ML082200171
| ML082200171 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/07/2008 |
| From: | - No Known Affiliation |
| To: | NRC/RGN-II |
| References | |
| 50-400/08-301 50-400/08-301 | |
| Download: ML082200171 (137) | |
Text
Draft Submittal (Pink Paper)
~~s. 2iJo8'-301
(,Ur;HEII £MM A])M,~~7C000 3/21IZOJB Reactor Operator Written Exam
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 1. 001 A3.04 002IBANKlWCNOC 2007 NRC/HIGHER//ROfHARRIS/3/2008/NO Initial conditions:
The plant is at 80% Reactor power and ramping UP at 1/2% per minute.
Tave and Tref are matched.
Rod Control is in AUTOMATIC.
Current conditions:
ONE (1) Control Bank D Rod has dropped and is now stuck at 170 steps.
All Other Control Bank D Rods are indicating 216 Steps.
Assuming NO action is taken, which ONE of the following describes the DEMAND for rod motion, and the effect on Axial Flux Difference (AFD) for the channel NEAREST the control rod problem?
A.
B~
C.
D.
ROD MOTION Outward Outward Inward Inward AFD EFFECT Less Negative More Negative Less Negative More Negative B is correct. With a dropped/slipped control rod during a power escalation, rate of change of turbine load vs. reactor power will tum towards the negative, requiring outward demand. (Turbine load rate of change would remain constant while reactor power will drop or slow rate of increase) Also, Tave will lower because of the dropped/slipped rod.
Rod slip/drop will cause flux to shift toward the bottom detector in a power range NI, making AFD go more negative.
A is incorrect because AFD will become more negative.
To make positive, rod would have to be withdrawn or boration would be performed.
C is incorrect because rod motion would be outward, and AFD would be more negative.
o is incorrect because rod motion would be outward.
The KA topic is met because discussion ofAFD in one quadrant (1 PRNI detector), and 1 rod dropping is related to QPTR, which is radial imbalance.
Though AFD is the term used, it is used in terms of 1 indicator, not in terms ofAFD due to a rod group position.
Saturday, January 05, 2008 12:00:22 PM 1
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to monitor automatic operation of the CROS, including: Radial imbalance Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
29 2
2 3.5 ROD CS May also need ref description of AFD trend Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
ROD CS-9 Actual item selected was Byron 2001 but item has also been used for Wolf Creek 2007 (Bank 41860 selected) 55.41.7
(
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 312008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
WCNOC 2007 NRC HARRIS NO Saturday, January 05, 2008 12:00:22 PM 2
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
,I"
- 2. 002 A2.02 001INEW//HIGHER//ROIHARRIS/3/2008INO Given the following:
The plant is at 100% power.
An RCS leak has developed.
The crew is performing AOP-016, Excessive RCS Leakage.
Current conditions:
Charging flow is at maximum.
One 45 GPM Letdown Orifice is in service.
RCS pressure is 2050 psig and lowering at 10 psig every 10 seconds.
PZR level is 35% and lowering by 2% every 10 seconds Which ONE of the following describes the effect on the OT Delta T setpoint, and the action required for the current plant conditions?
A. OT Delta T setpoint is rising; Trip the reactor and enter Path-1 and initiate SI.
B. OT Delta T setpoint is rising; Isolate Letdown and align VCT Makeup to the RWST.
C~ OT Delta T setpoint is lowering; Trip the reactor and enter Path-1 and initiate SI.
D. OT Delta T setpoint is lowering; Isolate Letdown and align VCT Makeup to the RWST.
C is correct. OT Delta T setpoint is reduced with lowering pressure. Rate ofpressure and level decrease determines need to trip the reactor. Based on AOP-016 guidance, conditions would not allow maintenance of VCT or PZR level.
A is incorrect but plausible if candidate believes OT Delta T setpoint increases as pressure lowers. Action is correct for leak rate.
B is incorrect but plausible if candidate believes OT Delta T setpoint increases as pressure lowers and fails to recognize that the leak rate exceeds makeup capability even once letdown is isolated.
C is incorrect but plausible since it would be correct if the leak rate was less than capability to makeup.
Saturday, January 05,200812:00:22 PM 3
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of coolant pressure Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
30 2
2 4.2 AOP-016 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday. January 05,200812:00:22 PM 4
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 3. 003 AKl.l1 001IBANK/IHIGHER/IROIHARRIS/3/2008/NO The plant is operating at 100% power when one control rod drops fully into the core causing Power Range N-41 to read lower than the other power range channels.
Which ONE of the following is the expected QPTR response over the next two to six hours and why?
A'! QPTR will increase due to the buildup of Xenon in the dropped rod's fuel assembly.
B. QPTR will decrease due to the buildup Xenon in the dropped rod's fuel assembly.
- c. QPTR will increase due to the change in temperature in the dropped rod's fuel assembly.
D. QPTR will decrease due to the change in temperature in the dropped rod's fuel assembly.
A is correct. Dropped rod will see xenon buildup over time, resulting in QPTR being higher.
B is incorrect because QPTR is higher.
C is incorrect because increased temperature has minimal effect (FTC).
D is incorrect for same reason as C but also because QPTR is higher.
Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: Long-range effects of core quadrant power tilt Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
57 1
2 2.5 Dropped rod analysis (Need Ref)
Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
McGuire 2005 55.41 Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:23 PM 5
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 4. 003 K5.03 003IBANKlIHIGHERlIROlHARRIS/3/2008INO Given the following:
A plant startup is in progress.
Reactor power is 20%.
"B" RCP trips.
Which ONE of the following describes the effect on the reactor and "B" loop Tave?
A'! Reactor remains at power; Loop "B" Tave lowers due to Thot lowering to the value of Tcold.
B. Reactor remains at power; Loop "B" Tave rises due to the decreased flow and increased transit time in the "B" loop.
C. Reactor automatically trips; Loop "B" Tave lowers due to Thot lowering to the value of Tcold.
D. Reactor automatically trips; Loop "B" Tave rises due to the decreased flow and increased transit time in the "B" loop.
A is correct.
Tave in the loop with the tripped pump will drop due to no heat input, and reverse flow causing the loop to go to Tcold. In this case, a reactor trip does not occur, because power is above P-7, although less than P-8.
B is incorrect because Tave lowers.
Credible because Tave would rise if natural circulation was setting up on loss of all RCPs.
C and 0 are incorrect because power is below P-8. If power was> P-8, C would be correct.
C uses same reason as correct answer, therefore plausible. 0 is provides same plausible reason as B, which is an effect that will happen if 3 RCPs trip.
The KA is matched because the test item requires knowledge of the effect of a tripped RCP on loop temperature, and also tests the reason why that effect exists.
Saturday, January 05, 2008 12:00:23 PM 6
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the operational implications of the following concepts as they apply to the RCPS: Effects of RCP shutdown on T-ave., including the reason for the unreliability of T-ave. in the shutdown loop Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
1 2
1 3.1 RPS text, Also need T&AA for RCP Trip Event (Single Loop loss of flow)
Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
RCS, Obj. 9 55.41.7 Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:23 PM 7
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 5. 004 K5.19 001INEW//HIGHERJIRO/HARRIS/3/2008INO Which ONE of the following evolutions, by itself, will RAISE Shutdown Margin?
A. Lowering the setpoint of the Letdown Temperature Control Valve, TCV-144, by 10 of.
B~ Raising the flow setting of the boric acid flow controller during a blended makeup to the VCT.
C. Raising the setting of the blended makeup flow totalizer by 100 gallons total during a blended makeup to the VCT.
D. Lowering the setting of the boric acid batch totalizer by 10 gallons total during a blended makeup to the VCT.
B is correct. SOM is determined by boron concentration and temperature. B will raise RCS boron concentration by providing a higher rate of boric acid flow to the VCT.
A is incorrect. Increased boron removal in letdown demineralizers reduces boron concentration, thus reducing SOM.
C is incorrect.
This increases the quantity ofblended flow at previously selected boron concentration, thus does not affect SOM.
o is incorrect.
This reduces boron addition which reduces boron concentration, thus reducing SOM.
Knowledge of the operational implications of the following concepts as they apply to the CVCS: Concept of SOM Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
2 2
1 3.5 CVCS Text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:23 PM 8
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 6. 005 Kl.l1 005/BANK//LOWERJ/ROIHARRIS/3/2008/NO Which ONE of the following sets of parameters and conditions will satisfy the interlocks 0
open the Residual Heat Removal Hot Leg Suction valves (1RH-1, 2, 39, and 40)?
A.
RCS temperature is 345 of, RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut, RHR suction from RWST valves, 1RH-322 and 1RH-323, are shut.
B." RCS pressure 355 psig, RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut, RHR suction from RWST valves, 1RH-322 and 1RH-323, are shut.
C.
RCS pressure 355 psig, RHR suction from RWST valves, 1RH-322 and 1RH-323, are shut.
RHR suction from Containment sump valves 1SI-300, 301, 310, and 311 are shut.
D.
RHR temperature is 345 of, RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut, RHR suction from Containment sump valves 1SI-300, 301, 310, and 311 are shut.
Interlocks to Open To open valves RH-1, 2, 39, and 40, the following must be met:
RCS pressure (PT-402, 403) < 363 psig RHR discharge to CSIP--SHUT Suction from RWST--SHUT This item meets the KA because the physical connection (RWST Suction Valves to RHR) have a cause and effect on the operation of the RHR system. If the RHR suction valves are not closed, and the RHR Hot Leg suction isolation valves are allowed to open, cross-connect of RCS and RWST would occur. Therefore, the cause is RWST suction open, effect is RCS suction interlocked to remain closed.
Saturday, January 05,200812:00:23 PM 9
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the following systems: RWST Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
3 2
1 3.5 RHR Text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:23 PM 10
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 7. 005 K6.03 014IMODIFIEDIIHIGHERlIROlHARRIS/312008INO Given the following:
The plant is in Mode 4.
RHR Train "A" is in service.
RHR Heat Exchanger Bypass Valve 1RH-20 is in automatic with the output at 40% to maintain 3750 GPM.
RHR Heat Exchanger outlet valve 1RH-30 demand position is set at 30%.
The Instrument Air supply line to RHR Heat Exchanger Outlet Valve 1RH-30 becomes severed and is completely detached.
No other air operated valves are impacted by the failure.
Which ONE of the following describes the RHR system parameter changes from the initial steady state condition to final steady state condition?
RHR HX Outlet Temp Total RHR flow A.
Higher Lower B.
Higher Higher C~
Lower Higher D.
Lower Lower 0: Correct. RH-30 fails open, so there is less bypass flow mixing with more HX flow, resulting in a lower temperature on the HX outlet. Total RHR flow will be higher since RH-30 opening will open 70% increasing flow more than 1RH-20 can compensate.
A: Incorrect. This would be the conditions expected if RH-30 failed shut, but it is a fail open valve.
8: Incorrect. Total RHR flow will be higher, but temperature will not increase. Plausible if candidate doesn't understand that 1RH-20 will shut causing less mixing.
0: Incorrect. Total RHR flow would lower if RH-30 failed shut, but it fails open.
Temperature effect is correct..
Saturday, January 05, 2008 12:00:23 PM 11
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: RHR heat exchanger Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
4 2
1 2.5 RHR text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.41.7 Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:23 PM 12
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 8. 006 K1.08 001INEWIIHIGHERI/ROIHARRIS/3/2008INO Given the following:
A reactor trip and safety injection have occurred.
RCS pressure is 1000 psig and lowering.
All equipment is operating as designed.
Which ONE of the following describes the MCB Charging Flow indication (FI-122.1),
and the Safety Injection flow indication (FI-943)?
A. MCB Charging flow 0 gpm; Safety Injection flow is stable.
B:' MCB Charging flow 0 gpm; Safety Injection flow is rising.
C. MCB Charging flow off-scale high; Safety Injection flow is stable.
D. MCB Charging flow off-scale high; Safety Injection flow is rising.
B is correct. On a SIAS, the charging line valves shut, both CSIPs start, and the BIT flowpath will open. Because pressure is lowering, CSIP Cold Leg flow will be rising.
A is incorrect but plausible if candidate believes CSIPs deliver constant volumetric flow.
C is incorrect but plausible if candidate doesn't recognize that the charging line isolations shut automatically on a Safety injection signal and believes the CSIPs deliver a constant volumetric flow.
o is incorrect but plausible if candidate doesn't recognize that the charging line isolations shut automatically on a Safety Injections signal. SI flow would rise.
Saturday, January 05, 200812:00:23 PM 13
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the physical connections and/or cause effect relationships between the ECCS and the following systems: CVCS Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
5 2
1 3.6 CVCS Text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:23 PM 14
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 9. 006 K4.05 002/BANK//HIGHER//RO/HARRIS/3/2008/NO Given the following:
The reactor is tripped.
All equipment is operating as designed.
The crew is performing actions of Path-1.
Conditions are as follows:
PZR press.
CNMT press.
1865 psig 2.9 psig 1865 psig 3.1 psig CH III 1845 psig 3.1 psig CH IV NA 2.9 psig Which ONE of the following describes the status of the SI system?
A. SI is actuated due to low PZR pressure.
B:-" SI is actuated due to high Containment pressure.
C. SI is NOT actuated, but will be actuated if the additional required PZR pressure transmitter reaches the setpoint D. SI is NOT actuated but will be actuated if the additional required CNMT pressure transmitter reaches the setpoint.
A is incorrect. Low PZR pressure, 1850 psig on 2 of 3 detectors will initiate SI.
B is correct. CNMT pressure 3 psig on 2 of 4 detectors actuates SI.
C is incorrect. Would be correct if Cnmt pressure had not already actuated SI.
D is incorrect. 2 of 4 already exceed the setpoint.
Saturday, January 05, 2008 12:00:23 PM 15
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Auto start of HPIfLPI/SIP Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
6 2
1 4.3 ESFAS Text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
Obj 4,8 10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:24 PM 16
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 10. 007 G2.1.23 004IBANKJSEQUOYAH 2007 NRC/HIGHERJ/RO/HARRIS/3/2008/NO Initial Conditions:
With the plant operating at 100% power and all equipment in its normal lineup, the RO takes the Reactor Trip switch to the TRIP position.
Current plant conditions are:
Reactor Trip Breaker "A" Red indication exists.
Reactor Trip Breaker "B" Green indication exists.
Reactor Power is 4% and lowering.
Rod bottom lights are lit with the exception of FOUR Control Bank 0 rods.
Their positions are as follows:
H 16 steps K 220 steps M 8 steps M 20 steps Which ONE of the following describes the condition of the reactor, and the action that will be required?
A. The reactor is tripped; Perform normal RCS boration for the stuck rods.
B~ The reactor is tripped; Initiate emergency boration for the stuck rods.
C. The reactor is not tripped; Manually insert control rods.
D. The reactor is not tripped; Initiate emergency boration for the stuck rods.
A. Incorrect. Emergency Boration will be directed by procedure, not normal boration.
B. Correct. Power decreasing and 1 RTB open means the reactor is tripped. EPP-004 will direct emergency boration to address stuck rods.
C. Incorrect. Indication is that reactor is tripped. If it was not, this would be correct.
D. Incorrect. Indication is that reactor is tripped. If not, these actions would occur.
Saturday, January 05,200812:00:24 PM 17
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
39 1
1 3.9 Path-1, EPP-4 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
SEQUOYAH 2007 NRC HARRIS NO Saturday, January 05,200812:00:24 PM 18
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 11. 007 K4.01 002/BANKI/HIGHERJ/RO/HARRIS/3/2008/NO Given the following:
The plant is at 100% power.
A Pressurizer PORV has a slow leak through the seat or disk.
The respective PORV isolation valve cannot be closed.
ALB-009-8-1, PRESSURIZER RELIEF TANK HIGH-LOW LEVEL PRESS OR TEMP, is actuated.
PRT Level is 73%.
PRT Temperature is 128 of.
PRT Pressure is 6.3 Psig.
Which ONE of the following parameters is causing the alarm, and which ONE of the following is the required action?
A.
Pressure; Purge the PRT as necessary to control pressure.
B. Pressure; Drain the PRT as necessary to control pressure while maintaining level within the normal band.
C~ Temperature; Recirculate the PRT contents through the RCDT Heat Exchanger to lower temperature.
D. Temperature; Drain PRT to the low end of the normal band and then refill with demineralized water to lower temperature.
A. Plausible if applicant believes this will control PRT pressure with steam leakage present.
B. Plausible if applicant believes PRT pressure is outside the normal band.
C. Correct.
Temperature is the only parameter above the alarm setpoint.
D. Plausible since it is a possible means of cooling down the PRT but is not directed by procedure.
Saturday, January 05, 2008 12:00:24 PM 19
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the following: Quench tank cooling Question Number:
7 Tier:
2 Group:
1 Importance Rating:
2.6 Technical
Reference:
ALB-009-8-1, OP-100, Section 8 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.7 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:24 PM 20
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 12. 008 A2.08 001/NEW//HIGHER//RO/HARRIS/3/2008/NO Given the following:
The plant is at 100% power.
The temperature input to Letdown Heat Exchanger CCW flow control valve TCV-144, fails low.
Which ONE of the following describes the impact on the plant and the action that is required?
A.
High CCW flow to Letdown Heat Exchanger; Place TCV-144 in manual and adjust flow to restore normal cooling.
B. High CCW flow to Letdown Heat Exchanger; Isolate letdown and place Excess Letdown in service.
C~ High temperature letdown diversion to VCT; Place TCV-144 in manual and adjust flow to restore normal cooling.
D. High temperature letdown diversion to VCT; Isolate letdown and place Excess Letdown in service.
C is correct. The input to TCV-144 failing low will cause CCW to throttle flow to the HX in an attempt to raise temperature.
This will cause actual temperature to increase and an automatic diversion to the VCT will occur to protect the demineralizers.
Correct response is to take manual control of TCV-144 and restore proper cooling flow.
o would only be performed if C did not work correctly.
A & B are incorrect because the input to TCV-144 failing low will cause CCW to reduce cooling flow to the Letdown HX in an attempt to increase the temperature. High CCW flow would occur if the input failed high causing CCW to increase its flow to the Letdown HX.
Saturday, January 05,200812:00:24 PM 21
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effects of shutting (automatically or otherwise) the isolation valves of the letdown cooler Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
8 2
1 2.5 ALB -007-3-2 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:24 PM 22
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 13. 008 AK2.03 001/NEW//HIGHER//RO/HARRIS/3/2008/NO Given the following:
A reactor trip has occurred from 100% power.
Pressurizer pressure is 1100 psig and lowering.
Pressurizer level is rising rapidly.
Containment pressure is 4 psig and rising.
Which ONE of the following indications is consistent with the conditions of the event in progress?
A. PORV discharge line temperature of 212 of B. Condenser Vacuum Pump Effluent Radiation monitor in HIGH alarm C~ Red light for Pressurizer PORV 444B D. PRT Pressure of 50 psig A. Incorrect. PORV discharge line temperature would be at saturation for containment atmosphere 4 psig (-225 OF). 212 of would be correct for apsig in containment.
B. Incorrect. This indication would be indicative of a SGTR, however pressurizer level would decrease for a SGTR.
C. Correct. Indications are consistent for vapor space break, which could be due to an open PORV with a release to containment in progress.
D. Incorrect. PRT pressure is normally 2 to 4 psig. This pressure would be consistent with a vapor space accident, but containment pressure of 4 psig indicates that the PRT rupture disc has already ruptured.
Saturday, January 05, 2008 12:00:24 PM 23
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Controllers and positioners Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
40 1
1 2.5 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:24 PM 24
~,
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 14. 009 EK2.03 003/MODIFIED//HIGHERJ/RO/HARRIS/3/2008/NO Given the following:
A reactor trip has occurred.
Safety Injection is actuated.
All actions required in Path-1 have been taken.
RCS pressure is 1450 psig andstable.
SI flow is 150 GPM.
Containment pressure is 4.5 psig and rising.
SG pressures are 1050 psig and stable.
Which ONE of the following describes the plant condition upon transition from Path-1?
A'! RCPs are running.
SGs are required for RCS heat removal.
B. RCPs are running.
SGs are NOT required for RCS heat removal.
C. RCPs are NOT running.
SGs are required for RCS heat removal.
D. RCPs are NOT running.
SGs are NOT required for RCS heat removal.
A is correct.
With RCS pressure higher than SG pressure, a secondary heat sink is required.
RCPs will be running because pressure is not low enough to trip and CS has not occurred.
B is incorrect. SGs are available and required to remove heat from the RCS.
C is incorrect. A SBLOCA is in progress as indicated by RCS pressure being above RHR Pump shutoff head. SGs would not be required for heat removal if LBLOCA in progress.
RCPs are ON.
D is incorrect.
SGs are required.
Saturday, January 05, 2008 12:00:24 PM 25
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the interrelations between the small break LOCA and the following: S/Gs Question Number:
Tier:
Group:
Importance Rating:
41 1
1 3.0 Technical
Reference:
Path-1 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:25 PM 26
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- ):
,I;
- 15. 010 K2.01 002/MODIFIED//HIGHER//RO/HARRIS/3/2008/NO Initial Plant Conditions:
The plant was at 100% power.
Current plant conditions are:
A Loss of Off-site Power occurs.
Bus 1A-SA is locked out.
All other equipment has operated as designed.
Diesel loading sequence is complete.
RCS pressure is 2180 psig.
Assuming NO operator action has been taken, which ONE of the following describes the status of the PZR Heaters?
A'! ALL PZR Backup Heaters are DE-ENERGIZED.
B. Group B is the only PZR heater group ENERGIZED.
C. Group C is the only PZR heater group ENERGIZED.
D. Groups Band C are the only PZR heater groups ENERGIZED.
A. Correct. After a LOOP, manual action is required to reenergize 181 to provide power for backup heater Group 8. C heaters can not be restored until after the non-vital bus is restored.
- 8. Incorrect, but credible to believe 8 heaters will be sequenced on during Oieselloading of 18-S8 bus.
C. Incorrect, but credible to believe C heaters will be sequenced during Oieselloading since C heaters are normally always energized, powered from 102.
O. Incorrect, but credible to believe 8 and C heaters will be sequenced during Oieselloading.
KA is matched because the applicant must know that the power to 8 backup heaters is bus 181, and not bus 18-S8. They must also know that 181 is manually reenergized after a loss of off-site power.
With RCS pressure below the backup heater setpoint, it is a reasonable misconception that heaters will be energized if the power supply is not known.
Saturday, January 05,200812:00:25 PM 27
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of bus power supplies to the following: Pressurizer Heaters Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
9 2
1 3.0 PZR Text Page 8 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
Modified from Harris Bank 55.41.7 Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRlS NO Saturday, January 05,2008 12:00:25 PM 28
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 16. 011 EA1.l5 001/NEW/ILOWERJ/RO/HARRIS/3/2008/NO Which ONE of the following describes the characteristics of a Large Break LOCA fifteen (15) minutes into the event?
A. RCS temperature is at saturation temperature for intact SG pressure; RCS pressure is stable below normal SI accumulator pressure, but above RHR pump shutoff head.
B. RCS temperature is at saturation temperature for intact SG pressure; RCS pressure stable below RHR Pump shutoff head.
C. RCS temperature is below saturation temperature for intact SG pressure; RCS pressure stable below normal SI accumulator pressure, but above RHR pump shutoff head.
D~ RCS temperature is below saturation temperature for intact SG pressure; RCS pressure stable below RHR Pump shutoff head.
D is correct. For a LBLOCA classification, RCS pressure will be below RHR pump shutoff head. Temperature will be below saturation for SGs as they become a heat source, due to cold SI flow filling the reactor.
A is incorrect but plausible if candidate doesn't recognize RCS temperature will drop below SG saturation temperature and believes the Cold Leg Accumulators will maintain pressure above RHR pump shutoff head.
B is incorrect but plausible if candidate doesn't recognize RCS temperature will drop below SG saturation temperature.
C is incorrect because the SI accumulators will not be able to maintain pressure on a LBLOCA.
Saturday, January 05,200812:00:25 PM 29
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to operate and monitor the following as they apply to a Large Break LOCA: RCS temperature and pressure Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
42 1
1 4.2 Need T &AA for LOCA Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:25 PM 30
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 17. 011 K2.0 1 002/MODIFIED//LOWERJ/RO/HARRIS/3/2008/NO Given the following:
The unit is at 100% power.
Unit electrical alignment is normal.
Aux Bus 1D deenergizes and is locked out.
Which ONE of the following describes an effect on the unit?
A. "B" RCP is deenergized.
B. "C" RCP is deenergized.
C'f "A" CSIP is momentarily deenergized.
D. "B" CSIP is momentarily deenergized.
A incorrect but plausible because Bus 1A and 1B supply RCPs.
B incorrect but plausible because Bus 1A and 1B supply RCPs.
C Correct Bus 10 is the normal supply to 6.9 KV Bus 1A-SA. The charging pump is momentarily de-energized while the EDG comes up to speed and powers the bus. The Charging pump will be loaded on when required by the sequencer.
o incorrect but plausible because losing Bus 1E will result in this effect.
Knowledge of bus power supplies to the following: Charging Pumps Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
31 2
2 3.1 6.9 KV Text pg 19/20 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
CVCS Obj 2 55.41.5/7 Source:
Cognitive Level:
Job Position:
Date:
MODIFIED LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:25 PM 31
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 18. 012 A3.02 021/BANK/IHIGHER/IROIHARRIS/3/2008/NO Given the following:
The plant is operating at 30% reactor power, steady state.
I&C technicians are preparing to perform a calibration on Power Range Channel N-41.
One I&C technician mistakenly pulls the control power fuses on N-42.
Realizing his mistake, he reinserts the fuses for N-42 and then pulls the control power fuses for the correct channel, N-41, causing a Reactor Trip.
Which ONE of the following describes the bistable(s) that indicate tripped?
A':' PR Rate Trip ONLY.
B. PR Neutron Flux High Setpoint Trip ONLY.
C. PR Rate Trip AND PR Neutron Flux High Setpoint Trip ONLY.
D. PR Rate Trip, PR Neutron Flux Low Setpoint, AND Neutron Flux High Setpoint Trips A Correct. One rate trip channel tripped when N-42 fuses pulled. The second channel tripped when the second channel fuses were tripped. The first channel rate trip must be manually reset before it will clear, meaning 2 rate channels were in trip.
B Incorrect. The PR flux trip does not require manual reset. The trip is either active or not, depending on the setpoint. Plausible because the trip will be active when fuses are pulled C Incorrect.
Rate Trip will be active because it was not manually reset. PR flux will not be active.
D Incorrect. Rate Trip will be active because it was not manually reset. PR flux will not be active. Plausible because it is reasonable to assume that all drawer bistables are tripped when power is lost to a drawer.
Saturday, January 05,200812:00:25 PM 32
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to monitor automatic operation of the RPS, including: Bistables Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
11 2
1 3.6 RPS text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Editorial Mods throughout distractors Source:
BANK Cognitive Level:
HIGHER Job Position:
RO Date:
3/2008 Saturday, January 05,200812:00:25 PM Source ifBank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO 33
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 19. 012 K6.03 002/BANKlVCS 2006 NRCIHIGHERJIROlHARRIS/312008INO Pressurizer Pressure Protection Channel PT-455 fails and is properly removed from service.
Which ONE of the following identifies the MINIMUM additional channels required to meet the ESF and RPS actuation logic to initiate a reactor trip and safety injection on low pressurizer pressure?
A'! Reactor Trip - 1; Safety Injection - 1 B. Reactor Trip - 1; Safety Injection - 2 C. Reactor Trip - 2; Safety Injection - 1 D. Reactor Trip - 2; Safety Injection - 2 A is correct. Rx Trip and SI are normally 2/3 for PZR pressure.
Channel 455 feeds both circuits. When a protection channel is removed from service, bistables are tripped in all cases except for the AUTO RB Spray actuation. Thus, AUTO SI will occur if either of the two remaining bistables trip and Reactor trip will occur if either of the 2 remaining bistables trip.
B is incorrect. Plausible if candidate believes that with the channel removed from service it's input is removed from the ESFAS actuation circuitry.
C is incorrect. Plausible if candidate believes that the with the channel removed from service it's input is removed from the RPS actuation circuitry.
o is incorect. Plausible if candidate believes that with the channel removed from service it's input is removed from both the ESFAS and RPS actuation circuitry.
Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Trip logic circuits Question Number:
Tier:
Group:
10 2
1 Importance Rating:
3.1 Technical
Reference:
RPS text Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.7 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source ifBank:
Difficulty:
Plant:
Previous NRC?:
VCS 2006 NRC HARRIS NO Saturday, January 05,200812:00:25 PM 34
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 20. 013 K3.03 003/BANKNCS 2007 NRC/HIGHER//RO/HARRIS/3/2008/NO Given the following:
A LOCA has occurred.
RCS pressure is 200 psig.
"A" Containment Spray Pump is Out of Service.
Containment pressure is 12 psig and slowly increasing.
Train "B" Phase A has failed to actuate.
All other ECCS equipment is running as required.
The most recent Chemistry sample of the RCS indicated that RCS activity is 5X10-2 microcuries/ml Dose Equivalent Iodine.
Assuming no action by the crew, which ONE of the following describes the effect on the plant?
A. Containment will exceed its design pressure.
B. Off-Site releases from Containment will exceed accident analysis assumptions.
C~ Only 1 Containment Isolation Valve in each Phase A penetration will be closed.
D. Only half of the Containment penetrations required for isolation will be isolated.
A. Incorrect.
Cnmt Spray from 1 train will maintain design.
B. Incorrect.
1 valve in each penetration is closed.
C. Correct. If 1 train fails, the system will still perform its function with the other train.
D. Incorrect.
Half the valves will be closed, but al/ the penetrations will still be isolated.
Knowledge of the effect that a loss or malfunction of the ESFAS will have on the following: Containment Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
12 2
1 4.3 ESFAS text Proposed References to be provided to applicants during examination - NONE Learning Objective -
10 CFR Part 55 Content - 41.7 Comments -
Saturday, January 05,200812:00:25 PM 35
(
Source:
Cognitive Level:
Job Position:
Date:
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F BANK Source if Bank:
VCS 2007 NRC HIGHER Difficulty:
RO Plant:
HARRIS 3/2008 Previous NRC?:
NO Saturday, January 05, 2008 12:00:25 PM 36
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 21. 015 AK1.05 001/BANKI/HIGHER//RO/HARRIS/3/2008/NO Given the following:
The plant is at 20% power.
Rod Control is in AUTO.
The operating crew is preparing to stop RCP 1C due to rising vibration.
Assuming that reactor power is maintained at 20%, which ONE of the following describes the effect on Loop 1 Delta T and Loop 1 OT Delta T setpoint when RCP 1C is stopped?
Loop 1 Delta T Loop 1 OT Delta T Setpoint A.
remain the same; rise B.
remain the same; lower C.
rise; rise D~
rise; lower
(
A. Plausible if applicant believes stable power = stable DT and it balances the choices.
B. Plausible if applicant believes stable power =stable DT and understands the OT Delta T calculation.
C. Plausible if applicant understands effect on operating loop DT but misunderstands the OT Delta T calculation.
D. Correct.
Knowledge of the operational implications of the following concepts as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Effects of unbalanced RCS flow on in-core average temperature, core imbalance, and quadrant power tilt Question Number:
43 Tier:
1 Group:
1 Importance Rating:
2.7 Technical
Reference:
T8 Table 2.2.1, page 2-7, AOP-018, Attachment 7 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.5 Comments:
Saturday, January 05,2008 12:00:26 PM 37
Source:
Cognitive Level:
Job Position:
Date:
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F BANK Source if Bank:
HIGHER Difficulty:
RO Plant:
HARRIS 3/2008 Previous NRC?:
NO Saturday, January 05,2008 12:00:26 PM 38
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 22. 016 K3.03 001INEW//HIGHERI/RO/HARRIS/3/2008/NO Given the following:
The plant is at 60% power during a plant startup.
Steam Dumps are in the Tave mode of control.
First Stage Pressure Transmitter PT-446 fails high.
Assuming the reactor remains at power, which ONE of the following describes the effect on the steam dump system?
A. Steam Dumps will arm.
B. Steam Dumps will receive a modulation (open) signal.
C. Steam Dumps will NOT arm if required.
D~ Steam Dumps will NOT modulate if required.
A and C are incorrect because PT-447 provides the arming signal.
a is incorrect because a mismatch would develop to cause this if the instrument failed LOW o is correct. PT-446 is required to modulate the steam dumps unless a turbine trip occurs.
Knowledge of the effect that a loss or malfunction of the NNIS will have on the following: SOS Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
32 2
2 3.0 SDS Text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:26 PM 39
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 23. 017 K6.01 001/BANKJIHIGHER//ROIHARRIS/3/2008/NO Given the following:
The crew is performing EPP-004, Reactor Trip Response.
Natural circulation verification is in progress.
TWO (2) Core Exit Thermocouples are failed due to open circuits.
Which ONE of the following describes the effect on the Inadequate Core Cooling Monitor (ICCM) and whether the failed thermocouples are used by the ICCM in the subcooling margin used to verify natural circulation?
A.
Inputs are failed low; Input's are used by ICCM.
B~ Inputs are failed low; Input's are NOT used by ICCM.
C. Inputs are failed high; Input's are used by ICCM.
D. Inputs are failed high; Input's are NOT used by ICCM.
B is correct because a failed low input will not be used on IGGM (Only highest temperature and lowest pressure).
A is incorrect because IGGM will not use the value.
G and 0 are incorrect because thermocouples fail low on an open, not high.
Saturday, January 05,200812:00:26 PM 40
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the effect of a loss or malfunction of the following ITM system components: Sensors and detectors Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
33 2
2 2.7 ICCM Text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
Editorial mods 2004 exam 55.41 Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRlS NO Saturday, January 05,200812:00:26 PM 41
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 24. 022 ALOI 00IINEW//LOWER//ROIHARRIS/3/2008INO
('
\\
Given the following:
Containment Cooling is in the Normal Cooling Mode of operation with Train "A" in service.
Containment temperature has been slowly rising.
The BOP has been directed to place Containment Cooling in maximum cooling mode.
Which ONE of the following correctly identifies the temperature at which a Technical Specification action statement must be entered and places Containment Cooling in the Maximum Cooling Mode?
A. 118°F Start ONE Train B Fan; Stop ONE Train A fan; Start BOTH fans in the additional Train B AHU; B. 118 of Start BOTH fans in one Train B AHU; Stop BOTH fans in one Train A AHU; Start ONE fan in the additional Train B AHU; Start ONE Train B Fan; Stop ONE Train A fan; Start BOTH fans in the additional Train B AHU; D. 120 of Start BOTH fans in one Train B AHU; Stop BOTH fans in one Train A AHU; Start ONE fan in the additional Train B AHU; C is correct. 120 degrees F is the TS limit. 118 is the temperature at which maximum cooling is placed in service.
Sequence is correct on A and C. Band 0 plausible because the same number of fans are operating, except that Train A will have 1 additional fan.
Saturday, January 05,200812:00:26 PM 42
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Containment temperature
(
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
13 2
1 3.6 ccs text Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41.5 Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:26 PM 43
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 25. 022 G2.1.28 001INEW//LOWERI/ROIHARRIS/312008INO Given the following:
The plant is at 100% power.
VCT Level Channel LT-112 fails high.
The crew is performing actions of AOP-003, Malfunction of Reactor Makeup Control.
Which ONE of the following describes the function(s) lost due to this failure?
A. ONLY Divert to RHT will be disabled 8:1 ONLY Auto Swapover from RWST will be disabled.
C. Auto Swapover from RWST AND Auto Makeup will be disabled.
D. Divert to RHT AND Auto Makeup will be disabled.
B is correct. Requires 2 of 2 to function.
A is incorrect because divert will function with a failure. It must be manually stopped.
C and 0 are incorrect because Auto Makeup is controlled by LT-115.
Conduct of Operations: Knowledge of the purpose and function of major system components and controls.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
44 1
1 3.2 AOP-003, Attachment 1 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:26 PM 44
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 26. 022 K1.01 001INEW//LOWERlIROIHARRIS/31200SINO Initial conditions:
The plant is at 100% power.
Train "B" Containment Fan Cooling is in service.
Current conditions:
A loss of off-site power has occurred.
All equipment is operating as designed.
Which ONE of the following describes the operation of Containment Cooling?
A. One fan in each train operating; Normal Service Water aligned B. One fan in each Fan Cooler Unit operating; Normal Service Water aligned C. One fan in each train operating; Emergency Service Water aligned D~ One fan in each Fan Cooler Unit operating; Emergency Service Water aligned D is correct. One fan in each Fan Cooler Unit will be operating with cooling supplied by ESW.
A & B are incorrect because though NSW is the normal cooling supply on a loss of offsite power NSW will deenergize and the ESW pumps will start and automatically realign the system to supply cooling.
C is incorrect. On a LOSP all operating fans will trip due to load shed. The sequencers will then start one fan in each unit in high speed.
Saturday, January 05, 2008 12:00:26 PM 45
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems:
SWS/cooling system Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
14 2
1 3.5 CCS Text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
CCS,4.h 55.41 Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:26 PM 46
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 27. 024 AK2.03 001INEW//LOWERlIROIHARRIS/3/2008INO Given the following:
Following a load rejection, the crew is performing an Emergency Boration in accordance with AOP-002, Emergency Boration.
The crew is required to perform the boration from the RWST.
The RO performs the required valve alignment to provide suction flow to the CSIPs.
Which ONE of the following describes the action and/or verification required to ensure that the required boration flow is achieved?
A.
Ensure a minimum of 30 GPM on FI-110, Emergency Boration flow. No other action required.
B. Ensure a minimum of 90 GPM on FI-110, Emergency Boration flow. No other action required.
C. Adjust FCV-122 as necessary to achieve a minimum of 30 GPM on FI-122.1, Charging Header flow.
D~ Adjust FCV-122 as necessary to achieve a minimum of 90 GPM on FI-122.1, Charging Header flow.
D is correct. Flow from RWST will go through normal charging flowpath, not the emergency boration flowpath.
A & B are incorrect because boration flow from the RWST does not go through the emergency boration flowpath.
C is incorrect because the 30 gpm minimum is only when using the normal borated water source. When using the RWST, which has a lower boron concentration, a greater flow rate is required to be equivalent.
Saturday, January 05, 2008 12:00:26 PM 47
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the interrelations between the Emergency Boration and the following: Controllers and positioners Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
58 1
2 2.6 AOP-002 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:27 PM 48
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
';"28. 025 AA1.20 002/NEW//HIGHER//RO/HARRIS/3/2008/NO Given the following:
The plant is in Mode 5.
An RCS leak and loss of RHR occurs..
The crew is performing actions of AOP-020, Loss of RCS Inventory or Residual Heat Removal While Shutdown.
The crew is aligning to provide RCS Makeup using CSIP flow in accordance with section 3.6, Establishing Sl Following a Major RCS Leak.
Which ONE of the following describes the indications available to verify CSIP flow?
A~ ONE CSIP control switch red light on.
Flow indication of approximately 500 GPM through the BIT.
B. ONE CSIP control switch red light on.
Flow indication of approximately 150 GPM through the normal charging line.
C. TWO CSIP control switch red lights on.
Flow indication of approximately 500 GPM through the BIT.
D. TWO CSIP control switch red lights on.
Flow indication of approximately 150 GPM through the normal charging line.
A is correct. Total of 500 GPM through BIT and one CSIP operating.
B is incorrect. Flow is through the BIT, not normal charging.
C is incorrect. Only 1 red light on, the other CSIP would be tagged out for these plant conditions.
o is incorrect. Only 1 red light on, the other CSIP would be tagged out for these plant conditions.
Saturday, January 05,200812:00:27 PM 49
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to operate and I or monitor the following as they apply to the Loss of Residual Heat Removal System: HPJ pump control switch, indicators, ammeter running lights, and flow meter
(
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
45 1
1 2.6 AOP-020 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:27 PM 50
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 29. 026 A3.0J 002/MODIFIED//HIGHERlIRO/HARRIS/3/2008/NO Initial Conditions:
Surveillance testing is in progress on Containment Spray Train "A".
"A" Containment Spray Pump is running.
1CT-24-SA and 1CT-25-SB, Containment Spray Eductor Test Valves, are open for testing.
1CT-50-SA, Containment Spray Pump 1A-SA Discharge Valve, is closed.
Current conditions:
A LOCA occurs.
RCS pressure is 1600 psig.
Containment Pressure is 10.5 psig.
Which ONE of the following correctly lists the position of the Containment Spray Eductor Test Valves and the 1A-SA Discharge Valve for the current plant conditions?
1CT-24-SA and 1CT-25-SB 1CT-50-SA A.
OPEN OPEN
(
B~
CLOSED OPEN C.
OPEN CLOSED D.
CLOSED CLOSED o is incorrect.
1CT-24/25 will close on a Phase A if open, but 1CT-50 will open on Hi-3 pressure.
Current pressure is above Hi-3 (10 psig)
A is incorrect. Plausible because eductor valve is open to start with, and high containment pressure will open spray discharge valve, but the Phase A would have shut the eductor valve.
B is correct. Eductor valve will close, and pressure is high enough for the spray discharge valve to be open.
C is incorrect. Spray discharge will be open and eductor valve receives a close signal on Phase A at 3 psig.
Saturday, January 05, 2008 12:00:27 PM 51
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to monitor automatic operation of the CSS, including: Pump starts and correct MOV positioning
(
Question Number:
15 Tier:
2 Group:
1 Importance Rating:
4.3 Technical
Reference:
OMM-004 Attachment 4, OST-1118 Proposed references to be provided to applicants during examination:
None Learning Objective:
CSS Text obj 6 10 CFR Part 55 Content:
41.5 Comments:
Modified from previous Harris item Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:27 PM 52
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 30. 026 02.2.22 091/MODIFIED//HIOHER//RO/HARRIS/3/2008/NO Given the following:
The plant is in Mode 1.
12:00 Containment Spray Pump 1A-SA declared INOPERABLE due to a failed surveillance.
12:27 Containment Spray Pump 1B-SB also declared INOPERABLE due to the results of a common cause failure analysis.
14:21 Containment Spray Pump 1A-SA returned to OPERABLE status.
14:40 Containment Spray Pump 1B-SB returned to OPERABLE status.
Which ONE of the following describes the Technical Specification requirements for operation of the plant?
Actions to initiate a plant shutdown must commence no later than...
A. 12:27; The shutdown may be terminated no earlier than 14:21.
B. 12:27;.
The shutdown may be terminated no earlier than 14:40.
C~ 13:27; The shutdown may be terminated no earlier than 14:21.
D. 13:27;.
The shutdown may be terminated no earlier than 14:40.
A. Incorrect. When the LCO action is no longer 3.0.3, actions may be terminated.
B. Incorrect.
Credible because the applicant may misunderstand entry and exit to TS 3.0.3.
C. Correct.
D. Incorrect. Credible because the applicant may misunderstand entry and exit to TS 3.0.3.
Saturday, January 05,200812:00:27 PM 53
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Equipment Control Knowledge of limiting conditions for operations and safety limits.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
16 2
1 3.4 TS 3.6.3, TS 3.0.3 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.43.2 Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 200812:00:27 PM 54
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 31. 027 AA 1.03 027/MODIFIED//HIGHER!/RO/HARRIS/3/2008/NO
(
Given the following:
The plant is operating at 100% power.
A failure of the PT-444 input to PK-444A, Pressurizer Pressure Master Controller, caused actual pressurizer pressure to decrease to 2190 psig.
PK-444A has been placed in MANUAL.
Which ONE of the following describes the action required to return pressure to 2235 psig?
A"! Decrease the controller output.
B. Increase the controller output.
C. Lower the pressure setpoint adjustment.
D. Raise the pressure setpoint adjustment.
A is correct. Decreasing controller output will energize heaters and raise pressure.
B is incorrect. Increasing controller output will de-energize heaters/open spray valves increasing pressure.
C & D are incorrect, once in manual adjusting the setpoint will have no effect. Plausible if applicant believes setpoint is still in the control circuitry while in manual.
Saturday, January 05, 2008 12:00:27 PM 55
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to operate and I or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: Pressure control when on a steam bubble Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
46 1
1 3.6 AOP-019, PPCS Text Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:27 PM 56
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 32. 029 A4.04 028/MODIFIED/IHIGHERlIROIHARRlS/3/2008/NO Given the following:
The unit is in Mode 6.
Refueling activities are in progress.
A fuel assembly has been ruptured during removal from the core.
Radiation levels are rising steadily and are currently as follows:
REM-01LT-3502A-SA, Cnmt RCS Leak Detection Monitor, is in HIGH ALARM REM-01LT-3502B-SB, Cnmt Pre-Entry Purge Monitor, is in HIGH ALARM Which ONE of the following describes the system isolation signal(s), if any, that have been automatically initiated, and action required in accordance with AOP-013, Fuel Handling Accident?
A. ONLY a Containment Pre-Entry Purge isolation signal has been initiated.
Containment Evacuation is required.
B~ BOTH Normal Containment Purge AND Containment Pre-Entry Purge isolation signals have been initiated.
Containment Evacuation is required.
C. ONLY a Containment Pre-Entry Purge isolation signal has been initiated.
Radiation Protection must be dispatched to determine if Containment Evacuation is required.
D. BOTH Normal Containment Purge AND Containment Pre-Entry Purge isolation signals have been initiated.
Radiation Protection must be dispatched to determine if Containment Evacuation is required.
A is incorrect but plausible if recognition that 35028 generates an isolation signal.
8 is correct C is incorrect but plausible if confusing normal and pre-entry.
o is incorrect but plausible if candidate confuses with 3561 monitors which will generate an isolation signal to both Normal and Pre-entry purge.
Matches KA since knowledge of automatic system response to high radiation levels is required to monitor rad levels from the MCR.
Saturday, January 05,200812:00:27 PM 57
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to manually operate and/or monitor in the control room: Containment evacuation signal Question Number:
35 Tier:
2 Group:
2 Importance Rating:
3.5 Technical
Reference:
AOP-013 Proposed references to be provided to applicants during examination:
None Learning Objective:
LPAOP13 Obj 3 10 CFR Part 55 Content:
41.10 Comments:
Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:27 PM 58
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 33. 029 EA2.05 00I/BANKI/LOWERlIROIHARRIS/3/2008/NO Given the following:
The plant is at 100% power A transient on SG level required a reactor trip, but the reactor did not trip.
The crew is performing FRP-S.1, Response To Nuclear Power Generation /
ATWS.
The crew notes that the Pressurizer pressure is 2350 psig Control rods are inserting in AUTO.
All Pressurizer PORV valve position indicating green lights are on and red lights are off.
Which ONE of the following actions are required in relation to the PZR PORVs and what are the reasons for those actions?
A. Leave the Pressurizer PORVs in Automatic to minimize DNB concerns during the ATWS.
B. Leave the Pressurizer PORVs in Automatic to minimize containment pressure concerns during the ATWS.
C. Open the Pressurizer PORVs and reduce pressure to avoid exceeding ASME pressure vessel code requirements.
D~ Open the Pressurizer PORVs and reduce pressure to allow for adequate boration flow to the core.
A. Incorrect. PORVs are required to be open in FRP-S. 1 if pressure is >2335 psig.
Plausible because DNB is more likely as pressure lowers.
B. Incorrect. PORVs are required to be open in FRP-S.1 if pressure is >2335 psig.
Plausible because opening PORVs will send RCS water to the PRT which will rupture to containment.
C. Incorrect. Safety Valves will protect vessel and the procedure requires the PORVs to be opened to raise boration flow, not protect the vessel. Plausible because there are high pressure requirements for the vessel.
D. Correct. FRP-S.1 step 6.d requires PORVs to be opened and pressure reduced to less than 2135 psig in order to aI/ow for adequate boration flow.
Saturday, January 05, 2008 12:00:28 PM 59
QUESTIONS REPORT
.>, II for HARRIS 2008 - WORKSHEET 1 REV F Ability to determine or interpret the following as they apply to a ATWS: System component valve position indications
(
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
47 1
1 3.4 FRP-S.1 and SO Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
Farley 55.41 Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:28 PM 60
c.
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 34. 033 AK3.02 001/NEW//HIGHERJIRO/HARRIS/3/2008/NO Given the following:
The plant is at 40% power.
Intermediate Range Channel N-35 loses compensating voltage.
I&C is called to investigate.
Prior to any action by I&C, a reactor trip occurs.
Which ONE of the following describes the plant condition related to N-35 as the crew performs Path-1?
A. Source Range Instruments will automatically energize prematurely; they must be manually de-energized until approximately 5 minutes post-trip to prevent damage to the detectors.
B. Source Range Instruments will automatically energize prematurely; they must be manually de-energized until approximately 15 minutes post-trip to prevent damage to the detectors.
C. Source Range Instruments will not automatically energize when required; they must be manually energized approximately 5 minutes post-trip to provide indication of power.
D~ Source Range Instruments will not automatically energize when required; they must be manually energized approximately 15 minutes post-trip to provide indication of power.
o is correct. Loss of compensation is under compensated, which means that IR power will read higher than actual. SR energization requires 2 of 2 IR detectors < P-6.
Assuming -1/3 OPM SUR, -15 minutes post trip is when the Source Range is required.
A & B are incorrect, but plausible if candidate incorrectly believes loss of compensating voltage will make IR power read lower than actual.
C is incorrect, but plausible if candidate assumes the standard 1 OPM from procedures to travel the required five decades.
Saturday, January 05,2008 12:00:28 PM 61
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the reasons for the following responses as they apply to the Loss of Intermediate Range Nuclear Instrumentation:
Guidance contained in EOP for loss of intermediate-range instrumentation Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
59 1
2 3.6 NIS text Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 312008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:28 PM 62
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 35. 034 G2.1.14 001/NEW//LOWER//RO/HARRIS/3/2008/NO Initial plant conditions:
The plant is in Mode 6 with Refueling in progress.
Current plant conditions are:
Fuel movement has stopped due to a problem with the Manipulator.
The Main Control Room has been informed that initial troubleshooting is in progress on the Manipulator.
The troubleshooting team desires to operate TS-5, the TROLLEY INTERLOCK BYPASS switch to permit forward and reverse motion of the trolley without the gripper tube at its top limit.
Which ONE of the following describes the permission and concurrence, if any, required for this action?
A. The SRO-Fuel Handling must approve. No concurrence is required.
B~ The SRO-Fuel Handling must approve with the concurrence of the SSO.
C. The SSO must approve with concurrence of the Manager - Mechanical Maintenance.
D. The Plant General Manager must approve. No concurrence is required.
B is correct, FHP-020, P&L.
A. is incorrect. SRO-Fuel Handling can give permission, but for bypassing interlocks the SSO must concur.
C is incorrect.
The SSO only needs to concur with bypassing the interlock and the Manager - Mechanical Maintenance is only required to be involved if troubleshooting involved a fuel storage rack, not the Manipulator (P&L 6).
D is incorrect. The Plant General Manager's permission would be required for operations involving Spent Fuel Pool "0" (FHP-014, P&L 13), but not for bypassing interlocks.
Saturday, January 05,2008 12:00:28 PM 63
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Conduct of Operations: Knowledge of system status criteria which require the notification of plant personnel.
Question Number:
36 Tier:
Group:
2 2
Importance Rating:
2.5 Technical
Reference:
AOP-013 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
HARRIS NO Source if Bank:
Difficulty:
Plant:
Previous NRC?:
NEW LOWER RO 3/2008 Really supposed to be Fuel Handling Equipment, is there any notification related to that system?
Source:
Cognitive Level:
Job Position:
Date:
Saturday, January 05,2008 12:00:28 PM 64
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 36. 036 AA2.01 001INEW//LOWERJIROIHARRIS/3/200SINO Given the following:
Refueling is in progress.
A spent fuel assembly is being moved in the Fuel Handling Building (FHB) when it's damaged by contacting a wall of the pool.
Spent Fuel Pool area radiation monitor RM-1FR-3566A-SA is in HIGH alarm.
Spent Fuel Pool area radiation monitor RM-1FR-3567B-SB is in ALERT.
Which ONE of the following describes the effect on the plant?
A"! ONLY ONE (1) train of Fuel Handling BUilding Ventilation Emergency Exhaust has received an automatic start signal.
B. BOTH trains of Fuel Handling Building Ventilation Emergency Exhaust have received automatic start signals.
C. NEITHER train of Fuel Handling Building Ventilation Emergency Exhaust has received an automatic start signal, and manual start is NOT required.
D. NEITHER train of Fuel Handling Building Ventilation Emergency Exhaust has received an automatic start signal, but manual start is required by AOP-013, Fuel Handling Accident.
A is correct. Anyone of a train's ARMs in HIGH alarm in the FHa will start 1 train of FHa emergency exhaust.
a is incorrect, but plausible if the candidate believes that an ARM in ALERT will cause a start of FHa emergency exhaust.
C & 0 are incorrect because an automatic start signal has been generated by the ARM in HIGH alarm, but plausible if candidate believes there is any coincidence requirements for generating this automatic signal.
Saturday, January 05, 2008 12:00:28 PM 65
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to determine and interpret the following as they apply to the Fuel Handling Incidents: ARM system indications Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
60 1
2 3.2 AOP-013, FHV text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:28 PM 66
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F r,
- 37. 038 EK1.03 001/BANK//HIGHER/IRO/HARRIS/3/2008/NO Given the following:
A Steam Generator Tube Rupture has occurred.
Off-Site power has been lost.
Both DG's are operating as required.
Which ONE of the following describes a plant concern during the performance of Path-2 for these conditions?
A. Voiding in the inactive regions of the RCS during the rapid RCS cooldown to target temperature.
B. Loss of RCS subcooling during depressurization using main or auxiliary spray.
C~ Voiding in the inactive regions of the RCS during depressurization using PZR PORVs.
D. Loss of RCS subcooling due to the time required to cooldown to target temperature with condenser steam dumps unavailable.
C is correct. Loss ofpower, no Reps, depressurization must be performed with PORVs.
A is incorrect because initial cooldown is performed at higher pressure prior to RCS reaching saturation.
B is incorrect because main spray will not be available with a LOOP.
o is incorrect because cooldown to target is performed quickly, even if using PORVs.
Knowledge of the operational implications of the following concepts as they apply to the SGTR: Natural Circulation Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
48 1
1 3.9 Path-2 and SO Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Saturday, January 05, 2008 12:00:28 PM 67
Source:
Cognitive Level:
Job Position:
Date:
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F BANK Source if Bank:
HIGHER Difficulty:
RO Plant:
HARRIS 3/2008 Previous NRC?:
NO Saturday, January 05, 2008 12:00:28 PM 68
(
~
.(..
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 38. 039 A4.01 001INEW//LOWERlIROIHARRIS/31200SINO Given the following:
A reactor trip has occurred from 100% power.
All systems functioned as designed.
Which ONE of the following describes the position of valves associated with the Main Turbine?
A. Throttle Valves - CLOSED Intercept Valves - CLOSED Reheat Stop Valves - OPEN B. Governor Valves - OPEN Intercept Valves - OPEN Reheat Stop Valves - CLOSED C~ Throttle Valves - CLOSED Intercept Valves - CLOSED Reheat Stop Valves - CLOSED D. Governor Valves - OPEN Intercept Valves - CLOSED Reheat Stop Valves - CLOSED C is correct. Reactor trip from 100% power will cause a turbine trip. Throttle, reheat stop, governor, and reheat intercept valves ALL receive close signals on turbine trip.
B is incorrect. A reactor trip will result in a turbine trip signal which will send a close signal to the Reheat Stop Valves. This would be correct for an overspeed condition on the turbine.
A is incorrect. A reactor trip will result in a turbine trip signal which will send a close signal to the Intercept valves. Plausible if applicant confuses this with an overspeed trip which does shut only shut two pairs of valves.
o is incorrect. A reactor trip will result in the governor valves going closed. Plausible if candidate confuses with some Westinghouse designs that leave the governor valves in the as-is position on a trip.
Saturday, January 05, 2008 12:00:28 PM 69
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to manually operate and/or monitor in the control room: Main steam supply. valves Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
17 2
1 2.9 MT text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:29 PM 70
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 40. 041 Kl.05 001/MODIFIED//HIGHERJ/ROIHARRIS/3/2008/NO Given the following:
The plant is at 10% power during a mid-cycle startup.
Steam Dumps are aligned in the Steam Pressure Control Mode of operation.
If the steam dump controller setpoint is raised by 20 psig, which ONE of the following describes the effect on the unit?
A. Steam Dump Valves open; RCS temperature rises; Reactor power lowers.
B~ Steam Dump Valves close; RCS temperature rises; Reactor power lowers.
C. Steam Dump Valves open; RCS temperature lowers; Reactor power rises.
D. Steam Dump Valves close; RCS temperature lowers; Reactor power rises.
A. Incorrect. Reactor temp rises and power lowers.
B. Correct. Reactor temp rises, power lowers and the dump valves will close.
C. Incorrect. Raising the pressure setpoint will cause less steam flow since the dumps will close which will heatup the RCS.
D. Incorrect. The dump valves will close, causing temperature to rise.
Knowledge of the physical connections and/or cause-effect relationships between the SDS and the following systems: RCS Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
34 2
2 3.5 SOS text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:29 PM 73
SYSTEM OPERATION AUTOMATIC STEAM PRESSURE CONTROL MODE Only the condenser steam dump valves (Group 1 and Group 2) will operate when the STEAM DUMP MODE SELECTOR is in the STM PRESS mode.
With the steam dump pressure controller, PK-464.l, in AUTO, the condenser steam dump valves will automatically operate to maintain steam header pressure. This assumes that the conditions below are met. These are the same conditions that were previously discussed as allowing manual operation of the controller in the STM PRESS mode.
STM PRESS selected - arming solenoid G9 interlock satisfied - arming solenoid P-12 interlock o
Group 1 solenoids: P-12 satisfied or bypassed o
Group 2 solenoids: P-12 satisfied 9
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F 41.045 K5.23 001/BANK//LOWER/IROIHARRIS/3/2008/NO Given the following:
The plant is at 20% power.
The crew is raising load lAW GP-005, Power Operation.
Which ONE of the following describes how Tave is maintained equal to Tref in accordance with approved plant procedures?
A. Rods are manually withdrawn above the 100% power insertion limit prior to the load increase, then placed in AUTO. Tave is maintained equal to Tref using automatic rod control and RCS boron dilution during the load increase.
B. RCS boron concentration is set at its 100% power value prior to the load increase.
Tave is maintained equal to Tref using rod withdrawal only.
C. Rods are manually withdrawn above the 100% power insertion limit prior to the load increase. Tave is maintained equal to Tref during the load increase using boron dilution only.
D~ Load is raised with Rod Control automatically maintaining Tave equal to Tref. RCS Boron concentration is adjusted as necessary to ensure rods stay within the Insertion Limits.
o is correct. Above 15% power the procedure directs rods to be placed in Auto.
A incorrect. Rods would not be withdrawn first and then placed in Auto.
B incorrect because if boron dilution was performed to the 100% value, rods would most likely be below the insertion limits.
C incorrect because the procedure just has the crew use a combination as necessary.
It is easier to control Tave using manual rod control than it is intermittently diluting.
Saturday, January 05, 200812:00:29 PM 74
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the operational implications of the following concepts as the apply to the MT/G System: Relationship between rod control and ReS boron concentration during T/G load increases
(
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
37 2
2 2.7 GP-005 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41.10 Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:29 PM 75
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 42. 054 AA2.04 001INEW//LOWER//RO/HARRIS/3/200SINO Given the following:
Time = 0 s Time = 10 s Time = 15 s Reactor was tripped due to a loss of both Main Feedwater Pumps.
Narrow Range level in all 3 SGs reached 5% prior to recovering slowly.
Current time.
Which ONE of the following describes the current operation of the AFW system for this event?
A. ONLY the MDAFW pumps are running; Manual control required to throttle control valves closed.
B. ONLY the MDAFW pumps are running; Manual control required to throttle control valves open.
C~ MDAFW AND TDAFW pumps are running; Manual control required to throttle control valves closed.
D. MDAFW AND TDAFW pumps are running; Manual control required to throttle control valves open.
C is correct. Low level in 2 of 3 SGs will start TDAFW (1 of 3 SGs for MDAFW). FCVs are aligned in the 100% open position and must be manually throttled to control flow.
A & B are incorrect, but plausible if candidate does not recognize conditions for automatic start of TDAFW.
D is incorrect but plausible if candidate believes manual control will be required to open theAFWFCV.
Saturday, January 05,200812:00:29 PM 76
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Proper operation of AFW pumps and regulating valves Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
50 1
1 4.2 AFW text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:29 PM 77
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 43. 056 A2.12 001INEW//HIGHERJIROlHARRIS/3/2008INO Given the following:
The plant is at 100% power.
An Extreme HI-HI level is received in Feedwater Heater 1A.
Which ONE of the following describes the impact on the unit and the action that is required?
A.
ONLY Feedwater Heater 1A is bypassed; Tave will INCREASE and must be restored to Tref by inserting control rods.
B. ONLY Feedwater Heater 1A is bypassed; Tave will DECREASE and must be restored to Tref by lowering turbine load.
C. Feedwater Heaters 1A and 2A are bypassed; Tave will INCREASE and must be restored to Tref by inserting control rods.
D~ Feedwater Heaters 1A and 2A are bypassed; Tave will DECREASE and must be restored to Tref by lowering turbine load.
o is correct. Bypass will be for both FWH 1A and 2A (1CE-330) as well as 1Band 2B.
With both LP FWH strings bypassed, power must be reduced to 70%.
A & B are incorrect but plausible if candidate believes an Extreme Hi-HI level signal will affect only FWHs 1A.
C is incorrect but plausible if candidate doesn't recognize that Tave will decrease.
Saturday, January 05, 2008 12:00:29 PM 78
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those mal-functions or operations: Opening of the heater string bypass valve Question Number:
38 Tier:
Group:
2 2
Importance Rating:
2.8 Technical
Reference:
OP-136, FWH text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
HARRIS NO Source if Bank:
Difficulty:
Plant:
Previous NRC?:
Make sure I got this right, I could not tell whether the A side or A and B side will be bypassed on a high level in only 1 side Source:
NEW Cognitive Level:
HIGHER Job Position:
RO Date:
3/2008 Saturday, January 05, 2008 12:00:29 PM 79
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 44. 056 G2.1.2 001IBANK//HIGHER//RO/HARRIS/3/2008/NO Given the following:
The plant was operating at 98% power when a loss of off-site power occurred.
Twenty minutes later, the following plant conditions exist:
RCS pressure is 2235 psig and stable.
RCS Loop THOT is 596°F in all 3 loops and lowering.
RCS Loop TCOLD is 552°F in all 3 loops and lowering.
Core exit TCs indicate approximately 600°F and lowering slowly.
Steam Generator pressures are approximately 1015 psig and stable.
Which ONE of the following describes the current plant conditions and the action required?
(Steam Tables are provided.)
A. Natural Circulation does not exist. Heat removal must be established by opening the condenser steam dumps.
B. Heat removal is being maintained by condenser steam dumps. Verify that Natural Circulation exists.
C. Natural Circulation does not exist. Heat removal must be established by opening the SG PORVs.
D~ Heat removal is being maintained by SG PORVs. Verify that Natural Circulation exists.
A. Incorrect. Condenser steam dumps are not available because off-site power is lost and Circ Water is unavailable.
B. Incorrect. Condenser steam dumps are not available.
C. Incorrect. With 5G pressure stable just above PORV setpoint and temperatures stable or lowering, heat removal is occurring.
D. Correct.
PORVs are open, and Natural Circulation is establishing.
Saturday, January 05,200812:00:29 PM 80
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Conduct of Operations: Knowledge of operator responsibilities during all modes of plant operation.
Question Number:
51 Tier:
1 Group:
1 Importance Rating:
3.0 Technical
Reference:
Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:30 PM 81
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 45. 058 AK3.02 001/NEW/ILOWER//RO/HARRIS/3/2008/NO Given the following:
The plant is in Mode 3.
A loss of DC Bus DP-1 B-SB has occurred.
The crew is performing actions of AOP-025, Loss of One Emergency AC Bus (6.9 kV) or ONE Emergency DC Bus (125V)
Which ONE of the following describes the reason for ensuring that letdown orifice valves are shut in accordance with AOP-025?
A. Prevent water hammer or flashing in the letdown line.
B:-" Prevent RCS leakage in excess of Technical Specification limits.
C. Minimize reduction in PZR level with loss of charging flow.
D. Prevent damage to the Regenerative Heat Exchanger.
B is correct. CS-11 will go shut however none of the upstream valves will. This will cause the letdown relief to lift resulting in RCS leakage in excess of tech spec limits.
A is incorrect. Plausible since this is a concern if the pressure control valve fails open causing letdown pressure to drop and flashing in the letdown stream to occur.
C is incorrect. Plausible since this is the reason letdown is isolated during the immediate actions ofAOP-018.
D is incorrect. Plausible since letdown would be isolated to prevent flashing in the regenerative heat exchanger, but this would occur due to a loss of cooling to the letdown stream.
Saturday, January 05, 200812:00:30 PM 82
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Actions contained in EOP for loss of dc power Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
52 1
1 4.0 AOP-025 Basis Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:30 PM 83
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 46. 059 A3.02 001INEW//LOWERlIROIHARRIS/3/200SINO For the Steam Generator Water Level Control System (SGWLCS), which ONE of the following describes this system's normal operation and program level input?
A. SGWLCS is a level dominant system that ultimately adjusts Feed Reg valve position by level error.
Program level is variable based on input from Turbine First Stage pressure.
B~ SGWLCS is a level dominant system that ultimately adjusts Feed Reg valve position by level error.
Program level is constant at 57% NR.
C. SGWLCS is a flow dominant system that ultimately adjusts Feed Reg valve position by mismatch in steam flow vs. feed flow.
Program level is variable based on input from Turbine First Stage pressure.
D. SGWLCS is a flow dominant system that ultimately adjusts Feed Reg valve position by mismatch in steam flow vs. feed flow.
Program level is constant at 57% NR.
B is correct. Level dominant system. Level error could be provided by program from FSTP but is zeroed out.
A is incorrect. Program level input does not come from Turbine First Stage Pressure.
C is incorrect. This describes a flow dominant system with it's input from Turbine First Stage Pressure.
D is incorrect. Program level input is correct, but the description is of a flow dominant system instead of a level dominant system.
Saturday, January 05, 2008 12:00:30 PM 84
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to monitor automatic operation of the MFW, including: Programmed levels of the S/G C*
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
18 2
1 2.9 SGWLC Text, pg 15 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:30 PM 85
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 47. 059 G2.4.50 002/BANKI/HIGHERI/RO/HARRIS/3/2008/NO Given the following:
"A" ESW Train is in service for OST-1214, ESW System Operability Train A Quarterly.
REM-01 SW-3500A, SW from WPB to Circ Water radiation monitor is in HIGH alarm.
Chemistry sample verifies high activity in the piping monitored by REM-01 SW-3500A.
Which ONE of the following describes the status of any release in progress, and the action required in accordance with AOP-005, Radiation Monitoring System?
A. The radioactive release will be automatically terminated.
Secure the "A" ESW Train.
B. The radioactive release will be automatically terminated.
Direct the Radwaste Operator to initiate isolation of individual components to locate the leak.
C. The radioactive release will NOT be automatically terminated.
Secure the "A" ESW Train.
D~ The radioactive release will NOT be automatically terminated.
Direct the Radwaste Operator to initiate isolation of individual components to locate the leak.
o is correct. AOP-005 directs a choice of actions, depending on which rad monitor is in alarm. For this monitor, WPB components will be checked for leaks and NSW stopped.
A is incorrect. Unlike many other rad monitors, this rad monitor does not have an automatic isolation on high alarm and would not align NSW to ESW because ESW does not supply WPB components.
B is incorrect.
This rad monitor does not have an automatic isolation on high alarm.
The action is correct.
C is incorrect. The release will not auto terminate. Action is incorrect but plausible if candidate believes a WPB component could be leaking into ESW.
Matches KA since rad monitor in high alarm indicates an Accidental Liquid Release is in progress. Response to this alarm requires recognition by the operator as to what automatic actions are supposed to occur in response to this alarm.
Saturday, January 05, 200812:00:30 PM 86
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Emergency Procedures I Plan Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
(
Question Number:
Tier:
Group:
Importance Rating:
61 1
2 3.3 Technical
Reference:
AOP-005, AOP-008 Proposed references to be provided to applicants during examination:
Learning Objective:
10 CFR Part 55 Content:
41.13 Comments:
None Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:30 PM 87
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 48. 059 K3.03 001IBANK//HIGHER//RO/HARRIS/3/2008/NO Which ONE of the following instruments failures will cause feedwater flow to the affected SG to INITIALLY lower? (Assume selected)
A. SG level fails low B. Feedwater flow fails low C. Steam pressure fails high D~ Steam flow fails low o is correct because if steam flow fails low, feed flow will indicate high. Therefore, Feed flow must be reduced by the FRV closing.
A is incorrect, SG level failing low will cause an increased level error, drive FRVs open, and raise level.
a is incorrect, FW flow failing low will can increased flow error, drive FRVs open initially, and increase SG level.
C is incorrect, Steam pressure failing high will cause calculated steam flow to increase.
Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/GS Question Number:
19 Tier:
Group:
2 1
Importance Rating:
3.5 Technical
Reference:
SGWLC text Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
HARRIS NO Source if Bank:
Difficulty:
Plant:
Previous NRC?:
This was written new but called a bank item because I am sure we have something similar, but did not find in our bank Source:
BANK Cognitive Level:
HIGHER Job Position:
RO Date:
3/2008 Saturday, January 05,2008 12:00:30 PM 88
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 49. 06002.1.32 001/NEW//LOWERJ/RO/HARRIS/3/2008/NO Given the following:
A Gaseous Waste release of Gas Decay Tank C is in progress.
An ALERT alarm is received on REM-3546, WPB Stack 5 PIG monitor.
Activity level is stable just above the ALERT setpoint.
Which ONE of the following describes the action required in accordance with OP-120.07?
A. The release MUST be stopped; release may continue under the same release permit after REM-3546 is determined to be operable and curie content of the release is determined to be within limits.
B. The release MUST be stopped; a new release permit must be generated prior to resuming the decay tank release.
C. The release may continue; if activity level approaches or exceeds the HIGH alarm setpoint, stop the release; release may continue under the same release permit after REM-3546 is determined to be operable and curie content of the release is determined to be within limits.
D~ The release may continue; if activity level approaches or exceeds the HIGH alarm setpoint, stop the release; a new release permit must be generated prior to resuming the decay tank release.
D is correct. ALERT does not require stopping release. HIGH requires stopping.
OP-120.07 and AOP-005 provide guidance.
A and B are incorrect. The release is not required to be stopped for an ALERT, only for a HIGH.
C is incorrect. The release may continue, but the procedure specifically calls for a new release permit if the release is stopped in this situation.
Saturday, January 05,200812:00:30 PM 89
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Conduct of Operations: Ability to explain and apply all system limits and precautions.
(
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
62 1
2 3.4 OP-120.07, AOP-005 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
(
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:30 PM 90
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 50. 061 G2.2.22 003IBANKIROBINSON 2007 NRC/LOWER//RO/HARRIS/3/2008/NO Given the following:
The plant is operating at 50% power.
The Turbine Driven AFW pump was taken OOS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago for bearing replacement.
Both Motor Driven AFW pump motors have been determined to be INOPERABLE due to a common cause failure analysis.
Which ONE of the following actions is required?
A'! Immediately initiate action to restore one AFW train to operable status; power operation is currently allowed with all three AFW Pumps Inoperable.
B. Restore at least 2 AFW Pumps to service within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or be in Hot Standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C. Restore at least 1 AFW Pump to service within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or be in Hot Standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. Enter the action of TS 3.0.3; be in at least HOT STANDBY within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> from the time it was determined that no AFW pumps were operable.
A is correct.
B is incorrect.
2 pumps not required to avoid a shutdown. Applicant may also confuse pumps versus trains or tlowpeths required for AFW system.
C is incorrect. No shutdown required if no AFW pumps available because there would be no source of feed during SO.
o is incorrect.
3.0.3 conditions would be met for most systems, but not in this case.
Equipment Control Knowledge of limiting conditions for operations and safety limits.
Question Number:
Tier:
Group:
Importance Rating:
20 2
1 3.4 Technical
Reference:
TS 3.7.1.2 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
43.2 Comments:
Saturday, January 05,200812:00:31 PM 91
Source:
Cognitive Level:
Job Position:
Date:
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F BANK Source if Bank:
ROBINSON 2007 NRC LOWER Difficulty:
RO Plant:
HARRIS 3/2008 Previous NRC?:
NO Saturday, January 05,200812:00:31 PM 92
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 51. 061 K5.0 1 002/BANK/IHIGHER//RO/HARRIS/3/2008/NO Given the following:
- The plant is in mode 3
- RCS heatup is in progress The heat transfer rate between RCS and the steam generators will.....
A'! increase as RCS temperature increases and AFW flow increases.
B. decrease as RCS temperature decreases and AFW flow increases.
C. increase as AFW temperature increases and AFW flow increases.
D. decrease as AFW temperature decreases and AFW flow increases.
A. correct - as the temperature differential increases the heat transfer rate increases B. incorrect - as the temperature differential stabilizes the heat transfer rate stabilizes C. incorrect - as the temperature differential decreases the heat transfer rate decreases D. incorrect - as the temperature differential stabilizes the heat transfer rate stabilizes q=mc(Delta T)
Knowledge of the operational implications of the following concepts as they apply to the AFW: Relationship between AFW flow and RCS heat transfer Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
21 2
1 3.6 GFES Heat Transfer, ran on simulator to verify.
Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Vogtle - Written by NRC 55.41.5 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source ifBank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:31 PM 93
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 52. 062 A1.03 002/BANKlHARRIS 2005 NRC/LOWERJIROlHARRIS/3/200SIYES Given the following:
The plant is at 100% power.
Recovery from a Loss of Instrument Bus 1DP-1A-S1 is in progress.
The crew has de-energized the associated Process Instrumentation Cabinet (PIC) in preparation for energizing Instrument Bus 1DP-1A-S1.
The crew is evaluating bistable status prior to energizing the bus.
Which ONE of the following describes the reason for checking bistable status?
A. When the Instrument bus is energized with the PIC deenergized, a reactor trip may occur due to 'de-energize to actuate' bistables becoming actuated. Checking other bistables ensures a Reactor Trip will not occur.
B:t When the PIC is energized after the Instrument Bus is energized, 'energize to actuate' bistables may experience a momentary inadvertent trip. Checking other bistables ensures an ESF actuation will not occur.
C. Bistables are checked to ensure that each parameter for Process or Protection goes to its required state when the Instrument Bus and PIC is energized.
D. Bistables are checked to ensure that all lights are out, verifying that the PIC normal and alternate supply breakers are open prior to reenergizing the Instrument Bus.
B is correct, directly from procedure, check bistables to ensure inadvertent actuation does not occur.
A is incorrect because the concern is energize to actuate bistables. Deenergize to actuate bistables would have caused a trip already.
C is incorrect. Bistables are checked for required state, but not prior to energizing a PIC.
D is incorrect. Bistables are checked by looking at the lights but this does not verify the alternate supply breakers are open. This is done by checking the breakers prior to reenergizing the Instrument Bus.
Saturday, January 05,200812:00:31 PM 94
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Effect on instrumentation and controls of switching power supplies Question Number:
Tier:
Group:
Importance Rating:
22 2
1 2.5 Reference(s) - OP-156.02 Proposed References to be provided to applicants during examination - None Learning Objective - LPAOP3-24 Obj 4c Question History - Harris 2005 10 CFR Part 55 Content - 41(b).10 Comments -
Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source ifBank:
Difficulty:
Plant:
Previous NRC?:
HARRIS 2005 NRC HARRIS YES Saturday, January 05, 2008 12:00:31 PM 95
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 53. 062 AK3.02 00I/NEW//HIGHER//RO/HARRIS/3/2008/NO Initial Plant Conditions:
Yesterday, a loss of ESW Header "A" occurred due to a failure shaft shear of the "A" ESW Pump.
The crew completed AOP-022, Attachment 1, Equipment Alignment Due to Loss of an ESW Header.
The crew implemented OWP-SW, Operations Work Procedure Service Water, for an extended loss of the "A" ESW header.
Current Plant Conditions:
A loss of off-site power occurs coincident with a safety injection actuation.
Which ONE of the following describes the alignment of ESW loads for the current plant condition?
A"! ESW will NOT be supplied to the "A" EDG.
"A" EDG has been disabled and will NOT automatically start.
B. ESW will NOT be supplied to the "A" EDG.
"A" EDG will automatically start, but must be manually tripped.
C. ESW will be supplied to the "A" EDG.
"A" EDG is disabled and will NOT automatically start.
D. ESW will be supplied to the "A" EDG.
"A" EDG will automatically start.
Saturday, January 05,200812:00:31 PM 96
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F A is correct. With loss of offsite power, NSW will no longer be supplying the "A" ESW header and AOP-022, Attachment 1 and OWP-SW would be implemented for a loss of an ESW pump and both would place the respective EDG in Maintenance Mode. In Maintenance Mode, ALL automatic starts of the EDG are disabled.
8 is incorrect but plausible if candidate does not recognize that auto starts of the EDG will be disabled for these conditions.
C is incorrect but plausible if candidate recognizes that the EDG will be disabled but doesn't recognize that LOSP disables NSW (normal supply) and that "8" ESW header, while available, does not cross-connect to supply the "A" EDG.
o is incorrect.
The EDG auto starts will be disabled and there will be no ESW flow to the EDG.
Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS Question Number:
53 Tier:
1 Group:
1 Importance Rating:
3.6 Technical
Reference:
Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 200812:00:31 PM 97
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 54. 063 K3.02 001/BANKlILOWER//RO/HARRlS/3/2008/NO Given the following:
The plant is in Mode 3.
AFW Pump 1A-SA is operating to provide secondary inventory.
DC Bus DP-1A-SA becomes de-energized.
Which ONE of the following describes the effect on the operating AFW pump?
A'! MCR control switch indication is extinguished.
Pump remains running.
MCR breaker control is lost B. MCR control switch indication is extinguished.
Pump remains running.
MCR breaker control is available C. MCR control switch indication is available.
Pump trips.
MCR breaker control is lost D. MCR control switch indication is available.
Pump trips.
MCR breaker control is available A is correct. Loss of DC Bus OP-1A-SA means control power lost to operating AFW pump. Switch indication and MCR control is lost, but pump remains running.
B is incorrect. MCR breaker control will NOT be available since OP-1A-SA supplies control power to the "A" AFWpump.
C is incorrect. The AFWpump will not trip and the lights will not be available. Breaker control will be lost.
o is incorrect. The AFWpump will not trip, the lights will not be available, and breaker control will not be available.
Saturday, January 05,200812:00:31 PM 98
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the effect that a loss or malfunction of the dc electrical system will have on the following: Components using de control power Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
23 2
1 3.5 DC Text, AFW text Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:31 PM 99
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 55. 064 K4.04 001INEW//LOWERI/ROIHARRlS/3/2008INO Which ONE of the following describes the MAXIMUM continuous rating of the Emergency Diesel Generators?
A. 6500 KW at a power factor of 0.8 leading B:t 6500 KW at a power factor of 0.8 lagging C. 7150 KW at a power factor of 0.8 leading D. 7150 KW at a power factor of 0.8 lagging Incorrect. Lagging power factor (VARS out/overexcited)
Correct.
Incorrect. Represents maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> overload rating Incorrect. Represents maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> overload rating.
Lower cog requires memorization of 2 facts; discriminates between continuous and 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating, and between leading and lagging PF Knowledge of ED/G system design feature(s) and/or inter-Iock(s) which provide for the following: Overload ratings Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
24 2
1 3.1 DE text, OP-155 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.41.5 Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:31 PM 100
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 56. 069 AK2.03 002/MODIFIED/ILOWERJ/RO/HARRIS/3/2008/NO Given the following:
The unit is in Mode 4.
Maintenance reports that the inner door on the Containment Emergency Airlock will not seal properly after leaving Containment.
Which ONE of the following describes the action required, if any, in accordance with Technical Specifications?
A. Immediately verify the outer door is closed.
B. Immediately initiate action to evaluate overall containment leak rate.
C~ Verify the outer door closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
D. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate a cooldown to Mode 5.
B. is correct. T. S. 3.6. 1.3 requires the outer door verified closed in one hour for these conditions.
A is incorrect because the requirement is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, not immediately.
The actions are consistent with standard TS action times
,C is incorrect because this action would only be required if more than one door was inoperable.
D is incorrect because mode 5 does not have to be achieved in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Mode 5 would be required within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, but only if the outer door could not be verified closed.
All of the options are plausible because they relate to the correct airlock door and T. S.
actions from LCO 3.6.1.3 are used..
Saturday, January 05,200812:00:31 PM 101
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the interrelations between the Loss of Containment Integrity and the following: Personnel access hatch and emergency access hatch Question Number:
Tier:
Group:
Importance Rating:
63 1
2 2.8 Technical
Reference:
TS 3.6.1.3 Proposed references to be provided to applicants during examination:
Learning Objective:
Cont Text Obj 10, 11 10 CFR Part 55 Content:
43.2 Comments:
None Source:
Cognitive Level:
Job Position:
Date:
MODIFIED LOWER RO 312008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:32 PM 102
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 57. 073 A4.02 002/BANK/ILOWER//ROIHARRIS/3/2008/NO Given the following The plant is at 100% power.
The MCR RM-11 has experienced a communications failure and is "locked up".
Which ONE of the following describes the status of the radiation monitors normally monitored at that terminal?
A"! All associated monitors can be monitored at the RWCR RM-11 terminal.
B. All associated monitors can ONLY be monitored at their associated RM-23.
C. All RM-23 monitors must be declared inoperable until the MCR RM-11 is operable.
D. All RM-23 monitors must be declared inoperable until they are being displayed by the ERFIS computer.
A. Correct.
The MCR and RWCR RM-11 's are paired as backups for each other.
B. Plausible if applicant does not know the pairing.
C. Plausible because the RM-11's monitor RM-23 functions but have no control function.
O. Plausible if applicant believes RM-23's must be displayed on anything other than their own readout.
Ability to manually operate and/or monitor in the control room Radiation monitoring system control panel Question Number:
25 Tier:
2 Group:
1 Importance Rating:
3.7 Technical
Reference:
RMS Student Text (pgs. 1, 2), OP-118, pg. 33 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.11 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:32 PM 103
C' QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 58. 074 EK1.06 001/NEW//HIGHER//ROfHARRIS/3/2008/NO Given the following:
The crew entered FRP-C.1 with the following conditions present:
( /
Core Exit temperature 717 degrees F RCS pressure 1650 psig----
The crew has exited FRP-C.1 with the following conditions present:
/.
Core Exit temperature 560 degrees F
\\
(,...R9~.Er.e~~~.!:.EU 225J~.§.ig__...
....._~
Which ONE of the following describes the condition of the RCS during the performance of FRP-C.1, Response to Inadequate Core Cooling?
A. Saturated upon entry to FRP-C.1; Saturated upon exit from FRP-C.1.
B. Saturated upon entry to FRP-C.1; Subcooled upon exit from FRP-C.1.
C. Superheated upon entry to FRP-C.1; Saturated upon exit from FRP-C.1.
D~ Superheated upon entry to FRP-C.1; Subcooled upon exit from FRP-C.1 D is correct. RCS superheated (temperature above saturation) when entering FRP-C.1. RCS subcooled at 1225 psig upon exit.
A is incorrect. Plausible if candidate doesn't recognize condtions for superheated vapor and subcooled liquid.
B is incorrect. Plausible if candidate doesn't recognize conditions for superheated vapor.
C is incorrect. Plausible if candidate doesn't recognize condtions for subcooled liquid Saturday, January 05,200812:00:32 PM 104
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the operational implications of the following concepts as they apply to the Inadequate Core Cooling: Definition of superheated steam Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
64 1
2 3.0 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.41 Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:32 PM 105
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 59. 076 A2.01 002/BANK/HARRIS 2005 NRCIHIGHERI/ROIHARRIS/3/2008NES Given the following:
The plant is operating at 55% power.
The following annunciator is received in the Control Room:
APP-ALB-002-7-2, SERV WTR PUMPS DISCHARGE LOW PRESS The RO notes that Cooling Tower Basin Level is decreasing rapidly.
Service Water header pressure is 45 psig and lowering.
One minute later, Service Water header pressure is 25 psig and continues to lower.
CTMU cannot maintain Cooling Tower Basin level.
The crew enters AOP-022, Loss of Service Water and completes the immediate actions.
APP-ALB-002-7-2 is still in and the Cooling Tower Basin Level continues to decrease rapidly.
RAB Operator reports that a large volume of water is gushing from overhead piping in the vicinity of 1SW-276, Headers A & B Return To Normal SW Header valve.
The area is inaccessible.
All automatic plant systems have functioned as designed.
Which ONE of the following describes the location of the leak, and the action required?
A':' Unisolable leak located in the Normal Service Water System; Trip the reactor and go to PATH-1.
B. Unisolable leak located in the Emergency Service Water System; Trip the reactor and go to PATH-1.
C. Isolable leak located in the Normal Service Water System; Ensure NSW is properly aligned to equipment listed in AOP-022, Attachment 1.
D. Isolable leak located in the Emergency Service Water System; Ensure ESW is properly aligned to equipment listed in AOP-022, Attachment 1.
Saturday, January 05,200812:00:32 PM 106
c QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F A Correct. Based on SW pressure indications, ESW should have automatically started and isolated ESW from NSW Cooling Tower level continuing to decrease therefore indicates a leak on NSW The report from the field indicates that the leak is nonisolable. Because suction cannot be maintained, and power is >P-10, the reactor will be tripped.
B Incorrect. The actions are correct but location is incorrect. Plausible if candidate fails to recognize that ESW would have automatically initiated and isolated from NSW in response to the lowering NSW pressure.
C Incorrect. Plausible since action is correct for an isolable leak, but based on field report of the leak location the leak is not isolable.
D Incorrect. Would be correct if the leak were isolable and on ESW.
Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Question Number:
26 Tier:
Group:
2 1
None HARRIS 2005 NRC HARRIS YES Source if Bank:
Difficulty:
Plant:
Previous NRC?:
BANK HIGHER RO 3/2008 Importance Rating:
3.5 Reference(s) - AOP-022, section 3.2 APP-ALB-002-7-2 Proposed References to be provided to applicants during examination -
Learning Objective -
10 CFR Part 55 Content - 41.10 Comments -
Source:
Cognitive Level:
Job Position:
Date:
Saturday, January 05, 200812:00:32 PM 107
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 60. 078 G2.1.28 053INEW//LOWER//RO/HARRIS/3/2008INO Which ONE of the following describes the operation of Service Air Header Isolation Valve, 1SA-506?
A. Closes automatically when Instrument Air header pressure decreases below 90 psig.
Automatically reopens on rising Instrument Air Header pressure.
B. Closes automatically when Service Air header pressure decreases below 90 psig.
Automatically reopens on rising Service Air Header pressure.
C~ Closes on signal from decreasing Instrument Air header pressure.
Will have to be manually reopened on rising Instrument Air Header pressure D. Closes on signal from decreasing Service Air header pressure.
Will have to be manually reopened on rising Service Air Header pressure C. Correct. At 90 psig in IA system, SA-506 shuts automatically in an attempt to protect the IA system if the fault is on the service air system..
A and B are incorrect because valve will not automatically open on increasing pressure.
D incorrect because the pressure is sensed on Instrument Air, not Service Air.
Conduct of Operations: Knowledge of the purpose and function of major system components and controls.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
27 2
1 3.3 ISA text Proposed references to be provided to applicants during examination: None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.41.5 Have written similar style, but this item examines where pressure is sensed Saturday, January 05,200812:00:32 PM 108
(
Source:
Cognitive Level:
Job Position:
Date:
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F NEW Source if Bank:
LOWER Difficulty:
RO Plant:
HARRIS 3/2008 Previous NRC?:
NO Saturday, January 05,200812:00:32 PM 109
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 61. 103 Al.Ol 001INEW//LOWER//ROIHARRIS/3/2008INO Given the following:
The plant is at 100% power.
An inadvertent Containment Spray actuation has occurred on Train "A".
Train "A" Containment Spray has been secured.
Containment pressure indicates (-)2.4 inches H20.
Which ONE of the following describes how Containment pressure will be restored to within limits?
A.
Containment Vacuum Relief System will automatically operate to restore Containment pressure to within technical specification limits. No operator action is required.
B:-" Containment Vacuum Relief System will automatically operate to restore Containment pressure to a value where Containment Normal Purge may be placed in service to restore pressure.
C. Containment Vacuum Relief System must be manually placed in service to restore pressure to within technical specification limits. Operation of Containment Normal Purge is not required.
D. Containment Vacuum Relief System must be manually placed in service to restore pressure to a value where Containment Normal Purge may be placed in service to restore pressure.
B is correct. System automatically operates to reduce pressure but check valve will close prior to T. S. pressure being reached. Mini-Purge must be used to reduce to within T. S. limits.
A is incorrect. Normal purge will be required to restore pressure inside containment.
C and D are incorrect. Plausible if candidate is unaware of check valve that will close prior to T. S. pressure being reached.
Saturday, January 05,200812:00:32 PM 110
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: Containment pressure, temperature, and humidity Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
28 2
1 3.7 CVS Text pg 18 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41
(
Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:32 PM 111
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 62. E04 EK2.2 002/BANKI/LOWERJ/ROfHARRIS/3/2008/NO Which ONE of the following correctly describes a method for confirmation of leak isolation in accordance with EPP-013, LOCA Outside Containment?
A. PZR level rising.
B:o" RCS pressure rising.
C. Safety Injection flow lowering.
D. RAB radiation levels lowering.
A is incorrect per EPP-013 because the break could be isolated with PZR level off-scale low B is correct. RCS pressure and visual identification, if available, are used to determine break isolation C is incorrect. SI flow will be lowering as pressure is rising, but it is not used as an indicator of isolation D is incorrect. RAB radiation levels are a consideration for attempting to identify and isolate a leak, but not used to determine isolation Knowledge of the interrelations between the (LOCA Outside Containment) and the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Question Number:
54 Tier:
1 Group:
1 Importance Rating:
3.8 Technical
Reference:
EPP-013 step 6/7 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.10 Comments:
This was modified editorially, correct answer is different than what is in the bank, but the conditions of the question were not changed Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:32 PM 112
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 63. E05 EA2.2 002/BANKJ/HIGHER/IRO/HARRIS/3/2008/NO Given the following:
The reactor was tripped on simultaneous loss of the Main Feedwater Pumps.
All AFW was subsequently lost.
RCS Bleed and Feed is in progress in accordance with FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
Core Exit Thermocouples have stabilized at an average of 595 of.
Main Feedwater Pump "A" has been started.
Containment pressure is 1.0 psig and stable.
Which ONE of the following describes the method and rate of establishing feedwater flow?
A':I Feed one Steam Generator at the MINIMUM controllable rate until WIDE range level is >15% using the respective Feedwater Control Bypass Valve.
B. Feed one Steam Generator at the MAXIMUM rate until NARROW range level is
>25% using the respective Feedwater Control Bypass Valve.
C. Feed all Steam Generators at the MINIMUM controllable rate until WIDE range level is >15% using the Feedwater Control Valves.
D. Feed all Steam Generators at the MAXIMUM rate until NARROW range level is
>25% using the Feedwater Control Valves.
A. Correct. This is the process when ICT's are stable.
B. Plausible since this is correct for ICT's rising.
C. Plausible since this is correct except for "all Steam Generators" and feedwater control valves.
D. Plausible since this is correct for ICT's rising except for "all Steam Generators" and feedwater control valves.
Saturday, January 05, 2008 12:00:33 PM 113
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to determine and interpret the following as they apply to the (Loss of Secondary Heat Sink) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
(
Question Number:
Tier:
Group:
Importance Rating:
55 1
1 3.7 Technical
Reference:
FRP-H.1, Attachment 1 Proposed references to be provided to applicants during examination:
Learning Objective:
10 CFR Part 55 Content:
41.10 Comments:
None Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:33 PM 114
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 64. ElO EA1.3 OOIINEW//LOWER//ROIHARRIS/3/2008INO Given the following:
A reactor trip and loss of off-site power have occurred.
The crew is performing a cooldown using EPP-007, Natural Circulation With Steam Void in Vessel (Without RVLlS).
Off-Site power has been restored.
Preparations are being made to start an RCP.
Which ONE of the following describes the minimum PZR level required for RCP restart in accordance with EPP-007, and the reason for the level?
A. 10% to ensure minimum inventory for adequate pressure control.
B. 25% to ensure minimum inventory for adequate pressure control.
C. 35% to ensure adequate volume for collapsing the void D'l" 65% to ensure adequate volume for collapsing the void o is correct. 65% will accommodate collapsing the void when the RCP is started A is incorrect but plausible since 10% is the level at which EPP-007 would direct initiation of Safety Injection.
B is incorrect but plausible since 25% is the minimum level required by EPP-007 to accommodate void growth (step 3.c.)
C is incorrect but plausible since 35% is the top of the range EPP-007 requires to accommodate void growth (step 3.c.)
Saturday, January 05,200812:00:33 PM 115
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to operate and / or monitor the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLlS) Desired operating results during abnormal and emergency situations.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
65 1
2 3.4 EPP-007, Step 1 Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41.10 Thought we had similar in Bank, could not locate Source:
NEW Source if Bank:
Cognitive Level:
LOWER Difficulty:
Job Position:
RO Plant:
Date:
3/2008 Previous NRC?:
Saturday, January 05,2008 12:00:33 PM HARRIS NO 116
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 65. Ell EK3.3 005/BANKlBVPS-1 2007 NRC/LOWERI/ROIHARRIS/3/2008INO Which ONE of the following describes the reason and requirements for depressurizing the RCS in accordance with EPP-012, Loss of Emergency Coolant Recirculation?
A'! To minimize RCS leakage; To depressurize the RCS maintaining MINIMUM RCS subcooling; To reduce CSIP pump flow.
B. To ensure SI Accumulator injection; To depressurize the RCS maintaining MINIMUM RCS subcooling; To terminate CSIP pump flow.
C. To minimize RCS leakage; To depressurize the RCS maintaining MAXIMUM RCS subcooling; To stabilize RCS temperature while attempting to restore makeup sources.
D. To ensure SI Accumulator injection; To depressurize the RCS maintaining MAXIMUM RCS subcooling; To stabilize RCS temperature while attempting to restore makeup sources.
A Correct. The depressurization is performed to decrease leakage, therefore decreasing makeup requirements.
B Incorrect. Setup for accumulator injection is performed later in the procedure after SG depressurization.
C Incorrect. Will not stabilize RCS temperature o Incorrect. Setup for accumulator injection is performed later in the procedure after SG depressurization, and will not stabilize RCS temperature.
Saturday, January 05, 2008 12:00:33 PM 117
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation)
Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
56 1
1 3.8 EPP-012 and basis Proposed references to be provided to applicants during examination:
Learning Objective:
Question History:
None 10 CFR Part 55 Content:
Comments:
55.41.10 Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
BVPS-I 2007 NRC HARRIS NO Saturday, January 05,200812:00:33 PM 118
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 66. G2.1.3 002IMODIFIED//LOWERJIRO/HARRlS/3/2008INO Given the following:
You are assigned as the RO on day shift.
You have been called for Fitness for Duty screening.
You must leave the Control Room for approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
lAW OMM-002, Shift Turnover Package, which ONE of the following is the minimum required for the shift relief?
Note:
(Attachment 14, Documentation of Short Term Assumption of Duties)
(Attachment 5, Control Operator Shift Turnover Checklist)
A. Oral turnover to the remaining Board Operator. Both watchstanders Initial 4. No log entry required.
B~ Oral turnover to the remaining Board Operator. Both watchstanders Initial 4 and document relief for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the Control Operator log.
C. Perform a turnover using Attachment 5. Both watchstanders Initial Attachment 14.
No log entry required.
D. Perform a turnover using Attachment 5. Enter the information in the Control Operators log, and sign the log over.
A-Incorrect. Required to documen relief for greater than one hour in the Control Operator log.
B-Correct. Relief> 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> requires log entry C-Incorrect. Short term assumption does not require turnover sheet, unless directed by the S-SO. Log entry would be required.
D-Incorrect. Do not need to do a turnover sheet or sign over the logs unless directed by the S-SO Saturday, January 05, 2008 12:00:33 PM 119
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of shift turnover practices.
Question Number:
Tier:
Group:
Importance Rating:
66 3
1 3.0 Reference(s) - OMM-002 Proposed References to be provided to applicants during examination - None Learning Objective -
Question History - Modified from Harris Bank 10 CFR Part 55 Content - 41.10 Comments -
Source:
Cognitive Level:
Job Position:
Date:
MODIFIED LOWER RO 3/2008 Source ifBank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:33 PM 120
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 67. G2.1.32 001INEWIIHIGHERlIROIHARRIS/31200SINO Given the following:
A power increase is in progress in accordance with GP-005, Power Operation.
Average Power Range Nls indicate 40% power.
Turbine power indicates 42% power.
Average Loop Delta T indicates 35% power.
Which ONE of the following describes the actions required in accordance with GP-005?
A. Power must be reduced less than 30% by all indications and a calorimetric performed to determine actual power.
B~ Power increase should be stopped and a calorimetric must be performed to determine actual power.
C. Power increase should be stopped and the PRNls adjusted to match turbine power.
D. Power increase may continue using turbine power and no further action is required unless turbine power and average PRNls deviate by 5% or greater.
B is correct. Over 30% power, a calorimetric will be performed if redundant power indications disagree by more than 5%. The power increase should be stopped in order to perform a calorimetric properly.
A in incorrect. Plausible if candidate misunderstands the 30% limit from the GPs.
Once over 30% a 5% mismatch requires a calorimetric, but it does not require reducing power back to <30%.
C is incorrect. Plausible since power would need to be stopped to adjust Nls and candidate may believe that adjusting Nls to match highest reading indication is the most conservative action.
o is incorrect. Plausible since per the procedure turbine power is the indication that would be used in this situation. Wrong since the 5% deviation requirement includes Average delta T indication, notjust turbine power and Nls.
Saturday, January 05, 2008 12:00:33 PM 121
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to explain and apply all system limits and precautions.
(
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
67 3
1 3.4 GP-005 P & L Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.41.10 Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 200812:00:33 PM 122
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
-~ 68. G2.2.12 001/BANKlILOWERJ/RO/HARRIS/3/2008/NO Which ONE of the following activities is considered ACCEPTABLE preconditioning of equipment related to performance of a surveillance on that equipment?
A.
Lubrication of a valve stem prior to each scheduled testing of the valve.
B:I Periodic or occasional venting of pumps prior to testing, not associated with the surveillance being performed.
C. Adjusting the bolt torque on a valve collar prior to stroke time testing of the valve.
D. Operation of a pump shortly before a test, if a situation could be avoided to operate the pump while maintaining plant and personnel safety.
A. Incorrect. Lubrication is not acceptable preconditioning.
B. Correct. If by coincidence venting occurs prior to the surveillance then this is acceptable.
It would only be unacceptable if this was a routine practice prior to testing the pump.
C incorrect. Changing torque is unacceptable.
o incorrect. Operation of the equipment to warm it up is not acceptable if it is preventable or not required for plant or personnel safety.
Knowledge of surveillance procedures.
Question Number:
69 Tier:
3 Group:
2 Importance Rating:
3.0 Technical
Reference:
OMM-007 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.10 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source ifBank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,2008 12:00:34 PM 123
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 69. G2.2.26096/BANKJ/LOWERJ/RO/HARRIS/3/2008/NO Given the following:
The unit is in Mode 6.
Refueling operations are in progress.
The 30th fuel assembly is being loaded into the core.
According to GP-009, Refueling Cavity Fill, Refueling, and Drain of the Refueling Cavity, Modes 5-6-5, which ONE of the following would require fuel loading operations to be stopped immediately?
A'! Communications is lost between Containment and the Control Room.
B. Water in the Spent Fuel Pool in not clear enough to view the Fuel top Nozzles without supplemental lighting.
C. Boron concentration drops by more than 10 ppm as determined by two successive samples of Reactor Coolant.
D. An unanticipated rise in count rate by a factor of two occurs on 1 of 2 operable Source Range channels during any single loading step.
O. incorrect - Must have an increase of a factor of two on both responding SR channels to stop fuel movement. Examinee may confuse with a factor of 5 on any SR channel to stop fuel movement.
A. correct - If communication is lost between the control room and containment then fuel loading must stop.
B. incorrect - Fuel handling is only required to be stopped when top nozzles are not viewable with supplemental lighting. Examinee may confuse the precaution.
C. incorrect - The number 10 comes from RHR temperature rising 10 deg F Examinee may confuse the precaution.
Saturday, January 05,2008 12:00:34 PM 124
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of refueling administrative requirements.
(
Question Number:
68 Tier:
3 Group:
2 Importance Rating:
2.5 Technical
Reference:
FHP-014, GP-009, section 4.0, P&L 2 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
43.6,41.10 Comments:
Harris Bank from WBN Bank Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:34 PM 125
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 70. G2.3.2 004IMODIFIEDNCS 2006 NRC/HIGHERI/ROIHARRIS/3/2008INO Given the following conditions at a work site:
Airborne activity - 5 DAC Radiation level - 40 mrem/hr.
Radiation level with shielding - 20 mrem/hr.
Time to conduct task WITH respirator - 40 minutes.
Time to conduct task WITHOUT respirator - 30 minutes.
Assumptions:
The airborne dose with a respirator will be zero.
A dose rate of 40 mrem/hr will be received while placing the shielding. Assume no benefit from shielding during placement.
All tasks will performed by one worker.
Shielding can be placed in 15 minutes with or without a respirator.
The shielding will not be removed.
Which ONE of the following would result in the lowest whole body dose?
A. Conduct task WITHOUT respirator or shielding.
B. Conduct task WITH respirator and WITHOUT shielding.
C~ Place shielding while wearing respirator and conduct task WITH respirator.
D. Place shielding while wearing respirator and conduct task WITHOUT respirator.
DISTRACTORS:
A INCORRECT
.(30/60)*40 + (2.5*5*.5) =20 + 6.25 =26.25 B INCORRECT
.(40/60)*40 + 0 =26.67 C CORRECT (15/60)*40 + (40/60)*20 + 0 = 10 + 13.33 = 23.33 D INCORRECT (15/60)*40 + (30/60)*20 + (2.5*5*.5) =10 + 10 + 6.25 =26.25 Saturday, January 05,2008 12:00:34 PM 126
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of facility ALARA program.
Question Number:
71 Tier:
3 Group:
3 Importance Rating:
2.5 Technical
Reference:
NEED REF Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.13 Comments:
VCS 2006 Developed by NRC Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
VCS 2006 NRC HARRIS NO Saturday, January 05,200812:00:34 PM 127
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 71. G2.3.4 002INEW//LOWER//ROIHARRIS/3/2008INO Per DOS-NGGC-0004, Administrative Dose Limits, which ONE of the following describes the annual Progress Energy dose limit and the MINIMUM authorization required for an individual to exceed that limit?
A. 2000 mrem; The individual's Progress Energy supervisor B~ 2000 mrem; Site Vice President C. 4000 mrem;
. The individual's Progress Energy supervisor D. 4000 mrem; Site Vice President B is correct. Per step 9.7.7 of DOS-NGGC-004 and Attachment 2, Site VP is required to authorize exceeding 2000 mrem.
A is incorrect. Plausible since an individual's Progress Energy supervisor is required to sign the Dose Limit Change request (step 9.7.1), but Site VP is the authorization required.
C and D are incorrect, but plausible since 4000 mrem is the annual total dose limit.
Saturday, January 05,200812:00:34 PM 128
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
70 3
3 2.5 DOS-NGGC-004, Attachment 1 Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
Comments:
55.41.10 Have written similar but none for PGN available Source:
Cognitive Level:
Job Position:
Date:
NEW LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:34 PM 129
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 72. G2.4.10 002/NEW/IHIGHERJ/RO/HARRIS/3/2008/NO Given the following:
The unit is at 100% power.
Instrument Air is aligned in SEQUENCE 3 with all lACs available.
The following alarm is received:
ALB-002-8-5, COMPUTER ALARM AIR SYSTEMS The RO determines that the alarm was initiated by Instrument Air pressure.
Instrument Air pressure is 120 psig.
Which ONE of the following describes the status of the Instrument Air system, and the action required for the current condition?
A':' Instrument Air System pressure is higher than normal; 1C air compressor should be the only air compressor running; determine if air compressor 1A or 1B is running.
B. Instrument Air System pressure is higher than normal; either 1A and/or 1B air compressor should be the only air compressor running; determine if 1C air compressor is running.
C. Instrument Air System pressure is lower than normal; 1C air compressor should be the only air compressor running; determine if it is tripped, and verify the automatic operation of 1A and/or 1B air compressors.
D. Instrument Air System pressure is lower than normal; 1A or 1B air compressor should be the only air compressor running; determine if it is tripped, and verify the automatic operation of 1C air compressor.
A is correct. 120 psig is higher than normal.
In sequence 3, 1C is running. A and B IACs should not be running.
B is incorrect. Pressure is higher than normal, but 1A and/or 1B running would be consistent with Sequence 1 or 2, not with Sequence 3.
C is incorrect. Actions would be correct for sequence 3 if candidate believes air pressure is too low vice too high.
D is incorrect. Actions would be correct for sequence 1 or 2 if air pressure is too low.
Saturday, January 05,2008 12:00:34 PM 130
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of annunciator response procedures.
Question Number:
72 Tier:
3 Group:
4 Importance Rating:
3.0 Technical
Reference:
ALB-002, 8-5 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
43.2 Comments:
Source:
Cognitive Level:
Job Position:
Date:
NEW HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:34 PM 131
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 73. G2.4.29002!MODIFIED//HIGHERlIRO/HARRIS/3/2008/NO Given the following:
At 1302, a steam generator tube leak is identified.
At 1318, a plant shutdown is commenced due to exceeding TS leakage limits.
At 1319, an Unusual Event is declared by the Site Emergency Coordinator.
(SEC)
At 1321, a reactor trip occurs.
At 1327, the crew identifies SG "A" as the ruptured SG.
At 1330, an ALERT is declared by the SEC.
At 1340, the Emergency Notification Form was completed and signed by the SEC.
Which ONE of the following describes the latest time that the initial notification to State/County officials AND the NRC is due?
A.
8:1 C.
D.
State/County 1334 1334 1345 1345 NRC 1334 1419 1419 1430 B is correct.
15 minutes after declaration of event to notify state. One hour to notify NRC A is incorrect. Plausible if candidate believes NRC must also be informed within 15 minutes.
C is incorrect. Plausible if candidate believes the 15 minute requirement doesn't apply to UE's but only Alerts and higher but still correctly identifies need to properly inform NRC.
o is incorrect. Plausible if candidate believes notification time limits should be from the time of the ALERT, not the UE.
Saturday, January 05,200812:00:34 PM 132
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge of the emergency plan.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
75 3
4 2.6 E-Plan Proposed references to be provided to applicants during examination:
None Learning Objective:
Question History:
10 CFR Part 55 Content:
55.41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
MODIFIED HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05, 2008 12:00:34 PM 133
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 74. G2.4.48 002IBANKIROBINSON 2007 NRC/HIGHER//ROIHARRIS/3/2008/NO Given the following:
One Shutdown Bank-A, Group 2 Rod has dropped into the core.
The crew is recovering the dropped rod.
ALB-13-7-1, ROO CONT SYSTEM URGENT FAILURE is received.
Which ONE of the following describes the reason for the alarm and the plant response?
A. Withdrawing the rod while the remaining Group 2 Lift Coils are deenergized.
Rod withdrawal is blocked until the alarm is reset.
B. Initiation of an "out" signal to SO Bank "A" Rods, and its Group 1 rods do not move.
Rod withdrawal is blocked until the alarm is reset.
C. Withdrawing the rod while the remaining Group 2 Lift Coils are deenergized.
Rod withdrawal is unaffected and recovery may continue.
O~ Initiation of an "out" signal to SO Bank "A" Rods and its Group 1 rods do not move.
Rod withdrawal is unaffected and recovery may continue.
o is correct. Urgent failure occurs when opposite group does not respond to command. The alarm does block rod motion in auto or manual but for these conditions Rod Control will be selected to SO Bank A, which will not be blocked.
A is incorrect.
Incorrect reason and requirement for alarm reset. Credible because the reason for the alarm may not be readily apparent; it requires system knowledge to determine why the alarm occurred. The alarm will occur but it is due to the failure of the opposite group to move.
B is incorrect. Credible because failure is correct. Wrong because the alarm does not have to be reset for withdrawal.
C is incorrect. Credible because rod withdrawal is unaffected. Wrong because cause of the alarm is incorrect.
Saturday, January 05, 2008 12:00:35 PM 134
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.
(
Question Number:
74 Tier:
3 Group:
4 Importance Rating:
3.5 Technical
Reference:
ALB-13-7-1, AOP-001 Proposed references to be provided to applicants during examination:
None Learning Objective:
10 CFR Part 55 Content:
41.7, 10 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK HIGHER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
ROBINSON 2007 NRC HARRIS NO Saturday, January 05, 2008 12:00:35 PM 135
(
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F
- 75. G2.4.6 008/BANK//LOWERlIRO/HARRIS/3/2008/NO Given the following:
The Unit has experienced a SBLOCA.
EPP-009, Post LOCA Cooldown and Depressurization is in progress.
All RCPs are running.
RCS pressure is 1690 psig.
An RCS cooldown has been initiated by dumping steam to the atmosphere.
Which ONE of the following describes the optimum RCP configuration, and the basis for this configuration?
A. All RCPs should be stopped; minimize RCS inventory loss when the break uncovers.
B. One RCP should be stopped; produces effective heat transfer, provides boron mixing for RHR operations, and provides RCS pressure control.
D'l'" Two RCPs should be stopped; minimizes RCS heat input, and still produces effective heat transfer and RCS pressure control.
C. All RCPs should be left running; ensures symmetric heat transfer to the S/Gs, aids in RCS pressure control, and prevents steam voiding in the Reactor vessel head.
..l--
.J D is correct. Step 15 of EPP-009 would have both RCPs stopped and leave only one RCP running to ensure heat transfer and mixing of RCS.
A is incorrect, but plausible since this is the action and reason for stopping RCPs per the RCP Trip foldout criteria.
B is incorrect, but plausible since action is correct but reason is incorrect since boron mixing for RHR is not a concern.
C is incorrect, but plausible if candidates believe the best course of action is to leave all Reps running.
Saturday, January 05,200812:00:35 PM 136
QUESTIONS REPORT for HARRIS 2008 - WORKSHEET 1 REV F Knowledge symptom based EOP mitigation strategies.
Question Number:
Tier:
Group:
Importance Rating:
Technical
Reference:
73 3
4 3.1 EPP-OOg Proposed references to be provided to applicants during examination:
None Learning Objective:
Question Source:
Bank Question History:
Surry Question Cognitive Level:
Lower 10 CFR Part 55 Content:
41 Comments:
Source:
Cognitive Level:
Job Position:
Date:
BANK LOWER RO 3/2008 Source if Bank:
Difficulty:
Plant:
Previous NRC?:
HARRIS NO Saturday, January 05,200812:00:35 PM 137