ML043170098
| ML043170098 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/22/2004 |
| From: | Christman R Entergy Nuclear Indian Point 2, Entergy Nuclear Northeast |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Shared Package | |
| ML041450472 | List: |
| References | |
| Download: ML043170098 (200) | |
Text
Page 1 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 WA # 000008 AK3.03 Importance Rating 4.1 4.6 Knowledge of the reasons for actions contained in EOP for PZR vapor space accident/LOCA Proposed Question: Common #1 Given the following plant conditions:
0 The Unit has just tripped from 100% power due to a small break LOCA that was caused by a stuck open Pressurizer PORV and Block Valve.
During implementation of E-1, Loss of Reactor or Secondary Coolant, subcooling lowers to 12°F.
The team has just tripped all the Reactor Coolant Pumps.
Which of the following indicates the reason the RCPs were tripped by the team?
A. To minimize RCS inventory loss.
B. To minimize the cooldown rate.
C. To prevent RCP damage from cavitation.
D. To remove pump heat input to RCS Proposed Answer:
A. To minimize RCS inventory loss.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
EOP Executive Volume RCP Trip Criteria Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-010-540 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
Page 2 of 241 New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (3) 55.43 Comments:
Page 11 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 000022 AK1.02 Importance Rating 2.7 3.6 Knowledge of the operational implications of the relationship of charging flow to pressure differential Proposed Question: Common #2 The position of HCV-142, Charging Line Flow Control Valve, is changed to vary RCP seal injection flow. IF HCV-142 is closed slightly, THEN:
Charging Pump RCP Seal Charging Flow to Discharge Press Injection Flow Regen Hx A. Increases Increases Decreases B. Increases Decreases Increases C. Decreases Increases Decreases D. Decreases Decreases Increase Explanation (Optional):
Technical Reference(@: (Attach if not previously provided)
IP2-SOD-18 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-O30-30105/30106 (As available)
Question Source: Bank # INPO 26073 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Prairie Island 1 9/1/2003
Page 12 of 241 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X c
10 CFR Part 55 Content: 55.41 (3)(8)(10) 55.43 Comments:
Stem reworded to make plant specific
Page 15 of 241 Examination Outline Cross-reference: Level RO SRO
~L Tier ## 1 7 Group # 1 WA # 000025 AK1.01 Importance Rating 3.9 4.3 Knowledge of the operational implications of a loss of RHRS during all modes of operations Proposed Question: Common #3 Given the following conditions:
0 The Unit is in Mode 6.
0 RCS temperature is 125°F.
0 21 RHR Pump and 21 RHR Heat Exchanger are in service.
0 Reactor Vessel level is 68' with Reactor Head detensioned.
HVC-638, 21 RHR Heat Exchanger Flow Control Valve, drifts CLOSED due to an electrical problem.
Assuming NO action by the operating team, which one of the following describes the effect of this failure on plant operation?
A. Decrease of NPSH to 21 RHR pump due to increased temperature.
B. OPS actuation due to over pressurization of the RCS.
C. Loss of RHR letdown resulting in loss of VCT level and operating charging pump.
D. 21 RHR Pump will supply RCS cooling through 22 RHR Heat Exchanger.
Proposed Answer:
A. Decrease of NPSH to 21 RHR pump due to increased temperature.
Explanation (Optional):
A. Correct, RCS will heat up due to pumps heat and decay heat B. Incorrect, RCS pressure will not increase with Rx Head detensioned C. Incorrect, RHR letdown will NOT be lost since upstream of HVC-638 D. Incorrect, 22 RHR Heat Exchanger would need to be manually aligned Technical Reference(s): (Attach if not previously provided) 4.' IP2-SOD-020
Page 16 of 241 Proposed References to be provided to applicants during examination: Graph Learning Objective: SYS-C-O42-115/126 (As available)
Question Source: Bank ##
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (8) 55.43 Comments:
New Question
Page 17 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 a Group # 1 WA ## 000026 AA1.07 Importance Rating 2.9 3.0 Ability to operate and/or monitor flow rates to the components and systems that are serviced by the CCWS; interactions among the components Proposed Question: Common #4 Given the following conditions:
A loss of all AC power has occurred 0 After 15 minutes, power was restored to Busses 5A and 6A 0 The actions of ECA-0.1, Loss of All AC Power Recovery Without SI Required, are being performed to start a CCW Pump Why is MOV-789, RCP Thermal Barrier Return Isolation Valve verified closed prior to restarting the CCW Pump?
A. Reduce CCW System heat loads to the minimum based on SW loads.
B. Prevent damage to the RCP bearings due to excessive cooldown rate.
C. Maximize flow to the CVCS components for reestablishing charging, letdown and seal return.
D. Protect CCW System availability by precluding steam formation in the CCW piping.
Proposed Answer:
D. Protect CCW availability by precluding steam formation in the CC piping.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ECA-0.1 Background Step 1, Page 11 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Page 18 of 241 Question Source: Bank # INPO 19416 Modified Bank # (Note changes or attach parent)
New X I P2 Question History: Kewaunee 1 12/11/2000 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7)(14) 55.43 Comments:
Page 47 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 22 Group # 2 WA # 000032 AK2.01 Importance Rating 2.7 3.1 Knowledge of the interrelations between the Loss of Source Range Nuclear Instrumentation and the power supplies, including proper switch positions Proposed Question: Common #5 Unit 2 is stable at the POAH with Physics testing in progress.
0 PR channel N-44 has been removed from service due to an instrument failure.
0 A fault occurs that results in a loss of Instrument Bus 21.
Which one of the following describes the effect on SR indications and the basis for this?
A. SR channel N-32 will remain de-energized due to the P-10 interlock, N-31 will have no power due to the loss of Instrument Bus 21.
B. SR channel N-31 will re-energize and N-32 will remain de-energized due to the loss of Instrument Bus 21.
C. SR channels N-31 and N-32 will remain de-energized since the 2/2 permissive cannot be met due to the loss of power to N-36.
D. SR channel N-31 will de-energized due to the loss of 21 Instrument Bus and N-32 will re-energize due to the loss of P-10 interlock.
Proposed Answer:
A. SR channel N-32 will remain de-energized due to the P-10 interlock, N-31 will have no power due to the loss of Instrument Bus 21.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-AOP-IB-1 Page 53 SD-13 Page 78 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Page 48 of 241 Question Source: Bank # INPO 25731 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Surry 1 311412003 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Question, answer and distracters modified to make plant specific
Page 49 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 23 Group # 2 WA # 000037 AK1.02 Importance Rating 3.5 3.9 Knowledge of the operational implications of the leak rate vs. pressure drop concept as it applies to a Steam Generator Tube Leak Proposed Question: Common #6 Unit 2 is shutting down from 100% power in response to a steam generator tube leak. What would be the expected trend of the leak rate during the shutdown and why?
(Assume the flaw size remains constant.)
A. Leakage would increase because air ejector flow rate would decrease.
B. Leakage would decrease because primary to secondary pressure difference is reduced.
C. Leakage would remain the same because isotopes analyzed are independent of power.
D. Leakage would decrease due to reduced steam flow from the steam generator.
Proposed Answer:
B. Leakage would decrease because primary to secondary pressure difference is reduced Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning 0bjective: (As available)
Question Source: Bank # INPO 20591 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Point Beach 1 2/2/2002
Page 50 of 241 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis
'v 10 CFR Part 55 Content: 55.41 (8)(10) 55.43 Comments:
Page 51 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 24 Group # 2 Rev per TF KIA # 000059 AK3.01 Importance Rating 3.5 3.9 Knowledge of the reasons for the termination of a release of radioactive liquid as it applies to the Accidental Liquid Radwaste Release Proposed Question: Common #7 Given the following plant status:
A release of 14 Waste Distillate Storage Tank (WDST) is in progress The release permit was approved for the release of the total contents of 14 WDST 0 After proper recirculation of 14 WDST, chemistry obtained a sample of the tank contents to be used on the release permit At the start of the release, R-54, Unit 1 Liquid Waste Distillate Monitor, was in service With the release still in progress, what are the required actions to be taken in accordance with SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases, should R-54 become inoperable?
'V A. Continue with the release, declare R-54 inoperable, direct chemistry to commence taking periodic samples of 14 WDST for the duration of the release, and submit new release permit if any changes are found to existing permit B. Terminate the release, declare R-54 inoperable, verify actual volume released prior to termination is consistent for expected flow rate during release of 14 WDST, and then continue with the release.
C. Terminate the release, have chemistry take two independent samples of 14 WDST, have two persons (RO/CRS) independently verify the discharge rate calculations and have two persons independently verify the discharge valve lineup prior to recommencing the release.
D. Continue with the release since 14 WDST was sampled prior to release, and the sample results indicated a release activity less than the maximum normally allowable for the entire contents of the tank.
Proposed Answer:
C. Terminate the release, have chemistry take two independent samples of 14 WDST, have two persons (RO/CRS) independently verify the discharge rate calculations and have two persons independently verify the discharge valve lineup prior to recommencing the L release.
Explanation (Optional):
Page 52 of 241 Technical Reference(s): (Attach if not previously provided)
L SOP-5,1.2 Pages 1,2 SOP-5.1.5 Pages 5,7 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-051-137 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES NEW Question History: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) (10)
- Comments:
Page 3 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 2 Group # 1 KIA # 000009 EA2.34 Importance Rating 3.6 4.2 Ability to determine or interpret conditions for throttling or stopping HPI as they apply to a small break LOCA Proposed Question: Common #8 Given the following plant conditions:
0 The Unit has tripped from 100% due to a small break LOCA.
0 Conditions have stabilized and operators are evaluating the criteria for terminating Safety Injection.
0 Containment pressure has stabilized at 1.5 psig.
0 Containment Radiation levels peaked at 17 Whr.
Which one of the following conditions would PREVENT SI termination per E-1, "Lossof Reactor or Secondary Coolant"?
A. RCS subcooling is 25°F and stable.
- 6. Pressurizer level is 10% and stable.
C. Only one Steam Generator level is >lo% narrow range.
D. RCS pressure is 1700 psig. and stable Proposed Answer:
- 6. Pressurizer level is 10% and stable.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
E-1 Step 11 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-011-540 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Page 83 of 241 Examination Outline Cross-reference: Level RO SRO
- 40 Tier #
Group #
2 1
Rev per TF - check WA ## 056 A2.04 Importance Rating 2.6 2.8 Ability to (a) predict the impacts of a Loss of condensate pump on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of the loss of condensate pumps Proposed Question: Common #9 Unit 2 was operating with 21 and 23 condensate pumps in service and 22 Condensate pump in standby. 21 condensate pumps subsequently trips due to a motor fault Given the following initial plant conditions:
Reactorpower - 60%
MBFP suction pressure - 450 psig All 4 SG levels, 48 - 49%
Tave is 554°F What is the affect of 21 Condensate Pump tripping and what are the appropriate u operator actions?
A. Reduced MBFP suction pressure, manually start 22 Condensate pump and open Flexitest switches for 22 Condensate Pump B. 22 Condensate Pump starts Automatically, open Flexitest switches for 22 Condensate Pump C. Reduced MBFP suction pressure, manually start 22 Condensate pump and open Flexitest switches for 22 and 23 Condensate Pump D. 22 Condensate Pump starts Automatically, open Flexitest switches for 22 and 23 Condensate Pump Proposed Answer:
- 6. 22 Condensate Pump starts Automatically, open Flexitest switches for 22 Condensate Pump Explanation (Optional):
A. 22 Cond Pumps starts automatically B. Correct C. 22 Cond Pumps starts automatically and Flexitest switches are only opened for 22 Cond Pump D. Flexetex switches only opened for 22 Cond Pump
Page 84 of 241 Technical Reference(s): (Attach if not previously provided) 2-POP-1.3 Page 34 4 2-A0P-FW-1 Pages 25,28 2-SOP-20.2 Pages 6,7, 13 Proposed References to be provided to applicants during examination: NONE Learning Objective: AOP-C-FW1-11503 (As available)
SYS-C-200-364 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 c Comments:
New Question
Page 53 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 c
25 Group # 2 Rev per TF KIA ## 000068 AAI .03 Importance Rating 4.1 4.3 Ability to operate and / or monitor the S/G levels as they apply to the Control Room Evacuation Proposed Question: Common #lo The Team has evacuated the Control Room in accordance with 2-AOP-SSD-1, CONTROL ROOM INACCESSABILITY SAFE SHUTDOWN CONTROL.
Which ONE of the following describes the preferred method of maintaining SG inventory during the cooldown per 2-AOP-SSD-l?
A. Feed all 4 SGs to maintain corrected Wide Range level at approximately 63 - 68% to ensure symmetric heat removal B. Feed 21 and 22 SGs unless explicitly directed to steam from the intact SGs by the EOPs or FRPs since they are the only SGs with reliable backup level indication at the Safe shutdown Panel L-'
C. Feed 22 and 23 SGs unless explicitly directed to steam from the intact SGs by the EOPs or FRPs since they supply steam to 22 Auxiliary Boiler Feed Pump D. Feed any combination of SGs that ensures greater than 400 gpm total auxiliary feedwater flow to maintain adequate heat sink Proposed Answer:
B. Feed 21 and 22 SGs unless explicitly directed to steam from the intact SGs by the EOPs or FRPs since they are the only SGs with reliable backup level indication at the Safe shutdown Panel Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-AOP-SSD-1 Attachment 2 Page 5 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Page 54 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Page 77 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 c
37 Group # 1 WA # 026 K4.06 Importance Rating 2.8 3.2 Knowledge of the CSS design feature@)and/or interlock(s) which provide for Iodine scavenging via the CSS Proposed Question: Common #11 Containment Spray Pumps are designed to protect the Containment Structure against overpressure conditions. In addition, Tri-Sodium Phosphate (TSP) Baskets are located inside containment on the 46' El. for introduction into the Containment environment during the recirculation phase in order to maintain the Containment Sump pH basic.
What is the reason for controlling the pH?
A. Maintains Iodine in solution.
B. Maintains Hydrogen in solution.
C. Reduces Iodine concentration in solution.
D. Reduces Hydrogen concentration in solution.
Proposed Answer:
A. Maintains Iodine in solution.
Explanation [Optional):
Technical Reference(@: (Attach if not previously provided)
ES-1.3 Background Page 62 ES-1.2 Background Page 79 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-102 - KR 158b (As available)
Question Source: Bank # INPO 20630 Modified Bank # (Note changes or attach parent)
New Yes I P2 Question History: Point Beach 1 2/2/02
Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis c
10 CFR Part 55 Content: 55.41 (7) 55.43 Comments: Question modified to make plant specific for Na3P04baskets
Page 9 of 241 Examination Outline Cross-reference: Level RO SRO L-Tier # 1 5 Group # 1 KIA # 000015 AK3.02 Importance Rating 3.0 3.1 Knowledge of the reasons for responses of CCW lineup and flow paths to RCP oil coolers during RCP malfunctions Proposed Question: Common #12 Unit 2 is operating at 100% power. The following indications are noted:
Annunciator "SAF 3-1, Reactor Coolant Pump Motor Bearing Oil High Level" is lit.
21 RCP Upper Radial Bearing temperature is currently reading 215°F and rising.
Component Cooling Water Surge Tank level is 49% and lowering.
21 RCP seal injection flow is 7 gpm.
21 RCP No. 1 seal return is 1.2 gpm.
Which of the following describes the required action and the reason for the action that would explain all of the above abnormal conditions?
A. Reactor must be tripped and 21 RCP stopped because the high oil level is preventing proper oil flow from the bearings.
B. MOV-769/797, Component Cooling Supply to RCPs, must be shut because 21 motor bearing oil cooler is leaking.
C. Reactor must be tripped and 21 RCP stopped because its oil has been emulsified with CCW and this has affected bearing lubrication D. Continue operation and initiate monitoring for abnormal RCP bearing temperatures.
Proposed Answer:
C. Reactor must be tripped and 21 RCP stopped because its oil has been emulsified with CCW and this has affected bearing lubrication Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-A0 P-RCP-1 ARP SAF Window 3-1 ARP SCF Window 1-6
Proposed References to be provided to applicants during examination: NONE c Learning Objective: SYS-C-O13-40/41 (As available)
AOP-C-RCP1-1601039 Question Source: Bank # INPO 26198 Modified Bank # X (Note changes or attach parent)
New X IP2 Question History: Point Beach 1 9/29/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (3)(5)(10) 55.43 (5)
Comments:
Stem, answer and distracters modified to make plant specific
Page 85 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 41 Group # 1 WA # 061 K5.01 Importance Rating 3.6 Knowledge of the operational implications of the relationship between AFW flow and RCS heat transfer Proposed Question: Common #13 A reactor trip occurs from 100% power due to a loss of main feedwater.
The following conditions exist:
All RCPs are running.
0 The turbine driven AFW pump is in service feeding all 4 SGs.
0 Both motor driven AFW pumps tripped upon startup and remain unavailable.
0 The turbine driven AFW pump speed has begun to slowly lower due to a malfunctioning governor.
Which one of the following describes the impact on Pressurizer level if the turbine driven AFW pump speed CONTINUES to lower?
Pressurizer level:
A. rises due to increased primary to secondary heat transfer.
B. rises due to decreased primary to secondary heat transfer.
C. lowers due to increased primary to secondary heat transfer.
D. lowers due to decreased primary to secondary heat transfer.
Proposed Answer:
B. rises due to decreased primary to secondary heat transfer.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE
- __ ~~~ ~ .~
Page 86 of 241 Learning Objective: (As available)
Question Source: Bank # INPO 25021 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Beaver Valley 1 12/01/02 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 Comments:
Question modified to make plant specific
Page 89 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 43 Group ## 2 WA # W/E07 G2.4.18 Importance Rating 2.7 3.6 Knowledge of the specific bases for EOPs Proposed Question: Common #14 Step 1 of FR-C.3, "Response to Saturated Core Conditions", checks if the RHR system has been placed in service in the shutdown cooling mode.
Which of the following describes the basis for this step?
A. To ensure an ORANGE or RED condition in Core Cooling will not arise while performing this procedure.
- 6. If RHR is in service in the shutdown cooling mode, the saturated core cooling condition is a problem with RHR and this procedure will not address this condition.
C. To verify RHR is aligned for long term cooling if the appropriate conditions are met D. If RHR is in service in the shutdown cooling mode, the saturated core cooling condition c- is a problem with RHR and this procedure will identify and isolate the affected train.
Proposed Answer:
- 6. If RHR is in service in the shutdown cooling mode, the saturated core cooling condition is a problem with RHR and this procedure will not address this condition.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
FR-C.3 Background Page 8 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 22526 Modified Bank # (Note changes or attach parent)
New X Question History: Diablo Canyon 1 10/1/2002
Page 90 of 241 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (10) 55.43 Comments:
Page 91 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 44 Group # 2 WA # W/E15 EK1.2 Importance Rating 2.7 2.9 Knowledge of the operational implications of normal, abnormal and emergency operating procedures associated with Containment Flooding Proposed Question: Common #15 The following conditions exist:
A large break LOCA has occurred.
The plant is tripped and ECCS is operating as expected.
Accumulators have discharged and are isolated.
The SM directs performance of FR-2.2, Containment Flooding.
Which one of the following describes the required actions per FR-Z.2 and their purpose?
A. Secure all water sources from outside of containment to prevent damaging vital electrical equipment and diluting the containment water inventory.
B. Secure all water sources from outside of containment to prevent overloading concrete containment structures and diluting the containment water inventory.
C. Locate source of flooding in an attempt to prevent damaging vital electrical equipment and diluting the containment water inventory.
D. Locate source of flooding in an attempt to prevent overloading concrete containment structures and diluting the containment water inventory.
Proposed Answer:
C. Locate source of flooding in an attempt to prevent damaging vital electrical equipment and diluting the containment water inventory.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
FR-Z.2 Page 3 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Page 92 of 241 Question Source: Bank # INPO 24609 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Seabrook 1 5/30/2003 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (8,lO) 55.43 Comments:
Page 93 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 45 Group # 2 WA # W/E16 EA2.2 Importance Rating 3.0 3.3 Ability to determine and interpret adherence to appropriate procedures and operation withing the limitations in the facility's license and amendments as they apply to High Containment Radiation.
Proposed Question: Common #16 Given the following plant conditions:
A loss of coolant accident has just occurred.
0 During the initial phases of the accident, containment pressure peaked at 32 psig and containment radiation dose rate peaked at 2.5E6 Whr.
0 The CRS has directed that adverse containment numbers be used during EOP implementation.
0 Approximately 30 minutes later, containment pressure lowered to 6 psig and containment radiation dose rate lowered to 1E3 Whr.
The CRS must direct that adverse containment numbers:
C' A. still be used until containment pressure is less than 4 psig.
B. still be used until relaxed by Technical Support Center personnel.
C. not be used since the containment radiation level is no longer indicative of adverse containment conditions.
D. not be used since the containment pressure is no longer indicative of adverse containment conditions.
Proposed Answer:
B. still be used until relaxed by Technical Support Center personnel.
Explanation (Optional):
Technical Reference(@: (Attach if not previously provided)
OAP-012 Page 10 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Page 94 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
i
Page 5 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 u
3 Group # 1 KIA # 000011 EK2.02 Importance Rating 2.6 2.7 Knowledge of the interrelations between pumps and a Large Break LOCA Proposed Question: Common #17 Unit 2 is shutdown following a Loss of Offsite Power with a LOCA event. The operators are performing actions in. E-1, Loss of Reactor or Secondary Coolant.
Which ONE of the following statements is the basis for placing ALL non-running CCW pump control switches in PULL-TO-LOCKprior to resetting the SI signal?
A. Prevent Thermal shock to the RCP Thermal Barriers.
B. Prevent an overload condition on the Emergency Diesel Generators.
C. Prevent CCW System overpressure with all 3 CCW pumps starting simultaneously.
D. Prevent steam formation in the RHR heat exchanger CCW side.
L--
Proposed Answer:
B. Prevent an overload condition on the Emergency Diesel Generators.
Explanation (Optional):
Technical Reference(@: (Attach if not previously provided)
E-1 Background Step 5, Page 47 ProDosed References to be Drovided to amlicants durina examination: NONE Learning Objective: EOP-C-011-540 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES c-Question History:
Question Cognitive Level: Memory or Fundamental Knowledge X
Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (7, 10) 55.43 Comments:
Page 19 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 9 Group # 1 KIA # 000027 AA2.15 Importance Rating 3.7 4.0 Ability to determine and interpret the actions to be taken if PZR pressure instrument fails high Proposed Question: Common #18 Given the following conditions:
The plant is at 100% power.
0 ALL control systems are in their normal automatic alignments.
0 Pressurizer pressure channel PT-455 indicates 2275 psig and slowly rising.
All other narrow range pressurizer pressure indications are 2220 psig and slowly dropping Which of the following actions is required in accordance with 2AOP-INST-1?
A. Place the affected PORV control switch in CLOSE.
B. Place the pressurizer pressure master controller in MANUAL and control RCS pressure.
v C. RESET and reenergize pressurizer heaters D. TRIP the reactor, enter E-0, Reactor Trip or Safety Injection.
Proposed Answer:
- 6. Place the pressurizer pressure master controller in MANUAL and control RCS pressure.
Explanation (Optional):
A. - Incorrect. Only for channels directly impacting PORVs B. - Correct. Controlling channel is failing C. - Incorrect. Heaters will not energize until pressure control in manual D. - Incorrect. Rx trip criteria not yet met Technical Reference(s): (Attach if not previously provided) 2-A0 P-INST-1 Page 7 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-014-50 (As available)
Question Source: Bank # INPO 23382
Modified Bank # (Note changes or attach parent)
New No IP3 ii Question History: Indian Point Unit 3 3/10/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
Stem modified to make procedure plant specific
Page 21 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1
'v 10 Group ## 1 WA ## 000029 EK2.06 Importance Rating 2.9 3.1 Knowledge of the interrelations between the breakers, relays, and disconnects following an ATWS Proposed Question: Common #19 A reactor trip and SI have occurred from 100% power. E-0,"Reactor Trip or Safety Injection",
has just been implemented.
The following are observed:
0 "A" Reactor Trip Breaker (RTA) is OPEN 0 "B" Reactor Trip Breaker (RTB) is CLOSED Both bypass breakers are open Reactor power is decreasing in the intermediate range, with SUR at -0.3 dpm All rods are fully INSERTED, and rod bottom lights LIT A manual trip of the Reactor Trip Pushbutton was performed, however the "B" Reactor Trip c Breaker is still CLOSED.
What action should be taken next?
A. Locally trip 21 and 22 Motor Generator Set breakers.
B. Commence a boration to cold shutdown boron concentration C. Continue with E-0, Step 2, and subsequently dispatch operator to locally open RTB.
D. Transition to FR-S.l , "Response to Nuclear Power Generation/ATWS".
Proposed Answer:
C. Continue with E-0, Step 2, and subsequently dispatch operator to locally open RTB.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
E-0 Step 1 Standards and Expectations
Page 22 of 241 Proposed References to be provided to applicants during examination: NONE
- c. Learning Objective: (As available)
Question Source: Bank # INPO 22465 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Diablo Canyon 1 10/1/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
Page 23 of 241 Examination 0utIine Cross-reference: Level RO SRO c Tier # 1 11 Group # 1 WA # 000038 EA1.ll Importance Rating 3.8 3.9 Ability to operate and monitor SG level indicators as they apply to a SGTR Proposed Question: Common #20 A SGTR on 24 SG caused an automatic SI on Unit 2.
The operating team is in E-3, Steam Generator Tube Rupture, performing SI RESET actions 0 24 SG is isolated TAVEis stable 21, 22 and 23 SG NR levels were stable at 30%
0 23 SG NR level has started to rise slowly with no change in AFW flow or steaming rate Which one of the following describes the required action(s)?
L-' A. Continue performing the steps of E-3 B. Return to E-3, Step 1 C. Reduce AFW flow to 23 SG and monitor level while continuing in E-3 D. Re-initiate SI and return to E-0, Step 1 Proposed Answer:
B. Return to E-3, Step 1 Explanation (Optional):
(A) E-3 only isolates a ruptured SG if started from the beginning of the procedure, (B) Correct answer when a tube rupture in a second SG is identified, (C) This could mask another SG tube leak or rupture, (D) E-0 would only identify a SG tube rupture and initiate E-3 at step 1 Technical Reference(s): (Attach if not previously provided)
E-3 foldout page Proposed References to be provided to applicants during examination: NONE
Page 24 of 241 Learning 0bjective: (As available)
Question Source: Bank # INPO 23122 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Salem Unit 1 1 1/04/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
c
Page 29 of 241 Examination Outline Cross-reference: Level RO SRO b
Tier # 1 14 New14 Group # 1 WA # 000056 G2.1.20 Importance Rating 4.3 4.2 Ability to execute procedure steps.
Proposed Question: Common #21 A Reactor Trip with Loss of Offsite power occurred from 100% power 30 minutes ago.
The following conditions are noted:
ALL SGs are available.
RCS subcooling is 26°F.
Average of Qualified CETs is 530°F and rising slowly:
Loop T-hots are 520°F and rising slowly.
Loop T-colds are 490°F and rising slowly.
Which of the following actions, should be taken in accordance with ES-0.1, Reactor Trip Response, to enhance natural circulation?
'\,
A. Turn on available pressurizer heaters B. Initiate Auxiliary Spray C. Throttle open the Auxiliary Feed Water control valves D. Throttle open the Atmospheric Dump Valves Proposed Answer:
D. Throttle open the Atmospheric Dump Valves Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ES-0.1 Step 10 & Attachment 3 L,
Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-004-509 (As available)
Page 30 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (1 0) 55.43 (5)
Comments:
Page 35 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 16 Group # 1 WA # W/E04 EK2.1
~
Importance Rating 3.5 3.9 Knowledge of the interrelations between the (LOCA Outside Containment and the components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Proposed Question: Common #22 The following plant conditions exist:
The unit is in MODE 4 RHR cooldown is in progress.
RCS Temperature - 340°F slowly decreasing.
RCS pressure - 300 psig decreasing.
PZR level - 42% decreasing.
Containment pressure - 0.2 psig and steady.
PAB 98 ft. elevation radiation monitor R-5987 is alarming Plant vent monitors R-43 and R-44 are alarming All S/G Narrow Range levels are steady at approximately 42%
S/G pressures are steady at approximately 125 psig What event is taking place?
A. A steam leak has occurred inside containment.
B. The Low Temperature Overpressure Protection (LTOP) system has actuated.
C. Letdown line pressure control valve, PCV-135 has failed open.
D. A LOCA has occurred on the suction of the RHR pump.
Proposed Answer:
D. A LOCA has occurred on the suction of the RHR pump.
Explanation (Optional):
A, B - inside containment C - Incorrect (wrong lineup)
D.- Correct (radiation levels indicate LOCA in PAB)
Technical Reference(s): (Attach if not previously provided)
Page 36 of 241 ARP SAF-1 window 2-8 b
Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 24608 Modified Bank # (Note changes or attach parent)
New X I P2 Question History: Seabrook 1 5/30/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
Question modified to make plant specific
Page 39 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 L
18 Group # 1 Rev per TF WA ## 000065 G2.1.2 Importance Rating 3.0 4.0 Knowledge of operator responsibilities during all modes of plant operation.
Proposed Question: Common #23 Given the following conditions:
The plant is at 100% power.
A Loss of Instrument Air pressure has occurred The CRS has directed entry to 2-AOP-AIR-1, Loss of Instrument Air Which of the following plant conditions will require a reactor trip in accordance with 2-AOP-AIR-l?
A. Steam Generator Levels 45% and decreasing slowly B. VCT Level 4% and decreasing slowly u C. Pressurizer Level is 55% and increasing slowly D. Instrument Air header pressure is 85 psig and decreasing slowly Proposed Answer:
B. VCT Level 4% and decreasing slowly Explanation (Optional):
A - Rx trip required for >lo% level change from program B - Correct (4% Trip Rx)
C - >5%0above program requires plant S/D D - No trip required for low air pressure only required to check other parameter if <95 psig Technical Reference(s): (Attach if not previously provided) 2-A0P-AIR-1 Pages 7,8,9
- Proposed References to be provided to applicants during examination:
Learning Objective: SYS-C-292-474 NONE (As available)
~ __ ~
Page 40 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History: New Question Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Page 41 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 c
19 Group # 1 WA # W/E05 EK1.2 Importance Rating 3.9 4.5 Knowledge of the operational implications of normal, abnormal and emergency operating procedures associated with the (Loss of Secondary Heat Sink)
Proposed Question: Common #24 The following plant conditions exist:
a The team is responding to a LOCA in accordance with E-1, Loss of Reactor or Secondary Coolant.
A RED path occurs on the "Heat Sink Critical Safety Function Status Tree".
The team transitions to FR-H.1, "Response to Loss of Secondary Heat Sink".
Total available AFW flow is 200 gpm.
RCS pressure is 525 psig and STABLE.
Containment pressure is 10 psig and INCREASING.
SG pressures are all 950 psig and STABLE.
SG wide range levels are 45% and DECREASING.
Which of the following actions are required?
A. Transition back to E-1, "Loss of Reactor or Secondary Coolant" B. Attempt to establish feed to the SG using the Main Boiler Feed Pumps C. Attempt to establish feed to the SG using the Condensate Pumps D. Steps 9 through 15 should be performed immediately to establish bleed and feed Proposed Answer:
A. Transition back to E-1, "Loss of Reactor or Secondary Coolant" Explanation (Optional):
RCS pressure is less than all non-faulted SGs. Secondary heat sink is not required. Note, "Adverse Conditions I' DO NOT change pressure setpoints Technical Reference(s): (Attach if not previously provided)
FR-H.l Page 2 Proposed References to be provided to applicants during examination: NONE
Page 42 of 241 Learning Objective: EOP-C-044-3561 (As available) v Question Source: Bank # INPO 24715 Modified Bank # YES (Note changes or attach parent)
New X IP2 Question History: Seabrook 1 5/30/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
Question and distracters Modified
Page 45 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 21 Group # 2 WA # ~~
000028 AK2.02
~
Importance Rating 2.6 2.7 Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and sensors and detectors Proposed Question: Common #25 The plant is operating at 100% power with all control systems operating normally. The reference leg of LT-460 has just developed a leak where the reference leg connects to the D/P cell. Which one of the following best describes the plant response from this leak? LT-459/460 is selected for PZR level control and alarm (Level 3 in DEFEAT).
A. LT-459 - indication will decrease, LT-460 indication will increase, LT-461 - indication will increase, charging flow will increase.
B. LT-459 - indication will decrease, LT-460 indication will increase, LT-461 - indication will decrease, charging flow will decrease C. LT-459 - indication will increase, LT-460 indication will decrease, LT-461 indication will decrease, backup heaters will deenergize.
D. LT-459 - indication will decrease, LT-460 indication will decrease, LT-461 indication will increase, backup heaters will energize.
Proposed Answer:
B. LT-459 - indication will decrease, LT-460 indication will increase, LT-461 - indication will decrease, charging flow will decrease Explanation (Optional):
LT-460 will indicate high, 460 is in control and 459 is in alarm with defeat switch to defeat channel 3 (461), charging pump speed will decrease and actual level will decrease Technical Reference(s): (Attach if not previously provided) 2-AOP-INST-1 IP2 SOD 007 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 24612
~ __ ~- - - -__ ~ _ _ ~ - - ~ -
Page 46 of 241 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Seabrook 1 5/30/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Question, answer and distracters modified to make plant specific
Page 63 of 241 Examination 0ut1ine Cross-reference: Level RO SRO Tier # 2 30 Group # 1 WA # 003 K5.05 Importance Rating 2.8 3.0 Knowledge of the operational implications of the dependency of RCS flow rates upon the number of operating RCPs Proposed Question: Common #26 The Plant is in MODE 3 with all Steam Generators available. Which statement describes the effect on the Reactor Coolant System (RCS) of the number of operating Reactor Coolant Pumps (RCPs)?
A. Fifteen minutes after shutting off ALL RCPs there will be NO flow in the RCS, and margin to DNB will be reduced.
B. Operating ALL RCPs raises RCS flow rate, but results in a reduction in DNB margin due to pump heat input.
C. Reducing the number of operating RCPs lowers the RCS flow rate causing a REDUCTION in DNB margin.
D. Reducing the number of operating RCPs lowers the RCS flow rate causing a RISE in DNB margin.
Proposed Answer:
C. Reducing the number of operating RCPs lowers the RCS flow rate which causes a REDUCTION in DNB margin.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 26298 Modified Bank # (Note changes or attach parent)
____ ~-
Page 64 of 241 New X IP2 Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 Comments:
Page 65 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 L
31 Group # 1 WA # 004 A4.15 Importance Rating 3.6 3.7 Ability to manually operate and/or monitor in the control room Boron concentration Proposed Question: Common #27 Given the following conditions:
Unit 2 is at 100% power.
Core Burnup is 11,000 MWD/MTU.
0 Rod Control is in MANUAL.
All other plant controls are in their normal configuration.
AUTO makeup initiated to the VCT.
The boron addition rate is set 5 gpm higher than required for present RCS conditions.
Assuming NO operator action, what will be the effect on the following parameters 15 minutes after the auto makeup is complete?
Reactor Power RCS Tave Main Generator Electrical Output A. Lower Lower Higher B. Higher Higher Lower C. Higher Higher Higher D. Lower Lower Lower Proposed Answer:
D. Lower Lower Lower Explanation (Optional):
Technical Reference(s): (Attach if not previ usly provided) c Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 24074 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Salem Unit 1 5/05/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Page 103 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 50 Group # 1 WA # 010 A3.02 Importance Rating 3.6 3.5 Ability to monitor automatic operation of PZR PCS, including: PZR pressure.
Proposed Question: Common #28 Given the following:
0 PRZR Pressure Control System in position "DEFEAT 3 & 4" 0 Both PORV Block Valves CLOSED with control switches in AUTO 0 Both PORVs CLOSED with control switches in AUTO 0 All PRZR Heater control switches in AUTO 0 PRZR Spray Valve controllers in AUTO 0 PRZR Pressure Master Controller in AUTO Which ONE of the following statements describes the RCS/Pressurizer system response should PRZR pressure transmitter PT-455, Channel 1, fail LOW? {ASSUME: NO operator action.}
A. ALL pressurizer heaters turn ON and Both PORVs available to automatically cycle for control of pressurizer pressure.
B. ALL pressurizer heaters turn ON and Only 1 PORV available to automatically cycle for control of pressurizer pressure C. ALL pressurizer heaters turn ON and Spray valves cycle to control pressurizer pressure.
D. ALL pressurizer heaters turn ON and Reactor trips on high pressurizer pressure condition.
Proposed Answer:
B. All pressurizer heaters turn ON and Only 1 PORV available to automatically cycle for control of pressurizer pressure Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
IP2-SOD-007 Proposed References to be provided to applicants during examination: NONE
Page 104 of 241 Learning Objective: SYS-C-014-54 (As available)
L- Question Source: Bank # INPO 20120 Modified Bank # (Note changes or attach parent)
New Question History: Cook 1 9/10/2001 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (357) 55.43 Comments:
Questions, answer and distracters modified to make plant specific
Page 107 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 52 Group # 1 WA # 012 K1.02 Importance Rating 3.4 3.7 Knowledge of the physical connections and/or cause effect relationships between the RPS and the 125VDC System.
Proposed Question: Common #29 Which of the following describes the effect that a loss of 125VDC breaker control power has on the Reactor TRIP and BYPASS breakers?
A. All TRIP and BYPASS breakers will open B. The BYPASS breakers will open but the TRIP breakers will NOT open C. The TRIP breakers will open but the BYPASS breakers will NOT open D. All TRIP and BYPASS breakers will NOT open L- Proposed Answer:
D. All TRIP and BYPASS breakers will NOT open Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-AOP-DC-1 Pages 99,l25 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-161-277 (As available)
SYS-C-2718-6454 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis
10 CFR Part 55 Content: 55.41 (6) 55.43 L--
Comments:
4
Page 135 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 66 Group # 2 WA # 011 K5.15 Importance Rating 3.6 4.0 Knowledge of the operational implications of the PZR level indication when RCS is saturated Proposed Question: Common #30 During a natural circulation cooldown, which of the following pressurizer level responses would indicate the presence of a void in the reactor vessel upper head?
A. A Pressurizer level increase when charging flow is directed through the auxiliary sprays.
B. A Pressurizer level decrease when charging flow is directed through the auxiliary sprays.
C. A Pressurizer level increase when charging flow is directed into the cold legs.
D. A Pressurizer level decrease when there is an increase in the cooldown rate.
Proposed Answer:
L ,
A. A Pressurizer level increase when charging flow is directed through the auxiliary sprays.
Explanation (Optional):
Auxiliary spray flow would decrease the pressure in the pressurizer and cause a steam void to form in the upper head resulting in water being displaced to the pressurizer Technical Reference(s) : (Attach if not previously provided)
ES-0.3 Background Pages 18-22 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-008-3531 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New Yes Question History:
W' Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X
Page 136 of 241 10 CFR Part 55 Content: 55.41 (3,8,14) 55.43 Comments:
Page 137 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 67 Group # 2 WA # 014 Al.03 Importance Rating 3.6 3.8 Ability to predict and/or monitor changes in parameters associated with operating the RPlS controls, including PDIL, PPDIL Proposed Question: Common #31 Which one of the following instrument failures would directly cause a change in the computer calculated rod insertion limits?
A. An impulse pressure channel failing HIGH.
B. A THOTRTD channel failing HIGH.
C. A Power Range NIS channel failing HIGH.
D. A Pressurizer pressure channel failing LOW.
L Proposed Answer:
B. A THoT RTD channel failing HIGH.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-163-292/293/295 (As available)
Question Source: Bank # INPO 20629 Modified Bank # (Note changes or attach parent)
New Question History: Point Beach 1 2/02/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X
Page 138 of 241 10 CFR Part 55 Content: 55.41 (6) 55.43 v
Comments:
Page 141 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 69 Group # 2 WA # 017 A2.02 Importance Rating 3.6 4.1 Ability to (a) predict the impacts of core damage on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of core damage Proposed Question: Common #32 A severe accident has occurred and the operating team is currently implementing the Emergency Operating Procedures. The following conditions exist:
0 All RCPs are off.
0 PZR level is off scale low.
0 RVLIS, Natural Circ Range, is 68%
0 RCS pressure is 400 psig.
0 Core exit thermocouples are reading 750°F.
What course of action should the operating team take?
A. Transition to FR-C.1, Response to Inadequate Core Cooling because core damage is occurring.
B. Transition to FR-C.l, Response to hadequate Core Cooling because core uncovery is likely occurring.
C. Transition to FR-C.2, Response to Degraded Core Cooling because core damage is occurring.
D. Transition to FR-C.2, Response to Degraded Core Cooling because core uncovery is likely occurring.
Proposed Answer:
D. Transition to FR-C.2, Response to Degraded Core Cooling because core uncovery is likely occurring.
Explanation (Optional):
A. FR-C.l requires >120O0Fforcore damage B. FR-C.l requires >7OO0Fwith RVLIS ~ 4 1 % for core damage imminent C. Core damage occurs >1200"F D. Correct Technical Reference(s): (Attach if not previously provided)
F-0.2 FR-C.1 Background
FR-C.2 Background Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-001-500 (As available)
EOP-C-O18-576,3539 EOP-C-019-3540 Question Source: Bank # INPO 21574 Modified Bank # (Note changes or attach parent)
New Question History: Kewaunee 1 910612002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7, 14) 55.43 Comments:
Minor modification to Question given parameters
Page 153 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 75 Group # 2 WA # 086 A3.02 Importance Rating 2.9 3.3 Ability to monitor automatic operation of the Fire Protection System including actuation of the FPS Proposed Question: Common #33 Fire Protection System pressure has lowered to 120 psig, and is continuing to lower slowly.
Which one of the following best describes the sequence in which the alternate pumps will start if system pressure were to continue to lower at a slow rate?
A. 11 Fire Main Booster Pump, 12 Fire Main Booster Pump, Diesel Fire Pump.
B. 12 Fire Main Booster Pump, 11 Fire Main Booster Pump, Diesel Fire Pump.
C. Diesel Fire Pump, 11 Fire Main Booster Pump, 12 Fire Main Booster Pump.
D. Diesel Fire Pump, 12 Fire Main Booster Pump, 11 Fire Main Booster Pump.
Proposed Answer:
B. 12 Fire Main Booster Pump, 11 Fire Main Booster Pump, Diesel Fire Pump.
Explanation (Optional):
12 Fire Main Booster Pump starts 105 psig, 11 Fire Main Booster Pump starts at 90 psisg, Diesel Fire Pump starts at 65 psig Technical Reference(s): (Attach if not previously provided)
SOP-29.6 Pages 16 & 28 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-296-486 (As available)
Question Source: Bank # IP2 TM SYSC296-1 Modified Bank # (Note changes or attach parent)
New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X
Page 154 of 241 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Page 25 of 241 Examination Outline Cross-reference: Level RO SRO
'V Tier # 1 12 Group # 1 WA # 000054 G2.4.2 Importance Rating 3.9 4.1 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions Proposed Question: Common #34 Given the following conditions:
0 RCS pressure is 1000 psig and trending down.
Safety Injection has actuated.
21 SG NR level is 5% and trending down, pressure is 500 psig and trending down slowly.
22 SG NR level is 7% and trending down, pressure is 480 psig and trending down slowly.
23 SG NR level is 3% and trending down, pressure is 490 psig and trending down slowly.
24 SG NR level is 3% and trending down, pressure is 500 psig and trending down slowly.
Maximum available AFW flow is 180 GPM Containment pressure is 3 psig and rising.
The team has just implemented E-0, Reactor Trip or Safety Injection.
Under these conditions, which of the following procedures will be entered from E-O?
A. E-2, Faulted Steam Generator Isolation.
B. ECA-2.1, Uncontrolled Depressurization of All Steam Generators.
C. FR-H.l Response to Loss of Secondary Heat Sink.
D. FR-H.5, Response to Steam Generator Low Level.
Proposed Answer:
C. FR-H.l Response to Loss of Secondary Heat Sink.
Explanation (Optional):
A-Incorrect. Not RED, and not an FR B-Correct. Not RED, and not an FR C-Correct. Entry met for FR-H.l D-Correct. Not RED. Yellow path procedure
Page 26 of 241 Technical Reference(s): (Attach if not previously provided)
EOP Rules of Usage, Generic Issue CSFST F.0.3 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 23273 Modified Bank # (Note changes or attach parent)
New Question History: Indian Point Unit 2 3/10/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
Page 27 of 241 Examination 0utline Cross-reference: Level RO SRO
--..-. Tier # 1 13 Group # 1 KIA # 000055 EK3.02 Importance Rating 4.3 4.6 Knowledge of the reasons for the actions contained in EOP for loss of offsite and onsite power Proposed Question: Common #35 Which of the following describes the correct operator actions that will be required in accordance with ECAO.0, Loss of All AC Power, to complete the below statement?
The SI signal will be manually actuated.
A. if no Emergency Diesel Generator is running and SI will be reset to facilitate restoring equipment upon power restoration.
B. under all conditions in preparation for RCP seal failure and SI will not be reset until transition from ECA-0.0.
C. only if the automatic SI signal failed to actuate and SI will be reset after power is u restored to at least one (1) 480V bus.
D. upon transition from ECA-0.0 to ECA-0.1 and SI will not be reset until directed in E-1 after transition from ECA-0.1, Loss of All AC Power Recovery Without SI Required.
Proposed Answer:
A. if no Emergency Diesel Generator is running and SI will be reset to facilitate restoring equipment upon power restoration.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ECA-0.0 Step 5, 6 Caution ECA-0.0 Background Page 110 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-036-3554 (As available)
J Question Source: Bank # INPO 24038 Modified Bank # YES (Note changes or attach parent)
New X I P2 Question History: Salem Unit 1 5/05/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5)(10) 55.43 (5)
Comments:
Answer and distracters completely changed
Page 59 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 i,
28 Group # 2 WA # WE03 EK3.2 Importance Rating 3.4 3.9 Knowledge of the reason for normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
Proposed Question: Common #36 Given the following plant conditions:
0 Operators are responding to a small break LOCA using ES-1.2 "Post LOCA Cooldown and Depressurization."
RCS temperature is 400°F.
0 After depressurizing the RCS to restore pressurizer level, one (1) Safety Injection (SI)
Pump is stopped.
While checking the step to "Verify SI Flow Not Required", the OTC observes that subcooling decreased to 18°F and is slowly rising.
Which ONE of the following actions should be taken for these conditions?
A. Manually actuate SI.
B. Wait and see if subcooling recovers. If subcooling recovers, then continue with SI reduction.
C. Start the SI pump just secured only until subcooling is restored, then stop it.
D. Start the SI pump just secured and leave it running until SI reduction or termination criteria are satisfied.
Proposed Answer:
B. Wait and see if subcooling recovers. If subcooling recovers, then no action is needed.
Explanation (Optional):
Technical Reference(@: (Attach if not previously provided)
ES-1.2 Background Pages 49-52 Proposed References to be provided to applicants during examination: NONE
Page 60 of 241 Learning Objective: EOP-C-012-55413347 (As available)
Question Source: Bank # INPO 21515 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Kewaunee 1 910612002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5)(10) 55.43 (5)
Comments:
Page 67 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 32 Group # 1 KIA # 004 K3.08 Importance Rating 3.6 3.8 Knowledge of the effect that a loss or malfunction of the CVCS will have on RCP Seal Injection Proposed Question: Common #37 The following plant conditions exist on Unit 2:
Unit 2 is at 90% power.
0 All systems are in normal at power condition.
0 The instrument air line to operating charging pump has just broken loose.
What would be the effect on the following flows as a result of this failure?
Charging Flow 0 RCP Seal Injection Flows Charging Flow RCP Seal Inj. Flow A Increases Decreases B Decreases Increases C Increases Increases D Decreases Decreases Proposed Answer:
C Increases Increases Explanation (Optional):
Charging pumps fails to maximum speed on loss of Instrument Air Technical Reference(s): (Attach if not previously provided) 2-AOP-AIR-1 Page 27 SOD-18 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Page 68 of 241 Question Source: Bank # INPO 22965 Modified Bank # (Note changes or attach parent)
New X I P2 Question History: Prairie island 2 8/16/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Question and Answer modified to make plant specific
Page 69 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2
'i, 33 Group # 1 OK per TF WA # 005 K2.03 Importance Rating 2.7 2.8 Knowledge of the bus power supplies to the RCS pressure boundary motor-operated valves Proposed Question: Common #38 Unit 2 is operating in Mode 4 with RHR cooling in service. Residual Heat Loop Inlet Stop Valves, MOV-730 and MOV-731, are kept in order A. Energized ... to allow auto isolation on high RCS pressure for RHR system overpressure protection.
B. Energized ... to allow rapid manual isolation for inventory control during RHR system leak.
C. De-energized ... to prevent auto isolation on high RCS pressure to maintain RHR suction flowpath.
'b D. De-energized ... to prevent inadvertent isolation from electrical short circuit.
Proposed Answer:
D. De-energize ... to prevent inadvertent isolation from electrical short circuit .
Explanation (Optional):
A. Valves are de-energized not energized B. Valves are de-energized not energized C. MOV-730 & 731 have overpressure interlock to prevent opening but do not have interlock to close valves on high pressure D. Correct Technical Reference(s): (Attach if not previously provided)
SOP-4.2.1 Pages 4,5 Proposed References to be provided to applicants during examination: NONE i/
Learning Objective: SYS-C-042 - 118 (As available)
Page 70 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES NEW Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (1)
Comments:
730/731 interlock only prevents opening if pressure is >450 psig
Page 71 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 34 Group # 1 WA # 006 K3.02 Importance Rating 4.3 4.4 Knowledge of the effect that a loss or malfunction of the ECCS will have on the fuel Proposed Question: Common #39 A LOCA occurs which results in all core exit temperature thermocouples reading about 1300°F.
Which method is the preferred and most effective means of cooling the core?
A. Reduce RCS pressure by dumping steam from the secondary to inject the accumulators.
B. Reduce RCS pressure by opening the pressurizer PORVs to inject the accumulators.
C. Start reactor coolant pumps one at a time.
D. Establish ECCS flow to the core.
Proposed Answer:
D. Establish ECCS flow to the core.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
FR-C. 1 Background Page 1 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 22445 Modified Bank # (Note changes or attach parent)
New X IP2 Question History: Diablo Canyon 1 10/01/2002
Page 72 of 241 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Page 79 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 38 Group ## 1 WA # 039 A2.05 Importance Rating 3.3 Ability to predict the impacts of Increasing steam demand, its relationship to increases in reactor power operation on the MRSS Proposed Question: Common #40 The Unit is operating at 80% power with all systems in automatic. One Group of condenser steam dump valves fails full OPEN. Assuming that NO operator action occurs, what will be the resulting Rx power level?
A. 0%
B. 70%
C. 80%
D. 90%
Proposed Answer:
D. 90%
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New X Question History:
Question Cognitive Level: Memory or Fundamental Knowledge
Page 80 of 241 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 (5)
Comments:
Page 95 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 i,
46 Group # 1 WA # 003 Al.10 Importance Rating 2.5 2.7 Ability to predict andor monitor changes in parameters associated with operating the controls including RCP standpipe levels Proposed Question: Common #41 The Unit is operating at 100% power.
Which one of the following will cause RCP Standpipe level(s) to rise?
A. Failure of #1 Seal.
B. Failure of #3 Seal.
C. MOV-222, RCP Seal Return Isolation Stop Valve, fails closed.
D. HCV-142, Charging Line Flow Control Valve, fails closed.
Proposed Answer:
A. Failure of #1 Seal.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-S-O13-31/41 (As available)
Question Source: Bank # INPO 23064 Modified Bank # (Note chanaes or attach Darent)
New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis
Page 96 of 241 10 CFR Part 55 Content: 55.41 (3)(5) 55.43 Comments: Question Distracters modified to make plant specific
Page 99 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 48 Group # 1 KIA # 007 Al.01 Importance Rating 2.9 3.1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with maintaining quench tank water level within limits Proposed Question: Common #42 Which ONE of the following describes the adverse affects of NO operator action with a leaking pressurizer PORV?
A. There are NO adverse affects. The PRT is designed to handle continuous in-leakage.
B. The cyclic temperature stresses in combination with inner wall erosion on the PORV tailpipe may lead to premature piping failure C. Mechanical breakdown of the PORV seating surface may cause the PORV to fail when needed for overpressure protection.
D. The PRT rupture disc may break with subsequent elevated radiation, temperature and pressure indications in containment.
Proposed Answer:
D. The PRT rupture disc may break with subsequent elevated radiation, temperature and pressure indications in containment.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-O14-49/62 (As available)
Question Source: Bank # INPO 22895 Modified Bank # (Note changes or attach parent)
New X I P2 Question History: Cook 1 12/9/2002
Page 100 of 241 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (3, 14) 55.43 Comments:
Page 109 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 53 Group # 1 KIA # 013 K2.01 Importance Rating 3.6 3.8 Knowledge of the bus power supplies to the ESFAS/Safeguards equipment control.
Proposed Question: Common #43 Given the following:
0 Offsite power is lost during preparations to depressurize the RCS to minimize break flow per Step 17 of E-3, Steam Generator Tube Rupture.
The EDGs automatically supply power to all 480V buses.
Fifteen seconds later, the Watch Engineer observes that the SI pumps are no longer running. They were running before the loss of offsite power.
Should the SI pumps have restarted automatically by this point in time and why?
A. Yes. The Safety Injection timers should have started the SI pumps.
B. Yes. The Blackout timers should have started the SI pumps.
C. No. The Safety Injection timers did not actuate because the SI signal has been reset.
D. No. The Safety Injection timers did not actuate because they did not have sufficient time to start the pumps.
Proposed Answer:
C. No. The Safety Injection timers did not actuate because the SI signal has been reset.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
E-3 Caution prior to step 9 E-3 Backaround Page 80 Proposed References to be provided to applicants during examination: NONE Learning 0bjective: (As available)
Question Source: Bank # INPO 22853 Modified Bank # YES (Note changes or attach parent)
New
Page 110 of 241 Question History: Cook 1 12/09/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (3, 5 )
55.43 (5)
Comments:
Question, answer, and distracters modified to make plant specific
Page 111 of 241 Examination Outline Cross-reference: Level RO SRO W'
Tier # 2 54 Group ## 1 KIA # 022 A4.04 Importance Rating 3.1 3.2 Ability to manually operate and/or monitor in the control room valves in the CCS.
Proposed Question: Common #44 Given the following conditions:
0 The plant is operating at 100% power.
0 21, 23, and 25 FCUs are in service to provide Containment Cooling.
Subsequently, reactor trip and Loss of Off-Site power occur. All equipment functions as designed.
Which of the following describes the resulting Containment Cooling lineup?
A. FCUs must be started manually. Cooling water flow is raised by providing a Service Water flow path parallel to TCV-1103, CNTMT BLDG Air Temperature controller..
B. FCUs must be started manually. Cooling water flow is maintained by TCV-1103.
C. Only 21, 23, and 25 FCUs will be in service. Cooling water flow is raised by providing a Service Water flow path parallel to TCV-1103.
D. All FCUs will be in service. Cooling water flow is maintained by TCV-1103 Proposed Answer:
B. FCUs must be started manually. Cooling water flow is maintained by TCV-1103.
Explanation (Optional):
A. Incorrect. Parallel flow path only provided in safeguards mode B. Correct. All previously running fans will restart C. Incorrect. All fans start only in safeguards mode and no parallel flow path is provided D. Incorrect. All fans start only in safeguards mode.
Technical Reference(s): (Attach if not previously provided)
L-Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-102-161 (As available)
_~ ~ ~~
Page 112 of 241 Question Source: Bank # INPO 23215 IP2 Modified Bank # (Note changes or attach parent)
New Question History: Indian Point 2 (Unit) 3/10/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (4) 55.43 Comments:
Page 33 of 241 Examination Outline Cross-reference: Level RO SRO v
Tier # 1 15 Group ## 1 WA # 000057 AK3.01 Importance Rating 4.1 4.1 Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus Actions contained in EOP for loss of vital AC electrical instrument bus Proposed Question: Common #45 Given the following conditions:
0 The plant is at 80% power.
0 A loss of Instrument Bus 24 has occurred Which of the following statements describes why the Hi-Hi Containment Pressure relays are blocked when subsequently addressing failed indications and alarms in accordance with ZAOP-INST-1, Instrument / Controller Failures?
A. Blocks inadvertent actuation of Containment Spray in the case of a redundant channel failure B. Provides a channel trip of Containment Spray to change the coincidence to 1 out of 3 for Spray actuation C. Makes up part of the coincidence circuitry for Spray initiation, since Containment Spray relays are energized to actuate D. Blocks the actuation signal from the channel supplied from the de-energized instrument bus from causing an inadvertent Phase B containment isolation signal Proposed Answer:
C. Makes up part of the coincidence circuitry for Spray initiation, since Containment Spray relays are energized to actuate Explanation (Optional):
A-Incorrect. Makes up part of trip coincidence B-Incorrect. Logic does not change C-Correct D-Incorrect. Channel is energize to actuate Technical Reference(s): (Attach if not previously provided) 2AOP-IB-1
Page 34 of 241
-2AO P-I NST- 1 v
Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 23258 Modified Bank # (Note changes or attach parent)
New NO Question History: Indian Point Unit 2 3/10/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5)(10) 55.43 Comments:
Page 81 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2
\/
39 Group # 1 OK per TF WA # 059 K3.04 Importance Rating 3.6 3.8 Knowledge of the effect that a loss or malfunction of the MFW will have of the RCS Proposed Question: Common #46 Given the following conditions:
83% Reactor power.
Both Main Feedwater pumps are operating in AUTOMATIC.
Steam Generator Water Level Controls are in AUTOMATIC.
Which ONE of the following failures will cause RCS TAVE to INITIALLY INCREASE?
A. 21 SG Level Channel, 417B, fails HIGH B. 21 Steam Flow Channel, 419B, (CONTROLLING) Fails HIGH C. 21 Feed Flow Channel, 4188, (CONTROLLING) Fails LOW u D. 21 Steam Pressure Channel, 419C, Fails LOW Proposed Answer:
A. 21 SG Level Channel, 417B, fails HIGH Explanation (Optional):
A. Feedflow decreases due to high SG level, Tcold 21 loop increases, Tave increases B. Feedflow increases to match SF, Tcold decreases, Tave decreases C. Feedflow increases to match SF,Tcold decreases, Tave decreases D. Atmos 21 SG opens, SF increases, Tcold decreases, Tave decreases Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-012-27 , (As available)
SYS-C-211-3983
'L SGOPSAOP8-1601066 Question Source: Bank #
Page 82 of 241 Modified Bank # (Note changes or attach parent)
New YES L
Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7, 14) 55.43 Comments:
New Question
Page 101 of 241 Examination 0utI ine Cross-reference: Level RO SRO Tier # 2 49 Group # 1 WA # 006 K6.18 Importance Rating 3.6 3.9 Knowledge of the effect that a loss or malfunction of the ECCS will have on Subcooling Margin Indicators Proposed Question: Common #47 A small break LOCA has occurred on Unit 2.
0 ES-1.2, Post LOCA Cooldown and Depressurization, is in progress.
0 Safety Injection Pump 21 has just been stopped in accordance with Step 11.
0 Safety Injection Pumps 22 and 23 are running.
The following conditions are noted:
0 Subcooling Monitor, Channel A 75°F and stable 0 Subcooling Monitor, Channel B 10°F and stable 0 RCS Wide Range Pressure 1335 psig 0 Core Exit Thermocouple avg 570°F Containment pressure 5 psig 0 Containment rad levels 4 Whr After comparing the subcooling readings with RCS pressure and CETs, the team will determine that:
A. Subcooling Monitor Channel A is reading inaccurately, Safety Injection Pump 21 will be started to restore subcooling.
B. Subcooling Monitor Channel B is reading inaccurately, Safety Injection Pump 22 or 23 will be stopped since adequate subcooling exists.
C. Subcooling Monitor Channel A is reading accurately, Safety Injection Pump 21 will NOT be started, the team will continue in ES-1.2.
D. Subcooling Monitor Channel B is reading accurately, Safety Injection Pump 22 or 23 will be stopped since adequate subcooling exists.
Proposed Answer:
A. Subcooling Monitor Channel A is reading inaccurately, Safety Injection Pump 21 will be started to restore subcooling.
Explanation (Optional):
Page 102 of 241 Technical Reference(s): (Attach if not previously provided)
ES-1.2 Proposed References to be provided to applicants during examination: Steam Tables Learning Objective: (As available)
Question Source: Bank ## ~
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (10,14) 55.43 (5)
Comments:
Page 115 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 c
56 Group # 1 Rev per TF WA # 076 A4.01 Importance Rating 2.9 2.9 Ability to manually operate and/or monitor in the control room SWS Pumps Proposed Question: Common #48 Given the following plant conditions:
0 Unit 2 at 100%
0 24/25/26 Essential Service Water Header 0 Three Header Service Water System Operation 0 Operating Service Water Pumps prior to Rx Trip
- a. 21
- b. 22 powered from 2A
- c. 25 powered from 3A
- d. 26 From the list below, determine the service water pump combinations for 22 and 25 Service Water Pumps that would result following a Reactor Trip with a Station Blackout with no other equipment malfunctions:
SWP 22 25 A. Running - 2A Running - 2A B. Stopped Running -2A C. Running -2A Running -3A D. Stopped Running -3A Proposed Answer:
B. Stopped Running -2A Explanation (Optional):
A. No Non-essential SWP receives a start signal B. Correct - 25 SWP receives start signal first for bus 2A C. 25 SWP will only start on bus 3A if 2A start failed D. No Non-essential SWP receives a start signal and 25 SWP will only start on bus 3A if 2A start failed
Page 116 of 241 Technical Reference(s): (Attach if not previously provided)
SD-10.0 Pages 25,26 L,
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-c-240-393 (As available)
SYS-C-271A-2832 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (4,7, 8 )
55.43 u Comments:
Page 117 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 57 Group ## 1 WA # 076 K1.05 Importance Rating 3.8 4.0 Knowledge of the physical connections andlor cause-effect relationships between the SWS and the DIG Proposed Question: Common #49 What are three signals that will cause the EDG service water valves FCV-1176 and FCV-1176A to open fully?
A. High Lube Oil Temp, High Casing Temp and Safety Injection B. High Lube Oil Temp, High Jacket Water Temp and Phase A C. High Jacket Temp, High Casing Temp and Phase A D. High Lube Oil Temp, High Jacket Water Temp and Safety Injection Proposed Answer:
D. High Lube Oil Temp, High Jacket Water Temp and Safety Injection Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
E-0 Page 25 2-ARP-003 Windows 1-3, 1-8 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-240-399d (As available)
Question Source: Bank # IP2 SYSC240-2 Modified Bank # (Note changes or attach parent)
New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X
Page 118 of 241 10 CFR Part 55 Content: 55.41 (4, ,7) 55.43 Comments:
Page 125 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 61 Group # 1 WA # 063 K3.02 Importance Rating 3.5 3.7 Knowledge of the effect that a loss or malfunction of the DC Electrical System will have on the following: Components using dc control power.
Proposed Question: Common #50 A loss of which ONE of the following DC panels will result in the majority of the Control Room Supervisory Alarm Panels losing power?
A. 21 DC Power Panel
D. 24 DC Power Panel Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-A0 P-ANNUN-1 Pages 25,33 Proposed References to be provided to applicants during examination: NONE Learning Objective: AOP-ANNUN-27141 (As available)
Question Source: Bank # INPO 20912 Modified Bank # YES (Note changes or attach parent)
New Question History: Palisades 1 12/2 1/2001 Question Cognitive Level: Memory or Fundamental Knowledge X Comr>rehensionor Analvsis
Page 126 of 241 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Question, Answer and distracters changed to make plant specific c-
Page 225 of 241 Examination Outline Cross-reference: Level RO SRO L.
Tier # 2 111 Group # 1 WA # 078 K3.02 Importance Rating 3.4 3.6 Knowledge of the effect that a loss or malfunction of the IAS will have on systems having pneumatic valves an controls Proposed Question: Common #51 Given the following conditions:
Unit 2 is in Mode 3 0 21 and 23 ABFP maintaining SG levels ABFP suction aligned to the CST Nitrogen Backup in the Aux Feed Building is isolated 0 A major loss of instrument air to the City Water supply valves to the ABFPs occurs Which of the following describes the suction valve alignment for 21 and 23 ABFPs?
A. PCV-1187/1188, CW Supply to 21/23 ABFPs CLOSE and FVC-l205A, CW ABFPs OPEN b
B. PCV-1187/1188, CW Supply to 21/23 ABFPs OPEN and FVC-l205A, CW ABFPs CLOSE C. PCV-1187/1188, CW Supply to 21/23 ABFPs CLOSE and FVC-I205A, CW ABFPs CLOSE D. PCV-1187/1188, CW Supply to 21/23 ABFPs OPEN and FVC-l205A, CW ABFPs OPEN Proposed Answer:
A. PCV-1187/1188, CW Supply to 21/23 ABFPs CLOSE and FVC-l205A, CW ABFPs OPEN Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-AOP-AIR-1 Page 31 u
Proposed References to be provided to applicants during examination: NONE
Page 226 of 241 Learning Objective: SYS-C-292-474 (As available)
AOP-C-AI R-29301 L
Question Source: Bank ##
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (4, 5, 7) 55.43 Comments:
Page 37 of 241 Examination Outline Cross-reference: Level RO SRO L. Tier # 1 17 Group # 1 WA # 000058 AA2.03 Importance Rating 3.5 3.9 Ability to determine and interpret DC loads lost; impact on ability to operate and monitor plant systems as they apply to the loss of DC Power Proposed Question: Common #52 Which of the following describes how a loss of 125VDC to the Reactor Trip Relays Train A affects the Reactor Trip Breaker, RTA?
A. The loss of voltage de-energizes the UV coil and the breaker OPENS.
B. The loss of 125VDC will prevent ALL trip signals to RTA.
C. The breaker is NOT capable of opening on a signal to the UV trip coil of RTA D. The loss of voltage de-energizes the shunt coil and the breaker OPENS.
Proposed Answer:
A. The loss of voltage de-energizes the UV coil and the breaker OPENS..
Explanation (Optional):
125VDC power is used to power the shunt trip coil for Reactor Trip Breakers. This is in addition to the Undervoltage Trip which is also on each reactor trip breaker. Loss of power to the UV portion of breaker will trip the breaker. Power is supplied to energize the shunt trip coil as a backup to the UV trip.
Technical Reference@): (Attach if not previously provided) 2-AOP-DC-1 Page 125 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-(3-161-277 SYS-C-271B-6454 Question Source: Bank # INPO 24061 W
Modified Bank # ~
(Note changes or attach parent)
New X I P2
Page 38 of 241 Question History: Salem Unit 1 5/5/2003 Question Cognitive Level: Memory or Fundamental Knowledge X L
Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 (5)
Comments:
Page 193 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 95 Group # 2 WA # G2.2.22 Importance Rating 3.4 4.1 Knowledge of limiting conditions for operations and safety limits.
Proposed Question: Common #53 Given the following plant conditions:
0 Unit 2 is at 100% power.
0 22 ABFP is tagged out for maintenance.
0 Engineering has just notified the Shift Manager that a common electrical problem has been discovered in the controllers for the motor driven ABFP flow control valves, FCV-406A, through FCV-406D 0 The Shift Manager has declared 21 and 23 ABFPs inoperable.
In addition to initiating action to restore the flow control valves to service, which of the following statements describes an action required for Unit 2?
A. A reactor shutdown to Mode 2 is required.
B. A reactor shutdown to Mode 3 is required.
C. A reactor shutdown to Mode 4 is required.
D. Maintain stable plant conditions Proposed Answer:
D. Maintain stable plant conditions Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
T.S. 3.7.5, Condition D Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-(2-210-383 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
Page 194 of 241 New YES Question History:
L-.-,
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (2)
Comments:
New Question
Page 195 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 96 Group # 3 KIA # G2.3.11 Importance Rating 2.7 3.2 Ability to control radiation releases.
Proposed Question: Common #54 The Shift Manager has directed a plant shutdown based on Chemistry results indicating RCS activity exceeding TS 3.4.1 6 limits.
In the event of a subsequent SGTR, what action is required by Technical Specifications to limit the release of radioactivity?
A. RCS is cooled down below 500°F.
B. Condenser air ejector exhaust is diverted to containment C. SG blowdown is diverted to the Secondary Boiler Blowdown Purification System D. SG atmospheric dump valve setpoints are raised Proposed Answer:
A. RCS is cooled down below 500°F.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
TS 3.4.16 Page 3.4.1 6-1 TS 3.4.1 6 Bases Page B 3.4.1 6-3 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-O11-3/12 (As available)
Question Source: Bank # I P2 C236 Modified Bank # (Note changes or attach parent)
New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge
Page 196 of 241 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (12) 55.43 (2)
Comments:
Minor Modification
Page 197 of 241 Examination OutIine Cross-reference: Level RO SRO Tier # 3 97 Group # 3 KIA # G2.3.1 Importance Rating 2.6 3.0 Knowledge of 10 CFR: 20 and related facility radiation control requirements.
Proposed Question: Common #55 During a plant emergency an operator receives a radiation exposure of 10 REM to the lenses of both eyes.
Regarding 10 CFR 20, "Standards for Protection Against Radiation" and Entergy's administrative radiation control limits, which, if any, of these limits have been exceeded?
A. NEITHER of the exposure limits listed have been exceeded.
B. BOTH 10CFR20 AND plant admin. limits have been exceeded.
C. Plant admin. limits have been exceeded, but NOT 10CFR20 limits.
D. NEITHER of the exposure limits apply for the above situation.
Proposed Answer:
A. NEITHER of the exposure limits listed have been exceeded.
Explanation (Optional):
Entergy limits are 80% of 10CFR20 resulting in limits of 12 REM to the lens of the eyes Technical Reference(s): (Attach if not previously provided) 10CFR20.1201 IP-SMM-RP-201 Pages 8 &9 Proposed References to be provided to applicants during examination: NONE Learning 0bjective: (As available)
Question Source: Bank # INPO 26338 Modified Bank # YES [Note changes or attach parent)
New Question History: Palisades 1 8/01/2003 Question Cognitive Level: Memory or Fundamental Knowledge X
Page 198 of 241 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (12)
'L' 55.43 (4)
Comments:
Question and Answer modified to make plant specific
Page 223 of 241 Examination Outline Cross-reference: Level RO SRO W
Tier # 2 110 Group # 1 WA # 008 K1.03 Importance Rating 2.8 3.3 Knowledge of the physical connections and / or cause-effect relationships between the CCWS PRMS Proposed Question: Common #56 A Reactor Coolant Pump thermal barrier heat exchanger rupture occurred approximately 10 minutes ago. Given the following indications:
High Radiation alarm on CCW Radiation Monitor R-47 0 CCW Surge Tank level indicates OFFSCALE HIGH 0 NPO reports the CCW Surge Tank Relief Valve is lifting periodically 0 FCV-625, RCP Thermal Barrier CCW Return Valve indicates OPEN MOV-789, RCP Thermal Barrier CCW Return Isolation Valve indicates OPEN 0 RCV-017, CCW Surge Tank Vent Valve indicates CLOSED Determine which of the following explains the given status of the CCW System? (Assume NO operator actions have been taken)
A. RCV-017 has failed to automatically OPEN B. MOV-789 has failed to automatically CLOSE C. FCV-625 has failed to automatically CLOSE D. CCW Surge Tank Level Transmitter has failed high Proposed Answer:
C. FCV-625 has failed to automatically CLOSE Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ARP SAF-1 Window 3-8 2-AOP-LICCW-1 Pages 7-17 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-041-102 (As available)
Page 224 of 241 Question Source: Bank # IP2 SYSCO41-15 Modified Bank # (Note changes or attach parent)
Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (3,7) 55.43 Comments:
Page 113 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 55 Group # 1 WA # 062 K2.01 Importance Rating 3.3 3.4 Knowledge of bus power supplies to the major system loads.
Proposed Question: Common #57 Which one of the choices lists only equipment powered from 480V 3A?
A. 21 RHRPump 21 Recirc Pump 22 Charging Pump 23 Fan Cooler Unit 6% 21 Aux Feedwater Pump 21 RHR Pump 22 Charging Pump 24 Fan Cooler Unit C. 21 RHRPump 22 CCW Pump MCC-211 24 Fan Cooler Unit D. 25 SW Pump MCC-24A 22 Charging Pump 21 Aux Feedwater Pump Proposed Answer:
6, 21 Aux Feedwater Pump 21 RHR Pump 22 Coolant Charging Pump 24 Fan Cooler Unit Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
E-1, Attachment 1 Page 21 Proposed References to be provided to applicants during examination: NONE
Page 114 of 241 Learning Objective: (As available)
Question Source: Bank # INPO 231a3
.L Modified Bank # YES (Note changes or attach parent)
New Question History: Salem Unit 1 11/04/2002 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Question, answer and distracters modified to make plant specific
Page 131 of 241 Examination Outline Cross-reference: Level RO SRO
.-.--, Tier # 2 64 Group # 1 WA # 103 A3.01 Importance Rating 3.9 4.2 Ability to monitor automatic operation of the containment systems including containment isolation Proposed Question: Common #58 An inadvertent Safety Injection Actuation and automatic Reactor Trip has occurred. It was noted during the performance of E-0, Reactor Trip or Safety Injection, that Letdown Isolation Valve, 201 failed to automatically close as required, and had to be manually closed. SI has subsequently been placed in DEFEAT and has been RESET in ES-1.l, SI Termination.
However, Containment Isolation (CIA) Phase A could NOT be reset when attempted.
Which of the following could be a cause for the failure of CIA, Phase A, to reset?
A. Letdown Isolation Valve, 201 failed to AUTOMATICALLY close as required.
B. Control switch for the Weld Channel & Penetration Pressurization System (WCPPS) is OPEN.
i--
C. Equipment Hatch Solenoid control switch is in NORM.
D. Isolation Valve Seal Water System valves (141 0, 1413, SOV-3518, and SOV-3519) control switches are OPEN.
Proposed Answer:
C. Equipment Hatch Solenoid control switch is in NORM.
Explanation (Optional):
A. Daisy Chain made up from switch position not valve position B. Control switch for WCPPS not Phase A valves C. Correct, switch needs to be in INCIDENT to make up Daisy Chain D. IVSWS valves switches should be open for Daisy Chain Technical Reference(s): (Attach if not previously provided)
E-0, Attachment 1, step 12 Page 29 Proposed References to be provided to applicants during examination: NONE v
Learning Objective: SYS-C-107-107108 (As available)
Page 132 of 241 Question Source: Bank # TM SYSC107-29 Modified Bank # (Note changes or attach parent)
.---- New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7,9) 55.43 Comments:
Page 139 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 68 Group # 2 WA # 001 K4.07 Importance Rating 3.2 3.4 Knowledge of the CRDS design feature(s) and/or interlock(s) which provide for the rod stops Proposed Question: Common #59 The following plant conditions exist on Unit 2:
Unit 2 is at 20% power.
Control rods are in MANUAL control.
WHICH ONE of the following describes two conditions that will prevent MANUAL OUTWARD movement of Control Bank D rods?
A. Power Range Nuclear Power 20% (1/4), Overtemperature AT variable setpoint (1/4) exceeded B. Intermediate Range Nuclear Power 20% equivalent (1/2), Overpower AT variable setpoint (1/4) exceeded C. Overtemperature AT variable setpoint (1/4) exceeded, TAVE- Avg T A V(+5"F)
~
D. Overpower AT variable setpoint (1/4) exceeded, First Stage Turbine Impulse Pressure, PT-412A, less that 15% power equivalent (1/1)
Proposed Answer:
B. Intermediate Range Nuclear Power 20% equivalent (1/2), Overpower AT variable setpoint (1/4) exceeded Explanation (Optional):
A. PR only provides 106% rod stop and 5%/5sec rod stop, OTnT correct B. Correct C. OTnT correct, TAvE- Avg TAVE (+5"F) Auto withdrawal rod stop not manual withdrawal D. OPnT correct, PT-412A Auto withdrawal block not manual block Technical Reference(s): (Attach if not previously provided)
ARP SAF Windows 1-8, 2-8 ARP FCF Windows 1-2, 1-3, 1-4 Proposed References to be provided to applicants during examination: NONE
~~ ~
Page 140 of 241 Learning 0bjective: SYS-C-161-289 (As available)
Question Source: Bank # INPO 22962 Modified Bank # YES (Note changes or attach parent)
New Question History: Prairie Island 2 8/16/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (6,7) 55.43 Comments:
Question, answer and distracters modified
Page 143 of 241 Examination Outline Cross-reference: Level RO SRO u-Tier # 2 70 Group # 2 WA # 033 K4.03 Importance Rating 2.6 2.9 Knowledge of design features@)and/or interlock(s) which provide for anti-siphon devices Proposed Question: Common #60 Which one of the following statements describes a design feature that prevents inadvertent draining of the spent fuel pool through the spent fuel pool cooling (SPFC) System?
A. SPFC pumps will automatically trip when the low SFP level alarm is annunciated.
B. SFPC discharge piping has a siphon breaker slightly below the normal water level.
C. Deepest SFPC piping extends only 6 feet down into the SFP.
D. Primary makeup valve to the SFP automatically opens on a low level in the SFP.
Proposed Answer:
B. SFPC discharge piping has a siphon breaker slightly below the normal water level.
Explanation (Optional):
A. There is no auto trip from low level for the SFP Pumps B. Correct C. Discharge piping extends to within 5'4" of top of the spent fuel racks D. Primary makeup to SFP is manual Technical Reference(@: (Attach if not previously provided)
SOD - 004 SD-4.3 Proposed Referencesto be provided to applicants during examination: NONE Learning Objective: SYS-(2-043-2630 (As available)
Question Source: Bank # INPO 25137 Modified Bank # YES (Note changes or attach parent)
New Question History: Millstone 2 12/04/2002 Question Cognitive Level: Memory or Fundamental Knowledge
Page 144 of 241 Comprehension or Analysis X
\--
10 CFR Part 55 Content: 55.41 (7) 55.43 Comments:
Question, Answer and distracters modified to make plant specific c
Page 145 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 L-71 Group # 2 WA # 035 K5.01 Importance Rating 3.4 3.9 Knowledge of operational implications of the effect of secondary parameters, pressure, and temperature on reactivity Proposed Question: Common #61 Given the following plant conditions:
Turbine load is at 100%.
0 CD-19, "23/24/25, Feedwater Heater Bypass Valve" is inadvertently opened.
How and why will reactor power respond to this condition?
A. Reactor power will decrease for a very short time due to less steam leaving the turbine extraction lines causing TCoLD to increase; MTC will add negative reactivity.
B. Reactor power will decrease due to the decrease in steam generator pressure caused by the colder feedwater entering the feed ring, less reactor power is needed to produce steam.
C. Reactor power will increase due to the colder water entering the steam generators causing TCoL, to drop; MTC will add positive reactivity.
D. Reactor power will increase for a very short time due to MTC adding negative reactivity, but then decrease as the steam generator pressure increases.
Proposed Answer:
C. Reactor power will increase due to the colder water entering the steam generators causing T c o L D to drop; MTC will add positive reactivity.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE L-Learning Objective: (As available)
Question Source: Bank # INPO 20633
Page 146 of 241 Modified Bank # (Note changes or attach parent)
New Question History: Point Beach 1 2/02/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5, 14) 55.43 Comments:
Minor modifications to question and distracters to make plant specific
Page 105 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 51 Group # 1 WA # 010 K6.01 Importance Rating 2.7 3.1 Knowledge of the effect that a loss or malfunction of the ECCS will have on Pressure Detection Systems Proposed Question: Common #62 The unit is at 100% power, steady state, normal operating temperature and pressure. The Pressurizer Pressure Master Controller setpoint fails to 2185 psig. Assume a step change in the setpoint and assume that pressurizer pressure control remains in automatic.
Which of the following is the immediate automatic response of the system?
A. PORV 455C opens, Spray valves open, Variable Heaters energize.
B. Spray valves open, Variable Heaters energize.
C. Spray valves close, Variable Heaters de-energize.
D. Spray valves open, Variable Heaters de-energize
'L Proposed Answer:
D. Spray valves open, Variable Heaters de-energize Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-(2-014-55 (As available)
SGOPSAOP8-1601066 Question Source: Bank # INPO 19189 Modified Bank # (Note changes or attach parent)
New Question History: Braidwood 1 10/20/2000
Page 106 of 241 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 13.7) 55.43 Comments:
Question modified to change correct answer
Page 147 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 72 Group # 2 WA # 041 G2.1.10 Importance Rating 2.7 3.9 Knowledge of conditions and limitations in the facility license.
Proposed Question: Common #63 Which one of the following is considered to be the most limiting event (time critical) concerning operation of the Atmospheric Dump Valves?
A. Inadequate Core Cooling accident with loss of off site power.
B. Main Steam Line Break accident inside containment with a loss of off site power.
C. Small Break Loss of Coolant accident without a loss of off site power.
D. Steam Generator Tube Rupture accident with a loss of off site power.
Proposed Answer:
D. Steam generator Tube Rupture accident with a loss of off site power.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: TAA-C-009-TO325, E02623 (As available)
Question Source: Bank # INPO 26186 Modified Bank # (Note changes or attach parent)
New Question History: Point Beach 1 9/29/2003 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (43)
____~
-~ _
Page 148 of 241 55.43 (1)
Comments:
J Minor modification to disctracter
Page 149 of 241 Examination Outline Cross-reference: Level RO SRO i, Tier # 2 73 Group # 2 WA # 045 Al.06 Importance Rating 3.3 3.7 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including expected response of secondary plant parameters following T/G trip Proposed Question: Common #64 The following plant conditions exist:
0 The plant is operating at 100%.
0 All systems are lined up in their normal lineups.
0 All control systems are in automatic.
0 A fault signal occurs from MO Disconnect Switch F7-9.
Which of the following describes the expected immediate plant response?
A. S/G pressure initially increases as main turbine is lost, S/G levels initially decrease due to shrink, feed flow initially increases.
B. S/G pressure initially increases as main turbine is lost, S/G levels initially decrease due to shrink, feed flow initially decreases.
C. S/G pressure initially decreases as main turbine is lost, S/G levels initially increase due to lower steam pressure, feed flow initially decreases.
D. S/G pressure initially decreases as main turbine is lost, S/G levels initially decrease due to shrink, feed flow initially increases.
Proposed Answer:
B. S/G pressure initially increases as main turbine is lost, S/G levels initially decrease due to shrink, feed flow initially decreases.
Explanation (Optional):
D - correct - initially (prior to steam dumps opening), steam header pressure increases due to the loss of steam demand. The increased back-pressure in the S/Gs partially suppresses boiling which causes shrink to occur in the S/Gs. The reduced steam demand inputs to the feed controller to reduce feed thus feed flow decreases.
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE
Page 150 of 241 Learning Objective: TAA-C-005-2503 (As available)
Question Source: Bank # INPO 24696 Modified Bank # {Note changes or attach parent)
New Question History: Seabrook 1 5/30/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5, 14) 55.43 Comments:
Page 151 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 74 Group # 2 WA # 075 G2.1.8 Importance Rating 3.8 3.6 Ability to coordinate personnel activities outside the control room Proposed Question: Common #65 The Circulating Water System Pumps (CW Pumps) are two speed pumps. Switching CW Pump speed from HIGH to LOW or LOW to High requires which one of the following items?
A. An operator imposed 20 second delay when switching from high to LOW B. The pump to be stopped prior to switching speeds C. No delay when switching from LOW to HIGH D. The pump recirculation valve to be opened Proposed Answer:
L B. The pump to be stopped prior to switching speeds Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
SOP-23.1 Page 1 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-240-230109 (As available)
Question Source: Bank # IP2 SYSC230-6 Modified Bank # (Note changes or attach parent)
New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge L'
Comprehension or Analysis X
Page 152 of 241 10 CFR Part 55 Content: 55.41 (7, 10) 55.43 Comments:
Page 127 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 c-62 Group # 1 WA # ~
064 G2.1.28
~ ~~
Importance Rating 3.4 3.3 Knowledge of the purpose and function of the major system components and controls Proposed Question: Common #66 Select the ONE answer that describes EDG governor and voltage control with the EDG paralleled to the BUS and the UNIT-PARALLEL switch in PARALLEL.
A. Increasing the governor will INCREASE bus frequency and Increasing the voltage rheostat will DECREASE bus voltage.
- 8. Increasing the governor will INCREASE EDG load and Increasing the voltage rheostat will DECREASE bus voltage.
C. Increasing the governor will INCREASE EDG load and Increasing the voltage rheostat will INCREASE lagging VARs.
D. Increasing the governor will INCREASE bus frequency and Increasing the voltage rheostat will INCREASE leading VARs.
Proposed Answer:
C. Increasing the governor will INCREASE EDG load and Increasing the voltage rheostat will INCREASE lagging VARs.
Explanation (Optional):
Technical Reference(@: (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-273-2790 (As available)
Question Source: Bank # Taskmaster SYSC273-3 Modified Bank # (Note changes or attach parent)
New Question History:
Page 128 of 241 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (8) 55.43 Comments:
Page 159 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 78 Group # 1 WA # 073 K1.O1 Importance Rating 3.6 3.9 Knowledge of the physical connections and/or cause-effect relationships between the PRM system and those systems served by PRMs Proposed Question: Common #67 What conditions must be met to reset a Containment Ventilation Isolation after a high containment air particulate or radiogas alarm has isolated the Containment Purge and Containment Pressure Relief lines in accordance with 2-SOP-5.4.3, Vapor Containment Purge?
A. The containment air particulate and radiogas alarms, R41/42, are the only signals that must be clear prior to resetting the Containment Ventilation Isolation.
B. Containment Phase A and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
C. Safety Injection must be reset and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
D. No conditions need to be met, the Containment Purge and Pressure Relief Lines do not
.-.. close on a high containment air particulate or radiogas alarm.
Proposed Answer:
C. Safety Injection must be reset and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-SOP-5.4.3 Page 23 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-120-120112 (As available)
Question Source: Bank # IP2 SYSC120-20 Modified Bank # (Note changes or attach parent)
New Question History:
Page 160 of 241 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7,8,9, 11) 55.43 Comments:
L-'
Page 187 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 92 Group # 1 WA # G2.1.29 Importance Rating 3.4 3.3 Knowledge of how to conduct and verify valve lineups.
Proposed Question: Common #68 During an independent verification a valve is found out of position. How should the verifier handle the component out of position situation?
A. Do NOT change valve position. Notify the Shift Manager of the discrepancy.
B. Do NOT change valve position. Notify the initial valve positioner of the discrepancy.
C. Correct the valve position. Have Shift Manager obtain new verifier for independent verification for that valve only.
D. Correct the valve position. Have the initial valve positioner perform the independent verification for that valve only.
Proposed Answer:
A. Do NOT change valve position. Notify the Shift Manager of the discrepancy.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
OAP-019 Page 6 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 26135 Modified Bank # (Note changes or attach parent)
New Question History: Prairie Island 1 10/3/2003 Question Cognitive Level: Memory or Fundamental Knowledge X
Page 188 of 241 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (10) 55.43 Comments:
Page 157 of 241 Examination 0utline Cross-reference: Level RO SRO Tier # 2 77 Group # 1 KIA # 064 A4.01 Importance Rating 4.0 4.3 Ability to manually operate and/or monitor in the control room local and remote operation of the ED/G Proposed Question: Common #69 Determine the affect on Emergency Diesel Generator operation if the Jacket Water Pump on an Emergency Diesel Generator had a broken shaft and the Emergency Diesel Generator received an AUTO start signal?
A. The Emergency Diesel Generator would start and continue to run, but the field would not
'flash' so there would be no generator output B. Without jacket water pressure the Emergency Diesel Generator would start, run for 2 minutes and shut down normally C. The Emergency Diesel Generator would run until it overheated, then low oil pressure would trip the 86 device D. The Emergency Diesel Generator would start but only run for about 37 seconds, then the 86 would trip Proposed Answer:
D. The Emergency Diesel Generator would start but only run for about 37 seconds, then the 86 would trip Explanation (Optional):
A. Jacket water pressure is used to allow field flash but the EDG would S/D B. Normal shutdown would not occur with 86 trip C. 37 seconds is not long enough for EDG to overheat D. Correct - Overcrank is sensed from Jacket Water Pressure Technical Reference(s): (Attach if not previously provided) 2-ARP-003 Window 1-2 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-273-2797/2798 (As available)
Question Source: Bank # I P2 27300301
Modified Bank # (Note changes or attach parent)
New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7,8) 55.43 Comments:
Minor modification to question
Page 189 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 93 Group # 1 KIA # G2.1.7 Importance Rating 3.7 4.4 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
Proposed Question: Common #70 The following plant parameters exist:
0 RCS pressure is 1600 psig and lowering.
0 Pressurizer level is slowly lowering.
0 PORVs and spray valves are closed.
0 All steam generator water levels are normal Plant ventilation radiation monitors are rising.
Containment pressure and sump levels are normal.
Which one of the following is the correct plant condition?
A. Faulted Steam Generator B. Ruptured Steam Generator C. LOCA Inside Containment D. LOCA Outside Containment Proposed Answer:
D. LOCA Outside Containment Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning 0bjective: (As available)
Question Source: Bank # INPO 20585 Modified Bank # (Note changes or attach parent)
___- ~ __ - -~
Page 190 of 241 New Question History: Point Beach 1 2/2/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 (5)
Comments:
Page 191 of 241 Examination Outline Cross-reference: Level RO SRO v-Tier # 3 94 Group ## 2 WA # G2.2.33 Importance Rating 2.5 2.9 Knowledge of control rod programming.
Proposed Question: Common #71 Given the following conditions:
0 Reactor power is 90%
0 Control Bank D is at 200 steps 0 Automatic rod control is selected Which ONE of the following statements describes the response of the rod control system if TAVE becomes 45°F more than TREF? (Assume no power mismatch effects)
A. The control rods step in at 32 steps per minute.
B. The control rods step in at 48 steps per minute.
C. The control rods step in at 56 steps per minute.
D. TAVEdeviation of more than 4°F will inhibit rod insertion.
Proposed Answer:
C. The control rods step in at 56 steps per minute.
Explanation (Optional):
A. 32 Steps per minute is rods speed / O F error B. 48 steps per minute is rod speed for 1.5"F above dead band minus 8 steps/min initial C. Correct D. TAVE to Average T A V E deviation blocks rod motion Technical Reference(s): (Attach if not previously provided)
SD-16.1 Figure 27 IP2-SOD-022 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-161-280 (As available)
Question Source: Bank # IP2 SYSCl61-11
~ ~ .___ ~ _ _ _ _ ___~
Page 192 of 241 Modified Bank # (Note changes or attach parent)
New i-Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (6) 55.43 (6)
Comments:
Page 199 of 241 Examination 0utIine Cross-reference: Level RO SRO Tier # 3 L
9a Group # 4 WA # G2.4.16 Importance Rating 3.0 4.0 Knowledge of EOP implementation hierarchy and coordination with other support procedures.
Proposed Question: Common #72 A reactor trip has occurred. During the CRS read-through of E-0, Reactor Trip Or Safety Injection, Step 3, an Orange Path condition is observed by the Watch Engineer to exist on a Critical Safety Function (CSF) Status Tree.
Transition to the Orange Path procedure should take place:
A. immediately after confirming the Orange Path condition NO Red Path condition is verified to exist on remaining status trees.
B. immediately after the CRS completes reading step 4 and NO Red Path condition is verified to exist on remaining status trees.
C. when transitioning to another E-series procedure and NO Red Path condition is verified to exist on remaining status trees.
D. as soon as NO Red Path condition is verified to exist on remaining status trees.
Proposed Answer:
C. when transitioning to another E-series procedure.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
OAP-012 Page 11 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
L, Question Source: Bank # INPO 26142 Modified Bank # (Note changes or attach parent)
New
Page 200 of 241 Question History: Prairie Island 1 10/03/2003 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Page 201 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 99 Group # 4 WA # G2.4.6 Importance Rating 3.1 4.0 Knowledge symptom based EOP mitigation strategies Proposed Question: Common #73 Given the following plant conditions:
0 Following a series of plant malfunctions, operators are currently implementing ECA 0.0, Loss of All AC Power.
0 The operators have reached the point in the procedure where they are to begin depressurization of the Steam Generators.
Which of the following statements indicates the reason that a secondary depressurization is performed?
A. To ensure the reactor remains subcritical and does not result in a restart accident.
- 6. To remove stored energy in the Steam Generators to prevent a secondary side Safety Valve from lifting.
C. To minimize RCS inventory loss through the RCP seals, which maximizes time to core uncovery.
D. To depressurize the RCS in order to prevent a challenge to the "Integrity" Critical Safety Function Status Tree which is being monitored for implementation.
Proposed Answer:
C. To minimize RCS inventory loss through the RCP seals, which maximizes time to core uncovery.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ECA-0.0 Background Page 104 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Page 202 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent) c New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Page 203 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 100 Group # 4 KIA # G2.4.1 Importance Rating 4.3 4.6 Knowledge of EOP entry conditions and immediate action steps.
Proposed Question: Common #74 The following conditions exist:
The plant has sustained an ATWS.
The team has entered FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, from E-0, Reactor Trip or Safety Injection, step 1.
The OTC operator was unable to trip the turbine by pressing the Manual Turbine Trip pushbutton.
What action should he take next?
A. Open the Generator breaker.
B. Close MSIVs.
L- C. Manually run back the turbine.
D. Commence Emergency Boration of RCS Proposed Answer:
C. Manually run back the turbine.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
FR-S.1 Step 2 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-002-503 (As available)
Question Source: Bank # INPO 24659 Modified Bank # (Note changes or attach parent)
New
Page 204 of 241 Question History: Seabrook 1 5/30/2003 d-Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Page 219 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 108 Group # 1 KIA # G2.1.20 Importance Rating 4.3 4.2 Ability to execute procedure steps.
Proposed Question: Common #75 Unit 2 is operating at 100% power when a sequence of annunciators actuate, indicating a loss of feedwater and a reactor trip, but NO reactor trip occurs. The following plant status is noted:
0 All attempts to perform a manual reactor trip fail.
0 An urgent failure prevents all rod motion.
0 All auxiliary feedwater pumps are operating.
0 The turbine remains on-line (AUTO turbine trip did not occur).
0 Reactor power remains near 100%.
0 Reactor coolant system temperature and pressure slowly increase from 100% power values.
Which one of the following correctly states the action that the operator should take to mitigate the transient from this condition?
A. Reduce turbine load slowly to avoid a rapid reactor coolant system temperature and pressure increase, leading to opening of a pressurizer safety valve.
B. Trip the turbine to conserve the secondary coolant inventory to allow future RCS cooldown and depressurization.
C. Open the PORVs immediately because the increasing pressure will take the pressurizer solid, resulting in insufficient water relief.
D. Align maximum auxiliary feedwater flow to one steam generator to maintain it as a heat sink for cooldown of the reactor coolant system.
Proposed Answer:
B. Trip the turbine to conserve the secondary coolant inventory to allow future RCS cooldown and depressurization.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
FR-S.l Step 2 FR-S.l Background Page 64
Page 220 of 241 Proposed References to be provided to applicants during examination: NONE i-.
Learning Objective: EO P-C-042-3559/4633 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Page 217 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 L
107 Group ## 4 WA # G2.4.6 Importance Rating 3.1 4.0 Knowledge of symptom based EOP mitigation strategies Proposed Question: Common #76 SRO-only Given the following sequence of events:
0 The plant was initially operating at 35% power.
0 High containment pressure resulted in Safety Injection, Steamline Isolation and Containment Spray Actuation.
0 RCS Pressure is 0 psig Containment Pressure is 25 psig 0 No ABFPs can be started from the control room 0 All SG Narrow Range Levels indicate 15%.
0 All SG pressures have stabilized at 700 psig Which of the following describes the correct sequence of EOP implementation?
The team will enter E-0, Reactor Trip or Safety Injection; transition to:
A. E-1, Loss of Reactor or Secondary Coolant, FR-H.1, Loss of Heat Sink, from Status Trees, after SG levels lower to less that 10% Narrow Range B. FR-H.1, Loss of Heat Sink, when no Aux Feedwater Flow can be established, then back to E-0, with RCS pressure less than SG pressure C. FR-H.l, Loss of Heat Sink, when no Aux Feedwater Flow can be established, then to E-1, with RCS pressure less than SG pressure D. E-1, Loss of Reactor or Secondary Coolant, then to ES-1.3 when RWST level drops below 9.24 feet Proposed Answer:
B. FR-H.l, Loss of Heat Sink, when no Aux Feedwater Flow can be established, then back to E-0, with RCS pressure less than SG pressure Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
E-0 Step 7 FR-H.1 Step 1
Page 218 of 241 Proposed References to be provided to applicants during examination: NONE L
Learning 0bjective: (As available)
Question Source: Bank # INPO IP2 23309 Modified Bank # YES (Note changes or attach parent)
New Question History: Indian Point 2 3/10/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Question, Answer and Distracters modified
Page 87 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 42 Group # 2 Rev per TF WA # 002 K5.07 Importance Rating 3.3 3.6 Knowledge of the operational implications of reactivity effects of RCS boron, pressure and temperature as they apply to the RCS Proposed Question: Common #77 SRO-only The unit is in MODE 6 for a refueling outage. Fuel movements are in progress to reload the reactor core.
Chemistry's sample of the RCS indicates that the boron concentration of the reactor coolant is 1960 ppm. What TS ACTION is required?
A. Continue with CORE ALTERATIONS, suspend any positive reactivity additions and initiate actions to restore boron concentration limit B. Immediately lower any suspended fuel assemblies back into reactor vessel and initiate action to restore boron concentration limit C. Immediately suspend all core reload operations, core offload operations may continue provided actions to restore boron concentrations limit is commenced D. Immediately suspend CORE ALTERATIONS, suspend positive reactivity additions and initiate action to restore boron concentration limit Proposed Answer:
D. Immediately suspend CORE ALTERATIONS, positive reactivity additions and initiate action to restore boron concentration limit Explanation (Optional):
A. Must suspend all core alterations B. Lowering suspended fuel into core is required for decreasing cavity level C. Must suspend all core alterations even off load D. Correct Technical Reference(s): (Attach if not previously provided)
Tech Spec 3.9.1, Cond A Page 3.9.1 -1 COLR Page 5 Proposed References to be provided to applicants during examination: COLR Page 5 Learning Objective: ITS-C-012-0393, 0394 (As available)
Page 88 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 (2,6, 7)
Comments:
Page 119 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 L-58 Group # 1 WA # 000009 EK2.03 Importance Rating 3.0 3.3 Knowledge of the interrelations between the small break LOCA and the Steam Generators.
Proposed Question: Common #78 SRO-only The following plant conditions exist:
0 A reactor trip with SI has occurred.
0 The team transitioned from E-0, Reactor Trip or Safety Injection, to FR-H.l, Loss of Secondary Heat Sink, from step 7, based on AFW flow e400 gpm and all SG levels
<lo%
RCS pressure is 700 psig and slowly decreasing.
0 All S/G pressures are approximately 950 psig and stable.
Which of the following summarizes plant conditions and what procedure should be implemented?
A. Remain in FR-H.l until feed is restored then transition to E-1 where a depressurization of the secondary is prescribed to increase the heat transfer between the RCS and S/Gs.
B. Heat transfer in the RCS during this event is such that the S/Gs are currently not functioning as a heat sink. Remain in FR-H.l to restore S/G levels to normal band.
C. Heat transfer in the RCS during this casualty is such that the S/Gs are currently not functioning as a heat sink and therefore not required. Transition back to E-0, Reactor Trip or Safety Injection, step 7.
D. Heat transfer in the RCS during this casualty is such that the S/Gs are currently not functioning as a heat sink and therefore not required. Transition to E-1, Loss of Reactor or Secondary Coolant, step 1.
Proposed Answer:
C. Heat transfer in the RCS during this casualty is such that the S/Gs are currently not functioning as a heat sink and therefore not required. Transition back to E-0, Reactor Trip or Safety Injection, step 7.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
E-0 Step 7 FR-H.l Step 1
Page 120 of 241 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-044-3561 (As available)
Question Source: Bank # INPO 24717 Modified Bank # YES (Note changes or attach parent)
New Question History: Seabrook 1 5/30/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (5)
Comments:
Page 121 of 241 Examination Outline Cross-reference: Level RO SRO
'V' Tier # 1 59 Group # 1 WA # 000015/017 A2.02 Importance Rating 2.8 3.0 Ability to determine and interpret abnormalities in RCP air vent flow paths and/or oil cooling system as they apply to the Reactor Coolant Pump Malfunction Proposed Question: Common #79 SRO-only A Component Cooling water leak inside containment has caused reduced flow to the RCPs.
The following conditions exist:
Unit 2 is at 100% power.
Temperatures / RCP# 21 22 23 24 Motor Bearing 189°F 205°F 177°F 181"F Stator Winding 220°F 225°F 215°F 229°F Seal Inlet 195°F 185°F 205°F 200°F Annunicator RCP Hi Not Lit Not Lit Not Lit Not Lit Vibration v Which ONE of the following set of actions must be taken?
A. Trip Reactor, secure all RCPs, Initiate E-0 B. Trip Reactor, secure 22 RCP, Initiate E-0 C. Trip Reactor, secure 23 RCP, Initiate E-0 D. Perform a rapid plant shutdown, secure RCPs as necessary to isolate CCW leak Proposed Answer:
B. Trip Reactor, secure 22 RCP, Initiate E-0 Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-AOP-RCP-1, Step 1
'*c' Proposed References to be provided to applicants during examination: NONE Learning Objective: AOP-C-RCP1-1601040 (As available)
~ ~~
Page 122 of 241 Question Source: Bank # INPO 22799 Modified Bank # YES (Note changes or attach parent)
New Question History: Cook 1 12/9/2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 Comments:
Question, answer and distracters modified
Page 123 of 241 Examination Outline Cross-reference: Level RO SRO
'v Tier # 1 60 Group # 1 WA # 000040 G2.4.6 Importance Rating 3.1 4.0 Knowledge of symptom based EOP mitigation strategies Proposed Question: Common #80 SRO-only You have entered ECA-2.1, "Uncontrolled Depressurization of All Steam Generators" and are performing SI Termination. Steam generator #24 pressure suddenly begins to rise.
Which one of the following actions is correct?
A. Once the SI termination is complete, ECA-2.1 is complete and you are returned to procedure step in effect.
B. Continue performing SI Termination and complete remaining steps of ECA- 2.1, the RCS is now cooled to a point that the steam generators are beginning to fill.
C. Stop performing SI Termination and go to E-2 because the pressure boundary has been established in steam generator #24.
i, D. Complete performing SI Termination and then go to E-2, because the pressure boundary has been established in steam generator #24.
Proposed Answer:
D. Complete performing SI Termination and then go to E-2, because the pressure boundary has been established in steam generator #24.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ECA-2.1 - Foldout Page Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-026-3546 (As available)
Question Source: Bank # INPO 19545 Modified Bank # (Note changes or attach parent)
New
Page 124 of 241 Question History: Cook 1 5/2 1/200 1 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 Comments:
Minor modifications to answer and distractors
Page 97 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 47 Group # 2 Replaced per TF KIA # G2.2.25 Importance Rating 2.5 3.7 Equipment Control; Knowledge of bases in technical specifications for limiting conditions for operations and safety limits Proposed Question: Common #81 SRO-only It is determined that the Containment Spray System and FCU TS LCO (TS 3.6.6) is not met solely due to an AC electrical distribution subsystem (TS 3.8.9) being declared inoperable.
Which one of the following describes when a safety function determination must be performed?
A. When the support system's Required Actions direct entry into Conditions and Required Actions for the supported system.
B. When the support system's Required Actions direct the supported system to be declared inoperable.
C. When the Conditions and Required Actions associated with the supported system LCO are NOT entered.
D. When the Conditions and Required Actions associated with the support system LCO are NOT entered.
Proposed Answer:
C. When the Conditions and Required Actions associated with the supported system LCO are NOT entered.
Explanation (Optional):
When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. In this event, an evaluation shall be performed in accordance with TS 5.5.13.
Technical Reference(s): (Attach if not previously provided)
TS 5.5.13 Pages 5.5-13 & 14 TS Section 3.0, LCO 3.0.6 Page 3.0-2 Section 3.0.6 Bases Pages 3.0-8 & 9 Proposed References to be provided to applicants during examination: NONE Learning Objective: ITS-C-001-0103 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent) c New YES Question History: New Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (2)
Comments:
Page 155 of 241 Examination Outline Cross-reference: Level RO SRO
'L Tier # 1 76 Group # 1 WA # W/E11 EA2.2 Importance Rating 3.4 4.2 Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to Loss of Emergency Coolant Recirculation Proposed Question: Common #82 SRO-only The following sequence of events occurs:
Unit 2 was operating at 100% power 0 Small break LOCA occurred 25 minutes ago.
0 The Team is currently implementing ECA 1.l, Loss of Emergency Coolant Recirculation due to loss of recirculation capability.
0 RCS Pressure is 450 psig 0 Containment pressure is 4 psig.
Given the attached reference from ECA 1.l, Loss Of Containment Sump Recirculation, which of the following indicates the REQUIRED correct combination of Containment Fan Cooler Units and Containment Spray Pumps that should be operating under these conditions?
A. 4 FCUs, 0 Spray Pumps B. 1 FCU, 1 Spray Pump C. 0 FCU, 1 Spray Pump D. 0 FCU, 2 Spray Pumps Proposed Answer:
D. 0 FCU, 2 spray Pumps Explanation (Optional):
25 minutes from start of small break LOCA with no RHR pumps injecting, the RWST level will be >9.24 ft. With VC pressure 4 psig, Table Step 4 requirements only met with 0 FCUs and 2 Spray Pumps Technical Reference(s): (Attach if not previously provided)
ECA-1.1 Step 4 Table Proposed References to be provided to applicants during examination: ECA-1.1, Step 4 Table
Page 156 of 241 Learning Objective: (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledae Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (5)
Comments:
Page 161 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 79 Group # 1 WA # 000038 EK2.02 Importance Rating 2.4 2.5 Knowledge of the interrelations between sensors and detectors and a SGTR Proposed Question: Common #83 SRO-only After a Reactor Trip the following parameter values and trends are noted:
0 Pressurizer Level is 0%.
0 RCS Pressure is 1500 psig and lowering.
RCS TCoLDis 530°F and slowly trending down.
0 Containment pressure is 0.2 psiv and steady.
0 Containment Average Temperature is 105°F and lowering.
0 Main Steam Line Radiation Monitor R29 is in alarm and trending up.
0 SG 21 22 23 24 Wide Range 46% 31% 47% 45%
Level trending up trending down trending up trending up
.- AFW Flow 205 stable 200 stable 200 stable 210 stable Assuming that all other equipment responded as designed, Which of the following statements describes the events in progress?
A. Steam Generator Tube Rupture and isolated LOCA in the Letdown System.
B. Main Steam Line Break outside Containment and Steam Generator Tube Rupture.
C. Main Steam Line Break outside Containment and isolated LOCA in Letdown.
D. Main Steam Line Break and Loss of Coolant Accident inside Containment.
Proposed Answer:
B. Main Steam Line Break outside Containment and Steam Generator Tube Rupture.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-032-635 (As available)
Question Source: Bank # INPO 25582 Modified Bank # (Note changes or attach parent)
New Question History: ANO, Unit 2 7111/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
Question modified to make plant specific
Page 163 of 241 Examination Outline Cross-reference: Level RO SRO u
Tier # 1 80 Group # 1 KIA # 000054 AK1.01 Importance Rating 4.1 4.3 Knowledge of the operational implications of a MFW line break depressurizes the S/G concepts as it applies to a Loss of Main Feedwater Proposed Question: Common #84 SRO-only The following conditions exist immediately following a reactor trip from 50% power:
Pressurizer Level 38% (lowering)
Pressurizer Pressure 2150 psia (lowering)
Containment sump levels rising Containment temperature145°F (rising)
Containment pressure 2.6 psig (rising)
Containment area radiation monitors R41/42 - 2.1 E-11 vCi/cc Containment wide range area radiation monitors R25/26 - 1.1 Whr LOOP 21 22 23 24 TCOLD 539°F 538°F 539°F 533°F lowering lowering lowering lowering e
Stm Gen 21 22 23 24 NR Level 44% 44% 44% 0%
lowering lowering lowering stable WR Level 49% 49% 49% 34%
increasing increasing increasing decreasing Pressure 910 psig 910 psig 910 psig 800 psig Which of the following is indicated by the given plant conditions?
A. Pressurizer Steam Space Small Break LOCA B. Loop 24 Main Feedwater Break Inside Containment C. Loop 24 Main Steam Break Outside Containment D. Loop 24 Cold Leg Small Break LOCA L Proposed Answer:
B. Loop 24 Main Feedwater Break Inside Containment
Page 164 of 241 Explanation (Optional):
'V Technical Reference(s): (Attach if not previously provided)
Proposed References to be provided to applicants during examination: NONE Leaming Objective: (As available)
Question Source: Bank # INPO 25583 Modified Bank # YES (Note changes or attach parent)
New Question History: ANO, Unit 2 7111/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 (8,10) 55.43 (5)
Comments:
Question, Answer and Distracters modified
Page 165 of 241 Examination Outline Cross-reference: Level RO SRO I .. '
Tier # 1 81 Group # 1 WA # 000056 AK3.02 Importance Rating 4.4 4.7 Knowledge of the reasons for actions contained in EOP for loss of offsite power as they apply to Loss of Offsite Power Proposed Question: Common #85 SRO-only A Reactor Trip with Loss of Offsite Power has occurred. During the performance of ES-0.2, Natural Circulation Cooldown, the RCS is depressurized to 1890 psig. What is the reason for stopping the depressurization at 1890 psig?
A. Minimize vessel stress caused by uneven cooldown during natural circulation.
B. Ensure NPSH met for restart of RCP's when power is restored.
C. Prevent 1700 psid between RCS and S/G.
D. Maintain minimum of 50°F subcooling.
Proposed Answer:
D. Maintain minimum of 50°F subcooling.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ES-0.2, step 7 & 8 Background Pages 27,28 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-007-3530 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES c
Question History:
Question Cognitive Level: Memory or Fundamental Knowledge
Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5, 10) 55.43 (5)
Comments:
New Question L-,
Page 167 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 82 Group ## 2 WA # 000001 AK1.03 Importance Rating 3.9 4.0 Knowledge of the operational implications of the relationship of reactivity and reactor power to rod movement as they apply to Continuous Rod Withdrawal Proposed Question: Common #86 SRO-only Given the following plant conditions:
Reactor Power 10-8 amps, BOL 0 RCS at normal operating temperature and pressure Control Bank D at 80 steps withdrawn 0 Pressurizer Pressure and Level control in automatic 0 OTC commences rod withdrawal to raise power to 10-6 amps per POP-1.2, Reactor Startup, Mode 3 to Mode 2 When intermediate SUR indicates 0.4 DPM OTC releases shim switch but rods continue to move outward due to stuck shim switch.
With no further operator action, determine the effect on the reactor A. Reactor will trip due to Turbine Trip with power greater than P-8 B. Reactor will trip due to Pressurizer High Pressure Reactor Trip C. Reactor will trip due to Intermediate Range High Flux Reactor Trip D. Reactor remains critical, Rod motion will stop at 20% due to Intermediate Range Flux Level High Rod Stop Proposed Answer:
A. Reactor will trip due to Turbine Trip with power greater than P-8 Explanation (Optional):
A. Correct - P-8 clears at 20%
B. Pressurizer Pressure control in automatic will maintain proper pressure C. Turbine tripped will cause Rx trip prior to 25% intermediate range reactor trip D. Rod motion will stop at 20% but reactor will trip due to turbine tripped Technical Reference(s): (Attach if not previously provided)
ARP - FDF Window 4-7
Page 168 of 241 ARP - FAF Window 1-2
- Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (8, 10) 55.43 (6)
Comments:
New Question
Page 171 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 84 Group # 2 KIA ## W/E 01 EK1.2 Importance Rating 3.4 4.0 Knowledge of the operational implications of normal, abnormal and emergency operating procedures associated with Reactor Trip or Safety Injection / Rediagnosis Proposed Question: Common #87 SRO-only The plant has undergone a Reactor Trip and Safety Injection. The Team transitioned to E-3, Steam Generator Tube Rupture, from E-0, Reactor Trip or Safety Injection, due to elevated Steam Generator Radiation levels from a previous 0.5 gpm Steam Generator tube leak.
The CRS has transitioned to ES-0.0, Rediagnosis, to evaluate if the Team is in the correct guideline.
Given the following:
All SI pumps and 21 RHR pump are running RCS press is 1900 psig and rising slowly PZR level is 30 % and rising slowly TAVE is 544°F and rising slowly SG radiations levels same as from SG tube leak All SG Pressures are 1000 psig and stable All SG Levels are 5% NR and rising slowly AFW Flow is 200 gpm to each SG Based on the given plant conditions, the CRS should transition to which of the following procedures?
A. ES-1.1, SI Termination, Step 1 B. E-0, Reactor Trip or Safety Injection, Step 1 C. E-1, Loss of Reactor or Secondary Coolant, Step 1 D. E-3, Steam Generator Tube rupture, Step 1 Proposed Answer:
C. E-1, Loss of Reactor or Secondary Coolant, Step 1 Explanation (Optional):
A. SI termination criteria met for given plant conditions but must first transition to E-1 B. E-0 was already completed prior to transition to E-3 C. Correct, there is no faulted SG or SG with uncontrolled increase in level or abnormal radiation levels D. E-3 not required since radiation levels from SG tube leak and no SG level increasing
Page 172 of 241 abnormally Technical Reference(s): (Attach if not previously provided)
ES-0.0 Pages 2,3 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-003-507 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (8, 10) 55.43 (5)
Comments:
New Question
Page 221 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 L
109 Group # 2 WA # 000069 G2.2.14 Importance Rating 2.1 3.0 Knowledge of the process for making configuration changes Proposed Question: Common #88 SRO-only Unit 2 is preparing to enter a maintenance outage. The Unit is in Mode 4 with RHR system in service and 1 RCP operating. The Maintenance Supervisor has requested to override the 80 ft.
VC airlock mechanical interlocks to facilitate placing required maintenance equipment into containment. Determine which of the below statements will allow the mechanical interlocks to be overridden in accordance with OAP-007, Containment Entry and Egress:
A. The VC airlock mechanical interlocks may be overridden ANYTIME with Shift Manager approval.
B. The VC airlock mechanical interlocks may be overridden ONLY with the Unit in Mode 5 or Mode 6 C. The VC airlock mechanical interlocks may be overridden during Mode 4 with a dedicated L watch assigned to set containment integrity.
D. The VC airlock mechanical interlocks may be overridden after a Temp Alt has been written in accordance with ENN-DC-136, Temporary Alterations.
Proposed Answer:
B. The VC airlock mechanical interlocks may be overridden ONLY with the Unit in Mode 5 or Mode 6 Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
OAP-007 Page 47 TS 3.6.2 Page 3.6.2-1 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
~G Question Source: Bank #
Modified Bank # (Note changes or attach parent)
Page 222 of 241 New YES Question History:
c Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (3)
Comments:
New Question L-.
Page 177 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 87 Group # 1 WA # 004 K5.19 Importance Rating 3.5 3.9 Knowledge of the operational implications of the concept of SDM as it applies to the CVCS Proposed Question: Common #89 SRO-only Given the following:
0 The Unit is in Mode 3 0 Plant cooldown is in progress 0 RCS temperature is 520°F 0 RCS Boron Concentration is 600 ppm Reactor Engineering informs the control room that the SDM is 1.2%
Using the attached COLR, determine what action, if any, is required to be performed for the given conditions.
A. Initiate boration to restore SDM to within limits within 15 minutes B. Initiate boration to restore SDM to within limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Cooldown may continue but do not enter Mode 4 until SDM within limits D. No action required, SDM within limits of COLR for given conditions Proposed Answer:
A. Initiate boration to restore SDM to within limits within 15 minutes Explanation (Optional):
A. Correct, TS 3.1 .l, Condition A, required SDM from COLR Figure 2 is 1.5 B. Completion time is 15 minutes to restore SDM C. TS 1.1.1 is applicable in Modes 2 with Keff e1 .O and 3, 4 & 5 D. SDM required to be above curve of COLR Figure 2 Technical Reference(s): (Attach if not previously provided)
TS 3.1.1 Page 3.1.1 -1 GraDh RPC-5 COLR Fiaure 2 Proposed References to be provided to applicants during examination: Graph RPC-6 COLR Figure 2
Page 178 of 241 Learning Objective: SYS-C-O30-30105/30114 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New NEW Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 (1,2)
Comments:
New Question
Page 179 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 L.
88 Group ## 1 WA # 005 A2.03 Importance Rating 2.9 3.1 Ability to predict the impacts of RHR pump/motor malfunctions or operations on the RHRS and based on those predictions use procedures to correct, control or mitigate the consequences of those malfunctions or operations Proposed Question: Common #90 SRO-only The Unit is in Mode 6 for Vessel Head O-Ring repair with 21 RHR pump in service providing core cooling. A loss of 21 RHR occurs and 2-AOP-RHR1, loss of RHR, is implemented. Per 2-AOP-RHR-1, containment closure is required to be established if RCS temperature will reach 200°F within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Given the following plant conditions:
0 Reactor Vessel Head is in the process of being de-tensioned 0 Reactor has been shutdown for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 0 RCS temperature is 130°F and stable L- Using the attached graphs, determine the amount of time remaining before the RCS exceed 200°F.
A. 2.5 minutes
- 6. 8 minutes C. 28 minutes D. 53 minutes Proposed Answer:
B. 8 minutes Explanation (Optional):
A. Warning time in procedures that boiling could occur in as little as 2.5 minutes
- 6. Correct from Graph ACS-2C, RCS level at 66 C. Time to 200°F using Graph ACS-2D, Reactor Cavity level at 92 D. Time to 200°F using Graph ACS-2F, RCS filled and Coupled Technical Reference(s): (Attach if not previously provided) 2-AOP-RHR- 1
Page 180 of 241 Graph ACS 2C Rev 9 Graph ACS 2D Rev 8 Graph ACS 2F Rev 0 Proposed References to be provided to applicants during examination: Graph ACS-2C, 2D, 2F Learning Objective: SYS-C-042-114 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 (5)
Comments:
- .- New Question
Page 181 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 89 Group # 1 WA # 008 A2.02 Importance Rating 3.2 3.5 Ability to predict the impacts of Highhow surge tank level malfunction or operations on the CCWS and based on those predictions use procedures to correct, control or mitigate the consequences of those malfunctions or operations Proposed Question: Common #91 SRO-only Given the following plant conditions:
Unit 2 was operating at 100% power when a loss of coolant event occurred.
The operating Team has just entered ES-1.3, Transfer To Cold Leg Recirculation.
Shortly after initiating ES-1.3, a service water leak has caused ALL 3 CCW pumps to trip on overcurrent.
The CRS directs that all 3 CCW pumps be placed in pullout.
All other equipment is operating per design.
Based on these conditions, which of the following correctly describes the impact of these events during subsequent actions to establish cold leg recirculation?
A. Start 2 CCW pumps regardless of CCW Surge Tank level while performing ES-1.3. A transition to ECA 1.I, Loss of Emergency Coolant Recirculation, will be required when the last CCW pump trips.
B. Alignment for cold leg recirculation will NOT continue without CCW. A transition to ECA 1.l, must be made immediately.
C. 2-AOP-CCW-1, Loss of Component Cooling Water, must be entered immediately to address the CCW leak. ES-1.3 will be utilized as a secondary priority until CCW is restored.
D. Alignment for cold leg recirculation will continue without CCW. Auxiliary Component Cooling Water Pumps will be verified running.
Proposed Answer:
D. Alignment for cold leg recirculation will continue without CCW. Auxiliary Component Cooling Water Pumps will be verified running.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
ES-1.3, step 7 Page 5
Page 182 of 241 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-013-3535 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5)
Comments:
Page 175 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 86 Group # 2 KIA ## W/E09 EA2.2 Importance Rating 3.4 3.8 Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to Natural Circulation Operations Proposed Question: Common #92 SRO-only Given the following plant conditions:
0 Loss of Offsite power has occurred.
0 A plant cooldown is in progress per ES-0.2, "Natural Circulation Cooldown" 0 Adequate RCS subcooling is being maintained 0 The Control room operators suspect void formation in the reactor vessel head due to large variations in Pressurizer level Cooldown and Depressurization with vessel void formation is NOT desirable In accordance with ES-0.2, "Natural Circulation Cooldown", which of the following is used to collapse the void?
A. Implement ES-0.3, Natural Circulation Cooldown with Steam Void In Vessel, to collapse the void.
B. Increase Reactor Coolant System (RCS) pressure using pressurizer heaters.
C. Decrease RCS temperature while maintaining RCS pressure constant D. Increase RCS pressure by starting Safety Injection pumps.
Proposed Answer:
B. Increase Reactor Coolant System (RCS) pressure using pressurizer heaters.
Explanation (Optional):
A. ES-0.3 only used if C/D and Depressurization required to be done at rate that will produce a void, Note prior to step 12.
B. Correct C. Cooldown is stopped only if subcooling is lost, step 13 D. Safety Injection pumps are not used in ES-0.2 Technical Reference(s): (Attach if not previously provided)
ES-0.2 & Background Step 14 & Background Page 41
Page 176 of 241 Proposed References to be provided to applicants during examination: NONE Learning Objective: EOP-C-007-3530 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (5)
Comments:
Page 183 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 90 Group ## 1 KIA # 062 K4.01 Importance Rating 2.6 3.2 Knowledge of AC distribution system design features and/or interlocks which provide for Bus lockouts Proposed Question: Common #93 SRO-only Unit 2 was operating at 100% power when a winding short developed on 21 RCP. The overcurrent conditions caused a loss of 6.9KV Bus section 1. With no operator action, determine the electrical plant (6.9KV and 480V) configuration 60 seconds after the fault on 6.9KV Bus section 1.
A. 6.9KV Buses 2, 3, 4, 5 & 6 energized from Station Auxiliary Transformer and Bus 1 de-energized 480V Buses 2A, 3A, 5A & 6A energized from Station Service Transformers 2,3,5 & 6 B. 6.9KV Buses 3,4, 5 & 6 energized from Station Auxiliary Transformer and Buses 1 & 2 de-energized 480V Buses 3A, 5A & 6A energized from Station Service Transformers 3, 5 & 6 and 480V Bus 2A de-energized C. 6.9KV Buses 3,4, 5 & 6 energized from Station Auxiliary Transformer and Buses 1 & 2 de-energized 480V Buses 5A & 6A energized from Station Service Transformers 5 & 6 and 480V Buses 2A & 3A de-energized D. 6.9KV Buses 3,4, 5 & 6 energized from Station Auxiliary Transformer and Buses 1 & 2 de-energized 480V Buses 2A, 3A, 5A & 6A energized from EDGs 21,22 & 23 Proposed Answer:
B. 6.9KV Buses 3,4, 5 & 6 energized from Station Auxiliary Transformer and Buses 1 & 2 de-energized 480V Buses 3A, 5A & 6A energized from Station Service Transformers 3, 5 & 6 and 480V Bus 2A de-energized Explanation (Optional):
Loss of Bus Section 1 will cause single loop loss of flow Rx trip. Loss of bus section 1 will cause loss of auto transfer of Bus section 2 due to loss of sync check. Bus sections 5 & 6 will remain powered from Station Aux Trans. And Buses 3 &4 will auto transfer to Bus section 6.
480V buses 3A, 5A & 6a remain powered from Bus Sections 3,5 & 6 due to no Blackout signal present. Buses 2A will be de-energized. All 3 EDGs start but do not auto close onto the buses.
Technical Reference(s): (Attach if not previously provided)
Page 184 of 241 L
Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-271-426/427 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (71 Comments:
Page 185 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 2 91 Group # 2 WA # 034 A2.01 Importance Rating 3.6 4.4 Ability to predict the impacts of a dropped fuel element on the Fuel Handling System and based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations Proposed Question: Common #94 SRO-only The following conditions exist:
There is a core off-load in progress.
The fuel handler was moving irradiated fuel to a location in the spent fuel pool.
You are notified that the spent fuel bundle was accidentally dropped in the spent fuel pool.
The fuel handler reports the fuel bundle fell into the correct pool location.
R44, Plant Vent radiation monitor reads 4E-3 pCi/cc and is steady.
What actions, if any, are required?
./ A. No action is required.
B. Enter procedure 2-AOP-FH-1, Fuel Damage or Loss of SFP/Refueling Cavity Level.
Suspend ALL fuel handling operations in FSB, Evacuate non-essential personnel from the FSB, secure FSB ventilation and monitor R44.
C. Enter procedure 2-AOP-FH-1, Fuel Damage or Loss of SFP/Refueling Cavity Level.
Suspend ALL fuel handling operations in FSB, Evacuate ALL personnel from the FSB, dispatch an operator to close ALL FSB doors and monitor R44.
D. Enter procedure 2-AOP-FH-1, Fuel Damage or Loss of SFP/Refueling Cavity Level.
Suspend ALL fuel handling operations in FSB, Evacuate ALL personnel from the FSB and dispatch an operator to independently verify proper fuel bundle location and monitor R44.
Proposed Answer:
C. Enter procedure 2-AOP-FH-1, Fuel Damage or Loss of SFP/Refueling Cavity Level.
Suspend ALL fuel handling operations in FSB, Evacuate ALL personnel from the FSB, dispatch an operator to close ALL FSB doors and monitor R44.
Explanation (Optional):
i-.
All personnel must be evacuated, ventilation is not secured and independent verification of location not required
Page 186 of 241 Technical Reference(s): (Attach if not previously provided) 2-AOP-FH-1 Pages 7,9,11 Proposed References to be provided to applicants during examination: NONE Learning Objective: AOP032FH1-I 7304 (As available)
Question Source: Bank # INPO 24712 Modified Bank # Yes minor (Note changes or attach parent)
New Question History: Seabrook 1 5/30/2003 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (5) 55.43 (5,7)
Comments:
Minor modifications to make plant specific k-...
Page 205 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 1 101 Group # 2 WA # 000076 G2.1.28 Importance Rating 3.2 3.3 Knowledge of the purpose and function of major system components and controls Proposed Question: Common #95 SRO-only Given the following:
Unit 2 is at 100% power.
0 2-AOP-HIACT-1, "High RCS Activity," has been implemented due to an increase in RCS activity.
0 The OTC is instructed to adjust letdown flow.
WHICH ONE of the following is the required action and reason for the adjustment?
A. Decrease letdown to minimum to minimize the radioactive letdown that is flowing throughout the auxiliary building.
- 6. Increase letdown flow to maximum so that more RCS water can be diverted and processed by the waste management system.
C. Increase letdown flow to maximum so that more water can flow through the letdown ion exchangers.
D. Increase letdown flow so that a maximum amount of water can flow into the VCT to increase sparging of the radioactive gases from the top of the VCT.
Proposed Answer:
C. Increase letdown flow to maximum so that more water can flow through the letdown ion exchangers.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-H IACT- 1 Page 9 2-HIACT-1 Background Page 2 Proposed References to be provided to applicants during examination: NONE
'4.
Learning Objective: AOP031 HIA1-28981/28982 (As available)
Page 206 of 241 Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 (7) 55.43 (5)
Comments:
Page 207 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 102 Group ## 1 WA ## G2.1.33 Importance Rating 3.4 4.0 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications Proposed Question: Common #96 SRO-only Given the following plant conditions:
-Unit 2 is at 80% power.
-Bank D step counter indicates 200 steps.
Which of the following control board indications will require an entry into a Technical Specification Action Condition?
A. AFD verified outside target band for 45 minutes in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. CBD Rod H-8 position is verified at 185 steps C. 21 SG Activity verified at 0.1 Vci/gm 1-131 equivalent D. 21 SG Tube leakage verified at 0.2 gpm Proposed Answer:
D. 21 SG Tube leakage verified at 0.2 gpm Explanation (Optional):
A. TS 3.2.3 5 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is limit B. TS 3.1.4 524 steps is limit C. TS 3.7.14 50.1 5 Vci/gm 1-131 equivalent is limit D. TS 3.4.13 150 gpd is limit (0.2 gpm = 288 gpd)
Technical Reference(s): (Attach if not previously provided)
TS 3.1.4 TS 3.2.3
~~
TS 3.4.13 TS 3.7.14
Page 208 of 241 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (2,3)
Comments:
Page 227 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 112 Group # 1 WA # G2.1.6 Importance Rating 2.1 4.3 Ability to supervise and assume a management role during plant transient and upset conditions Proposed Question: Common #97 SROOnly As the Shift Manager, you have been informed by the National Weather Service, that a Hurricane Warning for the Mid Atlantic Coast of the United States has just been issued. As Shift Manager you should perform which of the following:
A. Declare a Notification of Unusual Event (NUE), commence a plant shutdown, notify NRC of forced plant shutdown B. Call in Staffing Level I1 personnel, coordinate with Consolidated Edison to remove the unit from the system C. Notify the Unit 2 OM, designate a Storm Coordinator, review the Emergency Plan to determine if emergency classification exists for conditions.
D. Monitor storm progress and take no actions until the National Weather Service issues a Hurricane Warning for the Peekskill area.
Proposed Answer:
C. Notify the Unit 2 OM, designate a Storm Coordinator, review the Emergency Plan to determine if emergency classification exists for conditions.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
OAP-008 Page 4 , 9 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New YES
Page 228 of 241 Question History:
Question Cognitive Level: Memory or Fundamental Knowledge L-Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (6)
Comments:
Page 213 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 L
105 Group # 3 WA # ~
G2.3.4
~~
Importance Rating 2.5 3.1 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized Proposed Question: Common #98 SRO-only Given the following conditions on Unit 2:
0 A LOCA outside containment occurred 0 A Site Area Emergency was declared 0 The broken line was manually isolated locally, but the operator performing the task was injured and cannot leave the area on his own 0 Initial dose estimates are 110 Whr gamma 0 The rescue time for a 2-man team is estimated to be 5 minutes with a maximum of 10 minutes Under these circumstances, the injured person:
L' A. should be moved immediately, by risk-informed volunteers, unless moving the individual is life threatening.
B. should be moved immediately, by risk-informed volunteers, unless moving the individual would cause serious medical complications.
C. should be moved, by risk-informed volunteers, as soon as Emergency Medical Technician / First Aid Responder authorizes.
D. should NOT be moved until after dose levels are reduced, by any means, to less than 10 Whr gamma.
Proposed Answer:
A. should be moved immediately, by risk-informed volunteers, unless moving the individual is life threatening.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
I P-EP-630 Page 6
Page 214 of 241 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 26167 Modified Bank # YES (Note changes or attach parent)
New Question History:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (4)
Comments:
Modified Question
Page 215 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 106 Group ## 4 WA # G2.4.27 Importance Rating 3.0 3.5 Knowledge of fire in the plant procedures Proposed Question: Common #99 SRO-only If there is a fire in the plant that cannot be brought under control in a reasonable amount of time, in accordance with SMM-DC-901, IPEC Fire Protection Program Plan, the Fire Brigade Leader should:
A. request additional fire fighting qualified plant personnel to assist in fighting the fire.
B. call the Verplanck Fire Department directly for assistance.
C. call the Buchanan Fire Department directly for assistance.
D. request the CRS notify the Verplanck Fire Department for assistance.
Proposed Answer:
D. request the CRS notify the Verplanck Fire Department for assistance.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
SMM-DC-901 Page 37 Proposed References to be provided to applicants during examination: NONE Learning Objective: (As available)
Question Source: Bank # INPO 26168 Modified Bank # YES (Note changes or attach parent)
New Question History: Prairie island 1 9/01/2003 Question Cognitive Level: Memory or Fundamental Knowledge X
~ ~ _ _
Page 216 of 241 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 (10) 55.43 (5)
Comments:
Question, Answer and Distracters modified
Page 21 1 of 241 Examination Outline Cross-reference: Level RO SRO Tier # 3 c
104 Group # 2 WA # G2.2.26 Importance Rating 2.5 3.7 Knowledge of refueling administrative requirements Proposed Question: Common #lo0 SRO-only The RCS is being drained to 63 feet for vacuurn refill following refueling. The current RCS level is 66 feet. The operable level indicators are the CCR Foxboro and the Mansell Level Monitoring System. During the draindown the hard drive on the Mansell fails resulting in a loss of indication from this instrument. What actions, if any, are required?
A. No actions required, continue with the draindown using the CCR Foxboro B. Ensure the CCR Foxboro is still tracking accurately, then continue with the draindown C. Stop the draindown and evaluate conditions. Shift Manager approval required before proceeding D. Stop the draindown and evaluate conditions. Operations Manger approval required before proceeding Proposed Answer:
D. Stop the draindown and evaluate conditions. Operations Manger approval required before proceeding Explanation (Optional):
Technical Reference(s): (Attach if not previously provided)
SOP-4.2.2 Pages 2 & 3 Proposed References to be provided to applicants durina examination: NONE Learning Objective: (As available)
Question Source: Bank # I P2 SYSl71-3 Modified Bank # (Note changes or attach parent)
Question History:
Page 212 of 241 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 (5)
Comments:
c