrect: The reason is stator-winding temperatures Plausible: if the candidate remembers this as a high temperature concern - another adverse consequence of multiple starts on motors Correct Answer: Incorrect: The reason is stator-winding temperatures Plausible: NCP seal seating is the basis for a different cold start precaution - seal leakoff limit after seal replacement Incorrect: The reason is stator-winding temperatures Plausible: if the candidate is confused regarding the basis for the precautio Level: RO & SRO KA: 000015/17 AK3.01 (2.5/3.1)

Source: BANK Level of Knowledge: Memory Lesson Plan Objective PS-NCP-Obj. 10 References:

Ques_959.doc

)OP'6SCsanb VZOO/0919/V/I/(10

Bank Question: 967 Answer. D 1 Pt(s) Unit 1 is responding to a feed line break inside containment. Given the following events and conditions:

Completed EP/l/A/5000/E-0 (ReactorTrip or Safety Injection)

Entering EP/1/A/5000/E-1 (Loss ofReactor or Secondary Coolant)

The STA reported the following valid Critical Safety Functions:

"* Subcriticality - yellow path

"* Containment Pressure - orange path

"* Heat Sink - orange path

"* All other CSFs are green or yellow Which one of the following statements correctly describes the proper procedure flow path? Remain in E-1 (Loss of Reactoror Secondary Coolant) Transition immediately to FR-S.2 (Response to Loss of Core Shutdown) Transition immediately to FR-Z.1 (Responseto High ContainmentPressure) Transition immediately to FR-H.1 (Response to Loss of Secondary Heat Sink)

Distracter Analysis: Incorrect: - must transition to CSFs Plausible: - if candidate does not know restrictions and applicability of F-0 Incorrect: - Orange path does not have priority over red paths Plausible: - if candidate does not know rules of usage Incorrect:

Plausible: - if candidate does not know CSF rules of usage Correct answer: - Heat sink has priority over integrity Level: SRO Only KA: WE/05 EA2.1 (3.2/4.4)

Source: NEW Ques_967.doc

Level of Knowledge: Analysis Lesson Plan Objective: OP-MC-EP-INTRO Objs. 1,3,11 References 1. OMP 4-3 pages 16-19 Ques_967.doc

Bank Question: 969 Answer. C 1 Pt(s) Following a Small Break LOCA inside containment the following conditions exist:

Containment Temperature is 145 degrees * Containment Pressure is 3.2 psig

Reactor Coolant temperature is 500 degrees * Lower Containment humidity is 100%

Adverse Containment Conditions are determined by: Calculating the containment saturation pressur The operator taking into account the containment temperatur The operator through the use of containment pressur The saturation temperature of the Reactor Coolant System versus containment pressur Distracter Analysis: Incorrect:.

Plausible:. Incorrect:.

Plausible:. Correct: Incorrect:.

Plausible:.

Level: RO&SRO KA: EAPE09.K3.16 (3.8/4.1)

Lesson Plan Objective:

Source: New Level of knowledge: memory References: EP/E-0, Step 13 Ques_969.doc

Bank Question: 971 Answer., B Bank Question: 971 Answer: B 1 Pt(s) Unit 2 has experienced a load rejection from 100% R.T.P. due to the trip of the "2A" FWPT. As a result of the transient the following conditions exist:

Pressurizer level is greater than setpoint

2NV-238 (ChargingLine Flow Control)is closing

NC pump seal injection is <5 gpm per pump Which one of the following statements correctly describes the required operator action to restore adequate and proper NC pump seal injection flowrate? Open 2NV-241 (SealInj. Flow Control) Close 2NV-241 Close 2NV-238 while opening 2NV-24 Open 2NV-238 while opening 2NV-24 Distracter Analysis: Incorrect:

Plausible: Correct: Incorrect:

Plausible Incorrect:

Plausible:

Level: RO&SRO KA: APE 000022 AA1.01(3.4/3.3)

Lesson Plan Objective: PS-NV SEQ 3 Source: New Level of knowledge: Memory References: OP-MC-PS-NV page 117 Ques_971.doc

Bank Question: 984 Answer. A 1 Pt(s) Which one of the following pre-planned activities that has been evaluated and approved in advance by Operations can take place during shift turnover? Dilution to ECB ZPPT Drain to Mid-Loop Reactor Startup

Distracter Analysis: Correct: Incorrect: Should not be scheduled during turnover Plausible: Incorrect: Should not be scheduled during turnover Plausible Incorrect: Should not be scheduled during turnover Plausible:.

Level: RO&SRO KA: G2.1.3 (3.0/3.4)

Lesson Plan Objective: OP-MC-ADM-OMP Obj 2 Source: New Level of knowledge: memory References:

1. OMP 2-2 page 33 Ques_984.doc

Bank Question: 03 Answer: B

1 Pt(s) Unit 1 is heating up in Mode 4 with NCS temperature at 230 Which one of the following conditions would violate containment integrity if the condition existed for 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months in the current mode?

REFERENCES PROVIDED: Tech Spec 3.6.1 & 3. KF-122 (FuelTransfer Tube) is known to be leaking by its sea RN-253A (RB Non ESS Sup Cont Inside Isol) failed its stroke timing test, but can be closed from the control roo KC-429B (Rx Bldg DrainHdr Cont Inside Isol) power supply has failed, and is close IVQ-1A (ContAirRel Inside Isol) has its air supply removed and has failed close Distracter Analysis: Incorrect: 1KF-122 is normally open, and not automatically closed Plausible: if the candidate does not recognize that integrity is provided by the blind flang Correct: Incorrect: Closed without power retains containment integrity Plausible: This is an automatic cont. isolation valve that is inoperable Incorrect: closed with air isolated retains containment integrit Plausible: This is an automatic cont. isolation valve that is inoperable Level: SRO Only IOCFR55.43(b)(2)

KA: APE069A2.01 (3.7 / 4.3)

Lesson Plan Objective: CNT-CNT SEQ 9 Source: Bank; Ques_34.1 McGuire NRC 2002 Level of knowledge: Comprehension Ques-034.1.doc

References:

1. OP-MC-CNT-CNT page 31 2. Tech Spec 3.6.1 and 3.6.3 - PROVDED Ques_034.1.doc

Bank Question: 03 Answer: A 1 Pt(s) Unit 1 was conducting a reactor startup following a refueling outage. Given the following conditions during the reactor startup:

"* N-31 indicates 2.1xl0 4 cps

"* N-32 indicates 2.0x10 4 cps

"* N-35 indicates 5.5x10n1 amps

"* N-36 indicates 1.0xl010 amps

"* Rods are in manual with no rod motion

" SR and IR NIs are slowly increasing

"* Tave is holding steady Which one of the following best explains the indications? N-35 compensating voltage is set too high N-35 compensating voltage is set too low N-36 compensating voltage is set too high N-36 compensating voltage is set too low

Distracter Analysis: Correct: N-35 reads too low for the conditions given, compensating voltage is too hig Incorrect: N-35 reads too lo Plausible: candidate reverses the effect of compensatio Incorrect: overlap is proper for N-36 Plausible: If candidate does not know that P6 = lx10-10 IR is about 2x104 CPS S Incorrect: overlap is proper for N-36 Plausible: If candidate does not know that P6 = lxO0-10 IR is about 2x104 CPS S Level: RO&SRO KA: SYS 015 K5.02(2.7/2.9)

Lesson Plan Objective: IC-ENB SEQ 7 Source: Bank Level of Knowledge: analysis References:

1. OP-MC-IC-ENB pages 25, 69, 79 Ques_037.2.doc

Bank Question: 09 Answer. C 1 Pt(s) Unit 1 was responding in E- 1 (Loss ofReactor or Secondary Coolant)to small break LOC Given the following parameters at the indicated times:

Parameter 0200 0205 0210

"* NCS pressure (psig) 1500 1550 1600

"* Core exit T/C temp (0 F) 576 584 586

"* Tave (F) 567 569 572

"* Thot (F) 570 574 578

"* T 0 id ( 0F) 563 564 566

"* Pressurizer level (%) 10% 19% 28%

"* Containment pressure (psig) .9 CA flow to all 4 S/Gs exceeds 450 gpm from 0200 to 021 What is the earliest time (if any) when adequate subcooling exist such that the operators can transition to ES-i.1 (Safety Injection Termination)?

REFERENCES PROVIDED:

E-1 Databook Curve 1.10B Steam Tables Transition to ES-1.1 at 2:00 Transition to ES-1.1 at 2:05 Transition to ES-1.1 at 2:10 Remain in E-1, SI flow may be not terminated

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Distracter Analysis:

The objective of this question is to determine if the candidates can apply the SI termination criteria and assess saturation conditions in the NC syste Use of the Unit I Databook curve 1.10B is NECESSARY. Accurate use of the steam tables will lead to an incorrect answer due to a failure to consider the instrument errors involved. If Steam Tables are used to determine subcooling, then at 0205 the candidates have met the criteria to terminate S Ques_093.1.doc

From the steam tables:

1500 psig + 14.6 = 1514.6 psia 597 IF = 1510 psia saturation pressure Incorrect: Not >11% PZR level, saturated using curve 1.1OB, which accounts for instrument error and must be used to determine all EOP transition Plausible: if the candidate uses Databook, this point is subcooled

< 578 O Incorrect: - not saturated - by curve book - >582 0F Plausible: - if the candidate does not determine Psat correctly - or if he uses RTD temperatures in place of T/C temperatures for core temperature determinatio Correct answer: by the curve book, the core is < 588 Incorrect: meets the criteria at 021 Plausible: - if the candidate does not determine P-sat correctly thinks ACC values come in at 1 psig containment pressur Level: SRO Only 55.43b(5)

KA: 000074 K1.01 (4.3/4.7)

Lesson Plan Objective: IC-ICM SEQ 9 Source: Bank Level of knowledge: analysis References:

1. OP-MC-IC-ICM pages 33, 35 2. EP/1/A/5000/E-1 page 5 3. Unit 1 Databook Curve 1.1OB 4. Steam Tables 5. OMP 4-3 page 9 Ques_093.1.doc

Bank Question: 12 Answer: C 1 Pt(s) A worker is preparing to enter a 'High Radiation Area' to work on a valve in the reactor building. During the pre-job briefing, RP states that the expected whole body radiation levels are as follows:

"* Dose rate in the center of the room = 100 mrem/hr

"* Dose rate 18 inches from valve = 200 mrem/hr

"* Contact reading = 1100 mrem/hr How should the area around the valve be classified? The room is a 'Radiation Area'; the valve is a HOT SPOT The room is a 'High Radiation Area'; valve is NOT a HOT SPOT The room is a 'High Radiation Area'; the valve is a HOT SPOT The room is an 'Extra High Radiation Area'; the valve is NOT a HOT SPOT

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Distracter Analysis: Incorrect: 100 mrem/hr general area dose rate > 100 mrem/hr =

high radiation area Plausible: if the candidate does not know that the lower limit for a high radiation area is 100 mrem/hr - and the valve is a hot spot Incorrect: The valve is a hot spot Plausible: the room is a high radiation area - if the candidate thinks that the definition of a hot spot is > 5x general area dose rate when measured 18 inches from the contact reading Correct Answer: Incorrect: The room is not an extra high radiation area Plausible: if the candidate thinks that the definition of a hot spot is

> 5x general area dose rate when measured 18 inches from the contact reading Level: RO&SRO KA: G2.3.10 Source: BANK Level of Knowledge: Memory Ques_125.1.doc

Lesson Plan Objective: OP-MC-RAD-RP Obj 71 Reference:

1. GET Student Guide pages 109-114 Ques_125.1.doc

Bank Question: 14 Answer. B 1 Pt(s) Today, you are directed to complete a valve lineup on Unit 1in accordance with enclosure 4.10 to OP/l/A/6200/005, Spent Fuel Cooling System. The controlled copy of the procedure has a restricted change noted for valve 1KF-145. This normally open valve has been locked open in accordance with a special order that remains in effect until October 1 Which one of the following statements describes the correct action needed to validate your working copy of the procedure? (Your copy of the procedure is in other respects identical to the controlled copy.) Replace your working copy with an updated procedure printed from the NEDL syste Annotate the working copy with a pen and ink change for the valve position for 1KF-145; change to "Locked Open", annotate the restricted change number and initial the chang Annotate the working copy with just the restricted change number (as a cross reference) next to the 1KF-145 line item, and initial the chang Use the working copy as is since restricted changes of this nature are not required to be written into working copie Distracter Analysis: Incorrect: Cannot print because NEDL will not list this procedure as issue Plausible: NEDL is an approved source of working copies for non changed procedure Incorrect: Must write in the actual change languag Plausible: The controlled copy is annotated with only the restricted change #. Correct: Incorrect: Must write in the actual change languag Plausible: It is not necessary to annotate working copies if the change does not affect the job or no longer applies - would be true after October 1st" Level: RO&SRO KA: G2.1.21 (3.1/3.2)

Ques_143.2.doc

Lesson Plan Objective: ADM-OP Obj 8 Source: BANK Level of knowledge: memory References:

1. OMP 4-1 pages 11-12 Ques_143.2.doc

Bank Question: 19 Answer: B 1 Pt(s) Unit 1 was operating at 100% power when a total loss of feedwater occurred. The operators reached Step 7 of FR-H. 1 (Response to Loss of Secondary Heat Sink), which attempts to establish CA flow to at least one S/G. Sub-step 7.k states:

Maintainfeed flow rate less than or equal to 100 GPM until S/G WR level is greaterthan 12% (17%

ACC).

Given the following conditions:

LoonA Loop B Loon C Loop D S/G (WR)[%] 0 15 9 10 NC THOt [0 F] 150 555 530 545

"* Containment pressure is 3.4 psig

"* The TD CA pump is available to feed the S/Gs Which one of the following statements correctly describes the bases for the restrictions for restoring feedwater flow following feed and bleed in FR-H. 1? Restore flow to the 'A' S/G because loop 'A' T-hot is the lowest of the loops and this will reduce the chance of thermal shocking the S/G. Flow should not be restored to the 'B' and 'C' S/Gs because they will be reserved for use later to provide a steam supply for the TD CA pum Restore flow to the 'B' S/G because 'B' S/G level is the highest and this will reduce the chance of thermal shocking the S/ Flow should be preferentially restored to the 'B' or 'C' S/G to maintain the TD CA pump steam suppl Restore flow to the 'C' S/G because loop 'C' T-hot is less than loop 'B' T-hot and this will reduce the chance of thermal shocking the S/G. Flow should be preferentially restored to the

"B' or 'C' S/G to maintain the TD CA pump steam suppl Restore flow to the 'D' S/G because the 'D'S/G is higher than

'A' S/G level, which will reduce the risk of thermal shock. Flow should not be restored to the 'B' and 'C' S/Gs because they will be reserved for use later to provide a steam supply for the TD CA pum Ques_191.2.doc

Distracter Analysis: There was a change in this procedure since the last NRC exam. The previous guidance was to select the B and C S/Gs for restoration of flow. Now the guidance is to select the S/G that has the highest apparent level and to preferentially select the B or C S/ Incorrect: T-hot should not be used to determine which S/G should receive flow. It is not a reliable means of determining S/G shell temp in a dry stagnant loo Plausible: The apparent temp of the A loop is the lowest and it may appear that the chance of thermal shock is lessene Correct answer: feed the S/G that has the highest level and preferentially feed B & C S/Gs to maintain steam supply to the TD CA pum Incorrect: C S/G has a lower S/G level than B S/G Plausible: C S/G has a lower T-hot than B S/G Incorrect: No basis for reserving the B & C S/Gs for restoring flow Plausible: There is a high probability that restoring feed to a dry S/G could rupture the tube sheet due to thermal stress. It makes sense to select a S/G that is NOT used to supply steam to the TD CA pump for the initial restoration of the heat sin Level: RO&SRO KA: 2.4.18 (2.7/3.6)

Level of Knowledge: Analysis Lesson Plan Objective: OP-MC-EP-FRH, Ob Source: BANK (7/8/2002)

References:

1. EP/FR-H. 1, Step 7.k (NOTE prior)

Ques_191.2.doc

Bank Question: 19 Answer. D 1 Pt(s) Unit 1 was conducting a plant start up. At 1% power, an instrument malfunction caused an inadvertent reactor trip. Given the following indications:

"* Two rod bottom lights are NOT lit

"* Reactor trip and bypass breakers are open

" IR amps = 2x10-8

"* IR SUR = -0.3 DPM Which one of the following response actions is required? Implement AP/14, (ControlRod Misalignment) and respond to the stuck rod Implement E-0, (Reactor Trip or Safety Injection), and immediately transition to FR-S.2, (Response to Loss of Core Shutdown). Implement E-0, (ReactorTrip or Safety Injection) and immediately transition to FR-S.1, (Response to Nuclear Power Generation/ATWS). Implement E-0, (ReactorTrip or Safety Injection), and then transition to ES-0.1, (Reactor Trip Response).

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Distracter Analysis: A recent change to E-0 has the operator performing the RNO for step 2 - trip the reactor - if 2 rods are stuck out of the cor However, the RNO will evaluate the need to transition to FR-S. 1 based on indications of reactor criticality. Transition is not appropriate unless reactor power is > 5%and not decreasin Incorrect: If above P-11 (1955 psig) must use E- Plausible: This would be the correct answer for a reactor trip below P-1 Incorrect: There is no yellow path because SUPR < -0.2dpm. In addition, F-0 is not in effect at this point in the procedure Plausible: This would be the correct response if SUR > -0.2 dp Incorrect: inappropriate to enter FR-S.1 because the reactor is subcritical and F-0 is not in effect Plausible: If the candidate makes a literal reading of E-0 without knowledge of the ERG background positions on what constitutes a tripped reactor. Some plants enter FR-S.I for two rods stuck ou Ques_195.4.doc

D. Correct:

Level: SRO Only 55.43.(b)6 KA: EAPE 007 EA1.06 (4.4/4.5)

Lesson Plan Objective: EP-EO LPSO 10 Source: BANK Level of knowledge: Memory References:

1. OP-MC-IC-IRE page 35 2. OP-MC-EP-FRS page 15, 17 3. OP-MC-EP-EO pages 19, 27 4. F-0 page 1 5. E-0 page 3 6. AP-14 page 2 Ques_195.4.doc

Bank Question: 24 Answer: D 1 Pt(s) Unit 1 is in Mode 1 conducting a plant startup. The operators have reached 11% R.T.P. when a momentary electrical transient on the 'lA' Main Bus Line occurs resulting in the following conditions:

Bus ITA 1TB 1TC lTD Frequency (Hz) 55 60 55 60 Voltage (VAC) 6410 6900 6410 6900 Which one of the following sequences would occur? NCPs 1A and IC trip because of Under-Frequency while NCPs 1B and ID continue running and a reactor trip does NOT occu NCPs IA and IC trip because of Under-Voltage while NCPs lB and ID continue running and a reactor trip occur All 4 NCPs trip because of Under-Frequency and a reactor trip does NOT occu All 4 NCPs trip because of Under-Frequency and a reactor trip occur ...................................------------------------------------------------------. .

Distracter Analysis: When 2/4 NCP U.F. relays actuate, all 4 NCP supply breakers ope Incorrect: all 4 NCPs trip due to the NC pump monitor system action Plausible: only 2 pumps have a low frequency condition Incorrect: all 4 NCPs trip due to the NC pump monitor system action - the reactor does trip as power is above P-7 (10%)

Plausible: only 2 pumps have a low voltage condition Incorrect : the reactor does trip above P-7 Correct: the reactor does trip above P-7 (10%)

Plausible: all four NCPs trip due to under-frequency on 2/4 NCPs Level: RO&SRO KA: SYS 012 K6.10 (3.3/3.5)

Lesson Plan Objective: OP-MC-IC-IPE Obj. 10 Source: BANK Level of Knowledge: Analysis Reference:

1. OP-MC-IC-IPE page 79 Ques_243.1.doc

Bank Question: 30 Answer. C 1 Pt(s) Unit 1 was operating at 100% power when a crud burst occurred. Given the following events and conditions:

"* 1EMF-48 (Reactor Coolant Hi Rad) Trip 2 alarm

"* 1EMF-18 (Reactor Coolant Filter 1A) Trip 2 alarm Which one of the following actions per AP/1/A/5500/18 (Activity in the Reactor Coolant System) is required to reduce coolant activity due to a crud burst in the NC system? (Assume no clad damage has occurred.) Purge the VCT with nitrogen Place/ensure both mixed bed demineralizers are in service Increase letdown flow Add hydrogen to the reactor coolant

...................................------------------------------------------------------..

Distracter Analysis: Incorrect: Will not correct a high NC activity from a crud burst Plausible: One of the subsequent actions in AP/18 is to purge the VCT to the waste gas system with Hydrogen. In addition, Nitrogen is used to purge the VCT for shutdown. It is likely that a candidate could mix up these purge Incorrect: Do not want to load crud particles into BOTH mixed bed demineralizers Plausible: Mixed bed demins will filter crud particles and remove fission product ionic impurities - this action required for fuel element failure/high fission product activity in AP/1 8 - but not for crud burst Correct: Will increase removal rate of crud particles by increased filtratio Incorrect: Will not remove crud burst particulate activity Plausible: Used to scavenge Oxygen from the NC coolant and thus reduce the corrosion rates and crud production in the RC However, this does not affect crud burst particulates that are already in the NC system coolan Level: SRO ONLY 10CFR50.43 KA: 076 AA2.03 (2.5/3.0)

Ques_307.1.doc. 1

Source: BANK Level of Knowledge: Memory Lesson Plan Objective: OP-MC-CH-PC Obj.12 Reference:

1. AP/1/A/5500/18 page 2 2. OP-MC-CH-PC pages 73 and 75 Ques_307.1.doc. 1

Bank Question: 30 Answer: D 1 Pt(s) Unit I is operating at 100% power. Given the following conditions:

"* Rod control is in 'MANUAL'

"* Control Bank D is at 200 steps If the rods in control bank D start stepping out at 8 steps per minute, which one of the following actions is required at this time? Select Control Bank D on the rod selector switch and manually insert Control Bank D Select "AUTO" on the Bank Select Switch and see if rod motion stops Commence emergency boration Trip the reactor S...........................................................................................

Distracter Analysis: Incorrect: The correct response is to trip the reactor for a rod withdrawal Plausible: this action could stop the rod withdrawal, as the rods in signal should over-ride the rods out signal Incorrect: Trip the reactor is the correct respons Plausible: If the malfimction was in the manual section of the rod control circuitry, this could stop the rods. If the rod control was in auto - then going to manual would be the correct answer. This reverses that thought proces Incorrect: Trip the reactor is the correct response Plausible: This action would be required to insert negative reactivity if the trip did not work Correct answer: Immediate action in step 3 of AP-14 Level: RO&SRO KA: SYS 014 A4.01 (3.3/3.1)

Level of Knowledge: Memory Source: BANK Ques_308.1.do Lesson Plan: OP-MC-AP-14 Obj. 4 References:

1. AP/1/A/5500/14 page 3 2. OP-MC-AP-14 page 4 Ques_308.1.do Bank Question: 31 Answer: A 1 Pt(s) Unit 1 is operating at 50% power. Given the following conditions:

"* Pressurizer pressure is 2235 psig

"* Pressurizer Relief Tank (PRT) pressure is 20 psig

"* PRT temperature is 125 0F

"* PRT level is 81%

"* The PRT is being cooled by spraying from the RMWST

"* A pressurizer code safety valve is suspected of leaking by its seat What temperature would be indicated on the associated safety valve discharge RTD if the code safety were leaking by?

REFERENCES PROVIDED: Steam Tables OF OF OF °F

Distracter Analysis: Correct answer Incorrect: Temp is too low - the correct temp is 260 OF Plausible: If the candidate makes the mistake of not correcting for atmospheric pressure by failing to adding 14.6 psi to the PRT pressure and uses 20 psi Incorrect: Temp is too low - the correct temp is 260 OF Plausible: If the candidate reverses the correction for atmospheric pressure by subtracting 14.6 psi from PRT pressure of 20 psig to get 5 psi Incorrect: Temp is too low - the correct temp is 260 0F Plausible: If the candidate thinks that the discharge temperature will be at the same temperature as the PRT flui Level: RO&SRO KA: SYS 010 K5.01 (3.5/4.0)

Source: BANK Level of Knowledge: Analysis Objective: OP-MC-THF-EB Obj. 8 Reference: OP-MC-THF-EB pages 23-26 Ques_311.1.doc

Bank Question: 35 Answer. D 1 Pt(s) A male worker needs to repack a valve in an area that has the following radiological characteristics:

"* The worker's present exposure is 1800 mrem for the yea "* General area dose rate = 65 mrem/hr

"* Airborne contamination concentration = 20 DAC The job will take 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with a mechanic wearing a full-face respirator. It will only take 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if the mechanic does NOT wear the respirato Which of the following choices for completing this job would maintain the workers exposure within the Station ALARA requirements? The worker should wear the respirator otherwise he will exceed 25% of the DAC limi The worker should NOT wear the respirator because the dose received will exceed neither NRC nor site dose limit The worker should wear the respirator because the total TEDE dose received will be less than if he does not wear on The worker should NOT wear the respirator because the total TEDE dose received will be greater if he wears on Distracter Analysis:

Radiation exposure comparison:

Without respirator DDE = 65 mremihr x 2 hr = 130 mrem From airborne contamination:

CEDE = 20 DAC 2 hr x 2.5 mrem/DAC-hr = 100 mrem TEDE = 130 + 100 = 230 mrem from job Total exposure for year = 1800 + 230 = 2030 mrem With respirator DDE = 65 mrem/hr x 4 hr = 260 mrem CEDE = 0 TEDE = 260 mrem Total exposure for year = 260 + 1800 = 2060 mrem (with respirator) (without respirator)

Ques_353.1.do TEDE = 2060 mrem > 2030 mrem = do NOT use a respirator Incorrect: Will not exceed 25% the DAC limit - this is not how DAC is applied to exposure limits Plausible: 25% DAC is the limit at which an area requires posting as a high airborne contamination are Incorrect: The dose will exceed station admin limits of 2000 mrem Plausible: if the candidate does not know the station admin limit or miscalculates the dose received Incorrect: The exposure will be greater if you wear the respirator Plausible: If the candidate incorrectly computes the exposure - this was the correct answer on the 1997 Catawba NRC exam Correct answer Level: RO&SRO Source: BANK Level of Knowledge: Analysis KA: G2.3.4 (2.5/3.1)

Lesson Plan Objective: RAD-RP Obj 59,60 Reference:

1. GET Rad Worker Training Guide pages 90,91 Ques_353.1.doc. 1

Bank Question: 39 Answer. B 1 Pt(s) Unit 2 is in the process of starting up the reactor in accordance with all controlling procedures. Given the following conditions and events:

2 EMF-3 (CONTAINMENTREFUELING BRjDGEMONITOR) Trip 1 setpoint is 7x10 1 mR/hr and Trip 2 setpoint is 1.5x10 2 mR/h x10 1 1.1x10 2 1.6x102 2.7x102 2EMF 3 (mR/hr)

N-31 (CPS) 1.2x10 4 1.7x10 4 2x10 4 0 N-32 (CPS) 9.2x10 3 1.1x10 4 0 0 N-35 (amps) 9.lxl0"l 1.0x10-lO 1.2x10-0 1.2x10-1'

N-36 (amps) 9.3x10" 1.1x1 0"l° 1.3xl1' 0 ° 1.3x10l°'

If channel N-32 is deenergized due to a SR detector failure at 0210, what is the earliest time (if any) that the containment evacuation alarm will actuate in Unit 2 during the startup? The containment evacuation alarm will not actuate

Distracter Analysis: Incorrect: - both SR high flux trips are active, but the EMF is still below Trip Plausible: - if the candidate thinks that Trip 1 actuation causes the alarm Correct answer Incorrect: Both SR high flux trips are blocked Plausible: - if the candidate reverses the logic that BOTH SR high flux trips must be blocked Incorrect: - alarm actuates at 0210 Plausible: - if candidate thinks that some other action or interlock blocks the alarm Level: RO&SRO KA: W/E 16 EA1.0(2.9/3.3)

Ques_398.1.doc

Lesson Plan Objective: WE-EMF Obj. 3 Source: Bank Level of knowledge: analysis References:

1. OP-MC-WE-EMF page 43 2. OP-MC-IC-ENB pages 21-23 Ques_398.1.doc

Bank Question: 40 Answer: A Bank Question: 40 Answer A 1 Pt(s) Unit 1 was responding to a small break LOCA. Containment pressure reached

3.5 psig. The Subcooling Margin Monitor currently indicated +35 F. Which of the following statements correctly describes the status of subcooling in the core? The core is subcooled by 35 °F The core is superheated by 35 0F The core is superheated by more than 35 0 F due to the effects of adverse containment conditions The core is subcooled by more than 35 IF due to the effects of adverse containment conditions Distracter Analysis: This is a modified question from a previous NRC exam. The original question asked what the core conditions were if ICCM was reading -35 IF. The original answer was "C". Note: the upper limit for measuring superheat is -35 IF. The lower limit is +200 Although the ICCM was designed for ACC inputs, this option was never used because the pressure transmitters were located outside of containment Correct: Incorrect: - subcooling is 35 "F Plausible: - if the candidate reverses the meaning of the indication (i.e. - means subcooled, + means superheated) Incorrect: - subcooling is 35 IF Plausible: - if the candidate reverses the meaning of the indication this was the answer on the NRC exam in 199 Incorrect: - subcooling is 35 OF Plausible: - if the candidate reverses the meaning of the indicatio Level: RO&SRO KA: 017 A4.01 (3.8/4.1)

Lesson Plan Objective: OP-MC-IC-ICM, Obj. 9,10 Source: BANK References: Op-MC-IC-ICM, p. 33-35 Level of Knowledge: Memory Ques_404.1.doc. 1

Bank Question: 40 Answer: D 1 Pt(s) Unit 1 has initiated a liquid radioactive waste release from the Ventilation Unit Condensate Drain Tank (VUCDT) through the RC system. All lineups and authorizations have been properly made in accordance with OP/O/B/6200/35 using the normal path. Two RC pumps are the minimum required under the LWR documen Given the following initial conditions:

3 RC pumps are running

1EMF-44 (CONT VENT DRN TANK OUT) correctly set for trip 1 and trip 2 activity limits

MRIRR = 75 GPM based on boron concentration

No other releases are in progress If the release automatically terminates 40 seconds after initiation, which one of the following conditions could have terminated the release and what is the proper operator response? WM-46 (LIQUID WASTE DISCH VALVE) closing automatically if 1 RC pump tripped, and the release may not be restarted until Chemistry resamples the tan WM-46 closing automatically if 1EMF-44 reached the trip 2 setpoint, the release may be restarted two additional time WP-35 (WMT & VUCDT TO RC CNTRL) closing automatically if 1 RC pump tripped, and the release may not be restarted until Chemistry resamples the tan WP-35 closing automatically if 1EMF-44 reached the trip 2 setpoint, the release may be restarted two additional time ............. .....................-----------------------------------------------------...

Distracter Analysis: Incorrect: - RC pump interlock will not actuate - set at 2 pumps (minimum required on LWR document). WM-46 is isolated and not used anymore as a release pat Plausible: - this was formerly the normal release path Incorrect: - WM-46 receives a closing signal from EMF-44 but this is not the normal path for a release. WM-46 is isolated and not used anymor Plausible: - this was formerly the normal release path Ques_407.1.doc

C. Incorrect: - RC pump interlock will not actuate - set at 2 pumps (minimum required on LWR document).

Plausible: - if the candidate misunderstands the RC pump interlock-this was the correct answer on a prior NRC exam D. Correct answer Level: RO & SRO KA: SYS 68 G2.4.31 (3.3/3.4)

Lesson Plan Objective: WE-WL Obj. 3 Source: Bank; Level of knowledge: comprehension References:

1. OP-MC-WE-WL pages 21, 27, 59 2. OP-MC-WE-EMF page 31 Ques_407.1.doc

Bank Question:41 Answer. B I Pt(s) Unit 1 is operating at 80% power when an electrical transient causes several condensate system pumps to trip. Given the following conditions and events:

Start 10 sec 20 sec 30 sec 40 sec CF pump 1A Suction Pressure (psig) 451 238 232 229 227 CF pump 1B Suction Pressure (psig) 448 227 224 240 238

Hotwell Pumps running 2 2 3 2 1

Condensate Booster Pumps running 2 1 0 2 1 Which one of the following is the earliest time and the reason that BOTH main feedwater pumps will have tripped? seconds, due to 2/3 Condensate Booster Pumps Tripped seconds, due to 3/3 Condensate Booster Pumps Tripped seconds, due to suction pressure seconds, due to 2/3 Condensate Booster Pumps and 2/3 Hotwell Pumps Tripped

Distracter Analysis: This is the 1999 version of the question with slight modifications. It was used in different versions in 2000 and 2001 (Catawba). Incorrect: - CF pump 1A continues to run as suction pressure remains > 230 psig Plausible: - CF pump 1B will trip on low suction pressure Correct answer: - both CF pumps trip when 3/3 condensate booster pumps trip - trip is irrespective of suction pressure Incorrect: - CF pump lA trip criteria met but trip occurred earlier at 20 se Plausible: - if candidate does not know that the CBPs are interlocked with the CF pumps Incorrect: - tripping criteria are met at 20 sec Plausible: - if candidate does not know CF pump trips Level: RO&SRO KA: SYS 056K1.03 (2.6/2.6)

Ques_415.2.doc

Lesson Plan Objective: CF Obj 4 Source: Modified; Ques_415.1, McGuire NRC 2002 Level of knowledge: analysis References:

1. OP-MC-CF-CF page 19 Ques_415.2.doc

Bank Question:4322 Answer. A 1 Pt(s) Unit I has just entered Mode 5 in preparation for refueling. Given the following conditions and events:

"* A lower containment entry is planned for the next shif "* The SRO directs the RO to purge the containment in preparation for the containment entr "* Currently the VP system is secured with all fans off and containment purge and exhaust valves closed Which one of the following describes the proper alignment of the containment purge system? The NORMAL-REFUEL SELECTOR switch is placed in the

"NORM" position and ratio of supply air is 2/1 (Upper/Lower Containment). The NORMAL-REFUEL SELECTOR switch is placed in the

"NORM" position and ratio of supply air is 4/1 (Upper/Lower Containment). The NORMAL-REFUEL SELECTOR switch is placed in the

"REFUEL" position and ratio of supply air is 2/1 (Upper/Lower Containment). The NORMAL-REFUEL SELECTOR switch is placed in the

"REFUEL" position and ratio of supply air is 4/1 (Upper/Lower Containment).

Distracter Analysis: Correct: - this is the proper position for this operatio Incorrect: Air ratio is 2/1 not 4/1 Plausible: Incorrect: - this will over-pressurize the upper containment Incorrect: - this will over-pressurize the upper containmen Plausible: .

Level: RO&SRO KA: G2.3.9 (2.5/3.4)

Lesson Plan Objective: CNT-VP Obj. 2 Ques_432.2.doc

Source: BANK Level of knowledge: comprehension References:

1. OP-MC-CNT-VP pages 19, 21, 27 Ques_432.2.doc

Bank Question: 44 Answer: D 1 Pt(s) Unit 1 is shutdown, Mode 6, in a refueling outage. Given the following conditions:

"* Containment airlock doors are both open

"* A full shift of qualified maintenance personnel are available inside containment

"* The Refueling SRO is in the control room

"* The Fuel Handling Supervisor is inside containment Refueling has been completed and the Fuel Handling Supervisor (who is not a qualified SRO) requests permission to latch all control rods to prepare for the reactor startup. What additional requirements must be met (if any) to proceed with latching rods? Latching rods may proceed at the discretion of the Fuel Handling Superviso Latching rods may not proceed until after containment integrity has been restore Latching control rods may not proceed until after the Refueling SRO arrives inside containment to supervis Latching control rods may not proceed until after the Refueling SRO arrives inside containment and containment integrity has been restore Distracter Analysis: Incorrect: - the Refueling SRO is required to supervise this evolution and containment integrity must be restored Plausible: - if the candidate does not recognize that latching rods is a core alteration or doesn't recognize that this requires containment integrity to be established Incorrect: - the Refueling SRO is required to supervise this evolution Plausible: - if the candidate does not recognize that latching rods is a core alteration Incorrect: - containment integrity must first be established Plausible: - core alterations requires SRO coverage and containment integrity Correct answer Ques_447.1.doc

Level: SRO Only 55.43b(7)

KA: G2.2.26 Level of Knowledge: Memory Lesson Plan Objective: OP-MC-FH-FC, Obj. 2 Source: BANK Referemees: 1. OP-MC-FH-FC, p. 9 Ques_447.1.doc

Bank Question: 45 Answer: B 1 Pt(s) Unit 1 is shutdown in a refueling outage. Given the following events and conditions:

"* The VI system was in a normal lineu "* The VS system was in a normal lineu "* A VI header rupture occur "* 'VI Low' and 'Low Low Pressure' Annunicators alarm

"* The VI system completely depressurize What effect does a total loss of the VI system have on the VS system? VI-820 will auto-close as VI header pressure decreases below 82 psig and the VS air compressor will start automatically to maintain VS header pressur VI-820 will auto-close as VI header pressure decreases below 90 psig and the VS air compressor must be manually started to maintain VS header pressur Check valves in the VI - VS cross-connect line will close to isolate VS system pressure before it drops below 90 psi VS pressure in the Fire Protection Pressurizer Tank will be lost until a VS air compressor can be starte ....................................................------------------------------........

Distracter Analysis: Incorrect: - the VS air compressor does not automatically start to maintain pressure Plausible: - The VI system is safety significant, VI-820 used to close 82 psig but the setpoint was recently changed from 82 psig to 90 psig. There is a separate VS air compressor, which has an automatic startup feature - but is normally in "off' and requires operator action to star Correct answer Incorrect: - there are no check valves in this line Plausible: - this is another possible method to prevent depressurizing the VS header at some plant Incorrect: - the RF system tank is pressurized with VS air - but is maintained isolated from the VI header Plausible: - if the candidate does not know that the RF system air tank is isolated from the VS header.

Ques_451.1.doc

Level: SRO Only KA: APE 000065 AA2.01 (2.9/3.2)

Lesson Plan Objective: SS-VI LPRO 7 Source: Bank; NRC McGuire 1999 Ques_451 Level of Knowledge: comprehension References:

1. OP-MC-SS-VI page 67 Ques_451.1.doc

Bank Question:46 Answer: B 1 Pt(s) If a fire was reported in the McGuire Office Complex (MOC), which one of the following responses is correct by station procedures? Offsite fire departments are responsible for all fire suppression activities at the scene. The Fire Brigade must be held in reserve for station fires inside the protected are Offsite fire departments are responsible for all fire suppression activities at the scene. The Fire Brigade may provide limited support if resources allo The Fire Brigade is responsible for the initial response at the scene. They are required to turn over control of the scene as soon as an offsite fire department arrives and immediately return to the protected are The Fire Brigade is responsible for fire suppression activities at the scene. An offsite fire department may be called to provide support if additional resources are require S........ ......... ....... ----- ..............................................................

Distracter Analysis: Incorrect: - the Fire Brigade is allowed to leave the protected are Plausible: - they have restrictions regarding leaving the sit Correct answer Incorrect: - the Fire Brigade is not responsible for initial response and they are not required to return to the protected are Plausible: - if the candidate thinks that they cannot remain outside the protected are Incorrect: - The Fire Brigade is not primarily responsible to fight fire outside the protected are Plausible: - If the candidate does not understand fire brigade responsibilitie Level: RO&SRO KA: APE 067 K3.02 (2.5/3.3)

Lesson Plan Objective: None Source: Bank; Level of knowledge: memory References:

1. RP/1/A/5700/025 Enclosure 4.1 page 5 Ques_460.1.doc

Bank Question:46 Answer. B 1 Pt(s) Unit 1 is in the process of making a radioactive gaseous waste release from the waste gas decay tank in accordance with OP/0/A/6200/19 (Waste Gas Decay Tank Release). Given the following conditions:

"* Most Restrictive Instantaneous Release Rate (MRIRR) = 35 CFM

"* EMF-50(L) trip 1 setpoint = 1.0E5 CPM

"* EMF-50(L) trip 2 setpoint = 2.0E5 CPM

"* EMF-36(L) is out of service

"* The operators reset IEMF-50(L) whenever procedural direction allows Time 0200 0215 0230 0245 Release rate (CFM) 22 37 32 41 EMF-50(L) (CPM) 1.1E5 2.1E5 2.2E5 2.2E5 What was the earliest time that the operators were required to terminate (and not restart) the gaseous releas cannot release with 1EMF-36(L) out of service must terminate due to exceeding MRIRR must terminate due to 2 nd trip of EMF-50(L) must terminate after 3 rd trip of EMF-50(L)

............... ...................------------------------------------------------------..

Distracter Analysis: Incorrect: - allowed to conduct this release as long as EMF-50(L) is in service Plausible: - 1EMF-36(L) is the plant vent monitor and is normally in the release path. This has an automatic trip associated with i Correct answer - release rate > MRIRR and EMF-50 trips and closes release path Incorrect: - release already stopped at 0215 Plausible: - and this is only the 2 nd trip ofEMF-50 - the operators could reset EMF-50 and restart this release at 0215 if they had not exceeded MRIRR Incorrect: - release already stopped at 0215 due to exceeding allowed release rate Plausible: - This action would be allowed if 1EMF-36(L) was in service Ques_469.1.doc

Level: RO&SRO KA: 073 AI.01 (3.2/3.5)

Source: BANK Level of Knowledge: Analysis Lesson Plan Objective: 5 References:

1.OP-MC-WEW-RGR pages 13.15 Ques_469.1.doc

Bank Question:47 Answer. B 1 Pt(s) Unit 1 is in the process of making a radioactive gaseous waste release from the waste gas decay tank in accordance with OP/0/A/6200/18 (Waste Gas Operation). Given the following conditions:

"* Most Restrictive Instantaneous Release Rate (MRIRR) = 31 CFM

"* Maximum Observed System Release Rate (MOSRR) = 40 CFM

"* EMF-50 (WASTE GAS DISCH)trip 1 setpoint = 2.0E5 CPM

"* EMF-50 trip 2 = 3.0E5 CPM

"* EMF-36 (UNIT VENT GAS) is in service Time 0200 0215 0230 0245 Release rate (CFM) 30 32 41 27 EMF-50 (CPM) 2.8E5 3.2E5 3.1E5 4.2E5 If the operators reset EMF-50 whenever allowed by procedure, what is the earliest time that the operators are required to terminate (and not immediately restart) the gaseous release? ............................................------------------------------------------...

Distracter Analysis: Incorrect: - neither Trip 2 nor MRIRR exceeded at 020 Plausible: If candidate thinks Trip 1 is sufficient to terminat Correct: the release rate (32 CFM) > MRIRR (31 CFM) (most restrictive instantaneous release rate) Incorrect: - exceeded MRIRR at 021 Plausible: - exceeded MOSRR (maximum observed system release rate) - if the candidate thinks he/she can reset EMF-50 once before being required to terminate the release - this is the 2 nd time EMF-50 has reached trip Incorrect: - exceeded MRIRR at 0215 Plausible: - exceeded trip 2 on EMF-50 for the 3 rd time - allowed to reset this trip 2 times before terminating release Level: RO/SRO Ques_479.2.doc

KA: APE 000060 AK2.01(2.6/2.9*)

Lesson Plan Objective: WE-RGR SEQ 5 Source: Bank; Ques_479.1, McGuire NRC 2002 Level of knowledge: analysis References:

1. OP-MC-WE-RGR page 15 Ques_479.2.doc

Bank Question: 51 Answer: B I Pt(s) Unit 2 was in the process of starting up the reactor following a refueling outage. Given the following plant conditions and events:

"* Reactor trip breakers are closed

"* Withdrawal of 'A' control bank has commenced

"* Train A of Wide Range Shutdown Monitoring is inoperable If source range N-32 fails low, which one of the following actions is required? Startup may continue with train B of the Gamma-Metrics Shutdown Monitor System substituting for the failed N-32 source range channel Immediately stop withdrawal of shutdown banks Immediately open the reactor trip breakers Immediately reinsert shutdown banks and open the reactor trip breakers

Distracter Analysis: Incorrect: Cannot substitute gamma metrics for SR channel Plausible: Allowed to substitute SR channels for gamma metrics Correct answer: Required by Tech Specs Incorrect: Not required unless 2 SR channels fail Plausible: This is the immediate action step 1 of AP/16 if BOTH SR channels fail Incorrect: Not a tech spec action Plausible: If candidate does not know tech spec requirements Level: RO/SRO Subject: APE000032 K3.01 (3.2/3.6)

Level of Knowledge: Analysis Source: BANK Ques_512.1.doc

References:

OP-MC-IC-ENB pages 41-43

AP/1A/5500/16 page 2,3 o ITS 3.3.1.5 (Condition 'I')

Ques_512.1.doc

Bank Question: 54 Answer: B I Pt(s) Unit 1 was operating at 100% power when main condenser vacuum dropped suddenly from 25 inches vacuum to 23 inches vacuum. Given the following events and conditions:

"* All 3 condenser steam air ejectors (CSAEs) are in service

"* Both primary and secondary jets are operating

"* The system lineup is in the normal configuration Which one of the following statements correctly describes the cause of this problem? Loss of YM supply to the condenser boot seals CM flow to all CSAE inter-coolers has been obstructed Loss of the main steam supply to the CSAEs A CSAE drain was left open

Distracter Analysis: Incorrect: A recent change no longer runs seals water to the condenser boot seal Plausible: Seal water to the boot seals was originally designed to prevent condenser leakage Correct answer - reduces effectiveness of steam jets and causes vacuum to decreas Incorrect: Main steam does not supply the CSAEs Plausible: There are physical connections for main steam to be the back up supply for aux steam - but these connections are not use Incorrect: CSAE drains are normally open to allow condensate to drain out of the air ejector Plausible: If the drain is left closed, the condensate will build up and flood out the CSAE, which could cause a loss of vacuum. This is the reverse of the distracte Level: RO&SRO KA: SYS 055K3.01 (2.5 / 2.7)

Lesson Plan Objective: MT-ZM SEQ 4, 5, 9 Ques_547.2.doc

Source: Bank Level of knowledge: comprehension References:

1. OP-MC-MT-ZM pages 11, 13,15, 23, 27 Ques_547.2.doc

Bank Question: 61 Answer. B 1 Pt(s) Unit 2 is responding to an ATWS without Safety Injection actuatio Given the following indications:

Pressurizer level begins to go down

The 2A NV pump ammeter indicates running amps are low If all automatic control systems operated normally, which one of the following conditions would cause the 2A NV pump rnning amps to decrease to the lowest value? NV-238 (CHARGING LINE FLOW CONTROL) failed open NV-238 (CHARGING LINE FLOW CONTROL) failed closed NV-241 (SEAL IN.FLOW CONTROL) failed open NV-241 (SEAL INJ FLOW CONTROL) failed closed

..................................------------------------------------------------------..

Distracter Analysis: Incorrect: pump amps and pressurizer level would initially increase Plausible: If the candidate does not understand the charging flow path or does not understand the relationship between pump amps and flo Correct answer: This would block the charging flow path and pumps amps would reduce to minimum as the reduced charging flow was diverted through the NV-150 and NV-151 mini-flow valves Incorrect: this would increase charging flow, which would increase charging pump amps. It would also increase pressurizer level, which would cut back on charging flow and stabilize the pressurizer leve Pump amps would not go to minimum valu Plausible: If the candidate thought that this could divert charging flow or did not understand the relationship between pump amps and flo Incorrect: NV-241 closing would increase backpressure on the charging system, which would divert more charging flow through the NCP seals. However, the drop in pressurizer level would act to open 2NV-238 to compensate for the flow reduction. The overall effect would be to increase pump amps as flow tried to remain the same but at a higher backpressur Plausible: If the candidate does not consider the effect of the PZR level control circuit.

Ques_613.1.doc

Level: SRO Only KA: 000029 EA2.03(2.9*/3.1")

Lesson Plan Objective: OP-MC-PS-NV Obj 6 Source: Bank; Ques_613, McGuire NRC 2000 Level of knowledge: comprehension References:

1. OP-MC-PS-NV pages 37, 115 Ques_613.1.doc

Bank Question: 61 Answer. A 1 Pt(s) Unit 2 was operating at 90% power after a start-up from a refueling outag A pressurizer PORV is found to be leaking and the associated PORV block valve was shut. The PRT was cooled down to the following PRT conditions:

"* PRT Level - 65%

"* PRT Pressure - 9 psig

"* PRT Temperature - 100 0F

"* Lower Containment Temperature - 118 'F What actions are required to restore and maintain normal operating conditions to the PRT for the long term? Vent the PRT to the waste gas syste Vent the PRT to containmen Cool the PRT by pressurizing with nitrogen and initiating spray flow from the NCD Cool the PRT by initiating spray flow through the sparger line from the RWST

-...................-- ................................-----------------------------........

Distracter Analysis: With PRT pressure > 8 psig and temperature <

containment temp, cooling the PRT will only result in the PRT heating back up agai Correct: Incorrect: cannot be performed at power as the vent valve is inside containment and is inaccessible at power Plausible: venting to containment would accomplish the required action Incorrect: Lower Containment temp is 118 'F. Cooling the tank further would only delay the time when it would heat back up again and require further cooling. The PRT can be cooled by pressurizing the PRT with nitrogen - but then spray flow must be initiated from the RMWST not the NCD Plausible: Cooling will reduce pressure temporarily but will not allow the PRT to reheat to its normal limit of 114'F without getting a high-pressure condition (containment temp is 118'F). In addition, recirculating through the NCDT using the NCDT pumps cools the PRT and pressure would be reduced - temporarily.

Ques_617.2.doc

D. Incorrect: Cannot cool the PRT through the sparger line Plausible: can cool the PRT by recircing through the RWST - must pressurize with N2 and recirculate RWST water through the spray and drain connection Level: SRO Only 10CFR55.43(b) 5 KA: SYS 007 A2.02 (2.6/3.2)

Lesson Plan Objective: PS-NC SEQ 20, 24 Source: BANK; NRC McGuire 2002 Ques_61 Level of knowledge: memory References:

1. OP-MC-PS-NC pages 41, 43 2. OP/1/A/6150/004 pages 3 3. OP/1/A/6150/004 Encl 4.1 page 1 Ques_617.2.doc

Bank Question: 68 Answer. C 1 Pt(s) Unit 2 was operating at 100% when a "FLOOR COOLING GLYCOL HIGH TEMPERATURE" annunciator is received. A review of the RTD panel reveals that several ice condenser floor slabs have high temperature indicate Which one of the following statements correctly describes the operational concern raised by this annunciator? High glycol temperatures will cause the in-service glycol compressor to trip causing a loss of NF cooling and excessive ice sublimatio Low floor cooling glycol temperatures could cause cracks in the ice condenser thermal barrie Slab freeze and thaw cycles could result in floor buckling that could interfere with lower door operatio Slab freeze and thaw cycles could cause gaps between the floor and the intermediate deck doors resulting in a bypass flow pat Distracter Analysis: Incorrect: none of the compressors trip on high glycol temperature Plausible: if the candidate does not know the basis for the temperature limits - low glycol temperature can cause a compressor tri Incorrect: not the problem - glycol floor cooling does not effect the thermal barrie Plausible: low temperatures can cause cracks in some systems due to thermal stress Correct Answer: this has been a problem as described in PIP 2 M97-2686 (July 1997) Incorrect: the intermediate deck doors are not physically located near the floor sla Plausible: if the candidate does not know the mechanism for floor bucklin Level: RO&SRO KA: SYS 025k4.02(2.8*/3.0*)

Ques_681.1.doc

Lesson Plan Objective: CNT-NF SEQ 15 Source: Bank; Level of knowledge: memory References:

1. OP-MC-CNT-NF pages 21, 37, 41 Ques_681.1.doc

Bank Question: 77 Answer: D 1 Pt(s) Unit 1 is operating at full power and Unit 2 is refueling. Unit 1 is releasing a minimally decayed waste gas decay tank when a significant packing leak starts on isolation valve 1WG-160, (WG Decay Tank Outlet to Unit Vent Control).

Which one of the following statements correctly describes the automatic actions required to assure that the leak is contained and filtered? EMF-50 (WASTE GASDIScHHIR.D) automatically closes 1WG-160, and 1EMF-41 (AUXBLDG VENTHIRAD) automatically stops the auxiliary building ventilation unfiltered exhaust fan EMF-41 automatically stops the auxiliary building ventilation unfiltered exhaust fans, and 1EMF-36 (UNIT VENTH1RAD)

automatically closes 1WG-16 EMF-36 automatically closes 1WG-160, and 1EMF-35 (UNIT VENTPARTHIRAD) automatically aligns the auxiliary building ventilation filter train EMF-35 automatically stops the auxiliary building ventilation unfiltered exhaust fans, and 1EMF-41 automatically aligns the auxiliary building ventilation filter train Distracter Analysis: Incorrect: EMF-50 will not get to Trip 2 because it is set for the activity being released, and EMF-41 does not automatically stop these fan Plausible: These are valid automatic actions for EMF monitor Incorrect: EMF-41 does not automatically stop these fan Plausible: if the candidates do not recognize that this is not an automatic action for EMF-41 but for 35/3 Incorrect: EMF-35 does not realign ventilation filter Plausible: partially correct - EMF 36-will close 1WG-16 Correct answer: EMF-35 will secure VA fans, and EMF-41 will realign filter trains to contain and filter the release in the Aux Bld Level: RO&SRO KA: SYS 071K1.06(3.1*/3.1)

Lesson Plan Objective: WE-EMF Obj. 2,3 Ques_771.2.doc

Source: Bank Level of knowledge: comprehension References:

1. OP-MC-PSS-VA pages 29,45 2. OP-MC-WE-EMF pages 21 - 27 Ques_771.2.doc

Bank Question: 85 Answer: A I Pt(s) Unit 2 is in Mode 6 with refueling activities in progress. Given the following events and conditions:

"* A containment purge is in progress

"* A fuel element was rammed into the side of the reactor vessel

"* 2EMF-3 (CONTAINMENTREFUELING BRIDGE) and 2EMF-38 (CONTAINMENT PARTICULATE) are in Trip 2 alarm Which one of the following actions should occur, assuming that operators follow the required procedure steps? The containment evacuation alarm sounds automatically. The containment purge stops automaticall The containment evacuation alarm can only be actuated by the control room. The containment purge stops automaticall The containment evacuation alarm sounds automatically. The containment purge is stopped manuall The containment evacuation alarm can only be actuated by the control room. The containment purged is stopped manuall ........... .......................-----------------------------------------------------...

Distracter Analysis: Correct: Containment purge will stop and containment alarm will actuate when the EMF goes into trip Incorrect: a plant page is made by the control roo Plausible: If the candidate confuses the plant page with the containment evacuatio Incorrect: containment purge stops automatically Plausible: candidate knows the alarm, but fails to realize purge will stop automaticall Incorrect: both occur automatically Plausible: candidate does not know the auto actions for the EMFs Level: RO&SRO KA: APE 000036 AA1.01 (3.3/3.8)

Lesson Plan Objective: WE-EMF SEQ 3 Ques_859.2.doc

Source: BANK Level of knowledge: Comprehension References:

1. OP-MC-WE-EMF pages 43, 105 2. OP-MC-CNT-VP page 21 3.AP/2/A/5500/25 page 2-3 4. GET RAD Worker Training Manual page 124 Ques_859.2.doc

Bank Question: 86 Answer. D 1 Pt(s) Unit I has experienced four CRUD bursts this month. Given the following events and conditions:&

IA reactor coolant filter d/p was indicating 40 psi EMF-18 (REACTOR COOLANTFILTER ]A) reads 5 times its normal valu A reactor coolant filter was taken out of servic B reactor coolant filter was placed in servic B reactor coolant filter d/p is 10 psi A mixed bed demineralizer is in servic EMF-48 (REACTOR COOLANT) reads its normal valu Local radiation readings near reactor coolant filter 1B are 3 times norma If the detector for 1EMF-1 9 (REACTOR COOLANT FILTER 1B) fails, what actions (if any) are the operators required to take in response to these conditions? Switch mixed bed demineralizer Shift back to 1A reactor coolant filter until IEMF-19 is returned to servic Place both mixed bed demineralizers in service until 1EMF-19 is returned to servic No action is require S...........................................................................................

Distracter Analysis: Incorrect: No action is require Plausible: If the candidate believes that the filters and demineralizers are train relate Incorrect: No action is require Plausible: If the candidate thought that procedures called for using a filter with an operable RAD monito Incorrect: No action is required. EMF-48 indicates no crud burst Plausible: This action would be required if another crud burst were to occu Correct answer Level: SRO Only KA: APE 076A2.07(2.4/2.7*)

Ques_860.1.doc

Lesson Plan Objective: None Source: BANK Level of knowledge: Comprehension References:

1. OP-MC-WE-EMF pages 43,45 2. OP/1/A/6100/010S window D4 Ques_860.1.doc

Bank Question: 88 Answer: B 1 Pt(s) Unit 2 is operating at 100% power. Given the following events and conditions:

"* Operators started RV pumps 'A' & 'B' due to rising containment temperature "* Containment Upper temperature is 90 'F, decreasin "* Containment Lower temperature is 119 TF, decreasin "* At 0200, a station blackout occurs on both Units I and 2

"* Operators implement the appropriate procedure Which one of the following pumps provides the assured source of cooling water to maintain containment temperature within Tech Spec limits? '2C' RV pump only '2A' RN pump only '2B' RN pump only Either '2A' or '2B' RN pump Distracter Analysis: Incorrect: RN pump 2A supplies. RV pumps could lose power post blackou Plausible: RV pump C could be considered the supply since it will try to start on loss of cooling water pressur Correct: on blackout signal, B train RN supply valves close, but the 42A does not, leaving cooling from the A RN pum Incorrect: RN pump 2A supplies RV post blackou Plausible: if the candidate thinks supply comes from the B RN trai Incorrect: RN pump 2A supplies RV post blackou Plausible: if the candidate does not realize one train of valves close on blackou Level: RO/SRO KA: SYS 076 K3.07 (3.7/3.9)

Lesson Plan Objective: CNT-RV Obj. 13 Source: BANK Level of knowledge: Memory Ques_882.1.doc

References:

1. OP-MC-PSS-RN pages 57, 85 2. OP-MC-CNT-RV page 29 Ques_882.1.doc

Bank Question: 89 Answer. D 1 Pt(s) Unit 1 has experienced a rapture of the RN piping inside containmen Emergency procedures prescribe successful response mechanisms if containment water level remains between 3.5 and 10.5 fee Why is safe plant recovery not assured for a design basis large break LOCA when containment water level exceeds 10.5 feet? Operation of the ND system is compromised by high suction pressur Operation of the NS pumps is endangered by excess debris fouling the containment suction strainer Operation of the hydrogen purge system is compromised by loss of direct access to the containment atmospher Operation of critical ECCS components needed for safe recovery is endangered by submersio Distracter Analysis: Incorrect: 10.5 feet of water will not lift the ND suction relief, or if it did the relief returns to the PR Plausible: High containment level increases ND suction pressur Incorrect: Submergence beyond the reference flood plane will not cause excess debris nor will it transport debris to the suction strainers, which are at the very bottom of the containment sum Debris is generated by impingement of high energy releases against containment SSCs - the design basis will prevent excess debris if containment is maintained free of foreign materia Plausible: Clogged suction strainers could occur if submergence of components was a mechanism, which could lift debris. This is a reason to keep foreign material out of containmen Incorrect: The hydrogen purge system is far above the 10.5 ft flood plane and would not be compromise Plausible: If the hydrogen purge system was submerged, it would fail to operat Correct: The containment flood plane reference is at 10.5 f Submersion beyond this level will expose unqualified components to a hostile environment that they are not qualified fo Level: RO&SRO Ques_891.1.doc

KA: EPE W/E 15 EK2.10 (2.7/3.2)

Lesson Plan Objective: EP-FRZ SEQ 4 Source: BANK Level of knowledge: Memory References:

1. OP-MC-EP-FRZ page 47 Ques_891.1.doc

Bank Question: 89 Answer. A 1 Pt(s) Unit 1 is operating at 100% power when the OAC registers a low spent fuel pool level alarm. Given the following events and conditions:

"* The operators read -2.1 ft SFP level and stable on the main control boar "* The operating KF pump has trippe "* An NLO reports a large leak in the auxiliary building has stoppe "* Normal SFP makeup is not availabl Which one of the following statements correctly describes the corrective action for this event? Implement AP/1/A/5500/41 (Loss ofSpent Fuel Cooling or Level),

find and isolate the leak on the KF discharge pipin Implement AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level)

Find and isolate the leak on the KF suction pipin Implement AP/1/A/5500/40 (Loss of Refueling CanalLevel), and initiate assured makeup due a leak on the discharge pipin Implement AP/1/A/5500/40 (Loss of Refueling CanalLevel), and initiate assured makeup due to a leak on the suction pipin Distracter Analysis: Correct: Incorrect: The leak is on the discharge pipin Plausible: If the candidate confuses the piping immersion depth with the suction pipes, which are at 4 fee Incorrect:

Plausible:. Incorrect: Do not use the assured source, and the leak is on the discharge pipin Plausible:.

Level: SRO Only KA: SYS 033 A2.02(2.8/3.3)

Lesson Plan Objective: FH-KF Obj. 4/5/14 Ques_892.2.doc

Source: BANK Level of knowledge: comprehension References:

1. OP-MC-FH-KF pages 19, 23, 49 Ques_892.2.doc

Bank Question:89 Answer: A 1 Pt(s) Unit 2 is operating at 100 % power. Given the following events and conditions:

"* "B" Train of essential operating equipment (RN, KC, NV) is in servic "* 2A RN train is in operation for surveillance testin "* The RN trains are separated with 2RN-41B (TRAINB TOCNON-ESSHDR ISOL) CLOSE Which one of the following statements correctly describes the potential consequence if 2RN-190B (RN To B KC Hx CoNTRoL) failed to perform its automatic function associated with decreasing B train RN flow? Overheating 2B RN pum B RN strainer goes to 'Backwash' mode due to hi d/ Overheating the running B train KC pump RN-41B will open to restore flow to the heat exchange Distracter Analysis: Correct: Lose mini-flow protection for RN pump 2 Incorrect: flow would decrease thus reducing d/ Plausible: candidate believes that flow through the strainer would increase, causing an auto backwas Incorrect: B train pumps cooled by separate suppl Plausible: candidate believes heat exchanger and pump cooling come from the same plac Incorrect: no auto open signal for RN41 Plausible: candidate feels there is some reason for the stated position of 41B in the setup and guesses it can auto open. Valve closes on blackout signa Level: RO&SRO KA: APE 000062 AA1.06(2.9/2.9)

Lesson Plan Objective: PSS-RN Obj 7 Source: Bank Ques_894.1.doc

Level of knowledge: Comprehension References:

1. OP-MC-PSS-RN pages 23, 41, 73, 85 2. OP-MC-PSS-KC page 39 Ques_894.1.doc

Bank Question: 90 Answer. A 1 Pt(s) Unit 2 has just begun to shutdown (decreasing 2MWe/min) for refuelin Given the following events and conditions:

Pressurizer level is at program level and in 'automatic'.

The controlling pressurizer level transmitter fails at its current outpu * No operator action is take Which one of the following statements correctly describes the system response as plant load is reduced?

A. Charging flow decreases Letdown isolates Pressurizer heaters turn off B. Charging flow increases Pressurizer heaters energize Pressurizer level increase to the trip setpoint C. Charging flow decreases Letdown will not isolate Pressurizer level decreases until the pressurizer is empty D. Charging flow increases Pressurizer heaters will not energize Pressurizer level increases to the trip setpoin Distracter Analysis: As load is reduced, Tave will decrease, Program Pressurizer level will decrease. The system will see the controlling channel maintaining a high level and decrease charging in an effort to reduce leve Actual level will decrease. The backup channel will decrease and at 17%,

letdown will isolate and heaters will de energiz Correct: Incorrect: charging flow will decreas Plausible: candidate believes charging flow will increase in an effort to maintain the higher level Incorrect: letdown will isolate from the bakup channe Plausible: if the candidate believes the low level interlock will not be satisfied only from the controlling channe Incorrect: charging flow will decrease.

Ques_902.1.doc

Plausible: candidate believes charging flow will increase to maintain the higher level Level: RO&SRO KA: APE 028 K3.04 (2.9*/3.0*)

Lesson Plan Objective: PS-ILE Obj. 12 Source: BANK Level of knowledge: Comprehension References:

1. OP-MC-PS-ILE page 33 (Figure 7.2)

Ques_902.1.doc

Bank Question: 90 Answer: C 1 Pt(s) A station emergency battery is supplying DC bus loads without a battery charger online. If the load on the DC bus does not change, which one of the following statements correctly describes a vital battery's discharge rate (amps) as the battery is expended? The discharge rate will be fairly constant until the design battery capacity (amp-hours) is exhausted and then will rapidly decreas The discharge rate will decrease steadily until the design battery capacity is exhauste The discharge rate will increase steadily until the design battery capacity is exhauste The discharge rate will initially decrease until approximately 50% design capacity had been expended and then increase until the battery has been exhauste Distracter Analysis: Incorrect: The discharge rate increase Plausible: This is a typical response for many design systems - If the candidate does not recall that V= hx Incorrect: The discharge rate increase Plausible: If the candidate reverses the effect of decreasing voltage on discharge rat Correct: Incorrect: The discharge rate increase Plausible: If the candidate does not understand battery theor Level: RO&SRO KA: EPE 055 EK1.01 (3.3/3.7)

Lesson Plan Objective: EL-EPL Obj 12/20 Source: BANK Level of knowledge: Memory References:

1. OP-MC-EP-EPL pages 65-67 Ques_906.1.doc

Bank Question: 91 Answer. B I Pt(s) The crew has verified natural circulation in ES-0. 1 (Reactor Trip Response)

based on decreasing core exit thermocouple readings and subcooling > 0 0 Ten minutes later, the operator notes that the thermocouple input to both plasma displays is malfunctionin Which one of the following correctly describes a valid indication that natural circulation is continuing? S/G saturation temperatures are decreasing and REACTOR VESSEL UR LEvEL indication is greater than 100 %. S/G pressures are decreasing and Twotd is at S/G saturation temperatur S/G pressures are decreasing and REACTOR VESSEL DIP indication is greater than 100%. S/G pressure is at saturation pressure for T.ojd and REACTOR VESSEL D/P indication is greater than 100 %.

..........................---------------------------------------------------------------

Distracter Analysis: Incorrect: There is no indication of coupling between primary and secondar Plausible: These are important indications during natural circulatio Correct: Incorrect: RVLIS is unavailable during natural circulatio Plausible: S/G pressure decreases during natural circulation and RVLIS is one of the other plasma display indication Incorrect: RVLIS is unavailable during natural circulatio Plausible: S/G pressure will remain close to saturation for Tcold during natural circulation and RVLIS is one of the other plasma display indication Level: RO&SRO KA: EPE W/E09 EK2.1 (3.2/3.4)

Lesson Plan Objective: EP-EO Obj. 6 Source: BANK Ques_911.1.doc

Level of knowledge: Memory References:

1. OP-MC-EP-EO pages 117, 123 2. ES-0.1 page 15 3. ES-0.1 Enclosure 2 page 31 Ques_911.1.doc

Bank Question: 958 Answer:A 1 Pt(s) Given the following Unit I initial conditions:

"* Reactor power is at 40%

"* Power range NIS indicate:

o 40% (N41), 41% (N42), 41% (N43), 41% (N44)

"* Tave for each loop indicates:

o 5670F ('A'), 5670 F ('B'), 568 °F ('C'), 5680 F ('D')

"* Turbine power is at 481 MWe

"* Rod control is in automatic

"* Group demand counters and DRPI indicate Control Bank 'D' at 140 step Control Bank 'D' Rod L-12 drops fully into the core and the following conditions now exist:

"* Power range NIS indicate:

o 40% (N41), 38% (N42), 42% (N43), 42% (N44)

"* Tave for each loop indicates:

o 5640F ('A'), 564o F ('B'), 5630F ('C'), 5640 F ('D')

"* Turbine power is 478 MWe The effect of the dropped rod on the Rod Control System is that rods will initially: Move out due to the Tave signal providing the largest error signa Move out due to the Power Range NIS input processed by the Mismatch Rate Comparator creating the largest error signa Move in due to Power Range NIS input processed by the Mismatch Rate Comparator creating the largest error signa Move in due to the Tave signal providing the largest error signa Distracter Analysis: Correct: Rods move ou Plausible:. Incorrect:.

Plausible:. Incorrect: Incorrect:

Ques_958.doc

Plausible:

Level: SRO Only KA: 000003.AA2.02 (2.7/2.8)

Lesson Plan Objective: IC-IRX OBJ 5/10 Source: New Level of knowledge: memory References:

1. OP-MC-IC-IRX page 17 Ques_958.doc

Bank Question: 960 Answer. A I Pt(s) Unit 1 is in Mode 6 and fuel reload is complete. Given the following events and conditions:

"* Source range counts have increased in the past 45 minute "* The Source Range Hi Flux at Shutdown alarm has began to alarm intermittently for the past 30 minutes

"* Chemistry has reported boron in the refueling cavity 2650 pp "* Only one Charging Pump is available Which one of the following actions must be implemented under these conditions? Start emergency boration of the NC Block Source Range High Flux Reactor Tri Have IAE adjust Hi Flux at Shutdown setpoints up 1/2 decade Start alternate boration of the NCS Distracter Analysis: Note that in the question stem, the given that the Unit is in Mode 6 with core reload complete infers that the rx vessel head is removed or less than fully tensione Correct: Incorrect:.

Plausible: Incorrect:.

Plausible:. Incorrect:

Plausible:

Level: RO/SRO KA: EAPE 000024 G2.2.30(3.5/3.3)

Lesson Plan Objective: OP-MC-AP-AP38 Obj. 3 Source: New Level of knowledge: comprehension Ques_960.doc

References: AP/38, Step 11 Ques_960.doc

Bank Question: 961 Answer: A I Pt(s) Given the following events and conditions:

The Component Cooling Water System piping has just severed where the Reactor Coolant Pump Component Cooling return combines with the Excess Letdown Heat Exchange Which one of the following statements correctly describes the control room indication(s) that you would see for this failure? NCP Thermal Barrier Outlet valve(s) CLOSE Containment Sump 'A' level increasin Seal Water Return flow increasin Reactor Coolant Pump motor bearing(s) temperature increasin Distracter Analysis: Correct:. Incorrect:.

Plausible: Piping junction is located outside of containmen Incorrect:

Plausible: Hi KC flow due to the break will cause the Thermal Barrier valve to auto-clos Incorrect:

Plausible: High KC flows through the motor bearing coolers will cause temps to decrease Level: RO&SRO KA: APE 000026.AA1.06 (2.9/2.9)

Lesson Plan Objective: (None)

Source: INPO Exam Bank Question History: New Level of knowledge: Comprehension References: KC Flow Diagram 1.

Ques_961.doc

Bank Question: 962 Answer. C 1 Pt(s) Unit 1 was operating at 100%. Given the following events and conditions:

"* The following fans were in operation:

Pipe Tunnel Booster Fans

Return Air Fans

Lower Containment Fans

Upper Containment Fans

"* A LOCA occurs

"* All systems functioned as designed

"* Fan switches selected to low speed Which one of the following describes the alignment of the above containment cooling systems? Pipe Tunnel Booster Fans start and run in low speed Return Air Fans fans star Lower Containment Fans start and run in high speed Upper Containment Fans start and go to "MAX" positio Distracter Analysis: Incorrect: These fans will not continue to operate since S Plausible: These fans are Shunt tripped off during S Incorrect: These fans will not continue to operate since S Plausible: These fans are Shunt tripped off during SI Correct:

Plausible: Incorrect: These fans will not continue to operate since SI Plausible: These fans are Shunt tripped off during S Level: SRO Only KA: EPE 000011 EA2.06 (3.7*/4.0*)

Lesson Plan Objective: CNT-VUL Obj 5 Source: Bank Level of knowledge: memory References:

1. OP-MC-CNT-VUL page 39, 41 Ques_962.doc

..

Bank Question: 963 Answer: D I Pt(s) Unit 2 was at 75% R.T.P. when a loss of condenser vacuum occurre Given the following conditions:

"* Rods are in automatic

"* The steam dump select switch is selected to 'Tave' mode

"* Condenser vacuum is slowly decreasing

"* No component or instrument failures occurred

"* No operator action taken Which one of the following sequences best describes the actuation of the control rods to this event? Control rods move in due to decreased condenser back pressure Control rods move out due to decreased condenser back pressure Control rods move in due to increased condenser back pressure Control rods move out due to increased condenser back pressure Distracter Analysis: Incorrect:

Plausible: Incorrect:

Plausible:. Incorrect:

Plausible: Correct Level: RO/SRO KA: APE 000051 AK1.04 (2.5*/2.5*)

Lesson Plan Objective: OP-MC-STM-IDE Obj. 9 Source: Modified Level of Knowledge: Comprehension Ques_963.doc

References:

1.OP-MC-STM-IDE pages 17-33 (odd only)

Ques_963.doc

Bank Question: 964 Answer. D 1 Pt(s) Unit I was at 100% R.T.P. when the following transient occurs:

A Loss of Offsite Power occurs

A reactor trip occurs due to failure of the turbine to successfully runback to in house loads

Diesel Generator "A" fails to start

Diesel Generator "B" successfully loads bus ETB What is the basis in E-0 (ReactorTrip or Safety Injection) Step 4 RNO for restoration of power to ETA when time allows and continuing with E-O? Minimum shift crews are assumed in the EOPs and manpower is not available to restore power to ET The action to restore power to ETA is directed by the TSC only The actions to restore power to ETA will be addressed after transition to ECA 0.0 (Loss ofAIUA C Power). Only one train of safeguard equipment is required to deal with the emergency conditio Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible Incorrect: Correct:

Level: RO&SRO KA: EAPE 000057 AK3.01 (4.1/4.2)

Lesson Plan Objective: OP-MC-EP-EO Obj 6 Source: New Ques_964.doc

Level of knowledge: memory References:

1. OP-MC-EP-EO pages 27 2. E-0 Reactor Trip or Safety Injection Step 4 Ques_964.doc

Bank Question: 965 Answer. C 1 Pt(s) Unit 1 was operating at 100% power when the following occurred:

"IB" FWPT was manually tripped due to an oil leak

AP/1/A/5500/03 (Load Rejection) has been implemented and completed through step 1 Step 10 has the operator perform the following:

"* Place CF pump in manual

"* Check "CF Header Pressure at least 100 psig above steam header pressure".

"* If CF Header pressure is low the RNO states:

"WHEN S/G levels are greaterthan or equal to program level (and CF valves begin closing), THEN adjust CFPump speed to maintain CFHEADER PRESSURE 100-120psig above "STEAM HEADER PRESSURE".

What is the basis for this step? As S/G levels are restored the FWPT suction flow decreases and FWPT speed control is slow to decrease FWPT spee As S/G levels are restored the FWPT suction flow increases and FWPT speed control is slow to decrease FWPT spee As S/G levels are restored the CF control valves start to close down and FWPT speed control is slow to decrease FWPT spee As S/G levels are restored the CF control valves start to open and FWPT speed control is slow to decrease FWPT spee Distracter Analysis: Incorrect:

Plausible:. Incorrect:.

Plausible:. Correct: Incorrect:.

Plausible:.

Level: RO&SRO Ques_965.doc

KA: APE 000054 AK3.02 (3.4*/3.7*)

Lesson Plan Objective: OP-MC-AP-AP03, Obj. 3 Source: New Level of knowledge: Analysis References:

1. OP-MC-AP-AP03 2. AP/1/A/3300/03 Load Rejection Ques_965.doc

Bank Question: 966 Answer: B 1 Pt(s) Unit 1 is responding to a large-break loss of coolant accident inside containment. Given the following events and conditions:

"* Operators have implemented E-0 (Reactor Trip or Safety Injection), and are implementing Step 22 (Check if NC System INTACT), RN "* The RO has just energized the Hydrogen Igniters

"* Containment hydrogen pressure spikes to 5 psig and then immediately returns to 1.5 psi Which one of the following statements correctly describes the correct procedural flow path? Go to EP/llA/5OOO/E-1 (Loss of Reactoror Secondary Coolant)

and then EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure) Go to E-1 Go to FR- Implement Generic Enclosure 4 (StartHydrogen Recombiners)

Distracter Analysis: Incorrect:

Plausible: Correct:

Plausible: Incorrect:

Level: SRO ONLY KA: SYS 028 A2.03(3.4/4.0)

Lesson Plan Objective: VE SEQ 11 Source: NEW Level of knowledge: Comprehension References:

1. OP-MC-CNT-VE pages 11, 19, 31 Ques_966.doc

Bank Question: 968 Answer."C 1 Pt(s) A fire has occurred in the auxiliary building affecting Unit 1 equipmen Transfer of plant control to the auxiliary shutdown panel is not possible due to the fire. AP/l/A/5500/24 (Loss ofPlant ControlDue to Fire or Sabatoge)

has been implemented. Transfer of plant control for Unit 1 to the SSF is complete. The OSM asks you to determine natural circulatio As SRO located at the SSF what indications could you use to determine natural circulation? Steam Generator Pressure and Core Exit Thermocouples NC Loop W/R Pressure and Steam Generator Pressure Incore Thermocouples and NC Loop W/R Pressure NC Loop Tcold and Pressurizer level

.......................................---------------------------------------------

Distracter Analysis: Incorrect:

Plausible: Incorrect:

Plausible: Correct: Incorrect:.

Plausible:

Level: SRO Only KA: APE 068 AA2.11 (4.3/4.4)

Lesson Plan Objective: OP-MC-CP-AD Obj. 8 Source: New Level of knowledge: Analysis References:

1. OP-MC-CP-AD page 33 Ques_968.doc

Bank Question: 970 Answer. D I Pt(s) A reactor trip and safety injection has occurred and E-0 (Reactor Trip or Safety Injection) is in progress. When Safety Injection termination criteria are met, the crew is directed to stop all but one NV pump in Step 25. After securing one NV Pump, plant conditions are as follows:

"* S/G N/R levels are at 30% and decreasing

"* Pzr Level is stable at 12%

"* Pzr Pressure is going down

"* Subcooling based on Core Exit Thermocouples is 10 degrees

"* FWST level is 185 inches Select the appropriate procedure for these conditions: ES-1.3 (Transfer to Cold Leg Recirc). E-2 (FaultedSIG Isolation). E-i (Loss of Reactor orSecondary Coolant) ES-1.2 (PostLOCA Cooldown and Despressurization).

Distracter Analysis: Incorrect:.

Plausible:. Incorrect:.

Plausible:. Incorrect:

Plausible:. Correct:

Level: SRO ONLY KA: W/E03.EA2.01 (3.4/4.2)

Lesson Plan Objective: OP-MC-EP-El, Obj. #2 Source: NEW Level of knowledge: Analysis References: EP/E-0, Step 26.

Ques_970.doc

Bank Question: 1000 Answer:D 1 Pt(s) Unit 1 has experienced a Loss of All AC Power. EP/1/A/5000/ECA- (Loss of All AC Power) is in effect. The attempted start of the Standby Make-up Pump was unsuccessful. The crew is at Step 24 of ECA 0.0. This step directs the crew to "Depressurizeintact S/Gs to 210psig". Prior to Step 24 of ECA-0.0 there is a NOTE that reads:

"Pzrlevel may be lost and reactorvessel head voiding may occur due to depressurizationof the SIGs. Depressurizationshould not be stopped to prevent these occurrences."

Which one of the following describes the bases for this caution? S/Gs should be depressurized to allow the establishment of natural circulatio Reducing NC pressure and temperature maximizes NCP seal lif S/Gs should be depressurized to allow more CA flow to help with cooldow Reducing NC pressure and temperature minimizes NC inventory loss out of the seal Distracter Analysis: Incorrect:.

Plausible: Incorrect: NCP seals are not the main concern here. Inventory is the concer Plausible: Incorrect: Turbine Driven CA pump is available. This is not the basis of the step. Inventory is the concer Plausible: Correct:.

Level: RO&SRO KA: G 2.4.20 (3.3/4.0)

Lesson Plan Objective: OP-MC-EP-ECA-0 Obj. 4 Source: New Level of knowledge: Memory References:

1. OP-MC-EP-ECA-0 pages 45-47 Ques_1000.doc

Bank Question: 1001 Answer: C I Pt(s) Unit 2 has just tripped as a result of a loss of offsite power. The following plant conditions exist:

"2A" DIG failed to start

"2B" D/G started and loaded bus 2ETB

Four rods fail to fully insert into the cor * Reactor Trip Breaker "2B" is close * Intermediate Range SUR is ZERO

Pressurizer pressure is 2150 psig and slowly decreasing

Containment pressure is .4 psig and slowly increasin EP/2/A/5000/E-0 (ReactorTrip or Safety Injection) Immediate Actions are being performe Based on the above conditions which one of the following would be the correct procedure flow path? GO TO AP/2/A/5500/07 (Loss of ElectricalPower) Stay in E-0 (ReactorTrip or Safety Injection) GO TO EP/2/A/5000/ES-0.1 (Reactor Trip Response) GO TO EP/2/A/5000/FR-S.1 (Response to Nuclear Generation)

Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible: Correct: Incorrect:.

Plausible:

Level: SRO Only KA: G 2.4.4 (3.3/3.7)

Lesson Plan Objective: OP-MC-EP-EO Obj. 3 Ques_1001.doc

Source: New Level of knowledge: Analysis References:

1. OP-MC-EP-EO pages 25-29 2. EP/2/A/5000/E-0 page 3,4 Ques_1001.doc

Bank Question: 1003 Answer C 1 Pt(s) Unit 1 has just experienced a Safety Injection due to a failed open Pressurizer Power Operated Relief Valve (PORV). During the process of implementing EP/t/A/5000/E-0 (ReactorTrip Safety Injection), the STA notices that Train "B" of Phase 'A' did not actuate automatically. Which one of the following describes the communication process that should take place to ensure Phase 'A' Train "B" is actuated? The STA should directly tell the BOP to actuate Train "B" of Phase 'A'. The STA should directly tell the Control Room SRO to instruct the BOP to actuate Train "B" of Phase 'A'. The STA should tell the OSM who will instruct the Control Room SRO to tell the BOP to actuate Train "B" of Phase 'A'. The STA should tell the OSM and Control Room SRO that he/she (the STA) is going to actuate Train "B" of Phase 'A'.

Distracter Analysis: All communication from the STA should go to the OSM, who relays the communication to the Control Room SRO Incorrect:.

Plausible: Incorrect:

Plausible: Correct: Incorrect:.

Plausible:

Level: RO&SRO KA: G 2.4.15 (3.0/3.5)

Lesson Plan Objective: None Source: New Level of knowledge: Memory References:

1. OMP 4-3 page 25 Ques_1003.doc

Bank Question: 1004 Answer. B 1 Pt(s) Unit 1 has experienced a 50% load rejection which resulted in Control Bank

"D" Group 1 being greater than 12 steps misaligned from its associated step counter. Tech Spec 3.1.4 Rod Control Group Alignment Limits states:

"All shutdown and control rods shall be OPERABLE; with all individual indicatedrodpositionerswithinl2 steps of theirgroup step counter demand position".

Which one of the following is the basis for this Tech Spec? Ensure SDM limits are maintained and QPTR is maintained within limit Ensure power distribution and SDM limits are preserve Ensure QPTR is maintained within limits and rod alignments are correc Ensure AID is maintained and limit power distributio Distracter Analysis: Incorrect:.

Plausible: Correct: Incorrect:

Plausible: Incorrect:.

Plausible:

Level: SRO ONLY 55.43b(2)

KA: EAPE 00001AK3.02 (3.2/4.3)

Lesson Plan Objective:OP-MC-IC-IRX Obj. 14 Source: New Level of knowledge: Memory References:

1.T.S. 3.1.4 Bases Ques_1004.doc

Bank Question: 1005 Answer: A 1 Pt(s) During RCCA Movement Testing, a 'ROD CONTROL URGENT FAILURE' annunciator alarm IAE investigates and reports that two control rods are untrippabl Which one of the following describes the Action Statement per Tech Specs? Within one (1) hour verify SDM is within the limits of the COLR AND Be in Mode 3 in six (6) hours Initiate boration to restore SDM to within limits AND Be in Mode 3 in four (4) hour Within one (1) hour verify SDM is within the limits of the COLR OR Be in Mode 4 in six (6) hours Initiate boration to restore SDM to within limits OR Be in Mode 4 in four (4) hours Distracter Analysis: Correct:. Incorrect: Must be in Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Plausible: Incorrect: Tech Spec is Mode 3 Incorrect:. Tech Spec is Mode 3 and Six hours Level: SRO ONLY KA: 00001 SYS2.24 (2.6/3.8)

Lesson Plan Objective: OP-MC-IC-TRX Obj.16 Source: New Level of knowledge: Comprehension References: T.S. Bases 1. OP-MC-Ques_1005.doc

Bank Question: 1006 Answer: D 1 Pt(s) An NLO has been dispatched to recirculate the Ventilation Unit Condensate Drain Tank (VUCDT) in preparation for doing a release. As recirculation is being established, the 1EMF-44 flow meter ruptures and 'lEMF-44 LOSS OF SAMPLE FLOW' annunciator alarm Which one of the following describes the reason for this incident? Both Unit 1 VUCDT pumps were simultaneously starte WL-359 (VUCDTPump Recirc Throttle) was opened too far and too much flow was initiate Radwaste Chemistry failed to open 1WM-222 (VUCDT to RC Disch Hdr). WL-359 was not throttled prior to VUCDT pump star Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible: Correct:

Plausible Correct:.

Level: RO&SRO KA: EAPE 000059 AA1.03 (3.0/2.9)

Lesson Plan Objective: OP-MC-WE-RLR Obj. 5 Source: New Level of knowledge: Memory References:

1. OP-MC-WE-RLR page 17 2. OP/1/A/6500/01A page 16 Ques_1006.doc

Bank Question: 1007 Answer. B 1 Pt(s) A Unit 1 reactor trip results in an autostart of the #1 Turbine Driven Auxiliary Feedwater (#1 TDCA) Pum Which one of the following describes the design feature that provides for initiation of cooling water to the #1 Turbine Driven CA Pump turbine bearing oil cooler? Nuclear Service Water (RN) flow from the RN Essential Header is initiated upon autostart when the RN cooling water supply valve to the #1 TDCA Pump turbine oil cooler automatically open As the #1 TDCA Pump starts and rolls up to speed, Auxiliary Feedwater (CA) from the pump's own discharge piping begins to flow through the #1 TDCA Pump turbine oil cooler and is returned to the pum Component Cooling Water (KC) flow from the KC Essential Header is initiated upon autostart when the KC cooling water supply valve to the #1 TDCA Pump turbine oil cooler automatically open No cooling water from any source is supplied to either the #1 TDCA Pump's turbine or pump bearings. 'Oilers' with level sightglasses are checked by Non-Licensed Operators on their round Distracter Analysis: Incorrect:.

Plausible: RN is the cooling water supply to other ESF pump oil cooler Correct: Incorrect: KC is used to cool some ESF equipment and oil cooler Plausible: Incorrect:..

Plausible: 'Oilers' are found on most ESF pump bearing Level: RO&SRO KA: SYS 061 K4.13 (2.7/2.9)

Lesson Plan Objective: (None)

Source: New Level of knowledge: memory References:

1. MC 1592 - 1.02 (CA Flow Diagram)

Ques_1007.doc

Bank Question: 1008 Answer. B 1 Pt(s) Given the following events and conditions:

"* Unit 1 is operating at 37% powe "* Control Bank 'D' Rods are at 180 steps withdrawn

"* All control systems are in automati "* An electrical fault trips the 'ID' Reactor Coolant Pump Which one of the following describes the prompt effects for 'D' LOOP ONLY on the primary and secondary sides of the plant?

Tave S/G Press DeltaT S/G Level Increase Increase No Effect Decrease Decrease No Effect Decrease Decrease Increase Increase No Effect Increase Decrease No Effect Decrease Increase

Distracter Analysis: 'D' Loop flow quickly decreases and is promptly reversed in that loop (M' decreases). What was T-hot water now is coming from the T-cold region of the core. Tave will promptly decrease, causing 'D' S/G pressure to promptly decreas Because loop flow has been decreased, less Q0 is being removed from that loop and Loop DeltaT will promptly decrease. Because less Q0 is being transferred into 'D' S/G, that S/G level will

'shrink' promptl Incorrect:.

Plausible: Correct:

Plausible: Incorrect: Incorrect:.

Plausible:

Level: RO&SRO KA: SYS 002 A1.07 (3.3/3.5)

Lesson Plan Objective: (none)

Ques_1008.doc

Source: New Level of knowledge: Analysis References: (None)

Ques_1008.doc

Bank Question:1009 Answer: C 1 Pt(s) Given the following events and conditions:

"* Unit 1 has experienced a Large Break LOCA

"* Containment Pressure increased to 5 PSI "* NS system automatically started and reduced containment pressure to less than 0.35 PSI "* NS is secured (NS pumps stopped and NS discharge valves closed).

"* NS has not been 'RESET'.

"* Containment pressure returns to 1.1 PSI Which one of the following describes the response of the NS system to the subsequent containment pressure increase? NS pump discharge valves will open at 0.35 PSIG and the NS pumps will auto start at 0.35 PSI NS pump discharge valves will open at 0.8 PSIG and the NS pumps will auto start at 1.0 PSI NS pump discharge valves will open at 0.35 PSIG and the NS pumps will auto start at 0.8 PSI NS pump discharge valves will open at 0.8 PSIG and the NS pumps will auto start at 3.0 PSI Distracter Analysis: Incorrect:.Pump does not start until .8#

Plausible: Incorrect: Discharge valves open at .35# and Pump starts at .8#

Plausible: Correct: Incorrect:. Discharge valves open at .35# and Pump start at .8#

Plausible:

Level: RO&SRO KA: SYS 006 K1.13 (3.3*/3.6*)

Lesson Plan Objective: OP-MC-ECC-NS Objs. 5,6 Source: New Level of knowledge: Analysis References:

1. OP-MC-ECC-NS page 33 Ques_1009.doc

Bank Question: 1010 Answer: C 1 Pt(s) Given the following events and conditions:&

Unit 1 is approaching Mode 5 to replace a leaking Pressurizer PORV NC Cooldown is in progress

'A' Train ND is in the RHR mod 'A' Train KC is in service at maximum design flow

'A' Train RN is in service

'l A' KC Pump breaker trips (Overcurrent Relay)

Which one of the following describes the effect on the cooldown rate? The Reactor Coolant System heats up, the KC System is unaffecte No effect on the Reactor Coolant System, the KC System begins to heat u The Reactor Coolant System cooldown rate decreases as the KC System heats u The KC System only begins to heat up, but the ND System maintains a stable Reactor Coolant System cooldown rat Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible: Correct: Incorrect:.

Plausible:

Level: RO&SRO KA: EPE 025 AA1.01 (3.4/3.3)

Lesson Plan Objective: OP-MC-PS-ND Ob Source: New Level of knowledge: Analysis References:

1. OP-MC-PS-ND p.43 Ques_1OlO.doc

Bank Question: 1011 Answer. D 1 Pt(s) Unit 1 was responding in E- 1 (Loss of Reactor or Secondary Coolant) to small break LOCA. The crew has just completed Step 8.f when the OATC observes the following parameters:

Given the following parameters at the indicated time:

Parameter Value

"* Stable NCS pressure (psig) 1650

"* Core exit T/C temp ( F)0 586

"* Tave (F) 572

"* ThOr F) 578 0 566

"* Totld ( F)

"* Pressurizer level (%) 28%

"* Containment pressure (psig) "* CA flow to all 4 S/Gs exceeds 450 gpm Which one of the following is the crew's next required action?

REFERENCES PROVIDED:

E-1 Databook Curve 1.10B Steam Tables Remain in E-1, stop NS pumps Transition to ES-1.2 (PostLOCA Cooldown and Despressurization) Transition to ES-1.1 (Safety Injection Termination) Remain in E-1, return to step 7 Distracter Analysis:

The objective of this question is to determine if the candidates can apply the SI termination criteria and assess saturation conditions in the NC syste Use of the Unit 1 Databook curve 1.10B is NECESSARY. Accurate use of the steam tables will lead to an incorrect answer due to a failure to consider the instrument errors involved Ques_1011.doc

From the steam tables:

1500 psig + 14.6 = 1514.6 psia 597 'F = 1510 psia saturation pressure Incorrec Plausible: Incorrect:

Plausible: Incorrect answer: Correct:

Level: SRO Only; 10CFR55.43(b)(5)

KA: WE 02 EK1.2(3.4/3.9)

Lesson Plan Objective: EP - E-1 Objective 2 Source: Bank Modified; Level of knowledge: analysis References:

1. OP-MC- EP E-1 page 16 2. EP/1/A/5000/E-1 page 5 3. Unit 1 Databook Curve 1.1OB 4. Steam Tables Ques_1011.doc

Bank Question: 1012 Answer: D 1 Pt(s) Unit 1 is responding to a small break LOCA using E-1 (Loss of Reactor or Secondary Coolant). Given the following events and conditions:

"* FWST Level indicates 340 inches

"* Containment pressure indicates 1.5 psig

"* Containment Sump Level indicates 1.05 ft

1EMF-41 (A UXBLDG VENTILATION) is in Trip 2 alarm

Aux Building area radiation monitors are in alarm

1EMF-51A and B (CONTAINMENT TINA & B) indicates 25 Rfir

Hydrogen Analyzer indicates 0.7% in containment

NLO's report significant leakage at the seals of the "IA" ND pump The crew determines that a transition to ECA- 1.2 (LOCA Outside Containment)is required. Which one of the following actions of ECA- reduces excessive levels of radiation and guard against personnel exposure? Monitor 1EMF-41 (AUXBLDG VENTILATION) Dispatch NLO to energize Hydrogen Recombiners Secure VA (Aux. Bldg. Ventilation System) to limit airborne contaminatio Identify and isolate the break

Distracter Analysis: The initial conditions provide a LOCA into containment and a leakage path outside of containment. The question is which of the problems take priority? The purpose is not to memorize procedure steps but to answer this from a broader perspectiv Incorrect: Monitoring of rad levels does not minimize exposur Plausible: If the candidate thinks that the abnormal radiation level requires priority actio Incorrect: Energizing the Hydrogen Recombiners does not limit rad exposure in the Aux. Bld Plausible: Small Hydrogen Concentration inside containment exists). Incorrect: This is needed to limit personnel exposur Plausible: If the candidate thinks there is an airborne proble Correct:

Level: RO&SRO Ques_1012.doc

KA: WE 04G3.10 (2.9/3.3)

Lesson Plan Objective: EP-El OBJ 3 Source: Mod; Level of knowledge: comprehension References:

1. OP-MC-EP-E1 page 233,235 2. EP/1/A/5000/ECA- 1.2 Ques_1012.doc

Bank Question: 1013 Answer.:A 1 Pt(s) Given the following conditions and events:

Unit 1 has a very small S/G tube leak on S/G '1C'.

Chemistry reports the leak is .075 gp EMF-73 (Unit I Steam Line '1C' Monitor) is in Trip 1 alarm

1EMF-33 (Unit 1 Condenser Air Ejector) is in Trip 1 alar Which one of the following correctly describes how the flowpath for dilution of the Steam Jet Air Ejector (SJAE) exhaust is changed in response to this leak? No effects on SJAE exhaust alignment for dilution flowpath or EMF(s). SJAE exhaust dilution is swapped to discharge to the Auxiliary Building Ventilation (VA) Filtered Exhaust and diluted with VA to the Unit Ven All Unit 1 and Unit 2 VA Filtered Exhaust Fans (VA-FXF) and all Unit 1 and Unit 2 Unfiltered Exhaust Fans (VA-UXF) are started to dilute the SJAE exhaust to the Unit Vent(s). Unit 2 VA Supply Fans are secured and all Unit 1 and Unit 2 VA is routed to the Unit I Unit Vent to dilute the SJAE exhaus Distracter Analysis: The Unit Vent has is own radiation monitoring system, and no changed is required for SJAE exhaust dilutio Correct:. Incorrect:

Plausible: This is an actual potential alignment for Catawba. If the ability to align the MNS system here existed, this would dilute the exhaus Incorrect:

Plausible:This would increase Unit Vent stack flo Incorrect:.

Plausible: This would increase Unit Vent stack flo Level: SRO ONLY 55.43(b)4 KA: EAPE 037 AA2.07 (3.1/3.6)

Lesson Plan Objective: OP-MC-WE-EMF Obj. 2 Source: New Level of knowledge: Analysis References: OP-MC-WE-EMF p. 19 Ques_1013.doc

Bank Question: 1014 Answer:B 1 Pt(s) Unit 2 has experienced a Steam Generator Tube Rupture on S/G '2B'. The operators are currently in EP/2/A/5000/E-3 (Steam GeneratorTube Rupture). The NC System has been cooled down such that core exit T/Cs are less than required based upon the ruptured S/G pressure. '2B' S/G Narrow Range level indicates 100%. The operators are performing step 20,

"Depressurize the NC System".

Which one of the following operational implications of E-3 has the most effect on primary-to-secondary leak rate and NC System pressure drop while maintaining NC subcooling? Initiate NC Depressurization using maximum available Pzr spray flo Depressurize the NC System by opening one NC Pzr POR Depressurize the NC System by opening all NC Pzr PORV Open 1NV-21A (NV Spray To PZR Isol).

....................................-----------------------------------------------------..

Distracter Analysis: Incorrect:.

Plausible: Because S/G level is > 73%, is is urgent to rapidly reduce NC pressure and leak rate to preclude release to the environment through the S/G PORVs and Safety Correct: Incorrect:

Plausible: Only one PORV is used to control depressurization and maintain control over subcoolin Incorrect:.

Plausible: Because S/G level is > 73%, is is urgent to rapidly reduce NC pressure and leak rate to preclude release to the environment through the S/G PORVs and Safety Level: SRO ONLY 10CFR50.43(b)

KA: EPE 038 EK1.02 (3.9/4.2)

Lesson Plan Objective: OP-MC-EP-E3, Obj. 6 Source: New Level of knowledge: Analysis References:

1. OP-MC-EP-E3, pp. 84,85 Ques_1014.doc

2. EP/2/A/5000/E-3, Step 20 Ques_1014.doc

Bank Question: 1015 Answer: D 1 Pt(s) A BLACKOUT has occurred on 1ETA. D/G 'IA' failed to start due to an 86N relay actuation. On Annunciator Panel lAD-11, 'Battery EVCA Undervoltage' is in alar Per the Annunciator Response Procedure which one of the following addresses the Battery EVCA under voltage condition? Cross tie EVDB to EVD Cross tie EVDC to EVD Swap Battery Charger Connection box to 2EMX Swap Battery Charger Connection box to 2EMX Distracter Analysis: Incorrect:. No effect on the battery and can not cross connect EVDB and EVD Plausible: Incorrect: No effect on batter Plausible: Correct: Incorrect:.No effect on battery is power for Standby Charger EVCS Plausible:

Level: RO&SRO KA: EPE 058 AA2.02 (3.3*/3.6)

Lesson Plan Objective: OP-MC-EL-EPL Obj. 2 Source: New Level of knowledge: Analysis References:

1. Annunciator Response Procedure B4 - Battery EVCA Undervoltage Ques_1O15.doc

Bank Question: 1016 Answer:A I Pt(s) Given the following conditions and events:&

Unit 2 has experienced a large break LOCA inside containmen EP/2/A/5000/E-0 (ReactorTrip or Safety Injection) is complete and the crew has transitioned to EP/2/A/5000/FR-Z. 1 (Response to High ContainmentPressure).

While checking Phase 'B' HVAC equipment in service, the RO notices that the '2A' and '2B' Containment Air Return Fans are not runnin Which one of the following describes the reason the fans are NOT running and actions needed to start the fans? VX SYS CPCS TRAIN A/B INHIBIT status lights are LIT, dispatch operator to local panels to potentiometer to actuate relay VX SYS CPCS TRAIN A/B INHIBIT status lights are LIT, RO starts fans from control room switc VX SYS CPCS TRAIN A/B INHIBIT status lights are DARK, dispatch operator to local panels to potentiometer to actuate relay VX SYS CPCS TRAIN A/B INHIBIT status lights are DARK, dispatch operator to start fans from local panel on 767'

elevatio Distracter Analysis: Correct:. Incorrect: Status light must be dark and can not start without CPCS signal in effect with is indicated by status ligh Plausible: Incorrect:

Plausible: Fan would be running if status light was dar Incorrect:.

Plausible: Fan would be running if status light was dar Level: RO&SRO Ques_1016.doc

KA: SYS 013 K1.03 (3.8/4.1)

Lesson Plan Objective: OP-MC-CNT-VX Ob Source: New Level of knowledge: Analysis References:

1. OP-MC-CNT-VX page 15 2. EP/1/A/5000/FR-Z.1 Ques-1016.doc

Bank Question: 1017 Answer. C 1 Pt(s) Unit 2 is in Mode 6 loading fuel. Given the following plant alarms:

"* 2EMF-3 (ContainmentRefueling Bridge) Trip 2 alar "* 2EMF-4 (SpentFuel BuildingBRDG) Trip 2 alar "* "INCORE INST ROOM SUMP HI LEVEL" annunciator LI Which one of the following procedures should be implemented? API2/A/5500125 (Spent Fuel Damage) EP/2/A/5000/FR-Z.3 (Response to High ContainmentRadiation Level) AP/21A15500140 (Loss of Refueling CanalLevel) AP/21A/5500/18 (High Activity in Reactor Coolant)

Distracter Analysis: Incorrect: Must implement AP-40 Incorrect: Must implement AP-4 Plausible:. Correct These symptoms are an indication of a loss of level in the refueling cana Plausible: Incorrect: Must implement AP-4 Plausible Level: RO&SRO KA: SYS 034 A1.02 (2.9/3.7)

Lesson Plan Objective: OP-MC-FH-FC Obj. 6 Source: Bank; BANK Level of knowledge: comprehension References:

I. OP-MC-FH-FC page-19 Ques_1017.doc

Bank Question: 1018 Answer: D 1 Pt(s) Unit 1 has just experienced a Loss of Offsite Power and the Unit I Turbine has trippe Which one of the following describes the effect this transient has on the Condenser Circulating Water (RC) and Vacuum Priming (ZP) Systems? RC Waterbox Vacuum breaker valves remain closed if all RC pumps trip, to maintain vacuum in the RC pipin RC Waterbox Vacuum breaker valves open automatically if all RC pumps trip, to prevent structural collapse of the RC pipin RC Waterbox Vacuum breaker valves remain closed if all RC pumps trip, to prevent thermal shocking of the RC pipin RC Waterbox Vacuum breaker valves open automatically if all RC pumps trip, to prevent water hammer of the RC pipin Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible: eorret .4&A.) reC O Correct:.

Plausible:

Level: RO&SRO KA: SYS 075 G 2.1.28 (3.2/3.3)

Lesson Plan Objective: OP-MC-MT-RC Obj. 6 Source: New Level of knowledge: Comprehension References:

1. OP-MC-MC-RC page 19 Ques_1O18.doc

Bank Question: 1019 Answer: B 1 Pt(s) Unit 2 has experienced a Steam Generator Tube Rupture (SGTR) on the

'ID' S/G. The crew has completed EP/2/A/5000/E-O (Reactor Tri or Safety Injection) and has entered EP/2/A/5000/E-3 (Steam Generator Tube Rupture). The crew is performing Step 4 in E-3, which directs the RO to close the MSIV and MSIV bypass valves on the RUPTURED S/G. When the CLOSE push button is depressed the valve does not clos Which one of the following describes the RNO step and the subsequent method of cooldown? Close MSIVs and MSIV bypass valves on remaining INTACT S/Gs and use ALL PORVs to cool dow Close MSIVs and MSIV bypass valves on remaining INTACT S/Gs and use INTACT S/G PORVs to cool dow Close MSIVs and MSIV bypass valves on INTACT 'A' and 'B" S/Gs and cool down using PORV on RUPTURED S/ Close MSIVs and MSIV bypass valves on INTACT 'B' and 'C'

S/Gs and cool down using condenser dump valves from RUPTURED S/ ............ ....................--------------------------------------------------..

Distracter Analysis: (Note that "INTACT" and "RUPTURED" are W.O.G. constrained language words and should be Bolded, CAPITALIZED, and underlined.) Incorrect:.

Plausible: Correct:

Plausible: Incorrect: Incorrect:.

Plausible:

Level: RO&SRO KA: SYS 035 AA4.06 (4.5/4.6)

Lesson Plan Objective: OP-MC-EP-E3 Obj. 4 Source: New Ques_1019.doc

Level of knowledge: Comprehension References:

1. OP-MC-EP-E-3 pages 79 Ques_1019.doc

Bank Question: 1020 Answer: D 1 Pt(s) Unit 1 is beginning a cooldown to Mode 6 to enter a refueling outag Which one of the following describes the:&

Tech Spec/SLC cooldown limits on the NC system and Pressurizer Reason why (if any) for the difference Tech Spec cooldown limit for the NC System is 100 0 F/hou SLC cooldown limit for the Pressurizer is 200 0F /hou NC System cooldown rate is more limiting due to the decrease in the nil ductility reference temperature as exposure to neutron fluence in crease Tech Spec cooldown limit for the NC System is 100 0 F/hou SLC cooldown limit for the Pressurizer is 60 0 F /hou Pressurizer cooldown rate is more limiting due to the effects of insure/outsurg Tech Spec cooldown limit for the NC System is 100 0 F /hour SLC cooldown limit for the Pressurizer is 60 0 F /hour Pressurizer cooldown rate is more limiting due to the concern for non ductile failure of the pressurizer meta Tech Spec cooldown limit for the NC System 1000 F/hou SLC cooldown limit for the Pressurizer is 200 0 F/hou NC System cooldown rate is more limiting due to the increase in the nil ductility reference temperature as exposure to neutron fluence increase Distracter Analysis: The limits are 100 degrees/hour cooldown rate for the NC System and 200 degrees/hour for the Pressurizer. The reason for the difference is the exposure of the NC system to neutron embrittlement and subsequent changes in the RTnd Incorrect:.

Plausible: Incorrect:

Plausible: Incorrect: Correct:.

Plausible:

Level: RO&SRO Ques_1020.doc

KA: EPE W/EO8 EK2.1 (3.2/3.4)

Lesson Plan Objective:

Source: New Level of knowledge: Comprehension References:

1. OP-MC 2. SLC 16. . Tech Spec 3. . Tech Spec Basis 3.4.3 Ques_1020.doc

Bank Question: 1021 Answer:D 1 Pt(s) Given the following conditions and events:

"* Unit 1 is at 55% power when a Full load rejection occurs due to the loss of'1A' and '1B' Busline "* Main Turbine Impulse Pressure Channel 2 fails "AS IS".

Which one of the following describes the correct response of the steam dumps to this event? Error signal develops between auctioneered Tave and Tre Steam dumps open to reduce Tave until Tave = Tre Error signal develops between auctioneered Tave and Tref Steam dumps open and Tave reduces to 3 degrees above Tre No error signal developed between auctioneered Tave and Tre Steam dumps do not ope Error signal develops between auctioneered Tave and Tref Steam dumps do not ope ......... ................... ...

..-------------------------------------

Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible: Incorrect: Correct:.

Level: RO&SRO KA: SYS 016 K6.01 (3.3/3.5)

Lesson Plan Objective: OP-MC-STM-IDE Obj. 9 Source: New Level of knowledge: Analysis References:

1. OP-MC-STM-IDE pages 29,31 Ques_1021.doc

Bank Question:972 Answer. C 1 Pt(s) Unit 1 is at 100% power when the controlling Pressurizer Pressure instrument fails HIGH. Per AP/IA/5500/11 (PressurizerPressure Anomalies) the first action the operator must take is place "PZR PRESS CNTRL SELECT" switch to an operable channe What is the basis for this action? This failure causes PORVs INC-32B & 36B to open and a fast response is required to prevent a reactor trip on low pressur This failure causes all the Pressurizer heaters to energize and a fast response is required to prevent a reactor trip on high pressur This failure causes PORV 1NC-34A and reactor coolant pump spray valves to open and a fast response is required to prevent a reactor trip on low pressur This failure causes the reactor coolant pump spray valves to fail closed and the backup heaters to energize and a fast response is required to prevent a reactor trip on high pressur ..............................................----------------------------------------...

Distracter Analysis: Incorrect:.

Plausible:. Incorrect:.

Plausible: Correct: Incorrect:.

Plausible:

Level: SRO Only KA: APE 000027 AA2.15 (3.7/4.0)

Lesson Plan Objective: OP-MC-PS-IPE, Obj. 12 Source: Bank Level of knowledge: Memory References:

1. OP-MC-PS-IPE, p. 35 2. AP/1/A/5500/17, page 2 Ques_972.doc

Bank Question: 973 Answer. C 1 Pt(s) EMF 59 (Equipment Staging Building Ventilation Monitor) is in 'Trip 2'.

Which one of the following describes the actions that occur as a result of the Trip 2 alarm? If VK (EquipmentStaging Building Vent.) is in "Auto" the supply fans will tri If VK is in "On" the supply fans will trip If VK is in "Auto" the exhaust and supply fans will tri If VK is in "On" the exhaust and supply fans will tri Distracter Analysis: Incorrect: The exhaust and supply fans tri Plausible: Incorrect: No effect on syste Plausible:. Correct: Incorrect: No effect on system in ON positio Plausible:

Level: RO&SRO KA: APE 061 AA1.01 (3.6/3.6)

Lesson Plan Objective: OP-MC-WE-EMF, Obj. 3 Source: New Level of knowledge: memory References: OP-MC-WE-EMF, p. 41 Ques_973.doc

Bank Question: 974 Answer:D 1 Pt(s) Unit 2 is operating at 100%, all control system components are in their normal configuration (1-2 position). The controlling pressurizer level channel slowly fails to sixteen percent (16%). Which one of the following describes the effect on the letdown valves? NV-1A, 2NV-457A, 2NV-458A 2NV-35A close, and Pzr heaters energiz NV-iA, 2NV-457A, 2NV-458A, 2NV-35A close, and Pzr heaters de-energiz NV2A, 2NV-457A, 2NV-458A, 2NV-35A close and Pzr heaters energiz NV2A, 2NV-457A, 2NV-458A, 2NV-35A close and Pzr heaters de-energiz ..............................................------------------------------.......

Distracter Analysis: Incorrect:.Channel 1 failure closes NV-2A Plausibl Incorrect:.Channel 1 failure closed NV-2A Plausible:. Incorrect:Heaters de-energize Plausible Correct:.

Level: RO&SRO KA: SYS 004 K4.15 (3.0*/3.4)

Lesson Plan Objective:OP-MC-PS-ILE Obj. 10 Source: New Level of knowledge: memory References:

1. OP-MC-PS-ILE pages 15.23 and 33 2. OP-MC-PS-NV page 23 Ques_974.doc

Bank Question: 975 Answer: A 1 Pt(s) Unit 1 is responding to a LOCA from a trip at full power. Given the following events and conditions:

"* A safety injection occurred at 020 "* FWST level reaches 33 in. at 024 "* S/I, Sequencers, and Containment Spray have been reset for both train "* The 1A NS pump has been successfully swapped to the containment sum "* 1NS-lB (B NS Pump Suct From Cont Sump) will not ope Which one of the following is the reason 1NS-1B will not open? NI-184B (RB Sump to Train B ND & NS) is CLOSED "NS SYS CPCS TRAIN B INHIBIT" light LIT NS-38B (B ND to NS Containment Outside Isol) is CLOSED NS-38B (B ND to NS Containment Outside Isol) is OPEN

...................................-----------------------------------------------------...

Distracter Analysis: Correct:. Incorrect Plausible: Incorrect:.

Plausible:. Incorrect:.

Plausible:.

Level: RO&SRO KA: SYS 026K4.07(3.8*/4.1*)

Lesson Plan Objective: ECC-NS SEQ, Source: New Level of knowledge: comprehension References:

1. OP-MC-ECC-NS 2. OP-MC-PS-ND 3. EP/1/A/5000/ES-1.3 pages 10-11 Ques_975.doc

Bank Question: 976 Answer. B 1 Pt(s) Unit 2 is in an outage. All the fuel is in the spent fuel pool. The spent fuel pool ventilation system is in normal system operation. A fuel shuffle is in progress in the spent fuel pool. During the shuffle a fuel assembly is accidentally damaged and 2EMF-42 (Fuel Building Ventilation Radiation Monitor) goes into Trip Which one of the following describes the effect on spent fuel pool ventilation system as a result of 2EMF-42 in Trip The VF supply and exhaust fans trip and the filter is placed in the filtration mod The VF Filter Train Bypass Damper valve closes and the Filter Train inlet and outlet open The VF system is automatically placed in BYPASS MODE and the discharge dampers open and supply dampers close The VF system is automatically placed in the FUEL HANDLING MODE OF OPERATION and the supply fans tri Distracter Analysis: Incorrect:.

Plausible:. Correct: Incorrect:

Plausible: Incorrect:

Plausible:.

Level: RO&SRO KA: SYS 072 K4.02 (3.2*/3.4*)

Lesson Plan Objective: OP-MC-FH-VF Obj 8 & 9 Source: New Level of knowledge: memory References:

1. OP-MC-FH-VF pages 17 Ques_976.doc

Bank Question: 977 Answer. C 1 Pt(s) Unit 1 is at 100% power when indications are received of a "11B' Reactor Coolant Pump seal malfunction. AP/1/A/5500/08 (Malfunctionof NC Pump) is implemente Which one of the following conditions describes a number two seal failure? # 1 Seal Leak off flow - GOING DOWN NC Pump number 2 Seal Standpipe low level alarm - LIT NCDT input - STABLE, OR GOING DOWN # 1 Seal Leak off flow - GOING UP NC Pump number 2 Seal Standpipe high level alarm - LIT NCDT input - STABLE, OR GOING DOWN # 1 Seal Leak off flow - GOING DOWN NC Pump number 2 Seal Standpipe high level alarm - LIT NCDT input - GOING UP # 1 Seal Leak off flow - GOING UP NC Pump number 2 Seal Standpipe low level alarm - LIT NCDT input - GOING UP

Distracter Analysis: Incorrect:

Plausible: #1 Seal L/O WILL go down Incorrect:

Plausible: High Standpipe level alarm WILL lit Correct: Incorrect:

Plausible: NCDT input WILL go up Level: RO&SRO KA: SYS 003 (3.1/3.0)

Lesson Plan Objective: OP-MC-PS-NCP, Obj. 12 Source: New Level of knowledge: Comprehension References:

1. OP-MC-PS-NCP pages 25-29 2. AP/1/A/5500 Malfunction of NC Pump Ques_977.doc

Bank Question: 978 Answer:B 1 Pt(s) Unit 2 was operating at 75% power when the following indications were observed:

"* S/G Level Deviation Alarms for all S/Gs

"* Feedflow/Steamflow Mismatch Alarms for all S/Gs

"* FWPTs speed going down

"* All Feedwater control switches are in normal position Which one of the following correctly describes the failure affecting the main feedwater pumps? Steam header pressure transmitter fails HIG Steam header pressure transmitter fails LO Feedwater header pressure transmitter fails LO Feedwater pump d/p program fails HIG Distracter Analysis: Incorrect:.

Plausible:. Correct:.

Plausible:. Inorrect: Incorrect:.

Plausible:.

Level: RO&SRO KA: SYS 059 A3.04 (2.5"/2.6*)

Lesson Plan Objective: OP-MC-CF-IWE, Obj. 9 Source: New Level of knowledge: Analysis References:

1. OP-MC-CF-IWE, p.11 Ques_978.doc

Bank Question: 979 Answer:,A 1 Pt(s) The following conditions exist on Unit 2:&

100% power at 1180 MWe The valve positioner for atmospheric dump valve 2SV-30 fail Control room indication shows the valve OPE Which one of the following actions in AP/1A/5500/01 (Steam Leak)

correctly describes the FIRST direction from the SRO that will CLOSE the open atmospheric dump valve? Instruct the RO to select "OFF RESET" on the STEAM DUMP INTL BYPASS switche Instruct RO to depress the 'CLOSE' pushbutton on the atmospheric dump valve control room switc Instruct IAE to energize the P-12 solenoids to close the atmospheric dump valv Dispatch operator to isolate air to the atmospheric dump valv .............-- ......................................------------------------------. - ...

Distracter Analysis: Correct:. Incorrect:. This is the second action Incorrect:

Plausible: Incorrect:. This is the third action of the first two do not wor Level: SRO Only KA: SYS 041 A2.03(2.8/3.1)

Lesson Plan Objective: OP-MC-STM-ISE Obj. 4 Source: New Level of knowledge: Comprehension References:

1. OP-MC-STM-IDE page 57 2. AP/1/A/5500/01 Steam Leak page 5 Ques_979.doc

Bank Question: 980 Answer:'A 1 Pt(s) Unit I is holding at 60% power. Pressurizer level and pressure control are selected to the "3-2" position. Given the following conditions:

A leak develops on the low pressure (process) side of the transmitter for the controlling pressurizer level channe Assuming no operator action, which one of the following statements correctly describes the effect of this failure on the Pressurizer level and pressure control systems? Indicated pressurizer level decreases, NV-238 (ChargingLine Flow Control) opens, actual pressurizer level increases and pressure goes u Indicated pressurizer level increases, NV-238 closes, actual pressurizer level decreases and pressure goes dow Indicated pressurizer level decreases, the pressurizer level master output decreases to increase level and pressure goes u Indicated pressurizer level increases, the pressurizer level master output increases to decrease level, and pressure goes dow Distracter Analysis:

0 Correct:.

Plausible: Incorrect:

Plausible:. Cerzrnete ...

C-O" Incorrect:.

Plausible:.

Level: RO&SRO KA: SYS 011 K3.03 (3.23.7)

Lesson Plan Objective:OP-MC-PS-ILE Obj. 12 Source: New Level of knowledge: Analysis References:

1. OP-MC-PS-ILE pages 27 & 39 Ques_980.doc

Bank Question: 981 Answer. D 1 Pt(s) Unit 1 is operating at 100% power when a leak develops in the tubes of the 1B 1 feedwater heate Which one of the following describes the automatic actions that occur on an

'EMERGENCY HIGH LEVEL' in the 1B1 feedwater heater? Close ALL "B" feedwater heater inlet steam isolations Close "B" bleed steam check valve Close ALL 1 st stage reheater steam vents Close ALL "A" heater normal drain valves Close 1 st stage reheater drain control valves Open ALL "B" heater bleed steam drain valves Open 1st stage purge valve for 1B1 feedwater heater Close ALL "B" feedwater beater inlet steam isolations Close ALL "B" bleed steam check valves Close ALL lt stage reheater steam vents Close ALL "A" heater normal drain valves Close 1 st stage reheater drain control valves Close ALL "B" heater bleed steam drain valves Open 2 nd stage purge valve for IB1 feedwater heater Close "IBI" feedwater heater inlet steam isolation Close "B" bleed steam check valve Open ALL 1 st stage reheater steam vents Open IA1 heater normal drain valve Open ALL 1st stage drain control valves Open All "B" heater bleed steam drain valves Open All 1 st stage "B" heater purge valves Close "IBI" feedwater heater inlet steam isolation valve Close "B" bleed steam check valve Close lA1 heater normal drain valve Close All 1 st stage reheater steam vents Close WA1 1 St stage reheater drain control valve Open "B" heater bleed steam drain valves Open ALL lt stage drain valves

............. ...................------------------------------------------------------..

Distracter Analysis:

Ques_981.doc Incorrect:.

Plausible:. Incorrect:.

Plausible:. Incorrect:

Plausible: Correct:

Level: RO&SRO KA: SYS 039 A3.02 (3.1/3.5)

Lesson Plan Objective: OP-MC-MT-HAW Source: New Level of knowledge: memory References:

1. OP-MC-MT-HAW page 19 Ques_981.doc

Bank Question: 982 Answer:'A 1 Pt(s) Unit 2 has experienced a Steam Line Break inside containment. The "2C" S/G has depressurized to 100 psig and actual W/R level is approximately 10%.

Which one of the following describes the indicated "2C" S/G W/R level response? S/G W/R level reference leg density decreases, actual d/p goes down, indicated S/G level goes u S/G W/R level reference leg density increases, actual d/p goes down, indicated S/G level goes down S/G W/R level reference leg density decreases, actual d/p goes up, indicated S/G level goes down S/G W/R level reference leg density increases, actual d/p goes up, indicated S/G level goes up

Distracter Analysis: Correct:

Plausible: Incorrect:

Plausible:

Level: RO&SRO KA: 000040 K3.06 (3.4/3.9)

Lesson Plan Objective: Op-MC-CF-IFE, Obj. 8,11 Source: New Level of knowledge: Analysis References:

1. Data Book 2. OP-MC-CF-IFE p. 35 Ques_982.doc

Bank Question: 983 Answer. B I Pt(s) "B" Train of essential equipment is in operation on Unit While performing OP/l/A/6350/002 (Diesel Generator)with the "IA'

diesel running in parallel to the grid, the following sequence of events occurs:

"* Load is reduced on the diesel to 200KW in anticipation of opening the EMERGENCY breake "* The RO accidentally OPENS the normal feeder breaker from 1AT Which one of the following describes the system response and the proper procedural response to deal with this situation? Degraded voltage is sensed on lETA and the BLACKOUT sequencer actuates, the crew will use AP/1/5500/07(Loss of Electrical Power). The Diesel Generator Sequencer does not actuate, and the diesel generator assumes the load of the bus. The operator uses OP/1/A/6350/002 to return to normal alignmen Undervoltage is sensed on 1ETA and the BLACKOUT sequencer actuates, the crew will use AP/l/5500/0 The Diesel Generator BLACKOUT sequencer recloses the breaker from 1ATC. Crew reloads the bus using AP/1/A/5500/07, Enclosure 1 (ManualLoadingofEmergency Bus).

Distracter Analysis: Incorrect:

Plausible: Correct:

Plausible: Incorrect: Incorrect:.

Plausible:.

Level: RO&SRO KA: SYS 064 AA4.04 (2.7/3.0)

Ques_983.doc

Lesson Plan OP-MC-DG-EQB Objective:5 Source: New Level of knowledge: Comprehension References:

1. OP-MC-DG-EQB pages 17, 23 Ques_983.doc

Bank Question:985 Answer. A I Pt(s) A work team of Maintenance and R.P. personnel have been dispatched to repack the seals on a pump. The work area around the pump is a 800 mrem/hr High Radiation Area. The R.P. personnel are monitoring the Maintenance crew from a low dose area of 60 mrenvh Which one of the following work teams and estimated repair times would maintain worker exposure ALARA? Maintenance and 3 R.P. personnel (9 workers) working for 20 minutes Maintenance and 2 R.P. personnel (7 workers) working for 30 minutes Maintenance and 2 R.P. personnel (6 workers) working for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Maintenance and 2 RIP. personnel (4 workers) working for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Distracter Analysis: Correct: [6x(800/3)] + [3x(60/3)] = 1660 mrem total dos Incorrect: [5x(800/2)] + [2x(60/2)] = 2060 mrem total dos Plausible: Fewer worker Incorrect: [4x800] + [2x60] = 3320 mrem total dos Plausible: Fewer worker Incorrect: [2x(800x2)] + [2x(60x2)] = 3440 mre Plausible: Fewer worker Level: RO&SRO KA: G2.3.2 (2.5/2.9)

Lesson Plan Objective: RAD-RP Obj. 27,29 Source: NEW; Level of knowledge: comprehension References:

1. OP-MC-RAD-RP page 135 Ques_985.doc

Bank Question: 986 Answer: D 1 Pt(s) Level in the "2C" S/G is slowly increasing due to a failure of the Channel 1 N/R S/G level transmitte Which one of the following describes the correct response of the S/G level control system to this failure? The flow error will initially be greater than the level error. A 1% level error will initially produce a 3% valve position chang The flow error will initially be greater than the level error. A 1% level error will initially produce a 1% valve position chang The level error will initially be greater than the flow error. A 1% level error will initially produce a 1% valve position chang The level error will initially be greater than the flow error. A 1% level error will initially produce a 3% valve position chang Distracter Analysis: Incorrect:. Level error is greater than flow error Plausible: Incorrect: A level error of 1% produces a 3% vzalve change Plausible: Incorrect: A level error of 1% produces a 3% v alve change Plausible: Correct:.

Level: RO&SRO KA: SYS 059 K3.03 (3.5/3.7)

Lesson Plan Objective: OP-MC-CF-WFE Objs.6,10 Source: New Level of knowledge: Comprehension References:

1. OP-MC-CF-IFE pages 23,47 Ques_986.doc

Bank Question: 987 Answer: B 1 Pt(s) The Diesel Generator DC Control Power Breaker for the "lA" D/G has failed and must be replaced by IA Which one of the following components is affected by this failure? DIG "IA" Diesel Fuel Oil Booster Pump D/G "IA" Speed Switches D/G "IA" Battery Charger lEDGA D/G "IA" Sump Pump Control Power

.............. ....................------------------------------------------------------.

Distracter Analysis: Incorrect:.This pump has its own DC breaker Plausible: Correct: Incorrect:This is an AC load Plausible Incorrect:. This is an AC load Plausible:

Level: RO&SRO KA: SYS 055 K3.O1 (3.7*/4.1)

Lesson Plan Objective: OP-MC-DG-EPQ Obj. 3 Source: New Level of knowledge: memory References:

1. OP-MC-DG-EPQ pages 13,19 Ques_987.doc

Bank Question: 988 Answer. D 1 Pt(s) PCB 7 and PCB 8 are part of the 230 KV switchyard. Which one of the following describes the RO's indication he/she has from the control room to monitor breaker position? Both PCB 7 and PCB 8 are on the OAC and Main Control Board PCB 7 and PCB 8 are ONLY available on the OAC Main Control Board indication ONLY for PCB 7 and OAC ONLY for PCB 8 Main Control Board and OAC indication for PCB 8 and OAC indication only for PCB 7 Distracter Analysis: Incorrect:. No control board indication for PCB 7 Plausible: Incorrect: PCB 8 has a control board indication Plausible: Incorrect: PCB has no control board indication; PCB 8 is also on the control board Plausible Correct:.

Level: RO&SRO KA: SYS 062 A4.04 (2.6/2.7)

Lesson Plan Objective: OP-MC-EL-EP Obj 8 Source: New Level of knowledge: memory References:

1. OP-MC-EP-EPL pages27,28 Ques_988.doc

Bank Question: 989 Answer:D 1 Pt(s) There has been a fire in the Unit 2 turbine building basement. The "A' Main Fire Pump auto-started due to a low fire header pressure signal. The fire brigade has extinguished the fire after forty-five minute "* "IA" and "IB" Jockey Pumps are 'OFF'

"* "A" Main Fire Pump is running

"* "B" and "C" Main Fire Pumps are 'OFF'

Which one of the following describes the procedural process of recovering from a low fire header pressure and returning the Main Fire and Jockey pumps to normal alignment? Stop the "A" Main Fire Pump, place the Jockey pump to be started in "MAN", and place the other Jockey pump in

"START". Stop the "A" Main Fire Pump, place the Jockey pump to be started in "START", and place the other Jockey pump in

"6MAN". Place the Jockey pump to be started in "START", the other Jockey pump in "MAN, and stop the "A" Main Fire Pum Place the Jockey Pump to be started in "MAN", "START" the Jockey Pump selected to "MAN", and stop the "A" Main Fire Pum ..........................................................................................

Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible: Correct:.

Level: RO&SRO KA: SYS 086 A2.02 (3.0/3.3)

Lesson Plan Objective:

Source: New Level of knowledge: memory References: OP/1/A/6400/002A Encl. 4.1 page 6 Ques_989.doc

Bank Question: 992 Answer. B 1 Pt(s) Which one of the following describes the automatic operation of 1KC-122 (KC Surge Tank Vent Valve)? EMF-46A (B) in Trip 1 alarm will cause the vent to close; when the alarm clears the valve will utomatically re-open (the

"OPEN" position seals in). EMF-46A (B) in Trip 2 alarm will cause the vent to close; when the alarm clears the valve will automatically re-open (the

"OPEN" position seals in). IEMF-46A (B) in Trip 1 alarm will cause the vent to close and the "CLOSE" positions seals in; the valve must be locally re opene EMF-46A (B) in Trip 2 alarm will cause the vent to close and the "CLOSE" positions seals in; the valve must be locally re opene Distracter Analysis: Incorrect:. Valve does not actuate on trip 1 Plausible: Correct: Incorrect: Valve does not actuate on trip 1 Incorrect:.Valve will re-open once signal has cleared Plausible:

Level: RO&SRO KA: SYS 008 K4.02 (2.9/2.7)

Lesson Plan Objective: OP-MC-PSS-KC Obj 10 Source: New Level of knowledge: memory References:

1. OP-MC-PSS-KC page 21 2. OP-MC-WE-EMF page 33 Ques.992.doc

Bank Question: 993 Answer. A 1 Pt(s) Which one of the following describes the power supply alignment during a BLACKOUT or SAFETY INJECTION for the following containment cooling fans? On a BLACKOUT the VU Fans (on the affected bus) start, on a SAFETY INJECTION the VU Fans (on the affected bus) are shunt tripped OF On a BLACKOUT the VL Fans (on the affected bus) are shunt tripped OFF, on a SAFETY INJECTION the VL Fans (on the affected bus) start and run in low spee On a BLACKOUT the VR Fans (on the affected bus) swap to EMERGENCY power, on a SAFETY INJECTION the VR Fans (on the affected bus) are shunt tripped OF On a BLACKOUT the RA Fans (on the affected bus) are shunt tripped OFF, on a SAFETY INJECTION the RA Fans (on the affected bus) star Distracter Analysis: Correct:. Incorrect: The VL fans start on affected bus, are shunt tripped off and swap to emergency power on an SI Plausible: Incorrect: The VR fans start on affected bus, and swap to emergency power on an SI Incorrect:. The RA fans start on affected bus on Blackout, and are shunt tripped off on S Plausible:

Level: RO&SRO KA: SYS 022 K2.01 (3.0*/3.1)

Lesson Plan Objective: OP-MC-CNT-VUL Obj. 5 Source: New Level of knowledge: memory References:

1. OP-MC-CNT-VUL pages 41 Ques_993.doc

Bank Question: 994 Answer. D 1 Pt(s) During the delivery of chlorine gas cylinders on site a cylinder fell from the truck and ruptured. All control room VC intakes closed except 1VC-9A and 1VC-1 1B which were mechanically bound and failed to close completel Chlorine gas has entered the control room. AP/1/A/5500/17 (Loss of Control Room) has been implemented on both Unit As SRO, which one of the following describes your instructions (per AP/17)? Direct one RO to the reactor trip breakers and immediately trip the reactor. Direct one operator to the front standard of the main turbine and standb Direct one RO to the reactor trip breakers and standby. Direct one operator to the front standard of the main turbine and immediately trip the turbin Direct one RO to the reactor trip breakers and immediately trip the reactor. Direct one operator to the front standard of the main turbine and immediately trip the turbin Direct one RO to the reactor trip breakers and standby. Direct one operator to the front standard of the main turbine and standb ................................----------------------------------------------.......

Distracter Analysis: Incorrect:. Do not trip reactor immediatel Plausible: Incorrect: Do not trip turbine immediately Plausible: Incorrect: Do not trip reactor and turbine until direct later in procedur Correct:.

Level: RO&SRO KA: G 2.1.8 (3.8/3.6)

Lesson Plan Objective: None Source: New Ques_994.doc

Level of knowledge: Memory References:

1. OP-MC-PSS-VC page 15 2. AP/2/A/5500/17 page 3 Ques_994.doc

Bank Question: 995 Answer: D 1 Pt(s) Unit 2 is operating at 100% power with all rods out. Given the following events and conditions:

"* Control Rod 'H-8' drops into the cor "* AP/2/A/5500/14 (Rod ControlMalfunction), Enclosure 1 (Response to DroppedRod) has being implemente "* Control Rod 'H-8' has been pulled 150 steps off the bottom of the cor "* Rod 'K-14' drops into the cor Which one of the following statements correctly describes the operator's response to this event? Continue withdrawal of rod 'H-8'. GO TO AP/l/A/5500/38 (Emergency Boration) Return to Step one (1) of AP/1/A/5500/1 Trip the reactor and GO TO E-0 (Reactor Trip/Safety Injection)

Distracter Analysis: Incorrec Plausible: By definition, a rod misaligned by more than 50 steps is considered 'dropped'. Incorrect:

Plausible: (See Above) Incorrect:

Plausible: (See Above) Correct:

Level: SRO ONLY KA: APE 005 AA2.03 (3.5/4.4)

Lesson Plan Objective:

Source: New Level of knowledge: Memory References:

1. OP-MN-AP-14 background ENC. 2 step 5 page 32 2. AP-14 page 19 2. OP-MN-RT-RB page 27 Ques_995.doc

Bank Question: 996 Answer: D 1 Pt(s) Unit 1 has experienced a 50% runback due to the loss of Busline I AP/1/A/5500/03 Load Rejection has been implemented and the Immediate Actions have been completed. Based on the indicated Power Mismatch (PMM) and Temperature Mismatch (TMM), which one of the following correctly describes rod movement? PMM = 0, TMM = + Rods OUT at 40 steps per minute PMM = -4, TMM = Rods IN at 40 steps per minute PMM = +3, TMM = + Rods OUT at 72 steps per minute PMM = +1.5, TMM = + Rods IN at 8 steps per minute

..................................-----------------------------------------------------...

Distracter Analysis: (Note that both PMM and TMM are measured in degrees.) Incorrect:. Rods step IN Plausible: Incorrect: Rods step OUT Plausible: Incorrect: Rods step IN Correct:.

Level: RO&SRO KA: G 2.2.33 (2.5/2.9)

Lesson Plan Objective: OP-MC-IC-IRX Obj. 5,6,7,8 Source: New Level of knowledge: Analysis References:

1. OP-MC-IC-IRX pages 27,29,31 Ques_996.doc

Bank Question: 997 Answer: B 1 Pt(s) During the process of implementing a Temporary Modification (TM)

affected drawings are notated to refer the Operators to the appropriate TM packag Which one of the following describes the process for notating a Temporarily Modified on the drawing in the ontrol room? Flow diagrams and electrical one line drawings MUST always be red-marked to reflect the temporary modificatio Flow diagrams and electrical one line drawings should NOT be red-marked to reflect the temporary modificatio Flow diagrams MUST be red-marked to reflect the temporary modification, electrical one line drawings should NOT be red marked to reflect the temporary modificatio Flow diagrams should NOT be red-marked to reflect the temporary modification, electrical one line drawings MUST be red marked to reflect the temporary modificatio Distracter Analysis: Flow diagrams and electrical one line drawings should NOT be red marked to reflect the temporary modification due to the temporary nature of such change Incorrect:.

Plausible: Correct: Incorrect:

Plausible: Incorrect:.

Plausible:

Level: RO&SRO KA: G 2.2.11 (2.5/3.4)

Lesson Plan Objective:

Source: New Level of knowledge: memory References:

1. OMP 10-2, page 4 Ques_997.doc

Bank Question: 998 Answer:D 1 Pt(s) Which one of the following would require the use of an R&R for managing configuration control? Troubleshooting activities and needed to meet the intent of a procedure and is within the original system desig Long term system alignments and needed to meet the intent of a procedure and is within the original system design An alternate component or alignment which it NOT within the original design and intent of the system is desire The use of an alternate component or alignment is needed to meet the intent of a procedure and is within the original system desig Distracter Analysis: Incorrect:.

Plausible: Incorrect:

Plausible: Correct:

Plausible: Correct:.

Level: SRO ONLY KA: G 2.2.14 (2.1/3.0)

Lesson Plan Objective:

Source: New Level of knowledge: Memory References:

1. OMP-7-1, page 7 Ques_998.doc

Bank Question: 999 Answer: B 1 Pt(s) Which one of the following must the Control Room SRO ensure prior to authorizing a Liquid Waste Release from the Waster Monitor Tank (WMT)? A source check has been performed on EMF-4 The required number of RC pumps is in operatio The "Recommended Release Rate" is equal to the "Allowable Release Rate". The "Expected CPM of EMF 44" and the "EMF 44 Trip 1 Setpoint" are less than the "EMF 44 Trip 2 Setpoint"

Distracter Analysis: Incorrect:. EMF 49 is used for WMT releases Plausible: Correct: Incorrect: Recommended release rate must be less than allowable release rate Incorrect:.EMF 49 is utilized Plausible:

Level: SRO Only KA: G 2.3.6 (2.1/3.1)

Lesson Plan Objective: OP-MC-WE-RLR Obj. 3 Source: New Level of knowledge: Memory References:

1. OP-MC-WE-RLR page 13 Ques_999.doc

Bank Question: 991 Answer: A 1 Pt(s) Which one of the following is a correct list of SAFTETY LIMITS? Thermal Power, RCS Highest Loop Tave and Pressurizer Pressur Thermal Power, AFD, Pressurizer Pressur AFD, QPTR and Reactor Powe Li ear Heat Generation Rate, Thermal Power and QPT S....... ........ ...... ----- ....................................---............................

Distracter Analysis: Correct:.

Plausible: Incorrect:

Plausible: Incorrect: Incorrect:.

Plausible:

Level: SRO Only KA: G 2.1.10 (2.2/3.9)

Lesson Plan Objective: (None)

Source: New Level of knowledge: memory References:

1. Tech Spec 2.1.1 Ques_991.doc

Bank Question: 990 Answer: C 1 Pt(s) Which one of the following is the power supply to the "2B" Safety Injection Pump? lETB EMXB ETB EMXB Distracter Analysis: Incorrect: Unit 1 power supply Plausible: Incorrect: Unit 1 power supply Plausible: Correct: Incorrect:.Load center does not supply power to NI pump Plausible:

Level: RO&SRO KA: SYS 013 K2.01 (3.6/3.8)

Objective: Op-MC-ECC-NI, Obj. 5 Source: New Level of knowledge: memory References: OP-MC-ECC-NI, p. 13 Ques_990.doc

IR 05000370/2002302

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2002 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 30(0) Security Operator Exams 301(0) 302(0) Emergency Planning Other

IR 05000370/2002302

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