ML030560797
| ML030560797 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/10/2003 |
| From: | Ernstes M Division of Reactor Safety II |
| To: | Gasser J Southern Nuclear Operating Co |
| References | |
| 50-424/02-301, 50-425/02-301, ES-401-4 50-424/02-301, 50-425/02-301 | |
| Download: ML030560797 (113) | |
Text
Draft Submittal (Pink Paper)
- i. Reactor Operator Written Exam q- c 7 J-/AP) Sc-Z5 VOGTLE EXAM 2002-301 50-424 AND 50-425 NOVEMBER 26, &
DECEMBER 2 - 13, 2002
ES-401 PWR RO Examination Outline
- r*fi L-4'1-4 Facility: Vogtle Date of Exam: Exam Level: RO K/A Category Points Tier Group Point K K2 K3 K4 K5 K6 Al A2 A3 A4 G Total
- 1. 1 2 4 ,WN M 0 15 M 2 16 16 Emergency & 3 7 1 Abnormal 2 4 3 1 M M ! 1111, 5 1 M 3 17 17 PlantPat3 1 0 1 1 01* 0 033 3 3 Evolutions Tier 7 6 6 6 6 5 36 36 Totals 1 3 1 2 3 3 3 2 2 0 2 2 23 23 2.
Plant 2 3 1 3 1 1 1 3 1 2 2 2 20 20 Systems 3 1 1 1 1 1 0 0 1 1 0 1 8 8 Tier 7 3 6 5 5 4 5 4 3 4 46 51 51 Totals
- 3. Generic Knowledge and Abilities Cat 1 = Cat 2 Cat 3 Cat 4 13 13 3 1 3 3 4 F Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
6.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000005 Inoperable/Stuck Control Rod / 1 1 AK2.02 Knowledge of interrelationship between stuck rods and breakers, relays, 2.5/2.6 R disconnects, and control room switches (CFR 41.7, 45.7) 000015/17 RCP Malfunctions/4 1 AK1.02 - Consequences of an RCPS failure(CFR 41.8 / 41.10/45.3) 3.7/4.1 B BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 1 EA2.2 - Adherence to appropriate procedures and operation within the 3.4/3.8 B limitations in the facility s license and amendments. (CFR: 43.5 / 45.13) 000024 Emergency Boration / 1 1 AK2.01 - Valves - (CFR 41.7 / 45.7) 2.7/2.7 B 000026 Loss of Component Cooling Water / 8 1 AK3.01 - Knowledge of the reasons for the following responses as they 3.2/3.5 B apply to the Loss of CCW: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS collers (CFR 41.5,4t.10 / 45.6 / 45.13) 000027 Pressurizer Pressure Control System 1 AK3.03 - Actions contained in EOP for PZR PCS malfunction (CFR 3.7/4.1 B Malfunction / 3 41.5,41.10 / 45.6 / 45.13) 000040 (BW/E05; CE/E05' W/E12) Steam Line 1 AG2.4.4 Abilit to recognize abnormal indications for system operating 4.0/4.3 B Rupture - Excessive Heat transfer / 4 parameters 45.6 are entry level conditions for EOPs and AO Ps (CFR 41.10,43.2, which CE/Al1; W/E08 RCS Overcooling - PTS / 4 1 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
3.4/4.2 R (CFR: 43.5/45.13) 000051 Loss of Condenser Vacuum / 4 1 AA2.02 - Conditions requiring reactor and/or turbine trip (CFR: 43.5 / 45.13) 3.9/4.1 R 000055 Station Blackout / 6 1 EK3.02 - Actions contained in EOP for loss of offsite and onsite power (CFR 4.3/4.6 B 41.5 / 41.10 / 45.6 / 45.13) 000057 Loss of Vital AC Elec. Inst. Bus / 6 1 AA2.18 - Ability to determine and interpret the following as they apply to the 3.1/3.1 R Loss of Vital AC Instrument Bus: The indicator valve breaker, or amper position which will occur on a loss of power (CFR: 43.5 / 45.13) 000062 Loss of Nuclear Service Water / 4 1 AG2.4.24 - Knowledge of loss of cooling water procedures. (CFR: 41.10/ 3.3/3.7 B 45.13) 000067 Plant Fire On-site / 9 1 AK1.02 - Fire fighting (CFR 41.8 / 41.10/45.3) 3.1/3.9 B 000068 (BW/A06) Control Room Evac. / 8 1 AK3.18 - Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation: Actions contained in EOP for control 4.2/4.5 B room evacuation emergency task. (CFR 41.5,41.10 / 45.6 / 45.13) 000069 (W/E1 4) Loss of CTMT Integrity / 5 1 AK2.03 - Personnel access hatch and emergency access hatch (CFR 41.7 / 2.8/2.9 B 45.7) 000074 (W/E06&E07) Inad. Core Cooling / 4 1 EA2.2 - Ability to determine and interpret the following as they apply to the 3.3/3.9 R (Saturated Core Cooling) Adherence to appropriate procedures and operations within the limitations in the facility's license and amendments.
I__ I(CFR 43.5 / 45.13)
BW/EO3 Inadequate Subcooling Margin / 4 1 1 000076 Hi ro Reactor Coolant Activity / 9 I (3/4 (
ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE #/Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points BW/A02&AO3 Loss of NNI-XY /77 KIACateory Totals: 2 3 4 0 5 2 Grou Point Total: 16 16 6' ((
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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function Ki K2 K3 Al A2 G K/A Topic(s) Imp. Points 000001 Continuous Rod Withdrawal / 1 1 AK1.05 - Knowledge of the operational im ljcations of the following 3.5/3.8 B concepts as they apply to Continuos Rod Withdrawal: Effects of turbine reactor power mismatch on rod control (CFR:41.8/41.10/45.3) 000003 Dropped Control Rod / 1 1 G2.4.49 - Ability to perform without reference to procedures those actions 4.0/4.0 B that require immediate operation of system components and controls.
(CFR: 41.10/43.2/45.
000007 (BW/E02&E1 0; CE/E02) Reactor Tnp Stabilization - Recovery / 1 8W/AOl Plant Runback / 1 BW/A04 Turbine Trip /4 000008 Pressurizer Vapor Space Accident / 3 1 AKI.01 - Knowledge of the oNerational implications of the following 3.2/3.7 B concepts as they applyato a Peressunzer Vapor Space Accident:
Thermodynamics 41.8 / 41.10 / 45.3)and flow characteristics of open or leaking valves (CFR 000009 Small Break LOCA / 3 1 EA2.39 - Abilit to determine or interpret the following as they apply to a 4.3/4.7 R small break LOCA: Adequate cooling. (CFR 43.5 / 45.13) 000011 Large Break LOCA / 3 1 EK2.02 Knowledge of the inter-relationship LB LOCA and pumps 2.6/2.7 B W/E04 LOCA Outside Containment 3 BW/E08; W/E03 LOCA Cooldown/Depress. / 4 1 EK2.2 - Facility's heat removal systems, including primary coolant, 3.7/4.0 B egegy coolan t, the decay heat removal systems, and relations nbetween tnproper operation of these systems to the operation of the facility. (CFR: 41.7 145.7)
W/E1 1 Loss of Emergency Coolant Recirc. / 4 1 EA1.3 - Desired operating results during abnormal and emergency 3.7/4.2 B situations.__CFR:_41.7/ 5.5 / 45.6)
W/EO1 & E02 Rediagnosis &SI Termination / 1 EK1.2 - Normal, abnormal and emergency operating procedures 3.4/4.0 R associated with (Reactor Trip or Safey Injection / ediagnosis). (CFR:
45.3) 41.8 /41.10/
000022 Loss of Reactor Coolant Makeup / 2 1 AG2.1.32 - Abili to/e l]ain and apply all system limits and precautions. 3.4/3.8 B (CFR: 41.10143.2145.12) 000025 Loss of RHR System / 4 1 AK2.02 - LPI or Decay Heat Removal/RHR pumps (CFR 41.7 / 45.7) 3.2/3.2 B 000029 Anticipated Transient w/o Scram / 11 EAI.13 - Manual trip of main turbine (41.8/41.10/45.3) 4.1/3.9 B 000032 Loss of Source Range NI / 7 1 AK1.01 - Effects of voltage changes on performance (CFR 41.8 / 41.10/ 2.5/3.1 B 45.3) 000033 Loss of Intermediate Range NI / 7 000037 Steam Generator Tube Leak / 3 1 AK3.07 - Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: Actions contained in EOP for 4.2/4.4 B S/G lube leak (CFR 41.5, 41.10/45.6/45.13) 000038 Steam Generator Tube Rupture / 3 000054 (CE/E06) Loss of Main Feedwater / 4 1 EG2.4.48 - Ability to interpret control room indications to verify the status 3.5/3.8 B and operation of system and understand how operator actions and directives affect plant and system conditions. (CFR: 43.5 / 45.12)
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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points BW/E04; W/E05 Inadequate Heat Transfer - Loss 1 EA1.3 - Desired operating results during abnormal and emergency 3.8/4.2 B of Secondary Heat Sink / 4 situations. (CFR: 41.7/45.5 / 45.6) 000058 Loss of DC Power /6 000059 Accidental Liquid Radwaste Rel. / 9 AA1.01 - Radioactive-liquid monitor (CFR 41.7 / 45.5 / 45.6) 3.5/3.5 B 000060 Accidental Gaseous Radwaste Re[. / 9 000061 ARM System Alarms / 7 1 AA1.01 - Ability to operate and / or monitor the following as they apply to 3.6/3.6 R the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation (CFR 41.7 / 45.5 / 45.6)
W/E1 6 High Containment Radiation / 9 CE.E09 Functional Recovery K/A Category Point Totals: 14 I3 I I I5 I Group Point Total: 17 I 17
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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000028 Pressurizer Level Malfunction / 2 000036 (BW/A08) Fuel Handling Accident / 8 000056 Loss of Off-site Power / 61 AK1.01 - Principle of cooling by natural convection CFR 41.8 / 41.10 / 45.3) 3.7/4.2 R 000065 Loss of Instrument Air / 8 1 AAl.03 - Restoration of systems served by instrument air when pressure is 2.9/3.1 5 regained (CFR 41.7 /45.5/45.6)
BW/E13&E14 EOP Rules and Enclosures BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 CEAl 6 Excess RCS Leakage / 2 W/E13 Steam Generator Over-pressure / 4 1 EK3.2 - Normal, abnormal and emergency operating proedures associated 2.9/3.3 R with Steam Generator Over pressure). ( 1F 141.10, 45.6, 45.13)
- 41.5 W/E15 Containment Flooding / 5 K/A Category Point Totals: It 10 I1 [t Io Io IGroup Point Total: 3I
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ES-401 PWR RO Examination Outline Form ES-401-4
______________________________ Plant Systems -Tier 2Group 1 _______________
System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 001 Control Rod Drive 1 and/or Knowledqe K1.05 cause-effectof relationship connections the physicalbetween the 4.5/4.4 B CRDS and the followin systems: NIS and RPS (CFR 41.2 to 41.9/ .7 to 45.8) 003 Reactor Coolant Pump A2.02 Conditions which exist for an abnormal 3.7/3.9 R shutdown of an RCP in comparison to a normal shutdown of an RCP (CFR: 41.5/
43.5/ 45.3 / 45/13) 004 Chemical and Volume Control 1 K4.04 Knowledge of CVCS design features 3.2/3.1 R and interlocks that provide for manual/automatic transfers of controls (CFR 41.7) 004 Chemical and Volume Control 1 K6.04 Knowledge of the operational 2.8/3.2 R implications of the following concepts as they apply to the CVCS: Reason for hydrogen cover gas in VCT (oxygen scavenge) (CFR:
41.5/ 45.7) 004 Chemical and Volume Control 1 A2.12 Ability to (a) predict the impacts of the 4.1/4.3 B following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedure to correct, control, or mitigate the consequences of those malfunctions or 4g.3 / 45.5) CIAS, SIAS (CFR: 41.5 / 43.5/
operations:
004 Chemical and Volume Control 1 A4.07Ability to manually operate and/or 3.9/3.7 B monitor in te control room: Boration/dilution.
(CFR: 41.7 / 45.5 to 45.8) 013 Engineered Safety Features Actuation 1 K6.01 on theofsensors Knowledie malfunction the effect a loss orwill andofdetectors 2.7/3.1 R have on the ESFAS (CFR 41.7, 45.5 to 8) _
013 Engineered Safety Features Actuation 1 K2.01 ESFAS/safeguards equipment control 3.6/3.8 B (CFR: 41.7) 015 Nuclear Instrumentation 1 G2.2.12 Knowledge of surveillance 3.0/3.4 R procedures (CFR 41.10, 45.13) 015 Nuclear Instrumentation 1 K4.06 Reactor trip bypasses (CFR: 41.7) 3.9/4.2 B 015 Nuclear Instrumentation 1 K5.04 Knowledge of the operational 2.6/3.1 B implication of the following concepts as they apply to the NIS: Factors affecting accuracy and reliability of calorimetric calibrations.
(CFR: 41.5 45.7) 017 In-core Temperature Monitor K3.01 Natural circulation indications 3.5/3.7 B (CFR: 41.7 / 45.6) 022 Containment Cooling 025 Ice Condenser I
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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # /Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 025 Ice Condenser 056 Condensate 1 K1.03 - MFW (1FR: 41.2 to 41.9 / 45.7 to 2.6/2.6 B 45.8) 059 Main Feedwater 1 K6.09 Effect of loss of MFW pump and flow 2.4/2.6 B regulating valves 059 Main Feedwater 1 K4.19 Knowledge of MFW design Features 3.2/3.4 R and / or interlocks that provide for automatic feedwater isolation of MFW (CFR 41.7) 059 Main Feedwater
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I A4.1 1 - Recovery from automatic feedwater isolation (CFR: 41.7 / 45.5 to 45.8) 3.1/3.3 B 061 Auxiliary/Emergency Feedwater 1 K5.01 Knowledge of the operational 3.6/3.9 R implications of te relationship between AFW flow and RCS heat transfer (41.5, 45.7) 061 Auxiliary/Emergency Feedwater I A1.04 - Ability to predict and/or monitor 3.9/3.9 B changes in parameters (to prevent exceeding design limits) associated with operating the AM controls including: AFW source tank level. (CFR: 41.5/45.5) 068 Liquid Radwaste 1 K1.07- Sources of liquid wastes for LRS 2.7/2.9 B (CFR: 41.2 to 41.9 / 45.7 to 45.8) 068 Liquid Radwaste 1 K6.10 Knowledge of the effect of a loss or 2.5/2.9 R malfunction on the following will have on the Liquid Radwaste System: Hadiation monitors.
(CFR: 41.7 / 45.7) 071 Waste Gas Disposal K3.05 Knowledge of the effect that a loss of 3.2/3.2 B the waste gas disposal will have on ARM and PRM (CFI*41.7, 45.6) 072 Area Radiation Monitoring 1 A1.01 Predict/monitor levels to changes prevent exceeding in radiation design limits 3.4/3.6 B (CFR 41.5, 45.5) 1 072 Area Radiation Monitoring 1 G2.1.28 Knowledge of the purpose and 3.2/3.3 B function of major system components and controls. (CFR41.7) 31112 813 1813 2 12 Io 2 2 Groupont-ta,: 23 1 1 213
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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 002 Reactor Coolant K5.10 Operational implications of relationship between reactor power and RCS differential 3.6/4.1 B temperature (CFR 41.5, 45.7) 006 Emergency Core Cooling 1 K1.07 Know!ledge of the physical connections 2.9/3.3 B and/or cause-effect relationship between the ECCS and the followingsystems: MFW system.
(CFR 41.2 to 41.9 / 45.7 to 45.8) 006 Emergency Core Cooling A1.11I Ability to predict and/or monitor changes 3.1/3.4 B in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Boron concentration. (CFR 41.5/45.5) 010 Pressurizer Pressure Control 1 K3.01 RPS (CFR Knowledge of the loss of PZR PCS on 41.7, 45.6) 3.8/3.9 B 011 Pressurizer Level Control 1 A3.03 Ability to monitor automatic operation of 3.2/3.3 B PZR LCS including: Charging and letdown (CFR 41.7/45.5) 012 Reactor Protection 1 K6.1 0 Effect of loss of permissive circuits on 3.3/3.5 B RPS (CFR 41.7, 45.5) 014 Rod Position Indication 1 A4.01 Rod selection control (CFR: 41.7 / 45.5 3.3/3.1 B to 45.8) 016 Non-nuclear Instrumentation 1 K3.02 Knowledge of the effect that a loss or malfunction of the NNIS has on PZR LCS 3.4/3.5 R 026 Containment Spray 1 A1.01 - Ability to predict and/or monitor changes 3.9/4.2 B in parameters (to prevent exceeding design limits) associated with operating the C0S controls including: Containment pressure (CFR:
41.5/45.5) 029-Containment Purge I K1.02 Knowledge of the physical connections and/or cause-efect relationship between the 3.6/3.8 R Containment Purge System and the following systems: Containment radiation monitor 033 Spent Fuel Pool Cooling 1 G2.4.18 Knowiedge of the specific bases for 2.7/3.6 R EOPs (CFR 41.10/45.13) 035 Steam Generator 1 K1.09 Cause / effect between S/G and RCS 3.8/4.0 B (CFR 41.2 - 9, 45.7 - 8) 039 Main and Reheat Steam 1 A1.03 Ability to predict and/or monitor changes 2.6/2.7 B in parameters (to prevent exceeding design limits) associated with operating the MRS controls including: Primary system temperature indications, and required valves, during main steam system warm-up. (CFR 41.5 / 45.5) 055 Condenser Air Removal 1 K3.01 Knowledge of the effect that a loss or 2.5/2.7 R malfunction of the CARS will have on the following: Main condenser. (CFR 41.7 / 45.6)
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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System # /Name K1 K2 K3 K4 K5 K6 Al A2 AS A4 G K/A Topic(s) Imp. Points 062 AC Electrical Distribution 1 A3.05 Ability to monitor automatic operation of 3.5/3.6 B the ac distribution system, including: Safety related indicators and controls. (4 [.7 / 45.5) 063 DC Electrical Distribution 064 Emergency Diesel Generator I K2.03 Knowledge control power power supplies (CFR41.7) 3.6/3.9 B 073 Process Radiation Monitoring 1 A2.01 Ability to (a) predict the impacts of the 2.5/2.9 R following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedure to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply. (CFR:
41.5 / 43.5/45.3 / 45.13) 075 Circulating Water 1 A4.01 Abilityto operate/monitor 45.5 -8) I emergency 3.2/3.2 B essential SwS pumps (CFR41.7, 079 Station Air K4.01 Knowledge of SAS design feature and 2.9/3.2 B cross-connection with IAS (CFR41.7) 086 Fire Protection 1 G2.4.25 Knowlede of fire protection procedures ps) 20 2.9/3.4 Io2B 0 4 1 .10 / 4 5 .1T ot IA CategoryPointTotals: 13 It 13 I1 It It 13 1 12 12 12 IGroup Point Total:
K / AFR 120 II20 K
ES-401 PWR RO Examination Outline Form ES-401-4 ES-401 _Plant Systems - Tier 2/Group 3 System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 005 Residual Heat Removal 1 K5.03 Operational effects of reactivity 2.9/3.1 R effects of RHR fill water (CFR41 .5, 45.7) 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water K1.02 Knowledge of the physical 3.3/3.4 R connections an (orcause-effect relationship between the COWS and the followingsstems: Loads cooled by CCWS.
(CFR: 41.2tol1.9 / 45.7 to 45.9) 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 034 Fuel Handling Equipment provideDesign K4.01 features and fue rprotection from interlocks which binding and 2.6/3.4 B dropping (CFR41.7) 041 Steam Dump/Turbine Bypass Control K3.04 Effect of a malfunction of the SDS has on reactor power (CFR41.7, 45.6) 3.5/3.4 B 045 Main Turbine Generator A3.05 Ability to monitor auto operation of 2.6/2.9 B the MT/G system, including:
Electrohydraulic control. (CFR 41.7 / 45.5) 076 Service Water K2.08 Power supplies to ESF-actuated 3.1/3.3 B MOV (CFR 41.7) 078 Instrument Air 1 G2.4.11 Knowledge of abnormal conditions 3.4/3.6 R procedures (CPA 41.10, 43.5,_45.13) 103 Containment 1 A2.03 Predict impact and use procedures 3.5/3.8 R to address malfunction of phase A and B isolation (CFR 41.5, 43.5, 45.3, 45.13)
K/A Catecory Point Totals: J1J1LI ii I o o I I0 1I0 I11 Group Point Total: _____I 8 Plant-Specific Priorities System /Topic Recommended Replacement for... Reason Points Plant-Specific Priority Total: (limit 10) !
Facility: Date of Exam: Exam Level: RO Category K/A # Topic Imp. Points 2.1.3 Knowledge of shift turnover practices 3.0/3.4 B 2.1.2 Knowledge of operator responsibility during all modes of 3.0/4.0 B Conduct of operation Operations 2.1.32 Ability to explain and apply all system limits and precautions 3.4/3.8 B 2.1.
2.1.
Total 3 2.2.3 Knowledge of the design, procedural and operational differences 3.1/3.3 B between Units Equipment Control 2.2.12 Knowledge of surveillance procedures 3.0/3.4 B 2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4/4.1 B Total 3 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control 2.6/3.0 B requirements 2.3.4 Knowledge of radiation exposure limits and contamination control 2.5/3.1 B Radiation Control _ including permissible levels in excess of those authorized 2.3.9 Knowledge of the process for performing a containment purge 2.5/3.4 B Total 3 2.4.1 Knowledge of EOP entry conditions and immediate action steps 4.3/4.6 B Emergency 2.4.14 Knowledge of general guidelines for EOP flowchart use 3.0/3.9 B Procedures/ Plan 2.4.8 Knowledge of how the event-based emergency/abnormal 3.0/3.7 B operating procedures are used in conjunction with the symptom based EOPs 2.4.11 Knowledge of abnormal condition procedures 3.4/3.6 B Total 4 Tier 3 Point Total 13 RO 1 12
REPORT QUESTIONS for VOGTLEFINDRFT1028
- 1. 00IAK1.05 001 The following conditions exist:
- Reactor power = 100 25%
- Control Bank D is at 137 steps withdrawn
- Rod control is in AUTO If PT-505 fails LOW, how will the rods in Control Bank D respond?
A. Move inward at 48 steps per minute.
Bf Move inward at 72 steps per minute.
C. Move outward at 72 steps per minute.
D. Move outward at 48 steps per minute.
REF: VG LP-271 01 C-5 Rod Control distracter A - 48 SPM is the speed for manual operation of control banks and wrong direction.
Distracter B - inward movement is a misapplication of PT-485 failing high.
Answer C - correct maximum speed of 72 SPM in the outward direction Distracter D - 48 SPM is the speed for manual operation of control banks.
Changed Power to 22% as requested from Utility to get further above C-5 auto-rod interlock.
Made 4th item match MCB nomencalture.
Removed "for input to the rod control system" to avoid "teaching" in the stem.
..... *..or0 n'.na.&o M 1 I uesday, Femary ,
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 2. 001K1.05 001 Given the following:
- 75% power
- Channel N-41 - 740-80
- Channel N-42 - 730/o.75
- Channel N-43 - 75/-2
- Channel N-44 - 74%.50
- Rod control is in Automatic Which of the following describes Rod Control system response to channel N-41 failing LOW low?
A. Control Rods drive in at a maximum rate until C-5 blocks rod motion or a reactor trip on low PRZR press occurs.
B. Control Rods drive in until the temperature mismatch equals the power mismatch and Tavg stabilizes at a lower temperature.
C: Control Rods remain in present position until pewor mismatch caucoc a cignal to meve-*Tave is 1.5 degrees F above Tref.
D. Control Rods drive out until the temperature mismatch equals the power mismatch and Tavg stabilizes at a lower temperature.
New, REF: LO-LP-27101-21
- a. incorrect - auctioneered hi is used in the rod circuitry, and N-43 is the hi not N-41
- b. incorrect - auctioneered hi is used in the rod circuitry, and N-43 is the hi not N-41
- c. correct - auctioneered hi is used in the rod circuitry, and N-43 is the hi not N-41
- d. incorrect - auctioneered hi is used in the rod circuitry, and N-43 is the hi not N-41 Tuesday, February 25, 2003 07:06:39 AM 2
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 3. 002K5.10 001 Given the following conditions:
- Tavg is on program
- Unit 1 is at 94% power and ramping up.
- Rods are in automatic with Bank D at 200 steps
- Turbine load set is raised to 1220 MWe using the increase pushbutton
- Turbine control valves are opening and megawatts are increasing Which ONE of the following describes Tavg behavior assuming no operator action?
A. Tavg and Tref will increase and continue to be matched until the ontrol valves roach tho I.miter.settinturbine reaches set load.
B. Tref will increase until the centrnl-valves turbine reaches set load the lim.iter *cting, but Tavg will remain constant.
C. Tavg and Tref will remain constant and matched as the turbine load increases. ,entral lvec
.. roach the limiter coiling.
D." Ta'g will initially incroace, but then docroaco as the control valves roach the limiter Getting.
Until the turbine reachec cot load.
Tavg will decrease and Tref will increase until the turbine reaches set load.
Ref: VG LO-LP-28103 - C Distactor analysis:
D is correct because Bank D hits the C11 rod stop at 220 steps. As the governor valves continue to open, turbine power continues to rise along with Pimp (Tref). However, no more positive reactivity is added (no dilution per stem) and no rods due to C11, but doppler adds negative reactivity which drives Tavg down until Moderator temp coefficient balances at a lower Tavg.
A, B,and C are incorrect they have Tavg either rising or remaining constant.
_ . , .. *, ,, a.o.a *.' A Iuesday, February 25, uu03 u0:uo6ou Nvi 3
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 4. 003A2.02R 001 Given the following:
- Unit 1 is at 39% power
- Annun-cator ALB30 A05 "RCP 1 CONTROLLED LKG HI/LO FLOW" alarms PanelA2 window A 4, RCP 1 No. 2 SEAL LKOF= HI FLOW islit
- RCP 1 Seal Wnet injection temperature is at 240'F and increasing.
Which ONE of the following describes the correct actions for the control room crew?
A. Trip-the RCP 1, close #1 Seal Return F-GV valve, trip the Rx and initiate 19000-C, "E-0, Rx Trip or Safety Injection" B! Trip the Rx and initiate 19000-C, "E&-, Rx Trip or Safety Injection," trip RCP 1, and close #1 Seal Return F-GV valve C. Trip the RCP 1, close #1 Seal Return FCV valve and continue in 12004-C, "Power Operation (MODE 1)"
D. Trip the RCP 1, close #1 Seal Return F-QV valve and initiate 18005-C, "Partial Loss of Flow" Ref: VG 13003-1, 18005-C, 17008-1 Distractor analysis:
A is incorrect because actions are in wrong order B is correct per procedures for RCPs 1 - 3 C is incorrect based procedures D is incorrect because power is less than P-8, 48% but greater than 15% so should trip RX per procedure Tuesday, February 25, 2003 07:06:39 AM 4
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 5. 003G2.4.49 001 At 11:00 you are notified that RCP #1 OGS ACCW inlet line is leaking badly. Maintenance was notified and is in the process of determining what type of repairs are needed. At 11:05 via plant computer and other control room indications, you determine that the following conditions exist:
- Motor bearing temperature is 195 F and rising at 1 F / min
- Motor stator winding temperature is 315 F and steady
- Seal water Inlet temperature is 240 F and steady Based on the above conditions, what action(s) should be taken?
A. Immediately trip the RCP B. Trip the RCP if seal*injeetien ACCW to the pump is not re-established by 11:16 with total
- 1 seal flow is-greater than 5 gpm C. Trip the RCP if sea!InjOGtiOn ACCW flow is not re-established by 11:10 D. Trip the RCP, then the reactor if seal water temperature is not returned to 2350 F by 11:16 Ref: VG LO-LP-16401, 13003-1
- AlA5 . - .
Tuesday, February 25, zuu2 u07u:639 AMw
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 6. 004A2.12 001 Given the following:
- Unit 2 is at 100% power
- CCP "A"is in service, providing normal charging flow
- An inadvertent "B"train SI was generated by I&C
- "A"train SI "A"train is net NOT present
- No operator action takes place Which of the following is correct?
A. Normal mini-flow paths for both CCPs are isolated, alternate flow-paths for both CCPs are available.
B. Normal mini-flow paths for both CCPs are isolated, CCP "A"alternate minif low path is isolated, CCP "B"alternate mini-flow path is available.
C. CCP "A"normal mini-flow path is available, CCP "A"alternate minif low path is isolated, CCP "B"alternate mini-flow path is available.
D. Normal mini-flow paths for both CCPs are isolated, alternate flow-paths for both CCPs are isolated.
Ref : VG bank, LO-LP-09201-01-05 A. incorrect - train A Isolation occurred B. correct C. incorrect - train A valves closed D. incorrect - train B valves unaffected 6
Tuesday, February 2b, 2UU3 u0:u06:39 AMv
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 7. 004A4.07 001 Which of the following describes the proper reactor makeup control system valve positions after the roaGte Makeup Maste Control Switch is placed to the START position with the ReaoteeMakeup Mode selector switch in DILUTE?
AK Blolndor Acid Supply Flow Control Valvo CLOSED Makoup to CCP Suction Flow Control Valvo CLOSED DI:KM P
,,r uoric~~~ u;.X/
Hi,vGiv +9 Lve , ,,,,'
KIM * . ~~
ew ýci +inu ...
G F n ..
Blondor Primary Water Flow Control Valve MODULIATED Boric Acid to Blender Valve (FV-01 1OA) - CLOSED Blender Outlet to Charging Pumps Suction Valve (FV-01 lOB)- CLOSED Blender Outlet to VCT Valve (FV-01 11 B)- OPEN RX MU WTR to BA Blender Valve (FV-01 11A)- MODULATED B. Blondor Acid Supply FlowControl valve CLOSED Makeup to CCP Suction Flow Control Valvo OPEN Boric Acid Blondor to VCT Inlot Flow Control alo, MODULATrED BlodorPriaryWator Flcw Control V'alve CLOSED Boric Acid to Blender Valve (FV-01 1OA) - CLOSED Blender Outlet to Charging Pumps Suction Valve (FV-0110B)- OPEN Blender Outlet to VCT Valve (FV-01 11 B)- MODULATED RX MU WTR to BA Blender Valve (FV-01 1IA)- CLOSED C. Blonder Acid Supply Flow Control valvo , OEN Makeup to CCP Suction Flow Control Valvo OPEN Boric-AcdR Bond*or t VCT" inlet Flow Control Valvo CLOSED Blondor Primary Water Flow Control Valvo MODULATED Boric Acid to Blender Valve (FV-01 10A) - OPEN Blender Outlet to Charging Pumps Suction Valve (FV-01 10B)- OPEN Blender Outlet to VCT Valve (FV-01 11 B)- CLOSED RX MU WTR to BA Blender Valve (FV-01 11A)- MODULATED D. Blondor Acid Supply Flow Control valve MODULATED Makeup to CCP Suction Flew Control Valvo" MO.DU L,.A.TED Boric AcAid Blondor to VCT Inlot Flowv Control Valvo OPE;N B-londoer_ Primary Wator FlwF Control VAlvo OPEN Boric Acid to Blender Valve (FV-0110A) - MODULATED Blender Outlet to Charging Pumps Suction Valve (FV-01 1OB)- MODULATED Blender Outlet to VCT Valve (FV-01 11 B)- OPEN RX MU WTR to BA Blender Valve (FV-01 11A)- OPEN Ref: Farley Exam Bank, verified for Vogtle, LP 09401
- a. correct dilute flowpath b., c, d, incorrect flowpaths see drawing
-- - - On nnQ~.ff.f uoU ARA Iusaruur 7 T uesday, F-ebruary 25o, 4003 0,uv;o~o ~~
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 8. 004K4.04 001 NOT VALI-1 DATED FOR OGLca't idlgic drawings for VGT makeup valves VG LP 09401 talks about switch contrl*
ASK Dan Unit 1 is rocovcring from a Main Control Roomn evacuation in accordanoo with A0l 27, Main COntrol- Room Inant cacoibity and gCntrol has boon formally transferred from the Auxiliar; Control Room The UO attemptod to porfarm a blended makeup to thoVCT whon arnnciatOr 112 E, PW to Blender FlowDv iainlrmd Wheic ONE of the follawing doscribesthe cause of the alarm?
Unit 1 is recovering from a remote shutdown outside the control room. The Auxiliary Building SO is currently locally controllingcVoS charging flow using 1FHC-0121 outside the charging pump rooms.
Which of the following is the correct method of transfering charging flow control back to the control room?
A. Trancfor switch for Primary' Water Pumps loft in Aux position Place both the local (FHC-0121) and control room (FIC-0121) controllers at 0%demand, then place the charging pump transfer switch in the control room position.
BA Trsfenrr switch for FesV 62 143, Blende Primar; Water FlowiCntrol Valve loft in Aux Match the control room demand (on siC-0121) with the local controller (FHC-0121), then place transfer switch in the control room position.
C. Transfor switch for VOT- LEVEL= XMTR 41 LCV 62-118 left in Aux position Place the local controller in 'REMOTE", the control room demand automatically tracks the local demand.
D. Transfor switch for FCV 62 1114, Makoup to CCP Suction Flow Control Valvo loft in Aux Place the control room controller (FIC-Ol 21) in "AUTO", no local action is required.
Ref: WB procedure AOI-27 No learning objective found Distracter analysis:
A is incorrect, switch does not exist B is correct, in Aux position at the Auxiliary Control Room, FCV-143 remains closed regardless of activities on the Main Control Board C is incorrect because level is not an input when performing a manual makeup o isincorrect because this switch does not exist 8
I uesday, Feuruary or , On""' 0:06:39 AM~
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 9. 004K5.04 001 Which one of the following is a result of maintaining a hydrogen cover gas in the VCT during normal at power operations?
A. To assure N-1 6 concentrations are ALARA B. To maintain RCS pH within T-RM limits C. To maintain conductivity below .017 micro Mhos D. To maintain oxygen concentration bolow the TRM uppor limit within limits Ref: NA 2002 - validated to VG LO-LP-09001-10 and TRM 13.4.1 Chemistry
- b. incorrect RCS pH is controlled by primary chemistry not with cover gases
- c. incorrect conductivity is controlled by water quality efforts not cover gases
Tuesday, February 2b, 2UU3 u0:u0:39 AM
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 10. 005AK2.02R 001 Unit 1 was at 25% power and ramping up when the RO noticed that one of the Control Bank C control rods is 13 steps below the other rods in Control Bank C which were at 215 steps and moving as designed.
Power accension was halted. The rod had an electrical problem which was repaired and the operations management staff has concurred with realignment of the misaligned rod in accordance with 18003-C, Rod Control System Malfunction. Toch Spoc reouiremonts havo been met.
Which ONE of the following outlines the method of realigment in accordance with AOP 18003-C?
A. Record information from Bank Overlap Unit, step counters, and P/A converter. Disconnect lift coil for the affected rod, reset step counters, select Bank C and insert Bank C control rods. Log the final rod position.
B. Reset Master Cycler, record information from Bank Overlap Unit, step counters, and P/A converter. Disconnect lift coil of the affected rod, select Bank C and insert Bank C. Log final position of affected rod.
Cf Position Rod Bank Selector Switch to affected bank, roset tho aff.ctod group stop-. untr*
te-zero, disconnect all lift coils in Bank C except the affected rod, and withdraw affected control rod, reset the affected group step counter to recorded position. Log the final rod position.
D. Reset master cycler, record information for P/A converter, and step counters. Disconnect all lift coils in Bank C except the affected rod, select Bank C and withdraw the affected rod.
Ref: VG AOP 18003-C Distractor analysis:
A is incorrect the procedure for aligning a rod NOT in the controlling bank is to move the rod to the bank, not the bank to the rod.
B is incorrect same as A, also missing some steps.
C is correct per 18003-c D is incorrect because information from BOU and P/A converter do not have to be recorded prior to realignment.
- . . ,...',.,.,anflfA~d10 Iuesday, F-eDruary 25, zuu2 u0:uoo 0,lVI
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 11. 005K5.03R 001 Unit 1 is in Mode 4 with #1 Reactor Coolant Pump running. "A"train RHR has JUST been placed in service when the Reactor Operator notes source range counts suddenly increasing on both channels. ALB10 C01 "SOURCE RANGE HI FLUX LEVEL AT SHUTDOWN" alarms.
Which ONE of the following describes the correct action?
A. Commence a maximum an emergency boration per 13009-1, CVCS Reactor Makeup Control System.
B. Start the #2 Reactor Coolant Pump and secure the #1 Reactor Coolant Pump.
C. Start "B"Train RHR and secure "A"train RHR.
D. Commence a normal boration until the source range counts begin to decrease.
Ref: TP Exam Bank, no specific learning objective found Need to verify per UOP Distractor Analysis:
A is correct because operating procedure 13009-1 provides guidance to immediatly borate when uncontrolled +reativity is inserted.
B is incorrect because swapping RCP's will not add negative reactivity to the core.
C is incorrect same as answer B.
D is incorrect because there is no guidance for a normal boration.
-* . -..... ,,aaan,.flo.flf ^ 11 I uesday, February 25, 20 u :uo0o0 Xlw
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 12. 006A1.11 001 Given the following plant conditions:
- 19031, "ES-,3.1, Post-SGTR Cooldown Using Backfill", is in progress.
- Ruptured SG level is 25% NR.
RCS5 is a-t 390'F.
ROS is at 400 pasig-.
Crew is cooling down using steam dumps to condenser.
RCP #4 in service.
19031, Post-SGTR Cooldown Using Backfill" 0
- Step 14 requires a return to step 3 if RCS temperature is greater than 200 F.
- Step 3 requires the operator to ensure adequate shutdown margin.
ES 3.1, stop 114roquirs a return to stop 3 if P,9 tomporaturo i groator than 200 0 F.- Stop 3r oquiroc the oporator to ensuro adoquate shutdown margin.
Why is it necessary to re-verify shutdown margin at this point in the procedure?
A. The RCS temperature change during cooldown will cause significant boron concentration changes due to PZR outsurge.
B. Charging to maintain PZR level during cooldown will cause significant boron concentration changes.
Cf The secondary fluid in the ruptured SG will cause significant ber*n Gconcntration chango*s*.
dilution of the RCS.
D. The auxiliary spray will cause significant boron concentration changes.
Ref: WB bank, VG 19031
- a. incorrect - cooldown does not effect the boron concentration
- b. incorrect - charging should be set for the desired boron concentration
- c. correct - this guidance results in the S/G backfeeding into the RCS with the nonborated feedwater
- d. incorrect - spray should be causing increased boron concentration which will increase the shutdown margin 12 Tuesday, February 25, 2UU3 u0:u0*:9i AM
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 13. 006K1.07 001 Given the following sequence of events ,endlftiees:
- The plant is operating at 100% power.
- Inadvetent Safety Injection occurred duo to an Instrument Maintenance technician working in tho instrumont rackc w~ho accidontally shorted a circuit board-.
- Reactor tripped due to the SI signal
- Controlling #1 SG level transmitter that contro. M^DAF,.- purmp LCV failod Inv; the.AFRV fails Glesed low after the trip
- #4 SG PG ARV opened momentarily after thoe racto trip- and developed a large packing leak.
Which ONE of the following would cause the INITIAL-iRitia main feedwater isolation during this transient?
A. The #1 SG level reached 86%.
B.f The safety injection actuation signal.
C. Tavg dropping to 564 0F following the reactor trip.
D. When., tho south valvo vault level had risen to 4 inc*hs duo to the PORV packing leak. When #4 SG level reached 38%.
Ref: LP-28103
- a. Incorrect - level may reach 86% but FWI would already have been actuated by the SI.
- b. Correct - SI causes immediate FWl.
- c. Incorrect - would normally actuate FWI following a reactor trip however the SI initiated the FWI immediately.
- d. Incorrecty - PORV leak would cause increase in level in the vault room however FWI would have already been actuated by the SI.
- - 'r~ar~ra A RlAA 13 I uesday, February 25, 2 tU. v:,,
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 14. 008AKI.01 001 Given the following:
- Unit 1 is stable at 100% power
- A pressurizer safety valve opens and fails to reseat, remaining 25% open and the Unit trips
- RCS pressure stabilizes at 1600 psiq SI actuates
- PRT pressure gradually increases from 5 psiq to 100 psiq Which of the following indications would the operator expect to see as a result of this event-iR tho next 30 minutoc?
A. Safety tailpipe temperature would increase to greater than 600 F and then slowly decrease.
B. Safety tailpipe temperature would increase to greater than 600 F and then slowly increase.
C. Safety tailpipe temperature would increase to beteoen 220 and 310 F and thenslowly decreaseo and Ftabliz.
Safety tailpipe temperature would increase to approximately 230 F and then slowly decrease to 212 F a R rsuegaulyicess incroaco.s and ctabl'izo.
Safety tailpipe temperature would increase to approximately 230 F and then slowly increase to 330 F as PRT pressure gradually increases.
Ref- Farley 2000, validated for VG, LO-LP-16301, Pzr and PRT
- a. incorrect - the temperature is correct for pressures of 2240
- b. incorrect - the temperature is correct for pressures of 2240
- c. correct - since it relieves to the PRT, the pressure will increase until the rupture disc relieves (100 psig) and then the pressure (and temperature ) will decrease and eventually stablize
- d. incorrect - will not continue to increase once the PRT rupture disc relieves.
KA 14 ITuesday, F-ebruary 25, 2003 u 0:06:4v Al
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 15. 008K1.02R 001 Which ONE of the following correctly describes the uses of ACCW in the containment building.
A. RCP motor coolers, Seal Water Htx-.X and RCP thermal barriers.
B. RCP motor coolers, RCP thermal barriers and CVCS Letdown Regen HtxX.
C. RCP motor coolers, RCP thermal barriers and CVCS Normal Letdown HX D. RCP motor coolers, RCP thermal barriers and CVCS Excess Letdown HXtX.
Ref: WB bank, verified VG LP-04101-19-C Distractor analysis:
- a. incorrect - seal wtr hx not in containment
- b. incorrect - regen hx not an ACCW load
- c. Non-regenative hx not ACCW load
- d. correct 15 Tuesday, February 2b, 2UU3 U0:'6:4U AM
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 16. 009EA2.39R 001 Given the following conditions:
- Small break LOCA in progress
- RCS pressure is at 1100 psig
- No SI pumps
- No Charging pumps Which one of the following explains why RCPs are NOT tripped under these conditions?
W.hich ONE of the following oxplains why it is proforablo to loave the ROP's running during a small broak LOCA iftho ROS proccurn POP trip critoria on the foldout page are met but thoro i6 S!flow?
A. To provide heat removal through th- br!eak and the S/G's.
B. To maintain two phase mixture level above the break longer.
C. To limit single phase inventory loss out of the break.
D. To prevent boron stratification in the core.
Ref: DC Cook exam bank, VG LP-37111-15-C, pg 9 A is correct because the pumps will pump two phase (or steam) flow and cool by reflux in S/G's B is incorrect because the two phase mixture will continue to exit the vessel.
C is incorrect same as B.
D is incorrect because there will be boron stratification in the core due to severe inventory depletion.
naanr7.A.An 9~A16 ITuesday, F-ebruary 25, 400u u/;u,=u n:
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 17. 010K3.01 001 Given the following:
- The Pressurizer Master Pressure Controller fails to a constant output equivilent to 2230 2219 psig.
- Pressurizer pressure is 2230 2270 psig and rising.
- The variable heaters are energized.
- The spray valves are closed.
Which ONE of the following describes the response of the pressure control system if the operator takes no further action?
A. Pressure will rise until the spray valves open to control pressure.
BŽ Pressure will rise until PORV 456 opens to control pressure.
C. Pressure will rise until PORV 455 opens to control pressure.
D. Pressure will cycle on the variable heaters at a higher setpoint.
Ref: WB bank, VG LP-1 6303-19-C, LP-1 6301 Distractor analysis:
A is incorrect because PORV continues to receive a constant input and therefore remains closed.
B is correct because PORV 456 receives input from PT 456 which is seeing the actual pressure rise.
C is incorrect because the spray valves remain closed because there input is not changing from the master controller and is spray open setpoint.
D is incorrect because the input to the variable heaters is constant at a value less than their shutoff point.
. . .. ...... . naanfl1f .Afl AA 17 Iuesday, February 25, 2u03 uO:.uobuU ,A,,V'
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 18. 011A3.03 001 Given the following:
- Unit is at 50% power.
- All automatic control systems are in their normal lineup.
- Pressurizer program level sticks at constant output for 50% power.
- Controlling proccurizor program level fails to an outp)ut co~rroponding to 50% lead.
- Assume no operator action is taken.
Which of the following describes the effect on charging flow and PZR level as the plant load is increased to 100%?
A. Charging flow increases and actual PZR level remains constant.
Actual PZR level remains constant and charging flow increases.
B. Charging flow decreases and actual PZR level decreases.
Actual PZR level decreases and charging flow decreases.
Cý Charging flow docroasoc and actual PZR loVol incroaco-.
Actual PZR level increases and charging flow decreases.
D. Charging flow remains constant and actual PZR level increases.
Actual PZR level increases and char ing flow remains constant.
Reference:
WB bank, VG LO-LP-1 6302 Distractor analysis:
A is incorrect because Tav increases as power increases which will make PZR actual level increase.
B is incorrect, same reason as A C is correct because as PZR level rises with coolant expansion due to Tav increase, with LT-459 output at 50%, an error is generated that PZR level is too high, causing charging flow to decrease.
D is incorrect, same as A for PZR level, charging flow increases, see C.
Tuesday, February 25, 2003 07:06:40 AM 18
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 19. 011EK2.02 001 Given the following conditions:
A large break LOCA occurred Operators havo just complotod swapovor to Containment Sump Operators have just completed 19013-C, "Transfer to Cold Leg Recirculation" A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?
A. Pull to lock SIPs and CCPs until the RHR pumps are started by the blackout sequencer after the diesel generators start and load the 4160 vital buses.
BY Ensure the RHR pumps ar manually . started after the diesel genorators start and load the 4160 vital buses, thon manually start SIPs.
Manually start the RHR pumps after the diesel generators start and load the 4160 vital buses, then manually start SiPs.
C. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators start and load, then manually start CCPs and SIPs as needed D. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize 4160 vital buses.
WB bank - modified distractors Validated in 19013-C caution statement
- a. incorrect - RHR pumps manually started
- b. correct
- c. incorrect - RHR pumps are manually started
-. - ,- - a ~af7 A R.nAA 19 Iuesaay, February 2o, 40uuo u,.uubrvJ
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 20. 012K6.10 001 Given the following conditions
- Unit shutdown in progress
- Power at 9%
- Permissive "P-7 LO POWER TRIPS BLOCKED" illuminates Unit 1 is at 1000% powcr Pormiscive 7-0-D, P 7 LO0 POWNER TRIPS BLOCKED illuminatos Which ONE of the following describes the effects on RPS?
A. The reactor will not trip on Pressizer High Pressure.
B. Tho roactor w4illnot trip On ProccurizorLow L& tor Lovl.
The reactor will not trip on high positive rate C' The reactor will not trip on Pressurizer Low Pressure.
D. Tho roactor wAill not trip on Loss of Flow in ono loop.
The reactor will not trip on low steam generator level Ref: VG LO-LP-28103 NEED WINDOW INFORMATION Distractor analysis:
A is incorrect because P-7 is not an input to the trip.
B is incorrect because PZR Lo Water Level is not a trip.
C is correct, because P-7 blocks it when P-7 is off (light on).
D is incorrect because P-8 is unaffected and trips Rx on 1/4 logic.
-- .. _ -I-. - ..-... n , l lnn.n l.AAn AI.A 20 T uesday, February 4b, Zuud Vl : .:u'*~
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 21. 013K2.01 001 Given the following:
- SIP1A&lBareinAuto
- Control power is lost to SIP 1A
- Safety injection (Sl) occurs
- l A A and l B B Si pumnp breakores are 'racked 4Rn" A fuse blows in the NORMAL DC Trip Circui for the !A A SI pump A safety injection (SI) acutation occurs Which of the following describes the response of the Sl pumps to the Safety Iniection S4 signal?
Aý 1B SI pumnp will start, but 1!A S! pumnp will not auto start until tho control power supplyi a* ns.ferred.
SIP 1B will start, but SIP 1A will not auto or manually start until the control power supply is restored.
B. 16B SI pump will start, but !A SI pumnp will not auto start And must be started fromn MCR handswitch.
SIP 1B will start, but SIP 1A will not auto start and must be started from MCR handswitch.
C. Both SI pumps will auto stat*, but tho IlA SI pum,p can not be stopped from the MGR.
Both SI pumps will auto start, but the SIP 1A can not be stopped from the MCR.
D. Both SI pumps will auto start, but the l-A SI PUMP can not be stopped from the mechanically at the break(er.
Both Sl pumps will auto start, but the SIP 1A can not be stopped except mechanically at the breaker.
Watts Bar exam bank - NEED CONFIRMATION ON BREAKER LOGIC
- - ~ a-.a,.AflflA21 Tuesday, F-eDruary 25, 2uu3 0.7uo:0+U *-V,
QUESTIONS REPORT for VOGTLEFINDRFT1028 2%* 013K6OfIt 00*1 An upscale failure of which one of the following will result in an automatic actuation of ESFAS equipment?
A. Containment pressure instrument, PT-936.
B. Control Room Area monitor, RE-0001.
C. Pressurizer Pressure instrument, PT-454 455.
DW Control Room Air Intake monitor, RE-12116 Ref: Lo-LP-32101 Tuesday, February 25, 2003 07:06:40 AM 22
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 23. 014A4.01 001 Given the following:
- Operators are preparing. e conducting a reactor startup
- Bet shutdown banks w. withdrawn
- All-control banks are .till.fully inserted being withdrawn in 50 step increments Tho rod control startup rosot switch is manipulated in orror
- The SS notices that Control Bank A is at 200 steps and Control Bank B is at 0 steps Which Of the following dosc.ibo. the roguirod actions to procood with tho startup?
Which of the following explains these indications?
A. Roestor theo P/A scnvrtor to 230 stops.
Rod bank selector switch is in the manual position.
B:! Rostoro; tho s~hu-tdown group stop co11unter to 230 stops.
Rod bank selector switch is in the Control Bank A postion.
C. Rostoro the bank overlap unit to 230 stops.
The rod control startup switch is stuck in the reset postion.
D. RoA.nRinsor;al shutdown banks.
DRPI Data B failure has occurred.
INPO bank - validated for VG in LO-LP-27102-12
- a. incorrect - P/A converter does not need to be reset because the control banks are fully inserted
- b. correct - all group step counters are reset to 0 by the reset switch
- c. incorrect - bank overlap counters are at 0 because the control rods are fully inserted
- d. the shutdown group counters can be manually reset - reinsertion is not required
-. ASS23 Tuesday, -ebruary 25, zuu2 u0:0uo64 ,lVI
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 24. 015G2.2.12R 001 W.hich ono of tho following doerbswo tho HFASA (hot functional at Shutdown Alarm) is appIcb Modo 6?
i-.n HFASA must be operational ifthoboratodoher. co*uo . isolation valve(s) are opened....
NIS channel check surveillance is required every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by technical specfications. The last channel check was completed at 0615 on 10/31/02. Outage activities are hindering completion of this surveillance.
The NIS channel would be declared INOPERABLE ifthe next channel check is not completed by:
AY for an" reason othor than porformanco of Source Range N'31 or Intormediato Rango N35 surveilancos porformoed at the same timo.
2115 on 10/31/02 B. for any reason othor than performance of individu-al Sourc. Rango N31 or Intermediate N35 Range .urvoillancos-.
2215 on 10/31/02 C. for any roacon othor than tho po.f.rmanco of TS 3.9.2 6s..oeilaRncos.
0615 on 11/01/02 D. fr-any..easo..
1215 on 11/01/02 REF: Procedure 14423-1 The purpose of this procedure is to verify the operability of the Nuclear Instrumentation System (NIS) Source Range and/or Intermediate Range Instrumentation for Channels N31 and/or N35.
In Mode 6, the HFASA must be operational ifthe unborated water source isolation valve(s) are opened for any reason. Ensure the valves are secured per TS 3.9.2 prior to initiating this surveillance.
Section 5.1 is also performed in Mode 3, 4, 5 and 6 to verify Source Range Instrument operability and the HFASA function if not performed in the last 92 days. Performance of Sections 5.2 and 5.3 will satisfy the Source Range Instrument operability requirements if performed within the last 92 days. (TS SR 3.3.1.7)
At least once every 92 days for HFASA when in Modes 3, 4 and 5.
24 Tuesday, F-ebruary 5b,20UU0u07:06:U AMli
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 25. 015K4.06 001 While operating at 90% power, one power range channel N41 ofnua instrum.ntation Power Range High Flux Reactor Trip is placed in bypass (B.TIfor a surveillance.
Whet is the coincidencg f this rators trip and how long can this reator trip?remain Which one of the following conditions would result in a reactor trip?
A. 2 ou-t of 4 and can be bypassed for no more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Any of the other 3 PR NIS channels fail high B. 1 out of 2 and can bo bypassed for no mere than 12 houArs.
Any 2 of the 4 channels reading 105%
Cr 2 out of 4 and can be bypasod for no mre than 7-2 hoursp.
PR channels N41 and N44 lose control power 1 It Of,.r2 eAd Gan be' b-vnnnred J $nn rn~ nrn thin 7:2 hor~s.
Operator places PR channel N42 in test INPO bank - validated for Vogtle by LO-LP-17301-24, TS 3.3.1
- a. incorrect - coincidence changes to 1 out of three when in bypass
- b. correct - coincidence changes to 1 out of 3 and in bypass for 12 hrs for surveillance
- c. incorrect - wrong logic and bypass limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- d. incorrect - bypass status limited to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance Tuesday, February 25, 2003 07:06:40 AM 25
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 26. 015K5.04 001 Manual calibration of the NIS is being performed in accordance with procedure 14030-2, "Nuclear Instrument Calorimetric Calibration." Feedwater average temperature is incorrectly calculated to a value 17 degrees less than actual. For these conditions, which of the following is correct?
Calculated reactor thermal power will be ......
A. lower than actual and a gain adjustment of the NI channels using the calculated value would be non-conservative such that the indicated power is farther from the setpoints.
B. higher than actual and a gain adjustment of the NI channels using the calculated value would be non-conservative such that the indicated power is farther from the setpoints.
C. lower than actual and a gain adjustment of the NI channels using the calculated value would be non-conservative such that the indicated power is closer from to the setpoints.
DW higher than actual and a gain adjustment of the NI channels using the calculated value would be conservative such that the indicated power is closer from to-the setpoints.
ref: 14030-2, LP-LO-17301
- a. incorrect the calculated is higher than actual and conservative
- b. incorrect the calculated is higher but conservative
- c. incorrect the calculated is higher but conservative.
Tuesday, February 25, 2003 07:06:40 AM 26
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 7. 06Tc.02 001 With Pressurizer Level Control Selector Switch LS-459D selected to 459/460, the following SEQUENTIAL plant events occur due to a failure without operator action.
- Charging flow increases to maximum
- Pressurizer level begins to rise
- Letdown isolates and heaters turn off
- Pressurizer level eventually rises to the high level reactor trip Which ONE of the following failures occurred?
A. Level channel LT-459 failed high.
B. Level channel LT-460 failed high.
C." Level channel LT-459 failed low.
D. Level channel LT-460 failed low.
Ref: Vogtle LP-16302, proc 17011, 18001 Distractor analysis:
A is incorrect because charging "see" the level as high, throttles to minimum. Actual level decreases and channel LT 459 shut letdown valve and isolates heaters. With no letdown, even an minimum charging, actual level rises to the high level trip setpoint.
B is incorrect because LT-460 can't be selected for input to master level contoller C is correct because failing low makes charging increase and level would initially go up rapidly due to letdown also isolating and cause a trip the Rx D is incorrect same as B
- r. .A.. O 7 A*A .ARA 27 I uesuay, Fer~uaryI
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 28. 017AK1.02 001 IF RCP #1 trips when the plant is at 13 30% power during a load increase to 100%, which one of the following statements is correct?
A. A reactor trip will occur and operators should implement 19000-C.
B.0 The affected pressurizer spray valve should be shut to prevent spray flow from bypassing the pressurizer.
C. The affected S/G blowdown rate may be isolated to facilitate level control.
D. An immediate plant snutdgown is roguiFru pureH11a iucuniute: : ...
Reactor trip breakers should be immediately opened to comply with the action statement for LCO 3.4.4, "RCS Loops-Modes 1 and 2".
Ref: VG bank Tuesday, February 25, 2003 07:06:41 AM 28
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 29. 017K3.01 001 Given the following conditions:
- All RCPs are tripped
- All core-exit thermocouples are inoperable 19001-C step 9 has the operators verify that natural circulation flow is occurina. What indication(s) would the operator use?
If All coro oit thormocou.plo. aro i.op.rablo during an event in which tho RCPS woo trippod.,
what indication(e) mnay bo used to vorify that natural circlation cooling is occurring?
A. RCS hot log tomperaturos only RCS loop delta T's stable or lowering B. RCS celd log tomporaturoc only RCS loop delta T's increasing to full power values C' Both ROS cold log and hot log temperaturos Both RCS hot leg temperature stable or lowering and RCS cold leg temperature at saturation for SG pressure D. There are no adequate indications for RCS temperature is available in this condition.
Bank (NA'02) - validated for Vogtle in EOP 19001-C
- a. incorrect - insufficient information
- b. incorrect - insufficient information
- c. correct - the difference in temperatures will be adequate to determine of natural circulation has been established
- d. incorrect, using both hot and cold legs is adequate
_ ^ A.*A5 29 Iuesday, February z2, 2uu,0 u0:uo0:4- ,lVI
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 30. 022AG2.1.32 001 During water solid operations with letdown from RHR, procedure 13011-1 requires that 1-HV-0128, Letdown From RHR, be full open.
Which ONE of the following describes the basis for this precaution?
A. To ensure maximum letdown flow rate for purification.
B. To ensure VCT level can be maintained under all charging flow conditions.
C." To ensure 1-PIC-0131, Low Pressure Letdown Controller can control pressure transients.
D. To ensure RCS to RHR Supply Line Relief Valves PSV-8708B and PSV-8708A isn't challenged.
VG 13011-1, pg 21 caution Distractor analysis:
Answer A is incorrect because charging flow controls letdown flow.
Answer B is incorrect because balancing charging and letdown controls VCT level.
Answer C is correct because with hv-0128 less than full open, it can in effect limit flow and prevent pressure reduction whenpic-0131 fully opens in response to a high pressure transient.
Answer D is incorrect because the suction relief can be challenged by other factors (eg. pump starts) even with hv-0131 full open.
. . . ,-fl ...... A"- 30 Iuesaay, February 25, 0uuo u, u.v I , ,lv,
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 31. 024AK2.01 001 rL. .
mlfJA .... %lAk:I, A; *F+k R) idontifioc 2 control rods failod to inco~t. An omorgency boration was initiatod, using both boroi acid transcfr pumps, aligneod through omorgoncy berato valve 1 HV 8101. Hoovor,
-iven followin conditionse:esennga Dwewh oerrectly And 1 Fl0182A indicatedboration eefaon of-02 HV- 01 failed to operate gpm, althoug charging flow gpm. iam2 Given the following conditions:
- 2 rods stick out on a reactor trip
- The RO initiates emergency boration using HV-8104
- Boric flow on FI-0183A isc23 gpm and charging flow is 42 gpm Which of the following is the correct response to this condition?
The RO can correct this condition by....
A. Placing charging flow controller FIC-01 21 in manual and increasing the set point to >42 gpm, ensuring charging flow increases and FI-0183A indicates >30 gpm.
B. Realign;. the........... 1 n flow
...... by G.,,.. HV 8104., opening FV-110A, closing FV-110B, and ensuring FI-0183A indicates >30 gpm.
C' roalign the omorgency flow path by do.ing HV 8101, opening HV-1 12D and HV-1 12E, then closing HV-1 12B and HV1 12C, ensuring charging flow is >87.5 gpm.
D. roalign the omorgoncy flow path .. by o.ing HV 8101, opening HV-1 12B and HV-1 12C, then closing HV-1 12D and HV1 12E, ensuring charging flow is >87.5 gpm.
Ref: LO-LP-09402, 13009-1, 17010-1 window D04
- a. incorrect because the intial conditions indicate HV-1804 is limiting the boration flow, charging flow is adequate.
- b. incorrect because FV-1 1OB also needs to be open for a complete flowpath
- c. correct, correct valves in the correct order
- d. incorrect because the order will isolate the suction to the charging pumps causing cavitation.
Tuesday, February 25, 2003 07:06:41 AM 31
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 32. 025AK2.02 001 Given the following:
- RCS temperature is 118 F
- Reactor Vessel head is removed
- Reactor Upper Internals are installed in the reactor vessel
- Refueling Level is 186 ft, 6 inGhos 188 ft, 3 inches.
- RCS draining is in process at 10 gpm
- The RO increases RHR pump A flow from 3000 to 3800 gpm
- RHR pumnp A is running with indicatod flow of 3800 gpm
- RHR pump A begins to exhibit indications of cavitation The cavitation and resulting loss of RHR is occurring due to .......
A. draining with the upper internals in place, which reduced the RHR suction pressure.
B. steam binding of the RHR pump, caused by low recirculation flow.
C. air entrapment at the RHR suction inlet, caused by the high flow conditions.
D. draining with the upper internals in place, which reduced the RHR discharge pressure.
Ref. Bank - VG verification LO-LP-12101-39, 12008, Data Book, Tab 8
- a. incorrect, upper internal installation will not effect RHR suction pressure.
- b. incorrect, recirculation flow valve shuts at 14000gpm
- c. correct, air entrapment occurs at higher flow rates, normal midloop flow rate is 3000 - 3500
- d. incorrect, upper internals installed will not effect RHR discharge pressure to this extent Tuesday, February 25, 2003 07:06:41 AM 32
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 33. 026A1.01 001 Given the following conditions on Unit 2:
- Following a LOCA, containment pressure is rising.
- Containment pressure has reached 20 psig on three channels and 22 psig on one channel.
Whickh. of the following is a comploto list of tho minimum required automatic/manual manpulations required to stad containment spray?
Which one of the following will result in containment spray actuation?
A. When one (1) mnere containment pressure channel transmitter indicates containment prossure of 22 psig, or whon ono (1)ma~nual handewiitch is actuiated on the QMCB.
When 1 more containment pressure channel indicates 22 psig, or when 1 manual handswitch is actuated.
B! When ono (1) more containment pressure channel transmitter indicates contanma ent pressure of 22 psig, Or when two (2) manual handswitch is actuated on the QMCB.
When 1 more containment pressure channel indicates 22 psig, or when 2 manual handswitches are actuated.
C. When two (2)more containment pressure channel tFrasm~itter indicates containment pressure of 22 psig, or when ono (1)manu al handew~itch isactuated on the QMCB.
When 2 more containment pressure channels indicate 22 psig, or when 1 manual handswitch is actuated.
D. When two (2) mnere containment pressure channel transmnitter indicates containment pressure of 22 psig, or when two (2) manual handswiA4tch is actuiated on the QMCB.
When 2 more containment pressure channels indicate 22 psig, or when 2 manual handswitches; are actuated.
Ref: VGLO-LP-15101 all actuation signals for Containment spray - when 2/4 containment pressure transmitters indicate cont press of 21.5 psig or when 2/2 manual switches are actuated on the QMCB Tuesday, February 25, 2003 07:06:41 AM 33
QUESTIONS REPORT for VOGTLEFINDRFT1 028 "Li. i194AK'f 01 001 Given the following plant conditions:
- Unit 2 is in Mode 3 for* a-intonnco
- ALB 04, window A2, "ACCW LO HDR PRESS" is alarming
- ALB 07, window D3, "LTDN HX OUT HI TEMP" is alarming Which one of the following events would cause both of these alarms?
A. Letdown Hx Tube Rupture B.' ACCW Supply Header Rupture C. Loss of Seal Injection D. Loss of Charging Flow Ref: VG exam 2000
- b. correct
- c. incorrect - loss of seal injection will not cause either of these
- d. incorrect loss of charging would cause the hi temp alarm but not the letdown alarm
Reference:
Tuesday, February 25, 2003 07:06:41 AM 34
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 35. 027AK3.03 001 Given the following conditions:
- Unit 1 is at 100% power.
Annunciator 89A, PZR PORV LINE TEFMP HI, illuminatos.
- ALB12 E01 "PRZR RELIEF DISCH HI TEMP" illuminates
- Both PORV's indicate closed.
- PORV-455 tailpipe temperature is reading 220 degrees F.
- PORV-456 tailpipe temperature is reading 187 degrees F.
- Pressurizer pressure is lowering nermak In accordanco wioth ARP 17-012 1 which ONE of tho following is the corroct action and eacon Which one of the following is the correct action?
A. Close the associated block valve for PORV-4565 because a vapor-space leak causes PZR level to increase.
B. Close both block valves because a vapor-space leak causes PZR level to increase.
Cf Close the associated block valve for PORV-455 to stop leakage to the PRT beoause the PRT willr uptur..
D. Close both block valves to stop leakage to the PRT bocauco the PRTr will rupture.
Ref: NEED VOGTLE EQUIVALENT INDICATION AND RESPONSE Disaster analysis:
Answer A is incorrect because PZR level rise is only associated with large leaks that affect PZR pressure.
Answer B is incorrect because the - requires the leaking PORV to be determined by alternately closing the block valve and AOI requires closing only the associated block valve.
Answer C is correct because it follows the ARI guidance and small leaks can raise PRT pressure to the rupture disc setpoint.
Answer D is incorrect same as B and A.
1", t*l*l C,I krtla, O2 2003 07:06:4TR1 AM 35 I e a**ly, e ruarblly .- ,tl#.'. . '* .ri*v
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 36. 029EA1.13 001 Which ONE of the following is the NEXT action the operator is required to take if the main turbine does NOT trip automatically and CANNOT be manuall tripped from the Control Room ,MGR;-p&-FR-&4 per 19211-C "RESPONSE TO NUCLEAR POWER G ENERATION/ATWT"?
A. Place both EHC pumps control switches in PTL.
B. Trip the turbine locally at the front standard.
C. Manually Runback the turbine.
D. Shut the MSIV's.
WB exam bank, validated VG procedure 19211-C, step 2 RNO Distractor analysis:
A is incorrect because it is a followup action later in the procedure, step 9 RNO.
B is incorrect because it is a local action if MCR actions fail, step 9 RNO.
C is correct per RNO step 2 D is also in RNO step 2, but only occurs if runback doesn't work.
Tuesday, February 25, 2003 07:06:42 AM 36
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 37. 029K1.02 001 Which ONE of the following d-cio-h apl aho E2565) RE 002, Cntmt Low Rlango, and offoct of oxcooding thoeIG alarm cotpoiffnt?
RE-2565 RE--90--30 samples the and initiates a Containment upon hiqh alarm.
A. Cntmt Purge Exhaust direhar§e ; Purge trip BW Cntmt Purge Exhaust suretie; Vent Isolation C. Cntmt Purge Exhaust di*sha~ge Supply ; Vent Isolation D. Cntmt Purge ExIhau6t suctioR Supply ; Purge trip Ref: Vogtle Lesson PLan lo-lp-32101, drawing 1x4db213-1 A. incorrect, sample on suction pipe B. correct
- c. incorrect sample suction pipe and causes CVI
- d. incorrect - causes CVI flffl ,"~fQAo ARA 37 ITuesday, F'ebruary 45, &uuO u .v.,*,
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 38. 032AK1.01 001 Given the following conditions:
- Reactor Startup in progress Shutdown Banks withdrawn Control Bank withdra;walismont
- SRM N-32 indicates appro.*mate! 1000 cps
- SRM N-31 is in bypass Which ONE of the following will occur if the control power fuse for SRM N-31 blows?
A. Lose indication for SRM N-31 on Main Control Board and NIS cabinets.
B. Both SRM drawers deenergizes and the "non-operate" alarm acuates.
Cf Reactor will trip.
D. Rod withdrawal is blocked.
Modified from WB bank - rewrote question stem and changed distractor. Validated for Vogtle in LO-LP-17103-00-C
- a. incorrect-not all indicatipon lost since instrument power is available
- b. incorrect-SRM N132 unaffected by loss of control power to SRM N131
- c. correct- loss of control power deenergizes bistables and initiates trip signal (1/2 logic)
- d. incorrect - Source range low does not initiate rod stop Tuesday, February 25, 2003 07:06:42 AM 38
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 39. 033G.2.4.18R 001 rr,,fln r ~oa +,,' ,,+:. nv. n knn .c- hrnJ t 1
h fuenl nnn! a Ta4. .- - -ri
-an n nr~
army A; kI- hnfl, ,; -Spnr'n+ $nI nanI njjj 0
ALt..... flfl ... 8... .*e.a *ke.
N/a,. e.nnr Akne.rmol flnar F -. flhnnnA, rap 101V2A C' tempraturo Is 125 135 dogroes n icesigwt ono of the trains has boon rostored.
Which ONE of the following is the appropriate action?
Given the following conditons:
- Unit 1 core has been completely off loaded to the SFP
- Both trains of SFPC are in service
- SFP temperature steady at 115 degrees F
- A total loss of SFPC occurs
- The crew implemented AOP 18030-C, "Loss of SPF Cooling"
- 20 minutes later train B SFPC has been restored
- SFP temperature is 135 degrees F and increasing Which ONE of the following is the appropriate action?
AM A.Rm~ain *RAbnormal i Operating Procodures 18030-C because one train of spent fuel peelcoolng my nt bo able to maintafin the temperature below 130 F.
Exit Abnormal Operating Procedure 18030-C after placing the second train of SFPC in service and SFP temperature returns to normal.
B. Exit Abnormal Operating Procedure 18030-C and return to the procedure step in effect.
C. Rgnini Abnormal flnnrntinn Prnc~ndWr 18030 Q until tho fuol [)eel temperatur~e is below 1 Al* .+... nrn+, i.n +nI nrn. 'nri ,rn... n..... .....
Remain in Abnormal Operating Procedure 18030-C until CCW flow to the SFP Hx is increased, then return to the procedure step in effect.
D. Remain in Abnormal Operating Procedure 18030-C, until the cask loading gates are closed, then return to the procedure step in effect.
Ref: 18030-C 5 of 12 NOTE: During refueling outages after the entire irradiated core has been discharged to the SFP, one train of SFP cooling may not be able to maintain SFP water temperature less than 130'F. Open cask loading pit gates and maintain them open to allow circulation between pools.
Tuesday, February 25, 2003 07:06:42 AM 39
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 40. 034K4.01 001 Which one of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?
A. The Gripper is mechanically engaged and disengaged by a remote operating handle on the bridge and requires no power or air to operate.
B.f The gripper requires air to disengage, however, a mechanical latch prevents gripper release under load even ifair is supplied.
C. The gripper will disengages upon loss of air, however, a mechanical latch prevents gripper release under load even if air is removed.
D. When the gripper is engaged, the fuel handlers operaters mechanically lock gripper in place with extension shaft which must be unlocked before the gripper can release.
Ref: lesson LO-LP-25101-19-C, STILL NEED DETAIL INFO ON THE MECHANICS OF THE GRIPPER
- a. incorrect - air required to disengage
- b. correct - mechanical latch on gripper works under load
- c. incorrect - engages on loss of air
- d. incorrect - no operator action required for gripper mechanical latch to operate Tuesday, February 25, 2003 07:06:42 AM 40
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 41. 035K(1.09 001 Given the following plant conditions:
- The reactor is operating at 50% power.
- Rod control is in MANUAL.
- Turbinh centrol is in AUTO.
- #3 S/G ARV PQRV fails OPEN.
Which ONE of the following describes the resulting steady-state conditions?
(Assume no reactor trip, no operator action and turbine power remains constant)
A. Final Tavg < initial Tavg and final power > initial power.
B. Final Tavg < initial Tavg and final power = initial power.
C. Final Tavg = initial Tavg and final power > initial power.
D. Final Tavg = initial Tavg and final power = initial power.
Reference:
general theory Distractor analysis:
A is correct steam loss through PORV causes Tav decrease which adds positive reactivitiy which causes power to rise. Tav will remain less than initial Tav because some of the reactivity is used to overcome power defect associated with power rise.
B, C, and D are incorrect because they conflict with the above correct answer.
.- c -~-no..~ Ao ARA 41 ITuesday, February 25, 40u3 ui~u).v-: v
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 42. 037AK3.07 001 Given the following:
- A SG #3 tube loak of approximat.. has a 30 gpm leak hac boon*..;.
idontifi.d On SG M3.
- Tho oporating
- row hag ntoreod AOP 18009-C, Steam Generator Tube Leak, is being implemented Oporatore havo oamplotod Stop A9 of the AOP and havo isolated food flow to
- Stop A12 rogui.ro that the level in the leaking S/G {SIG-#3) is maintained greater than 10%.
Which ONE of the following is a bases for ensuring the attected SG level greater man IUr/o; A. To ensure that the pressure and temperature limits of the SG shell are maintained.
B!1 To prevent the RCS cooldown from causing depressurization of the affected SG.
C. To prevent SG overfill.
D. To prevent thermal shock to the tubes during RCS cooldown.
Ref: VG AOP 18009-C A is incorrect in that these limits apply to CSD conditions B is correct because the insulating layer of water above the tubesheet helps trap pressure in the S/G and minimize tube d/p during cooldown.
C is incorrect because level control is not an issue.
D is incorrect because there is no sudden introduction of cold water after the level is attained.
- LfrC~l l.a A AA R 42 I uesday, February 2o, 4U0O vt u.*uL nuvu
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 43. 039A1.03 001 rL... . .,.. IOgII ('nnrlane Ar. r.nA CnnA..,n+r.r pnn4"n A A fl rtpr.;n rnrd.s.ntnr Systom Warmup Using BA'B Foodwator Heators. Tho crow complotod tho following cog uoneo.
1.1.6.2* Ro*tuD FW hoator 5A High Lovol Controllor 1 LCH 1286 to A.UT a..ESTABIISHo.mmunicationc with por.onnol at tho PHPF
- b. P lAC Hoater 5A Normal Loval ContFrllor 1 ILC 1-28 iA A'UTO
- c. ENSIURE hoator 5A High Lovol Controllor, 1 LCH 1286, iinmanual
- d. SOWL Y RAI S the I LCH-1286 output to c*le, 1 LV 1286 You noto that 1 LCH 1286 is not roeponding and RCS temperature is docroacing slightly.
Whfich o*n of the following could hafivo caucod the?*
Unit 2 is in mode 3 at NOPT for a post refueling start up MSIVs are shut and the main steamlines need to warmed SG ARVs are in manual controlling loop Taves at 557 F Which of the following correctly describes the method used and the indications observed while warming the main steamlines?
A. inadoguato 'oveo in th 5,A hoater Slow open MSIVs one at a time. RCS pressure will remain constant while temperature decreases.
B. high 'evo! in tho 5A hoator Open steam dumps to 1% to 2% after placing both bypass switches in the bypass position.
RCS temperature will decrease and RCS pressure will decrease.
Cf food flow~ wqac not in corico prior to ectablishing foodwator hoating Open MSIV bypass valve(s). RCS temperature and pressure will both decrease.
D, tho unit it otill inLong Cyclo rocirculation Open MSIV bypass valve(s) after placing both steam dump bypass switches in the bypass position. RCS temperature and pressure will both decrease.
REF: 13615-1, Condensate and Feedwater sect 4.4.6 Note: Due to inadequate level in the heater 1-LV-4282 may not respond until heating steam has been initiated Sfli f.lQAn AK.A 43 T uesday, Feruar~y 45, 4003. - :,
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 44. 040AG2.4.4 001 Given the following plant conditions:
- Unit was at 100% power
- A main steam line break occurred in the Turbine Building
- Operators were unable to close the MSIVs and transitioned to ECA-2.1, "Uncontrolled Depressurization of All Steam Generators."
-SI tormination stoewaro i proroc
- Loop 3 MSIV is closed locally
- The CRO observes the # 3 S/G pressure rising slowly Which of the following actions should be performed?
A. Immediately transition to E-2, "Faulted S/G Isolation" B. Immediately transition to ES-i.1, "SI Termination" C. Remain in ECA-2.1 until RHR is in service D. Remain in ECA-2.1 until SI is terminated Ref: WB bank, verified for VG ECA-2.1, ES-I.1, E-2 A. incorrect-wrong because do not leave ECA-2.1 until SI terminated B. incorrect - wrong because do not leave ECA-2.1 until SI terminated C. incorrect - wrong because stay in procedure until SI terminated not RHR in service D. correct - complete SI termination prior to transitioning to E-2
- . . -anntV~1fltAflA*A44 I uesaay, February 2O, 0u03 u/:.U:O.C NVO
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 45. 041K3.04 001 Given the following conditions:
- Unit at 400-75% power, EOL conditions.
Turbine oporating in manual
- A steam dump valve inadvertently comes full open.
- All other control systems normal.
Which ONE of the following correctly describes the plant conditions, when plant stabilizes, and assuming NO operator action?
A. Megawatts electrical same as initial; reactor power increases.
B. Megawatts electrical same as initial; reactor power dereases.
C. Megawatts electrical decreases; reactor power increases.
D. Megawatts electrical decreases; reactor power decreases.
Ref: WB Exam Bank, modified for VG
,_An ,.n,.,o A, ARAo 45 Tuesday, F-ebruary 45:, 4003 vi:u*c ,:..v
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 46. 045A3.05 001 The following plant conditions exist:
- Unit 1 is at 90% power
- Main Turbine is in STANDBY to repair a failed speed sensor Which ONE of the following correctly describes the status of the Turbine Control System?
A. All overspeed protection has been defeated except for the Mechanical Trip and the Backup Overspeed Trip.
B. Overspeed protection from the speed control circuits and PLU has been defeated. IVFast Closure, Mechanical Trip, and Backup Overspeed Trip are still operable.
C0 The Power Load Unbalance circuit is still active and will allow fast closure of the Control Valves and the Intercept Valves if a sudden load rejection of more than 40% occurs.
D. The Power Load Unbalance circuit is defeated and the Backup Overspeed Trip setpoint is reduced to 105%.
Ref: VG Exam Bank VG Lesson Plan LO-LB-30303 Obj. 20 fllll At. A"A 46 Tuesday, F-ebruary 25, 4003 ui;ub.: ,*
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 47. 051AA2.02R 001 Given the following:
- Condenser pressure rising; operators dropping turbine load in attempt to maintain vacuum.
- Condenser vacuum is decreasing, currently reading 25.20 inches Hg.
Which ONE of the following would be the FIRST to automatically occur or be procedurally required if condenser pressure continues to rise?
A. Auto main turbine trip on low vacuum.
B. Manual reactor trip.
C. Loss of steam dump capability.
D. Manual turbine trip.
Ref: WB Exam bank - VG ARP 17019-2, window B04 Distractor analysis:
A is incorrect because auto trip does not occur until vacuum >22.42 Hg B is incorrect because the procedure turbine trip not required.
C is correct because are incapable when vacuum reaches 24.92 Hg D is incorrect - not required at that vacuum (24.92)
- r~ anv~,a.fl.AflAkA47 Iuesday, February 25, 20U3 uviuo.c, Mv
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 48. 054EG2.4.48 001 Given the following:
- Unit 1 is at 100% power.
- Annunciator ALBi 3 0r01 STM GEN 1 HI/LO LVL DEVIATION alarm is illuminated
- Tho oporator noticoc only S/G #1 loVol ricing along with MFP spood.
- S/G #1 level rising
- Both MFPs speed are rising
- The other S/G levels are slightly below program Which ONE of the follow describes the (1) cause, (2) required action and (3) direct consequence of an operator failing to take action?
A. (1) #1 S/G FRV is opening, (2) stabailize #1 S/G level at new level, (3) Turbine Runback Initiated B. (1) #1 S/G FRV is opening, (2) return #1 S/G level to program, (3) Feedwater Isolation initiated C. (1) MFP master controller failing high, (2) control MFP speed using manual, (3) Auto Turbine Trip initiated D. (1) MFP master contrroller failing high, (2) manually trip turbine, (3) Feedwater Isolation initiated Ref: VG 18016-C, section D Distractor analysis:
A is incorrect because the consequence is a P-14, Hi-Hi SG level which initaties a FW isolation.
B is correct because only one SG is rising, hence a FRV is the cause, action is from 18016-c for FRV failure and FW isolation occurs with no operator action at P-14.
C is incorrect because a problem with the MFP controller would affect all SG's the same.
D is incorrect same as C.
Tuesday, February 25, 2003 07:06:43 AM 48
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 49. 055EK3.02 001 Which ONE of the following is a purpose of depressurizing all intact SGs to 300 psig during the performance of 19100-C EGA-0.0 "Loss of All AC Power"?
A. Reduces DP across SG U-tubes to minimize possibility of tube rupture.
Bf Reduces DP across RCP seals to minimize leakage and loss of RCS inventory.
C. Maximizes Natural Circulation flow before Ref lux cooling begins as the RCS becomes saturated.
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM are unavailable.
The correct answer is B
- a. Incorrect - the most likely failure for this event is loss of inventory through failed RCP seals not SGTR.
- b. Correct - reduces potential for a seal LOCA by reducing the driving force.
- c. Incorrect - steaming is a method to increase natural circ and would occur, however minimizing inventory loss is a greater concern at this point.
- d. Incorrect - steaming is a method to increase natural circ and would occur, however minimizing inventory loss is the greater concern at this point.
References:
ECA-0.0; ECAOOOO.03 K/A 055 EK3.02 [4.3/4.6]
Tuesday, February 25, 2003 07:06:43 AM 49
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 50. 055K3.01 001 Given the following conditions:
- Reactor power is steady-state at 100%.
- Rod control is in automatic.
- Condncore VacuumF Pumps 1!A and 1B are running with 10 pump out fOr.ll of corFVicoG maintoA.Enanco._
- Sealing steam pressure drops to 0 psip due to a malfunction Which ONE of the following conditions will result if NO operator action is taken in response to this condition?
W*hich OQN= of tho following conditions could rccult if NO operator action is takon in roeponco to a COND VACUUM PUMP 18 SEAL WTR PRESS LOW alam A. Rising megawatt output and rising steam seal header pressure.
B. Rising megawatt output and rising condenser hotwell level.
C. Dropping megawatt output and dropping condenser pressure condonsato tomporature.
DW Dropping megawatt output and rising condenser pressure cond.ncato tomp.raturo.
WB Lesson plan 3-OT-SYS1100, obj 4 NEED TO GET VOGTLE VALIDATION Distractor analysis:
Degraded vacuum causes megawatt output to decrease due to reduce delta H. Therefore, A and B are incorrect.
Condenser is a saturated system, so higher Psat means higher Tsat. Therefore D is correct and C is incorrect.
Tuesday, February 25, 2003 07:06:43 AM 50
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 51. 056AKI.OIR 001 Given the following plant conditions:
- Unit 1 has experienced a Loss of Offsite Power
- The operating crew is currently performing a cooldown, in accordance with 19002-C ES-0.2, Natural Circulation Cooldown
- Prior to initiating the cooldown, two CRDM fans trip Which ONE of the following describes the maximum allowable cooldown rate?
A. <100 'F in any one hour BŽ <50 0F in any one hour C. <25°F in any one hour D. <75°F in any one hour Ref: VG procedure 19002-C, step 12 Distractor analysis:
Answer A is incorrect per ES=0.2 Answer B is correct Answer C is incorrect per ES-0.2, Answer D is incorrect per ES-0.2 I
Tuesday, February 25, 2003 07:06:43 AM 51
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 52. 056K1.03 001 Unit 1 is at 7270% power. A limit switch problem causes 2-$V-3440 MFP 1A turbine exhaust valve to close 1-te-slowly-elee&
Which ONE of the following describes the effect on continued plant operation?
A. 1A MFP rolls to idle, the Standby condensate beeste pump starts and Rx power can remain at 70%
B.f 1A MFP trips, the standby condensate beester pump remains in standby, does net stat and Rx power can remain at 70%.
C. 1A MFP trips, the standby condensate beoste pump starts and Rx power must be reduced to 56%.
D. 1A MFP rolls to idle, the standby condensate beoste* pump does not start and Rx power must be reduced to below 56%
Ref: Vogtle ARP-17015-2.
Distractor analysis:
A and D are incorrect, because the 1A MFP trips on low condenser vacuum C is incorrect because the standbycondensate pump auto starts B is correct, because the standby condensate pump starts and the lb MFP can carry 76%,
the sum of which is above 72%.
Tuesday, February 25, 2003 07:06:43 AM 52
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 53. 057AA2.18R 001 Given the following:
- Unit 1 at 100% power
- Alarms received indicate a failed electrical bus board Othor indoiationc a.o:
- All channel 1 trip status lights illuminated out
- MSIV's remain open and the unit does not trip
- All channel 1 instruments fail down scale
- Low co.al flow' to RCP'c duo to FCV 62 89 failing opon
- High charging flow duo to FCV 62 93 failing open Which ONE of the following identifies which electrical bus board that-was is de-energized lost?
A. 125F V PC Vital Batter; Board I 125 V DC Vital Bus lADI B! 120 VAC Vital Inctrument Powor Board 1-.
120 VAC Vital Instrument Bus 1AY1A C. 412 V DC Vital ,.attor; Board I 125 V DC Vital Bus 1BD1 D. 120 VAC Vital intruron....t Power Board 1 120 VAC Vital Instrument Bus 1BY1B Ref: 18032-1 Distractor analysis:
See attached procedures which show loads from each of the above boards.
Tuesday, February 25, 2003 07:06:43 AM 53
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 54. 059A4.11 001 After which one of the following events can the feedwater isolation be reset by operating the feedwater isolation reset handswithches puehbuttons without performing any other actions?
A. A spray valve fails open causing pressurizer pressure to drop to 1725 psig. The spray valve is closed and pressure returns to 2235.
B. At 40-75% Rx power, the operator overfeeds a single steam generator to the High-High Level setpoint causing a turbine trip and then clears the High-High Level.
C. A turbine trip from 65% Rx power, causing a reactor trip. Steam dumps open to control Tavg at 557 0 F.
D. A high steam line flow causes a low Tavg and an SI. Main Steam isolation terminates high flow condition and allows Tavg to return to 5570 F.
Ref: Vogtle lo-lp-18201-17C Distractor analysis:
Answers A and D are incorrect because the SI input must also be reset.
Answer C is incorrect because both the FWI switches AND pushbuttons must reset.
Answer B is correct because when only a Hi-Hi S/G level input is present, when it clears, only the pushbutton needs depressing to break the seal-in. See attached logic drawing.
Note: This needs to be discussed with the licensee carefully Tuesday, February 25, 2003 07:06:43 AM 54
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 55. 059AA1.01 001 Given the following plant conditions:
- Plant is operating a 100% power
- Plant systems aligned and operating for normally- at power operation
- RE-1950, Auxiliary Component Cooling Water radiation monitor, is in alarm Which ONE of the following lists the type and process flows that are sensed by the alarming radiation monitor?
A.' Gamma; Thermal Barrier leakage B. Beta; Excess Letdown Hx leakage C. Gamma; RHR Hx leakage D. Beta; RCP Motor Cooler leakage Ref: VG LO-LP-1 6401, LO-LP-04101 Distractor analysis:
- a. Correct - liquid process monitors utilize gamma scintillation detectors. The thermal barrier would give direct leakage path for RCS should it develop a leak.
- b. Incorrect - liquid process monitors utilize gamma scintillation detectors. The thermal barrier would give direct leakage path for RCS should it develop a leak.
- c. Incorrect - liquid process monitors utilize gamma scintillation detectors, but ACCW does not cool RHR hx
- d. Incorrect - liquid process monitors utilize gamma scintillation process monitors utilize gamma scintillation detectors.
Tuesday, February 25, 2003 07:06:43 AM 55
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 56. 059K4.19 00l Which ONE of the following describes the automatic functions which take place on receipt of a feedwater isolation signal due to a reactor trip with T-ave less than 564 degrees F?
A. Main feed pumps trip, main feedwater isolation valves close, main feed regulating and bypass feed regulating valves close, bypass feed isolation valves close B:! Main feedwater isolation valves close, main feed regulating and bypass feed regulating valves close, bypass feed isolation valves close C. Main feedwater isolation valves close, bypass feed isolation valves close, auxiliary feedwater isolation valves close D. Main feed pumps trip, main feedwater isolation valves close, auxiliary feedwater isolation valves close REF:
LO-LP-18201-12-C Tuesday, February 25, 2003 07:06:43 AM 56
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 57. 059K6.09 001 Given the following:
- Unit is at 60% power with both A-and-B MFP's operating in AUTO.
- PT-507, Steam Header Pressure, output begins to slowly drift low.
Which ONE of the following describes the initial effect on the Main Feed Water System, assuming no operator action?
A. Both MFP's discharge pressure begins to increase and all Feed Water Reg valves begin to close.
B. Both MFP's discharge pressure begins to increase and all Feed Water Reg valves begin to open.
Cf Both MFP's discharge pressure begins to decrease and all Feed Water Reg valves begin to open.
D. Both MFP's discharge pressure begins to decrease and all Feed Water Reg valves begin to close.
Ref: VG LO-LP-18001, student text 13A logic diagram Distractor analysis:
C is correct because input from d/p program remains constant because steam flow remains contant. However, PT-507 failing low, causes the d/p actual (as sensed) to increase above program. This in turn causes the speed summer to decrease its output to the speed control station which will reduce feedpump speed and it's discharge pressure. Flow rate will decrease and the FRV's will open to increase flow to the S/G's.
All other answers are incorrect because they are variations of the answer with one parameter going in the wrong direction.
Tuesday, February 25, 2003 07:06:43 AM 57
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 58. 061A1.04 001 Given the following plant conditions:
- The Unit 1 is at 100% power
- CRT lovel is lo lo A loss of off;eit powor 9ocurs
- A loss of both RATs occurs due to a switchyard fault
- The unit is manually tripped
- 1AA02 and 1BA03 are energized by their D/Gs
- during thc event, one of the SIG AARV PORVs stuck opon Which of the following correctly describes the effect this will has on CST level and the actions that will be necessary?
W.hich of tho following states the mnaximum capability of tho CST undor these conditions?
Tho CST supply to the TDAF=W will bo8 suffiient for CST #1 level will:
Af 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followed by a conroll1ed ~eoldown to cold shutdown.
continuously lower requiring manual swap to CST #2.
B. An irmmediate cooldown to hot shutdown.
be maintained by automatic makeup.
C. I hours followed by a conroll1ed ceeldown to hot shutdown.
continuously lower and automatically swaps to CST #2.
D. an imme~diate cooldown to ncold s~hutdown.
remain full until CST #2 level reaches 66%.
Modified from Byron - validated from LO-LP-20101-C,
- a. incorrect - capacity is for a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold then cool to mode 4
- b. incorrect - capacity for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and then cool to mode 4
- c. correct - stand pipe in CST ensures 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold and then cooldown to mode 4
- d. incorrect - capacity to hold for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with cooldown to mode 4 ticnnO A7 l~An AMA 58 T uesday, Feruruu*y 25o, uo*.u.or=,
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 59. 061AA1.01 001 Which of the following area radiation monitors intiate a CVI?
A. ARE-014, Waste Gas Effluent Monitor B! ARE-003, Containment Low Range C. ARE-2533A, Fuel Handling Building D. RE-12117, Control Room Ventilation New- Lesson plan LO-LP-32101-34-C
- a. incorrect - auto isolates gas release but not CVI
- b. correct - 003 initiates a CVI
- c. incorrect - 2533A shifts the FHB to emergency mode, no CVI
- d. incorrect - places control room in emergency mode, no CVi Tuesday, February 25, 2003 07:06:43 AM 59
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 60. 061K5.01 001 Given the following plant conditions:
- The Unit 1 reactor tripped from 100% power
- All systems responded as designed The hoat transfer rate between P05 and the steam gonorators will ...
Which of the following would have the highest heat transfer rate from the RCS to the S/Gs?
Aiincroaso as ROS tomporature incroaGco and AFW flow incrnasos.
Steam Dumps are 50% open; total AFW flow 500 gpm B. "ncroaso as RCS tomporatur stabalizos and AFW flowi Steam Dumps are 25% open; total AFW flow 500 gpm C. inc6rease as ARV tomperaturo incroac and AF.W flowin e.
Steam Dumps are 50% open; total AFW flow 250 gpm D. docroase as AFW tomporature stabalizos a-nd AF flow I, in.r.
Steam Dumps are 25% open; total AFW flow 250 gpm Modified from INPO bank
- a. correct - as the temperature differential increases the heat transfer rate increases
- b. incorrect - as the temperature differential stabalizes the heat transfer rate stabalizes
- c. incorrect - as the temperature differential decreases the heat transfer rate decreases
- d. incorrect - as the temperature differential stabalizes the heat transfer rate stabalizes Tuesday, February 25, 2003 07:06:43 AM 60
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 61. 062A3.05 001 Given-that the following .......-... sequence:
- A small break LOCA occurred which resultinged in a reactor trip and SI.
- The SI signal was reset during the performance of 19010-C, "&-I, Loss of Reactor or Secondary Coolant."
- A loss of offsite power-(L-QP) occurred and the diesel generators loaded as designed.
Assuming no operator actions, which ONE of the following would be the status of the loads on the 4160Vac 1E buses. 6.9kV SD beards?
A. All equipment powered from the 416OVac 1E buses 4160 safety boards with the control board switch in automatic will be restarted.
B. No 41 6OVac 1E bus ..911 SD board loads are automatically restarted.
C.f Equipment normally started during a LOSP will be automatically restarted; Sl and RHR pumps remain OFF.
D. All equipment that was operating prior to the LOSP will be automatically restarted; All running ESF equipment will be reenergized
Reference:
WB bank, validated from VG LO-LP-280201.
Tuesday, February 25, 2003 07:06:43 AM 61
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 62. 062AG2.4.24 001 The crew is in 19100-C, "Reactor Trip or Safety Injection". Prior to the step that the crew places equipment in PTL, the procedure cautions that 2 NSCW pumps should be available to load on each AC Emergency Bus.
These pumps are required to provide cooling for the .........
A. SI pump.
B. MDAFW pump.
C. ACCW pump.
DW EDG Ref: 19100-C Caution Before Step 7 Tuesday, February 25, 2003 07:06:43 AM 62
QUESTIONS REPORT for VOGTLEFINDRFT1028 Unit 1 is at 100% power All Diesel Generators are currently operable Annunciator ALB38-B09, "DG1B ENGINE CNTL POWER B FAILURE", B!0, DG2B DISABLED GEN CONTROL DPWAIR AI IURE just illuminated Which ONE of the following describes the status of the Diesel Generator 2B with this annunciator in alarm?
A. DG2B still has capability to start and load once and is operable.
B. If DG2B was running On-paralel when this occurred it will continue to operate and can be shutdown from the control room. thoer is no affoct but eonc ctopped DG2B must be declared inoperable.
C. DG2B can be started and loaded manually but is inoperable.
Df If DG2B was running in parallol when this occurred, there will be a loss load control, it will continue to operate and can only be shutdown from the front standard. DG2B must be declared inoperable.
Ref: VG ARP 17038-2, window B10Distractor analysis:
A is incorrect because the starting air solenoids need power from the Diesel 125V DC.
B is incorrect because the voltage regulator and governor are out of the droop circuit C is incorrect because the field flash is inoperable.
D. is correct Tuesday, February 25, 2003 07:06:43 AM 63
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 64. 065AA1.03 001 Unit 1 just experienced a loss of air and entered AOP 18028-C, "Loss of Instrument Air" The header pressure is 70 psig. Given the current conditions, what action, per procedure, should be taken by the operator to prevent inadvertent operation of equipment repositioned due to the loss of air?
A. Because pressure is less than 80 psig, verify the cask loading pit gate seal assemblies are supplied with bottled nitrogen > 50 psig.
B. Because pressure is less than 80 psig, ensure the control to aux air ise valve 0 FQV 32 82 PV-9375 "Service Air Header Isolation Valve" is open.
C. IfMSIVs closed due to low air pressure, place the MSIV hand switches to closed.
D. Ifnormal letdown had not isolated due to low pressure, place the normal letdown isolation switches in open.
New - ref: AOl-10, Loss of Air.
- a. correct - 18028-C, step A3 requires nitrogen bottle alignment to cask loading seals
- b. incorrect - less than 80 psig, ensure the control - to - aux air isol valve 0-FCV-32-82 should be closed
- c. incorrect - procedure gives no guidance to msiv handswitch placement
- d. incorrect - normal letdown isolation switches fail closed
- .. nnnnn7.fl.AQ ALA 64 T uesday, F-ebruary 25, 400o 01:06:o ,v
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 65. 067AK1.02 001 There is a fire in the generator hydrogen cooling system. Fire fighting efforts have cause the fire main header pressure to lower. Which ONE of the following will cause the FIRST diesel driven fire pump to start automatically?
A fire header pressure of .......
A. 85 psig.
B! 95 psig.
C. 105 psig.
D. 110 psig.
REFERENCE VEGP LO-LP-43101-07-C, pg. 33, LO 9.
Tuesday, February 25, 2003 07:06:44 AM 65
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 66. 068AK3.18 001 Evacuation of the Control Room is required due to a Control Room fire.
The actions of AOP 18038-1, "Operation From Remote Shutdown Panels," prior to evacuating the control room, include which of the following?
A. Trippiig the both main feedwater pumps.
B. Ensure S/G pressure control in AUTO C. Place the PZR pressure control in AUTO D. Trip al RCPs 1 2 and 3 Ref: VG AOP 18038-1, steps 1 - 4
- b. incorrect, this is done if there is NO control room fire
- c. incorrect - this is done if there is NO control room fire
- d. incorrect, only RCP 1 and 4 are tripped T. = k r 000307*9A4 OrA AMt 66 IuUsuay, erFluaIy CJ, C..vvJJ'J,
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 67. 068K1.07 001 Which one of the following describes how the incore instrumentation seal table leakage enters the Liquid Rad Waste system?
A. Drains to Reactor Cavity Sump, and then is pumped to the Waste Holdup Tank.
B. Drains to the floor drain, overflows into the Reactor Cavity Sump, and then is pumped to the Waste Monitor Evaporater Holdup-Tank C. Drains to the floor drain, overflows into the Reactor Cavity Sump, and then is pumped to the Waste Holdup Tank D. Drains to Reactor Cavity Sump, and then is pumped to the Waste Monitor EvaperatG Holdup Tank.
Ref: Vg drawing 1x4db143 (e-1)
NEED LESSON PLAN ON DRAINS AND SUMPS See see drawing Tuesday, February 25, 2003 07:06:44 AM 67
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 68. 068K6.10 001 Which ONE of the following would require termination of the release of Unit 1 Waste Monitor Tank (WMT) # 10 ?
AZ' 1-RE-0018 fails high B. 1-RE-039A fails high C. ARE-0014 fails low D. 1-RE-039A fails low VG Bank, changed distractors, A. correct - this is the monitor that actually monitors liquid releases B- D do not monitor liquid releases and would not isolate liquid release if alarmed Tuesday, February 25, 2003 07:06:44 AM 68
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 69. 069AK2.03 001 Unit 1 is at 100% power.
- Operation personnel enter Containment for.a preoutage walkdown
- The inner door is discovered ajar with a broken latch.
Annuciator UP1R CNT-MT AIRLOCK INNER'OUTER alarmed forF no apparent reason; on the previous shift. Operation personnel were dispatchod to investigate tho alarm. They ropofted that they opened the outer door and found tho inner door ajar with a brcken latch.
Which ONE of the following describes the correct actions required by technical specifications?
ACVerify the outer door closed within one hour and document thgu ecniifTr Close the outer door within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. Repair the inner door within ono hou--r and lock the outer door within 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />.
Close both doors within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Close the outer door within one hour and lock< the outer door within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-.
Place the unit in mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. Commence plant shutdown within one hour and be in Mode 5;within 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />.
Commence a unit shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and apply LCO 3.0.3 Ref: VG Tech Specs need correct window Distractor analysis:
A is incorrect because the ts action does not address logging tracking items B is incorrect because there is no requirement to repair the inner door within one hour.
C is correct per Tech Specs 3.6.2 condition A.
D is incorrect because there is no requirement per AOI 12 to commence shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
-- rL ----. n rrofVfCAA A ARA 69 Tuesday, r-bu aru*y 45, 400 .,.:..
- l ~~
QUESTIONS REPORT for VOGTLEFINDRFT1 028 "70J n171lvannl Chemistry has taken a grab sample of the release in progress from the gaseous radwaste system. The results indicate that the release is above the release permit setpoint 10-GFR-2 mt-s. Which one of the following caused this?
A" Waste Gas effluent monitor, RE-14, failed low.
B. Waste Gas effluent monitor, RE-14, failed high.
C. A loss of 125 VvDC power to radiation trip valve, RV-0014.
D. A loss of instrument air to radiation trip valve, RV-0014 Ref: VG LO-LP-46101 LO -11, text 17c, pg 14 Tuesday, February 25, 2003 07:06:44 AM 70
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 71. 072A1.01 001 ARE-2532A and ARE-2533A are indicating increasing levels of radiation.
Ifthis trend continues which of the following should occur?
A. Only the Train A FHB isolation dampers close, the supply unit trips but the post-accident filter unit does not start.
B. The AREs will alarm locally and in the control room, causing normal FHB HVAC units all F=HBIHVAG to trip and isolate on an intermediate alarm from both monitors.
C. Only the Train A supply and exhaust dampers isolate, supply and exhaust units continue to run and the post-accident filter units start.
DW Train A and B supply and exhaust dampers isolate, the supply and exhaust units trip on low flow, and the post-accident filter units start on a high alarm from either monitor.
VG LO-LP-23301, LO-LP-32101-C
- a. incorrect because signal is 1/2 all dampers isolate
- b. incorrect - supply unit trips
- c. incorrect - the post accident unit will start
- d. correct - FHB normal supply and exhaust dampers isolate, supply and exhaust units trip and filter units start Tuesday, February 25, 2003 07:06:44 AM 71
QUESTIONS REPORT for VOGTLEFINDRFT1028 00l
- 72. 072G2.1.28 001
- 72. 072G2.1.28 RE-0019, 0020 and 0021 are in alarm. Waste Water Retention Basin Valve RV-0021 and SGBD Demin Isolation Valve I4FV-1 150 have just closed.
Which equipment caused the closure?
A. RE-0019 Only B. RE-0020 Only C. RE-0021 Only D. The Combination of both RE-001 9 and RE-0020 Ref: LO-LP-24101 Learning Objective 9 EXPLAIN THE PURPOSE OF RAD MONITORS RE-0019 AND RE0021:
RE-001 9 Measures radiation levels of Blowdown fluid upstream of demins - Alarms and indication only RE-0021:
Measures radiation levels of Blowdown fluid downstream of demins Isolates blowdown flow to Waste Water Retention Basin by closing RV-21 and HV-1 150 on high radiation alarm. Also gives indication of valve position.
Tuesday, February 25, 2003 07:06:44 AM 72
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 73. 073A2.01R 001 Given the following:
- Unit 1 is at 100% power
- a liquid waste release is in progress.
- A,.nnu-ciator ALB 05, window G93, The HIGH RADIATION ALARM, alarms is lit.
-Looking at the Prococc and Effluo-nt Radiation Monitnorn Sytmaamei tdtorrminod
-- that- -RE-0018 spiked to high alarm due to an erractic power supply, and is now decreasing to less than backgound.
Which ONE of the following describes the initial required actions by the control room operators?
A. Have the detector assembly cleaned.
B. Notify RADCON to take radiation readings in the detector area.
C. Verify liquid rad waste release valve 1-RV-0018 is shut.
D. Initiate a work order to repair 1-RE-0018.
Ref: VG Io-lp-32101, ARP 17100-1ARP 17005-1 Distractor analysis:
A is incorrect because there is no guidance to clean the detector although low readings could be the result of fouling.
B is incorrect due to no guidance to confirm that areas readings are suddenly less than typical background D is correct based on the guidance in the ARI and the philosophy to secure releases to the environment when process monitors fail.
D is incorrect as an initial action although ultimately the detector will need repair at a later time.
Tuesday, February 25, 2003 07:06:44 AM 73
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 74. 075A4.01 001 An operator making rounds reports that 1-TI-1712, which measures the NSCW temperature at the outlet of the CCW Hx is reading 204 degrees F and suspects that it is broken.
Which one of the following describes how this can be verified in the control room?
A. Use D/G jacket water inlet temperature since this is essentially the same temperature as the CCW Hx outlet temperature.
B. ACCW Hx outlet temperature can be used, a table is available to convert the indicated temperature.
Cf Use the IPC since redundant information is available on the IPC at peint T2607.
D. CCW Hx and ACCW Hx flow can be used since a nomograph is available to convert the indicated temperature.
Ref: procedure 13150, step for setting additional jacket water Hx NSCW flow.
Tuesday, February 25, 2003 07:06:44 AM 74
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 75. 076K2.08 001 AAIL.:-d-. ý ."--91ý 4k"- -h -. - -*- ;-. A CfXl'tIJZ 0 1 --- rflrt,,nnn iC Coolor Supply?
Which one of the following describes the power supply for containment coolers 7 & 8 NSCW Supply Valve (HV-1809)?
A. 1890 V Roacnt**r AM1OV BRoar 1B2 B 480 Vac switchgear 1AB1 6 B. 480 V Shu4tdownh-, Beard 1B2 B 480 Vac switchgear 1NB21 C 4180 V Roactor MOV Board 2B1 B 480 Vac MCC 1 BBD D. 480 V Shutdown Board 1B4 B 480 Vac MCC 1NBM Ref: WB Lesson Plan 3-OT-SYS067A, no specific learning objective Dwgs: 1-45W760-67-5 1-45W751-11 1-45W749-4 1-45-W724-2 Distractor Analysis:
A is correct based on attached dwg's.
B and D are incorrect because the 480 V shutdown board does not directly feed any MOV's C is incorrect because they have unit 2 designators.
Tuesday, February 25, 2003 07:06:44 AM 75
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 76. 078G2.4.11 001 Given the following conditions:
- Plant in Mode 3.
- Total Loss of Instrument Air has occurred.
- The RO QAG reports that Pressurizer level is 92% and slowly rising.
- COB is in coricoe with flow to, the RDP thermal ba..roe.
Which ONE of the following actions should be taken to control Pressurizer level per 18028-C, "Loss of Instrument Air"?
A. Locally isolate charging and letdown and place excess letdown in service.
B. Stop CCPs until PZR level is less than 70% then cycle a CCP on and off to maintain PZR level between 65 and 70%.
C. Locally Isolate charging until PZR level is less than 70% then adjust-then locally operate 1FHC-0121 4.FGV 62-93 to control charging flow.
D. Place the reactor Head Vent System in service, adjust head vent flow valves to desired letdown rate.
Ref: VG- AOP 18028-C, step B13 Distractor Analysis:
A is incorrect, the procedure does not direct placing excess letdown inservice B is incorrect, no procedural guidance to cycle charging between 65% and 70 %
C is incorrect, no procedural guidance to locally operat FCV D is correct per 18028 section B step B13 Tuesday, February 25, 2003 07:06:44 AM 76
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 77. 079K4.01 001 If Station Instrument and Service Air System air pressure is dropping, the Twtne Building-Service Air System automatically isolates from the Instrument Air System when pressure drops below which ONE of the following?
AT 80 psig.
B. 100 psig.
C. 78 psig.
D. 70 psig.
Ref: WB Exam Bank, VG lo-lp-021 1lDistractor analysis:
A is correct, see lesson plan pp. 33 (attached)
B is incorrect, corresponds to service air header lo pressure alarm C is incorrect, doesn't correspond to any auto event D is incorrect, instrument air lo pressure Tuesday, February 25, 2003 07:06:44 AM 77
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 78. 086G2.4.25 001 During the response to a fire in the turbine building, an injured person must be transported off site. The only safe way to transport this person is via the Turbine Building elevator. The elevator is locked out. According to procedure 92005-C, which one of the following persons can authorize the use of 1q7403A-G,4efrthe elevator during the fire fire scrVico rcoall?
Aý Fire Team Captain, only B. The Unit Shift Supervisor of the affected unit, only C. Any Fire alarm response Team Member D. The Burke County Emergency Management Agency Ref: If the fire team captian has determined it is safe to use the elevator(s), and the elevator is locked out, it may be necessary to reference proc. 17103A-C for the elevator fire service recall section it ..... A,. O Ck lfnnl n7fl7-fIA AA,,A 78
, uesd;aiy, Ferluaury ,:~ILU /,u'"",,~
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 79. 1A3A2.03R001~
Given the following conditions for Unit 1:
- Safety Injection has actuated
- The crew is performing 19000-C, "E-0, Reactor Trip or Safety Injection", when the RO notes that Containment Pressure is 23.2 psig and Containment Spray has not actuated.
Which ONE of the following describes the minimum action(s) required?
Af Manually actuato either Phase A manual handewitchoc and manually start tho Containmont Spray pumps.
Manually actuate both containment spray handswitches B. Must manually actuate both Train A manual handswitches and manually start the Containment Spray pumps.
C. Manually actuate either Phase A manual handswitches and manually shut the MSIV's and bypasses.
D. Must manually actuate both Train A manual handswitches and manually shut the MSIV's and bypasses.
Ref: VG procedure 19000-C, LO-LP-28103, drawing 7243D07 Need licensee to check switch name and common title use (is it called phase B on the board or how are the switches designated)
Distractor analysis:
Get Vogtle to review this closely for terminology and accuracy, (what handles the the valves other sites control with Phase B?)
Tuesday, February 25, 2003 07:06:44 AM 79
QUESTIONS REPORT for VOGTLEFINDRFT1028 R0. G.1.2f001 Given the following indications on Unit 1:
Stoam gonorator tuba rupturoe has occurrod and you aro podor~ming ac*tios Of 9030 C (SGTR)
- 19030-C, SGTR is being implemented Roactor istrippod and powor is in tho courco rango
- Both CCPs and both SIPs are running PFroscur izor lovol is 10%and falling slowly
- RCS pressure 1350 psig and falling slowly
- Level in S/G 1 is 80% NR rising slowly
- Level in other S/Gs is 5% NR rising slowly
- MSIVs are open
- RCS temperature is 558 degrees F and rising slowly Which ONE of the following describes the action to be taken and the basis for that action?
A. Dump steam at the maximum rate to cooldown the RCS.
B. Isolate SG#1 to minimize RCS cooldown.
C." Stop all RCPs because RCP trip Criteria have been met prior to initiation of RCS cooldown.
D. Stabilize the level in intact S/Gs to preserve a heat sink for cooldown.
- REFERENCE .
LO-LP-37311-08-C, Objective 10, RCP Trip Criteria is met Tuesday, February 25, 2003 07:06:44 AM 80
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 81. G2.1.3 001 An procedure writer In6stot-with an active RO license is in the control room to review a mate.ia.... procedure revision an upcoming walkthrough oxamination. The RO QA_ G is called for a random drug test. The RO QATG requests that the procedure writer relieve him for about 15 minutes for the drug test.
Which one of the following describe the shift relief requirements for this situation?
The procedure writer instruetor-mayr--relieve the RO QATG provided...
A ... the procedure writer 6nstrueten reviews the narrative logs, rounds sheets, and checklists for his station. The review shall include narrative logs since the last shift worked or the preceding 3 days, which ever is longer.
B ... the procedure writer inuetrotor-and the on-shift RO QATG independently walk-down their assigned control boards to verify checklists items and discuss equipment status.
C. ..up to 15 m providod that a) the relieving operator is knowledgeable of plant
.inutoc conditions, b) they perform a joint walkdown of applicable control panels, and c) the Unit Shift Supervisor acknowledges the relief.
D. ..... however, a full turnover is required as described in procedure 10004-C, Shift Relief.
Ref: Surry exam 2002, VG 10004-C section 4 NEED to check this closely - does it matter if the relieving RO is the BOP or assigned plant tours Tuesday, February 25, 2003 07:06:44 AM 81
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 82. G2.1.32 001 Which ONE of the following describes the normal configuration of the Component Cooling Water system and the reason, respectively?
A. 2 pumps running, one pump in pull-to-lock, to prevent CCW Hx tube vibration damage from excessive flow rates.
B. 2 pumps running, one pump in pull-to-lock, to avoid system pressure exceeding relief setpoints C. 2 pumps running, one pump on standby, to avoid system pressure exceeding relief setpoints D. 2 pumps running, one pump on standby, to prevent CCW Hx tube vibration damage from excessive flow rates.
Ref: VG proc 13715-1 Distractor analysis:
C is correct, see P&L A,B, and D are incorrect due to pump in pull-to-lock or wrong reason.
Tuesday, February 25, 2003 07:06:45 AM 82
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 83. G2.2.12 001 Unit 1 is at 100%
Surveillance 14905-1, RCS Leakage Calculation (Inventory Balance) is in progress 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since commencing data collection Final readings indicate that tho total RCS leakage rate is 0.08 gpm W..hich 0ONE Of tho following doscriboc tho corerec action to be taken?
Which ONE of the following would invalidate the leak rate calculation?
A' Sign the cur.iollance as satifactor RCS diluted 50 gallons to raise RCS temperature back to program B. Contfinue data, collection for an additional hour Main turbine load reduced 5 MWe to prevent exceeding allowed power limits.
C. Void tho cur.'eillanco and pedoerm at A lator timoA Control rods inserted 5 steps for AFD control.
D. investigate to determnine the source of inleakago to the ROS ECCS accumulator filled with an SI pump due to a slow leak Ref: Vogtle 14905-1 pg 2 A is incorrect because data must be collected for at least an additional hour before the surveillance can be termed complete B is correct, see SI-68-32, pp. 16 & 17 C is incorrect because it is contrary to procedure guidance D is incorrect - surveillance already considers normal inleakage calculations Tuesday, February 25, 2003 07:06:45 AM 83
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 84. G2.2.22 001 Using the reference provided determine which one of the following sets of conditions represents a violation of a technical specification safety limit and required action?
A. Power = 10%, Pressure = 2400 psig, Tavg = 6550 F, restore to within limits OR be in Mode 3 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0
BW Power = 80%, Pressure = 2250 psig, Tavg = 640 F, restore to within limits AND be in Mode 3 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0
C. Power = 10%, Pressure = 2400 psig, Tavg = 655 F, restore to within limits in 2 hrs or be in Mode 3 in 6 hrs 0
D. Power = 80%, Pressure = 2250 psig, Tavg = 640 F, restore to within in 2 hrs or be in Mode 3 in 2 hrs Ref: Modified from TP 2000, validate VG TS 2.0 Distractor analysis:
A and C are incorrect because they are within limits and no action required D is incorrect, because even though it is out of limits, it must be restore within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is the DNB parameter spec.
B is correct because it is both out of limits and has the correct required action per TS I A I ~ te ~
iC 2003' t~... 07:06:4 AM 84 ue attL*y, r*u ar~y C.,, --*' .1,.* -- , ll
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 85. G2.2.3 001 Which one of the following decribes the Plant Integrated Computer (IPC) terminals?
They are in mirror image locations. The IPC terminals are identical except that the .....
A. common radiation monitors go to Unit 2 only and weather data goes to Unit 1.
B. common radiation monitors go to Unit 1 only and weather data goes to Unit 2.
Cf both, the common radiation monitors and weather data go to Unit 1 only.
D. boththe-common radiation monitors and weather data go to Unit 2 only.
Ref: 61300 The IPCs do not have common inputs to Unit 2, so both, the common radiation monitors and weather data go to Unit 1 only.
Tuesday, February 25, 2003 07:06:45 AM 85
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 86. G2.3.1 001 Which one of the following dose components are combined in a Radiation Worker's Occupational Dose?
A. Total Effective Dose Equivalent and Planned Special Exposures.
B. Planned Special Exposures and Committed Effective Dose Equivalent.
C. Total Effective Dose Equivalent and Committed Effective Dose Equivalent D. Deep Dose Equivalent and Committed Effective Dose Equivalent.
Ref: Surry exam 2002, VG lo-lp-63920 Tuesday, February 25, 2003 07:06:45 AM 86
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 87. G2.3.4 001 Given the following plant conditions:
A LOCA occurred and a Site Area Emergancy was declared.
T-ho TSC And OSO havo boon activatod.
It is recommended that entry be made into the Safety Injection Pump Room 1A to determine why the pump will not start.
Projected dose rate in the pump room is 1.16x10 5 mr/hr.
Duration of the exposure is expected to be 3 minutes.
Which ONE of the following is required to may authorize this exposure?
A. EOF Manager B. Operations Support Center Manager C. Health Physics Supervisor D. Emergency Director
REFERENCES:
WBN Exam Bank, VG proce 91102-C, 91301-C Exposure calculates to be 5.8 rem/hr, greater than 10 CFR 20 limit for any ONly the Emergency director can approve exposures that exceed the 10 CFR 20 limits Tuesday, February 25, 2003 07:06:45 AM 87
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 88. G2.3.9 001 Given the following conditions:
- Unit 1 is in Mode 2 following a refueling outage
- Containment Mini-Purge System was placed in operation for ALARA considerations in preparation for maintenance personnel to make a containment entry.
- Maintenance has requested the Mini-purge system be shutdown prior to entry to reduce noise levels while they perform their activities.
- Tho Shift Manager hat directed that tho Containment Purgo System boeouo i~n acconrdance 131:25 1, Containment Purgo System.
Which ONE of the following should be considered prior to securing Containment Purge?
A. Outside air temperature and pressure B. Containment humidity C. Containment rRadiological impliatinsc*onditions D. Containment Purge HEPA and Charcoal filter DP Ref: VG Procedure 13125-2 Distractor analysis:
A and D are incorrect because they only apply while the system is in service B is incorrect, because it only applies when placing the system in service C is correct because changes in ventillation, particularly reduction in ventillation can have adverse affects on radiation levels. This is also a precaution in the procedure related to securing CTMT purge. (see below)
Caution in procedure:
For ALARA and respirable air quality, the Mini-Purge System should be placed in service approximately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to planned containment entries. After work is complete and all personnel have exited containment, the Mini-Purge System should be shut down.
Tuesday, February 25, 2003 07:06:45 AM 88
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 89. G2.4.1 001 Given the following events:
- Unit 1 reactor trip
- Operators enter 19000-C and observe the following conditons on step 3
- 1AA02 is deenergized due to a bus fault
- 1B-DG suppling 1BA03
- 1BB06 feeder breaker trips during load sequencing Which of the following would describe the correct actions to take?
Unit 1 just had a loss of all AC powor. Wfhich one of tho following doscriboc your roguirod actions?
Enter 19100 C, then vorify roactor and turibino trip, thon ..
A. .. start a diosol gonorator, verify AC omr~egoncy bus of tho started DIG automnatically one rgized.
Remain in 19000-C on step 3 until power is restored to 1BB06 B.c..hock if ROS is isolated, and verify AFW flow is greater than 57-0 gpmn.
Transition to 19100-C "LOSS OF ALL AC POWER" C.t..ransition to 10100 G, than start a diesel gonorator, and Vorit' AC emergency bus of tho started DIG automatically .n.rgizod* .
Perform 18031-C 'LOSS OF CLASS IE ELECTRICAL SYSTEMS" in parallel with 19000-C Df ...transi*tion to 19100 C, then chock if RCS isioaeand verify AFW flow is greater than 5:70 gpm.
Continue in 19000-C while trying to restore power to 1AA02 and 1BB06 ref - VG 19000-C, 19100-C, lo-lp-37031 19100-C is entered directly, and the awf is verified after the reactor and turbine trip prior to attempting to address the DGs The first two IMMEDIATE OPERATOR ACTIONS required by procedure 19100-C, Loss of All AC Power (ECA-0.0) are:
" "Verify Reactor trip and Verify Turbine trip".
Which ONE of the following describes the remaining step(s).
- d. Check SGs secondary pressure boundaries, verify if CST is isolated from hotwell Tuesday, February 25, 2003 07:06:45 AM 89
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 90. G2.4.11 001 Unit 1 is at 100% power operating in 18009-C "STEAM GENERATOR TUBE LEAK" Action Level 1, with known leakage in SG #2 of 0.0gpm 72 GPD.
Leakage is being monitorod validatod by chcmnictr,, sampling over; 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
RE-724 & RE-810 both indicate leakaqe increased to 86 GPD and has remained constant for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Chemistry sampling confirms the radiation monitor trends.
The chomi-try por.onn.l reports that tho sample at 1300 hr, indicatod loakago is 0.06 (86 GIRD), up from 0000 hrc cample indication of 0.05 gpm loakago.
Which ONE of the following should be performed?
Reference provided A. Be in Mode 3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Reduce load to hot standby within 2 hrs, then cooldown and depressurize the RCS.
C. Trip the reactor; enter E-0, then transition to E-3.
D. Convene PORG PRB to evaluate continued operation.
VG 180049-C, Distractor analysis:
A is correct per step B3 RNO and caution prior to step (unstable leak rate change of > 10%)
B is incorrect the 2 hrs is the action for a leakage of 30 gpd/hr C is incorrect because 0.6 is well within charging capability which is the decision point for E-0 D is incorrect because it is the action for leaks less than 0.05 per day Tuesday, February 25, 2003 07:06:45 AM 90
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 91. G2.4.16 001 While in the Emergency Response procedures the team is directed to "Go To" another procedure, which one of the following is the correct implementation of this action?
A. The "GO TO" implies the procedure in use is still not applicable, and therefore any tasks in progress need not be completed.
B. The original procedure remains applicable because tasks still in progress must be completed prior to the transition directed by the "GO TO" step.
C' The "GO TO" implies the procedure in use is no longer applicable, transition to the new procedure but any tasks in progress should be completed.
D. Tasks still in progress need not be completed prior to the transition directed by the "GO TO" step, unless preceded by a note stating otherwise.
Bank: From Surry 2002, Vogtle proc. 100012 Distractor analysis:
Answer C is correct, Answer A and B are incorrect due to timing or required completion Answer D is incorrect because double astericks relates to high and low level steps vice transitions.
Tuesday, February 25, 2003 07:06:45 AM 91
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 92. G2.4.8 001 Unit 1 Is rosponding to a Reactor Trip and Safety Injection Unit 1 new has the following symptoms:
- Reactor is tripped
- core exit TC temperatures greater than 1200 Frand
- a-RVLIS full range indication is 25%lecs than 3 1/2 feet above the bo..om of the .ative fuel Which ONE of the following are your required actions?
Enter 19221-C FA GA, Response to Inadequate Core Cooling, from one of the two A. Orange paths. frm Critical Safety Function Statue Tree, F 0.2 on Core Cooling, and
- 1) Reinitiateieonef high pressure safety injection
- 2) Rapidly depressurize the steam generators
- 3) Restart RCPs and/or opening PRZR PORVs B. Orange paths*f rm C S.afety Function Statue Tree, = 0.2, on Core Cooling, and
.ritical
- 1) Reinitiateien-ef-high pressure safety injection
- 2) Slowly depressurize the steam generators
- 3) Stop all running RCPs and open PRZR PORVs C. Red paths fro . Saf Critical Function Status Tree, F 0.2, on Core Cooling, and
.ty
- 1) Reinitiateien-ef-high pressure safety injection
- 2) Rapidly depressurize the steam generators
- 3) Restart RCPs and/or openieg-PRZR PORVs D. Red paths from Critical Saf.ety Function Status Tree, Fm 0.2, C on Core Cooling, and
- 1) Reinitiateienoef-high pressure safety injection
- 2) Slowly secondary dopressurization Slowly depressurize the steam generators
FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, has been developed to address the symptoms for inadequate core cooling.
The basis for these symptoms can be found in the Critical Safety Function Status Tree background document, F-0.2, CORE COOLING.
The guideline is entered from F-0.2 on either of two RED priorities. The major actions to be performed in this guideline include:
- 1) Reinitiation of high pressure safety injection
- 2) Rapid secondary depressurization
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 93. WE02EK1.2R 001 Depressurization," is used following a LOCA event in 1901 19012-C, 'Post LOCA 2-0, "Post Cooldown and LOCA Cooldown and Depressurization," is used following a LOCA event in which the RCS remains at pressure, and it is determined that ..........
A.X SI termination criteria cannot be met or maintained.
B. SI termination criteria have been met and can be maintained.
C. the possibility of core voiding needs to be prevented.
D. a pressurized thermal shock condition is imminent.
REFERENCE LO-LP-37112-07, pg. 6
REFERENCES:
ES-0.2; ES-0.3; Modified INPO exam bank question 10CFR55.43.5/45.13 RO-N/A SRO-22 Tuesday, February 25, 2003 07:06:45 AM 93
QUESTIONS REPORT for VOGTLEFINDRFT1 028
- 94. WE03EK2.2 001 Given the following plant conditions:
- A small break LOCA has occurred.
- RCPs have been tripped.
- Appropriate actions in accordance with 19000-C & 19010-C E 0 and E 1 have been completed.
- RCS pressure is stable at 1525 psig.
- ECCS is operating in cold leg injection mode.
Which ONE of the following statements describes the primary method of decay heat removal at this time?
A. Heat transfer between the RCS and the S/Gs due to natural circulation flow.
B. Heat transfer between the RCS and CCS via the RHR Heat Exchangers.
C. Heat transfer from the injection of water from the RWST and the removal of steam/water out of the break.
D. Heat transfer from Reflux boiling in the S/Gs.
Ref: WB bank, VG 19000 Distractor Analysis:
A is correct because due to the thermodynamic ? H between the primary and secondary and resultant heat transfer rate will exceed the heat transfer into the injection flow water.
B is incorrect because CCS flow is isolated from the RHR Hx's at this point in the accident.
C is incorrect same as A D is incorrect because at this point in the accident the S/G U-tubes are still filled with water.
Tuesday, February 25, 2003 07:06:45 AM 94
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 95. WE05EA1.3 001 Given the following plant conditions:
Unit ic;oporating at 100% power at EOL.
- Tctal loes of f odw*v.ator
.ccurs and operators are implementing 19231 -C, "FRIH4, Response to Loss of Secondary Heat Sink".
No moans of f.odwator addition is available and the operator-s.h..
-4eiiated-RCS feed and bleed is required Manual Safety Injection was initiated and when the operator attempted to open the pressurizer PORVs, PORV 455 failed to open.
Which ONE of the following describes the correct operator mitigation strategy to respond to this problem?
A. Stop one Centrifugal Charging Pump to reduce loss of inventory through PORVs.
B. Close any open Pzr PORV to conserve RCS inventory and return to the steps to re-establish Main Feedwater.
C. Open the reactor head vents to reduce RCS pressure since one pressurizer PORV may not provide sufficient heat removal capacity.
D. Verify PORV 456 and it's block valve open to reduce RCS pressure since 1 Pzr PORV provides adequate heat removal capacity for a loss of heat sink.
Ref: WB lesson plan 3-OT-FRHOO01, obj. 9 & 10 Distractor analysis:PORV a.
Incorrect - one PORV is not sufficient to provide adequate heat removal.
- c. Correct - increases the bleed path capability and reduce pressure to ensure the core remains cooled.
- b. Incorrect - procedure directs bleed and feed not depressurizing a SG which would be a less effective cooling method.
- d. Incorrect - more bleed path capacity is needed to ensure pressure reduction and cooling capability, not less injection.
Tuesday, February 25, 2003 07:06:45 AM 95
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 96. WE07A2.02R 001 Given the following plant conditions:
- The Unit has tripped from 100% power with a LOCA in progress
- Pzr pressure is 1700 000 psig
- RCPs are tripped
- Core Exit thermocouples indicate 720 degrees F
- RVLIS full range indicates 36%
Which of the following describes the conditions existing in the core as applicable to the EOPs?
A. Saturated conditions, which does not present an imminent extreme challenge to the fuel matrix and fuel cladding as long as the hot leg temperatures remain at saturated conditions.
B. Super heated conditions, which does not present an imminent extreme challenge to the fuel matrix and fuel cladding as long as the cold leg temperatures remain at saturated conditions.
C. Saturated conditions, which present an iMmineRt extreme challenge to the fuel matrix and fuel cladding.
D. Super heated conditions, which present an imrninent extreme challenge to the fuel matrix and fuel cladding.
WB bank - validated on steam tables
- a. incorrect - not saturated conditions
- b. incorrect - is super heated but does challenge the fuel matrix and fuel cladding
- c. incorrect - not saturated conditions
- d. correct - superheated conditions that present a challenge to fuel matrix and cladding Tuesday, February 25, 2003 07:06:45 AM 96
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 97. WE08EA2.IR 001 Step 1 of 19241-C, "FRP-4*, Response Imminent Pressurized Thermal Shock Condition", has the operator check: that ROS preo..ur is gr.ator than 300 psig.
- RCS pressure < 300 psig
- RHR flow > 500 gpm This step is based on:
A. pFrovnting implementation of actions in FR PA1 ifa largo break iLOA has occu..rrod.
preventing implementation of 19241-C because a large break LOCA is in progress B. ensuring adequate low head safety injection cooling prior to isolating ECCS accumulators GLAs.
C. preventing core exit temperatures from exceeding the required temperature to place RHR in service.
D. ensuring RHR system is in service to provide adequate mixing in the cold leg downcomer region.
Ref: WB Lesson Plan 3-OT-FRPOO01, obj. 9,WB Bank, validated against Vogle proc 19241-C Answer A is correct, see attached lesson plan.
Tuesday, February 25, 2003 07:06:45 AM 97
QUESTIONS REPORT for VOGTLEFINDRFT1028
- 98. WE1OEA2.2 001 Given the following plant conditions:
Tech Spec action statement requires the unit to be in mode 4 within 60 minutes Reactor trip occurred with subsequent loss of RCPs.
Operators have implemented 19002, "ES-. , Natural Circulation Cooldown".
A cooldown rate of 50 25°F/hour has been established.
Current RCS temperature is 450°F ORCS dopresurization has been initiated wholo mraintainingrubooling.
ý' 1650F.
-Operators are monitoring PZR level and RVILIS for void formation.
I,-. CAC' ýk+ko Ine-4
'M n..nn' *l fl p.,,n'ý. . ~r~fl---it,.
mnr'nI.
Which ONE of the following describes the appropriate procedural actions to comply with the Tech Spec action statement?
A. Stop the cooldown and remain in 19002, "ES-0.2, Natural Circulation Cooldown".
B. Raise the cooldown rate and remain in 19002, "ES-0.2, Natural Circulation Cooldown".
C. Transition to 19003-C, "ES-0.3, Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS)" and LOWER-lewei the cooldown rate.
D.Y Transition to 19003-C, "ES-0.3, Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS)" and RAISE raise-the cooldown rate.
Ref Inpo quest, validated for VG - 19002, 19003
- a. Incorrect - loss of CST inventory should cue the examinee that transition to ES-0.3 is appropriate. Examinee may believe stopping cooldown is appropriate to conserve inventory.
- b. Incorrect - loss of CST inventory should cue the examinee that transition to ES-0.3 is appropriate. Examinee may believe raising cooldown rate would be appropriate in order to reach RHR conditions sooner however ES-0.2 does not provide instruction to do this.
- c. Incorrect - loss of CST inventory is an appropriate condition to require transition to ES-0.3 since more rapid cooldown rate is allowed while addressing voids in the RCS. Examinee may believe it is necessary to lower cooldown rate to conserve inventory.
d.. Correct - loss of CST inventory is an appropriate condition to require transition to ES-0.3 since more rapid cooldown rate is allowed while addressing voids in the RCS.
REFERENCES:
ES-0.2; ES-0.3; Modified INPO exam bank question 10CFR55.43.5/45.13 RO-N/A SRO-22 Tuesday, February 25, 2003 07:06:46 AM 98
QUESTIONS REPORT for VOGTLEFINDRFT1028 Og wnhllmA1 :mO1 Given the following plant conditions:
- Reactor trip and SI occurred on Unit 1 due to a small break LOCA.
- Crew has transitioned from 19013, "ES, 1.3, T*rn-for to Cold Log Rocircu-lat!n", to 19111. "ECA-1.1, Loss of Emergency Coolant Recirculation", due to the failure of both RHR sump suction valves to open.
- Crow; hat.F reduc-ed ECCS flow to 1 COP per step 11 of EGA 1.1.
- Current RCS conditions are 400°F and 700 psig
- RWST level is 10%
-F8 Cro ispodorming Stop !@ of EGA :1.1 to chock( makeup flow adequate and. o~bcr.'oc the follwing idctos Ne ROP. runnin RVIIS full range - 60% and slowly dropping Which one of the following lists the correct operator action for this condition?
A. Ensure Additional makeup source to RWST hat boon alind Reduce ECCS to one train B!ý Conrol charging to raise makeup flow-.
Stop all ECCS pumps C. Place RHR shutdown cooling in service.
D. Slowly dtepreCSuize acm to irjost CLAs.
Isolate the ECOS accumulators Ref: WB bank - validated for Vogtle, Procedures 19011, 19111 Per procedure Tuesday, February 25, 2003 07:06:46 AM 99
QUESTIONS REPORT for VOGTLEFINDRFT1028 100. WE 13EK3.2R 001 During tho por~fomanco of FR H.2, "Ros'ponso To Stoarn Genorater Overpressure", oporato rs am diroctod to verif hot laes than 540 0 F if initial attompts to doprossurizo tho SG(c) is.unsuccessful.
IWhich ONE of tho following is bases for this verification?
Given the following condtions:
- FRP 19232-C, "Response to SG Overpressure" is being implemented
- SG #1 pressure is 1250 psig
- The MSIVs are shut
- SG #1 ARV and code safety valves are failed shut Which one of the following actions is required to correct this situation?
Ar Ens~uroc that the SG leyel instruments (WR) will be within the roguired accuracy during the Dump steam from SG #1 by opening the MSIV bypass valves.
B. DeAtormines wihether SG blowdown can bo used as a moethod to depressurize tho affected Stop RCP #1 to reduce the heat input to SG #1 C. E-nsu--res; ROS saturation pressuro isbelow shutoff hood of SIPs in tho event SGs bmeEGB a heot SOURCE instoad of a hoot sink.
Emergency borate the RCS to help lower RCS temperature and SG #1 pressure D. E-nsu,,res oXcossivo heat transfer from tho RCS is NOT the causo for the SG-ovorprossure.
Actuate SI to inject cold water into the RCS to help lower SG #1 pressure Ref: WOG ERG Bases, Procedure 19232 Source WB exam bank Distractor analysis:
Answer D based on wog erg bases rus ,tly , ... o n7f Anr74.6A AM 100 I Uesuay, reuruarly ,O :V ;,uu/*~