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{{#Wiki_filter:,g Ciniimonwcalth lihuni Comliany
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liraittwoost Gcncrating Station
* Route
* I, llox H I liraceville, IL 60 a0-'%l 9 Tel H15-458 2801 July 30,1998 Mr. Hironori Peterson U. S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, IL 60532-4351
 
==Dear Mr. Peterson:==
Enclosed are the examination materials that Braidwood Generating L s n is submitting for review, comment, and approval for the Initial License Written Re-examination of Mr.
Robert Sherman scheduled for the week of September 14, 1998, at Byron Generating Station.
This submittal includes the Reactor Operator Written Examination.
This examination material has been developed in accordance with Interim Revision 8 of NUREG-1021, " Operator Licensing Examiner Standards". Please note that reference materials are attached to each individual examination question per your request.
Some minor modifications have been made to the Integrated Examination Outline with regards to the written examination in order to improve balance and content. These changes improve the examination quality and compliance with Interim Revision 8 of NUREG-1021, " Operator Licensing Examiner Standards".
Quantitative and qualitative validation of the examination material will occur during the next three weeks. Some modifications or adjustments to the examination material may be required.
Please ensure that these materials are withheld from public disclosure until after the examination is completed.
If you have any questions or concers regarding this submittal, please contact Scott Deprest at (815) 458-3411 extension 2250 or Paul Hippely at extension 2235.
Sincerely, l
T'
. Tulon j
' e Vice President raidwood Nuclear Generating Station e
9811060212 981102 PDR ADOCK 05000456 V
PDR A l'nicom (' niijiatiy a
 
I l
l.
l' Mr. Hironori Peterson l
' July 30,1998 l
Page 2 List of
 
==Enclosures:==
)
l Updated RO Written Exam Sample Plan i
[
RO Composite Examination with references attached Completed ES-401-6 Checklist -
Examination Security Agreement (ES-201-3)
Listing of Submitted Sample Plan Changes cc:
w/o Enclosures Regulatory Assurance B. Wegner J. Walker D. Hoots C. Cerovac P. Hippely T. Benton L. Holden Class File
. nrc/9so479t. doc 1
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ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Braidwood 1 & 2 Date of Exam:
September 14,1998 Exam Level: RO K/A Category Points Tier Group Point K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
Total l.
1 2
2 2
4 6
16 Emergency &
l 2
3 2
3 6
2 1
17 Abnormal Plant Evolutions 3
1 1
1 3
Tier Totals 5
4 6
11 9
1 36 1
3 2
1 2
2 1
1 2
3 4
2 23 2.
2 2
2 2
2 1
2 2
3 2
2 20 Plant Systems 3
2 1
1 1
1 1
1 8
Tier Totals 7
2 4
5 4
2 3
5 7
7 5
51
: 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 13 -
5 3
2 3
Note: 3 Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.
3 Actual point totals must match those specified in the table.
3 Select topics from many systems; avoid selecting more than two or three K/A topics from a given l
system unless they relate to plant-specific priorities.
3 Systems / evolutions within each group are identified on the associated outline.
3 The shaded areas are not applicable to the category / tier.
NUREG-1021 30 of39 Interim Rev. 8, January 1997 l
l
 
PWRRO amination' Outline -
Facility Braidwood Ex m Dats:
9/14/98 Examination Levet RO Section Title Genenc Krs;.t$ and Abilities t
RO Group 1
~
l System / Evolution K/A '
RO KA Statement Level. Question Topic Conduct of Operations 2.1.1
. 3.7 Krs;.t$ of conduct of opershons requirements. B ' Evaluation of requirement for"achve" license i
2.1.1 3.7 Krs;.tJue of conduct of operations requirements. B ' Direchon of NLO personnel 2.1.2 3.0 Knowledge of operator responsibilities during all B
Operating Daily Orders f
modes of plant operation.
2.1.23 3.9 Ability to perform specific system and integrated B
Procedure required usage plant procedures during all modes of plant operation.
2.1.24-2.8 Ability to obtain and interpret station electrical and B Use of electrical prints mechanical drawings.
Equipment Control 2.2.13 3.6 Knowledge of tagging and clearance pmcedures.
B MOVtagout -
I 2.2.26 2.5 Knowledge of refueling administrative B
RCS level discrepancy during refueling requirements.
t 2.2.32 3.5 Knowledge of RB outes in the control room during B - RO duties in Control Room during refueling i
fuel handtag such as alrms from fuel handling area, communication with fuel storage facility, systems operated fmm the control room in support of fueling operations, and supporting instrumentation.-
i Radiation Control 2.3.1 2.6 Knowledge of 10 CFR: 20 and related facility B
Radiation exposure determination i
radiation control requirements.
2.3.10 2.9 Ability to perform procedures to reduce excessive R Fuel Handling Accident Response levels of radiation and guard against personnel exposure.
Emergency 2.4.16 3.0 Knowledge of EOP implementation hierarchy and B Performance of Status Trees / Function Restoration f
Procedures / Plan coordination with other support procedures.
2.4.20 3.3 Knowledge of operationalimplications of EOP B
Applicability of EOP Foldout Page wamings, cautions, and notes.
2.4.31 3.3 Knowledge of annunciators alarms and indications, B Identification of inoperable CR annunciators and use of the response instructions.
Friday, July 24,1998 5:02:52 PM Page 1 Prepared by WD Associates. Inc.
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PWRRO amination Outline Facility-Brcidwood Exam Dat :
9/14/98 Examination Level: RO Section Title Plant Systems RO Group 1
System / Evolution K/A RO KA Statement Level Question Topic Control Rod Drive 001 A2.06 3.4 Effects of transient xenon on reactivity B
Effect of Xenon Transient & compensation System 001 K1.03 3.4 CRDM B
Application of DC Hold R; actor Coolant Pump 003 A1.06 2.9 PZR spray flow B
RCP and Pzr spray operations System 003 K2.01 3.1 RCPS R
RCP Breaker & interlocks Chemical and Volume 004 A3.11 3.6 Charging / letdown R
Charging & letdown flows (including seal injection)
Control System 004 A4.07 3.9 Boration/ dilution B
Calculation of dilution 004 K6.01 3.1 Spray / heater combination in PZR to assure R
Boron mixing unifonn boron concentration Engineered Safety 013 A3.01 3.7*
Input channels and logic B
CNMT Spray / Phase B Features Actuation System 013 K4.13 3.7 MFWisolation/ reset R
FW lsolation - P14 Nuclear 015 A2.02 3.1 Faulty or erratic operation of detectors or B
SR NIS discriminator failure instmmentation compensating components System 015 K2.01 3.3 NIS channels, components, and interconnections B
SR NIS-loss of control power 015 KS.06 3.4 Subcritical multiplications and NIS indications R
Eval for 1/M - Eightfold increase In-Core Temperature 017 K4.01 3.4 Input to subcooling monitors R
CETC failure effect on Subcooling Monitor / Iconic Monitor System Display Containment Cooling 2.1.32 3.4 Ability to explain and apply all system limits and R
RCFC operations requirements System precautions.
Miin Feedwater 2.1.7 3.7 Ability to evaluate plant performance and make B
S/G Level program -low power System operational judgments based on operating characteristics, reactor behavior, and instmment l
interpretation.
059 K1.04 3.4 S/GS waterlevel control system R
Effect of failure of S/G steam pressure channel Friday, July 24,1998 5:02:54 PM Page 2 Prepared by WD Associates. inc.
 
PWRRO amination Ouuine Facility t$rtidwood Ex:m DatI 9/14/98 Ex mination Level: RO.
Section Title Plant Systems RO Group
. 1 SystemEvolution K/A' RO. KA Statement Level Question Topic Auxiliary / Emergency 061 A3.01 4.1 AFW stastup and flows B
AFW Startup -
' Feedwater System 061 K5.02 3.2. Decay heat sources and magnitude B ' AFW flow requirements for cooldown Liquid Radwaste 068 A4.04.
3.8 Automaticisolation B
RCDT operation - effect of CNMT isolation System
- 068 K1.07 2.7. Sources ofliquid wastes for LRS.
R CNMT Sump sources of input during normal operation i
Waste Gas Disposal 071 A4.05 2.6* Gas decay tanks, including valves, indicators, and R Waste Gas Decay Tank Operations System sample line -
Area Radiation 072 A4.03 3.1 Check source for operability demonstration R
Check Source operation Monitoring System 072 K3.02 3.1 Fuel handling operations B
Loss of FHB Overtread Crane rad monitor. -
i P
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l Friday, July 24,1998 5:02:54 PM Page 3 Prepared by WD Associates, Inc.
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. _ _ - _ _ _ _ _ _ ~
PWRRO amination Outline
~
Facility-Brridwood Ecm Dats:
9/14/98 Ermin:. tion Lcvel: RO Section Title Plant Systems RO Group 2
System / Evolution K/A RO KA Statement Level Question Topic R, actor Coolant 002 A1.11 2.7 Relative level indications in the RWST, the B
Relationship of levels during refueling operations System refueling cavity, the PZR and the reactor vessel during preparation for refueling 002 A3.01 3.7 Reactor coolant leak detection system R
RCS leak Detection Systems 002 K4.09 3.2 Operation ofloop isolation valves.
R Use of Loop Isolation Valves Emergency Core 006 A2.13 3.9 Inadvertent SIS actuation B
Systems response to SI/ Actions Cooling System 006 K3.02 4.3 Fuel B
10CFR50.46 Design Criteria 006 K6.03 3.6 Safety injection Pumps B
Evaluation of flow ECCS pumps Pressurizer Pressure 010 A1.08 3.2 Spray nozzle DT B
Spray using Normal and Aux Spray Centrol System 010 KS.01 3.5 Determination of condition of fluid in PZR, using B
Evaluation of Pzrconditions steam tables Pressurizer Level 011 K1.04 3.8 RPS B
Pzr Level Reactor Trip Control System R; actor Protec2 ion 012 A3.07 4.0 Trip breakers R
Operation of BOTH Bypass Trip Breakers System 012 A4.03 3.6 Channel blocks and bypasses B
input that can be bypass & condition 012 KS.01 3.3*
DNB R
OTdTinputs & effect of changes Rod Position Indication 2.4.31 3.3 Knowledge of annunciators alarms and indications, R ROD BOTTOM Alarm operation System and use of the response instructions.
Non-Nuclear 016 K3.02 3.4*
PZR LCS B
NR RTD Failure effects Instrumentation System Containment Spray 026 A2.08 3.2 Safe securing of containment spray when it can be B Sequence for securing CNMT Spray System done) 026 A4.01 4.5 CSS controls R
Pump operation interiocks Spent Fuel Pool 033 K1.05 2.7* RWST R
RWST Purification Loops Cooling System Friday, July 24,1998 5:02:55 PM Page 4 Prepared by WD Associates, Inc.
 
PWR RO unination Outline Facility Brridwood Exam Date:
9/14/98 Examination Level: RO Section Title Plant Systems RO Group 2
System / Evolution K/A RO KA Statement -
Level Question Topic D.C. Electrical 2.1.30 3.9 Ability to locate and operate components, B
DC bus battery charger Distribution including local controls.
Emergency Diesel 064 A3.07 3.6* Load sequencing B
Sequencing of ESF pumps-SI & SI w LOP Generators Fire Protection 086 K4.06 3.0 CO2 B
Effect ofloss of DC - CO2 aduation System i
Friday, July 24,1998 5:02:56 PM Page 5 Prepared byWD Associates,Inc.
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~
PWR RO -
unination Outline Facility.- Esraidwood Ex:m Dato:
9/14/98 Examination Level: RO Section Title Plant Systems RO Group
'3 System /Evoluhon K/A RO KA Statement Level Question Topic.
l Residual Heat
' 005 K1.12 3.1 Safeguard pumps B
Recist interties to St Pumps & CV Pumps Removd System -
005 K4.10 3.1 Control of RHR heat exchanger outlet flow R
Failure of Hx Outlet Valve Pressurizer Relief 2.4.50 3.3 Ability to venfy system alarm setpoints and R
PRT conditions causing alann/ response Tank / Quench Tank operate controls identified in the alarm response System manual.
t Component Cooling 008 A2.05 3.3* ~ Effect ofloss of instrument and control air on the R
Determination of effect of valve pos. Toning
[
Water System position of the CCW valves that are air operated
[
Containment lodine 027 A4.03 3.3*
CIRS fans R
Charcoal Filters response to deluge f
Removal System Steam Dump System 041 A3.02 3.3 RCS pressure, RCS temperature, and reactor B
Steam Dump input malfunction i
and Turbine Bypass ~
power Control
[
Main Turbine 045 K1.20 3.4 Protection system R
Turbine Control response to Failed impulse Channel Generator System j
instrument Air System 078 K3.02 3.4 Systems having pneumatic valves and controls B
Evaluation of eqpt affected for slow loss
^
f i
i t
l i
Friday, July 24,1998 5:02:56 PM F.;e 6 Prepared by WD Associates, Inc.
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PWRRO nmination Outline Facility-t$rCidwood Excm Datz 9/14/98 Ermirttion Level: RO Section Title Emergency cnd Abnormal Plant Evolutions RO Group 1
Oystem/ Evolution K/A RO KA Statement Level Question Topic R; actor Coolant Pump 015 AA2.10 3.7 When to secure RCPs on loss of cooling or seal B
Evalloss of cooling fim Malfunctions injection 015 AK2.07 2.9 RCP seals B
Eval of RCP seal failure Emergency Boration 024 AA2.05 3.3 Amount of boron to add to achieve required SDM B
Time / amount E-boration for condition Loss of Component 026 AA1.05 3.1 The CCWS surge tank, including level control and B Evaluation of CCWleak Cooling Water level alarms, and radiation alarm Pressurizer Preseure 027 AA1.01 4.0 PZR heaters, sprays, and PORVs B
Pressure controller step change Control Malfunciion 027 AA2.15 3.7 Actions to be taken if PZR pressure instrument B
Non-Controlling channel failure fails high Steam Line Rupture 040 AA1.01 4.6 Manual and automatic ESFAS initiation B
Steamline isolation 040 AK1.06 3.7 High-energy steam line break considerations B
Eval of Leak Less of Condenser 051 AA2.02 3.9 Conditions requiring reactor and/or turbine trip B
Eval of conditions Vacuum Station Blackout 055 EK3.02 4.3 Actions contained in EOP forloss of offsite and B
Identification of RCP seal LOCA/cooldown onsite power 1
Loss of Vital AC
: 05) AA2.19 4.0 The plant automatic actions that will occur on the B
Eqpt affected on bus loss Instrument Bus loss of a vital ac electrical instrument bus Contrel Room 068 \\A1.21 3.9 Transfer of controls from control room to shutdown B Operations required for transfer Evacuatan panel orlocal control Inadequate Core 074 EK1.03 4.5 Processes for removing decay heat from the core B Major action categories i
Cooling High ReactorCoolant 070 AA2.02 2.8 Corrective actions required for high fission product B Actions for reducing activity Activity activity in RCS Pressurized Thermal E08 EK2.2 3.6 Facility's heat removal systems, includinq primary B Identification of heat removal process Shock coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Friday, July 24,1998 5:02:57 PM Page 7 Prepared by WD Assaciates, Inc.
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^
PWR RC amination Outline Facility-Braidwood Exam Date:
-9/14/98 Examination Level: RO ~
Section Title Emergency and Abnormal Plant Evolutions RO Group 1
SystenVEvolution K/A RO KA Statement Level Question Topic Natural Circulation E09 EK3.1 -
3.3. Facility operating characteristics during transient B
Natural Circ conditions and limits Operations conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
b t
I s
i 1
t r
Friday, July 24,1998 5:02:58 PM Page 8 Prepared by WD Assodates, Inc.
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PWRRC aminetion Outline Facility-t$rcidwood Ex:tm Dats:
9/14/98 Examination Levet RO Section Title Emergency and Abnonnal Pt;nt Evolutions RO Group 2
System / Evolution K/A RO KA Statement Level Question Topic Continuous Rod 001 AA2.05 4.4 Uncontrolled rod withdrawal, from available B
Evaluate conditions - unwarranted rod withdrawal Withdrawal indications Dropped Control Rod 003 AK3.10 3.2? RiL and PDIL B
P/A vs. Group Step Counters Reactor Trip 007 EA1.03 4.2 RCS pressure and temperature B
Stabilized RCS temperature with failure of Steam i
Dumps 007 EK2.03 3.5 Reactor trip status panel R
Reactor Trip requirements Pressurizer Vapor 008 AK1.01 3.2 Thermodynamics and flow characteristics of open R Tail-Pipe conditions ~
i Space Accident orleaking valves Small Break LOCA 009 EA1.10 3.8*
Safety parameterdisplay system B
Calculation of subcooled margin on Icorucs i
1 Large Break LOCA 011 EA1.03 4.0 Securing of RCPs B
RCP trip criteria evaluation i
Loss of Reactor 022 AA1.08 3.4 VCTlevel B
VCTlevel transmitter malfunction Coolant Makeup t
Loss of Residual Heat 025 AK1.01 3.9 Loss of RHRS during all modes of operation B
Calc of time to saturation / core boiling Removal System I
i
\\
025 AK3.01 3.1 Shift to altemate flowpath B
Altemate RCS cooling Anticipated Transient 2.4.48 3.5 Ability to interpret control room indications to verify B AMS conditions l
l Without Scram the status and operation of system, and 1
understand how operator actions and directives affect plant and system conditions.
[
Loss of Source Range 032 AK1.01 2.5 Effects of voltage changes on performance B
Evaluation of SR NlS voltage failure i
Nuclear Instrumentation c
Loss of Intermediate 033 AA2.04 3.2 Satisfactory overlap between source-range, B
Eval of failed IR channel on SU
[
Ringe Nuclear intermediate-range and power-range l
Instrumentation instrumentation
[
Steam Generator Tube 037 AA1.02 3.1
* Condensate exhaust system R
Monitors for S/G Tube leakage Leak t
Steam Generator Tube 038 EK3.06 4.2 Actions cWained in EOP for RCS water inventory B Loss of subcooling Rupture balanc' 3 tube rupture, and plant shutdown proced :es i
L Friday, July 24,1998 5:02:59 PM Page 9 Prepared by WD Associates, Inc.
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Facility-Braidwood Exam Datz 9/14/98 Extmination Level: RO
- Section Title Emergency and Abnormal Plant Evolutions.
RO Group 2
System / Evolution K/A RO KA Statement Level Question Topic Loss of Secondary EOS EK2.1 3.7 Components, and functions of control and safety B
Interfocks affecting reestablishment of feed Heat Sink systems, induding instrumentation, signals, interiocks, failure modes, and automatic and manual features.
Loss of Emergency E11 EA1.1 3.9 Components, and functions of control and safety B
Reason for rapid S/G depressurization Coolant Recirculation systems, induding instrumentation, signals, interlocks, failure modes, and automatic and l
manual features.
)
Friday, July 24,1998 5:02:59 PM Page 10 Prepared by WD Associates. Inc.
 
PWR RC mmination Outline Facility tsraidwood Exam Dat3:
9/14/98 Examination Level: RO Section Title Emergency and Abnormal Plant Evolutions RO Gmup 3
System / Evolution K/A RO KA Statement Level Question Topic Pressunzer Level 028 AK3.05 3.7 Actions contained in EOP for PZR level B
Failed level channellow.
Control Malfunction malfundion Loss of Off-Site Power 056 AA121 3.3*
Reset of the ESF load sequencers B
Reset of sequencer 056 AA2.46 4.2 That the ED/Gs have started automatically and B
Eval of electric bus status that the bus tie breakers are closed i
s t
[
Friday, July 24,1998 5:03:00 PM Page 11 Prepared bywo Associates,Inc.
 
=____ _
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ES-401 Site-Specific Written Examination Form ES-401-7 Cover Sheet a-
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R;cctnrOp ratorExamination
: 1. An operator sits for the NRC License Operator Examination (l'nitial), successfully passes the Examination and is granted an NRC Senior Operator License or Reactor Operator license this month. What are the requirements for having the license on ACTIVE STATUS?
: a. The individual must meet the time on shift requirements of SEVEN 8-hour shifts before the license is in ACTIVE STATUS.
: b. The license is considered in ACTIVE STATUS for the current quarter ONLY.
: c. The individual must meet the time on shift requirements of SEVEN 8-hour shifts to have a license in ACTIVE STATUS for the next quarter.
: d. The license is considered in ACTIVE STATUS for the current and next quarter.
2.The following conditions on Unit 1:
- Reactor power 45%
- 1 A and 1C Feedwater pumps are operating
- FW PUMP TURB BRNG OIL LEVEL HIGH LOW annunciator (1-16-D3) alarms and the SER monitor indicates a low level.
- An EA is dispatched and confirms a low level exists.
In performing actions to correct the condition (per BwOP TO-08 " Filling a Turbine Feed Pump Oil Reservoir"), what is the normal relationship between the US, the NSO and the EA?
: a. L The US will direct the EA's activities, but will inform the NSO before the job commences.
: b. The US will direct the EA's activities, and need NOT inform the NSO unless unit controls are
: affected,
: c. The NSO will direct the EA's activities, but will inform the US before the job commences.
: d. The NSO will direct the EA's activities, and need NOT inform the US unless unit load is affected.
Page 1 of 50
 
Rccctar Op: rater Excminction
-3. How is a procedure change, which significantly changes normal processes, procedurally conveyed to licensed members of the operating crew?
: a. The SM places the applicable information in the Daily Order Book, and issues an additional memo to all crew personnel that is initialed.
: b. The SM is informed by memo of the addition to the Daily Order Book, and makes an announcement of the addition during the shift briefing.
: c. The SOS places the applicable information in the Daily Order Book, and the individual operator is responsible for reviewing the Daily Order.
d.' The US places the applicable information in the Daily Order Book, and makes an announcement of the addition during the shift briefing.
- 4. An example of a licensed operator evolution that can be performed WITHOUT either referring to an operations procedure or having a procedure in-hand is...
: a. Adjusting rod position following a boration.
b, - Starting the 1 A Heater Drain Pump,
: c. Placing excess letdown in service.
: d. Latching and rolling up the main turbine.
5. Assuming an auto-close signal is continuously present in the circuit for the 1 A SI pump, which contact will be maintained open in order to prevent the starting relay (SR) from attempting repeated breaker closures onto a faulted bus?
(E 1-4030-S101 is provided for use.)
: a. LC SW
: b. 52/b
. c. Y H
: d. LS Page 2 of 50
 
React:r Operatcr Examination 6. An operator is preparing an OOS that designates 1CC685, RCP Thermal Barrier CC Return CNMT isolation valve, as an isolation point.
j What is the acceptability of using this isolation point?
The OOS is...
: a. acceptable only if the MOV is tagged at its control switch, power supply and valve handwheel.
: b. acceptable only if the.MOV is tagged at its control switch, power supply and a blocking device is placed on the valve.
: c. NOT acceptable because the MOV fails to meet isolation requirements.
: d. NOT acceptable because the valve fails open on a loss of power.
7.The following conditions exist for Unit 1:
- Unit shutdown and cooldown initiated 120 hours ago
- Lowering of RCS level to the reactor vessel flange is underway
- RCS temperature 95*
- RCS level Control Room indicators: 1LI-RYO46 - 401'0" 1Ll-RYO49 -
402'1"
- RH loop 1 A in operation with " normal" indications What is the appropriate action for these conditions?
: a.. The lowering of RCS level can continue.
: b. The level change must be stopped until the cause for the level discrepancy is determined.
. c. When temperature correction is applied to the highest Control Room level indication, the running RHR pump must be stopped to prevent cavitation.
: d. When temperature correction is applied to the lowest Control Room level indication, the available S1 Pump aligned for hot leg injection must be started.
8.What is a responsibility of the NSO during refueling operations?
: a. Checking source range counts while a fuel assembly is being placed in the core.
: b. Ensuring water level in 3 pent fuel pool is at least 23' above the fuel.
: c. Maintaining a 1/M plot while reloading fuel during a core shuffle.
: d. Monitoring the manipulator crane position by updating the Control Room tag board.
Page 3 of 50
 
R0cct::r Op: rater Excmination 9. An operator has the following exposure history this year until today:
Deep Dose Equivalent (DDE) 210 mrem Committed Effective Dose Equivalent (CEDE) 45 mrem Shallow Dose Equivalent (SDE) 33 mrem Committed Dose Equivalent (CDE) 28 mrem Today the operator was required to make two entries into containment:
Entry 1:
Gamma dose - 52 mrem; Neutron dose - 24 mrem Entry 2:
Gamma dose - 124 mrem How much radiation exposure is available to the operator if he has to make additional entries?
His available margin based on the routine Administrative Exposure Control Levels is...
: a. 100 mrem for that day; 2484 mrem for the year,
: b. 100 mrem for that day; 2545 mrem for the year.
: c. 124 mrem for that day; 2569 mrem for the year.
: d. 124 mrem for that day; 2614 mrem for the year.
10.The following conditions exist on Unit 1:
- Refueling operations in progress
- A HIGH alarm received on radiation monitor 1RE-AR012, Containment Fuel Handling incident When should the NSO initiate action and what action should he/she take from the control room? "
Indication of a fuel handling accident is considered when a...
: a. report is received from personnel in containment. The operator starts the containment charcoal filter fans.
: b. report is received from personnel in containment. The operator actuates Unit 1 CNMT evacuation alarm.
c corroborating rise is indicated on monitor 1RE-AR011. The operator starts the containment charcoal filter fans.
: d. corroborating rise is indicated on monitor 1RE-AR011. The operator actuates Unit 1 CNMT evacuation alarm.
Page 4 of 50
 
Re:cter Op:: rater Examination i
11.The following conditions exist on Unit 1:
l
- A reactor trip has occurred and both reactor trip breakers are verified open
- The turbine has tripped
- BwEP-0 " Reactor Trip OR Safety injection" has been entered.
- BUS 141 ALIVE light is NOT lit with bus voltage at ZERO volts
- BUS 142 AllVE light is lit with bus voltage at 4149 volts.
Which of the following describes the actions the operators are required to take?
: a. Continue with next step of BwEP-0.
: b. Turn on the synchroscope and manually close ACB 1412, SAT 142-1 feed breaker,
: c. Manually start 1 A DIG and verify ACB 1413, D/G output breaker, closes.
: d. Initiate actions of BwOA ELEC-3 and continue with next step of BwEP-0.
: 12. From the list of procedures identified below, which has(have)" Transfer to Cold Leg Recirculation" on the Operator Action Summary Page?
(NOTE: The following procedures are in the E-1 or CA-1 series:
BwEP-1 " Loss Of Reactor Or Secondary Coolant" BwEP ES-1.1 "Si Termination" BwEP ES-1.2 " Post-LOCA Cooldown And Depressurization" BwEP ES-1.3 " Transfer To Cold Leg Recirculation" BwEP ES-1.4 " Transfer To Hot Leg Recirculation" BwCA-1.1 " Loss Of Emergency Coolant Recirculation" BwCA-1.2 "LOCA Outside Containment")
: a. BwEP-1, BwEP ES-1.1 through ES-1.4, and BwCA-1.1 through BwCA-1.2 procedures.
: b. BwEP-1, BwEP ES-1.1 and ES-1.2 procedures ONLY.
: c. BwEP-1 and BwEP ES-1.2 procedures ONLY.
: d. BwEP-1 procedure ONLY.
l l
Page 5 of 50
 
Rrcter Opsratcr Examinttien 13.The following conditions exist on Unit 1:
- Reactor trip breakers status - OPEN
- RCS Tave - 557'F
- Pzr pressure - 2235 psig Annunciator RCFC VIBRATION HI (1-3-C5) has been in alarm for the past 1 % shifts due to a faulty vibration probe. While maintenance troubleshoots the vibration probe on RCFC 1C which of the l
following actions is appropriate for this alarm window?
: a. The alarm should be acknowledged for each actuation and the SER monitored for valid alarm inputs.
l
: b. The alarm should be acknowledged for each actuation and operators stationed locally at each RCFC to monitor vibration.
I
: c. The alarm should have been silenced without acknowledgement after obtaining Unit Operating Engineer's permission and the SER monitored for valid alarm inputs.
: d. The alarm should have been silenced without acknowledgement with US permission and operators stationed locally at each RCFC to monitor vibration.
14. A feed pump trip occurred resulting in a rapid power reduction on Unit 1. Power was reduced from 100% steady-state conditions using a combination of rods and boration.
The following conditions exist for Unit 1 following stabilization:
- Reactor Power - 60%
- Delta-1 target value - +2.0
- Control Bank D position - 160 steps withdrawn 1
-Tave - 572*F
- Delta-l - -10.5%
- Core Age - MOL What actions will be required to maintain the current power level and maintain Delta-l within its
. normal operating band over the next FIVE hours?
: a. Boration and control rod withdrawal, followed by dilution.
: b. Boration and control rod insertion, followed by dilution.
: c. Dilution and control rod withdrawal, followed by boration
: d. Dilution and control rod insertion, followed by boration.
Page 6 of 50
 
R:actcr Op; rat::r Extmination
: 15. A problem with the rod control system requires checking several rod bank circuits. The affected power cabinet repairs are to be made by supplying power from the DC hold supply cabinet.
What is the capacity of the DC Hold Supply Cabinet under these circumstances?
: a. ONE control rod bank group can be placed on DC HOLD, and these rods will drop ONLY if the controls are taken to OFF at the DC Hold cabinet.
: b. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, 3
and these rods will drop ONLY if the controls are taken to OFF at the DC Hold cabinet.
: c. ONE control rod bank group can be placed on DC HOLD, and these rods will automatically drop.
: d. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, and these rods will automatically drop.
l 16.The following conditions exist for Unit 1:
- Mode 5
- RCS is draining to Pzr level of 40%
- IM calibrations have been completed for LT-RYO48, Refuel Cavity level, in preparation for further draining What is the relationship between Pzr level instrument LT-459, Pzr level instrument LT-462 and LI-RYO487 At approximately 40% level indicated on Ll-462, level on..
: a. LI-459 and LI-RYO48 will be offscale high.
: b. Ll-RYO48 will be just onscale and Ll-459 will be offscale low.
: c. LI-459 will read higher than 40% and LI-RYO48 will just be onscale.
: d. LI-RYO48 will be offscale high and Ll-459 will read lower than 40%
Page 7 of 50
 
R :ct:r Op:ratcr Excmination 17, The following conditions exist for Unit 1:
- Reactor power - 100%
- RCS activity is elevated, but below Technical Specification (CTS) levels
- Pzr pressure - 2225 psig
- Pzr level - 44%
- PORV 1RY456 - dualindication
- Leak rate - 6 gpm in an attempt to isolate the leakage past the PORV, the Block Valve 1 RY80008 was taken to close. The valve failed to close and the operator placed 1RY456 in the CLOSE position. When conditions stabilize:
- Reactor power - 100%
- Pzr pressure - 2228 psig
- Pzr level - 44%
How would the operator be able to tell if the PORV has closed?
: a. Position lights for PCV-456 showing CLOSE indication ONLY.
: b. PORV downstream temperature indication 1Tl463 dropping.
: c. Level change in RCDT,
: d. Lower readings for containment radiation monitors RE-001 I A/0012A.
Page 8 of 50
 
Rrctar Op rattr Examination 18.The following conditions exist on Unit 1:
- RCS Loop C is isolated for maintenance
- RCS Loop A had been isolated for maintenance
- RCS Loop A Hot Leg Stop Isolation Valve (LSIV) was opened at 1001
- RCS Loop A Bypass Stop Valve was opened at 1005 with reliefline flow of 115 gpm verified
- RCS Loop A Cold Leg LSIVis closed
- RCS temperature - 110*F
- RCS Hot Leg Loop temperatures - 108*F (A); 119'F (B); 110*F (C); 125'F (D)
- RCS Cold Leg Loop temperatures - 103*F (A); 108'F (B); 90*F (C);
115'F (D)
- S/G levels (Narrow Range) - 20% (A); 30% (B); 15% (C); 32% (D)
What will occur when the operator takes the control switch for MOV-RC8002A (RCS Loop A Cold Leg LSIV) to OPEN at 15097 The valve...
i
: a. will travel fully open with NO automatic actuations.
: b. will travel fully open, and the AFW pumps get a start signal.
: c. remains closed because the temperature difference interlock remains active.
: d. remains closed because the timer interlock is still active.
19.The following Unit 1 conditions exist:
- RCS temperature (Average CETC) - 140*F
- RCS pressure - 365 psig
- A bubble has just been drawn in the Pressurizer
- Allloops are filled and vented
- Preparations are in progress ta start the first RCP for continuous run What is the effect of selecting the 1C RCP to start?
: a. Both Pzr Sprays will function normally for Pzr pressure control.
: b. Manual cycling of the Pzr heaters will be required for Pzr pressure control.
: c. PORV RY456 will open on high pressure from high pressure bistable PB456E.
: d. Normal Pzr spray will deliver minimal spray flow for Pzr pressure control.
Page 9 of 50
 
R:act:r Op;ratcr Excmination 20.The following conditions exist on Unit 1:
- Reactor power 26%
- Pzr pressure - 2235 psig
- Pzr level - 35%
RCP 1 A breaker trips due to sensed undervoltage from bus 157. What is expected as a result of the trip of the RCP7
: a. The reactor will trip due to the open RCP breaker.
: b. The reactor will trip due to RCS loop low flow condition.
: c. The reactor will be manually tripped by the operator,
: d. A normal plant shutdown will be initiated.
21.The following conditions exist on Unit 1:
- Reactor power - 100%
- PZR pressure - 2235 psig
- PZR level - 44% stable
- CV121 - In MANUAL
- CVCS letdown - Isolated due to leak in Letdown Hx
- CVCS Excess Letdown - In service with maximum flow of 20 gpm
- RCP sealinjection - 1 A CV pump aligned to all RCPs
- RCP seal leakoff flow - 3 gpm (1 A); 3.5 gpm (18); 3 gpm (1C); 2.5 gpm (1D)
What flow is indicated on Charging Header Flow indicator, F1-1217
: a. 5 gpm
: b. 25 gpm
: c. 32 gpm
: d. 65 gpm Page 10 of 50
 
R:actar Op3ratcr Examination
~ 22.The following conditions exist on Unit 2:
- Unit is in MODE 5
- Unit burnup is 5700 EFPH in Cycle 7
- SDM - 1.3% DeltaK/K
- RCS pressure - 400 psig
- RCS average temperature - 195'F
- RCS boron concentration - 1006 ppm
_ Differential boron worth - -10.75 pcm/ ppm
- PZR level - 32.3%
- SR NIS countrate - 10 cps, BOTH channels stable background levels
- An inadvertent dilution at 70 gpm begins at 1300 hours Assuming NO operator action is taken and PZR level remains constant over the time period, when would the HIGH FLUX AT SHUTDOWN alarm actuate?
: a. Never, because BDPS will actuate prior to actuation.
: b. 1430 hours.
: c. 1505 hours.
: d. 1734 hours.
23.The following conditions exist on Unit 1:
- Reactor power was 95% prior to the event
- A turbine runback resulted in rod insertion with control rods in AUTOMATIC
- Annunciator ROD BANK LO-2 INSERTION LIMIT (1-10-A6) is lit The operators initiated an emergency boration per BwOA PRl-2 " Emergency Boration" and have verified control rods are now withdrawing. Why does the operator energize the Pzr Backup Heaters?
This action..
: a. ensures Pzr boron concentration equalization with RCS by increasing normal spray flow.
b, counteracts RCS cooldown due the boration by the additional heat from the backup heaters.
: c. prevents loss of Pzr level by increasing the volume of fluid maintained in the Pzr.
: d. guarantees adequate subcooling margin is maintained by raising the saturation temperature of the Pzr.
Page 11 of 50
 
R:::ctnr Op rat:r Eximin tion 24.The following conditions exist on Unit 1:
- A LOCA has occurred
- Actions of 1BwEP ES-1.3, ' Transfer To Cold Leg Recirculation, have been completed.
- During alignment,1CV8804A, RH HX to CENT CHG Pumps isolation Valve, failed to open and could NOT be manually opened.
What is the status of the ECCS system?
: a. The RHR discharge headers are cross-tied with only RHR Pump 1B running and supplying suction to the Si pumps and Centrifugal Charging pumps from the B train connection.
: b. The RHR discharge headers are cross-tied v'ith both RHR pumps running and supplying suction to the Si pumps only from the B train connection. The Centrifugal Charging pumps are stopped.
: c. RHR Pump 18 is discharging through the B Train cold leg injection headers and supplying suction to the Sl Pumps. RHR Pump 1 A and the Centrifugal Charging pumps are stopped.
: d. RHR Pump 18 is discharging through the B Train cold leg injection headers and supplying suction to the SI pumps and Centrifugal Charging pumps. RHR Pump 1 A is discharging thrtugh the A Train cold leg injection headers.
Page 12 of 50
 
R:actar Op: rat 3r Excmin tien 25.The following conditions exist on Unit 1:
- Unit is in MODE 4 during cooldown per 1 BwGP 100-5 following unit shutdown 38 hours ago
- RCS temperature - 340*F
- RCS pressure - 345 psig
- PZR level - 33%
- RHR pump 1 A is operating in Shutdown Cooling mode
- RH-618 A Hx Bypass Flow Control Valve is in MAN at 3000 gpm
- RH-606 A HX Flow Control Valve controller demand is at 20%
- CV-128 RHR Ltdn Flow Contr Valve demand is at 100%
- PCV-131 is in AUTOMATIC set to maintain 350 psig A signal failure from the controller causes RH-606 to go fully closed. What is the system response to this failure WITHOUT operator action?
: a. PCV-131 will throttle open due to lower RH discharge pressure,
: b. RCS pressure willincrease due to RCS heatup.
: c. Pressurizer level will decrease due to increased letdown flow.
: d. RH-610 will throttle open due to lower RH flow.
Page 13 of 50
 
l RS ct::r Op3 rat:::r Examinition 26.The following conditions exist on Unit 1:
- A plant heatup is underway
- MODE 3 has just been entered l
- RCS pressure 450 psig l
SI Accumulator 1C was drained below required level during the outage for repair work. System configuration has NOT allowed refilling the Accumulator until now. The SI Accumulator line is being flushed in accordance with BwOP SI-14 "Si Accumulator Fill Line Flush"(Valve lineup includes: 1SI-8964, Si Test Lines to Radwaste Isolation Valve, and SI-8888, S1 Pps to Accumulator Fill Valve, are open.1SI 8821 A, SI Pump to Cold Leg Isolation Valve, and 181 8802A, Si to Hot Leg 1 A & 1D isol valve are closed). Si pump 1 A running. During the flushing, an inadvertent SI signalis generated.
What is the status of the ECCS based on the current alignment WITHOUT operator action?
: a. 1B SI pump ONLY is running with injection flow to the RCS cold legs and to the Accumulator 1C fill !ine flush.
' b. 1 A Si pump ONLY is running with flow directed to the Accumulator fill line flush ONLY.
: c. BOTH Si pumps are running with injection flow to the RCS cold legs and to the Accumulator 1C fill line flush.
: d. BOTH Si pumps are running with flow directed to the Accumulator 1C fill line flush ONLY.
27.To meet the 10CFR50.46 criteria, the ECCS System is designed such that under accident conditions it will maintain..
: a. total hydrogen production from zirconium-water reaction below maximum value of 5%.
: b. maximum fuel temperature at the inside surface of the cladding less than 2000'F.
: c. the core at least 5% shutdown to prevent an inadvertent return to criticality.
: d. fuel clad oxidation less than 17% of total clad thickness anywhere within the core.
l l
Page 14 of 50
 
R:cctor Op:ratar Extmination 28.The following conditions exist on' Unit 1:
- A LOCA has occurred
- Transfer to Cold Leg recirculation is required
- RCS pressure is approximately 50 psig
)
What is the approximate total SI pump flow indicated on the main control board and how will this value change following transfer of BOTH trains of ECCS to cold leg recirculation?
Total Flow Flow Change i
: a. 650 gpm Decrease i
: b. 800 gpm increase
: c. 1050 gpm Decrease
: d. 1300 gpm increase
)
t i
l Page 15 of 50 i
i
 
l RIctor Op3ratcr Ex min tion 29. During shift tumover for Unit 1, the NSO notes the following parameters:
i-RCS Tave - 566.5*F Pzr pressure - 2235 psig Pzrlevel - 38.3%
i PRT pressure - 4 psig PRT ievel - 74%
l PRTtemperature - 98'F One hour later when annunciator 1-12-A7, PRT LEVEL HIGH LOW alarmed, the NSO notes the i
i following parameters:
RCS Tave - 566.2*F Pzr pressure - 2233 psig Pzrlevel - 38%
PRT pressure - 5.9 psig PRTlevel - 81%
PRT temperature - 96*F What condition resulted in the change in parameters?
: a. PRT PW Supply inside Cnmt isol Valve RY-8030 opened.
: b. PRT to GW Comp Isol Valve RY-469 failed closed.
: c. CVCS letdown relief valve CV-8117 lifted.
: d. PORV RY-455A opened and reclosed.
: 30. Unit 1 is operating at 100% power in MOL conditions. All systems are functioning normally with rod controlin manual.
What is the effect on plant operations if instrument air supplied to the CVCS letdown Hx component cooling water outlet valve, CV-130 is lost?
TCV-130 goes fully...
: a. shut and reactor power decreases due to boration in the CVCS demineralizers.
: b. shut and the CVCS demineralizers are automatically bypassed on temperature signal.
: c. open and reactor power increases due to deboration in the CVCS demineralizers.
: d. open and the CVCS demineralizers are automatically bypassed on temperature signal.
Page 16 of 50
 
_.. ~. _
Reactar Op:ratcr Examination 31.What are the parameters and values used by the operator to ensure the temperature difference between the PZR and the spray fluid are within the specified limit (s) in the PRESSURE AND TEMPERATURE LIMIT REPORT when initiating PZR spray?
: a. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor space temperature limit is 50*F, and for aux spray, the difference between Regenerative Hx charging inlet temperature and PZR vapor space limit is 320*F.
: b. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 50'F, and for aux spray, the difference between Regenerative Hx i
l charging outlet temperature and PZR vapor space limit is 320*F.
: c. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor space temperature limit is 320*F, and for aux spray, the difference between Regenerative l
Hx charging inlet temperature and PZR vapor space limit is 320*F.
1
: d. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 320*F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is 320*F.
32.The following conditions exist on Unit 1:
- A load reject from 100% power has occurred
- Reactor power - 80%
- Pzr level - 56%
- Pzr vapor temperature - 655'F
- Pzr liquid temperature - 653*F
- RCS Tave - 578'F What is the current status of the Pressurizer based on given conditions?
: a. Backup and proportional heaters are fully on.
: b. Proportional heaters are modulated on.
: c. Pzr spray valves have modulated open.
: d. Pzr spray valves and Pzr PORVs are open.
i 1
Page 17 of 50 i
I
 
R cct r Opgrat:r Ex::minati n 33.The following conditions exist on Unit 1 with all controls in normal lineup:
- Reactor power - 30% stable
- RCS Tave - 564.5*F
- Pzr pressure - 2230 psig
- Pzr level - 36%
The pressurizer level controller 1LK-459 output fails low. What automatic actions result assuming NO operator action taken?
: a. The reactor will trip on high pressurizer level ONLY.
: b. Letdown will isolate on low pressurizer level and then the reactor will trip on high pressurizer 1
level.
: c. The reactor will trip on high pressurizer pressure ONLY.
: d. Letdown will isolate on low pressurizer level and then the reactor will trip on RCS low pressure.
34.The following conditions exist on Unit 1:
- Mode 3 NOT NOP with reactor trip breakers (RTA and RTB) closed
- Testing of reactor trip bypass breakers underway
- Reactor bypass breaker B (BYB) is racked in and closed
- An operator begins to perform test with reactor bypass breaker A (BYA).
What occurs as the operator operates the breaker BYA7 When reactor bypass breaker BYA is...
: a. locally closed, ONLY breaker BYB will trip.
: b. racked in to the CONNECT position, ONLY breaker BYB will trip,
: c. locally closed, all reactor trip and bypass breakers will trip.
: d. is racked in to the CONNECT position, all reactor trip and bypass breakers will trip Page 18 of 50 1
 
R%ct:r Op:ratcr Excmination 35. The following conditions exist on Unit 2:
- Unit shutdown is in progress
- Reactor power - 20%
- RCS Tave - 562*F
- Pzr pressure -2235 psig
- Pzr level - 32%
- First stage turbine pressure channel PT-506 fails high What affect does this failure have on operations as unit shutdown is continued, if NO action is taken for the failure?.
: a. At 10% power, the reactor will trip if the Source Range Block RESET pushbuttons are depressed.
: b. At 9% power, the reactor will trip if an RCP trips.
: c.. At 7% power, the reactor will trip if the TURBINE TRIP pushbuttons are depressed.
: d. At 5% power, the reactor will be manually tripped as during a normal shutdown by BwGP 100-5.
j
. 36.The following conditions exist on Unit 1:
- Power range NIS reading - 100%
- Tcold - 553*F
- Thot - 608'F
- RCS total flow - 372,000 gpm
- Pzr pressure -2215 psig
- Pzr level - 69%
How does the setpoint for Over Temperature Delta-T (OTdT) change when a listed parameter is changed? (Consider each change individually)
The setpoint...
: a. increases if Power range NIS output rises to 102%.
: b. increases if total reactor flow decreases to 370,000 gpm.
: c. decreases if pressurizer pressure increases to 2235 psig.
j
: d. decreases if the Thot rises to 612*F.
F Page 19 of 50 l
 
Reacter Op: rat::r Examination 37.The following conditions exist on Unit 1:
- Mode 3 with unit cooldown in progress
- RCS temperature - 520*F
- Pzr pressure - 1750 psig
- Pzr level - 33%
- MSIVs open What would directly happen if the operator were to take CONTAINMENT SPRAY & PHASE B ISOL switches for both trains to the ACTUATE position?
: a. NO ESF actuations would occur.
: b. Containment Phase B isolation and Containment Ventilation isolation ONLY would be actuated.
: c. Containment Phase B isolation and Containment Ventilation isolation, and Containment Spray ONLY would be actuated.
: d. Containment Phase B isolation and Containment Ventilation isolation, Containment Spray, and Main Steamline isolation would be actuated.
38.The following conditions exist on Unit 2:
- RCS temperature - 340'F
- RCS pressure - 900 psig
- All MSIVs for the S/Gs are closed
- The MSIV Bypass valves are open
- The FW-035s, Feedwater Tempering Isolation Valves, are open
- The FW-034s, Feedwater Tempering Flow Control Valves, are closed (opened periodically for level control)
- Feedwater pump N is reset and latched on turning gear
- The Start Up Fesdwater pump is running The level in the S/G 2B rises to 90%. How is the plant affected?
: a. No actuation occurs because of the position of the MSIVs.
: b. The 2C Feedwater pump and Start Up Feedwater pump trip.
: c. The 2C Feedwater pump trips and FW-035 valves close.
d.' The 2C Feedwater pump and Start Up Feedwater pump trip, the FW-035 valves close, and the MSIV Bypass valves close.
4 l
Page 20 of 50
 
l, I
l R:cctar Op:ratar Extminction l
39. During a reactor startup, when does the ROD AT BOTTOM alarm become active for each control bank?
The alarm will actuate for a dropped rod for...
: a. any Control Bank whenever Control Bank A DRPI output is above 9 steps.
: b. each Control Bank whenever that Control Bank demand position is above 3 steps.
: c. each Control Bank whenever that Control Bank DRPI output is above 9 steps.
I
: d. Control Banks A, B and C whenever their Control Bank demand position is above 9 steps, j
l and for Control Bank D whenever Control Bank D demand position is above 3 steps.
i 1
40.How would the failure of the pulse height discriminator to a low value affect the indication of the affected Source Range channel?
The output would...
: a. decrease due to electronic filtering which narrows the pulse height window.
: b. decrease due to failure in counting the higher amplitude neutron generated pulses.
: c. increase due to counting of the gamma generated pulses ONLY.
: d. increase due to counting of the gamma generated pulses and decay alpha generated pulses.
Page 21 of 50
 
Rnctar Op; rat:r Exrmination l
41.The following conditions exist on Unit 1:
l
- RCS at NOT NOP
- Reactor trip breakers - closed
- Source Range readings:
N31 - 18 cps N32 - 22 cps i
What indication would the operator observe if Control Power was lost to the N31 Drawer?
I The N31 meter would read..
3
: a. downscale, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.
: b. downscale, the associated drawer bistable lamps lit, and reactor trip breakers open.
: c. 18 cps, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.
: d. 18 cps, the associated drawer bistable lamps lit, and reactor trip breakers open.
Page 22 of 50
 
Rzct:r Op; rater Examiniti::n 42.The following conditions exist on Unit 1:
- A reactor startup is about to be performed
- All shutdown banks are 'ully withdrawn
- All control banks are ful!y inserted
- An ECC records the following:
Predicted Critical Position (ECP) - 130 steps on CBD Max rod position - 231 steps on CBD l
Min rod position - 58 steps on CBD The following parameters were recorded during the rod withdrawal:
ROD HEIGTH N31 cps N32 cps O on CBA 25 23 178 on CBA 34 31 178 on CBB 58 62 178 on CBC 116 106 80 on CBD 200 182 92 on CBD 237 225 When was the first time the operator was required to determine the Predicted Crit l cal Position?
: a. At 50 steps on CBA, with N32 as the designated Source Range detector.
: b. At 113 steps on CBC, with N31 as the designated Source Range Detector.
: c. At 80 steps on CBD, with N31 as the designated Source Range detector.
: d. At 92 steps on CBD, with N32 as the designated Source Range detector.
Page 23 of 50
 
l Rrctar Op:ratcr Examinttion 43.The following conditions exist on Unit 1:
- Reactor power - 50%
i
- RCS Tave - 570*F (A); 569'F (B); 569'F (C); 570'F (D)
- RCS Thot - 585'F (A); 584*F (B); 583*F (C); 585'F (D)
- RCS Tcold - 555'F (A) 554*F (B); 555'F (C); 555'F (D)
- Pzr pressure - 2235 psig
- Pr level - 43 %
i l
If loop B Thot output channel fails LOW, what is the response of Pzr level ?
i Pressurizer level will.,
: a. increases to 60%.
: b. remains the same.
: c. decreases to 25%.
: d. decreases to the letdown isolation setpoint.
44 With Unit 1 at 100% power and with normal operating parameters, how would the failure of the HOTTEST Core Exit Thermocouple affect the reading of subcooling margin on the SPDS Iconics (CETC/SMM display) for each of the two situations below-Situation 1 - The CETC output fails high slowly Situation 2 - The CETC output fails low slowly
: a. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and return to normal when CETC output reaches 2300*F.
Situation 2: Subcooling margin will increase, then stabilizes when the CETC output is smaller than TEN other TCs.
: b. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and return to normal when CETC output reaches 1200*F.
Situation 2: Subcooling margin will remain constant.
: c. Situation 1: Subcooling margin will increase to saturation then rise in superheat, and return to normal when CETC output reaches 1200*F.
Situation 2: Subcooling margin will decrease, then stabilizes when the CETC output is smaller than TEN other TCs.
: d. Situation 1: Subcooling margin will Inctease to saturation then rise in superheat, and return to normal when TC output reaches 2300*F.
Situation 2: Subcooling margin will remain constant.
l Page 24 of 50
 
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Rtactor Op::ratcr Examination 45.The following conditions exist on Unit 2:
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- RCS Temperature - 342*F p
- Pzr pressure - 375 psig I
- 2A,28, and 2D RCFCs are operating in high speed l
- Unit 2 RCFC Dry Bulb temperatures are recorded as follows:.
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- 2A RCFC - 119'F
-2B RCFC - 118'F
-2C RCFC - 127'F
-2D RCFC - 121*F Which of the following identifies the equipment status and actions for the above conditions?
What are the MINIMUM requirements for operation for the Reactor Containment Fan Coolers (RCFCs)?
l
. a. An additional RCFC must be started because the average of ALL the RCFC temperatures exceeds the limit.
: b. An additional RCFC must be started because ONE of the operating RCFCs temperatures is above the limit.
: c. NO action is necessary because ALL temperatures are within their appropriate limit.
: d. NO action is necessary because the average temperature of ALL operating RCFCs is below the limit.
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l Page 25 of 50
 
R: actor Operater Examination
' 46.The following conditions exist on Unit 1:
- A LOCA has occurred
- Transition has been made to BwEP ES-1.3 " Transfer To Cold Leg Recirculation"
- Containment Spray actuated due to high containment pressure
- All systems and components operating as expected What conditions allow for termination of Containment Spray?
: a. ONE pump is stopped when containment pressure is less than 15 psig. The other pump is
{
i stopped when RWST LO-3 level is reached.
)
' b.' ONE pump is stopped when containment pressure is less than 20 psig. The other pump is stopped after it has operated for a period of at least TWO hours
: c. BOTH pumps are stopped when containment pressure is less than 15 psig and have operated for a period of at least TWO hours,
: d. BOTH pumps are stopped when containment pressure is less than 20 psig and RWST LO-3 level is reached.
47.The following conditions exist on Unit 1:
- LOCA is in progress
- Containment pressure - 15 psig
- Containment Spray actuated due to high containment pressure
- Containment Spray signal has been reset
- The actions of BwEP ES-1.3 " Transfer To Cold Leg Recirculation" have been completed
- Offsite power is then lost and the D/G output breakers have just closed onto ESF buses How are the Containment Spray Pumps re-started?
: a. The pumps will auto start 15 seconds following closure of the D/G output breakers.
: b. The pumps will auto start 40 seconds following closure of the D/G output breakers.
: c. If the operator immediately places the CS & PHASE B ISOL switches for both trains to ACTUATE, the pumps will auto start 15 seconds following closure of the D/G output breakers.
: d. If the operator immediately places the PP 1_ TEST switches for both pumps in TEST, the pumps will auto start 40 seconds following closure of the D/G output breakers.
Page 26 of 50 A
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Rtcctor Optratcr Examination 46. Annunciator 0-33-C3, FILTER 1VP05FA TEMPERATURE HIGH, alarms in the Control Room while 1VP02CA CNMT Charcoal Filter Fan is operating. The alarm condition is verified locally.
Which of the following describes the actions taken and/or the system response for the Containment Ventilation System?
: a. The deluge valve FP244A will automatically open and the fan will automatically stop.
: b. The control room operator will open the deluge valve FP244A and the local operator will then stop the fan.
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: c. The local operator will open the deluge valve FP244A and the fan will automatically stop.
: d. The local operator will open the deluge valve FP244A and the control room operator will then stop the fan.
49.The following conditions exist:
l 1
- Unit 1 - 20% power with load increase in progress l
- Unit 2 - MODE 5 following refueling outage
- Unit 2 Spent Fuel Pool Cooling Loop is in service.
- Spent Fuel Pool Pump 1FC01P is OOS.
Which of the following is allowed under this situation?
Alignment and operation of...
: a. both Unit 1 RWST purification and Unit 2 RWST purification with flow through the Unit 2 Spent Fuel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.
: b. Spent Fuel Pool purification and Unit 1 RWST purification with flow through the Unit 1 Spent Fuel Pool Demineralizer and Unit 1 Spent Fuel Pool Filter.
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: c. Unit 2 RWST purification with flow through the Unit 1 Spent Fuel Poo! Filter ONLY.
: d. Unit 2 RWST purification with flow through the Unit 2 Spent i uel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.
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Page 27 of 50
 
R:act2r Op ratar Examintti::n 50.The following conditions exist on Unit 1:
- Reactor power was 65% when the turbine tripped
- An ATWS occurred
- The reactor tripped 15 seconds later when B reactor trip breaker was locally opened
- Reactor trip breaker A is failed closed
- RCS Tave - 559'F
- Pzr pressure - 2255 psig
- Steamline header pressure - 1100 psig
- No controls other than control rods and boration controls have been operated What is the status of the Steam Dump valves?
Steam Dun ps are..
: a. modulated open due to steam header pressure.
: b. modulated open due to Tave above no-load Tave.
: c. closed because Tave is NOT greater than 3*F above Tref.
: d. closed because the dumps are NOT armed.
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1 Rrct::r Operatcr Examinati::n 51.The following conditions exist on Unit 1:
- Reactor power 28%
- All systems normal
- Turbine EHC Panel settings:
Turbine REFERENCE DEMAND -580 MW Turbine REFERENCE - 330 MW
- The GO pushbutton is LIT i
What would be the DEHC System response to a slow failure to ZERO for the turbine impulse pressure channel that feeds into the DEHC7 Turbine load will...
: a. decrease until the difference between REFERENCE and impulse pressure exceeds 30%,
the operator would then be alerted to select MANUAL control.
: b. decrease until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%, then load will stabilize in MANUAL control.
: c. increase until the difference between REFERENCE and impulse pressure exceeds 30%,
i then load will stabilize in MANUAL control.
: d. increase until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%, the operator would then be alerted to select MANUAL control.
52.The following conditions exist on Unit 1:
- Reactor power 35%
- All systems normal What failure would cause a decrease in feedwater flow to all S/Gs?
: a. ONE condenser steam dump ONLY fails open.
: b. Main steamline pressure PT-507 fails low.
: c. ONE HD pump flow control valve ONLY fails open.
: d. Main feedwater header pressure PT-508 fails low.
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- Rc:ct:!r Oparater Examinttien 53.The following conditions exist on Unit 1:
- Reactor power 100%
- All systems normal
- FT-512 selected for steam flow input into SGWLC for S/G 1 A What is the initial effect of the pressure transmitter associated with FT-512 failing low?
: a. S/G 1 A level will decrease and feed pump speed will decrease.
: b. S/G 1 A level will decrease ONLY.
: c. S/G 1 A level will increase and feed pump speed will increase,
: d. S/G1 A level will increase ONLY.
54.The following conditions exist on Unit 1:
-The reactor tripped from 40% power
- The trip was caused by RCS loop 1C low flow condition due to undervoltage for RCP 1C bus
- Power Range NIS channel N42 failed at 100% on the trip
- ESF bus 141 undervoltage occurred
- 1 A D/G automatically started and ACB 1413 is closed
- S/G levels lowest readings were - 19% (A); 25% (B); 22% (C); 20% (D)
What is the status of the Auxiliary Feedwater (AF) Pumps on Unit 1 for these conditions at ONE minute following the trip?
: a. Both AF pumps are running.
: b. ONLY the 1 A AF pump is running
: c. ONLY the 1B AF pump is running.
: d. Neither AF Pump is running Page 30 of 50
 
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R cct2r Op:;rct:r Examinati:n 55. W hich of the following describes the designed MINIMUM AFW pump and S/G configuration necessary to remove all of the reactor decay heat load following a reactor trip from 102% power?
. a. The 1 A AF pump supplying 500 gpm to at least ONE S/G with S/G blowdown manually isolated.
l b.' The 18 AF pump supplying 740 gpm to at least ONE S/G with S/G blowdown in service
: c. The 1 A and 1B AF pump supplying 500 gpm total flow to at least TWO S/Gs with S/G blowdown in service.
: d. The 1 A and 18 AF pump supplying 740 gpm total flow to at least TWO S/Gs with S/G blowdown manually isolated.
56.The following conditions exist on Unit 1:
- Reactor power - 100%
investigation has located a ground on the 125 VDC Normal supply to the 1 A D/G from DC 111.
What action is required to transfer DC Control Power to the reserve source?
The Reserve power breaker from...
: a. DC 111 will be closed after opening the Normal power breaker and the Reserve power breaker at the D/G control panel.
: b. DC 111 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks at the D/G control panel.
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: c. DC 112 will be closed after opening the Normal power breaker and the Reserve power breaker at the D/G control panel.
: d. DC 112 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks at the D/G control panel.
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Page 31 of 50
 
React:r Op3ratcr Extmination 57. Unit 1 was being synchronized to the grid when the following occurred:
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- Trip of 345 KV breakers resulted in deenergizing the SATs
- A steamline break occurred that resulted in containment pressure reaching 20 psig 20 seconds after the D/Gs output breakers have closed When would the 1 A SX pump re-start?
: a. Always following start of the 1A CS Pump.
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: b. Between the start of the 1 A CV pump and the 1 A RH pump on the SDRA contacts (UV).
: c. Between the start of 1 A CC Pump and the 1 A AF Pump on the SARA contacts (SI).
: d. Coincident with the starting of the 1 A and 1C RCFCs.
58.The following conditions exist on Unit 1:
- Unit is in MODE 3
- A cooldown had just been initiated
- Steam Dump Bypass Interlock control switches have just been taken to BYPASS
- No other operator actions have been performed
- The Steam Dump valves fail open and the following parameters are observed:
- RCS temperature - 537'F (A); 539'F (B); 538'F (C); 538'F (D)
- Pzr pressure - 1820 psig
- Pzr level - 10%
- S/G pressure - 850 psig (A); 740 psig (B); 800 psig (C); 715 psig (D)
- S/G flow - 1.0 Mlb/hr (A); 1.5 Mlb/hr (B); 1.1 Mlb/hr (C); 1.6 Mlb/hr(D) l
- The level in the RCDT has risen to the alarm setpoint (80%) for REACTOR COOLANT DRAIN TANK UNIT 1 LEVEL Hi-LO Assuming all systems are functioning correctly, what is the status of the RCDT system?
: a. BOTH RCDT pumps are running and flow is directed to the Holdup Tanks.
: b. BOTH RCDT pumps are running and flow is recirculated back to the RCDT.
: c. ONE RCDT pump is running and flow is directed to the Holdup Tanks.
: d. NEITHER RCDT pump is running and NO flow exists for the system.
Page 32 of 50
 
1 Rrctor Op::rator Examinttien 59. During at-power operations with systems in their normal alignment, what is a normal source of water to the Containment Floor Sump?
: a. Output from the reactor cavity sump.
: b. Leakoff from the #2 RCP seals,
: c. Leakoff from the reactor vessel flange.
: d. Valve packing leakage from the CVCS letdown isolation valves.
60.When aligned for normal operation (BwOP GW-1), how does the Waste Gas System respond to high pressure sensed at the in-service Gas Decay Tank?
An alarm is generated that...
: a. alerts the operator to plaw an alternate Gas Decay Tank in service.
: b. indicates auto swap of in-service Gas Decay Tank to selected backup Gas Decay Tank, and alerts the operator to align another standby Gas Decay Tank.
: c. indicates auto swap of in-service Gas Decay Tank to selected standby Gas Decay Tank and auto swap of standby Gas Decay Tank to new standby Gas Decay Tank.
: d. shuts down the Waste Gas Compressors and isolates the in-service Gas Decay Tank.
: 61. Area Radiation Monitor for Fuel Bldg Fuel Handling incident (ORE-AR055) is being manually Check Source tested. What is the response when the monitor's CHECK SOURCE (C/S) pushbutton is depressed at the RM-23 panel?
: a. The alarm and automatic action output will be blocked, and the RM-23 amber INTLK LED will be lit.
: b. The alarm and automatic action output will be blocked, and the RM-23 green AVAIL LED will-be lit.
: c. The alarm will be actuate when value is reached, and the RM-23 amber INTLK LED will be lit.
: d. The alarm will be actuate when value is reached, and the RM-23 red HIGH LED will be lit.
Page 33 of 50 l
 
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Ratcter Operatcr Examination
. 62.The following conditions exist on Unit 2:
I
- Refueling operations are in progress While using the Fuel Handling Building Crane to move new fuel into the Spent Fuel Pool, the radiation monitor ORE-AR039, Fuel Handling Building Crane Monitor, goes into alarm. What action is affected?
: a. Traverse of the Fuel Handing Building Crane bridge and trolley.
: b. Both lowering and raising the Fuel Hanaing Building Crane hoist.
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: c. Traverse of the Fuel Handing Building Crane trolley and raising the hoist.
: d. Raising the Fuel Handing Building Crane hoist.
l 63.The following conditions exist on Unit 1:
- A unit startup is in progress with reactor power raised above 18%.
l
. - Turbine is at 1800 rpm ready to be synchronized to grid.
- Motor driven feedwater pump is supplying the SIGs with Feed Reg Bypass valves in AUTO.
- Steam Dump demand in AUTO at 12%.
- Instrument air header pressure begins to slowly drop due to a leak j
If the leak CANNOT be isolated and instrument air pressure continues to drop, which of the l
following would occur?
. (Assume NO operator action taken.)
: a. AF recirculation flow to the CST would be lost due to AF recirc failing closed.
: b. Pressurizer level would increase due to 1CV121 failing open.
: c. The main turbine would auto runback due to Diaphragm Interface Valve (DIV) opening.
: d. RCS temperature would drop to 550*F due to steam dumps failing open.
l Page 34 of 50 i,
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R actor Op:rcter Examination 64.With the fire protection systems in their normal alignment, what is the affect of a loss of DC power? -
i Loss of DC control power to the...
: a. halon control cabinet will cause halon release in the OA Control Room HVAC Room.
: b. battery control panel will cause automatic start of the diesel driven fire pump.
: c. fire detection system will cause start of the motor driven fire pump.
: d.. carbon dioxide system will cause the master discharge valve to fail open pressurizing the CO2 header.
65.The following conditions exist on Unit 1:
- Reactor power is 30%.
- Rod controlis in Automatic
- Tref - 564*F
- Tave values - 564*F (A); 565'F (B); 565'F (C); 564*F (D)
- Power Range NI-31% (N41); 29% (N42),30% (N43); 30% (N44)
- Control bank D is at 156 steps.
Which condition would result in continuous rod withdrawal?
: a. Turbine first stage pressure PT-505 fails upscale.
: b. Power Range channel N41 fails upscale.
: c. Loop A Tcold fails downscale.
: d. Tref signal fails downscale.
Page 35 of 50
 
R:actsr Operator ExEmination 66. A Control Bank D rod was dropped from 156 steps. The P-A converter was NOT zeroed when directed by the procedure.
l Select the effect of NOT performing this action?
ai While performing the procedure, the C-11 Rod Stop will be received prior to realigning the rod.
: b. While performing the procedure, the Rod Insertion Limit Alarm will be received at a lower rod
- position than required.
: c. After the procedure is complete, Bank C control rods will begin insertion at a lower value of l-Control Bank D.
: d. After the procedure is complete, Bank C control rods will begin insertion at a higher value of l
Control Bank D.
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67.On Unit 1, a loss of all circulating water pumps has resulted in a reactor trip. All control systems respond as expected. Significant decay heat causes RCS temperature to increase following the trip.
. At what RCS temperature should temperature stabilize?
Temperature should stabilize at the saturation temperature for...
: a. 1030 psig.
: b. 1092 psig.
: c. 1115 psig.
l d.' 1175 psig.
68. lf Unit 2 is operating at full load, which group of conditions will result in an automatic reactor trip either directly orindirectly?
: a. RCP bus frequency (Hz):56.9 (Bus 156) 57.1(Bus 157) 56.9 (Bus 158) 57.2 (Bus 159) l-
: b. Power range (%):
107 (N41) 108 (N42) 108 (N43) 109 (N44)
: c. PZR pressure (psig): 2375 (PT-455) 2380 (PT-456) 2385 (PT-457) 2380 (PT-458)
: d. S/G C NR level (%): 35 (LT-537) 38 (LT-538) 38 (LT-539) 37 (LT-558) l Page 36 of 50 I..
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R:acter Op ratSr Examination 69.With the RCS at normal operating pressure and temperature, what is the condition of the steam entering the PRT at normal conditions, if a PORV opens? (Assume an ideal thermodynamic process).
: a. Superheated steam at 239'F.
: b. Superheated steam at 222*F.
: c. Saturated steam-water mixture at 239'F.
: d. Saturated steam-water mixture at 222*F.
70 What are the parameters used to calculate Subcooling Margin in the SPDS leonics if only the 1C RCP and 1D RCP are running?
: a. RCS wide range pressure from loop C hot leg and core exit thermocouple temperatures.
: b. Pressurizer pressure and core exit thermocouple temperatures.
: c. RCS wide range pressure from loop A and loop C hot leg, and RCS loop A and loop C hot leg temperatures.
: d. Pressurizer pressure and RCS loop A hot leg temperature.
71.The following conditions exist during performance of BwEP-0.
4
- Train A ECCS pumps failed to start.
- RCS pressure is 1350 psig.
- Containment pressure of 7 psig.
- Bus 142 has an overcurrent trip on the normal feeder breaker.
- Si actuated due to High Containment Pressure.
- The highest critical safety function is Yellow on Heat Sink.
- All other equipment and components operated as expected.
Based on the RCP Trip Criteria, the RCPs should...
: a. NOT be stopped because NO Si pumps or Charging Pumps are running.
: b. NOT be stopped because RCS pressure is above the trip setpoint.
: c. be stopped because Si flow is established to the RCS.
: d. be stopped because CC flowpath to the RCP motor oil coolers is isolated.
4 Page 37 of 50 1
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1.
l Rerct: rop ratarExamination l72.On a loss of seal injection to the RCPs, what criteria is used to determine if the RCPs should be tripped?
: a. High temperatures on the RCP seal or bearing outlet temperatures.
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: b. Time elapsed since loss of seal injection.
: c. RCP Thermal Bearing Cooling Water low flow alarms.
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: d. #1 seal leakoff flow rate decreases to zero.
73. Unit 1 is operating at 100% power when the following alarm is received:
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- RCP SEAL LEAKOFF FLOW LOW (1-7-C3)
The NSO investigates and reports the following additional information:
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- RCP 1 A seal injection flow is 10.7 gpm
- #1 Seal Leakoff Flow on 1 A RCP is 0.4 gpm l
- RCP 1 A Seal Water Outlet Temperature is 140*F and STABLE l
- RCP 1 A Bearing Outlet Temperature is 145'F and STABLE Based on the above information, which of the following events has occurred?
: a. RCP 1 A #1 Seal has failed closed l
: b. - RCP 1 A #1 Seal has failed open.
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: c. RCP 1 A#2 Seal has failed closed.
: d. RCP 1 A #2 Seal has failed open.
74.Given the following:
The plant is at 90% power with ALL controls in AUTO.
VCT level transmitter, LT-112, fails HIGH causing a letdown diversion.
l What will occur if NO operator action is taken?
i l-VCT level decreases...
: a. until Auto makeup starts and maintains VCT level.
: b. with NO auto makeup capability and charging suction shifts to RWST.
c faster than auto makeup input and charging suction shifts to RWST.
: d. until charging pumps lose suction and start to cavitate.
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I React 2r Operater Examinttien 75. Given the following after a reactor trip:
- THREE rods remain withdrawn.
- Due to equipment malfunctions boration is only available from the RWST.
- Charging flow rate 132 gpm.
- RCS boron concentration was 1050 prior to the trip.
- 120 gpm letdown in service.
l Of the listed times, which would be minimum acceptable time that boration from the RWST would have to occur?
a.1 Hour
: b. 2 Hours
: c. 3 Hours
: d. 4 Hours 76..The following conditions exist on Unit 1:
- The plant was shutdown 8% days ago to repair a steam generator tube leak.
- Reactor vessel level is at 397' 1" with Thot at 212'F.
- A loss of RHR pumps due to cavitation has occurred j
Which of the following is the smallest amount of flow that meets the minimum makeup flow required to maintain current RCS level?
l
: a. 80 gpm
: b. 72 gpm
: c. 59 gpm
: d. 45 gpm i
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Page 39 of 50 I
 
Rrct:r Op:ratar Examinatinn
. 77.The following conditions exist on Unit 2:
MODE 5 operation during normal cooldown RCS temperature - 195* F RCS pressure - 325 psig Train A RH in service, train B RHR tagged out for repairs
- What is the preferred method of core cooling if a loss of RH cooling occurs?
' Altemate RCS cooling using...
: a. bleed and feed using reactor head vents.
: b. the SIGs.
: c. normal charging and RHR letdown.
: d. St Pump cold leg injection 78.The following conditions exist on Unit 1:
- The reactor is shutdown.
- RHR is in shutdown cooling.
- RCS temperature is 300'F.
- RCS pressure is 160 psig.
- CCW surge tank levelis decreasing What leak locations will produce these indications?
: a. RHR Heat Exchanger
: b. Thermal Bearing Heat Exchanger
: c. Letdown Heat Exchanger
: d. Seal Water Heat Exchanger Page 40 of 50
 
_ _... _. _ _ _.. ~
R:act:r Optratur Extmin:tian 79.The following conditions exist on Unit 2:
t i
- Reactor power is 100%
- Pressurizer pressure control is in automatic.
What is th6 immediate response of the pressure control system if the Master Pressure Controller L
setpoint is inadvertently changed to 2330 psig (step change)?
i,
: a. PORV RY455A cpens and spray valves open.
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: b. PORV RY455A opens, spray valves open, and all heaters energize.
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. c. Spray valves open and proportional heaters go to minimum.
: d. Spray valves close and proportional heaters go to maximum.
80.The following conditions exist on Unit 1:
- Reactor power is 100%
- All systems are in automatic
- Channel 1 Pressurizer Pressure Channel (PT-455) was declared inoperable and taken out of service with the appropriate bistables placed in the tripped condition.
- Controlling pressurizer pressure channel (PT-457) fails high
[
Assuming NO operator action, what is the plant response to the channel failure?
: a. Both PORVs and both spray valves open resulting in a reactor trip from low pressurizer pressure followed by Si actuation.
: b. The reactor will trip immediately on high pressure, and safety injection will actuate on low L
pressure due to spray valve operation.
: c. Pressurizer proportional heaters will de-energize and spray valves will open resulting in an ~
OTdT runback prior to tripping, and safety injection will actuate due to low pressurizer pressure.
: d. Both PORVs and both spray valves remain closed while pressurizer heaters de-energize.
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Page 41 of 50
 
R:act:r Operat:r Examinaticn 81.The plant is operating at 100% power with all control systems in AUTO. The following parameters are noted:
- Letdown Hx outlet flow (F1-132) - 75 gpm
- Charging Header flow (FI-121) - 87 gpm
- Total seal injection flow (FI-142 -Fi -45) - 33 gpm What is the effect on total seal injection flow initially if controlling Pzr level channel LT-459 fails j
LOW?
. Total seal injection flow will...
: a. decrease to O gpm.
: b. decrease to approximately 20 gpm.
: c. remain approximately 33 gpm.
: d. increase to greater than 40 gpm.
82.The following conditions exist on Unit 1:
- At t= 0 sec, Turbine load was decreased below 352 MW (30% power)
- At t=240 sec, The running main feedwater pump tripped.
The reactor did NOT trip due equipment malfunction.
- At t=250 sec, All feedflow indications decrease to 0% flow
- At t=320 sec, All steam generator levels decrease below 15%.
Based on this information, AMS would.
: a. initiate at t=320 sec.
: b. initiate at t=345 sec.
: c. initiate at t=360 sec.
: d. NOT initiate becau?e 0-20 is cleared.
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Page 42 of 50 5
 
R :ctar Op;ratcr Extminati::n 83.The following conditions exist on Unit 1:
- Reactor startup in progress
-Intermediate power range indication: 2.5E-5 amp N35 & 2.8E-5 amp N36 1
- SOURCE RANGE PERMISSIVE P-6 permissive light clear l
- SOURCE RANGE TRIP ACTIVE permissive light clear
- Source Range Channel N31 High voltage power supply fails to half its normal value What indication (s) would be available to alert the operator to this failure?
: a. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate lower than expected.
: b. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate higher than expected.
: c. Annunciator SR HIGH VOLTAGE FAILURE (1-10-B1) will alarm when power exceeds P-10.
: d. Annunciator SR HIGH VOL lE FAILURE (1-10-B1) will re-flash when the voltage source fails.
84.The following conditions exists on Unit 2:
- Plant shutdown is in progress.
- All power range channels indicate 6% reactor power.
- Intermediate range channel N-36 fails HIGH.
What is the plant response to this failure?
: a. The reactor will trip on high IR flux, and source range trip will reinstate when N-35 decreases-below P-6.
: b. The reactor will trip on high IR flux, and source range trip will NOT be reinstated.
: c. The reactor will NOT trip immediately, but will trip when the source range trip is reinctated when N-35 decreases below P-6
: d. The reactor wik NOT trip, and source range trip will NOT be reinstated.
Page 43 of 50
 
L Rrect::r Op: rater Examinctlan 85.The following conditions exist on Unit 1:
- Reactor power is 75%
- Troubleshooting has commenced due to reduced condenser vacuum with the air ejectors out of service.
y
- Hogging vacuum pumps are aligned to the main condenser to aid in maintaining vacuum.
What would be an indication of a Steam Generator Tube Leak under these conditions?
: a. Increasing radiation level on 1RE-PR027, "SJAE/ Gland Steam Exhaust Monitor".
: b. Decreasing S/G lovel for ONE S/G.
: c. Increasing feedwater flow to ONE S/G.
: d. Decreasing charging header flow to RCS.
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86. BwEP-3 " Steam Generator Tube Rupture" is being performed in response to a tube rupture on 2C S/G. The cooldown has just been completed but the target temperature value selected by the operators was higher than that stipulated in the procedure.
What condition could result because of this error?
: a. Loss of RCS subcooling before RCS and ruptured SIG pressures are equalized.
: b. Increase in pressure of the ruptured S/G with resultant lifting of the SIG Safety Valve.
: c. Increase in pressure of the non-ruptured S/Gs with resultant lifting of their S/G Safety Valves.
: d. Filling the Pressurizer solid during the subsequent depressurization.
l I
Page 44 of 50
 
Rract::r Op;ratcr Examinaticn 87.The following conditions exist on Unit 1:
- The Unit was in MODE 3 at normal operating temperature and pressure prior to the event.
- A faulted steam generator has occurred.
- RCS hot leg temperatures - 547'F (A),544*F (B),545*F (C),547'F (D)
- RCS cold leg temperatures - 545'F (A), 530*F (B), 543*F (C), 545'F (D)
- S/G pressures - 700 psig (A),635 psig (B),690 psig (C), 705 psig (D)
- S/G flow - 0.85 MLB/hr (B)
- Containment pressure (Channel) - 8 psig (1), 7.5 psig (2), 7.5 psig (3), 8 psig (4)
Based on these conditions, a main steam line isolation should..
: a. have occurred because of the low pressure in at least ONE S/G.
2
: b. have occurred because the steamline high negative rate occurred in S/G 1P.
: c. NOT have occurred because Containment pressure is belaw the setpoint for the CNMT High-2 pressure signal.
: d. NOT have occurred because THREE S/Gs have pressures above the isolation setpoint and do NOT indicate high steam flow.
88.The following conditions exist on Unit 1 following a trip from 100% power:
- Pressurizer levelis 0%
- Pressurizer pressure is 1500 psig
- Containment Pressure is 16 psig.
- Tcold is 420*F for allloops.
Where is the location of the leak?
: a. On one loop RCS cold leg.
: b. On a Main Steam Line inside containment.
: c. In a Steam Generator Tube.
: d. On a feedwater line between FWRV and Associated FWlV,1FWOO9.
Page 45 of 50
 
l R act:r Op;rattr Examinatien i
89 iln accordance with BwOA SEC-3, " Loss of Condenser Vacuum", which of the following sets of conditions requires the operator to trip the reactor?
: a. LOW POWER TRIP BLOCKED P-8 annunciator - LIT Turbine load - 200 MW Condenser pressure - 5.2 " HgA
: b. LOW POWER TRIP BLOCKED P-8 annunciator-I.lT Turbine load - 300 MW Condenser pressure - G.3" HgA
: c. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 600 MW Condenser pressure - 7.2" HgA
: d. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 900 MW Condenser pressure - 7.8" HgA 90. Select the primary basis for rapidly depressurizing the steam generators during a Loss of All AC.
: a. To provide maximum core cooling until power can be restored.
: b. To minimize RCS inventory loss from RCP seals.
: c. To enhance restoration of S/G level from the diesel dr'ven AF pump.
: d. To increase subcooling of the RCS.
: 91. How would the sequencer operate if a Safety injection (SI) actuation occurs while the sequencer is sequencing loads in response to an ESF bus undervoltage condition?
: a. There will be no change in operation; the undervoltage sequence overrides tha SI sequence.
: b. The undervoltage sequencing stops, the sequencer immediately resets and SI loads NOT already running will sequentially start.
: c. The undervoltage sequencing stops, all started loads are shed, and SI loads will sequentially start.
: d. The undervoltage sequencing completes its cycle, then resets to SI mode, and Siloads NOT already running will sequentially start.
Page 46 of 50
 
RS ct::r Op::rcter Examination l
92.The following conditions exist on Unit 1:
i
- Bus 141 is powered from its normal source
- D/G 1 A surveillance is being performed with the D/G paralleled to the bus What would occur if a failure of the undervoltage relay results in a sensed undervoltage condition on Bus 1417
: a. SAT feeder breaker ACB 1412 and D/G feeder breaker ACB 1413 remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.
: b. SAT feeder breaker ACB 1912 and D/G feede> breaker ACB 1413 will open. After a 10-second delay, ACB 1413 will close and the Safe Shutdown loads will sequence.
: c. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The Safe Shutdown loads will sequence normally.
: d. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.
93. On Unit 1 power is lost to 120 VAC Instrument Bus 111 How are the ESF and Safe Shutdown loads affected?
: a. "A" Train ESF loads will NOT load on an SI signal, but Safe Shutdown loads will load on a UN signal.
"B" Train loads are NOT affected.
: b. A" Train ESF loads will load on an SI signal, but Safe Shutdown loads will NOT load on a UN signal.
"B" Train loads are NOT affected.
c.
"A" Train ESF loads will NOT load on an SI signal, and Safe Shutdown loads will NOT load on a UN signal.
"B" Train loads are NOT affected.
: d. "A" Train AND "B" Train ESF loads will NOT load on an Si signal, but Safe Shutdown loads will load on a UN signal.
l Page 47 of 50 l
 
R actcr Op:ratur Examination 94. Select the method used for transferring controls to the remote shutdown panels PLO4/05J.
: a. Placing applicable transfer switches in LOCAL on RSP.
: b. Opening the isolation switches in the Auxiliary Electric Room.
: c. Deenergizing normal control power to individual controls.
: d. Taking local controls out of the PULL-TO-LOCK position.
: 95. When inadequate core cooling exists, which of the following sets of actions states the proper sequence of the major action categories to be performed in accordance with BwFR-C.1,
" RESPONSE TO INADEQUATE CORE COOLING", for removing decay heat from the core?
: a. Reinitiation of safety injection; RCP restart; rapid secondary depressurization.
: b. Reinitiation of safety injection; rapid secondary depressurization; RCP restart.
: c. RCP restart; reinitiation of safety injection; rapid secondary depressurization.
: d. RCP restart; rapid secondary depressurization; reinitiation of safety injection.
96. High coolant activity has been detected and chemistry has determined that it is due to corrosion product activation.
Identify the effect of placing the cation demineralizer in service.
The cation demineralizer...
: a. tuill remove lithium so it should NOT be used in this condition.
: b. will cause the activity level to decrease as soon as it is placed in service.
: c. is NOT effective in removing corrosion product activity,
: d. is less effective than the mixed bed demineralizer so it is placed in service ONLY if decontamination factor is less than 10.
Page 48 of 50
 
R:act:r Op;ratar Examin:.ti::n 97.The following conditions exist on Unit 1:
- Reactor power was 8% prior to the event below.
- A failure in the feedwater control system caused ONE S/G level to exceed P-14.
l
- The main turbine tripped.
- S/G levels have returned to their normal level range
-The Startup FW Pump is running What are all the conditions that would have to be met to feed the S/Gs using the FWO34's Feedwater Tempering Flow Control valves?
: a. The FW lsolation Aux Relays would have to be reset and FWO35 Feedwater Tempering isol valves opened.
: b. The reactor trip breakers would have to be cycled, the FW lsolation Aux Relays would have to be reset and FWO35 Feedwater Tempering isol valves opened.
: c. The FW lsolation Main Relays and Aux Relays would have to be reset and FWO35 Feedwater Tempering Isol valves opened.
: d. The reactor trip breakers would have to be cycled and FW lsolation Main Relays and Aux Relays reset and FWO35 Feedwater Tempering isol valves opened.
98.The following conditions exist on Unit 1:
- A leak developed on the RCS loop C flow instrument piping.
- Coincident with the RCS leak, on the reactor trip a S/G PORV failed open and was later isolated.
- FR-P.1 was entered to due to an ORANGE PATH condition.
- Si actuated and has been reset.
- All RCPs are stopped.
~
- Conditions required to support an RCP start are met.
What is the basis for operation of a RCP7 Under the current conditions starting the RCP will...
: a. cause excessive thermal stresses in the stagnant loops.
: b. cause a pressure surge that will aggravate the PTS condition.
: c. provide mixing of the ECCS injection flow thereby decreasing the likelihood of PTS.
: d. increase the RCS cooldown rate thereby increase the likelihood of PTS.
Page 49 of 50
 
R:act:r Operatar Examinatian l
99. Why is it important to run the CRDM vent fans when performing a natural circulation cooldown?
: a. Aids the operator in maintaining subcooling in tha reactor vessel head.
: b.. Aids in natu al circulation flow through the RCS head region.
: c. Minimizes stresses on the reactor vessel head due to uneven cooldown.
: d. Aids in natural circulation flow through the RCS.
100.Why are the S/Gs depressurized to less than 670 psig according to BwCA-1.1, " Loss of Emergency Coolant Recirculation"?
: a. To allow maximum AFW flow to the S/Gs.
: b. To ensure adequate subcooling for restart of the RCPs.
: c. To set up conditions for controlled injection to the RCS from the accumulators.
: d. To decrease RCS temperature and pressure which reduces break flow in a LOCA condition.
Page 50 of 50 i
 
A GENERIC FUNDAMENTALS EIRMINATION
*i EOUATIONS AND CONVERSIONS 5ANDOUT BEBET DOUATIOms
= AC,4T
. P = P.10"''
6 = idh P=Poe ' *" '
= UAAT A = A,e ^*
~
i h OC at Circ CR (1 - K.grz) = CR (1 - K.cgg) 2 at Circ 1/M = CR /CRx t
Kerr " 1/ (1 p)
DRW = (*t,/$,
2 e
p = (K rr - 1) /K.cr e
F = PA SUR = 26.06/r 6 = pAv r=8-p 4% = 44Pu A.cz #
E = IR-p=$+
Eff. = Net Work Out/ Energy In 1 + K'"f f
- P ) + (%* - %*) + g(zz - z2) = 0 p(P 2
L = 1 x 10'' seconds 2g, g,
Aerr = 0.1 seconds"*
g, = 32.2-lbm-ft/lbf-sec*
CONVERSIONS 3.41 x 10' Btu /hr 1 Curia 3.7 x 10** dps 1 Mw
=
=
2.54 x 10' Btu /.hr 1 kg 1 hp 2.21 lba
=
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8.35 lba
~
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Page 1 of 1 '
1 i
KI.T Pi E USE l8 BORON DILUTION RATE NOM 0 GRAPH
~
1 1
TEMP (*F)
Milba)
POWER 509,342 l
2MO 525 531,756 l
500' 546,347 400.
596,763 l
' 300 300 636,314 I
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APPROVED 10 7984P(080587)18 NOV 271987 A
BRAgW gDw
 
REV. 53 LOSS OF CONDENSER VACUUN 1Bw0A UNIT 1-SEC-3 4
4 j
s
.I i
j i
C 10 0
N D
E "8 NOT N
ACCEPTABLE SE 8 c
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0 100 200 300 400
.500 600 700' 800 900 1000 1100 1200 NEGAWATTS I
APPROVED FIGURE 1Bw0A SEC-3-1 APR'211994 i
TURBINE LOAD -vs-CONDENSER PRESSURE BRAgDWOOD i
ON.styg agyggw i
i Page 9 of 9
 
. ~. _
. _ - =. -. -..
l 4 a e
t REV.57 LOSS RH COOUNG UNIT - 1 1BwOA PRI-10
\\
1 i
l MAKEUP 120.0
/ l
\\
110.0 mas i-w 4 =
ss 1s2 s =
100.0 I
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FIGURE 1BwOA PRI 10 3 Minimum PAakeup Flow Required to Match Boiloff
)
APPROVED.
(11/21/96)
Page 11 of 62 NOV 261996 BRAIDWOOD en stic arvirW
 
l REV?.-1D REACTOR TRIP RESPONSE
'18:EP
. WOG 1B
_ UNIT 1
.ES-0.1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED VERI
' ALL' CONTROL RODS FULLY Perform the following:
5 I (SE t"ED:
: a. IE two or, more rods are All rod bottom lights - Iitt 3Q1 fully inserted, e
IEEt[. innergency borate 1200. GAL (3600 GAL FRW RMST) for~each rod HQI fully inserted per I
1BwCA PRI-2, EMERGENCY
,.SORATION.,.,.f z
0' 9.
*b. Within 1 HOUR calculate 1
Shutdown. Margin..oer I!. -
1BwOS 1.1.1.1.e-1, ew ad
. SHUTDOWN K--
'TW j
.VERIFICATIch DURING
~ SHUTDOWN (1BwOSR 3.1.1.1).
.~
l APPRQVED UUN 101998 BHAIDWOOD ON SITE Review Page 7 of 27
 
l J
Rocct:r Oper;t:r Ap3w r Ksy 1.d 26.c 2.c 27.d 3.c 28.d 4.a 29.a 5.c 30.c 6.a 31.d 7.b 32.c 8'.a 33.b 9.b 34.c j
10.d 35.d 11.d 36.d 12.b 37.c 13.c 38.c 14.a 39.c 15.c 40.d 16.c
: 41. d 17.b 42.c 18.a 43.b 19 d 44.a 20.c 45.d 21.c 46.c 22.c 47.c 23.a 48.c 24. d 49.d 25.b 50.b Page 1
 
t RIcct:r Operator Artw(r Kiy 51.c 76.b 52.b 77.b 53.a 78.d 54.b 79.d j
55.a 80.b 56 b 81.d 57.c 82.b 58.d 83.a 59.a 84.b 60.b 85.a
: 61. b 86.a 62.d 87.a 63.b 88.b 64.d 89. b j
65.a 90.b 66.a
: 91. b 67.c 92.d 68.a 93.c 69.d 94.a 70.a 95.b
: 71. a 96.b 72.a 97.a 73.d 98.c 74.d 99.a 75.b 100.c Page 2
 
=- --.. _...
Question Evaluation of requirem:nt far" active' license An operctor sits for the NRC Licens3 Oper: tor Ex:mination (Initirl), successfully pass:s ths Examination and is granted an NRC Senior Operator License or Reactor Operator license this month. What are the requirements for having the license on ACTIVE STATUS?
: a. The individual must meet the time on shift requirements of SEVEN 8-hour shifts before the license is in ACTIVE STATUS.
: h. The license is considered in ACTIVE STATUS for the current quarter ONLY.
: c. The individual must meet the time on shift requirements of SEVEN 8-hour shifts to have a license lh ACTIVE STATUS for the next quarter.
: d. The license is considered in ACTIVE STATUS for the current and next quarter.
l Answer d Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98
- KA: 2.1.1 RO Value:
3.7 SRO value:
 
===3.8 Section===
PWG RO Group:
1 SROGroup:
1 l
Systemevolution MA i
Knowledge of conduct of operations requirements.
l Explanation of l
Answer Reference Title /FacNity Reference Number Revisio L.O.
Braid wood Ops Memo #2 87 issued 5/1/97 rev. O Swd Tsk List Task P1-AM-TK-180 I
Material Required for Examination Question Source:
New Question Modincation Method:
3uestion Source Comments:
i Comment Type Comment f
A,.
l l
l l
l eMay, July 24,1996 4:33:45 PM Page 1 of 127 Prepared by WD Associates, Inc.
 
l Question Directi:n of NLO personn:l The following conditions on Unit 1.
- Reactor power 45%
- 1 A and 1C Feedwater pumps are operating
- FW PUMP TURB BRNG OIL LEVEL HIGH LOW annunciator (1-16-D3) alarms and the SER monitor indicates a low level.
l
- An EA is dispatched and confirms a low level exists.
. In performing actions to correct the condition (per BWOP TO-08 " Filling a Turbine Feed Pump Oil R:servoir"), what is the normal relationship between the US, the NSO and the EA?
1 i
l
: a. The US will direct the EA's activities, but will inform the NSO before the job commences.
: n. The US will direct the EA's activities, and need NOT inform the NSO unless unit controls are affected.
: c. The NSO will direct the EA's activities, but will inform the US before the job commences.
: 4. The NSO will direct the EA's activities, and need NOT inform the US unless unit load is affected.
Answer C Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate.
9/14/96 KA: 2.1.1 RO Value:
3.7 SRO Value:
 
===3.8 Section===
PWG RO Group:
1 SROGroup:
1 SystenWEvolution KA Knowledge of conduct of operations requirements.
Explanation of Answer Reference Title / Facility Reference Number Revisio L O.
aidwood Task List Task P1B-AM-TK-130 Material Required for Examination Question Source:
New Question Modification Method:
. Question Sou'ce Comments:
r Comment Type Comment Friday, July 24,1996 4:33:46 PM Page 2 of 127 Prepared by WD Associates, Inc.
 
. - _ = _ - -
1 Question Operating Daily Ord:rs How is a procedura ch*ng2, which significantly chinges normal processes, procedurclly conysynd to Licensed members of the operating crew?
: a. The SM places the applicable information in the Daily Order Book, and issues an additional memo to all crew personnel that is initialed.
: b. The SM is informed by memo of the addition to the Daily Order Book, and makes an announcement of the addition during the shift briefing.
: c. The SOS places the applicable information in the Daily Order Book, and the individual operator is responsible for reviewing the Daily Order.
: d. The US places the applicable information in the Daily Order Book, and makes an announcement of the addition during the shift briefing.
Answer C Exam Level B Cognitive Level Memory Faciuty: Braidwood ExamDate:
9/14/98 KA: 2.1.2 RO Value:
3.0 sRo value:
 
==4.0 section==
PWG RO Group:
1 SROGroup:
1 systemIEvolution KA Knowledge of operator responsit2 ties during all modes of plant operation.
Explanation of Answer b
Reference Title / Facility Reference Number Section Page Revisio L. O.
BwAP 340-2 rev. 8 C.7.b.4) 14 Intro ta Main Control Room Ops Lesson Plan 5
Braidwood Task Ust Task P1-AM.TK.026 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment l
l iday, July 24,1998 4:33:46 PM Page 3 of 127 Prepared byWD Associates,Inc.
 
ouestion Procedure required usa 03 An cxampla of a licensed operator cvolution th t can be performed WITHOUT eith:r referring to en operations procedure or having a procedura in-hrnd is...
: a. Adjusting rod position following a boration.
: m. Starting the 1A Heater Drain Pump.
: c. Placing excess letdown in service.
d.1.atching and rolling up the main turbine.
Answer a Exam Level B.
Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: 2.1.23 RO Value:
3.9 SRO Value:
 
==4.0 Section==
PWG RO Group:
1 SROGroup:
1 Systemevolution MA Ability to perform specific system and integrated plant procedures during all modes of plant operation.
sr.
s-- f - _ og Answer Reference Title / Facility Reference Number Section Page Revisio L O.
~pg 4,5 rev.12 Use Of Procedures For Operating Department BwAP 340-1 C.1.f.3)
Braidwood Task Ust Task P1-AM-TK-022 C
MaterialRequired for Examination Question Source:
New Question Modification Method.
Question Source Comments:
Comment Type Comment Friday, July 24,1996 4:33:47 PM Page 5 of 127 Prepared by WD Associates, Inc.
 
Question Use cf electrical pdnis Assuming en auto-close signal is continuously pres nt in th3 circuit for ths 1 A Si pump, which contact will be maintained open in order to prevent the starting relay (SR) from attempting repeated breaker closures onto a faulted bus?
(E 1-4030-Sl01 is provided for use.)
: a. LC SW n.52/b
: c. Y
: c. LS Answer c Exam Level B
~ Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 2.1.24 Ro value:
2.8 sRo value:
 
===3.1 section===
PWG Ro oroup:
1 sRooroup:
1 systan/ Evolution KA -
Ability to obtain and interpret station electrical and mechanical drawings.
Explanation of "Y"is an antipump relay that when prevented from energizing interru' pts the circuit that energizes the START Answer relayin tne AUTO mstart circuit C
Reference Title /Facally Reference Number section/Page Revisio L o.
Schematic Diagram Safety injection Pump 1A 20E-1-4030Sl01 Print Reading Lesson Plan Chap 3 pg 23 rev. 5 2c,3
~
Material Required for Examination Question source:
Facility Exam Bank Question Modification Method:
Editorially Modified Question sourca Comments:
Braidwood requal bank Comment Type Comment 4
tiday, July 24,1996 4:33.48 PM Page 6 of 127 Prepared by WD Associates, Inc.
 
Questien MOV taCout An operator is preptring en OOS th t d:signit:s 1CC685, RCP Therm I Barri:r CC Rsturn CNMT isolation valve, as an isolation point.
What is the acceptability of using this isolation point?
1; The OOS is...
: a. acceptable only if the MOV is tagged at its control switch, power supply and valve handwheel.
b, acceptable only if the MOV is tagged at its control switch, power supply and a blocking device is placed on the valve.
: c. NOT acceptable because the MOV fails to meet isolation requirements.
: d. NOT acceptable because the valve fails open on a loss of power.
l Answer a Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 l
.m: 2.2.13 RO value:
3.6 sRo value:
 
===3.8 section===
PWG Ro oroup:
1 sROGroup:
1 l
systemevolution KA Knowledge of tagging and cieerance procedures. f Explanation of Valve is MOV and requirements include tagging control switch, electrical power supply and local handwheel if Answer accessible.
Reference Title / Faculty Reference Number Section/Page Revisio L O.
SWAP 330-1 Out of Service Process D.4.a pg 12 l
D.4.c.1) pg 14 l
Naidwood Task List Task P1.AM-TK-010 Material Required for Examination I
Question Source:
New Question Modificati m Method:
Question Source Comments:
~ ' CommentType Comment l
l I
tiday, July 24,1996 4:33.49 PM Page 8 of 127 Prepared by WD Associates. Inc.
 
l Question RCS level discrepancy during refu ling Tha following conditions exist for Unit 1:
- Unit shutdown and cooldown initiated 120 hours ago
- Lowering of RCS level to the reactor vessel flange is underway 95*
- RCS temperature
- RCS level Control Room indicators: 1LI-RYO46 - 401' 0" 4
'1 LI-RYO49 -
402'1"
- RH loop 1 A in operation with " normal" indications What is the appropriate action for these conditions?
- c. The lowering of RCS level can continue.
: n. The level change must be stopped until the cause for the level discrepancy is determined.
: c. When temperature correction is applied to the highest Control Room level indication, the running RHR pump must be stopped to prevent cavitation,
: d. When temperature correction is applied to the lowest Control Room level indication, the available S1 Pump aligned for hot leg injection must be started.
Answer b Exam Level B c:...^ a Level Comprehension Faculty: Braidwood ExamDate:
9/14/98 KA: 2.2.26 RO Value:
2.5 sao value:
 
===3.7 section===
PWG Ro oroup:
1 sROGroup 1
SystemEvolution KA Knowledge of refuenng administrative requirements Explanation of With any level discrepancy, the reason for the discrepancy must be determin'ed before further draining can Answer continue.
steforence Title / Faculty Reference Number section/Page Revisio L 0.
BwoP RC4 Reactor Coolant System Drain D.1 12E1 12 2
SWOP 100 4 Refueling Outage lesson plan MaterialRequired for Examination Question Source:
Faculty Exam Bank Question ModBAcation Method.
Significar.tly Modified Question Source Comments:
Zioa exam ' bank Comment Type comment NRC Significant industry Event-s Frid y, July 24,1998 4:33:51 PM Page 11 of 127 Prepared by WO Associates, Inc.
 
Question RO duties in C::ntrol Room during refueling
;.- Whatis a responsibility of tha NSO during rcfueling operctions?
l
: a. Checking source range counts while a fuel assembly is being placed in the core.
: n. Ensuring water level in spent fuel pool is at least 23' above the fuel,
: e. Maintaining a 1/M plot while reloading fuel during a core shuffle.
: d. Monitoring the manipulator crane position by updating the Control Room tag board.
AnIwer 8 Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: 2.2.32 RO Value:
3.5 SRO Value:
 
===3.3 Section===
PWG RO Group:
1 SROGroup:
1 Syr.'em/ Evolution KA Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage f acility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
Explanation of Answer Reference Title / Facility Reference Number Section/Page Revisio L0 BwAP 200048 Reactivity Management F.2.h.8) pg 11 2E2 Braidwood Task Ust Task P1-QG-TK 051 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
+
Comment Type Comment Fridiy, July 24,1998 4:33.52 PM Page 12 of 127 Prepared by WD Associates, Inc.
 
.~
.... - -. ~.
. -. _. -.~ -. - -. -
Quesmon Radiition exposure detIrmin:ti:n
- An operctor h:s the following exposurs history this year until todty:
l Ocop Dose Equivalent (DDE) 210 mrem i
Jommitted Effective Dose Equivalent (CEDE) 45 mrem Shallow Dose Equivalent (SDE) 33 mrem Committed Dose Equivalent (CDE) 28 mrem i
l Today the operator was required to make two entries into containment:
Entry 1:
; Gamma dose - 52 mrem; Neutron dose - 24 mrem Entry 2:
Gamma dose - 124 mrem i
I i
How much radiation exposure is available to the operator if he has to make additional entries?
His available margin based on the routine Administrative Exposure Control Levels is...
l a.100 mrem for that day; 2484 mrem for the year.
b.100 mrem for that day; 2545 mrem for the year.
c.124 mrem for that day; 2569 mrem for the year.
- d.124 mrem for that day; 2614 mrem for the year.
l Answer b Esam Level B Cognieve Level Comprehension Faculty: Braidwood UsamDate:
9/14/98
: KA: - 2.3.1 RO Value:
2.6 SRO Value:
 
==3.0 Section==
PWG Ro oroup:
1 SROGroup:
1 1
SystenWEvolution l
A f
Knowledge of 10 CrR: 20 and related facility radiation control requirements.
l Explanation of Limits are 300 mrem routine DDE/ Day and 3000 mrem routine cumulative TEDE/ year. C. Neutron rad not 4
j Answer counted for delly & yearly; A. All counted for yearty; d. previous DDE+ CEDE only counted for year.
Reference Title /FacNity Reference Number Section/Page Revisio L O.
+
Selected SwRPs Lesson Plan Rev. 00 2,3A i
i Material Required for Examination j;
Question Source.
New Question Modification Method.
l Question Source Comments:
I Comment Type '
Comment i
I l
5 -
! Friday, July 24,1996 4:33:52 PM Page 13 of 127 Prepared by WD Associates, Inc.
I l
 
._~.
Question Fu:1 H:ndling Accident R:spons3 f
The following conditions exist on Unit 1:
- Refueling operations in progress I
- A HIGH alarm received on radiation monitor 1RE-AR012, Containment Fuel Handling incident When should the NSO initiate action and what action should he/she take from the control room?
Indication of a fuel handling accident is considered when a...
a.' report is received from personnel in containment. The operator starts the containment charcoal filter fans.
: b. report is received from personnel in containment. The operator actuates Unit 1 CNMT evacuation alarm.
: c. corroborating rise is indicated on monitor 1RE-AR011. The operator starts the containment charcoal filter fans.
: d. corroborating rise is indicated on monitor 1RE-AR011. The operator actuates Unit 1 CNMT evacuation alarm.
C Anewer d Exam I.svoi R Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 2.3.10 RO Value:
2.9 sRO Value:
 
===3.3 section===
PWG RO Group:
1 SROGroup:
1 systemevoluson KA Abimy to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
Empianation of Answer
.aference Title / Facility Reference Number Section/Page Revisto L O.
BwOA REF-1 Lesson Plan Rev.0 2,3,4 Material Required for Examination
~
rhdimi Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Friday, July 24,1996 4:33.53 PM Page 14 of 127 Prepared by WD Associates, Inc.
 
t l
euest&:n PIrf:rmance of Status Trees / Function Rist:rttiin 1
~
l The following conditions exist on Unit 1-
- A reactor trip has occurred and both reactor trip breakers are verified open
-The turbine has tripped
- BwEP-0 " Reactor Trip OR Safety injection" has been entered.
- BUS 141 ALIVE light is NOT lit with bus voltage at ZERO volts
- BUS 142 AllVE light is lit with bus Voltage at 4149 volts.
Which of the following describes the actions the operators are required to take?
: a. Continue with next step of BwEP-0.
: b. Turn on the synchroscope and manually close ACB 1412, SAT 142-1 feed breaker, l
: c. Manually start 1 A D/G and verify ACB 1413, D/G output breaker, closes.
: 4. Initiate actions of BwOA ELEC-3 and continue with next step of BwEP-0.
Answer d Esam Level B Cognitive Level Memory Facety: Braidwood ExamDate:
9/14/98 KA: 2.4.16 RO Value:
3.0 SRO Value:
 
==4.0 Section==
PWG RO Group:
1 SROGroup:
1 O
SystemEvolution KA Knowledge of EOP implementation hierarchy and coordineUon with other support procedures.
Explanation of Answer l
Reserence Title /Factity Reference Number section/Page Revisio L. O.
Reactor Trip or Safety Irgection BwEP 0 Step 3.b. RNO MP 8 Rx Trip or si Lesson Plan rev.11 1,3 MaterielRequired for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Friday, July 24,1998 4:33:53 PM Pape 15 of 127 Prepared by WD Associates. Inc.
r
 
m ouestion Applicability of EOP Foldout Paga l
From ths list of procedures id:ntified below, which h s(havo)" Transfer to Cold Leg Recirculation" on ths Operator Action Summcry Page?
(NOTE: The following procedures are in the E-ior CA-1 series:
BwEP-1 " Loss Of Reactor Or Secondary Coolant" i
BwEP ES-1.1 "Sl Termination" BwEP ES-1.2 " Post-LOCA Cooldown And Depressurization" BwEP ES-1.3 " Transfer To Cold Leg Recirculation" BwEP ES-1.4 " Transfer To Hot Leg Recirculation" l
BwCA-1,1 " Loss Of Emergency Coolant Recirculation" BwCA-1.2 "LOCA Outside Containment")
I
: a. BwEP-1, BwEP ES-1.1 through ES-1.4, and BwCA-1.1 through BwCA-1.2 procedures,
: n. BwEP-1, BwEP ES-1.1 and ES-1.2 procedures ONLY.
: c. BwEP-1 and BwEP ES-1.2 procedures ONLY.
: d. BwEP-1 procedure ONLY.
Answer b Exam Level B Cognitive Level Comprehension Facistty: araidwood ExamDate.
9/14/98 KA: 2.4.20 RO Value:
3.3 sRo value:
 
==4.0 section==
PWG Ro oroup:
1 sROGroup:
1 system 4 Evolution KA Knowled08 of OP* rational implications of EOP warnings, cautions, and notes.
Explanation of Answer staference Title / Faculty Reference Number section/Page Revisio L O.
AP-1 Loss of Reactor or Secondary Coolant Lesson Plan rev.11 1,10 Material Required for Examination Question source:
New Question Modification Method:
l Question source Comments:
Commett Type Comment Friday, July 24,1998 4:33:54 PM Page 16 of 127 Prepared by WD Associates, Inc.
t i
 
Question Id:ntification of in:perabia CR annunciators The following conditions exist on Unit 1:
- Reactor trip breakers status - OPEN
- RCS Tave - 557'F
- Pzr pressure - 2235 psig Annunciator RCFC VIBRATION HI (1-3-C5) has been in alarm for the past 1 % shifts due to a faulty vibration probe. While maintenance troubleshoots the vibration probe on RCFC.1C which of the following cctions is appropriate for this alarm window?
: a. The alarm should be acknowledged for each actuation and the SER monitored for valid alarm inputs.
: h. The alarm should be acknowledged for each actuation and operators stationed locally at each RCFC to monitor vibration.
: c. The alarm should have been silenced without acknowledgement after obtaining Unit Operating l
Engineer's permission and the SER monitored for valid alarm inputs.
: 4. The alarm should have been silenced without acknowledgement with US permission and operators stationed locally at each RCFC to monitor vibration.
1 An ww C Exami. eve B e; x t.svw : Comprehension Facety: Braidwood ExamDate' 9/14/98 l
KA: 2.4.31 RO Vdue:
3.3 sRO vehm:
 
===3.4 section===
PWG RO Group:
1 SROGroup:
1 sy.enwEveution MA Knowledge of annuncistors alarms and indications, and use of the response instructions Explanation of l
Answer l
Reference Titse/FacNety Reference Number Section/Page Revisio L 0.
RCFC VIBRATION HI /BwAR 1-3-C5 E.
1 51 HANDLING OF MAIN CONTROL BOARD and
~
RADWASTE PANEL ANNUNCIATOR ALARMS /
l BwAP 380-2 C.3 C.4 l
Braidwood Task List Task P1-AM-TK-033 i
Malertal Required for Examination l
Question Source:
New Question Modification Method.
Question Source Comments:
Comment Type Comment l
d y, July 24,1996 4:33:55 PM Page 18 of 127 Prepared byWD Associates,Inc.
 
Question Effect of XInon Transient & compensation A feed pump trip occurred r:sulting in a rapid power reduction on Unit 1. Pow:r was r:duced from 100%
st ady-stits conditions using a combin tion of rods end boration.
The following conditions exist for Unit 1 following stabilization-
- Reactor Power
.60%
- Delta-l target value - +2.0
- Control Bank D position - 160 steps withdrawn
- Tave - 572*F
-Delta-l - -10.5%
-Core Age - MOL What actions will be required to maintain t'he current power level and maintain Delta-l within its normal operating band over the next FIVE hours?
l
: a. Boration and control rod withdrawal, followed by dilution.
: n. Boration and control rod insertion, followed by dilution.
: c. Dilution and control ro'd withdrawal, followed by boration
: 4. Dilution and control rod inseftion, followed by boration.
Answer a Exam Level B C:.J ;; Level Application Facility: Braidwood ExamDate:
9/14/96 KA: 001 A2.06 RO Value:
3.4 sRO value:
3.7-section: SYS RO Group:
1 sROGroup:
1 sysionWEvolution Control Rod Drive System KA Ability to (a) predict the impacts of the following on the Control Rod Drive system and (b) based on those predictions, use procedures to correct, control, or miti0 ate the consequences of those abnormal operation:
Effects of transient xenon on reactMty Explanation of With delt-l near the negative limit of the band, boration would be initiated to to allow rod withdrawal and hence Answer shifting of power poduction toward positive delta-l (power shift toward top of core). Later as Xenon (neutron poison) builds in, dilution will be initiated to maintain power level
'heference Tkle/ Facility Reference Number section/Page Revisio L O.
DELTA I CONSIDERATIONS F.3,5,6 3,4-7 BwGP 100-8 BwGP 100-8 Lesson Plan rev 4 1
Material Required for Examination Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment Friday, July 24,1998 4:33:56 PM Page 19 of 127 Prepared by WD Associates, Inc.
 
- _ _ _ _ _.. _ _. ~... - _ _.. _ _ ~.
A problem with the rod control syst:m requires checking ssvercl rod bank circuits. Tha affected pow r cabinet repiirs are to be m ds by supplying pow r from thn DC hold supply cabin:t.
Nhat is the capacity of the DC Hold Supply Cabinet under'these circumstances?
: a. ONE control rod bank group can be placed on DC HOLD, and these rods will drop ONLY if the controls are taken to OFF at the DC. Hold cabinet.
: b. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, and these rods will drop ONLY if the controls are taken to OFF at the DC Hold cabinet.
: c. ONE control rod bank group can be placed on DC HOLD, and these rods will automatically drop.
l
: d. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, and these rods will automatically drop.
Answer C Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: 001 K1.03 -
RO value:
3.4 sRo value:
 
===3.6 section===
SYS RO Group:
,1 sRO Group:
1 systemevolution Control Rod Drive System
' ;,;, between Control Rod Drive System and the following' KA Knowledge of the Physical connections and/or cause-effect -
0 j
CROM
* = - - t et Only one GROUP of control mds can be placed on HOLD at a time in order to ensure the rods are held without Answer falling. Opening the reador trip breakers interrupts power to the power cabinet and DC Hold cabinet, so that power to the CRDM is intenupted when the breakers open Reference Title /FacNity Reference Number section/Page Revisio L O.
Rod Control System Chap 28 A.S.e pg 40 12 1,9 Material Required for Examination Question source:
New Question ModlAcation Method.
Question source Comments:
* CommentType Comment l
l I
l l
Friday, July 24,1996 4:33:57 PM Page 20 of 127 Prepared byWD Associates,Inc.
4
 
W Question RIlationship oflevels during refueling operations The following conditions exist for Unit 1:
- Mode 5
- RCS is draining to Pzr level of 40%
-lM calibrations have been completed for LT-RYO48, Refuel Cavity level, in preparation for further draining What is the relationship between Pzr level instrument LT-459, Pzr level instrument LT-462 and LI-RYO487 At epproximately 40% level indicated on LI-462, level on...
1
)
: a. Ll-459 and Ll-RYO48 will be offscale high.
: 6. LI-RYO48 will be just onscale and LI-459 will be offscale low.
: c. LI-4'39 will read higher than 40% and Ll-RYO48 will just be onscale.
: 4. Ll-RYO48 will be offscale high and LI-459 will read lower than 40%
Answer c Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98
)
j KA: 002 A1.11 RO Value:
2.7 SRO value:
 
===3.2 Section===
SYS RO Group:
2 SROGroup:
2 SystenWEvolution Reactor Coolant System
)
KA Ability to predict and/or monitor chan0es in parameters associated with operating the Reactor Coolant System controls including:
Relative level indications in the RWST, the refue8ng cavtty, the PZR and the reactor vessel during preparation for refueling 4-Explanation of Ll-462 is the cold calibrated Pzr level instrument and will read lower (but more accurately) than the hot Answer calibrated level instruments (LI 459/460/461) at lower RCS temperatures. The refueling cavity level instrument j
Just comes onscale at 40% Pzrlevel.
l
' maiorence Title / Facility Reference Number Section/Page Revisio L O.
REACTOR COOLANT SYSTEM DRAIN BWOP RC-4 D.2 pg 4 rev.12E1 Swop RC-4A5 BwCB % fig 31 BwGP 100-6 Refuel Outage lesson plan rev.12 1,2 MaterialRequired for Examination Question Source:
New Question Modification Method:
l Question Source Comments:
Comment Type Comment t
Friday, July 24,1998 4:33:57 PM Page 21 of 127 Prepared byWD Associates,Inc.
2
-~w
~,
 
~
Question '
RCS leak Det::cthn Systems
~
ThD following conditions cxist for Unit 1:
- Reactor power - 100%
- RCS activity is elevated, but below Technical Specification (CTS) levels
- Pzr pressure - 2225 psig l
- Pzr level - 44%
- PORV 1RY453 - dualindication
- Leak rate - 6 gpm in en attempt to isolate the leakage past the PORV, the Block Valve 1RY8000B was taken to close. The vrive failed to close and the operator placed 1RY456 in the CLOSE position. When conditions stabilize:
- Reactor power - 100%
- Pzr pressure - 2228 psig j
- Pzr level - 44%
How would the operator be able to tell if the PORV has closed?
\\
Position lights for PCV-456 showing CLOSE indication ONLY.
j
: n. PORV downstream temperature indication 1TI-463 dropping.
1
: c. Level change in RCDT.
: d. Lower readings for containment radiation monitors RE-0011N0012A.
%swer b Esam Level R c:.- ^ ;; Leves Comprehension Faclety: Braidwood ExamDate:
9/14/98 KA: 002 A3.01 RO Value:
3.7 sRO Value:
 
===3.9 section===
SYS no oroup:
2 sRooroup:
2 system / Evolution Reactor Coolant System KA ANuty to monitor automatic operations of the heactor Coolant System including:
Reactor coolant leak detection system 8=7'm '':. of Answer Reference Title /Facsity Reference Number section/Page Revisio L O.
rev51E2 1EwAR 12 C 4 task P1-OA-TK 058 Caldwood Task Ust Material Required for Examination Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment Friday, July 24,1998 4.33:58 PM Page 22 of 127 Prepared by WD Associates, Inc.
4
 
~
Question Us3 of Loop Isolati:n Valvis The following conditions exist on Unit 1:
- RCS Loop C is isolated for maintenance
- RCS Loop A had been isolated for maintenance
- RCS Loop A Hot Leg Stop Isolation Valve (LSIV) was opened at 1001
- RCS Loop A Bypass Stop Valve was opened at 1005 with relief line flow of 115 gpm verified
- RCS Loop A Cold Leg LSIV is closed
-RCS temperature - 110*F
- RCS Hot Leg Loop temperatures - 108'F (A); 119'F (B); 110*F (C); 125'F (D)
- RCS Cold Leg Loop temperatures - 103'F (A); 108'F (B); 90*F (C);
115'F (D)
- S/G levels (Narrow Range) - 20% (A); 30% (B); 15% (C); 32% (D)
What will occur when the operator takes the control switch for MOV-RC8002A (RCS Loop A Cold Leg LSIV) to OPEN at 15097 l
The valve...
: s. will travel fully open with NO automa' tic actu'ations.
i
: b. will travel fully open, and the AFW pumps get a start signal.
: c. remains closed because the temperature difference interlock remains active.
j
: d. remains closed because the timer interlock is still active.
Answer 8 Exam Level R cognitive i.evel Comprehension Facility: Braidwood Exam 0 ate:
9/14/98 u: 002 K4.09 RO Value:
3.2 SRO value:
 
===3.2 section===
SYS RO Group:
2 SROGroup:
2 systemIEvolution Reactor Coolant System KA Knowledge of Reactor Coolant System design feature (s) and or interiock(s) which provide for the following:
Operation ofloop Isolation valves.
Explanation of
. Answer Reference Title / Facility Reference Number Section/Page Revisio L O.
Simplified RCS/RC-1 valve interlocks /1 3
R: actor Coolant system lesson plan 8
9 Chipter 12 Material Required for Examination Question Source:
Facility Exam Bank Question Modification Method:
Signifcantly Modified Question Source Comments:
Question 30/35 on Braidwood 1996 NRC exam is about LSIV interlocks. Premise and answers signifcantly different. Question asked about interlock for opening HL LSIV.
Comment Type Comment day, July 24.1998 4:33.59 PM Page 24 of 127 Prepared by WD Associates. Inc.
 
~ - -.. -. - - -
.-... - -. - ~. -
Question RCP and Pzr spray cperations The following Unit 1 conditions exist:
140*F
- RCS temperature (Average CETC) 365 psig
- RCS pressure
- A bubble has just been drawn in the Pressurizer
- Allloops are filled and vented
- Preparations are in progress to start the first RCP for continuous run What is the effect of selecting the 1C RCP to start?
: a. Both Pzr Sprays will function normally for Pzr pressure control.
: b. Manual cycling of the Pzr heaters will be required for Pzr pressure control.
: e. PORV RY456 will open on high pressure from high pressure bistable PB456E.
: d. Normal Pzr spray will deliver minimal spray flow for Pzr pressure control.
Answer d Exam level B C.. a Level Memory Faculty: Braidwood ExamDate:
9/14/98 MA: 003 A1.06 Ro value:
2.9 SRO Value:
;3.1 Section: SYS RO Group:
1 SROGroup:
1 Systemevolution Reactor Coolant Pump System T KA AbiRy to predict and/or monitor chan0es in parameters associated with operating the Reactor Coolant Pump System controls PZR spray flow Explanation of Answer Reference Title / Facility Reference Number Section/Page Revisio L 0.
BwGP 100-1 Plant Heat up
: f. 57 pg 20
. rev 11 RwGP 100-1 Plant Heat up eson plan 12.,
1,2,3 MaterialRequired for Examination Question Source:
New Question Modification Method:
. Question Source Comments:
Comment Type Comment
*e
' day, July 24,1998 4:34:00 PM Page 25 of 127 Prepared by WD Associates. Inc.
 
.__m Question RCP Breaker &intrriocks The following conditions exist on Unit 1:
- Reactor power 26%
- Pzr pressure -2235 psig
- Pzr level - 35%
RCP 1 A breaker trips due to sensed undervoltage from bus 157. What is expected as a result of the trip of the RCP7 The reactor will trip due to the open RCP breaker,
: b. The reactor will trip due to RCS loop low flow condition.
: c. The reactor will be manually tripped by the operator.
: d. A normal plant shutdown will be initiated.
Answer c Exam Level R Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 003 K2.01 RO Value:
3.1 SRo value:
 
===3.1 Section===
SYS RO Group:
1 SROGroup:
1 SystemEvolution Reactor Coolant Pump System MA Knowled9e of electrical power supplies to the following;'
RcPS Explanation of No AUTO idp is expected due to power < P-8. Administrative direction for a RCP trip in these condiitons is a Answer manualtrip will be initiated.
Reference Title / Facility Reference Number Section/Page Revisio L O.
Chp 13, Reactor Coolant Pump lesson plan C. 4.a 2)/ pg 16 9
8 AC Electrical Distribution lesson plan chp 4 8
10b
'os Memo / special Op Order Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment l
l l
l l
l 4
i iday, July 24,1998 4:34:01 PM Page 27 of 127 Prepared byWD Associates,Inc.
i L
 
.a.
Question Chrrging & letdown flows (including sell inj;cti:n)
The following conditions exist on Unit 1:
- Reactor power - 100%
~ - PZR pressure - 2235 psig
- PZR level - 44% stable
- CV121 - In MANUAL
- CVCS letdown - Isolated due to leak in Letdown Hx
- CVCS Excess Letdown - In service with maximum flow of 20 gpm
- RCP seal injection - 1 A CV pump aligned to all RCPs
- RCP seal leakoff flow - 3 gpm (1 A); 3.5 gpm (18); 3 gpm (1C); 2.5 gpm (1D) l What flow is indicated on Charging Header Flow indicator, F1-1217 a 5 gpm
: b. 25 gpm c 32 gpm
: d. 65 gpm
.e An:wer c Exam Level R Cognitive Level Application Facility: Braidwood ExamDate:
9/14/98 KA: 004 A3.11 RO Value:
3.6 SRO Value:
 
===3.4 Section===
SYS RO oroup:
1 SROGroup:
1 system / Evolution Chemical and Volume Control System KA Ability to monitor automatic operations of the Chemical and Volume Control System including:
Charging / letdown Explanation of F1-121 Indicates total charging flow (chg header + RCP seal flow, less Chg pump recirc (60 gpm)), Flow An wor balance - Letdown: 20 + 12 = 32 & Chg: 0 + 20 + 12 = 32.
..nference Title / Facility Reference Number
.Section/Page Revisto L O.
CVCSI Schematic CV-1 Chp 15a Chemical VolumeControl System lesson plan 10 4,5,9,15
~ Materli Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment r v.
l Friday, July 24,1998 4:34:02 PM Page 28 of 127 Prepared by WD Associates, Inc.
l
 
_.m Quesuon Cilculation of diluti::n The following conditions exist on Unit 2:
- Unit is in MODE 5
- Unit burnup is 5700 EFPH in Cycle 7
- SDM - 1.3% DeltaK/K
- RCS pressure - 400 psig
- RCS average temperature - 195'F
- RCS boron concentration - 1006 ppm
- Differential boron worth - -10.75 pcm/ ppm
- PZR level - 32.3%
- SR NIS countrate - 10 cps, BOTH channels stable background levels
- An inadvertent dilution at 70 gpm begins at 1300 hours Assuming NO operator action is taken and PZR level remains constant over the time period, when would ths HIGH FLUX AT SHUTDOWN alarm actuate?
: a. Never, because BDPS will actuate prior to actuation.
b.1430 hours.
c c.1505 hours.
d.1734 hours.
Answer C Enam Level B c:.-
a Level Application FacNity: Braidwood ExamDate:
9/14/96 KA: 004 A4.07 RO Value:
3.9 SRO Value:
 
===3.7 section===
SYS RO Group:
1 SROGroup:
1 SystenWEvoluuon Chemical and Volume Control System KA Ability to manually operate and/or monitor in the control room:
sorstion/ dilution Explanation of Dilution rate dc/dt = (500)(C)(Y)/M where M is the RCS mass at the given temperature (200*F). M = 745,537 Answer Ibm; C = 1006 ppm (given); Y=70 gpm (given). The dil rate = 47.2 ppm /hr. HIGH FLUX AT SHUTDOWN alarms at 5 x background = 50 cps. With K1= 0.987 dK/K (p1=-0.01317), calculate K2 = 0.9974 DKr/K (p2=-0.00261). Delta-P = 1056 pcm.1056/-10.75=-98.2 ppm change required. Therefore the time required for the 98.2 ppm dilution is 98.2/47.2 = 2 hours 5 min. Difference in time based on use of Nomograph for RCS at normal pressure & temperature conditions. 'd' would only occur if count rate doubled in any 10 minute period. Assuming count rate increase is linear, for given dilution rate counts would change by 3 every 10 minutes.
Reference Titio/ Faculty Reference Number Section/Page Revisio L o.
RIactor Makeup Control system lesson plan 8
4,7,11 Source Range Nuclear instrumentation 6
6,10,11 Lesson plan Braidwood Curve Book Boron dilution rate nomograph Material Required for Examination Braidwood CURVE BOOK Figure 12.
Question Source.
New Question Modification Method:
Question Source Comments:
Comment Type Comment day, July 24.1998 4:34:02 PM Page 29 of 127 Prepared by WD Associates, Inc.
 
Topic Question B:ron mixing The fallowing conditions e.xist on Unit 1:
Reactor power was 95% prior to the event 4
- A turbine runback resulted in rod insertion with control rods in AUTOMATIC
- Annunciator ROD BANK LO-2 INSERTION LIMIT (1-10-A6) is lit Tha operators initiated an emergency boration per BwOA PRI-2 " Emergency Boration" and have verified control rods are now withdrawing. Why does the operator energize the Pzr Backup Heaters?
a This action...
: c. ensures Pzr boron concentration equalization with RCS by increasing normal spray flow,
: n. counteracts RCS cooldown due the boration by the additional heat from the backup
- heaters.
: c. prevents loss of Pzr level by increasing the volume of fluid maintained in the Pzr.
: d. guarantees adequate subcooling margin is maintained by raising the saturation temperature of the Pzr.
e 4
Answer a Exam Level R Cognitive Level Comprehension Faclety: Braidwood ExamDate:
9/14/98 KA: 004 K6.01 RO Value:
3.1 sRO Value:
 
===3.3 section===
SYS RO oroup:
1 sROoroup:
1 systemevolution Titie:
Chemical and Volume Control System KA Statement.
Knowled0e of the of the effect of a loss or malfundion on the following wM have on the Chemical and Volume Control System:
Spray / heater combination in PZR to assure uniform boron concentration Explanation of ta***r Reference Title /FacNety Reference Number Section/Page Revisio L O.
BwoA Prk2 Emergency Boration lesson plan 6
6 Reactor Makeup control system lesson plan 8
12 Material Required for Enamination Number (s) n Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment
.?
Friday, July 24,1998 4:34:03 PM Page 30 of 127 Prepared by WD Associates, Inc.
1
,r
 
Question R: circ intratirs to St Pumps & CV Pumps The following conditions exist on Unit 1:
- A LOCA has occurred
~ - Actions of 1BwEP ES-1.3, ' Transfer To Cold Leg Recirculation, have been completed.
l
- During alignmsnt,1CV8804A, RH HX to CENT CHG Pumps isolation Valve, l
failed to open and could NOT be manually opened.
l What is the status of the ECCS system?
: a. The RHR discharge headers are cross-tied with only RHR Pump 1B running and supplying suction to the SI pumps and Centrifugal Charging pumps from the B train connection.
: b. The RHR discharge headers are cross-tied with both RHR pumps running and supplying suction to the SI pumps only from the B train connection. The Centrifugal Charging pumps are stopped.
l
: c. RHR Pump 18 is discharging through the B Train cold leg injection headers and supplying suction to the SI Pumps. RHR Pump 1 A and the Centrifugal Charging pumps are stopped.
l
: 4. RHR Pump 1B is discharging through the B Train cold leg injection headers and supplying suction to the Si pumps and Centrifugal Charging pumps. RHR Pump 1 A is discharging through the A Train cold leg injection headers.
Answer d Exam Level B CognitiveLevel. Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 005 K1.12 RO Value:
3.1 sRO Value:
 
===3.4 section===
SYS RO Group:
3 sRoGroup:
3 systemevolution
. Residual Heat Removal System KA Knowled0e of the physical connections and/or cause-effect relationships between Residual Heat Removal System and the following:
safeguard pumps i
E-;
^m of CL recirc lineup has any ONE running RHR pump aligned to provide suction path to all other ECCS pumps (SI l
Answer
& CENT CHG). The discharge headers between RH trains are required to be separate so that the ONE running RH pump does not operate in runout condition.
Reference Title /FacNity Reference Number section/Page Revisio L C.
E.mtrgency Operating Procedures Less of Reactor or secondary coolant /
BwEP 1, BwEP ES 1.1-1.4 11 10 Chp 58 Emergency Core Cooling system Lesson plan 10 5,7,8,14 Material Required for Examination Question source:
New Guestion Modification Method:
- Question source Comments:
Comment Type Comment "id:y, July 24,1998 4:34:o4 PM Page 32 of 127 Prepared byWD Associates,Inc.
i 1
 
. -. -.. ~ - - ~-
- -. ~.. -. - -.... - - -.
cmeetion Fellure of Hx Outlet Vtiva The following conditions exist on Unit 1
- Unit is in MODE 4 during cooldown per 18wGP 100-5.following unit shutdown 38 hours ago
- RCS temperature - 340*F
- RCS pressure - 345 psig
- PZR level - 33%
- RHR pump 1 A is operating in Shutdown Cooling mode
- RH-618 A Hx Bypass Flow Control Valve is in MAN at 3000 gpm
- RH406 A HX Flow Control Valve controller demand is at 20%
- CV-128 RHR Ltdn Flow Contr Valve demand is at 100%
- PCV-131 is in AUTOMATIC set to maintain 350 psig A signal failure from the controller causes RH-606 to go fully closed. What is the system response to this frilure without operator action?
PCV-131 will throttle open due to lower RH discharge pressure.
: b. RCS pressure will increase due to RCS $eatup.
: c. Pressurizer level will decrease due to increased letdown flow.
: d. RH-610 will throttle open due to lower ~ RH flow.
Answer b Exam Level R Coennive Levd ' Application Faclety: Braidwood ExamDate.
. 9/14/96 KA: 005 K4.1o RO Value:
3.1 sRo value:
 
===3.1 section===
SYS RO Group:
3 sROGroup:
3 systenWEvolution ResidualHeat Removal System MA
. Knowled0e of Residual Hes* Removal System design feature (s) and or interlock (s) which provide for the followiry Control of RHR heet enchen0er outlet flow explanemon of RCS pressure will rise as fluid temperature increases due to loss of cooling flow through HX. IF flow Answer decreases system pressure downstream may decrease this will cause PCV-131 to throttle close in an attempt to raise pressure Reference Title /FacNity Reference Number section/Page Revisio L O.
~
RHR Cooldown/ RH-1 Schematic RH-1 1
Chp 18 Residual Heat Removal system 7
3,4,5,9 MaterialRequired for Examination Question source:
New Ometion Modification Method:
Question source Comments:
Comment Type Comment Friday, July 24,1998 4:34:o5 PM PeGe 33 of 127 Propered by WD Associates, Inc.
 
Question Syst!ms response is SI/Acti ns The following conditions exist on Unit 1:
- A plant heatup is underway
-MODE 3 has just been entered
- RCS pressure 450 psig l
SI Accumulator 1C was drained below required level during the outage for repair work. System configuration has NOT allowed refilling the Accumulator until now. The SI Accumulator line is being flushed in accordance with BWOP SI-14 "Si Accumulator Fill Line Flush" (Valve lineup includes: 1S1-8964, 1
SI Test Lines to Radwaste Isolation Valve, and SI-8888, S1 Pps to Accumulator Fill Valve, are open.1SI 8821 A, S1 Pump to Cold Leg Isolation Valve, and 1SI 8802A, Si to Hot Leg 1 A & 1D isol valve are l
closed). Si pump 1 A running. During the flushing, an inadvertent SI signal is generated.
What is the status of the ECCS based on the current alignment without operator action?
e.1B Si pump ONLY is running with injection flow to the RCS cold legs and to the Accumulator 1C fill line flush.
b.1 A Si pump ONLY is running with flow directsd to the Accumulator fill line flush ONLY.
: c. BOTH Si pumps are running with injection flow to the RCS cold legs and to the Accumulator 1C fili line flush.
: d. BOTH SI pumps are running with flow directed to the Accumulator 1C fill line flush ONLY.
Answer C Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 006 A2.13 RO Value:
3.9 SRO Value:
47 section: SYS RO Group:
2 sROGroup:
2 JystemEvolution Emergency Core Cooling System MA Ability to (a) prodk:t the impacts of the fo8owing on the Emergency Core Cooling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Inadvertent SIS actuation Explanation of Si pumps are operable; Sl8821 A remains closed; Sl8888 and Sl8964 remain open.
- Answer Reference Title / Facility Reference Number Section/Page Revisio L O.
Plant Heatup BwGP 100-1 F.49 pg 30 11 SI Accumulator Fill Line Flush BwOP Sl-14 6
Chp 58 Emefgency Core Cooling system Lesson plan 10 6,9 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment day, July 24,1998 4:34:06 PM Page 34 of 127 Prepared by WD Associates, Inc.
 
euestion 10CFR50.46 Design Crittris To meet ths 10CFR50.46 crittrin, ths ECCS Systam is d5 signed such that und:r cccident conditions it will maintain...
: a. total hydrogen production from zirconium-water reaction below maximum value of 5%.
: b. maximum fuel temperature at the inside surface of the cladding less than 2000*F.
: c. the core at least 5% shutdown to prevent an inadvertent return to criticality.
: d. fuel clad oxidation less than 17% of total clad thickness anywhere within the core.
Answw d Exam Level B Cognitive t.evel Memory FacMity: Braidwood ExamDate:
9/14/98 KA: 006 K3.02 RO Value:
4.3 SRO Value:
 
===4.4 Section===
SYS RO Group:
2 SROGroup:
2 systanIEvolution Emergency Core Cooling System KA-Knowledge of the effect that a loss or malfunction of the Emergency Core Cooling System wlR have on the following:
Fuel Explanation of Third selection addresses design criteria for reactivity control per CTS.
?
'Aeference Title /FacMity Reference Number
- Section/Page Revisio L O.
10CFR50/ 47 Chp 58 Emergency Core Cooling system
",.4 Lesson plan 10 2
Material Required for Examination Question Source:
FacAlty Exam Bank Question Modification Method:
Editorially Modified Question Source Comments:
Corrment Type Comment Friday, July 24,1998 4:34:06 PM Page 35 of 127 Prepared by WD Aasociates, Inc.
 
. ~..
a+
Evalu: tion of flow ECCS pumps The following conditions exist on Unit 1 i
' A LOCA has occurred
-Transfer to Cold Leg recirculation is required
- RCS pressure is approximately 50 psig l
What is the approximate total Si pump flow indicated on the main control board and how will this value l
change following transfer of BOTH trains of ECCS to cold leg recirculation?
Total Flow Flow Change 650 gpm Decrease
: n. 800 gpm Increase e.1050 gpm Decrease 1
4.1300 gpm increase i
Anewer d Exam Level B Cognitive Levd Comprehension Facety: Braidwood ExamDate:
9/14/96 KA: 006 K8.03 RO Value:
3.6, sRo value:
 
===3.9 section===
SYS Ro oroup:
2 000 oroup:
2
)
- systemevoluson Emergency Core Cooling System l
KA knowledge of the of the effect of a loss or malfunction on the following wm have on the Emergency Core tkW System:
safetyletection Pumps l
Explanation of Si pump design values provid e for 650 gpm flow per pump @ 1300 psig and 1300 gpm O 600 psig (or less).
Anewer The flow from the pumps increases since the RH pumps are now providing a suction pressure of approximately l
250 psig to the pumps instead of the lower pressure (30 psig or less) provided by the head associated with i
RWST Ievel.
~
J L
', Reference Time /Facielty Referen:e Number section/Page Revielo L O.
Chp 58, Emergency Cors cooling System Lesson plan 10 3,8a l
MaterialRequired for Examination Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment i
l l
l
~iday, Juh 24,1998 4:34:07 PM Page 36 of 127 Prepared byWD Associates,Inc.
I i
1
 
. _ ~
- Question PRT conditions causing ticrm/ response During shift turnover for Unit 1, the NSO not::s th3 following partmit:rs:
l RCS Tave. - 566.5*F Dzr pressure - 2235 psig Pzrlevel - 38.3%
PRT pressure - 4 psig PRT level - 74%
l PRT temperature - 98'F One hour later when annunciator 1-12-A7, PRT LEVEL HIGH LOW alarmed, the NSO notes the following parameters:
I RCS Tave - 566.2*F Pzr pressure - 2233 psig Pzrlevel - 38%
PRT pressure - 5.9 psig PRTlevel - 81%
PRT temperature - 96*F.
O What condition resulted in the change in parameters?
i l
PRT PW Supply inside Cnmt isol Valve RY-8030 opened,
: b. PRT to GW Comp Isol Valve RY-469 failed closed.
: c. CVCS letdown relief valve CV-8117 lifted.
: d. PORV RY-455A opened and reclosed.
Answer a Exam t.evel R Cognitive i.evel Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 2.4.50 RO Value:
3.3 SRO Value:
 
===3.3 section===
SYS
. RO Group:
3 SROGroup:
3
- system / Evolution Pressurizer Relief TanivQuench Tank System KA Ability to verify system alsrm setpoints and operate controls identified in the alarm response manual.
Explanation of The only input provided that would give a levelincrease and a temperatue decrease is the makeup from PW.
Answer Reference Title / Facility Reference Number Section/Page Revisio L. O.
Pressurizer Relief Tank Filling and Venting SWOP RY-3 3
PRT1.evel High law / SwAR 1-12-A7 51E1 Chp 14 Pressurizerlesson plan 9
13,14 Material Required for Examination Question Source:
New Question Modification Method:
Eddorially Modified Question Source Comments:
Ginna 9/90 NRC Exam Comment Type Comment Friday, July 24,1998 4:34:08 PM Page 37 of 127 Prepared by WD Associates, Inc.
 
Topic t.
j ouesuon Determination of effect of valve positioning Unit 1 is operating at 100% power in MOL conditions. All systems are functioning normally with rod
.:ontrol in manual.
What is the effect on plant operations if instrument air supplied to the CVCS letdown Hx component cooling water outlet valve, CV-130 is lost?
TCV-130 goes fully...
: a. shut and reactor power decreases due to boration in the CVCS demineralizers.
: n. shut and the CVCS demineralizers are automatically bypassed on temperature signal, l
: c. open and reactor power incret.ses due to deboration in the CVCS domineralizers.
: d. open and the CVCS demineralizers are automatically bypassed on temperature signal.
Anewer C Exam Level R Cognitive Level Comprehension Facility: greldwood ExemDete.
9/14/98 NA: 008 A2.05 RO Value:
3.3 sRo valur
 
===3.5 section===
SYS Ro oroup:
3 sRooraup:
3 synenmevosunon Component Cooling Water System MA Abity to (e) prodot the impacts of the following on the Component Cooling Water splom and (b) bened on thoes predictions, use precedures to correct, control, or mitl0ste the consequences of those obnormal operation-Essot of loss of instrument end control air on the poeWoa of the CCW valves that are air operated Explaneson of The CVCS letdown flow is overcooled and will give up boron to the resins in the CVCS demins (until a new Answer equilibrium value of boron reached in domins).
Reference T18e/iteceity Reference Number Section/Page Revisio L O.
ss of Instrument Air /10wOA Sec-4 Table A Component clo 2
_o Ch15a CVCS lesson ' lan 10 10,14 p
Service Air / Instrument Air Lesson plan review quest 14 8
9 MeterialRequired for Examination Question source:
New Question Modification Method:
Number (s) n i
Question source Comments:
Comment Type Comment
'May, July 24,1998 4:34:08 PM Page 38 of 127 Prepared by WD Associates, Inc.
 
Question Spray using Norm;lcnd Aux Spray What cra the partmrt:rs cnd vrlues used by tha operntor to ensure tho t:mperatura diff:rance betwun the PZR and ths spr y fluid cro within tho specified limit (s)in the PRESSURE AND TEMPERATURE LIMIT REPORT when initiating PZR spray?
: a. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor space temperature limit is 50*F, and for aux spray, the difference between Regenerative Hx charging inlet temperature and PZR vapor space limit is 320*F.
: n. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 50*F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is 320*F.
: c. For normal spray, the difference between RCS hot leg loop temperature an'd PZR vapor space
~
temperature limit is 320*F, and for aux spray, the difference between Regenerative Hx charging inlet temperature and PZR vapor space limit is 320*F.
: d. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 320*F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is'320*F.
Answer d Exam Level B
' CognWye Level -Memory 0 Facility: Braidwood ExamDate:
9/14/96 KA: 010 A1.08 RO Value:
3.2 sRO value:
 
===3.3 section===
SYS,y RO Group:
2 sROoroup:
2 systemEvolution Pressurizer Pressure Control System r-KA Ability to predict and/or monitor changes in parameters associated with operating the Pressurtzer Pressure Control System cont ois including:
Spray nozzle DT Explanation of Answer Wence Title / Facility Reference Number section/Page Revisio L O.
PressurizerTemperature Umit Surv/
18wOS 4.9.2-1 Pressurizer Spray Water Temperature
' Differential Umit surv/18wOS 4.9.2-2 1BwGP 100-1 Plant heat up lesson plan 12 1,2,3 Chp 14 Pressurizerlesson plan 9
7,8 Material Required for Examination Question Source:
New Question Modification Method:
significantly Modified
' Question source Comments:
Kewaunee 2/94 NRC Exam Comment Type Comment 1ay, July 24,1998 4 34:09 PM Page 39 of 127 Prepared by D Associates, Inc.
 
\\
l Question Evaluation of Pzr conditi:ns
~
i The following conditions exist on Unit 1:
- A load reject from 100% power has occurred
- Reactor power - 80%
i
- Pzr level - 56%
- Pzr vapor temperature - 655'F
- Pzr liquid temperature - 653*F
- RCS Tave - 578'F l
What is the current status of the Pressurizer based on given conditions?
Backup and proportional heaters are fully on.
: h. Proportional heaters are modulated on.
: c. Pzr sp[ay valves have modulated open.
: 4. Pzr spray valves and Pzr PORVs are open.
Answer C'
Exam Level B Cognitive Level Comprehension Faciety: Braidwood ExamDate:
9/14/98 KA: 010 K5.01 RO Value 3.5 sRO Value:
 
==4.0. lsection==
SYS Ro oroup:
2 sROGroup:
2 systenWEvolution Pressurizer Pressure Control System KA Knowledo' of th* OPerstionalimW of the fonowing concepts as they apply to the Pressurtzer Pressure Control System:
Determination of condition of fluid in PZR, using steam tables Explanation of At 655'F, saturation pressure is 2272 psig. At this pressure, with current PZR level deviation <5% of program Answer level (53%), the sprays are the only component "on".
Reference Title / Faculty Reference Number section/Page Revisto L. o.
'tr Pressure Control / RY-2 Pzr Pressure Setpoints 9
5,6,7 Chp 14 Pressurizerlesson plan St:am tables Saturation table Material Required for Examination Steam Tables uestion source:
FaciHty Exam Bar.k Question Modification Method.
Concept Used Q
Question source Comments:
Braidwood 1997 NRC exam Comment Type Comment Friday. July 24,1998 4:34:10 PM Pa0e 41 of 127 Prepared by WD Associates, Inc.
4
 
Question Pzr Lcvel React::r Trip The following conditions exist on Unit 1 with all controls in normal linaup:
- Reactor power - 30% stable
- RCS Tave - 564.5'F
- Pzr pressure - 2230 psig
- Pzr level - 36%
Th3 pressurizer level controller 1LK-459 output fails low. What automatic actions result assuming NO operator action taken?
: a. The reactor will trip on high pressurizer level ONLY.
: b. Letdown will isolate on low pressurizer level and then the reactor will trip on high pressurizer level.
: c. The reactor will trip on high pressurizer pressure ONLY.
: d. Letdown will isolate on low pressurizer level and then the reactor will trip on RCS low pressure.
An:wer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/96 KA: 011 K1.04 RO Value:- 3.8 sRO Value:
 
===3.9 section===
SYS RO Group:
2 sROGroup:
2 systerrWEvolution Pressurizer Level Control System KA Knowledge of the physical connections and/or cause-effect relationships between Pressurizer Level Control System and the RPS Explanation of NOTE that this failure is like the failure of the controlling level channel high in that charging flow falls to Answer minimum. At 17% level, letdown isolates charging continues at minimum (52 gpm) and Pu level sises to high level trip setpoint.).
Reference Title / Facility Reference Number Section/Page Revisio L O.
zr Level Control schematic RY-3 Pzrlevel setpts 2
Chp14 Pressurizerlesson plan 9
21 Material Required for Examination
~ Question Source:
Facility Exam Bank Question Modification Method:
Significantly Modified Question Source Comments:
Comment Type Comment Friday, July 24,1998 4:34:11 PM Page 42 of 127 Prepared by WD Associates, Inc.
 
Question Operatirn of BOTH Bypass Trip Breakers Th3 following conditions exist on Unit 1:
- Mode 3 NOT NOP with reactor trip breakers (RTA and RTB) closed
- Testing of reactor trip bypass breakers underway
- Reactor bypass breaker B (BYB) is racked in and closed
- An operator begins to perform test with reactor bypass breaker A (BYA).
What occurs as the operator operates the breaker BYA7 When reactor bypass breaker BYA is...
: e. locally closed, ONLY breaker BYB will trip.
: b. racked in to the CONNECT position, DNLY breaker BYB will trip.
l
: c. locally closed, all reactor trip and bypass breakers will trip.
: 4. is racked in to the CONNECT position, all reactor trip and bypass breakers will trip Answer C Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: 012 A3.07 RO Valuer 4.0 sRO Value:
 
==4.0 section==
SYS RO Group:
2 SROGroup:
2 system / Evolution Reactor Protection System KA Ability to monitor automatic operations of Me Reactor Protection System including:
Trip breakers Explanation of Closure of the second BYB results in SPSS generating a GENERAL WARNING on both trains which would Answer open all trip and bypass breakers.
Reference Title / Facility Reference Number Section/Page Revisio L 0, 3F setpoints Schematic EF-2 Rx Trip Byp brkr trips 5
wh 60a SSPS lesson plan 3
6,9 Material Required for Examination Question Source:
Facility Exam Bank Question ModlScation Method:
Editorially Modified Question Source Comments:
Comment Type Comment l
l Frid:y, July 24,1998 4:34:11 PM Page 43 of 127 Prepared byWD Associates,Inc.
 
-...-~-
Question
_ Input that can be bypass & conditi:n The following conditions exist on Unit 2:
- Unit shutdown is in progress
-Reactor power - 20%
- RCS Tave - 562*F
- Pzr pressure - 2235 psig
- Pzr level - 32%
l
- First stage turbine pressure channel PT-506 fails high l
l What affect does this failure have on operations as unit shutdown is continued, if NO action is taken for the failure?
: a. At 10% power, the reactor will trip if the Source Range Block RESET pushbuttons are depressed.
: b. At 9% power, the reactor will trip if an RCP trips.
: c. At 7% power, the reactor will trip if the TURBINE TRIP pushbuttons are depressed.
: d. At 5% power, the reactor will be manually tripped as during a normal shutdown by BwGP 100-5.
l Answer d Exam Level B Cognitive Levet Comprehension Facility: Braidwood ExamDate:
9/14/96 MA: 012 A4.03 RO Value:
3.6 sRO Value:
 
===3.6 section===
SYS RO Group:
2 SROGroup:
2 systemIEvolution Reactor Protedion System KA Ability to manually operate and/or monitor in the control room:
Channet blocks and bypasses l
Explanation of PT-506 failure results in P13 interlock NOT cleadng when turbine power falls below 10%. This also feeds into Answer P7 "AT POWER TRIPS" intedock also remains active. Tdps affected: 1) 2 loop loss of flow,2) Pu low press, l
: 3) Pu high level,4) RCP brkr open,5) RCP UV,6) RCP UF. At 10% power, the SR NIS should still be auto i
blocked by P-10 (active). The turbine is normally tripped from ~65 Mwe at 5% power per BwGP.
Reference Title / Facility Reference Number Section/Page Revisio L O.
Power Descension /1BwGP 100-4 note step F.27 16 j
l
~ESF Setpoints/ Schematic EF-1/ Permissive Rx Tdp 4
f Ch60b/ Reactor Protection system 6
4 l
Material Required for Examination l
Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Conwnent Friday, July 24,1998 4:34:12 PM Page 44 of 127 Prepared by WD Associates, Inc.
4 i
 
_.. - - - _....- - ~. - -
1
~
Topic ouestion OTdT inputs & sffect of changis The fcilowing conditions exist on Unit 1:
- Power range NIS reading - 100%
- Tcold - 553*F
- Thot - 608'F
- RCS total flow - 372,000 gpm j
- Pzr pressure -2215 psig
- Pzr level - 69%
How does the setpoint for Over Temperature Delta-T (OTdT) change when a listed parameter is chinged? (Consider each change individually)
Tha setpoint...
: a. increases if Power range NIS output rises to 102%.
: n. increases if total reactor flow decreases to 370,000 gpm.
: c. decreases if pressurizer pressure increasesjo 2235 psig.
: 4. decreases if the Thot rises to 612*F.
Answer d ExamLevel R cognitiveLevel Comprehension Facility: Braidwood ExamDate:
9/14/98 MA: 012 K5.01 Ro Value:
3.3 sRo value:
 
===3.8 section===
SYS Ro oroup:
2 sRooroup:
2 Time:
system / Evolution Reactor Protection System statement:
KA Knowledge of the operationalimplications of the following concepts as they apply to the Reactor Protection System:
DNB
*,"- -'; of a - NIS input is only for exceeding +/- delta-l; b - Flow affects when DNB occurs, but is NOT an input to OTdT; Answer c - Pressurize rise increases OTdT. That input to dT power for OTdT detefmination Number (s) n Reference Title / Facility Reference Number section/Page Revisio L o.
i!SF Setpoints/ EF-2 OTDT 5
l 6
3,4 CH 60b/ RPS lesson plan MaterialRequired for Examination Question source:
New Question Modification Method.
Question source Comments:
Comment Type Comment Friday, July 24,1998 4:34:14 PM Page 46 of 127 Prepared byWD Associates,Inc.
 
Quesuon CNMT Spray /Phise B The following conditions exist on Unit 1:
- Mode 3 with unit cooldown in progress
- RCS temperature - 520'F
- Pzr pressure - 1750 psig
- Pzr level - 33%
- MSIVs open What would directly happen if the operator were to take CONTAINMENT SPRAY & PHASE B ISOL switches for both trains to the ACTUATE position?
NO ESF actuations would occur.
: b. Containment Phase B isolation and Containment Ventilation isolation ONLY would be actuated.
: c. Containment Phase B isolation and Containment Ventilation isolation, and Containment Spray ONLY would be actuated.
: d. Containment Phase B isolation and Containment Ventilation isolation, Containment Spray, and Main Steamline isolation would be actuated.
c,-
Answer C Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 013 A3.01 RO Value:
3.7 sRO Value:
 
===3.9 section===
SYS RO Group:
1 sROGroup:
1 systenWEvoludon Engineered Safety Features Actuation System KA Ability to monitor automatic operations of the Engineered Safety Features Actuation System including:
l Input chant eis andlogic Explanation of Phase B, CS actuation and CNMT vent directly actuated. Main Steam isolation comes in auto on a rate CNMT Answer Hi-2 pressure (or manual MSLI) only.
Reference Title / Facility Reference Number section/Page Revisio L O.
ESF Setpoints/ EF-2 CS/ Phase B sig 5
CS/ MCB indications / CS-1, CS-2 CS Actuation sig 3
5 7,8
.4hp 61 ESF !ssson plan
~
Material Required for Exa.aination Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment Friday, July 24,1998 4:34:14 PM Page 47 of 127 Prepared by WD Associates, Inc.
 
Question FWlsolation - P14 The following conditions cxist on Unit 2:
- RCS temperature - 340*F i
- RCS pressure - 900 psig
- All MSIVs for the S/Gs are closed
- The MSIV Bypass _ valves are open
- The FW-035s, Feedwater Tempering Isolation Valves, are open
- The FW434s, Feedwater Tempering Flow Control Valves, are closed
- (opened periodically for level control) l
- Feedwater pump 2C is reset and latched on turning gear
- The Start Up Feedwater pump is running The level in the S/G 2B rises to 90%. How is the plant affected?
: a. No actuation occurs because of the position of the MSIVs.
: b. The 2C Feedwater pump and Start Up Feedwater pump trip.
: c. The 2C Feedwater pump trips and FW-035 v,alves c;ose.
: 4. The 2C Feedwattr pump and Start Up Feehater pump trip, the FW-035 valves close, and the MSIV Bypass valves close.
Answer C Exam Level R Cognieve Level Comprehension FacWty: Brakhvood ExamDate:
9/14/98 KA: 013 K4.13 RO value:
3.7 sRo value:
 
===3.9 Secuen===
SYS RO Group:
1 SROGroup:
1 SyseenWEvolution Engineered Safety Features Actuation System KA-Knowledge of Engineered Safety Features Actuation system design feature (s) and or interlock (s) which provide for the following:
MFWisoistion/ reset Explanation of Having Loop Isolation Stops closed does not defeat P-14.
Answer Reference Twe/FacMMy Reference Number Section/Page Revisto L O.
"Feedwater simple / FW-1 FWI signalt.
4
- SGWLC/ FW-2 S/U Flowpaths O
Chp61 ESF lesson plan 5
7 Materiel Required for Examination Question Source:
New Question ModWication Method
* Question Source Comments:
Comment Type Comment iday, July 24,1998 4.34:15 PM Page 48 of 127 Prepared byWD Associates,Inc.
 
Question ROD BOTTOM Alirm cper;ti n During a r :ctor startup, whzn does ths ROD AT BOTTOM alarm becoma activa for each control bank?
The alarm will actuate for a dropped rod for...
: c. any Control Bank whenever Control Bank A DRPI output is above 9 steps.
: b. each Control Bank ~whenever that Control Bank demand position is above 3 steps,
: c. each Control Bank whenever that Control Bank DRPI output is above 9 steps.
: d. Control Banks A, B and C whenever their Control Bank demand position is above 9 steps, and for Control Bank D whenever Control Bank D demand position is above 3 steps.
j Answer C Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: 2.4.31 RO Value:
3.3 sRO value:
 
===3.4 section===
SYS RO Group:
2 SROGroup:
1 systenWEvolution Rod Position Indication System MA
- Knowled0e of annunciators alarms and indications, and use of the response instructions.
Empianation of Note that the ROD BOlTOM comes direfctly from the DRPI unit with a setpoint of 9 steps; the alann actuates Answer when rod position is detected at 3 steps (or,less).
j Reference Title / Facility Reference Nunber SectiordPage Revisio L O.
ROD at Bottom /1BwAR 1-10-E6 2
Chp 29 rod Position Indication sys Lesson plan 9
4,5 i
Material Pequired for Examination Question dource:
New Question Modification Method:
Signifcantly Modified Question Source Comments:
Millstone 311/90 NRC Exam -
Comment Type Comment
?
i l
l iday, July 24,1998 4:34:16 PM Page 50 of 127 Prepared by WD Associates, Inc.
l l
 
Queenon SR NIS discriminat::rfailure How woul'd ths frilurs of tha pulse h::ight discriminator to a low valus affret the indication of tho affected Source Range channel?
The output would...
: c. decrease due to electronic filtering which narrows the pulse height window.
: b. decrease due to failure in counting the higher amplitude neutron generated pulses,
: c. increase due to counting of the gamma generated pulses ONLY.
: 4. increase due to counting of the gamma generated pulses and decay alpha generated pulses.
Answer d-Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: 015 A2.02 RO Value:
3.1 SRO Value:
 
===3.6 Section===
SYS RO Group:
1 SROGroup:
1 System /Evoludon Nuclear Instrumentation System MA Ability to (a) predict the impacts of the folkWng on the Nw: lear Instrumentation system and (b) based on those predictions, use procedures to correct, control, or mitigste the consequences of those abnormal operatiort Fauty or erratic operation of detectors or compensaung w...r.-
Explananon of Pulse height discriminator used to set window to detect those pulses with en'ergy level high enough to be from Answer event associated with neutron detection. Gamma and other interactions such as the alpha decay of fission product daughters is of lower heigth (energy) and disciminator normally electronically removes.
Reference Tine / Facility Reference Number Section/Page Revision L O.
Source Range Detector schematic N14 4
Chp 31 Source Range Nuclearinst 6
3 Material Required for Examination Question Source:
New Question Modification Method:
Queouon Source Comments:
Comment Type Comment l
Frid2y, July 24,1998 4:34:17 PM Page 52 of 127 ~
Prepared by WD Associates, Inc.
1
 
Quesuon SR NIS -loss of control power The following conditions exist on Unit 1:
- RCS at NOT NOP
- Reactor trip breakers - closed
- Source Range readings:
N31 - 18 cps N32-22 cps What indication would the operator observe if Control Power was lost to the N31 Drawer?
The N31 meter would read...
: c. downscale, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.
: n. downscale, the associated drawer bistable lamps lit, and reactor trip breakers open.
c.18 cps, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.
4.18 cps, the associated drawer bistable lamps lit, and reactor trip breakers open.
Answer d Exam Level B C.- ^W Level Comprehension Facility: Braidwood ExamDate:
9/14/98 3
KA: o15 K2.01 RO Value:
3.3 sRO Value:
 
===3.7 section===
SYS RO Group:
1 SROGroup:
1 systemevolution NuclearInstrumentation System KA Knowledge of electrical power supplies to the following:
Nis channels, components, and interconnections Explana6cn et Control power loss affects bistables which trip but NOT drawer instrument indication which is from Instrument
. Answer Power source.
Reference Time /FacNity Reference Number Section/Page Revision L O.
Source Range Detector Schematic N1-4 loss of Control power 4
Ch 31 Source Range NuclearInst 6
8.b Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Friday, July 24.1996 4:34.18 PM Page 53 of 127 Prepared by WD Associates, Inc.
 
m+
Evd for 1M - Eightfold incroise The f:llowing conditions exist on Unit'1:
- A reactor startup is about to be performed
- All shutdown banks are fully withdrawn
- All control banks are fully inserted
- An ECC records the following:
Predicted Critical Position (ECP) '- 130 steps on'CBD Max rod position - 231 steps on CBD Min rod position - 58 steps on CBD The following parameters were recorded during the rod withdrawal:
ROD HEIGTH N31 cps N32 cps 0 on CBA 25 23 178 on CBA 34 31 178 on CBB 58 62.
178 on CBC 116 106
~
80 on CBD 200 182 92 on CBD 237 225 When was the first time the operator was required to determine the Predicted Critical Position?
: e. At 50 steps on CBA, with N32 as the designated Source Range detector.
: b. At 113 steps on CBC, with N31 as the designated Source Ra'nge Detector.
: c. At 80 steps on CBD, with N31 as the designated Source Range detector.
: d. At 92 steps on CBD, with N32 as the designated Source Range detector.
Answer c Exam Level R cognitive Level Comprehension Faciuty: Braidwood ExamDate:
9/14/98 KA: 015 K5.06 RO Value:
3.4 sRO Value:
 
===3.7 section===
SYS Ro oroup:
1 sRooroup:
1 systanevolution Nuclearinstrumentation System J
1 KA Knowledge of the operationalimplicatione of the following concepts as they apply to the Nuclear instrumentation System:
Suberttical multiplications and NIS Indications E C - " of During reactor SU, hold point for ICRR determination is performed for each Control Bank at 50 steps and 113 steps withdrawn. The actual detemination of Predicted Critical Position is required at the eight-fold count An:wer increase holdpoint.
' Reference Title /Factity Reference Number section/Page Revision L O.
1BwGP 100-2 Reactor Startup 18wGP 100-2A1 12 13 2
1BwGP 100-2A1 Lesson plan Material Required for Examination Question source:
New Question Modification Method.
Question source Comments:
Frid y, July 24,1998 4:34:19 PM Pa0e 55 of 127 Prepared by WD Associates, Inc.
4
 
Question NR RTD Failure cffects The following conditions exist on Unit 1:
~
- Reactor power - 50%
- RCS Tave - 570*F (A); 569'F (B); 569'F (C); 570'F (D)
- RCS Thot - 585'F (A); 584*F (B); 583*F (C); 585'F (D)
- RCS Tcold - 555'F (A) 554*F (B); 555'F (C); 555'F (D) c
- Pzr pressure - 2235 psig
- Pzr level - 43 %
If loop B Thot output channel fails LOW, what is the response of Pzr level ?
Pr:ssurizer level will...
: a. Increases to 60%.
- b. remains the same.
: e. decreases to 25%.
: d. decreases to the letdown isolation setpoint.g Answer b Exam Level B Cognitive Loves Comprehension Facliity: Braidwood ExamDate:
9/14/98 KA: 016 K3.02 RO Value:
3.4 sRO Value:
 
===3.5 section===
SYS RO Group:
2 sROoroup:
2 systemevolution Non-Nuclear Instrumentation System KA Knowled9e of the effect that a loss w malfunction of the Non Nuclear instrumentation System will have on the fogowing:
PZR LCS Explanation of Thot fails to 510*F. With loop Tcold of 537'F, loop Tave is now 524'F. Auctioneered HIGH Tave is used Answer level program.
..eserence Title /FacMity Reference Number section/Page Revision L O.
PZR Level Control Schematic RY-3 2
18wCA Inst-2 leston plan 15 1
.,chp 12 RCS lesson plan 8
13 Material Required for Examination Question source:
Facility Exam Bank Question Modi 6 cation Method:
Concept Used Question source Comments:
Zion 2/92 NRC Exam (along with several others). Change includes failure of Thot loop, failure low and conditions Instead of dual condition.
Comment Type Comment Friday, July 24,1996 4:34:20 PM Page 56 of 127 Prepared by WD Associates, Inc.
 
. ~ -
l Question CETC failure effect cn Subcooling Monit:r/lconic Display With Unit'1 ct 100% pow:r end with normal operating parcmeters, how would th3 fritura of the HOTTEST Cora Exit Thermocoupin effect the rciding of subcooling margin on the SPDS leonics (CETC/SMM display) for each of the two situations below:
l Situation 1 - The CETC output fails high slowly 1
Situation 2 - The CETC output fails low slowly
: a. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and retum to normal when CETC output reaches 2300*F.
Situation 2: Subcooling margin will increase, then stabilizes when the CETC output is smaller than TEN other TCs.
: n. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and retum to normal when CETC output reaches 1200*F.
Situation 2: Subcooling margin will remain constant.
: c. Situation 1: Subcooling margin will increase to saturation then rise in superheat, and retum to normal when CETC output reaches 1200*F.
Situation 2: Subcooling margin will decrease, then stabilizes when the CETC output is smaller than TEN other TCs.
C
: 4. Situation 1: Subcooling margin will increase to saturation then rise in superheat, and retum to normal when TC output reaches 2300'F.
Situation 2: Subcooling margin will remain constant.
Answer a Exam Level R ca-!M Level Comprehension Faciety: Braidwood ExamDate:
9/14/98 KA: 017 K4.01 RO Value:
3.4 Sao value:
 
===3.7 Section===
"SYS RO Group:
1 SROGroup:
1 systemevolution
' In-Core Temperature Monitor System KA Knowledge of in Core Temperature Montor System design feature (s) and or interlock (s) which provide for the following:
Input to subcooling monitors Explanation of Fall high - Since it is initially tha highest, its input will remain active in average until high setpoint reached at An:wer 2300*F. Falllow. subcooling margin will slightly increase as temperature falls and input to average remains valid. When it reaches the 11th highest value, the subcooling margin will stabilize and reamin constant (assuming other 10 inputs do not change),
Reference Title / Facility Reference Number Section/Page Revision L. O.
j Ch pter 34b inadequate Core Cooling Detection 7
5,6 l
I Material Required for Examination 3-l Question Source:
Facility Exam Bank Question Modification Method Significantly Modified I
Question Source comments:
Braidwood 1997 NRc Exam. Difference in el answer choices similar promise in theory, but different wording.
l
. Comment Type comment hy, July 24,1998 4:34:21 PM Page 57 of 127 Prepared by WD Associates, Inc.
I
 
Question RCFC cperati:ns requirem:nts The following conditions exist on Unit 2:
- RCS Temperature - 342*F
- Pzr pressure - 375 psig
- 2A,2B, and 2D RCFCs are operating in high speed
- Unit 2 RCFC Dry Bulb temperatures are recorded as follows:.
-2A RCFC - 119'F
-2B RCFC - 118'F
-2C RCFC - 127'F
-2D RCFC - 121*F Which of the following identifies the equipment status and actions for the above conditions?
I-What are the MINIMUM requirements for operation for the Reactor Containment Fan Coolers (RCFCs)?
l l
l
: c. An additional RCFC must be started because the average of ALL the RCFC temperatures exceeds
~
l the limit.
: b. An additional RCFC must be started because ONE of the operating RCFCs temperatures is above l
the limit.
: c. NO action is necessary because ALL temperatures are within their appropriate limit.
d.'NO action is necessary because the average temperature of ALL operating RCFCs is below the limit.
Answer d Exam Levd R Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 l
KA: 2.1.32 RO Value:
3.4 sRO value:
 
===3.8 section===
SYS RO Group:
1 SRO Group:
1 systemevolution Containment Cooling System
* KA Ability to explain and apply a5 system limits and precautions.
l '
E;'--
- of Limits on CNMT temperature determined by average of temperatures for OPERATING RCFC outlet temps'.
I Answer Reference Title /Fecility Reference Number Section/Page Revision L O.
RCFC Start up 1BwOP VP-5 U2 Mode 1,2,3 shiftly daily Op surv 2BwCS-0.1-1,1.3 -
l chp 42 Containment Vent system lesson plan 4
6,10a Material Required for Examinatiorn i
l Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Friday, July 24,1998 4:34:21 PM Page 58 of 127 Prepared byWD Associates,Inc.
 
. Topic j
Question Sequence f:r securing CNMT Spray The following conditions exist on Unit 1:
- A LOCA has occurred
- Transition has been made to BwEP ES-1.3 " Transfer To Cold Leg Recirculation"
- Containment Spray actuated due to high containment pressure
- All systems and components operating as expected What conditions allow for termination of Containment Spray?
: a. ONE pump is stopped when containment pressure is less than 15 psig. The other pump is stopped when RWST LO-3 level is reached.
: n. ONE pump is stopped when containment pressure is less than 20 psig. The other pump is stopped after it has operated for a period of at least T'WO hours
: c. BOTH pumps are stopped when containment pressure is less than 15 psig and have operated for a
~
period of at least TWO hours.
: d. BOTH pumps are stopped when contininmek pressure is less than 20 psig and RWST LO-3 level is reached.
Answer c Exam Level B Co9nitive Level Comprehension ~ Faculty: Braidwood ExamDate:
9/14/98 KA: 026 A2.08 RO Value:
3.2 sRO Value:
 
===3.7 Section===
SYS RO Group:
2 sROGroup:
1 systenWEvolution Containment Spray System KA Ability to (a) predict the impacts of the following on the Containment Spray' System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation.
Safe securing of containment sprey when t can be done)
Explanation of Answer
 
==Title:==
Reference Title / Faculty Reference Number Section/Page Revision L O.
C:ntiinment Spray Schematic CS-1/ CS tefm 3
Loss cf Reactor or Sec Coolant /1BwEP-1 18 WOG-1B Ch 59 Containment Spray sys Lesson plan 6
14 Material Required for Examination Question Source:
New Question Modification Method.
Question Source Comments:
Comment Type Comment te
* I Friday, July 24,1998 4 34:22 PM Page 59 of 127 Prepared by WD Associates, Inc.
e e
e
 
~. _.
Question Pumpcperati:nintsrt cks The following conditions exist on Unit 1:
- LOCA is in progress 4
- Containment pressure - 15 psig
- Containment Spray actuated due to high containment pressure
- Containment Spray signal has been reset
-The actions of BwEP ES-1.3 " Transfer To Cold Leg Recirculation" have been completed
- Offsite power is then lost and the D/G output breakers have just closed i
onto ESF buses How are the Containment Spray Pumps re-started?
: e. The pumps will auto start 15 seconds following closure of the D/G output breakers.
: n. The pumps will auto start 40 seconds following closure of the D/G output breakers.
j i
: c. If the operator immediately places the CS & PHASE B ISOL switches for both trains to ACTUATE, the pumps will auto start 15 seconds following closure of the D/G output breakers.
c 4.-If the operator immediately places the PP 1_ TEST switches for both pumps in TEST, the pumps will auto start 40 seconds following closure of the D/G output breakers.
Answer C Esam Level R
% _ a Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 026 A4.01 Ro value:
4.5 Sao value:
 
===4.3 Section===
SYS RO Group:
2 SROGroup:
1 Systemevoludon Containment Spray System KA Ability to manually operate and/or monitor in the control room:
CSS controis Explanation of ' if the AUTO aduation input signal is absent and actuation input has been reset, manaul actuation is required Answer to get equiptment restarted following a LOSP.
Reference Title / Facility Reference Number Section/Page Revision L 0.
-Chp 59 Containment spray sys lesson plan 6
8,9 Material Respared for Examination Question Source:
New Question Modification Method:
i Question Source Comments:
Comment Type Comment t
Frid y, July 24,1998 4:34:23 PM Page 60 of 127 Prepared byWD Associates,Inc.
4
 
Question Charco11 Fitt:rs responsa ta d: lug)
Annunci; tor 0-33-C3, FILTER 1VP05FA TEMPERATURE HIGH, cl rms in thn Control Room whila 1VP02CA CNMT Charcoal Filter Fan is operating. The alarm condition is verified locally.
Which of the following describes the actions taken and/or the system response for the Containment Ventilation System?
: a. The deluge valve FP244A will automatically open and the fan will automatically stop.
: n. The control room operator will open the deluge valve FP244A and the local operator will then stop the fan.
: c. The local operator v/ill open the deluge valve FP244A and the fan will automatically stop.
: 4. The local operator will open the deluge valve FP244A and the control room operator will then stop the fan.
Answer c Exam Level R cognitive Level Memory Facility: Brakhvood ExamDate:
9/14/98 KA: 027 A4.03 RO Value:
3.3 SRO Value:
 
===3.2 Section===
SYS RO Group:
3 SROGroup:
2 SystemEvolution Containment lodine Removal System KA Abihty to manually operate and/or monitor in the control room:
CIRS fans g
Explanation of Operation of fp components associated with charcoal filter is local. But fan trips when deluge system An:wer activated.
Reserence Tme/FacNity Reference Number Section/Page Revision L O.
Filt:r 1VP05FA Temperature High
/18 war 1VP01J-1-A1 1
chp 42 Containment vent 7 purge 4
8 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
- CommentType Comment Friday, July 24,1998 4:34.24 PM Page 62 of 127 Prepared byWD Associates,Inc.
 
___.___.m Question RWST Purificati:n Loops The following conditions exist:
- Unit 1 - 20% power with load increase in progress
- Unit 2 - MODE 5 following refueling outage
- Unit 2 Spent Fuel Pool Cooling Loop is in service.
- Spent Fuel Pool Pump 1FC01P is OOS.
Which of the following is allowed under this situation?
Alignment and operation of...
: a. both Unit 1 PWST purification and Unit 2 RWST purification with flow through the Unit 2 Spent Fuel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.
: b. Spent Fuel Pool purification and Unit 1 RWST purification with flow through the Unit 1 Spent Fuel Pool i Demineralizer and Unit 1 Spent Fuel Pool Filter.
: c. Unit 2 RWST purification with flow through the Unit 1 Spent Fuel Pool Filter ONLY.
: d. Unit 2 RWST purification with flow through the Unit 2 Spent Fuel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.
j Answer d Exam Level R t. c..; Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: 033 K1.05 RO Value:
2.7 SRO Value:
 
===2.8 Section===
SYS RO Group:
2 SROoraup:
2 Systemevolution Spent Fuel Pool Cooling System KA Knowledge of the physical connections and/or cause-effect relationships between Spent Fuel Pool Cooling System and the RWsT Explanation of The lineup allows Unit 2 only to be used for Unit 2 RWST cleanup. Only one unit RWST can be aligned at Answer time due to common input path via Refueling Water Purification Pumps. With the cooling loop inservice only, the Unit's RWST may be aligned through the same Unit's, demin and filter train. Simultaneous use of Demin/ filter for the same Unit's SFP and RWST is NOT allowed due to concems of draining RWST.
Reference Title /Factitty Reference Number Section/Page Revision L O.
S/U purification sys to purify or Reciculate the RWST/ BwOP FC-7 7
Fuel Pool Cooling Schematic FC-1 3
Chp 51 Spent Fuel Pool Cooling And Cleanup 5
3 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment
. ridIy, July 24,1998 4:34:25 PM Page 64 of 127 Prepared byWD Associates,Inc.
f v
r-
 
Question St:am Dumpinput malfunctirn The following conditior.s exist on Unit 1 L
- Reactor power was 65% when the turbine tripped
- An ATWS occurred
- The reactor tripped 15 seconds later when B reactor trip breaker was locally opened l
- Reactor trip breaker A is failed closed
- RCS Tave - 559'F l
- Pzr pressure - 2255 psig l
- Steamline header pressure - 1100 psig
- No controls other than control rods and boration controls have been operated l
What is the status of the Steam Dump valves?
Stzm Dumps are...
: a. modulated open due to steam header pressure.
: b. modulated open due to Tave above no-load T' ave.
: c. closed because Tave is NOT greater than 3*F above Tref.
: d. closed because the dumps are NOT armed.
Answer b Exam Level B Cognieve Level Comprehension Faciuty: Braidwood ExamDate:
9/14/98 MA: o41 A3.02 RO Value:
3.3 sRo value:
 
===3.4 section===
SYS no oroup:
3 sRooroup:
3 systenvEvolution Steam Dump System and Turbine Bypass Control MA.
AtMty to monitor automatic operations or the Steam Dump System and Turbine Bypees Control including:
l RCS pressure, RCS temperature, and reactor power
(
s=;' - t of The "A" reactro trip breaker provides the arming signal for dumps on normal reactor trip. Since "A" RTB is still Answer closed, the steam dumps respond to event like load rejection, with C-7 load rejection (10% load decrease in 2 minutes sensed on PT-506) arming the dumps. Since the "B" RTP was opened, the steam dump controller l
does operate on the plant trip controller (No load Tave compared to Auct Hi Tave),
l
' Reference Title / Facility Reference Number section/Page Revisin L 0.
l Steam Dumpst Schematic MS-4 4
Chp 24 Steam Dumps Lesson Plan 7
3,4 Material Required for Examination Question source:
New Question Modification Method I
Question source Comments:
Comment Type Comment l
l t
day, July 24,1998 4:34:26 PM Page 65 of 127 Prepared by WD Associates, Inc.
4
)
 
ouwton Turbina C;ntrol response to Failed impuls3 Chinn11 The following conditions exist on Unit 1:
- Reactor power 28%
- All systems normal
-Turbine EHC Panel settings:
Turbine REFERENCE DEMAND - 580 MW l
Turbine REFERENCE -330 MW'
-The GO pushbutton is LIT What would be the DEHC System response to a slow failure to ZERO for the turbine impulse pressure chinnel that feeds into the DEHC7 L
- Turbine load will...
i decrease until the difference between REFERENCE and impulse pressure exceeds 30%, the operator would then be alerted to select MANUAL control.
: n. decrease until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%,
then load will stabilize in MANUAL control. J
: c. increase until the difference between REFERENCE and impulse pressure exceeds 30%, then load will stabilize in MANUAL control.
: 4. increase until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%,
the operator would then be alerted to select MANUAL control.
Answer c Eaam Level R cognieve Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 045 K1.20 RO Value:
3.4 sRO Vasue:
 
===3.6 section===
SYS RO Group:
3 sROoroup:
3 systemevolution Main Turbine Generator System KA Knowledge of the physical connections and/or cause effect relationships between Main Turbine Generator System and the Protection system
. r-4anation of When the difference between actual load and turbine impulse pressure (IMP IN) channel exceeds, circuit Answer AUTO transfer impulse feedback to IMP OUT Reserence Tme/Facally Reference Number section/Page Revision L 0.
TV/GV Control / schematic EHC-3/ Impulse 1
Chp 37a Main turbine Control And Protection 5
52 Material Required for Examination Question source:
New Question Modification Method:
Question source comments:
Comment Type Comment
. Friday, July 24,1996 4:34.26 PM Page 66 of 127 Prepared byWD Associates,Inc.
l
 
-~
i Question S/G L', vel program -low power The following conditions cxist on Unit 1:
l
- Reactor power 35%
l
- All systems normal What failure would cause a decrease in feedwater flow to all S/Gs?
: a. ONE condenser steam dump ONLY fails open.
: b. Main steamline pressure PT-507 fails low.
: c. ONE HD pump flow control valve ONLY fails open.
: 4. Main feedwater header pressure PT-508 fails low.'
Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 2.1.7 RO Value:
3.7 SRO Value:
 
===4.4 Section===
SYS RO Group:
1 SROGroup:
1 System / Evolution Main Feedwater System j
KA Ability to evaluate plant performance and make operational jud0ments based on operating characteristics, reactor behavior, and instrument Irderpretation.
Explanation of PT-507 fails lovi causes feed pump speed Io decrease which reduces FW pressure. This would initially result Answer 5 a decrease of flow to all S/Gs.
Reference Title / Facility Reference Number Section/Page Revision L 0.
Fw EH controls / schematic EHC-6/ DP 1
6 16 Chp 27 SGWLC MaterialRequired for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Friday, July 24,1998 4:34:27 PM Page 67 of 127 Prepared by WD Associates, Inc.
 
Question Eff:ct of f:.ilure of S/G stum pressura chann:l The following conditions exist on Unit 1:
- Reactor power 100%-
f
- All systems normal
- FT-512 selected for steam flow input into SGWLC for S/G 1 A What is the initial effect of the pressure transmitter associated with FT-512 failing low?
: a. S/G 1 A level will decrease and feed pump speed will decrease,
: b. S/G 1 A level will decrease ONLY.
: c. S/G 1 A level will increase and feed pump speed will increase.
: d. S/G1 A level will increase ONLY.
Answer a - Exam Level R Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 059 K1.04 RO Value:
3.4 sRO Value:
 
===3.4 section===
SYS RO Group:
1 sROGroup:
1 systemevolution Main Feedwater System KA Knowledge of the physical connections and/or cause-effect relationships between Main Feedwater System and the following:
S/GS waterlevelcontrol system Explanation of Steam flow is output to summator for FW control system program Delta-P. Delta-P program will decrease Answer causing feed pump speed and FW header pressure to decrease.
Reference Title / Facility Reference Number section/Page Revision L O.
FW EH controls / schematic EHC-6/DP 1
SGWLC schematic FW-2/ 512 loop 0
Chp 27 SGWLC lesson plan 6,
16 MaterialRequired for Examination.
Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment 4
Friday, July 24,1998 4:34:27 PM Page 68 of 127 Prepared byWD Associates,Inc.
'e+
uty m,
vn e-
 
- - _ = _ _ -.
Questien AFW Startup The following conditions exist on Unit 1:
-The reactor tripped from 40% power
- The trip was caused by RCS loop 1C low flow condition due to undervoltage for RCP 1C bus
- Power Range NIS. channel N42 failed at 100% on the trip
- ESF bus 141 undervoltage occurred
- 1 A D/G automatically started and ACB 1413 is closed
- S/G levels lowest readings were - 19% (A); 25% (B); 22% (C); 20% (D)
What is the status of the Auxiliary Feedwater (AF) Pumps on Unit 1 for these conditions at ONE minute following the trip?
: a. Both AF pumps are running.
: b. ONLY the 1 A AF pump is running
: c. ONLY the 1B AF pump is running.
s;
: d. Neither AF Pump is running e
Answer b Exam Leel B Cognmn Level Comprehension FaciNty: Braidwood ExamOate:
9/14/98 KA: 061 A3.01 RO Value:
4.1 SRO Value:
 
===4.2 Section===
SYS no oroup:
1 sRooroup:
1 j
SystenvEvolution Auxiliary / Emergency Feedwater System KA Ability to morutor automatic operations of the AuxRiary / Emergency Feedwater System including:
AFW startup and flows Esplanation of SG levels are above AF actuation setpoints and the motor driven AF pump starts on the deteded undervoltage.
Answer
.eforence Title /FacuMy Reference Number Section/Page Revision L 0.
Aux Feedwater System 2
5 Chp 26 AFW sys lesson plan 9
3,5 Chp 9 EDG lesson plan 7
7
~
Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Friday, July 24,1998 4:3428 PM Page 69 of 127 Prepared by WD Associates, Inc.
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.m.
i l-Question AFW flow requirements ftr cooldown W hich of tha following d:scribss the d: signed MINIMUM AFW pump cnd S/G configurttion necessiry to remova cll of th3 rsector decay hett lord following a re ctor trip from 102% power?
: a. The 1 A AF pump supplying 500 gpm to at least ONE S/G with S/G blowdown manually isolated.
: h. The 18 AF pump supplying 740 gpm to at least ONE S/G with S/G blowdown in service
: c. The 1 A and 1B AF pump supplying 500 gpm total flow to at least TWO S/Gs with S/G blowdown in service.
)
: d. The 1 A and 1B AF pump supplying 740 gpm total flow to at least TWO S/Gs with S/G blowdown manually isolated.
Answer a Exam Level B cognitive Level Memory Facility: Braidwood ExamDate:
9/1498 KA: 061 K5.02 RO Value:
3.2 SRo value:
 
===3.6 Section===
SYS RO Group:
1 SROGroup:
1 i
System / Evolution Auxiliary / Emergency Feedwater System KA Knowledge of the operationalimplications of the following concepts as they apply to the Auxiliary / Emergency Feedwater System:
Decay heat sources and magnitude
_y - m - _ og j
Answer
' Reference Title / Facility Reference Number
. Section/Page Revision L o.
AFW system lessson plan ch26 9
1,11 MaterialRequired for Examination Question Source:
New Question Modification Method:
Significantly Modified Question Source Comments:
Comanche Peak 11/93 NRC Exam Comment Type Comment Friday, July 24,1996 4:34:29 PM Page 70 of 127 Prepared by WD Associates, Inc.
 
. - -. -. -.. ~.. -.
. -. ~.
Questson DC bus battiry chirg:r l
The following conditions exist on Unit 1:
l l
- Reactor power - 100%
l l
Investigation has located a ground on the 125 VDC Normal supply to the 1 A D/G from DC iii, What cction is required to transfer DC Control Power to the reserve source?
Tha Reserve power breaker from...
: c. DC 111 will be closed after opening the Normal power breaker and the Reserve power l
breaker at the D/G control panel.
: n. DC 111 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks at the D/G control panel.
: c. DC 112 will be closed after opening the Normal power breaker and the Reserve power breaker at the D/G control panel.
: d. DC 112 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks l
at the D/G control panel.
Answer b Exam Level B Cognitive Level Memory Faculty: araidwood ExamDate:
9/14/98 KA: 2.1.3o RO Value:
3.9 SRO Value:
 
===3.4 Section===
SYS RO Group:
2 SROGroup:
1 SystenWEvolution D.C. Electrical Distribution KA j
Ability to locate and operate components, including local controls.
Explanation of Answer
..aference Title / Faculty Reference Number section/Page Revision L. O.
125 VDC system / schematic DC-1 0
DC Control powertransferfrom Normal to reserve source / BwoP-DC-6A1 51
~Chp 8a 125 VDC lesson plan 6
4,6 Material Required for Examination Question Source:
New Question Modification Method-Question Source Comments:
Comment Type Comment l
l I
I
'4 day, July 24,1996 4:34:30 PM Page 72 of 127 Prepared byWD Associates,Inc.
 
l Question Sequ:ncing of ESF pumps - SI & SI w LOP l
Unit 1 was being synchroniz:d to the grid wh n tha following occurred:
)
- Trip of 345 KV breakers resulted in deenergizing the SATs
- A steamline break occurred that resulted in containment pressure reaching 20 psig 20 seconds after the D/Gs output breakers have closed l
l When would the 1 A SX pump re-start?
: a. Always following start of the 1 A CS Pump.
: b. Between the start of the 1 A CV pump and the 1 A RH pump on the SDRA contacts (UV).
l
: c. Between the start of 1 A CC Pump and the 1 A AF Pump on the SARA contacts (SI).
: d. Coincident with the starting of the 1 A and 1C RCFCs.
Answer C Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:
g/14/98 KA: 064 A3.07 RO Value:
3.6 sRo value:
 
===3.7 section===
-SYS RO Group:
2 sRO Group:
2 system / Evolution Emergency Diesel Generators KA Ability to monitor automatic operations of the Emergency Diesel Generators including:
Load sequencing Explanation of The SX pump would be started in this case by the Si signal which is ovenides the UV condition. The SX pump Answer starts in following sequence: CV (0 sec); SI ((5 sec); RH (10sec); CS (15-18 secs, if actuation signal present); CC pumps (20 sec); SX pumps (25 sec); AF 1 A pump (35 sec); CS pump (40 sec, if acutalon signal
)
now present but not present at 18 sec) i i
Reference Title /FacMity Reference Number section/Page Revision L O.
'/G Relayin0/ schematic DG-2/ sequencing order 1
ap 9 EDGs and Aux sys lesson plan 7
7 Chp 20 Essential Service Water sys L::sson plan 7
8 Material Required for Examination
.., Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment I
i "riday, July 24,1996 4:34:31 PM Page 73 of 127 Prepared by WD Associates, Inc.
 
w%
RCDT operation - effect of CNMT isolati:n The following conditions cxist on Unit 1:
- Unit is in MODE 3
- A cooldown had just been initiated l
- Steam Dump Bypass Interlock control switches have just been taken to BYPASS l
- No other operator actions have been performed l
- The Steam Dump valves fail open and the following parameters are observed:
- RCS temperature - 537'F (A); 539'F (B); 538'F (C); 538'F (D)
.- Pzr pressure - 1820 psig l
- Pzr level - 10%
- S/G pressure - 850 psig (A); 740 psig (B); 800 psig (C); 715 psig (D)
- S/G flow - 1.0 Mlb/hr (A); 1.5 Mlb/hr (B); 1.1 Mlb/hr (C); 1.6 Mlb/hr (D)
- The level in the RCDT has risen to the alarm setpoint (80%) for REACTOR COOLANT DRAIN TANK UNIT 1 LEVEL Hi-LO
. Assuming all systems are functioning correctly, what is the status of the RCDT system?
: a. BOTH RCDT pumps are running and flow is, directed to the Holdup Tanks.
u
: b. BOTH RCDT pumps are running and flow is recirculated back to the RCDT.
: c. ONE RCDT pump is running and flow is directed to the Holdup Tanks, i
: d. NEITHER RCDT pump is running and NO flow exists for the system.
Answer d Exam Level B Cognitive Level Comprehension FacWty: Braidwood ExamDate:
9/14/98 KA: 068 A4.04 RO Value:
3.8 sRO value:
 
===3.7 section===
SYS' RO Group:
1 sRO Group:
1 i
systenmosution
. Liquid Radwaste System KA Ability to manualy operate and/or monitor in the control room:
Automatic leciation
~
: ;'--t : of Conditions for steam flow & low RCS temp. actuate Sl. The coincident CNMT Phase A isolation signal Answer isolates RCDT valves out. Closure of valve RE9170 cuses pumps to stop.
Reference Tm/ Facility Reference Number section/Page' Revision L 0.
PRT and RCDT/ schematic RY-4 2
Chp 48a Liquid Red Waste lesson plan 6
11 Ch61 ESFlesson plan 5
7 Malertal Required for Examination Question source:
New Question Modification Method.
Question source Comments:
Comment Type Comment Iday, July 24,1998 4:34:32 PM Page 74 of 127 Prepared by WD Associates, Inc.
 
. _. _ _ _, ~ _ _ _.. _ _ _ _ _ _ _.
Question CNMT Sump sources of input during n:rmtl operations During et-power operations with systems in th::ir normul clignm:nt, what is a normal source of water to the Containment Floor Sump?
: a. Output from the reactor cavity sump.
: h. Leakoff from the #2 RCP seals.
: c. Leakoff from the reactor vessel flange.
: d. Valve packing leakage from the CVCS letdown isolation valves.
Answer a Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:
9/W98 KA: 068 K1.07 Ro Value:
2.7 sRo value:
 
===2.9 section===
SYS Ro Qroup:
1 sRooroup:
1 systenWEvolution Liquid Radwaste System KA-Knowledge of the physical connections and/or cause-effect relationships between Uquid Radweste System and the following:
Sources ofliquid wastes for LRS Explanation of Rx cavity sump output to CNMT Floor sump, #2 seals directed to RCDT, RV flange to RCDT, valve leakoffs Answer directed to PRT Reference Title / Facility Reference Number
~ section/Page Revision L o.
Chp 46a Liquid Radwaste System 6
12
~
Material Required for Examination Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment Friday, July 24,1996 4:34:32 PM Page 75 of 127 Prepared byWD Associates,Inc.
 
Question W:ste Gas Decay Tank Operati:ns When cligned for norm:I op:rztion (BWOP GW-1), how does ths Wrsta Ggs System respond to high pressure sensed at the in-service Gas Decay Tank?
An alarm is generated that...
: a. alerts the operator to place an alternate Gas Decay Tank in service.
t:. indicates auto swap of in-service Gas Decay Tank to selected backup Gas Decay Tank, and alerts the operator to align another standby Gas Decay Tank.
: c. indicates auto swap of in-service Gas Decay Tank to selected standby Gas Decay Tank and auto swap of standby Gas Decay Tank to new standby Gas Decay Tank.
: d. shuts down the Waste Gas Compressors and isolates the in-service Gas Decay Tank.
An:wer b Exam Level R Cognitive Level Memory FacNity: Braidwood ExamDate:
9/14/98 KA: 071 A4.05 RO Value:
2.6 sRO Value:
 
===2.6 section===
SYS RO Group:
1 SROGroup:
1 systemevolution Waste Gas Disposal System MA Abitty to manualy operate and/or monitor in the control room:
Gas decay tanks, including valves, indicators, and sample Bne
*. M n of Indicates auto swap to standby WGD Tank at 95 psig.
Answer Reference Title /FacNity Reference Number Section/Page Revision L O.
Gas waste sys S/U & Operation /
BwOP GW-6 5
GDT sel sw reposition req'd/ OGWO2J-A1 51 Chgp 46 Gas Radwaste syslesson plan 6
6 Material Required for Examination Question source:
New Question ModlScation Method-Question source Comments-Comment Type Comment t
Friday, July 24,1998 4.34:33 PM Page 76 of 127 Prepared by WD Associates, Inc.
 
Queouen Check Srurce (perati:n Arem Radiation Monitor for Fuel Bldg Fuel Handling incid:nt (ORE-AR055) is being munuzily Chuck Source tested. What is the response when the monitor's CHECK SOURCE (C/S) pushbutton ~is depressed at the RM-23 panel?
The alarm and automatic action output will be blocked, and the RM-23 amber INTLK LED will be lit.
: b. The alarm and automatic action output will be blocked, and the RM-23 green AVAIL LED will be lit.
: c. The alarm will be actuate when value is reached, and the RM-23 amber INTLK LED will be lit.
: 4. The alarm will be actuate when value is reached, and the RM-23 red HIGH LED will be lit.
Answer b Exam Level R Cognitive Level Memory Facility: erakiwood ExamOate:
9/14/96 KA: o72 A4.03 RO Value:
3.1 sRo vehm:
 
===3.1 section===
SYS RO Group:
1 sROGroup:
1 systemEvolution Area Radiation Monitor'ng System KA AtMty to manually operate and/or monitor in the controi room:
Check source for operability demonstration Explanation of Depressing the C/S blocks the alarm and auto function of the minitor' but the AVAlllitght remains lit.
Answer Reference Tine /Factity Reference Number
/Page Revision L O.
Control Function Channel Check Source Energized /BwOP Mt/PR-11A26 B.1 1
~ Rad Monitor Sys lesson plan chp 49 7
3, 8 Material Required for Examination Question sowce:
New Question Modification Method.
mW source Comments:
Comment Type Comment
~
l Friday, July 24,1996 4:34:33 PM Page 77 of 127 Prepared by WD Anacciates, Inc.
 
.m Quesmon Less of FHB Overhead Crane rad m:nitor The following conditions exist on Unit'2:
- Refueling operations are in progress While using the Fuel Handling Building Crane to move new fuel into the Spent Fuel Pool, the radiation monitor ORE-AR039, Fuel Handling Building Crane Monitor, goes into alarm. What action is affected?
: a. Traverse of the Fuel Handing Building Crane bridge and trolley,
: n. Both lowering and raising the Fuel Handing Building Crane hoist.
: c. Traverse of the Fuel Handing Building Crane trolley and raising the hoist.
: d. Raising the Fuel Handing Building Crane hoist.
Anewer ' d Exam Levd B Cognitive Level Comprehension FacWty: Braidwood ExamDate:
grW98 KA: 072 K3.02 Ro Value:
3.1 sRo value:
3.5. - nan: SYS Ro oroup:
1 sRooroup:
1 systemevduuon Area Radiation Monitoring System j KA Knowledge of the effect that a lose or malfunc60n of the Area Radelion MontortnB System wls have on the following Fuel henden0 operatione g
sc- "n of Rad monitor prevents raisin 0 holst.
Answer 1
Reserence Title / Faculty Reference Number Section/Page Revision L. o.
Chp 49, Radiation Monitors lesson plan 7
4.a.3)
Meterial Required for Examination Question Source:
New Quesuon ModtAcation Method:
Question Source Comments:
Comment Type Comment e4 Nay, July 24,1996 4:34:34 PM Pope 78 of 127 Prepared by V D Associates. inc.
 
f Question Ev:.luation of eqpt (ffected far slow loss The following conditions exist on Unit 1:
- A unit startup is in progress with reactor power raised above 18%.
- Turbine is at 1800 rpm ready to be synchronized to grid.
- Motor driven feedwater pump is supplying the SIGs with Feed Reg Bypass valves in AUTO.
l
- Steam Dump demand in AUTO at 12%.
l
- Instrument air header pressure begins to slowly drop due to a leak l
f if the leak CANNOT be isolated and instrument air pressure continues to drop, which of the following l
would occur?
l (Assume NO operator action taken.)
l l
a.' AF recirculation flow to the CST would be lost due to AF recirc failing closed, i
: b. Pressurizer level would increase due to 1CV121 failing open.
: c. The main turbine would auto runback due to Diaphragm Interface Valve.(DIV) opening.
: d. RCS temperature would drop to 550*F due to steam dumps failing open.
l Antwer b Exam Level B Cognitive Level Compreh,ension Facility: Braidwood ExamDate:
9/14/98 MA: 078 K3.02 RO Value:
3.4 sRO Value:
 
===3.6 section===
SYS RO Group:
3 sRooroup:
3
- systemevolution instrument Air System KA Knowledge of the effect that a loss or malfunction of the Instrument Air System will have on the following:
Systems having pneumatic valves and controle Emptanation of Charging flow goes to maximum due to 1CV121 failing open, and letdown isol 1CV459 & 1CV460 fail closed.
l Answer
'a' is incorrect because both 1 A & 1B AF pump recirc valves fall open. 'c' main turbine not directly affected. 'd' not occur because steam dumps fait closed.
Jerence Title /FacMity Reference Number section/Page Revision L O.
Loss cfinstrument Air Lesson Plan 18woA SEC-4 Table A 52 8
9 l
Chp 53 lA/SAlesson plan Material Required for Examination Question Source:
New Question Modification Method:
l Question Source Comments:
Comment Type Comment i
i
,1 day, July 24,1998 4:34:35 FM Page 80 of 127 Prepared byWD Associates,Inc.
I
 
Question Eff;ct ofloss of DC - CO2 actuation With the fira prot:ction syst:ms in th:ir norm I clignm:nt, wh:1 is the eff:ct of a loss of DC power?
Loss of DC control power to the...
: a. halon control cabinet will cause halon release in the OA Control Room HVAC Room.
: b. battery control panel will cause automatic start of the diesel driven fire pump.
: c. fire detection system will cause start of the motor driven fire pump.
: d. carbon dioxide system will cause the master discharge valve to fail open pressurizing the CO2
: header, Answer d Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 086 K4.06 RO Value:
3.0 sRO Value:
 
===3.3 Section===
SYS RO Group:
2 SRO Group:
2 system / Evolution Fire Protection System KA Knowledge of Fire Protection System design feature (s) and or interlock (s) which provide for the following:
CO2 Explanation of EMPCs uses DC control power. On loss of power, the master EMPC valves fail open which in turn cause the Answer master discharge / selector valve to open, charging the affected header.
Reference Title / Facility Rsference Number
' Section/Page Revision L O.
Chp 57, Fire Protection System lesson plan 5
8 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Nay, July 24,1998 4:34:36 PM Page 81 of 127 Prepared by WD Associates, Inc.
 
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Quesuon Evaluita conditi:ns - unwarranted rod withdrawil The following conditions exist on Unit'1:
- Reactor power is 30%.
)
- Rod controlis in Automatic
- Tref-564*F
- Tave values - 564*F (A); 565'F (B); 565'F (C); 564*F (D)
- Power Range N1 - 31% (N41); 29% (N42),30% (N43); 30% (N44) 1
- Control bank D is at 156 steps.
Which condition would result in continuous rod withdrawal?
Turbine first stage pressure PT-505 fails upscale.
1
: b. Power Range channel N41 fails upscale.
: c. Loop A Tcold fails downscale.
. 4. Tref signal fails downscale.
Answer a Exam Level B Cognieve Level Comprehension FacMity: Braidwood ExamDate:
9/14/96 KA: 001 AA2.oS RO Value:- 4.4 SRO Vaiue:
 
===4.6 lSection===
EPE RO Group:
2 sROGroup:
1 Systemevolution Continuous Rod Withdrawal KA Ability to determine and interpret the fotowin0 as they apply to Continuous Rod Withdrawal:
Uncontrolled rod withdrawal, from available indications Explanation of Input to rod contiel Tref, auctioneered HIGH Tave & Auctioneered high PRNis: PT-505 provides input signal for development of Tref. If it fails high Tref goes to maximum value (581*F) and results in rods being withdrawn to Answer match Tave to Tref. PR failure high compares the rate of change of reactor power to the rate of change of turbine power. Initially high rate of change during failure but rapidly the rate of change falls to zero and so rods may initei!!y begin to insert but quickly stop motion with no more rate of change. Auctioneered high Tave is j
used and Tcold failing low will remove this input (if prevolusly auctioneered high). Tref falling low will cause rods to move inward to match Tave to Tref.
Reference Title / Faculty Reference Number Section/Page Revision L 0.
. Rod control Unit / Schematic RD-2 2
12 20 Chp 28 Rod control sys Lesson Plan Uncontrolled Rod Motion /18wCA ROD -1 6
3 Lcsson plan Malertal Required for Examination Question Source-New Question Modification Method.
Question Source Comments:
Comment Type Comment Friday, July 24,1996 4:34:36 PM Page 62 or 127 Prepared byWD Associates,Inc.
f w
w
 
Question P/A vs. Group St p C untIrs A Control B:nk D rod w:s dropped from 156 st:ps. Th3 P-A conv:rter w:s NOT z:roed wh n dirccted by the procedure.
S: lect the effect of NOT performing this action?
l
: a. While performing the procedure, the C-11 Rod Stop will be received prior to realigning the rod.
: n. While performing the procedure, the Rod Insertion Limit Alarm will be received et a lower rod position than required.
: c. After the procedure is complete, Bank C control rods will begin insertion at a lower value of Control Bank D.
: d. After the procedure is complete, Bank C control rods will begin insertion at a higher value of Control Bank D.
Ansme a Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:
9/1498 KA: 003 AK3.10 RO Value:
3.2 sRo value:
 
===4.2 section===
EPE RO Grc up:
2 sROGroup:
1 systenWEvolution Dropped Control Rod
~
KA Knowledge of the reasons for the fo#owing responses as they apply to Dropped Control Rod:
RlL and PDIL g
Explanation of The bank overlap units are bypassed when rods are moved with individual bank selector positions. The P to A Answer converter provides step information to rod position indication including the C-11 circuit. As the individual rod was withdrawn to approximately 67 steps the C11 circuit would sense that bank D was at 223 steps and block outward motion.
Reference Title / Facility Reference Number Section/Page Revision L O.
RD Data logging / rod stops schematic RD-5/RD-1 P/A & C-11 rod stop 0/0 ap 28 Rod Control sys lesson plan 12 1g,10 MaterialRequired for Examination Question Source:
New Question Modification Method:
Editorially Modified Question Source Comments:
D.C. Cook 6/13/1995
- CommentType Comment Friday, July 24,1998 4:34 38 PM Page 84 of 127 Prepared byWD Associates,Inc.
 
Strbilized RCS t' mperature with fIllure of St:am Dumps e
essetten l
~ On Unit 1, a loss of cli circuliting wit:r pumps his rcsult:d in a racctor trip. All control syst:ms respond cs expected. Significant decay heat causes RCS temperature to increase following the trip.
At what RCS temperature should temperature stabilize?
Tcmperature should stabilize at the saturation temperature for...
L 1030 psig..
n.1092 psig.
: c. _1115 psig.
i
. d.1175 psig.
I Answer C Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:
9/14/98 l
NA: 007 EA1.03 RO Value:
4.2 SRO Value:
 
===4.1 Section===
EPE
' RO Group:
2 SROGroup:
2 SystenWEvolution '
Reactor Trip
]
.KA Ability to operate and / or monitor the following as they apply to Reactor Trip:
RCs pressure and temperature Explananon of The condenser would NOT be available for steam dumps (either on trip controller or load rejection controller).
Th S/G pressurti would stabilize based on the seocndary PORV opening setpoint normally set at 1115 psig.
. Answer The Main Steam safety valve setting is 1175 psig.
Reference Tuse/ Facility Reference Number Section/Page Revision L 0.
' Steam dumps / schematic MS-4/ C-9 4
Chp 24 Steam dumps lesson plan 7
4 Chp 23 Main steam lesson plan 8
3 Material Required for Examination Question Source?
New Question Modincation Method:
Question Source Comments:
Comment Type Comment I
Friday, July 24,1996 4:34:39 PM Page 86 of 127 Prepared by WD Associates, Inc.
4 l
 
. - - ~ _ -. - ~.. -
Topic Question Reactor Trip requirements if Unit 2 is operating at full load, which group of conditions will result in an autornatic reactor trip either directly or indirectly?
RCP bus frequency (Hz):56.9 (Bus 156) 57.1(Bus 157) 56.9 (Bus 158) 57.2 (Bus 159)
: n. Power range (%):
107 (N41)
'108 (N42) 108 (N43) 109 (N44)
: c. PZR pressure (psig): 2375 (PT-455) 2380 (PT-456) 2385 (PT-457) 2380 (PT-458)
: d. S/G C NR level (%): 35 (LT-537) 38 (LT-538) 38 (LT-539) 37 (LT-558) l Answw a Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 1
KA: 007 EK2.03 Ro Value:
3.5 sRo value:-
 
===3.6 section===
EPE Ro oroup:
2 saooroup:
2 systensvolution Reactor Trip MA Knowledge c"5e interrelations between Reactor Trip and the following:
Reactor trip status panel Explanation of Trp condition RCP UF - 2/4 RCP buses < 57.0 Hz. Other trip setpoints: Rx power - 2/4 >109%; Pzr pressure Answw Titse: 2/4 > 2385 psig Reference Title /FacNity Reference Number sbion/Page Revision L o.
ESF Setpoints/ schematic EF-1/Rx trip 4
2BwEP-0 Reactor Trip or Si lesson plan 3
6 Chp 60b RPS lesson plan 6
4 Material Required for Examination
)
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Cornanche Peak 11/94 i
'omment Type Comment Friday, July 24,1998 4:34:40 PM Page 88 of 127 Prepared by WD Associates, Inc.
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Question Tail-Pipe conditions j
With the RCS ct normal opercting prassure arid t:mperaturo, what la the condition of tha st::am cntaring the PRT at normal conditions, if a PORV opens? (Assume an ideal thermodynamic process).
: a. Superheated steam at 239'F.
: b. Superheated steam at 222*F.
: c. Saturated steam-water mixture at 239'F.
l
: d. Saturated steam-water mixture at 222*F.
AnIww d Exam Level R Cognitive Level Application Facility: Braidwood ExamDate:
9/14/98 KA: 008 AK1.01 RO Value:
3.2 SRO Value:
 
===3.7 Section===
EPE Ro oroup:
2 SROGroup:
2 Systemmvolution Pressurizer Vapor Space Accident j
KA Knowledge of the operationalimplications of the following concepts as they apply to Pressurtzer Vapor Space Accident:
i Thermodynamics and flow characteristics of open or leaking valves l
Explanation of Nominal PRT pressure 3 psig; Hg = 1154 BTUAb. Saturation temperature 221.9'F. At NOP Pzr pressure 2235 Answw psig with Hg = 1117.7 BTUAb. Therefore PRT conditions are within saturation parameters.
Reference Title / Facility Reference Number
~ Section/Page Revision L O.
Stram Tables 9
25e Chp 14, Pressurizer lesson plan 7
Material Required for Examination Steam Tables Question Source:
New Question Modification Method:
Signircantly Modified Question Scurce Comments:
South Texas 9/95 Comment Type Comment Frid:y, July 24,1998 4:34 41 PM Page 90 of 127 Prepared byWD Associates,Inc.
 
_~...-e l
l Question Cilculati:n of subcooled mirgin en iconics l:
What tro ths parcmet::rs used to calculata Subcooling Mygin in ths SPDS leonics if only ths 1C RCP cnd 1D RCP are running?
: a. RCS wide range pressure from loop C hot leg and core exit thermocouple temperatures.
: b. Pressurizer pressure and core exit thermocouple temperatures.
: c. RCS wide range pressure from loop A and loop C hot leg, and RCS loop A and loop C hot leg temperatures.
: d. Pressurizer pressure and RCS loop A hot leg temperature.
Answer.a Exam Level B C :... la Level Comprehension Facility: Braidwood ExamOate:
9/14/98 KA: 009 EA1.10 RO Value:
3.8 sRO Value:
 
===3.9 section===
EPE RO Group:
2 sROGroup:
2 I
systemIEvolution Small Break LOCA KA Ability to operate and / or monitor the following as they apply to Small Break LOCA:
Safety parameter display system Explanation of Answer Reference Title /FaciHty Reference Number Sedion/Page Revision L O.
SPDS Display schematic CX-1/subcooling 1
Ch34b inadequate Core Cooling' O
Lesson plan 7
6 Material Required for Examination Question source:
New Question Modificatlan Method:
Question source Comnents:
Comment Type Comr.wnt 1
iday, July 24,1998 4:34.42 PM Page 91 of 127 Prepared by WD Associates, Inc.
 
_n. _
Question RCP trip critiria ev-_luiti:n The following conditions exist during performance of BwEP-0.
- Train A ECCS pumps failed to start.
- RCS pressure is 1350 psig.
- Containment pressure of 7 psig.
- Bus 142 has an overcurrent trip on the normal feeder breaker.
Si actuated due to High Containment Pressure.
- The highest critical safety function is Yellow on Heat Sink.
- All other equipment and components operated as expected.
Based on the RCP Trip Criteria, the RCPs should...
: a. NOT be stopped because NO Si pumps or Charging Pumps are running.
: 6. NOT be stopped because RCS pressure is above the trip setpoint.
: c. be stopped because Si flow is established to the RCS.
: d. be stopped because CC flowpath to the RCP motor oil coolers is isolated.
Answer a Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:
9/14/98 KA: 011 EA1.03 RO Value:
4.0 sRO Value:
 
==4.0 section==
EPE RO Group:
2 sROGroup:
1 systanevolution Large Break LOCA KA Ability to operate and / or monitor the following as they apply to Large Break LOCA:
Securing of RCPs Explanation of The trip caiteria is < 1425 psig, with No cooldown in progress, and HHSI flow > 50 gpm or Si flow > 100 gpm.
Answer
'forence Title / Facility Reference Number section/Page Revision L O.
,AS for 1BwEP-0 Trip RCPs 1C 18wEP-0 lesson plan RCP trip criteria 11 2,5 Material Required for Examination
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New Question Modification Method:
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Watts Bar 3/3/1995 Comment Type Comment Friday, July 24,1998 4:34:43 PM Page 93 of 127 Prepared by WD Associates, Inc.
 
.. ~.
. ~ _.
Question Eval 1:ss of cooling flow On a loss of se:I injection to tha RCPs, whnt criteri2 is ustd to d:t:rmina if tha RCPs should be tripped?
: a. High temperatures on the RCP seal or bearing outlet temperatures.
: b. Time elapsed since loss of seal injection.
: e. RCP Thermal Bearing Cooling Water low flow alarms.
: d. #1 seal leakoff flow rate decreases to zero.
Answer a Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:
g/14/98 KA: 015 AA2.10 RO Value:
3.7 SRO Value:
 
===3.7 Section===
EPE RO Group:
1 SROGroup:
1 Systemevolution Reactor Coolant Pump Malfunctions KA Ability to determine and interpret the following as they apply to Reactor Coolant Purnp Malfunctions:
When to secure RCPs on loss of cooling or sealinjection Explanation of Seal & bearing temperatures are monitored for trip setpoint.
Answer Reference Title / Facility Reference Number Section/Page Revision L O.
Loss cf seal cooling 18wOA RCP-2 54 Losss of Seal Cooling lesson plan 6
4 0
Material Required for Examination Question Source:
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- Comment l
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Friday,.!uty 24,1998 4:34:45 PM Page 96 of 127 Prepared byWD Associates,Inc.
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Question Evil of RCP se:1 f'ilure Unit 1 is oper: ting et 100% pow:r whtn ths following clarm is receiv d:
- - RCP SEAL LEAKOFF FLOW LOW (1-7-C3)
. The NSO investigates and reports the following additional information:
- RCP 1 A seal injection flow is 10.7 gpm
- #1 Seal Leakoff Flow on 1 A RCP is 0.4 gpm
- RCP 1 A Seal Water Outlet Temperature is 140*F and STABLE
- RCP 1 A Bearing Outlet Temperature is 145'F and STABLE B sed on the above information, which of.the following events has occurred?
: a. RCP 1 A #1 Seal has failed closed
: b. RCP 1 A #1 Seal has failed open.
: c. RCP 1 A #2 Seal has failed closed.
: d. RCP 1 A #2 Seal has failed open.
Answer d Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 MA: 015 AK2.07 RO Value:
2.9 SRO Value:
 
===2.9 Section===
EPE RO Group:
1 SROGroup:
1 Systemevolution Reactor Coolant Pump Malfunctions j
KA Knowledge of the interrelations between Reactor Coolant Pump Malfunctions and the following:
RCP seals Explanation of j
i Answer aforence Title / Facility Reference Number Section/Page Revision L. O.
RCP seal Failure /1BwoA RCP-1 SSB 18woA RCP-1 lesson plan 7
5
- MaterialRequired for Examination Question Source:
Facility Exam Bank Question Modification Method:
Editorially Modified Question Source Comments:
Braidwood bank Comment Type Comment I
Friday, July 24,1998 4.34 45 PM Page 97 of 127 Prepared byWD Associates,Inc.
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i Question.
VCTlev;ltransmitt:r malfunction Given ths following:
The plan't is'at 90% power with ALL controls in AUTO.
VCT level transmitter, LT-112, fails HIGH causing a letdown diversion.
What will occur if NO operator action is taken?
,VCT level decreases...
: a. until Auto makeup starts and maintains VCT level.
: b. with NO auto makeup capability and charging suction shifts to RWST.
: c. faster than auto makeup input and charging suction shifts to RWST.
: d. until charging pumps lose suction and start to cavitate.
Answer d Exam Level B Cognitive Level Application Faclety: Braidwood ExamDate:
s/14/98 KA: 022 AA1.08 Ro Value:
3.4 sao value:
 
===3.3 section===
EPE no oraup:
2 saooroup:
'2 systemevolution Loss of Reactor Coolant Makeup 1
KA Ability to operate and / or monitor the fotowmg as they apply to Laos of Reactor Coolant Makeup:
VCT level E ' --n of LT 112 provides for AUTO makeup to the VCT. If No operator action taken, then level will continue to fall until
)
Answer NPSH is lost to the CENT CHG pump (s). Transfer will NOT occur to RWST since both channels are required for swap. An alarm will be generated from LT-185 at 20% level.
Reserence Titie/FacNety Reference Number section/Page Revision L o.
CVCS notes / schematic CV-2/ LT 112 table 3
10 11,14
''hp 15a CVCS lesson plan Material Required for Examination Question source:
New Question ModlAcation Method:
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4 Friday, July 24.1998 4:34:46 PM Page 98 of 127 Prepared byWD Associates Inc.
 
Question Tim:;/ amount E-borati:n f:r condition Given the'following efter a racetor trip:
- THREE rods remain withdrawn.
- Due to equipment malfunctions boration is only available from the RWST,
- Charging flow rate 132 gpm.
- RCS boron concentration was 1050 prior to the trip.
- 120 gpm letdown in service.
Of the listed times, which would be minimum acceptable time that boration from the RWST would have to l
occur?
l a.1 Hour
: b. 2 Hours
: c. 3 Hours l
: d. 4 Hours Answer b Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:
9/14/98 j
MA: 024 AA2.06 RO Valuer 3.3 sRO Value:
 
===3.9 7section===
EPE RO Group:
1 sROGroup:
1 systemIEvolution Emergency Boration KA Ability to determine and interpret the following as they apply to Emergency Boration:
Amount of boron to add to achieve required SDM Explanation of 1BwEP ES-0.1 requires 3600 gallons boration from RWST for each rod not fully inserted, therefore requiring Answer 10,800 gallons. If net change over is 120 gpm, then required time is 10,800/120 = 90 minutes. Other answers based on counting 2 rods and/or borating from CV-8104 @ 57 gpm with total of 1200 gallons.
Nforence TitleIFaculty Reference Number -
section/Page Revision L O.
JwCA Pri-2 emefgency Boration SSB 1BwoA Pri-21esson plan 1
4,6 H
1BwEP-0 lesson plan 11 3
Material Required for Examin.cJon 1BwEP ES-0.1, page 6 (step 5)
. Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment Friday, July 24,199) 4:34:47 PM Page 99 of 127 Prepared by WD Associates, Inc.
 
Quesuon Cile of tims(3 saturatirn/ core boiling The following conditions exist on Unit 1
- The plant was shutdown 8% days ago to repair a steam generator tube leak.
- Reactor vessel level is at 397' 1" with Thot at 212*F.
- A loss of RHR. pumps due to cavitation has occurred Which of the following is the smallest aniount of flow that meets the minimum makeup flow required to m:intain current RCS level?
: a. 80 gpm i
: b. 72 gpm
: c. 59 gpm
: 4. 45 gpm Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 025 AK1.01 RO Value:
3.9 _ sRO Value:
 
===4.3 section===
EPE RO Group:
2 sROGroup:
2
)
systemevoluuon Loss of Residual Heat Removal System KA Knowled0e of the operationalimplications of the followi[lg concepts as they apply to 1 aos of Residual H0st Removal System.
i Loos of RHRS during all modes of operation s 'mrn of : 81/2 days is 204 afters shutdown. The curve shows minimum flw at approximately 70 gpm.
1 Answer Reference Title / Facility Refeu.nce Number Section/Page Revleion L. O.
Loss of RH cooling /1BwOA Pfi-10 56 4
1BwOA Pri-10 Lesson plan Material Required for Examination Figure 1BwCA PRI10-1 Question Source:
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Question Source Comments:
Comment Type Comment 1
Friday, July 24,1998 4:34:47 PM Page 100 of 127 Prepared by WD Associates, Inc.
w.
 
-_ _-.. -. _ -.. _.. _ ~
I
- Question Alt: mate RCS Cooling The following conditions exist on Unit 2:
MODE 5 operation during normal cooldown RCS temperature - 195* F RCS pressure - 325 psig Train A RH in service, train B RHR tagged out for repairs What is the preferred method of core cooling if a loss of RH cooling occurs?
Alt mate RCS cooling using...
: e. bleed and feed using reactor head vents.
: b. the S/Gs.
: c. normal charging and RHR letdown.
: e. Si Pump cold leg injection Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 4
KA: 025 AK3.01 RO Value:
3.1 SRO Value:
 
===3.4 Section===
EPE RO Group:
2 SROGroup:
2 Systemevolution Loss of Residual Heat Removal System KA Knowledge of the reasons for the following responses as they apply to Loss of Residual Heat Removal System-
. Shift to altemate flowpath Explanation of Steaming intad/nor,-isolated SGs is the preferred attemate decay heat removal method if the RCS is intact.
Answer Reference Title /FacNity Reference Number SectSn/Page Revision L. O.
s cf RHR Cooling /1BwOA Pri-10 Table A 56 I
.swOAPrl-10 Lesson Plan 4
Material Required for Examination
- Question Source:
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- Question Source Comments:
Comrnent Type Comment l
i Friday, July 24,1998 4:34:48 PM Page 101 of 127 Prepared byWD Associates,Inc.
i
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.-,m Question Evaluati n of CCWIrik The following conditions exist on Unit 1:
- The reactor is shutdown.
- RHR is in shutdown cooling.-
l
- RCS temperature is 300*F.
RCS pressure is 160 psig.
- CCW surge tank levelis decreasing What leak locations will produce these indications?
l l
RHR Heat Exchanger
: n. Thermal Bearing Heat Exchanger
: c. Letdown Heat Exchanger
: d. Seal Water Heat Exchanger Answer d Exam Level B Cognitive Levd Comprehension Faciuty: Braidwood ExamDate:
9/14/98 xA: 026 AA1.05 Ro Vdue:
3.1 sRo value:
 
===3.1 section===
.EPE Ro Qroup:
1 sRooroup:
1 systenvEvolution Loss of Component Cooling Water; KA Ability to operate and / of monitor the followin0 as they apply to Loos of Component Cooling Water.
The CCWS surge tank, including level control and level alarms, and radiation alarm Emptanation of The seal water HX would be the only location where the CC pressure would be lower than the process fluid Answer pressure. RHR HX approx.165 psig; UD Hx pressure should be approximately 160 psig; & Thermal barrier pressure should be about 160 psig.
Reference Title / Faculty Reference Number section/Page Revision L o.
CCW malfs/1BwCA Pri-6 Att B 56 3wOA Pri-6 lesson plan Att B 6
3 Material Required for Examination Question source:
Facility Exam Bank Question Modification Method:
Significantly Modified Question source Comments:
Zion 7/13/92 Comment Type Comment Friday, July 24.1998 4:34.48 PM Page 102 of 127 Prepared by WD Associates, Inc, l
 
..~
f Question Pressure controll:r stIp chInge The following conditions exist on Unit 2:
- Reactor power is 100%
- Pressurizer pressure control is in automatic.
- What is the immediate response of the pressure control system if the Master Pressure Controller setpoint is inadvertently changed to 2330 psig (step change)?
: a. PORV RY455A operi and spray valves open.
: n. PORV RY455A opens, spray *;alves open, and all heaters energize.
: e. Spray valves open and proportional heaters go to minimum.
L
: d. Spray valves close and proportional heaters go to maximum.
Answer d Exam Level B Cognidve Level Application Facility: Braidwood ExamDate:
9/1N98
[
KA: 027 AA1.01 RO Value:
4.0 SRO Value:
 
===3.9 Section===
EPE RO Group:
1 SROGroup:
2 system / Evolution Pressurizer Pressure Control Malfunction KA Ability to operate and / or monitor the following as they apply to Pressurizer Pressure Control Malfunction:
PZR heaters, sprays, and PORVs
- Explanation of Setting the pot setting higher reduces the ' 'utput from the controller and raises the demanded pressure o
Answer setpoint. This reduction results in spray valve closure & heaters turning fully on.
Reference Title / Facility Reference Number Section/Page Revisio L O.
l Pzr Pressure Controll schematic RY-2/PK.456A in Auto 3
9 30 Chp 14 Pressurizerlesson plan I
MaterialRequired for Examination Question Source:
New Question Modification Method:
Signircantly Modified Question Source Comments:
Calvert Cliffs 11/97 Comment Type Comment l
l t
c iday, July 24,1998 4:34:50 PM Page 104 of 127 Prepared by WD Associates,Inc.
r
?
l l
 
1 Question N:n-Controlling chinn:1 fiilure The following conditions exist on Unit'1:
- Reactor power is 100%.
- All systems are in automatic
- Channel i Pressurizer Pressure Channel (PT-455) was declared inoperable and taken out of service with the appropriate bistables placed in the tripped condition.
- Controlling pressurizer pressure channel (PT-457) fails high Assuming NO operator action, what is the plant response to the channel failure?
: e. Both PORVs and both spray valves open resulting in a reactor trip from low pressurizer pressure l
followed by Si actuation.
: b. The reactor will trip immediately on high pressure, and safety injection will actuate on low pressure due to spray valve operation.
: c. Pressurizer proportional heaters will de-energize and spray valves will open resulting in an OTdT runback prior to tripping, and safety injection will actuate due to low pressurizer pressure.
: d. Both PORVs and both spray valves remain closed while pressurizer heaters de-energize.
Answer b Exam t.evel B Cognitive Level Application FacWty: Braidwood ExamDate:
9/14/98 KA: 027 AA2.15 RO Value:
3.7 sRO Value:
 
==4.0 section==
EPE RO Group:
1 SROGroup:
2 systmWEvolution Pressurizer Pressure Control Malfunction KA Ability to determine and interpret the folowing as they apply to Presourtter Pressure Control Malfunction-Actions to be taken if PZR preneure instrument falls high Explanadon of TWO PZR pressure channels will have HIGH PZR PRESSURE bistables actauted resulting in the reactor trip.
Anawer The sparys wil have modulated fully open resulting in actual pressure decreasing (PORV 1RY455A would have also opened on the failure of PT-457, but would close when the PZR pressure fell to 2185 psig PT-458 will actaute the low pressure interlock closing the PORV) until Si occurs at 1829 psig.
Reference Title / Facility Reference Number Section/Page Revision L O.
,Pzr Pressure Control / schematic RY-2/ PZR press 3
9 30 Chp 14 Pressurizerlesson plan Material Required for Examination Question Source:
New Question Modification Method:
signiricantly Modird Question Source Comments:
BV 8/91 Comment Type Comment Friday, July 24,1998 4:34:50 PM Page 105 of 127 Prepared byWD Associates,Inc.
 
~.. - -
..~.-. n - - - - _..- -. -
Quescon Failed lev;l channellow.
The plant is operating et 100% power with cll control syst*ms in AUTO. The following piremsters are noted:
- Letdown Hx outlet flow (FI-132) - 75 gpm
--Charging Headerflow(FI-121) - 87 gpm
- Total seal injection flow (FI-142 -Fi -45) - 33 gpm What is the effect on total seal injection flow initially if controlling Pzr level channel LT-459 fails LOW?
Total sealinjection flow will...
. decrease to O gpm.
a
: n. decrease to approximately 20 gpm.
: c. remain approximately 33 gpm
: 4. increase to greater than 40 gpm.
Answer d Enam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 028 AK3,05 -
RO Value:
3.7 sRO value:
 
===4.1 section===
EPE RO Group:
3 SROGroup:
3 syseenwevolumen Pressurizer Level Control Malfunction KA Knowledge of the reasons for the following responses as they apply to Pressurtzer Level Control Malfunction:
Adions contained in EOP for PZR level malfunction Empianation of The failure of the level instrument low increases charging flow and charging dicharge header pressure. Since i
' Answer seal injection flow is normally increased by throttling close on CV182 to increase backpressure, the result is the same and seal injection flow will increase.
..sierence TitiefacNity Reference Number section/Page Revision L 0.
CVCS notes / schematic CV-2/cycs ratings 2
18woA inst 2 Att C lesson plan -
9 1
Material Required for Examination
-- Question source:
Facility Exam Bank Question Modification Method:
Significantly Modified Question source Comments:
Braidwood 1996'NRC exam. Modified premise from failed controller to failed level channel. Changed location of correct answer based on different response (increasing flow Instead of decreasing flow).
Comment Type Comment Friday, July 24.1998 4:34:51 PM Page 106 of 127 Prepared by WD Associates, Inc.
I
 
~ ouestion :
AMS conditi:ns The following conditions exist on Unit 1:
- At t= 0 'sec, Turbine load was decreased below 352.MW (30% power)
At t=240 sec, The running main feedwater pump tripped.
The reactor did NOT trip due equipment malfunction.
- At t=250 sec,. All feedflow indications decrease to 0% flow
- At t=320 sec, All steam generatorlevels dec. ase below 15%.
B* sed on this information, AMS would...
l
: a. initiate at t=320 sec.
: b. initiate at t=345 sec.
: c. initiate at t=360 sec.
: 4. NOT initiate because C-20 is cleared.
-- Answer _ b Exam Level B C-:. ^ a Level Application Faciuty: Braidwood ExamDate:
9/14/98 KA: 2.4.48 RO Value:
3.5 sRO Value:
 
===3.8 section===
EPE RO Group:
2 sROGroup:
1 SystemIEvolution Anticipated Transient Without Scrarc l
i g
Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.
Explanation of AMS remains armed for 6 minutes (360 sec) following decrease below 30%(C-20). The actuation sigan! is Answer _
generated after 3/4 SGs level have fallen 3% below the LO-2 (reactor trip) setpoints of 18% for a period of 25 l
seconds. C-20 would clear @ t=360sec. AMS actuation occurs at 320 + 25.= 345 sec.
I Reference Title /FacMity Reference Number Section/Page Revision L O.
'AS/ schematic PN-3/ logic 1 schem.
2 ofip 60b 6
7 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
- Comment Type Comment l
l l
I I
l Frid y. July 24,1998 4:34:51 PM Page 107 of 127 Prpared by WD Associates. Inc.
j-1 l
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ouestion Ev11uiti:n of SR NIS voltags failure The following conditions exist on Unit 1:
- Reactor startup in progress
-Intermediate power range indication: 2.5E-5 amp N35 & 2.8E-5 amp N36
- SOURCE RANGE PERMISSIVE P-6 permissive light clear
- SOURCE RANGE TRIP ACTIVE permissive light clear
- Source Range Channel N31 High voltage power supply fails to half its normal value What indication (s) would be available to alert the operator to this failure?
: a. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate lower than expected.
: b. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate higher than expected.
: c. Annunciator SR HIGH VOLTAGE FAILURE (1-10-81) will alarm when power exceeds P-10.
: d. Annunciator SR HIGH VOLTAGE FAILURE (1-10-B1) will re-flash when the voltage source fails.
An:wer a Exam Level B
' Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 032 AK1.01 RO Value:
2.5 sRO Value:
 
===3.1 section===
EPE RO Group:
2 SROGroup:
2 systenWEvolution Loss of Source Range Nuclear Instrumentation KA Knowledge of the operationallmplications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:
Effects of voltage changes on performance
]
Explanation of Based on Gas filled detector curve (Region lil), the number of events collected would drop (counts drop).
)
Answer Alarm and voltage input to SR detector is blocked until both IR NIS fall below the P-6 setpoint.
]
forence Title /FacMity Reference Number Section/Page Revision L O.
sR High Volt Failure /18 WAR 1-10-B1 setpts/ notes 1
Source Range detector / schematic NI-4 4
Chp 31 source range nuclearInst
{
6 2,3,11,12 L:sson plan
- Material Requited for Examination j
Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment Friday, July 24,1998 4:34:52 PM Page 108 of 127 Prepared byWD Associates,Inc.
 
=.
Question Eval of failed IR chtnn;l on SU The following conditions exists on Unit 2:
- Plant shutdown is in progress.
- All power range channels indicate 6% reactor power.
- Intermediate range channel N-36 fails HIGH.
What is the plant response to this failure?
: n. The reactor will trip on high IR flux, and source range trip will reinstate when N-35 decreases below P-6.
: b. The reactor will trip on high IR flux, and source range trip will NOT be reinstated.
: c. The reactor will NOT trip imrnediately, but will trip when the source range trip is reinstated when N-35 decreases below P-6
: d. The reactor will NOT trip, and source range trip will NOT be reinstated.
Answer b Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:
9/14/98 KA: 033 AA2.04 RO Value:
3.2 SRO Value:
 
===3.6 Section===
EPE RO Group:
2 SROGroup:
2 System / Evolution Loss of Intermediate Range Nuclear Instrumentation KA Ability to determine and interpret the following as they apply to Loos of intermediate Range Nuclear instrumentation:
Satisfactory overlap between source 4ange, intermediate-ranDe and power-range instrumentation Explanation of Since reactor power is < P-10 setpoint (10% power), the IR trip setpoint at 25% ElCAwill be exceeded Answer resulting in reactor tiip. SR will NOT be reinstated automatically because only one IR channel will fall below P-6 and Two are required to remove P-6.
Reference Title / Facility Reference Number Section/Page Revision L O.
' termediate Rangelschematic NI-3 4
a32 Intermediate range nuclearinst Lesson plan 6
4,8,9,10 Material Required for Examination
. Question Source:
New Question Modification Method:
Signirica'ntty Modified Question Source Comments:
Watts Bar 8/94
* Comment Type Comment Friday, July 24,1998 4:34:53 PM Page 109 of 127 Prepared by WD Associates, Inc.
 
i Question Monit:rs f:r S/G Tube leakags The following conditions cxist on Unit 1:
- Reactor power is 75%
-Troubleshooting has commenced due to reduced condenser vacuum with the air ejectors out of service.
- Hogging vacuum pumps are aligned to the main condenser to aid in maintaining vacuum.
What would be an indication of a Steam Generator Tube Leak under these conditions?
: a. Increasing radiation level on 1RE-PR027, "SJAE/Giand Steam Exhaust Monitor".
: b. Decreasing S/G level for ONE S/G.
: c. Increasing feedwater flow to ONE S/G.
i
: d. Decreasing charging header flow to RCS.
Answer a Exam Level R Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 037 AA1,02 rto Value:
3.1 SRO Value:
 
===2.9 Section===
EPE RO Group:
'2 SROGroup:
2 System /Evoiution Steam Generator Tube Leak KA Ability to operate and / or monitor the following as they Apply to Steam Generator Tube Leak:
Condensate exhaust system Explanation of The Hogger discharge is aligned thmugh the Off Gas header which is monitored by 1RE-PR027.
Answer Reference Title /Fac34ty Reference Number Section/Page Revisio L O.
SGTRlesson plan / BWOA Sec 8 6
4 Ch 49 rad monitors lesson plan 7
14 l
Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment l
Frid:y, July 24,1998 4:34.53 PM Page 110 of 127 Prepared,byWD Associates,Inc.
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Question Loss cf subcooling BwEP-3 "Stum G:nerator Tube Rupture" is being performrd in responsa to a tube rupturo on 20 S/G.
The cooldown has just been completed but the target temperature value selected by the operators was l
higher than that stipulated in the procedure.
What condition could result because of this error?
: a. Loss of'RCS subcooling before RCS and ruptured S/G pressures are equalized.
l
: b. Increase in pressure of the ruptured S/G with resultant lifting of the S/G Safety Valve.
: c. Increase in pressure of the non-ruptured S/Gs with resultant lifting of their S/G Safety Valves.
l
: d. Filling the Pressurizer solid during the subsequent depressurization.
Answer a Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:
' g/14/98 KA: 038 EK3.06 RO Value:
4.2 SRO Value:
 
===4.5 Section===
EPE RO oroup:
2 SROGroup:
2 system / Evolution Steam Generator Tube Rupture KA Knowledge of the reasons for the following responses as they apply to Steam Generator Tube Rupture:
Actions contained in EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures Explanation of An:wer C
Reference Title / Facility Reference Number Section/Page Revision L O.
SGTR lesson plan 1BwEP-3 12 1
ERG basis Material Required for Examination Question Source:
New Question Modification Method:
Editorially Modified Question Source Comments:
Salem 6/94 Comment Type Comment o
FridIy, July 24,1998 4:34:55 PM Page 112 of 127 Prepared by WD Associates, Inc.
l l
 
-..-.~.- -.- -
Question Stiamlin3 isolati:n i
The following conditions cxist on Unit 1;
- The Unit was in MODE 3 at normal operating temperature and pressure prior to the event.
- A faulted steam generator has occurred.
- RCS hot leg temperatures - 547'F (A),544*F (B), 545'F (C), 547'F (D)
- RCS cold leg temperatures - 545'F (A), 530*F (B), 543*F (C),- 545*F (D)
- S/G pressures - 700 psig (A), 635 psig (B),690 psig (C), 705 psig (D)
- S/G flow - 0.85 MLB/hr (B)
-_ Containment pressure (Channel) - 8 psig (1), 7.5 psig (2), 7.5 psig (3), 8 psig (4)
Based on these conditions, a main steam line isolation should..
have occurred because of the low pressure in at least ONE S/G.
: m. have occurred because the steamline high negative rate occurred in SIG 18.
: c. NOT have occurred because Containment pressure is below the setpoint for the CNMT High-2 pressure signal.
: d. NOT have occurred because THREE S/Gs have pressures above the isolation setpoint and do NOT indicate high steam flow.
Answer a Exam Level B Cognitive Levei ~ Application.
Facility: Braidwood ExamDate:
9/14/98 KA: 040 AA1.01 RO Value:
4.6 SRO Value:
 
===4.6 Section===
EPE RO Group:
1 SROGroup:
1 SystanfEvolution Steam Une Rupture KA Ablilty to operate and / or monitor the following as they apply to Steam Une Rupture:
Manual and automatic EsFAs initiation Explanation of The steamline isolation signalis generated by the low pressure sensed on 2/3 pressure transmitters in any Answer one SG. CNMT pressues is below the MSLI setpoint of 8.2 psig and steamline negative rate is blocked since initial condition has PZR pressure > P-11.
noserence Tuse/FacNity Reference Number Section/Page Revision L. O.
.ESF SetpointS/ schematic EF-2/ Simline isol 5
Ch 23 Main steam Sys lesson plan 8
5,13,15,16 Ch 61 ESFlesson plan 5
7 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type comment l
Friday, July 24,1998 4:34:55 PM Page 113 of 127 Prepared byWD Associates,Inc.
 
. _ _ _ _ _ _, _... _ ~. -. _ - _. _. _ _ _ _. - _ _ _.
Question Eval of Lsek The following conditions exist on Unit 1 following a trip from 100% power l
- - Pressurizer levelis 0%
l
- Pressurizer pressure is 1500 psig Containment Pressure is 16 psig.
L
- Tcold is 420*F for all loops.
Where is the location of the leak?
: a. On one loop RCS cold leg.
: n. On a Main Steam Line inside containment.
: c. In a Steam Generator Tube.
: 4. On a feedwater line between FWRV and Associated FWlV,1FWOO9.
Answer b Exam Level B C:. J'.; Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: o40 AK1.06 RO Value:
3.7 sRO Value:
 
===3.8 section===
EPE RO Group:
'1 sROGroup:
1 l
systemevolution Steam Line Rupture KA Knowledge of the operationalimplications of the following concepts as they apply to Steam Llne Rup'ture:
High-energy steam line break considerations Explanation of Secondary LOCA not indicated since Tcold is the same in all loops and RCS tcold is not consistent wth given An:wer CNMT pressure for steam / feed break. SGTR notindicated since CNMT pressure is elevated. LOCA condiiton indcated by consistent Tcold, and CNMT pressure increase.
Reference Title / Facility Reference Number section/Page Revisio L O.
1BwEP-0 Reactor Trip or Si lesson plan 3
6,7 1BwEP2 Faulted S?g isolation lesson plan 7
2,4 Material Required for Examination Question source:
New Question Modification Method:
Editorially Modified
' Question source Comments:
St. Lucie 10/13/97
-- Comment Type Comment l
l 1
Friday, July 24,1998 4:34:56 PM Page 114 of 127 Prepared by WD Associates, Inc.
t 1
 
_~.
l eueenen Eval cf conditions l
In cccorda'nce with BwOA SEC-3, " Loss of Condensar Vacuum", which of the following sets of conditions requires the operator to trip the reactor?
I
: a. LOW POWER TRIP BLOCKED P-8 annunciator - LIT.
l Turbine load -200 MW Condenser pressure - 5.2 " HgA
: b. LOW POWER TRIP BLOCKED P-8 annunciator - LIT Turbine load - 300 MW Condenser pressure - 6.3" HgA
: c. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 600 MW Condenser pressure - 7.2" HgA
: 4. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 900 MW Condenser pressure - 7.8" HgA Answer b Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:
9/14/98 MA: 051 AA2.02 RO Value:' 3.9 SRO Value:
 
===4.1 7Section===
EPE Ro Group:
1 SROGroup:
1 l
Syelemevoluson Loss of Condenser Vacuum MA Ability to determine and interpret the fotowing as they apply to Loss of Condenser Vacuum:
l Conditions requiring reactor and/or turbine trip P-8 pennissive active below 30% power (annunciator lit). At 480 MW and below, the minimum acceptable Explanation of Answer condenser pressure is 5.5 in HgA. At 600 MW minimum acceptable pressure is 7. 8 in HgA. At 610 MW and greater, minimum acceptable pressure is 8.0 in HG l-
*ence Titse/ Faculty Reference Number Section/Page Revision L o.
JwCA Ses-3 loss of condenser vaC lesson plan 6
5 Meterial Required for Examination Figure 1BwCA SEC 3-1 Question Source:
New Question Modification Method:
rh=aesant Source Comments:
Comment Type Comment I
i I
l l.
Friday, July 24,1996 4:34:56 PM Page 1155 of 127 Prepared by WD Associates, Inc, t,
1
)
i
 
Question identificati:n cf RCP sell LOCNcooldown Select the primtry basis for r pidly depressurizing ths st=m g:nnr:ttors during a Loss of All AC.
l
: a. To provide maximum core cooling until power can be restored,
: b. To minimize RCS inventory loss from RCP seals.
: c. To enhance restoration of S/G level from the diesel driven AF pump.
- c. To increase subcooling of the RCS..
An:wer b Exam Level B Cognitive Level Mernory Facility: Braidwood ExamDate:
9/14/98 KA: 065 EK3 02 RO Value:
4.3 SRO Value:
 
===4.6 Section===
EPE RO Group:
1 SROGroup:
1 systemIEvolution Station Blackout KA Knowledge of the reasons for the following responses as they apply to Station Blackout:
Actions contained in EOP for loss of offsite and onsite power Explanation of The rapid cooling allows depressuring the RCS reducing the leak rate via the RCP seals An:wer I
Reference Title / Facility Reference Number Section/Page Revision L O.
I Loss of All AC Power /18wCA 0.0 Caution 2 1B Wog 1B 1BwCA 0.0 lesson plan 4
1
)
l Material Required for Examination C
l Question Source:
New Question Modification Method:
(
Question Source Comments:
l Comment Type Comment i
i l
I Friday, July 24.1998 4:34.58 PM Page 117 of 127 Prepared by WD Associates, Inc.
f
 
l l
Question '
R: set of sequ ncer l
How would tha sequ:ncer operats if a Safsty injtetion (SI) acturtion occurs whils tha s:quencar is l
sequencing loads in response to an ESF bus undervoltage condition?
l
: a. There will be no change in operation; the undervoltage sequence overrides the SI sequence.
y b.' The undervoltage sequencing stops, the sequencer immediately resets and Si loads NOT already running will sequentially start.
: e. The undervoltage sequencing stops, all started loads are shed, and Si loads will sequentially start.
i
: d. The undervoltage sequencing completes its cycle, then resets to Si mode, and Si loads NOT already l
running will sequentially start.
Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 056 AA1.21 RO Value:
3.3 sRO value:
 
===3.3 section===
EPE RO Group:
3 sROGroup:
3 l
system / Evolution Loss of Off-Site Power KA Ability to operate and / or monitor the following as they apply to Loss of Off-Site Power:
Roset of the ESF load sequencers Explanation of The UV sequence is stopped and the SARA sequencing is initiated from step 1.
Answer Reference Title / Facility Reference Number section/Page Revision L O.
DIG Relaying schematic DG-21 SARA 8 SDRA 1
Ch 9 EDG and Aux sys lesson plan 7
7 Ch 4 AC Electrical distribution lesson plan 8
10,16 Ch 61 ESF lesson plan 5
7,8 Material Required for Examination Question source:
New Question Modification Method:
Signiricantly Modified Question source Comments:
Vogtle 5/91 Comment Type Comment Friday, July 24,1996 4:34.58 PM Page 118 of 127 Prepared by WD Associates. Inc.
i
 
~.
Question Eval of clIctric bus status The following conditions exist on Unit 1:
- Bus 141 is powered from its normal source
- D/G 1 A surveillance is being performed with the D/G paralleled to the bus What would occur if a failure of the undervoltage relay results in a sensed undervoltage condition on Bus 1417 l
1
: c. SAT feeder breaker ACB 1412 and D/G feeder breaker ACB 1413 remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.
: b. SAT feeder breaker ACB 1412 and D/G feeder breaker ACB 1413 will open. After a 10-second delay, ACB 1413 will close and the Safe Shutdown loads will sequence.
: c. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The 1
Safe Shutdown loads will sequence normally.
: d. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.
Answer d Exam Leve4 B Cognitive Level Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 056 AA2.46 RO Value:
4.2 SRO Value:
 
===4.4 Section===
EPE RO Group:
3 sROGroup:
3 systenWEvolution Loss of Off-Site Power A
Ability to determine and interpret the following as they apply to Loss of Off. Site Power:
That the ED/Gs have started automatically and that the bus tie breakers are closed Explanation of On sensed UV, the SAT feeder breaker opens (and alternate feeder breaker would also have opened if closed)
Answer and the control switches for the safe shutdown loads will be locked out.
Reference Title / Facility Reference Number Section/Page Revision L O.
Ch 4 AC Electrical Distribution 8
10,16 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment l
Frid:y, July 24.1998 4:34:59 PM Page 119 of 127 Prepared by WD Associates. Inc.
 
.~.
i Eqpt affected cn bus loss On Unit 1 power is lost to 120 VAC Instrum::nt Bus 111 How are the ESF and Safe Shutdown loads affected?
: a. "A" Train ESF loads will NOT load on an SI signal, but Safe Shutdown loads will load on a UN signal.
"B" Train loads are NOT affected,
: b. A" Train ESF loads will load on an SI signal, but Safe Shutdown loads will NOT load on a UN signal.
"B" Train loads are NOT affected.
i l
l
: c. "A" Train ESF loads will NOT load on an SI signal, and Sa% Shutdown loads will NOT load on a UN signal.
"B" Train loads are NOT affected.
: d. "A" Train AND "B" Train ESF loads will NOT load on an SI signal, but Safe Shutdown loads will load on a UN signal.
Answer C Exam Level B C: lxLevel Comprehension Facility: Braidwood ExamDate:
9/14/98 KA: 067 AA2.19 RO Value:
4.0 sRO Value!
4.3 ~ Section: EPE RO Group:
1 SROGroup:
1 systemevolution Loss of Vital AC Instrument Bus KA Ability to determine and interpret the following as they apply to Loss of Vital AC instrument Bus:
The plant automatic actions that wit occur on the loss of a vital ac electricalinstrument bus Explanation of Answer Reference Title / Facility Reference Number Section/Page Revision L. O.
'9woA Elec 2 Loss ofinst bus Table A 7
sti 60a SSPS lesson plan 3
11 18woA elec 2 lesson plan 6
3,5 I and C system notes I&C1 Material Required for Examination
* Question Source:
New Question Modification Method:
- Question Source Comments:
Comment Type Comment i
Asy, July 24,1998 4:34.59 PM Page 120 of 127 Prepared byWD Associates,Inc.
I i
 
_..... _ _ _ - ~, _ -. _ _ _ _ _ _.. _..
Question Operati:ns required for transfIr S:: lect the method used for transfcrring controls to tha remots shutdown pin:Is PLO4/05J.
Placing applicable transfer switches in LOCAL on RSP.
: b. Opening the isolation switches in the Auxiliary Electric Room.
: e. Deenergizing normal control power to individual controls.
: d. Taking local controls out of the PULL-TO-LOCK position.
Answer a Exarn Level B cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 KA: osa AA1.21 RO Value:
3.9 SRO Value:
 
===4.1 Section===
EPE RO Group:
1 SROGroup:
1 SystenWEvolution Control Room Evacuation KA Ability to operate and / or monitor the following as they apply to Control Room Evacuation:
Transfer of controls from control room to shutdown panel or local control Explanation of An:wer Reference Title / Facility Reference Number Section/Page Revisio L O.
RSP PLO4/5J/ schematic PN-1 2
Control Room Inaccessbility 18wOA Pri-5 lesson plan Att. A 578 Ch 62 Remote shutdown Panel Lesson plan 3
3,4 Material Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comment J
Friday, July 24,1998 4:35.00 PM Page 121 of 127 Prepared by WD Associates,Inc.
 
I l
euestion M: Jar ccti:n categories j
When ina'dequ;.ta cor:3 cooling exists', which of tha following sats of cctions ststr
% nrop:r s:quence of the major action categories to be performed in accordance with BwFR-C.1, "Ph Y E TO INADEQUATE CORE COOLING", for removing decay heat from the core?
: a. Reinitiation of safety injection; RCP restart; rapid secondary depressurization.
: m. Reinitiation of safety injection; rapid secondary depressurization; RCP restart.
l.
' e. RCP restart; reinitiation of safety injection; rapid secondary depressurization.
l l
: d. RCP restart; rapid secondary depressurization; reinitiation of safety injection.
l l
Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:
IW14/98 l
KA: 074 EK1.03 RO Value:
4.5 SRO Value:
 
===4.9 Section===
EPE RO Group:
1 SROGroup:
1 systenWEvolution inadequate Core Cooling KA Knowledge of the operationallmplications of the following concepts as they apply to inadequate Core Cooling:
Processes for removing decay heat from the core I
. Explanation of An:wer j
1 Reference Title / Facility Reference Number
* Section/Page.
Revisio L O.
Function Restoration Procedures BwFR-C.1, C.2, b.
5 2,3 T
C.3 lesson plan Material Required for Examinatbn Question Source:
New Question Modification Method:
Editorially Modified Question Source Comments:
VC Summer 5/94 Comment Type Comment l.-
l c iday, July 24,1996 4:35:00 PM Page 122 of 127 Prepared by WD Associates, Inc.
r 1
 
Question Actions for reducing activity High coolint activity his been d:t ct:d and ch:mistry has d:termin:d that it is dus to corrosion product cctivation.
dentify the effect of placing the cation demineralizer in service.
i The cation demineralizer..
: c. will remove lithium so it should NOT be used in this condition.
j
: b. will cause the activity level to decrease as soon as it is placed in service.
: e. is NOT efiective in removing corrosion product activity.
: d. is less offective than the mixed bed demineralizer so it is placed in ser. ice ONLY if decontamination factor is less than 10.
Answer b Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate 9/14/98 KA: 076 AA2.02 RO Value:
2.8 SRO Value:
 
===3.4 Section===
EPE RO Group:
1 SRO GroNp:
1 system / Evolution High Reactor Coolant Activity KA Ability to determine and interpret the following as tney apply to High Reactor Coolant Activity:
Corrective actions required for high fission product activity in RCs Explanation of The cation demin is highly effective in removing corrosion products from the coolant.
Answer Reference Title / Facility Reference Number hection/Page Revision L O.
i BwOP CV-8 1BwOA Pri-4 High coolant Activity lesson plan 1
4,5 ch 15a CVCS lesson plan 10 4
.aterial Required for Examination Question Source:
New Question Modification Method:
Question Source Comments:
Comment Type Comnwnt Friday, July 24,1998 4:35:01 PM Page 123 of 127 Prepared byWD Associates,Inc.
I
 
_m
 
===%
intirlocks affecting reestiblishm nt of feed The following conditions exist on Unit ~1:
- Reactor power was 8% prior to the event below.
A failure in the feedwater control system caused ONE S/G level to exceed P-14.
-The main turbine tripped.
- S/G levels have returned to their normal level range
-The Startup FW Pump is running What are all the conditions that would have to be met to feed the S/Gs using the FWO34's Feedwater Tempering Flow Control valves?
: a. The FW lsolation Aux Relays would have to be reset and FWO35 Feedwater Tempering isol valves
. opened.
: b. The reactor trip breakers would have to be cycled, the FW lsolation Aux Relays would have to be l
reset and FWO35 Feedwater Tempering isol valves opened.
l
: c. The FW lsolation Main Relays and Aux Relays would have to be reset and FWO35 Feedwater Tempering Isol valves opened.
: 4. The reactor trip breakers would have to be cycled and FW isolation Main Relays and Aux Relays reset and FWO35 Feedwater Tempering isol valves opened.
i Answer a Exam Level B Cog tiveLevel Application Facility: Braidwood ExamDate:
9/14/98 KA: E05 EK2.1 RO Value:~ 3.7 sa0 value:
 
===3.9 section===
EPE RO Group:
2 sROGroup:
2 l
systenWEvolution Loss of Secondary Heat Sink KA Knowledge of the interrelations between Loss of Secondary Heat Sink and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic j
and manuel features.
f Explanation of The P-14 dpei, once clear, only malnaltns FWI signal via the FW lsol Aux relays if NO reactro trip signalis Answer present. So reseting the FW lsolation Aux relay allows opeing of FWO35s (normal feed path at low power) and i
throttling of FWO34s
~
l Reference Title /Facally Reference Number section/Page Revision L O.
ESF setpoints/ schematic EF-2/ reset FWI 5
l Feedwater Simple /SGWLC FW-1,2/ reset FWI O
6 4,7,8 Ch 61 ESF lesson plan Material Required for Examination Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment l
Friday, July 24,1996 4-35:02 PM Pa0e 124 of 127 Prepared by WD Associates. Inc.
(
 
Topic th M Identification of heat rem: val process The following conditions exist on Unit 1:
l
- A leak developed on the RCS loop C flow instrument piping.
~
- Coincident with the RCS leak, on the reactor trip a S/G PORV failed open and was later isolated.
- FR-P.1 was entered to due to an ORANGE PATH condition.
l
- Si actuated and has been reset.
- All RCPs are stopped
- Conditions required to support an RCP start are met.
l What is the basis for operation of a RCP7 Under the current conditions starting the RCP will...
: a. cause excessive thermal stresses in the stagnant loops.
: 6. cause a pressure surge that will aggravate the PTS condition.
: e. provide mixing of the ECCS injection flow thsreby decreasing the likelihood of PTS.
l
: d. increase the RCS cooldown rate thereby increase the likelihood of PTS.
Answer C Exam Level B c:. ^'..Levet Comprehension ~ Facility: Braidwood ExamDate:
9/14/96 KA: E06 EK2.2 RO Value:
3.6 sRO Value:
 
==4.0. section==
EPE RO Group:
1 sROGroup:
1 systanIEvolution
 
==Title:==
Pressurized Thermal Shock KA statement:
Knowledge of the interrelations between Pressurtzed Thermal Shock snd the following:
Facility's heat removal systems, including primary coolant. emergency coolant. the decay heat removal systems. and relations between the proper operation of these systems to the operation of the facility.,
Explanation of Answer Reference Title / Facility Reference Number section/Page Revisin L O.
FRP 1BwFR P.1,2, lesson plan 4
3,4 Status Trees ST-l/ Integrity l
Material Required for Examination Question source:
New Question Modification Method:
(
Question source Comments:
Comment Type Comment "e
l
' day, July 24.1996 4:35:02 PM Page 125 of 127 Prepared by WD Associates, Inc.
 
Question Natural Circ conditi:ns and limits Why is it import nt to run the CRDM Wnt frns wh n performing a natural circuintion cooldown?
: a. Aids the operator in maintaining subcooling in the ~ reactor vessel head.
I
: b. Aids in' natural circulation flow through the RCS head region.
: c. Minimizes stresses on the reactor vessel heaci due to uneven cooldown.
: d. Aids in natural circulation flow through the RCS.
Answer a Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:
9/14/98 MA: E00 EK3.1 RO Value:
3.3 sRo value:
 
===3.6 section===
EPE Ro oroup:
1 sRooroup:
1 systenWEvolution Natural Circulation Operations KA Knowledge of the reasons for the followin0 responses as they apply to Natural Circulation Operations:
Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating firnitations and reasons for these operating characteristics.
Explanation of Answer Reference Title / Facility Reference Number section/Page Revision L O.
18wEP -0 Reactor Trip or SI Lesson plan 11 3,4,6 C
Material Required for Examination Question source:
New Question Modification Method:
Question source Comments:
Comment Type Comment l
i Friday, July 24,1998 4.35:03 PM Page 126 of 127 Prepared by WD Associates, Inc.
l l
 
Question RIsson forrapid S/G d:pressurizati n Why are the S/Gs d:pr:ssurized to less thin 670 psig according to BwCA-1.1, " Loss of Em:rg:ncy Coolant Recirculation'"?
To allow maximum AFW flow to the S/Gs.
: b. To ensure adequate subcooling for restart of the RCPs.
l
: c. To set up conditions for controlled injection to the RCS from the accumulators.
: 4. To decrease RCS temperature and pressure which reduces break flow in a LO'CA condition.
Answw C Exam Level B Cognitive Level Memory Facety: eraidwood ExamDate:
9/14/98 KA: E11 EA1.1 RO Value:
3.9 sRo value:
 
==4.0 section==
EPE RO Group:
2 sRooroup:
2 systenWEvolution Loss of Emegency Coolant Recirculation KA Ability to operate and / or monitor the followith as they apply to Loss of Emergency Coolant Recirculation:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
*- ' :":: of The concem is maximizing cooling volumes that supply water to RCS. By cooling RCS, depressurization of Answer RCS ca'i be initiated (while maintaining,subcooling) to the point where the Si accumulators inject their volumes into the RCS.
).
' M ion /Page Revision L. O.
Reference Title /FacMity Reference Number Loss of Emergency Coolant Recirc/1BwCA 1.1 1B WOG 1B 18wCA 1.1 and 1.2 lesson plan
.7 3
2 Material Required for Examination Question source:
New Question Modification Method:
Editorially Modified Question source Comments:
South Texas 9/92 comment Type Comment
\\
+
E Friday, July 24,1998 41.o4 PM Page 127 of 127 Prepared byWD Associates,Inc.
.}}

Latest revision as of 21:21, 10 December 2024

Forwards Exam Matls,For Review,Comment & Approval,For Initial License Written re-exam of R Sherman for Week of 980914
ML20155G138
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 07/30/1998
From: Tulon T
COMMONWEALTH EDISON CO.
To: Hironori Peterson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20155F786 List:
References
NUDOCS 9811060212
Download: ML20155G138 (120)
v • d • e


Text

,g Ciniimonwcalth lihuni Comliany

+,

liraittwoost Gcncrating Station

  • Route
  • I, llox H I liraceville, IL 60 a0-'%l 9 Tel H15-458 2801 July 30,1998 Mr. Hironori Peterson U. S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, IL 60532-4351

Dear Mr. Peterson:

Enclosed are the examination materials that Braidwood Generating L s n is submitting for review, comment, and approval for the Initial License Written Re-examination of Mr.

Robert Sherman scheduled for the week of September 14, 1998, at Byron Generating Station.

This submittal includes the Reactor Operator Written Examination.

This examination material has been developed in accordance with Interim Revision 8 of NUREG-1021, " Operator Licensing Examiner Standards". Please note that reference materials are attached to each individual examination question per your request.

Some minor modifications have been made to the Integrated Examination Outline with regards to the written examination in order to improve balance and content. These changes improve the examination quality and compliance with Interim Revision 8 of NUREG-1021, " Operator Licensing Examiner Standards".

Quantitative and qualitative validation of the examination material will occur during the next three weeks. Some modifications or adjustments to the examination material may be required.

Please ensure that these materials are withheld from public disclosure until after the examination is completed.

If you have any questions or concers regarding this submittal, please contact Scott Deprest at (815) 458-3411 extension 2250 or Paul Hippely at extension 2235.

Sincerely, l

T'

. Tulon j

' e Vice President raidwood Nuclear Generating Station e

9811060212 981102 PDR ADOCK 05000456 V

PDR A l'nicom (' niijiatiy a

I l

l.

l' Mr. Hironori Peterson l

' July 30,1998 l

Page 2 List of

Enclosures:

)

l Updated RO Written Exam Sample Plan i

[

RO Composite Examination with references attached Completed ES-401-6 Checklist -

Examination Security Agreement (ES-201-3)

Listing of Submitted Sample Plan Changes cc:

w/o Enclosures Regulatory Assurance B. Wegner J. Walker D. Hoots C. Cerovac P. Hippely T. Benton L. Holden Class File

. nrc/9so479t. doc 1

t l.

,m.

1

?

j l

ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Braidwood 1 & 2 Date of Exam:

September 14,1998 Exam Level: RO K/A Category Points Tier Group Point K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

Total l.

1 2

2 2

4 6

16 Emergency &

l 2

3 2

3 6

2 1

17 Abnormal Plant Evolutions 3

1 1

1 3

Tier Totals 5

4 6

11 9

1 36 1

3 2

1 2

2 1

1 2

3 4

2 23 2.

2 2

2 2

2 1

2 2

3 2

2 20 Plant Systems 3

2 1

1 1

1 1

1 8

Tier Totals 7

2 4

5 4

2 3

5 7

7 5

51

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 13 -

5 3

2 3

Note: 3 Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.

3 Actual point totals must match those specified in the table.

3 Select topics from many systems; avoid selecting more than two or three K/A topics from a given l

system unless they relate to plant-specific priorities.

3 Systems / evolutions within each group are identified on the associated outline.

3 The shaded areas are not applicable to the category / tier.

NUREG-1021 30 of39 Interim Rev. 8, January 1997 l

l

PWRRO amination' Outline -

Facility Braidwood Ex m Dats:

9/14/98 Examination Levet RO Section Title Genenc Krs;.t$ and Abilities t

RO Group 1

~

l System / Evolution K/A '

RO KA Statement Level. Question Topic Conduct of Operations 2.1.1

. 3.7 Krs;.t$ of conduct of opershons requirements. B ' Evaluation of requirement for"achve" license i

2.1.1 3.7 Krs;.tJue of conduct of operations requirements. B ' Direchon of NLO personnel 2.1.2 3.0 Knowledge of operator responsibilities during all B

Operating Daily Orders f

modes of plant operation.

2.1.23 3.9 Ability to perform specific system and integrated B

Procedure required usage plant procedures during all modes of plant operation.

2.1.24-2.8 Ability to obtain and interpret station electrical and B Use of electrical prints mechanical drawings.

Equipment Control 2.2.13 3.6 Knowledge of tagging and clearance pmcedures.

B MOVtagout -

I 2.2.26 2.5 Knowledge of refueling administrative B

RCS level discrepancy during refueling requirements.

t 2.2.32 3.5 Knowledge of RB outes in the control room during B - RO duties in Control Room during refueling i

fuel handtag such as alrms from fuel handling area, communication with fuel storage facility, systems operated fmm the control room in support of fueling operations, and supporting instrumentation.-

i Radiation Control 2.3.1 2.6 Knowledge of 10 CFR: 20 and related facility B

Radiation exposure determination i

radiation control requirements.

2.3.10 2.9 Ability to perform procedures to reduce excessive R Fuel Handling Accident Response levels of radiation and guard against personnel exposure.

Emergency 2.4.16 3.0 Knowledge of EOP implementation hierarchy and B Performance of Status Trees / Function Restoration f

Procedures / Plan coordination with other support procedures.

2.4.20 3.3 Knowledge of operationalimplications of EOP B

Applicability of EOP Foldout Page wamings, cautions, and notes.

2.4.31 3.3 Knowledge of annunciators alarms and indications, B Identification of inoperable CR annunciators and use of the response instructions.

Friday, July 24,1998 5:02:52 PM Page 1 Prepared by WD Associates. Inc.

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u- -

PWRRO amination Outline Facility-Brcidwood Exam Dat :

9/14/98 Examination Level: RO Section Title Plant Systems RO Group 1

System / Evolution K/A RO KA Statement Level Question Topic Control Rod Drive 001 A2.06 3.4 Effects of transient xenon on reactivity B

Effect of Xenon Transient & compensation System 001 K1.03 3.4 CRDM B

Application of DC Hold R; actor Coolant Pump 003 A1.06 2.9 PZR spray flow B

RCP and Pzr spray operations System 003 K2.01 3.1 RCPS R

RCP Breaker & interlocks Chemical and Volume 004 A3.11 3.6 Charging / letdown R

Charging & letdown flows (including seal injection)

Control System 004 A4.07 3.9 Boration/ dilution B

Calculation of dilution 004 K6.01 3.1 Spray / heater combination in PZR to assure R

Boron mixing unifonn boron concentration Engineered Safety 013 A3.01 3.7*

Input channels and logic B

CNMT Spray / Phase B Features Actuation System 013 K4.13 3.7 MFWisolation/ reset R

FW lsolation - P14 Nuclear 015 A2.02 3.1 Faulty or erratic operation of detectors or B

SR NIS discriminator failure instmmentation compensating components System 015 K2.01 3.3 NIS channels, components, and interconnections B

SR NIS-loss of control power 015 KS.06 3.4 Subcritical multiplications and NIS indications R

Eval for 1/M - Eightfold increase In-Core Temperature 017 K4.01 3.4 Input to subcooling monitors R

CETC failure effect on Subcooling Monitor / Iconic Monitor System Display Containment Cooling 2.1.32 3.4 Ability to explain and apply all system limits and R

RCFC operations requirements System precautions.

Miin Feedwater 2.1.7 3.7 Ability to evaluate plant performance and make B

S/G Level program -low power System operational judgments based on operating characteristics, reactor behavior, and instmment l

interpretation.

059 K1.04 3.4 S/GS waterlevel control system R

Effect of failure of S/G steam pressure channel Friday, July 24,1998 5:02:54 PM Page 2 Prepared by WD Associates. inc.

PWRRO amination Ouuine Facility t$rtidwood Ex:m DatI 9/14/98 Ex mination Level: RO.

Section Title Plant Systems RO Group

. 1 SystemEvolution K/A' RO. KA Statement Level Question Topic Auxiliary / Emergency 061 A3.01 4.1 AFW stastup and flows B

AFW Startup -

' Feedwater System 061 K5.02 3.2. Decay heat sources and magnitude B ' AFW flow requirements for cooldown Liquid Radwaste 068 A4.04.

3.8 Automaticisolation B

RCDT operation - effect of CNMT isolation System

- 068 K1.07 2.7. Sources ofliquid wastes for LRS.

R CNMT Sump sources of input during normal operation i

Waste Gas Disposal 071 A4.05 2.6* Gas decay tanks, including valves, indicators, and R Waste Gas Decay Tank Operations System sample line -

Area Radiation 072 A4.03 3.1 Check source for operability demonstration R

Check Source operation Monitoring System 072 K3.02 3.1 Fuel handling operations B

Loss of FHB Overtread Crane rad monitor. -

i P

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l Friday, July 24,1998 5:02:54 PM Page 3 Prepared by WD Associates, Inc.

l

. _ _ - _ _ _ _ _ _ ~

PWRRO amination Outline

~

Facility-Brridwood Ecm Dats:

9/14/98 Ermin:. tion Lcvel: RO Section Title Plant Systems RO Group 2

System / Evolution K/A RO KA Statement Level Question Topic R, actor Coolant 002 A1.11 2.7 Relative level indications in the RWST, the B

Relationship of levels during refueling operations System refueling cavity, the PZR and the reactor vessel during preparation for refueling 002 A3.01 3.7 Reactor coolant leak detection system R

RCS leak Detection Systems 002 K4.09 3.2 Operation ofloop isolation valves.

R Use of Loop Isolation Valves Emergency Core 006 A2.13 3.9 Inadvertent SIS actuation B

Systems response to SI/ Actions Cooling System 006 K3.02 4.3 Fuel B

10CFR50.46 Design Criteria 006 K6.03 3.6 Safety injection Pumps B

Evaluation of flow ECCS pumps Pressurizer Pressure 010 A1.08 3.2 Spray nozzle DT B

Spray using Normal and Aux Spray Centrol System 010 KS.01 3.5 Determination of condition of fluid in PZR, using B

Evaluation of Pzrconditions steam tables Pressurizer Level 011 K1.04 3.8 RPS B

Pzr Level Reactor Trip Control System R; actor Protec2 ion 012 A3.07 4.0 Trip breakers R

Operation of BOTH Bypass Trip Breakers System 012 A4.03 3.6 Channel blocks and bypasses B

input that can be bypass & condition 012 KS.01 3.3*

DNB R

OTdTinputs & effect of changes Rod Position Indication 2.4.31 3.3 Knowledge of annunciators alarms and indications, R ROD BOTTOM Alarm operation System and use of the response instructions.

Non-Nuclear 016 K3.02 3.4*

PZR LCS B

NR RTD Failure effects Instrumentation System Containment Spray 026 A2.08 3.2 Safe securing of containment spray when it can be B Sequence for securing CNMT Spray System done) 026 A4.01 4.5 CSS controls R

Pump operation interiocks Spent Fuel Pool 033 K1.05 2.7* RWST R

RWST Purification Loops Cooling System Friday, July 24,1998 5:02:55 PM Page 4 Prepared by WD Associates, Inc.

PWR RO unination Outline Facility Brridwood Exam Date:

9/14/98 Examination Level: RO Section Title Plant Systems RO Group 2

System / Evolution K/A RO KA Statement -

Level Question Topic D.C. Electrical 2.1.30 3.9 Ability to locate and operate components, B

DC bus battery charger Distribution including local controls.

Emergency Diesel 064 A3.07 3.6* Load sequencing B

Sequencing of ESF pumps-SI & SI w LOP Generators Fire Protection 086 K4.06 3.0 CO2 B

Effect ofloss of DC - CO2 aduation System i

Friday, July 24,1998 5:02:56 PM Page 5 Prepared byWD Associates,Inc.

i

~

PWR RO -

unination Outline Facility.- Esraidwood Ex:m Dato:

9/14/98 Examination Level: RO Section Title Plant Systems RO Group

'3 System /Evoluhon K/A RO KA Statement Level Question Topic.

l Residual Heat

' 005 K1.12 3.1 Safeguard pumps B

Recist interties to St Pumps & CV Pumps Removd System -

005 K4.10 3.1 Control of RHR heat exchanger outlet flow R

Failure of Hx Outlet Valve Pressurizer Relief 2.4.50 3.3 Ability to venfy system alarm setpoints and R

PRT conditions causing alann/ response Tank / Quench Tank operate controls identified in the alarm response System manual.

t Component Cooling 008 A2.05 3.3* ~ Effect ofloss of instrument and control air on the R

Determination of effect of valve pos. Toning

[

Water System position of the CCW valves that are air operated

[

Containment lodine 027 A4.03 3.3*

CIRS fans R

Charcoal Filters response to deluge f

Removal System Steam Dump System 041 A3.02 3.3 RCS pressure, RCS temperature, and reactor B

Steam Dump input malfunction i

and Turbine Bypass ~

power Control

[

Main Turbine 045 K1.20 3.4 Protection system R

Turbine Control response to Failed impulse Channel Generator System j

instrument Air System 078 K3.02 3.4 Systems having pneumatic valves and controls B

Evaluation of eqpt affected for slow loss

^

f i

i t

l i

Friday, July 24,1998 5:02:56 PM F.;e 6 Prepared by WD Associates, Inc.

I l

PWRRO nmination Outline Facility-t$rCidwood Excm Datz 9/14/98 Ermirttion Level: RO Section Title Emergency cnd Abnormal Plant Evolutions RO Group 1

Oystem/ Evolution K/A RO KA Statement Level Question Topic R; actor Coolant Pump 015 AA2.10 3.7 When to secure RCPs on loss of cooling or seal B

Evalloss of cooling fim Malfunctions injection 015 AK2.07 2.9 RCP seals B

Eval of RCP seal failure Emergency Boration 024 AA2.05 3.3 Amount of boron to add to achieve required SDM B

Time / amount E-boration for condition Loss of Component 026 AA1.05 3.1 The CCWS surge tank, including level control and B Evaluation of CCWleak Cooling Water level alarms, and radiation alarm Pressurizer Preseure 027 AA1.01 4.0 PZR heaters, sprays, and PORVs B

Pressure controller step change Control Malfunciion 027 AA2.15 3.7 Actions to be taken if PZR pressure instrument B

Non-Controlling channel failure fails high Steam Line Rupture 040 AA1.01 4.6 Manual and automatic ESFAS initiation B

Steamline isolation 040 AK1.06 3.7 High-energy steam line break considerations B

Eval of Leak Less of Condenser 051 AA2.02 3.9 Conditions requiring reactor and/or turbine trip B

Eval of conditions Vacuum Station Blackout 055 EK3.02 4.3 Actions contained in EOP forloss of offsite and B

Identification of RCP seal LOCA/cooldown onsite power 1

Loss of Vital AC

05) AA2.19 4.0 The plant automatic actions that will occur on the B

Eqpt affected on bus loss Instrument Bus loss of a vital ac electrical instrument bus Contrel Room 068 \\A1.21 3.9 Transfer of controls from control room to shutdown B Operations required for transfer Evacuatan panel orlocal control Inadequate Core 074 EK1.03 4.5 Processes for removing decay heat from the core B Major action categories i

Cooling High ReactorCoolant 070 AA2.02 2.8 Corrective actions required for high fission product B Actions for reducing activity Activity activity in RCS Pressurized Thermal E08 EK2.2 3.6 Facility's heat removal systems, includinq primary B Identification of heat removal process Shock coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Friday, July 24,1998 5:02:57 PM Page 7 Prepared by WD Assaciates, Inc.

l 4

^

PWR RC amination Outline Facility-Braidwood Exam Date:

-9/14/98 Examination Level: RO ~

Section Title Emergency and Abnormal Plant Evolutions RO Group 1

SystenVEvolution K/A RO KA Statement Level Question Topic Natural Circulation E09 EK3.1 -

3.3. Facility operating characteristics during transient B

Natural Circ conditions and limits Operations conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

b t

I s

i 1

t r

Friday, July 24,1998 5:02:58 PM Page 8 Prepared by WD Assodates, Inc.

l i

PWRRC aminetion Outline Facility-t$rcidwood Ex:tm Dats:

9/14/98 Examination Levet RO Section Title Emergency and Abnonnal Pt;nt Evolutions RO Group 2

System / Evolution K/A RO KA Statement Level Question Topic Continuous Rod 001 AA2.05 4.4 Uncontrolled rod withdrawal, from available B

Evaluate conditions - unwarranted rod withdrawal Withdrawal indications Dropped Control Rod 003 AK3.10 3.2? RiL and PDIL B

P/A vs. Group Step Counters Reactor Trip 007 EA1.03 4.2 RCS pressure and temperature B

Stabilized RCS temperature with failure of Steam i

Dumps 007 EK2.03 3.5 Reactor trip status panel R

Reactor Trip requirements Pressurizer Vapor 008 AK1.01 3.2 Thermodynamics and flow characteristics of open R Tail-Pipe conditions ~

i Space Accident orleaking valves Small Break LOCA 009 EA1.10 3.8*

Safety parameterdisplay system B

Calculation of subcooled margin on Icorucs i

1 Large Break LOCA 011 EA1.03 4.0 Securing of RCPs B

RCP trip criteria evaluation i

Loss of Reactor 022 AA1.08 3.4 VCTlevel B

VCTlevel transmitter malfunction Coolant Makeup t

Loss of Residual Heat 025 AK1.01 3.9 Loss of RHRS during all modes of operation B

Calc of time to saturation / core boiling Removal System I

i

\\

025 AK3.01 3.1 Shift to altemate flowpath B

Altemate RCS cooling Anticipated Transient 2.4.48 3.5 Ability to interpret control room indications to verify B AMS conditions l

l Without Scram the status and operation of system, and 1

understand how operator actions and directives affect plant and system conditions.

[

Loss of Source Range 032 AK1.01 2.5 Effects of voltage changes on performance B

Evaluation of SR NlS voltage failure i

Nuclear Instrumentation c

Loss of Intermediate 033 AA2.04 3.2 Satisfactory overlap between source-range, B

Eval of failed IR channel on SU

[

Ringe Nuclear intermediate-range and power-range l

Instrumentation instrumentation

[

Steam Generator Tube 037 AA1.02 3.1

  • Condensate exhaust system R

Monitors for S/G Tube leakage Leak t

Steam Generator Tube 038 EK3.06 4.2 Actions cWained in EOP for RCS water inventory B Loss of subcooling Rupture balanc' 3 tube rupture, and plant shutdown proced :es i

L Friday, July 24,1998 5:02:59 PM Page 9 Prepared by WD Associates, Inc.

i

Facility-Braidwood Exam Datz 9/14/98 Extmination Level: RO

- Section Title Emergency and Abnormal Plant Evolutions.

RO Group 2

System / Evolution K/A RO KA Statement Level Question Topic Loss of Secondary EOS EK2.1 3.7 Components, and functions of control and safety B

Interfocks affecting reestablishment of feed Heat Sink systems, induding instrumentation, signals, interiocks, failure modes, and automatic and manual features.

Loss of Emergency E11 EA1.1 3.9 Components, and functions of control and safety B

Reason for rapid S/G depressurization Coolant Recirculation systems, induding instrumentation, signals, interlocks, failure modes, and automatic and l

manual features.

)

Friday, July 24,1998 5:02:59 PM Page 10 Prepared by WD Associates. Inc.

PWR RC mmination Outline Facility tsraidwood Exam Dat3:

9/14/98 Examination Level: RO Section Title Emergency and Abnormal Plant Evolutions RO Gmup 3

System / Evolution K/A RO KA Statement Level Question Topic Pressunzer Level 028 AK3.05 3.7 Actions contained in EOP for PZR level B

Failed level channellow.

Control Malfunction malfundion Loss of Off-Site Power 056 AA121 3.3*

Reset of the ESF load sequencers B

Reset of sequencer 056 AA2.46 4.2 That the ED/Gs have started automatically and B

Eval of electric bus status that the bus tie breakers are closed i

s t

[

Friday, July 24,1998 5:03:00 PM Page 11 Prepared bywo Associates,Inc.

=____ _

i i

ES-401 Site-Specific Written Examination Form ES-401-7 Cover Sheet a-

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R;cctnrOp ratorExamination

1. An operator sits for the NRC License Operator Examination (l'nitial), successfully passes the Examination and is granted an NRC Senior Operator License or Reactor Operator license this month. What are the requirements for having the license on ACTIVE STATUS?
a. The individual must meet the time on shift requirements of SEVEN 8-hour shifts before the license is in ACTIVE STATUS.
b. The license is considered in ACTIVE STATUS for the current quarter ONLY.
c. The individual must meet the time on shift requirements of SEVEN 8-hour shifts to have a license in ACTIVE STATUS for the next quarter.
d. The license is considered in ACTIVE STATUS for the current and next quarter.

2.The following conditions on Unit 1:

- Reactor power 45%

- 1 A and 1C Feedwater pumps are operating

- FW PUMP TURB BRNG OIL LEVEL HIGH LOW annunciator (1-16-D3) alarms and the SER monitor indicates a low level.

- An EA is dispatched and confirms a low level exists.

In performing actions to correct the condition (per BwOP TO-08 " Filling a Turbine Feed Pump Oil Reservoir"), what is the normal relationship between the US, the NSO and the EA?

a. L The US will direct the EA's activities, but will inform the NSO before the job commences.
b. The US will direct the EA's activities, and need NOT inform the NSO unless unit controls are
affected,
c. The NSO will direct the EA's activities, but will inform the US before the job commences.
d. The NSO will direct the EA's activities, and need NOT inform the US unless unit load is affected.

Page 1 of 50

Rccctar Op: rater Excminction

-3. How is a procedure change, which significantly changes normal processes, procedurally conveyed to licensed members of the operating crew?

a. The SM places the applicable information in the Daily Order Book, and issues an additional memo to all crew personnel that is initialed.
b. The SM is informed by memo of the addition to the Daily Order Book, and makes an announcement of the addition during the shift briefing.
c. The SOS places the applicable information in the Daily Order Book, and the individual operator is responsible for reviewing the Daily Order.

d.' The US places the applicable information in the Daily Order Book, and makes an announcement of the addition during the shift briefing.

- 4. An example of a licensed operator evolution that can be performed WITHOUT either referring to an operations procedure or having a procedure in-hand is...

a. Adjusting rod position following a boration.

b, - Starting the 1 A Heater Drain Pump,

c. Placing excess letdown in service.
d. Latching and rolling up the main turbine.

5. Assuming an auto-close signal is continuously present in the circuit for the 1 A SI pump, which contact will be maintained open in order to prevent the starting relay (SR) from attempting repeated breaker closures onto a faulted bus?

(E 1-4030-S101 is provided for use.)

a. LC SW
b. 52/b

. c. Y H

d. LS Page 2 of 50

React:r Operatcr Examination 6. An operator is preparing an OOS that designates 1CC685, RCP Thermal Barrier CC Return CNMT isolation valve, as an isolation point.

j What is the acceptability of using this isolation point?

The OOS is...

a. acceptable only if the MOV is tagged at its control switch, power supply and valve handwheel.
b. acceptable only if the.MOV is tagged at its control switch, power supply and a blocking device is placed on the valve.
c. NOT acceptable because the MOV fails to meet isolation requirements.
d. NOT acceptable because the valve fails open on a loss of power.

7.The following conditions exist for Unit 1:

- Unit shutdown and cooldown initiated 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> ago

- Lowering of RCS level to the reactor vessel flange is underway

- RCS temperature 95*

- RCS level Control Room indicators: 1LI-RYO46 - 401'0" 1Ll-RYO49 -

402'1"

- RH loop 1 A in operation with " normal" indications What is the appropriate action for these conditions?

a.. The lowering of RCS level can continue.
b. The level change must be stopped until the cause for the level discrepancy is determined.

. c. When temperature correction is applied to the highest Control Room level indication, the running RHR pump must be stopped to prevent cavitation.

d. When temperature correction is applied to the lowest Control Room level indication, the available S1 Pump aligned for hot leg injection must be started.

8.What is a responsibility of the NSO during refueling operations?

a. Checking source range counts while a fuel assembly is being placed in the core.
b. Ensuring water level in 3 pent fuel pool is at least 23' above the fuel.
c. Maintaining a 1/M plot while reloading fuel during a core shuffle.
d. Monitoring the manipulator crane position by updating the Control Room tag board.

Page 3 of 50

R0cct::r Op: rater Excmination 9. An operator has the following exposure history this year until today:

Deep Dose Equivalent (DDE) 210 mrem Committed Effective Dose Equivalent (CEDE) 45 mrem Shallow Dose Equivalent (SDE) 33 mrem Committed Dose Equivalent (CDE) 28 mrem Today the operator was required to make two entries into containment:

Entry 1:

Gamma dose - 52 mrem; Neutron dose - 24 mrem Entry 2:

Gamma dose - 124 mrem How much radiation exposure is available to the operator if he has to make additional entries?

His available margin based on the routine Administrative Exposure Control Levels is...

a. 100 mrem for that day; 2484 mrem for the year,
b. 100 mrem for that day; 2545 mrem for the year.
c. 124 mrem for that day; 2569 mrem for the year.
d. 124 mrem for that day; 2614 mrem for the year.

10.The following conditions exist on Unit 1:

- Refueling operations in progress

- A HIGH alarm received on radiation monitor 1RE-AR012, Containment Fuel Handling incident When should the NSO initiate action and what action should he/she take from the control room? "

Indication of a fuel handling accident is considered when a...

a. report is received from personnel in containment. The operator starts the containment charcoal filter fans.
b. report is received from personnel in containment. The operator actuates Unit 1 CNMT evacuation alarm.

c corroborating rise is indicated on monitor 1RE-AR011. The operator starts the containment charcoal filter fans.

d. corroborating rise is indicated on monitor 1RE-AR011. The operator actuates Unit 1 CNMT evacuation alarm.

Page 4 of 50

Re:cter Op:: rater Examination i

11.The following conditions exist on Unit 1:

l

- A reactor trip has occurred and both reactor trip breakers are verified open

- The turbine has tripped

- BwEP-0 " Reactor Trip OR Safety injection" has been entered.

- BUS 141 ALIVE light is NOT lit with bus voltage at ZERO volts

- BUS 142 AllVE light is lit with bus voltage at 4149 volts.

Which of the following describes the actions the operators are required to take?

a. Continue with next step of BwEP-0.
b. Turn on the synchroscope and manually close ACB 1412, SAT 142-1 feed breaker,
c. Manually start 1 A DIG and verify ACB 1413, D/G output breaker, closes.
d. Initiate actions of BwOA ELEC-3 and continue with next step of BwEP-0.
12. From the list of procedures identified below, which has(have)" Transfer to Cold Leg Recirculation" on the Operator Action Summary Page?

(NOTE: The following procedures are in the E-1 or CA-1 series:

BwEP-1 " Loss Of Reactor Or Secondary Coolant" BwEP ES-1.1 "Si Termination" BwEP ES-1.2 " Post-LOCA Cooldown And Depressurization" BwEP ES-1.3 " Transfer To Cold Leg Recirculation" BwEP ES-1.4 " Transfer To Hot Leg Recirculation" BwCA-1.1 " Loss Of Emergency Coolant Recirculation" BwCA-1.2 "LOCA Outside Containment")

a. BwEP-1, BwEP ES-1.1 through ES-1.4, and BwCA-1.1 through BwCA-1.2 procedures.
b. BwEP-1, BwEP ES-1.1 and ES-1.2 procedures ONLY.
c. BwEP-1 and BwEP ES-1.2 procedures ONLY.
d. BwEP-1 procedure ONLY.

l l

Page 5 of 50

Rrcter Opsratcr Examinttien 13.The following conditions exist on Unit 1:

- Reactor trip breakers status - OPEN

- RCS Tave - 557'F

- Pzr pressure - 2235 psig Annunciator RCFC VIBRATION HI (1-3-C5) has been in alarm for the past 1 % shifts due to a faulty vibration probe. While maintenance troubleshoots the vibration probe on RCFC 1C which of the l

following actions is appropriate for this alarm window?

a. The alarm should be acknowledged for each actuation and the SER monitored for valid alarm inputs.

l

b. The alarm should be acknowledged for each actuation and operators stationed locally at each RCFC to monitor vibration.

I

c. The alarm should have been silenced without acknowledgement after obtaining Unit Operating Engineer's permission and the SER monitored for valid alarm inputs.
d. The alarm should have been silenced without acknowledgement with US permission and operators stationed locally at each RCFC to monitor vibration.

14. A feed pump trip occurred resulting in a rapid power reduction on Unit 1. Power was reduced from 100% steady-state conditions using a combination of rods and boration.

The following conditions exist for Unit 1 following stabilization:

- Reactor Power - 60%

- Delta-1 target value - +2.0

- Control Bank D position - 160 steps withdrawn 1

-Tave - 572*F

- Delta-l - -10.5%

- Core Age - MOL What actions will be required to maintain the current power level and maintain Delta-l within its

. normal operating band over the next FIVE hours?

a. Boration and control rod withdrawal, followed by dilution.
b. Boration and control rod insertion, followed by dilution.
c. Dilution and control rod withdrawal, followed by boration
d. Dilution and control rod insertion, followed by boration.

Page 6 of 50

R:actcr Op; rat::r Extmination

15. A problem with the rod control system requires checking several rod bank circuits. The affected power cabinet repairs are to be made by supplying power from the DC hold supply cabinet.

What is the capacity of the DC Hold Supply Cabinet under these circumstances?

a. ONE control rod bank group can be placed on DC HOLD, and these rods will drop ONLY if the controls are taken to OFF at the DC Hold cabinet.
b. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, 3

and these rods will drop ONLY if the controls are taken to OFF at the DC Hold cabinet.

c. ONE control rod bank group can be placed on DC HOLD, and these rods will automatically drop.
d. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, and these rods will automatically drop.

l 16.The following conditions exist for Unit 1:

- Mode 5

- RCS is draining to Pzr level of 40%

- IM calibrations have been completed for LT-RYO48, Refuel Cavity level, in preparation for further draining What is the relationship between Pzr level instrument LT-459, Pzr level instrument LT-462 and LI-RYO487 At approximately 40% level indicated on Ll-462, level on..

a. LI-459 and LI-RYO48 will be offscale high.
b. Ll-RYO48 will be just onscale and Ll-459 will be offscale low.
c. LI-459 will read higher than 40% and LI-RYO48 will just be onscale.
d. LI-RYO48 will be offscale high and Ll-459 will read lower than 40%

Page 7 of 50

R :ct:r Op:ratcr Excmination 17, The following conditions exist for Unit 1:

- Reactor power - 100%

- RCS activity is elevated, but below Technical Specification (CTS) levels

- Pzr pressure - 2225 psig

- Pzr level - 44%

- PORV 1RY456 - dualindication

- Leak rate - 6 gpm in an attempt to isolate the leakage past the PORV, the Block Valve 1 RY80008 was taken to close. The valve failed to close and the operator placed 1RY456 in the CLOSE position. When conditions stabilize:

- Reactor power - 100%

- Pzr pressure - 2228 psig

- Pzr level - 44%

How would the operator be able to tell if the PORV has closed?

a. Position lights for PCV-456 showing CLOSE indication ONLY.
b. PORV downstream temperature indication 1Tl463 dropping.
c. Level change in RCDT,
d. Lower readings for containment radiation monitors RE-001 I A/0012A.

Page 8 of 50

Rrctar Op rattr Examination 18.The following conditions exist on Unit 1:

- RCS Loop C is isolated for maintenance

- RCS Loop A had been isolated for maintenance

- RCS Loop A Hot Leg Stop Isolation Valve (LSIV) was opened at 1001

- RCS Loop A Bypass Stop Valve was opened at 1005 with reliefline flow of 115 gpm verified

- RCS Loop A Cold Leg LSIVis closed

- RCS temperature - 110*F

- RCS Hot Leg Loop temperatures - 108*F (A); 119'F (B); 110*F (C); 125'F (D)

- RCS Cold Leg Loop temperatures - 103*F (A); 108'F (B); 90*F (C);

115'F (D)

- S/G levels (Narrow Range) - 20% (A); 30% (B); 15% (C); 32% (D)

What will occur when the operator takes the control switch for MOV-RC8002A (RCS Loop A Cold Leg LSIV) to OPEN at 15097 The valve...

i

a. will travel fully open with NO automatic actuations.
b. will travel fully open, and the AFW pumps get a start signal.
c. remains closed because the temperature difference interlock remains active.
d. remains closed because the timer interlock is still active.

19.The following Unit 1 conditions exist:

- RCS temperature (Average CETC) - 140*F

- RCS pressure - 365 psig

- A bubble has just been drawn in the Pressurizer

- Allloops are filled and vented

- Preparations are in progress ta start the first RCP for continuous run What is the effect of selecting the 1C RCP to start?

a. Both Pzr Sprays will function normally for Pzr pressure control.
b. Manual cycling of the Pzr heaters will be required for Pzr pressure control.
c. PORV RY456 will open on high pressure from high pressure bistable PB456E.
d. Normal Pzr spray will deliver minimal spray flow for Pzr pressure control.

Page 9 of 50

R:act:r Op;ratcr Excmination 20.The following conditions exist on Unit 1:

- Reactor power 26%

- Pzr pressure - 2235 psig

- Pzr level - 35%

RCP 1 A breaker trips due to sensed undervoltage from bus 157. What is expected as a result of the trip of the RCP7

a. The reactor will trip due to the open RCP breaker.
b. The reactor will trip due to RCS loop low flow condition.
c. The reactor will be manually tripped by the operator,
d. A normal plant shutdown will be initiated.

21.The following conditions exist on Unit 1:

- Reactor power - 100%

- PZR pressure - 2235 psig

- PZR level - 44% stable

- CV121 - In MANUAL

- CVCS letdown - Isolated due to leak in Letdown Hx

- CVCS Excess Letdown - In service with maximum flow of 20 gpm

- RCP sealinjection - 1 A CV pump aligned to all RCPs

- RCP seal leakoff flow - 3 gpm (1 A); 3.5 gpm (18); 3 gpm (1C); 2.5 gpm (1D)

What flow is indicated on Charging Header Flow indicator, F1-1217

a. 5 gpm
b. 25 gpm
c. 32 gpm
d. 65 gpm Page 10 of 50

R:actar Op3ratcr Examination

~ 22.The following conditions exist on Unit 2:

- Unit is in MODE 5

- Unit burnup is 5700 EFPH in Cycle 7

- SDM - 1.3% DeltaK/K

- RCS pressure - 400 psig

- RCS average temperature - 195'F

- RCS boron concentration - 1006 ppm

_ Differential boron worth - -10.75 pcm/ ppm

- PZR level - 32.3%

- SR NIS countrate - 10 cps, BOTH channels stable background levels

- An inadvertent dilution at 70 gpm begins at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> Assuming NO operator action is taken and PZR level remains constant over the time period, when would the HIGH FLUX AT SHUTDOWN alarm actuate?

a. Never, because BDPS will actuate prior to actuation.
b. 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.
c. 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />.
d. 1734 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.59787e-4 months <br />.

23.The following conditions exist on Unit 1:

- Reactor power was 95% prior to the event

- A turbine runback resulted in rod insertion with control rods in AUTOMATIC

- Annunciator ROD BANK LO-2 INSERTION LIMIT (1-10-A6) is lit The operators initiated an emergency boration per BwOA PRl-2 " Emergency Boration" and have verified control rods are now withdrawing. Why does the operator energize the Pzr Backup Heaters?

This action..

a. ensures Pzr boron concentration equalization with RCS by increasing normal spray flow.

b, counteracts RCS cooldown due the boration by the additional heat from the backup heaters.

c. prevents loss of Pzr level by increasing the volume of fluid maintained in the Pzr.
d. guarantees adequate subcooling margin is maintained by raising the saturation temperature of the Pzr.

Page 11 of 50

R:::ctnr Op rat:r Eximin tion 24.The following conditions exist on Unit 1:

- A LOCA has occurred

- Actions of 1BwEP ES-1.3, ' Transfer To Cold Leg Recirculation, have been completed.

- During alignment,1CV8804A, RH HX to CENT CHG Pumps isolation Valve, failed to open and could NOT be manually opened.

What is the status of the ECCS system?

a. The RHR discharge headers are cross-tied with only RHR Pump 1B running and supplying suction to the Si pumps and Centrifugal Charging pumps from the B train connection.
b. The RHR discharge headers are cross-tied v'ith both RHR pumps running and supplying suction to the Si pumps only from the B train connection. The Centrifugal Charging pumps are stopped.
c. RHR Pump 18 is discharging through the B Train cold leg injection headers and supplying suction to the Sl Pumps. RHR Pump 1 A and the Centrifugal Charging pumps are stopped.
d. RHR Pump 18 is discharging through the B Train cold leg injection headers and supplying suction to the SI pumps and Centrifugal Charging pumps. RHR Pump 1 A is discharging thrtugh the A Train cold leg injection headers.

Page 12 of 50

R:actar Op: rat 3r Excmin tien 25.The following conditions exist on Unit 1:

- Unit is in MODE 4 during cooldown per 1 BwGP 100-5 following unit shutdown 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> ago

- RCS temperature - 340*F

- RCS pressure - 345 psig

- PZR level - 33%

- RHR pump 1 A is operating in Shutdown Cooling mode

- RH-618 A Hx Bypass Flow Control Valve is in MAN at 3000 gpm

- RH-606 A HX Flow Control Valve controller demand is at 20%

- CV-128 RHR Ltdn Flow Contr Valve demand is at 100%

- PCV-131 is in AUTOMATIC set to maintain 350 psig A signal failure from the controller causes RH-606 to go fully closed. What is the system response to this failure WITHOUT operator action?

a. PCV-131 will throttle open due to lower RH discharge pressure,
b. RCS pressure willincrease due to RCS heatup.
c. Pressurizer level will decrease due to increased letdown flow.
d. RH-610 will throttle open due to lower RH flow.

Page 13 of 50

l RS ct::r Op3 rat:::r Examinition 26.The following conditions exist on Unit 1:

- A plant heatup is underway

- MODE 3 has just been entered l

- RCS pressure 450 psig l

SI Accumulator 1C was drained below required level during the outage for repair work. System configuration has NOT allowed refilling the Accumulator until now. The SI Accumulator line is being flushed in accordance with BwOP SI-14 "Si Accumulator Fill Line Flush"(Valve lineup includes: 1SI-8964, Si Test Lines to Radwaste Isolation Valve, and SI-8888, S1 Pps to Accumulator Fill Valve, are open.1SI 8821 A, SI Pump to Cold Leg Isolation Valve, and 181 8802A, Si to Hot Leg 1 A & 1D isol valve are closed). Si pump 1 A running. During the flushing, an inadvertent SI signalis generated.

What is the status of the ECCS based on the current alignment WITHOUT operator action?

a. 1B SI pump ONLY is running with injection flow to the RCS cold legs and to the Accumulator 1C fill !ine flush.

' b. 1 A Si pump ONLY is running with flow directed to the Accumulator fill line flush ONLY.

c. BOTH Si pumps are running with injection flow to the RCS cold legs and to the Accumulator 1C fill line flush.
d. BOTH Si pumps are running with flow directed to the Accumulator 1C fill line flush ONLY.

27.To meet the 10CFR50.46 criteria, the ECCS System is designed such that under accident conditions it will maintain..

a. total hydrogen production from zirconium-water reaction below maximum value of 5%.
b. maximum fuel temperature at the inside surface of the cladding less than 2000'F.
c. the core at least 5% shutdown to prevent an inadvertent return to criticality.
d. fuel clad oxidation less than 17% of total clad thickness anywhere within the core.

l l

Page 14 of 50

R:cctor Op:ratar Extmination 28.The following conditions exist on' Unit 1:

- A LOCA has occurred

- Transfer to Cold Leg recirculation is required

- RCS pressure is approximately 50 psig

)

What is the approximate total SI pump flow indicated on the main control board and how will this value change following transfer of BOTH trains of ECCS to cold leg recirculation?

Total Flow Flow Change i

a. 650 gpm Decrease i
b. 800 gpm increase
c. 1050 gpm Decrease
d. 1300 gpm increase

)

t i

l Page 15 of 50 i

i

l RIctor Op3ratcr Ex min tion 29. During shift tumover for Unit 1, the NSO notes the following parameters:

i-RCS Tave - 566.5*F Pzr pressure - 2235 psig Pzrlevel - 38.3%

i PRT pressure - 4 psig PRT ievel - 74%

l PRTtemperature - 98'F One hour later when annunciator 1-12-A7, PRT LEVEL HIGH LOW alarmed, the NSO notes the i

i following parameters:

RCS Tave - 566.2*F Pzr pressure - 2233 psig Pzrlevel - 38%

PRT pressure - 5.9 psig PRTlevel - 81%

PRT temperature - 96*F What condition resulted in the change in parameters?

a. PRT PW Supply inside Cnmt isol Valve RY-8030 opened.
b. PRT to GW Comp Isol Valve RY-469 failed closed.
c. CVCS letdown relief valve CV-8117 lifted.
d. PORV RY-455A opened and reclosed.
30. Unit 1 is operating at 100% power in MOL conditions. All systems are functioning normally with rod controlin manual.

What is the effect on plant operations if instrument air supplied to the CVCS letdown Hx component cooling water outlet valve, CV-130 is lost?

TCV-130 goes fully...

a. shut and reactor power decreases due to boration in the CVCS demineralizers.
b. shut and the CVCS demineralizers are automatically bypassed on temperature signal.
c. open and reactor power increases due to deboration in the CVCS demineralizers.
d. open and the CVCS demineralizers are automatically bypassed on temperature signal.

Page 16 of 50

_.. ~. _

Reactar Op:ratcr Examination 31.What are the parameters and values used by the operator to ensure the temperature difference between the PZR and the spray fluid are within the specified limit (s) in the PRESSURE AND TEMPERATURE LIMIT REPORT when initiating PZR spray?

a. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor space temperature limit is 50*F, and for aux spray, the difference between Regenerative Hx charging inlet temperature and PZR vapor space limit is 320*F.
b. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 50'F, and for aux spray, the difference between Regenerative Hx i

l charging outlet temperature and PZR vapor space limit is 320*F.

c. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor space temperature limit is 320*F, and for aux spray, the difference between Regenerative l

Hx charging inlet temperature and PZR vapor space limit is 320*F.

1

d. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 320*F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is 320*F.

32.The following conditions exist on Unit 1:

- A load reject from 100% power has occurred

- Reactor power - 80%

- Pzr level - 56%

- Pzr vapor temperature - 655'F

- Pzr liquid temperature - 653*F

- RCS Tave - 578'F What is the current status of the Pressurizer based on given conditions?

a. Backup and proportional heaters are fully on.
b. Proportional heaters are modulated on.
c. Pzr spray valves have modulated open.
d. Pzr spray valves and Pzr PORVs are open.

i 1

Page 17 of 50 i

I

R cct r Opgrat:r Ex::minati n 33.The following conditions exist on Unit 1 with all controls in normal lineup:

- Reactor power - 30% stable

- RCS Tave - 564.5*F

- Pzr pressure - 2230 psig

- Pzr level - 36%

The pressurizer level controller 1LK-459 output fails low. What automatic actions result assuming NO operator action taken?

a. The reactor will trip on high pressurizer level ONLY.
b. Letdown will isolate on low pressurizer level and then the reactor will trip on high pressurizer 1

level.

c. The reactor will trip on high pressurizer pressure ONLY.
d. Letdown will isolate on low pressurizer level and then the reactor will trip on RCS low pressure.

34.The following conditions exist on Unit 1:

- Mode 3 NOT NOP with reactor trip breakers (RTA and RTB) closed

- Testing of reactor trip bypass breakers underway

- Reactor bypass breaker B (BYB) is racked in and closed

- An operator begins to perform test with reactor bypass breaker A (BYA).

What occurs as the operator operates the breaker BYA7 When reactor bypass breaker BYA is...

a. locally closed, ONLY breaker BYB will trip.
b. racked in to the CONNECT position, ONLY breaker BYB will trip,
c. locally closed, all reactor trip and bypass breakers will trip.
d. is racked in to the CONNECT position, all reactor trip and bypass breakers will trip Page 18 of 50 1

R%ct:r Op:ratcr Excmination 35. The following conditions exist on Unit 2:

- Unit shutdown is in progress

- Reactor power - 20%

- RCS Tave - 562*F

- Pzr pressure -2235 psig

- Pzr level - 32%

- First stage turbine pressure channel PT-506 fails high What affect does this failure have on operations as unit shutdown is continued, if NO action is taken for the failure?.

a. At 10% power, the reactor will trip if the Source Range Block RESET pushbuttons are depressed.
b. At 9% power, the reactor will trip if an RCP trips.
c.. At 7% power, the reactor will trip if the TURBINE TRIP pushbuttons are depressed.
d. At 5% power, the reactor will be manually tripped as during a normal shutdown by BwGP 100-5.

j

. 36.The following conditions exist on Unit 1:

- Power range NIS reading - 100%

- Tcold - 553*F

- Thot - 608'F

- RCS total flow - 372,000 gpm

- Pzr pressure -2215 psig

- Pzr level - 69%

How does the setpoint for Over Temperature Delta-T (OTdT) change when a listed parameter is changed? (Consider each change individually)

The setpoint...

a. increases if Power range NIS output rises to 102%.
b. increases if total reactor flow decreases to 370,000 gpm.
c. decreases if pressurizer pressure increases to 2235 psig.

j

d. decreases if the Thot rises to 612*F.

F Page 19 of 50 l

Reacter Op: rat::r Examination 37.The following conditions exist on Unit 1:

- Mode 3 with unit cooldown in progress

- RCS temperature - 520*F

- Pzr pressure - 1750 psig

- Pzr level - 33%

- MSIVs open What would directly happen if the operator were to take CONTAINMENT SPRAY & PHASE B ISOL switches for both trains to the ACTUATE position?

a. NO ESF actuations would occur.
b. Containment Phase B isolation and Containment Ventilation isolation ONLY would be actuated.
c. Containment Phase B isolation and Containment Ventilation isolation, and Containment Spray ONLY would be actuated.
d. Containment Phase B isolation and Containment Ventilation isolation, Containment Spray, and Main Steamline isolation would be actuated.

38.The following conditions exist on Unit 2:

- RCS temperature - 340'F

- RCS pressure - 900 psig

- All MSIVs for the S/Gs are closed

- The MSIV Bypass valves are open

- The FW-035s, Feedwater Tempering Isolation Valves, are open

- The FW-034s, Feedwater Tempering Flow Control Valves, are closed (opened periodically for level control)

- Feedwater pump N is reset and latched on turning gear

- The Start Up Fesdwater pump is running The level in the S/G 2B rises to 90%. How is the plant affected?

a. No actuation occurs because of the position of the MSIVs.
b. The 2C Feedwater pump and Start Up Feedwater pump trip.
c. The 2C Feedwater pump trips and FW-035 valves close.

d.' The 2C Feedwater pump and Start Up Feedwater pump trip, the FW-035 valves close, and the MSIV Bypass valves close.

4 l

Page 20 of 50

l, I

l R:cctar Op:ratar Extminction l

39. During a reactor startup, when does the ROD AT BOTTOM alarm become active for each control bank?

The alarm will actuate for a dropped rod for...

a. any Control Bank whenever Control Bank A DRPI output is above 9 steps.
b. each Control Bank whenever that Control Bank demand position is above 3 steps.
c. each Control Bank whenever that Control Bank DRPI output is above 9 steps.

I

d. Control Banks A, B and C whenever their Control Bank demand position is above 9 steps, j

l and for Control Bank D whenever Control Bank D demand position is above 3 steps.

i 1

40.How would the failure of the pulse height discriminator to a low value affect the indication of the affected Source Range channel?

The output would...

a. decrease due to electronic filtering which narrows the pulse height window.
b. decrease due to failure in counting the higher amplitude neutron generated pulses.
c. increase due to counting of the gamma generated pulses ONLY.
d. increase due to counting of the gamma generated pulses and decay alpha generated pulses.

Page 21 of 50

Rnctar Op; rat:r Exrmination l

41.The following conditions exist on Unit 1:

l

- RCS at NOT NOP

- Reactor trip breakers - closed

- Source Range readings:

N31 - 18 cps N32 - 22 cps i

What indication would the operator observe if Control Power was lost to the N31 Drawer?

I The N31 meter would read..

3

a. downscale, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.
b. downscale, the associated drawer bistable lamps lit, and reactor trip breakers open.
c. 18 cps, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.
d. 18 cps, the associated drawer bistable lamps lit, and reactor trip breakers open.

Page 22 of 50

Rzct:r Op; rater Examiniti::n 42.The following conditions exist on Unit 1:

- A reactor startup is about to be performed

- All shutdown banks are 'ully withdrawn

- All control banks are ful!y inserted

- An ECC records the following:

Predicted Critical Position (ECP) - 130 steps on CBD Max rod position - 231 steps on CBD l

Min rod position - 58 steps on CBD The following parameters were recorded during the rod withdrawal:

ROD HEIGTH N31 cps N32 cps O on CBA 25 23 178 on CBA 34 31 178 on CBB 58 62 178 on CBC 116 106 80 on CBD 200 182 92 on CBD 237 225 When was the first time the operator was required to determine the Predicted Crit l cal Position?

a. At 50 steps on CBA, with N32 as the designated Source Range detector.
b. At 113 steps on CBC, with N31 as the designated Source Range Detector.
c. At 80 steps on CBD, with N31 as the designated Source Range detector.
d. At 92 steps on CBD, with N32 as the designated Source Range detector.

Page 23 of 50

l Rrctar Op:ratcr Examinttion 43.The following conditions exist on Unit 1:

- Reactor power - 50%

i

- RCS Tave - 570*F (A); 569'F (B); 569'F (C); 570'F (D)

- RCS Thot - 585'F (A); 584*F (B); 583*F (C); 585'F (D)

- RCS Tcold - 555'F (A) 554*F (B); 555'F (C); 555'F (D)

- Pzr pressure - 2235 psig

- Pr level - 43 %

i l

If loop B Thot output channel fails LOW, what is the response of Pzr level ?

i Pressurizer level will.,

a. increases to 60%.
b. remains the same.
c. decreases to 25%.
d. decreases to the letdown isolation setpoint.

44 With Unit 1 at 100% power and with normal operating parameters, how would the failure of the HOTTEST Core Exit Thermocouple affect the reading of subcooling margin on the SPDS Iconics (CETC/SMM display) for each of the two situations below-Situation 1 - The CETC output fails high slowly Situation 2 - The CETC output fails low slowly

a. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and return to normal when CETC output reaches 2300*F.

Situation 2: Subcooling margin will increase, then stabilizes when the CETC output is smaller than TEN other TCs.

b. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and return to normal when CETC output reaches 1200*F.

Situation 2: Subcooling margin will remain constant.

c. Situation 1: Subcooling margin will increase to saturation then rise in superheat, and return to normal when CETC output reaches 1200*F.

Situation 2: Subcooling margin will decrease, then stabilizes when the CETC output is smaller than TEN other TCs.

d. Situation 1: Subcooling margin will Inctease to saturation then rise in superheat, and return to normal when TC output reaches 2300*F.

Situation 2: Subcooling margin will remain constant.

l Page 24 of 50

l l~

Rtactor Op::ratcr Examination 45.The following conditions exist on Unit 2:

L

- RCS Temperature - 342*F p

- Pzr pressure - 375 psig I

- 2A,28, and 2D RCFCs are operating in high speed l

- Unit 2 RCFC Dry Bulb temperatures are recorded as follows:.

l

- 2A RCFC - 119'F

-2B RCFC - 118'F

-2C RCFC - 127'F

-2D RCFC - 121*F Which of the following identifies the equipment status and actions for the above conditions?

What are the MINIMUM requirements for operation for the Reactor Containment Fan Coolers (RCFCs)?

l

. a. An additional RCFC must be started because the average of ALL the RCFC temperatures exceeds the limit.

b. An additional RCFC must be started because ONE of the operating RCFCs temperatures is above the limit.
c. NO action is necessary because ALL temperatures are within their appropriate limit.
d. NO action is necessary because the average temperature of ALL operating RCFCs is below the limit.

i i

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l Page 25 of 50

R: actor Operater Examination

' 46.The following conditions exist on Unit 1:

- A LOCA has occurred

- Transition has been made to BwEP ES-1.3 " Transfer To Cold Leg Recirculation"

- Containment Spray actuated due to high containment pressure

- All systems and components operating as expected What conditions allow for termination of Containment Spray?

a. ONE pump is stopped when containment pressure is less than 15 psig. The other pump is

{

i stopped when RWST LO-3 level is reached.

)

' b.' ONE pump is stopped when containment pressure is less than 20 psig. The other pump is stopped after it has operated for a period of at least TWO hours

c. BOTH pumps are stopped when containment pressure is less than 15 psig and have operated for a period of at least TWO hours,
d. BOTH pumps are stopped when containment pressure is less than 20 psig and RWST LO-3 level is reached.

47.The following conditions exist on Unit 1:

- LOCA is in progress

- Containment pressure - 15 psig

- Containment Spray actuated due to high containment pressure

- Containment Spray signal has been reset

- The actions of BwEP ES-1.3 " Transfer To Cold Leg Recirculation" have been completed

- Offsite power is then lost and the D/G output breakers have just closed onto ESF buses How are the Containment Spray Pumps re-started?

a. The pumps will auto start 15 seconds following closure of the D/G output breakers.
b. The pumps will auto start 40 seconds following closure of the D/G output breakers.
c. If the operator immediately places the CS & PHASE B ISOL switches for both trains to ACTUATE, the pumps will auto start 15 seconds following closure of the D/G output breakers.
d. If the operator immediately places the PP 1_ TEST switches for both pumps in TEST, the pumps will auto start 40 seconds following closure of the D/G output breakers.

Page 26 of 50 A

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Rtcctor Optratcr Examination 46. Annunciator 0-33-C3, FILTER 1VP05FA TEMPERATURE HIGH, alarms in the Control Room while 1VP02CA CNMT Charcoal Filter Fan is operating. The alarm condition is verified locally.

Which of the following describes the actions taken and/or the system response for the Containment Ventilation System?

a. The deluge valve FP244A will automatically open and the fan will automatically stop.
b. The control room operator will open the deluge valve FP244A and the local operator will then stop the fan.

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c. The local operator will open the deluge valve FP244A and the fan will automatically stop.
d. The local operator will open the deluge valve FP244A and the control room operator will then stop the fan.

49.The following conditions exist:

l 1

- Unit 1 - 20% power with load increase in progress l

- Unit 2 - MODE 5 following refueling outage

- Unit 2 Spent Fuel Pool Cooling Loop is in service.

- Spent Fuel Pool Pump 1FC01P is OOS.

Which of the following is allowed under this situation?

Alignment and operation of...

a. both Unit 1 RWST purification and Unit 2 RWST purification with flow through the Unit 2 Spent Fuel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.
b. Spent Fuel Pool purification and Unit 1 RWST purification with flow through the Unit 1 Spent Fuel Pool Demineralizer and Unit 1 Spent Fuel Pool Filter.

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c. Unit 2 RWST purification with flow through the Unit 1 Spent Fuel Poo! Filter ONLY.
d. Unit 2 RWST purification with flow through the Unit 2 Spent i uel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.

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Page 27 of 50

R:act2r Op ratar Examintti::n 50.The following conditions exist on Unit 1:

- Reactor power was 65% when the turbine tripped

- An ATWS occurred

- The reactor tripped 15 seconds later when B reactor trip breaker was locally opened

- Reactor trip breaker A is failed closed

- RCS Tave - 559'F

- Pzr pressure - 2255 psig

- Steamline header pressure - 1100 psig

- No controls other than control rods and boration controls have been operated What is the status of the Steam Dump valves?

Steam Dun ps are..

a. modulated open due to steam header pressure.
b. modulated open due to Tave above no-load Tave.
c. closed because Tave is NOT greater than 3*F above Tref.
d. closed because the dumps are NOT armed.

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1 Rrct::r Operatcr Examinati::n 51.The following conditions exist on Unit 1:

- Reactor power 28%

- All systems normal

- Turbine EHC Panel settings:

Turbine REFERENCE DEMAND -580 MW Turbine REFERENCE - 330 MW

- The GO pushbutton is LIT i

What would be the DEHC System response to a slow failure to ZERO for the turbine impulse pressure channel that feeds into the DEHC7 Turbine load will...

a. decrease until the difference between REFERENCE and impulse pressure exceeds 30%,

the operator would then be alerted to select MANUAL control.

b. decrease until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%, then load will stabilize in MANUAL control.
c. increase until the difference between REFERENCE and impulse pressure exceeds 30%,

i then load will stabilize in MANUAL control.

d. increase until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%, the operator would then be alerted to select MANUAL control.

52.The following conditions exist on Unit 1:

- Reactor power 35%

- All systems normal What failure would cause a decrease in feedwater flow to all S/Gs?

a. ONE condenser steam dump ONLY fails open.
b. Main steamline pressure PT-507 fails low.
c. ONE HD pump flow control valve ONLY fails open.
d. Main feedwater header pressure PT-508 fails low.

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- Rc:ct:!r Oparater Examinttien 53.The following conditions exist on Unit 1:

- Reactor power 100%

- All systems normal

- FT-512 selected for steam flow input into SGWLC for S/G 1 A What is the initial effect of the pressure transmitter associated with FT-512 failing low?

a. S/G 1 A level will decrease and feed pump speed will decrease.
b. S/G 1 A level will decrease ONLY.
c. S/G 1 A level will increase and feed pump speed will increase,
d. S/G1 A level will increase ONLY.

54.The following conditions exist on Unit 1:

-The reactor tripped from 40% power

- The trip was caused by RCS loop 1C low flow condition due to undervoltage for RCP 1C bus

- Power Range NIS channel N42 failed at 100% on the trip

- ESF bus 141 undervoltage occurred

- 1 A D/G automatically started and ACB 1413 is closed

- S/G levels lowest readings were - 19% (A); 25% (B); 22% (C); 20% (D)

What is the status of the Auxiliary Feedwater (AF) Pumps on Unit 1 for these conditions at ONE minute following the trip?

a. Both AF pumps are running.
b. ONLY the 1 A AF pump is running
c. ONLY the 1B AF pump is running.
d. Neither AF Pump is running Page 30 of 50

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R cct2r Op:;rct:r Examinati:n 55. W hich of the following describes the designed MINIMUM AFW pump and S/G configuration necessary to remove all of the reactor decay heat load following a reactor trip from 102% power?

. a. The 1 A AF pump supplying 500 gpm to at least ONE S/G with S/G blowdown manually isolated.

l b.' The 18 AF pump supplying 740 gpm to at least ONE S/G with S/G blowdown in service

c. The 1 A and 1B AF pump supplying 500 gpm total flow to at least TWO S/Gs with S/G blowdown in service.
d. The 1 A and 18 AF pump supplying 740 gpm total flow to at least TWO S/Gs with S/G blowdown manually isolated.

56.The following conditions exist on Unit 1:

- Reactor power - 100%

investigation has located a ground on the 125 VDC Normal supply to the 1 A D/G from DC 111.

What action is required to transfer DC Control Power to the reserve source?

The Reserve power breaker from...

a. DC 111 will be closed after opening the Normal power breaker and the Reserve power breaker at the D/G control panel.
b. DC 111 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks at the D/G control panel.

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c. DC 112 will be closed after opening the Normal power breaker and the Reserve power breaker at the D/G control panel.
d. DC 112 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks at the D/G control panel.

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Page 31 of 50

React:r Op3ratcr Extmination 57. Unit 1 was being synchronized to the grid when the following occurred:

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- Trip of 345 KV breakers resulted in deenergizing the SATs

- A steamline break occurred that resulted in containment pressure reaching 20 psig 20 seconds after the D/Gs output breakers have closed When would the 1 A SX pump re-start?

a. Always following start of the 1A CS Pump.

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b. Between the start of the 1 A CV pump and the 1 A RH pump on the SDRA contacts (UV).
c. Between the start of 1 A CC Pump and the 1 A AF Pump on the SARA contacts (SI).
d. Coincident with the starting of the 1 A and 1C RCFCs.

58.The following conditions exist on Unit 1:

- Unit is in MODE 3

- A cooldown had just been initiated

- Steam Dump Bypass Interlock control switches have just been taken to BYPASS

- No other operator actions have been performed

- The Steam Dump valves fail open and the following parameters are observed:

- RCS temperature - 537'F (A); 539'F (B); 538'F (C); 538'F (D)

- Pzr pressure - 1820 psig

- Pzr level - 10%

- S/G pressure - 850 psig (A); 740 psig (B); 800 psig (C); 715 psig (D)

- S/G flow - 1.0 Mlb/hr (A); 1.5 Mlb/hr (B); 1.1 Mlb/hr (C); 1.6 Mlb/hr(D) l

- The level in the RCDT has risen to the alarm setpoint (80%) for REACTOR COOLANT DRAIN TANK UNIT 1 LEVEL Hi-LO Assuming all systems are functioning correctly, what is the status of the RCDT system?

a. BOTH RCDT pumps are running and flow is directed to the Holdup Tanks.
b. BOTH RCDT pumps are running and flow is recirculated back to the RCDT.
c. ONE RCDT pump is running and flow is directed to the Holdup Tanks.
d. NEITHER RCDT pump is running and NO flow exists for the system.

Page 32 of 50

1 Rrctor Op::rator Examinttien 59. During at-power operations with systems in their normal alignment, what is a normal source of water to the Containment Floor Sump?

a. Output from the reactor cavity sump.
b. Leakoff from the #2 RCP seals,
c. Leakoff from the reactor vessel flange.
d. Valve packing leakage from the CVCS letdown isolation valves.

60.When aligned for normal operation (BwOP GW-1), how does the Waste Gas System respond to high pressure sensed at the in-service Gas Decay Tank?

An alarm is generated that...

a. alerts the operator to plaw an alternate Gas Decay Tank in service.
b. indicates auto swap of in-service Gas Decay Tank to selected backup Gas Decay Tank, and alerts the operator to align another standby Gas Decay Tank.
c. indicates auto swap of in-service Gas Decay Tank to selected standby Gas Decay Tank and auto swap of standby Gas Decay Tank to new standby Gas Decay Tank.
d. shuts down the Waste Gas Compressors and isolates the in-service Gas Decay Tank.
61. Area Radiation Monitor for Fuel Bldg Fuel Handling incident (ORE-AR055) is being manually Check Source tested. What is the response when the monitor's CHECK SOURCE (C/S) pushbutton is depressed at the RM-23 panel?
a. The alarm and automatic action output will be blocked, and the RM-23 amber INTLK LED will be lit.
b. The alarm and automatic action output will be blocked, and the RM-23 green AVAIL LED will-be lit.
c. The alarm will be actuate when value is reached, and the RM-23 amber INTLK LED will be lit.
d. The alarm will be actuate when value is reached, and the RM-23 red HIGH LED will be lit.

Page 33 of 50 l

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Ratcter Operatcr Examination

. 62.The following conditions exist on Unit 2:

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- Refueling operations are in progress While using the Fuel Handling Building Crane to move new fuel into the Spent Fuel Pool, the radiation monitor ORE-AR039, Fuel Handling Building Crane Monitor, goes into alarm. What action is affected?

a. Traverse of the Fuel Handing Building Crane bridge and trolley.
b. Both lowering and raising the Fuel Hanaing Building Crane hoist.

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c. Traverse of the Fuel Handing Building Crane trolley and raising the hoist.
d. Raising the Fuel Handing Building Crane hoist.

l 63.The following conditions exist on Unit 1:

- A unit startup is in progress with reactor power raised above 18%.

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. - Turbine is at 1800 rpm ready to be synchronized to grid.

- Motor driven feedwater pump is supplying the SIGs with Feed Reg Bypass valves in AUTO.

- Steam Dump demand in AUTO at 12%.

- Instrument air header pressure begins to slowly drop due to a leak j

If the leak CANNOT be isolated and instrument air pressure continues to drop, which of the l

following would occur?

. (Assume NO operator action taken.)

a. AF recirculation flow to the CST would be lost due to AF recirc failing closed.
b. Pressurizer level would increase due to 1CV121 failing open.
c. The main turbine would auto runback due to Diaphragm Interface Valve (DIV) opening.
d. RCS temperature would drop to 550*F due to steam dumps failing open.

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R actor Op:rcter Examination 64.With the fire protection systems in their normal alignment, what is the affect of a loss of DC power? -

i Loss of DC control power to the...

a. halon control cabinet will cause halon release in the OA Control Room HVAC Room.
b. battery control panel will cause automatic start of the diesel driven fire pump.
c. fire detection system will cause start of the motor driven fire pump.
d.. carbon dioxide system will cause the master discharge valve to fail open pressurizing the CO2 header.

65.The following conditions exist on Unit 1:

- Reactor power is 30%.

- Rod controlis in Automatic

- Tref - 564*F

- Tave values - 564*F (A); 565'F (B); 565'F (C); 564*F (D)

- Power Range NI-31% (N41); 29% (N42),30% (N43); 30% (N44)

- Control bank D is at 156 steps.

Which condition would result in continuous rod withdrawal?

a. Turbine first stage pressure PT-505 fails upscale.
b. Power Range channel N41 fails upscale.
c. Loop A Tcold fails downscale.
d. Tref signal fails downscale.

Page 35 of 50

R:actsr Operator ExEmination 66. A Control Bank D rod was dropped from 156 steps. The P-A converter was NOT zeroed when directed by the procedure.

l Select the effect of NOT performing this action?

ai While performing the procedure, the C-11 Rod Stop will be received prior to realigning the rod.

b. While performing the procedure, the Rod Insertion Limit Alarm will be received at a lower rod

- position than required.

c. After the procedure is complete, Bank C control rods will begin insertion at a lower value of l-Control Bank D.
d. After the procedure is complete, Bank C control rods will begin insertion at a higher value of l

Control Bank D.

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67.On Unit 1, a loss of all circulating water pumps has resulted in a reactor trip. All control systems respond as expected. Significant decay heat causes RCS temperature to increase following the trip.

. At what RCS temperature should temperature stabilize?

Temperature should stabilize at the saturation temperature for...

a. 1030 psig.
b. 1092 psig.
c. 1115 psig.

l d.' 1175 psig.

68. lf Unit 2 is operating at full load, which group of conditions will result in an automatic reactor trip either directly orindirectly?

a. RCP bus frequency (Hz):56.9 (Bus 156) 57.1(Bus 157) 56.9 (Bus 158) 57.2 (Bus 159) l-
b. Power range (%):

107 (N41) 108 (N42) 108 (N43) 109 (N44)

c. PZR pressure (psig): 2375 (PT-455) 2380 (PT-456) 2385 (PT-457) 2380 (PT-458)
d. S/G C NR level (%): 35 (LT-537) 38 (LT-538) 38 (LT-539) 37 (LT-558) l Page 36 of 50 I..

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R:acter Op ratSr Examination 69.With the RCS at normal operating pressure and temperature, what is the condition of the steam entering the PRT at normal conditions, if a PORV opens? (Assume an ideal thermodynamic process).

a. Superheated steam at 239'F.
b. Superheated steam at 222*F.
c. Saturated steam-water mixture at 239'F.
d. Saturated steam-water mixture at 222*F.

70 What are the parameters used to calculate Subcooling Margin in the SPDS leonics if only the 1C RCP and 1D RCP are running?

a. RCS wide range pressure from loop C hot leg and core exit thermocouple temperatures.
b. Pressurizer pressure and core exit thermocouple temperatures.
c. RCS wide range pressure from loop A and loop C hot leg, and RCS loop A and loop C hot leg temperatures.
d. Pressurizer pressure and RCS loop A hot leg temperature.

71.The following conditions exist during performance of BwEP-0.

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- Train A ECCS pumps failed to start.

- RCS pressure is 1350 psig.

- Containment pressure of 7 psig.

- Bus 142 has an overcurrent trip on the normal feeder breaker.

- Si actuated due to High Containment Pressure.

- The highest critical safety function is Yellow on Heat Sink.

- All other equipment and components operated as expected.

Based on the RCP Trip Criteria, the RCPs should...

a. NOT be stopped because NO Si pumps or Charging Pumps are running.
b. NOT be stopped because RCS pressure is above the trip setpoint.
c. be stopped because Si flow is established to the RCS.
d. be stopped because CC flowpath to the RCP motor oil coolers is isolated.

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l Rerct: rop ratarExamination l72.On a loss of seal injection to the RCPs, what criteria is used to determine if the RCPs should be tripped?

a. High temperatures on the RCP seal or bearing outlet temperatures.

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b. Time elapsed since loss of seal injection.
c. RCP Thermal Bearing Cooling Water low flow alarms.

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d. #1 seal leakoff flow rate decreases to zero.

73. Unit 1 is operating at 100% power when the following alarm is received:

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- RCP SEAL LEAKOFF FLOW LOW (1-7-C3)

The NSO investigates and reports the following additional information:

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- RCP 1 A seal injection flow is 10.7 gpm

- #1 Seal Leakoff Flow on 1 A RCP is 0.4 gpm l

- RCP 1 A Seal Water Outlet Temperature is 140*F and STABLE l

- RCP 1 A Bearing Outlet Temperature is 145'F and STABLE Based on the above information, which of the following events has occurred?

a. RCP 1 A #1 Seal has failed closed l
b. - RCP 1 A #1 Seal has failed open.

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c. RCP 1 A#2 Seal has failed closed.
d. RCP 1 A #2 Seal has failed open.

74.Given the following:

The plant is at 90% power with ALL controls in AUTO.

VCT level transmitter, LT-112, fails HIGH causing a letdown diversion.

l What will occur if NO operator action is taken?

i l-VCT level decreases...

a. until Auto makeup starts and maintains VCT level.
b. with NO auto makeup capability and charging suction shifts to RWST.

c faster than auto makeup input and charging suction shifts to RWST.

d. until charging pumps lose suction and start to cavitate.

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I React 2r Operater Examinttien 75. Given the following after a reactor trip:

- THREE rods remain withdrawn.

- Due to equipment malfunctions boration is only available from the RWST.

- Charging flow rate 132 gpm.

- RCS boron concentration was 1050 prior to the trip.

- 120 gpm letdown in service.

l Of the listed times, which would be minimum acceptable time that boration from the RWST would have to occur?

a.1 Hour

b. 2 Hours
c. 3 Hours
d. 4 Hours 76..The following conditions exist on Unit 1:

- The plant was shutdown 8% days ago to repair a steam generator tube leak.

- Reactor vessel level is at 397' 1" with Thot at 212'F.

- A loss of RHR pumps due to cavitation has occurred j

Which of the following is the smallest amount of flow that meets the minimum makeup flow required to maintain current RCS level?

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a. 80 gpm
b. 72 gpm
c. 59 gpm
d. 45 gpm i

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Page 39 of 50 I

Rrct:r Op:ratar Examinatinn

. 77.The following conditions exist on Unit 2:

MODE 5 operation during normal cooldown RCS temperature - 195* F RCS pressure - 325 psig Train A RH in service, train B RHR tagged out for repairs

- What is the preferred method of core cooling if a loss of RH cooling occurs?

' Altemate RCS cooling using...

a. bleed and feed using reactor head vents.
b. the SIGs.
c. normal charging and RHR letdown.
d. St Pump cold leg injection 78.The following conditions exist on Unit 1:

- The reactor is shutdown.

- RHR is in shutdown cooling.

- RCS temperature is 300'F.

- RCS pressure is 160 psig.

- CCW surge tank levelis decreasing What leak locations will produce these indications?

a. RHR Heat Exchanger
b. Thermal Bearing Heat Exchanger
c. Letdown Heat Exchanger
d. Seal Water Heat Exchanger Page 40 of 50

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R:act:r Optratur Extmin:tian 79.The following conditions exist on Unit 2:

t i

- Reactor power is 100%

- Pressurizer pressure control is in automatic.

What is th6 immediate response of the pressure control system if the Master Pressure Controller L

setpoint is inadvertently changed to 2330 psig (step change)?

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a. PORV RY455A cpens and spray valves open.

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b. PORV RY455A opens, spray valves open, and all heaters energize.

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. c. Spray valves open and proportional heaters go to minimum.

d. Spray valves close and proportional heaters go to maximum.

80.The following conditions exist on Unit 1:

- Reactor power is 100%

- All systems are in automatic

- Channel 1 Pressurizer Pressure Channel (PT-455) was declared inoperable and taken out of service with the appropriate bistables placed in the tripped condition.

- Controlling pressurizer pressure channel (PT-457) fails high

[

Assuming NO operator action, what is the plant response to the channel failure?

a. Both PORVs and both spray valves open resulting in a reactor trip from low pressurizer pressure followed by Si actuation.
b. The reactor will trip immediately on high pressure, and safety injection will actuate on low L

pressure due to spray valve operation.

c. Pressurizer proportional heaters will de-energize and spray valves will open resulting in an ~

OTdT runback prior to tripping, and safety injection will actuate due to low pressurizer pressure.

d. Both PORVs and both spray valves remain closed while pressurizer heaters de-energize.

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Page 41 of 50

R:act:r Operat:r Examinaticn 81.The plant is operating at 100% power with all control systems in AUTO. The following parameters are noted:

- Letdown Hx outlet flow (F1-132) - 75 gpm

- Charging Header flow (FI-121) - 87 gpm

- Total seal injection flow (FI-142 -Fi -45) - 33 gpm What is the effect on total seal injection flow initially if controlling Pzr level channel LT-459 fails j

LOW?

. Total seal injection flow will...

a. decrease to O gpm.
b. decrease to approximately 20 gpm.
c. remain approximately 33 gpm.
d. increase to greater than 40 gpm.

82.The following conditions exist on Unit 1:

- At t= 0 sec, Turbine load was decreased below 352 MW (30% power)

- At t=240 sec, The running main feedwater pump tripped.

The reactor did NOT trip due equipment malfunction.

- At t=250 sec, All feedflow indications decrease to 0% flow

- At t=320 sec, All steam generator levels decrease below 15%.

Based on this information, AMS would.

a. initiate at t=320 sec.
b. initiate at t=345 sec.
c. initiate at t=360 sec.
d. NOT initiate becau?e 0-20 is cleared.

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Page 42 of 50 5

R :ctar Op;ratcr Extminati::n 83.The following conditions exist on Unit 1:

- Reactor startup in progress

-Intermediate power range indication: 2.5E-5 amp N35 & 2.8E-5 amp N36 1

- SOURCE RANGE PERMISSIVE P-6 permissive light clear l

- SOURCE RANGE TRIP ACTIVE permissive light clear

- Source Range Channel N31 High voltage power supply fails to half its normal value What indication (s) would be available to alert the operator to this failure?

a. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate lower than expected.
b. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate higher than expected.
c. Annunciator SR HIGH VOLTAGE FAILURE (1-10-B1) will alarm when power exceeds P-10.
d. Annunciator SR HIGH VOL lE FAILURE (1-10-B1) will re-flash when the voltage source fails.

84.The following conditions exists on Unit 2:

- Plant shutdown is in progress.

- All power range channels indicate 6% reactor power.

- Intermediate range channel N-36 fails HIGH.

What is the plant response to this failure?

a. The reactor will trip on high IR flux, and source range trip will reinstate when N-35 decreases-below P-6.
b. The reactor will trip on high IR flux, and source range trip will NOT be reinstated.
c. The reactor will NOT trip immediately, but will trip when the source range trip is reinctated when N-35 decreases below P-6
d. The reactor wik NOT trip, and source range trip will NOT be reinstated.

Page 43 of 50

L Rrect::r Op: rater Examinctlan 85.The following conditions exist on Unit 1:

- Reactor power is 75%

- Troubleshooting has commenced due to reduced condenser vacuum with the air ejectors out of service.

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- Hogging vacuum pumps are aligned to the main condenser to aid in maintaining vacuum.

What would be an indication of a Steam Generator Tube Leak under these conditions?

a. Increasing radiation level on 1RE-PR027, "SJAE/ Gland Steam Exhaust Monitor".
b. Decreasing S/G lovel for ONE S/G.
c. Increasing feedwater flow to ONE S/G.
d. Decreasing charging header flow to RCS.

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86. BwEP-3 " Steam Generator Tube Rupture" is being performed in response to a tube rupture on 2C S/G. The cooldown has just been completed but the target temperature value selected by the operators was higher than that stipulated in the procedure.

What condition could result because of this error?

a. Loss of RCS subcooling before RCS and ruptured SIG pressures are equalized.
b. Increase in pressure of the ruptured S/G with resultant lifting of the SIG Safety Valve.
c. Increase in pressure of the non-ruptured S/Gs with resultant lifting of their S/G Safety Valves.
d. Filling the Pressurizer solid during the subsequent depressurization.

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Page 44 of 50

Rract::r Op;ratcr Examinaticn 87.The following conditions exist on Unit 1:

- The Unit was in MODE 3 at normal operating temperature and pressure prior to the event.

- A faulted steam generator has occurred.

- RCS hot leg temperatures - 547'F (A),544*F (B),545*F (C),547'F (D)

- RCS cold leg temperatures - 545'F (A), 530*F (B), 543*F (C), 545'F (D)

- S/G pressures - 700 psig (A),635 psig (B),690 psig (C), 705 psig (D)

- S/G flow - 0.85 MLB/hr (B)

- Containment pressure (Channel) - 8 psig (1), 7.5 psig (2), 7.5 psig (3), 8 psig (4)

Based on these conditions, a main steam line isolation should..

a. have occurred because of the low pressure in at least ONE S/G.

2

b. have occurred because the steamline high negative rate occurred in S/G 1P.
c. NOT have occurred because Containment pressure is belaw the setpoint for the CNMT High-2 pressure signal.
d. NOT have occurred because THREE S/Gs have pressures above the isolation setpoint and do NOT indicate high steam flow.

88.The following conditions exist on Unit 1 following a trip from 100% power:

- Pressurizer levelis 0%

- Pressurizer pressure is 1500 psig

- Containment Pressure is 16 psig.

- Tcold is 420*F for allloops.

Where is the location of the leak?

a. On one loop RCS cold leg.
b. On a Main Steam Line inside containment.
c. In a Steam Generator Tube.
d. On a feedwater line between FWRV and Associated FWlV,1FWOO9.

Page 45 of 50

l R act:r Op;rattr Examinatien i

89 iln accordance with BwOA SEC-3, " Loss of Condenser Vacuum", which of the following sets of conditions requires the operator to trip the reactor?

a. LOW POWER TRIP BLOCKED P-8 annunciator - LIT Turbine load - 200 MW Condenser pressure - 5.2 " HgA
b. LOW POWER TRIP BLOCKED P-8 annunciator-I.lT Turbine load - 300 MW Condenser pressure - G.3" HgA
c. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 600 MW Condenser pressure - 7.2" HgA
d. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 900 MW Condenser pressure - 7.8" HgA 90. Select the primary basis for rapidly depressurizing the steam generators during a Loss of All AC.
a. To provide maximum core cooling until power can be restored.
b. To minimize RCS inventory loss from RCP seals.
c. To enhance restoration of S/G level from the diesel dr'ven AF pump.
d. To increase subcooling of the RCS.
91. How would the sequencer operate if a Safety injection (SI) actuation occurs while the sequencer is sequencing loads in response to an ESF bus undervoltage condition?
a. There will be no change in operation; the undervoltage sequence overrides tha SI sequence.
b. The undervoltage sequencing stops, the sequencer immediately resets and SI loads NOT already running will sequentially start.
c. The undervoltage sequencing stops, all started loads are shed, and SI loads will sequentially start.
d. The undervoltage sequencing completes its cycle, then resets to SI mode, and Siloads NOT already running will sequentially start.

Page 46 of 50

RS ct::r Op::rcter Examination l

92.The following conditions exist on Unit 1:

i

- Bus 141 is powered from its normal source

- D/G 1 A surveillance is being performed with the D/G paralleled to the bus What would occur if a failure of the undervoltage relay results in a sensed undervoltage condition on Bus 1417

a. SAT feeder breaker ACB 1412 and D/G feeder breaker ACB 1413 remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.
b. SAT feeder breaker ACB 1912 and D/G feede> breaker ACB 1413 will open. After a 10-second delay, ACB 1413 will close and the Safe Shutdown loads will sequence.
c. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The Safe Shutdown loads will sequence normally.
d. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.

93. On Unit 1 power is lost to 120 VAC Instrument Bus 111 How are the ESF and Safe Shutdown loads affected?

a. "A" Train ESF loads will NOT load on an SI signal, but Safe Shutdown loads will load on a UN signal.

"B" Train loads are NOT affected.

b. A" Train ESF loads will load on an SI signal, but Safe Shutdown loads will NOT load on a UN signal.

"B" Train loads are NOT affected.

c.

"A" Train ESF loads will NOT load on an SI signal, and Safe Shutdown loads will NOT load on a UN signal.

"B" Train loads are NOT affected.

d. "A" Train AND "B" Train ESF loads will NOT load on an Si signal, but Safe Shutdown loads will load on a UN signal.

l Page 47 of 50 l

R actcr Op:ratur Examination 94. Select the method used for transferring controls to the remote shutdown panels PLO4/05J.

a. Placing applicable transfer switches in LOCAL on RSP.
b. Opening the isolation switches in the Auxiliary Electric Room.
c. Deenergizing normal control power to individual controls.
d. Taking local controls out of the PULL-TO-LOCK position.
95. When inadequate core cooling exists, which of the following sets of actions states the proper sequence of the major action categories to be performed in accordance with BwFR-C.1,

" RESPONSE TO INADEQUATE CORE COOLING", for removing decay heat from the core?

a. Reinitiation of safety injection; RCP restart; rapid secondary depressurization.
b. Reinitiation of safety injection; rapid secondary depressurization; RCP restart.
c. RCP restart; reinitiation of safety injection; rapid secondary depressurization.
d. RCP restart; rapid secondary depressurization; reinitiation of safety injection.

96. High coolant activity has been detected and chemistry has determined that it is due to corrosion product activation.

Identify the effect of placing the cation demineralizer in service.

The cation demineralizer...

a. tuill remove lithium so it should NOT be used in this condition.
b. will cause the activity level to decrease as soon as it is placed in service.
c. is NOT effective in removing corrosion product activity,
d. is less effective than the mixed bed demineralizer so it is placed in service ONLY if decontamination factor is less than 10.

Page 48 of 50

R:act:r Op;ratar Examin:.ti::n 97.The following conditions exist on Unit 1:

- Reactor power was 8% prior to the event below.

- A failure in the feedwater control system caused ONE S/G level to exceed P-14.

l

- The main turbine tripped.

- S/G levels have returned to their normal level range

-The Startup FW Pump is running What are all the conditions that would have to be met to feed the S/Gs using the FWO34's Feedwater Tempering Flow Control valves?

a. The FW lsolation Aux Relays would have to be reset and FWO35 Feedwater Tempering isol valves opened.
b. The reactor trip breakers would have to be cycled, the FW lsolation Aux Relays would have to be reset and FWO35 Feedwater Tempering isol valves opened.
c. The FW lsolation Main Relays and Aux Relays would have to be reset and FWO35 Feedwater Tempering Isol valves opened.
d. The reactor trip breakers would have to be cycled and FW lsolation Main Relays and Aux Relays reset and FWO35 Feedwater Tempering isol valves opened.

98.The following conditions exist on Unit 1:

- A leak developed on the RCS loop C flow instrument piping.

- Coincident with the RCS leak, on the reactor trip a S/G PORV failed open and was later isolated.

- FR-P.1 was entered to due to an ORANGE PATH condition.

- Si actuated and has been reset.

- All RCPs are stopped.

~

- Conditions required to support an RCP start are met.

What is the basis for operation of a RCP7 Under the current conditions starting the RCP will...

a. cause excessive thermal stresses in the stagnant loops.
b. cause a pressure surge that will aggravate the PTS condition.
c. provide mixing of the ECCS injection flow thereby decreasing the likelihood of PTS.
d. increase the RCS cooldown rate thereby increase the likelihood of PTS.

Page 49 of 50

R:act:r Operatar Examinatian l

99. Why is it important to run the CRDM vent fans when performing a natural circulation cooldown?

a. Aids the operator in maintaining subcooling in tha reactor vessel head.
b.. Aids in natu al circulation flow through the RCS head region.
c. Minimizes stresses on the reactor vessel head due to uneven cooldown.
d. Aids in natural circulation flow through the RCS.

100.Why are the S/Gs depressurized to less than 670 psig according to BwCA-1.1, " Loss of Emergency Coolant Recirculation"?

a. To allow maximum AFW flow to the S/Gs.
b. To ensure adequate subcooling for restart of the RCPs.
c. To set up conditions for controlled injection to the RCS from the accumulators.
d. To decrease RCS temperature and pressure which reduces break flow in a LOCA condition.

Page 50 of 50 i

A GENERIC FUNDAMENTALS EIRMINATION

  • i EOUATIONS AND CONVERSIONS 5ANDOUT BEBET DOUATIOms

= AC,4T

. P = P.10"

6 = idh P=Poe ' *" '

= UAAT A = A,e ^*

~

i h OC at Circ CR (1 - K.grz) = CR (1 - K.cgg) 2 at Circ 1/M = CR /CRx t

Kerr " 1/ (1 p)

DRW = (*t,/$,

2 e

p = (K rr - 1) /K.cr e

F = PA SUR = 26.06/r 6 = pAv r=8-p 4% = 44Pu A.cz #

E = IR-p=$+

Eff. = Net Work Out/ Energy In 1 + K'"f f

- P ) + (%* - %*) + g(zz - z2) = 0 p(P 2

L = 1 x 10 seconds 2g, g,

Aerr = 0.1 seconds"*

g, = 32.2-lbm-ft/lbf-sec*

CONVERSIONS 3.41 x 10' Btu /hr 1 Curia 3.7 x 10** dps 1 Mw

=

=

2.54 x 10' Btu /.hr 1 kg 1 hp 2.21 lba

=

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1 Btu =

778 ft-lbf 1 gal s.,=

8.35 lba

~

(5/9) (*F - 32) 1 f t'ot,

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Page 1 of 1 '

1 i

KI.T Pi E USE l8 BORON DILUTION RATE NOM 0 GRAPH

~

1 1

TEMP (*F)

Milba)

POWER 509,342 l

2MO 525 531,756 l

500' 546,347 400.

596,763 l

' 300 300 636,314 I

200

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1000

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M= TOTAL SYSTEM MASS t.

APPROVED 10 7984P(080587)18 NOV 271987 A

BRAgW gDw

REV. 53 LOSS OF CONDENSER VACUUN 1Bw0A UNIT 1-SEC-3 4

4 j

s

.I i

j i

C 10 0

N D

E "8 NOT N

ACCEPTABLE SE 8 c

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N 1

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9 A 0 i

0 100 200 300 400

.500 600 700' 800 900 1000 1100 1200 NEGAWATTS I

APPROVED FIGURE 1Bw0A SEC-3-1 APR'211994 i

TURBINE LOAD -vs-CONDENSER PRESSURE BRAgDWOOD i

ON.styg agyggw i

i Page 9 of 9

. ~. _

. _ - =. -. -..

l 4 a e

t REV.57 LOSS RH COOUNG UNIT - 1 1BwOA PRI-10

\\

1 i

l MAKEUP 120.0

/ l

\\

110.0 mas i-w 4 =

ss 1s2 s =

100.0 I

12 2ss

=

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=

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=

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~800.0 300.0 400.0 50.0 000.0 700.0 000.0 900.0

'0.0

.100.0 TDE AFTER Bb10504 9951 a.

FIGURE 1BwOA PRI 10 3 Minimum PAakeup Flow Required to Match Boiloff

)

APPROVED.

(11/21/96)

Page 11 of 62 NOV 261996 BRAIDWOOD en stic arvirW

l REV?.-1D REACTOR TRIP RESPONSE

'18:EP

. WOG 1B

_ UNIT 1

.ES-0.1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED VERI

' ALL' CONTROL RODS FULLY Perform the following:

5 I (SE t"ED:

a. IE two or, more rods are All rod bottom lights - Iitt 3Q1 fully inserted, e

IEEt[. innergency borate 1200. GAL (3600 GAL FRW RMST) for~each rod HQI fully inserted per I

1BwCA PRI-2, EMERGENCY

,.SORATION.,.,.f z

0' 9.

  • b. Within 1 HOUR calculate 1

Shutdown. Margin..oer I!. -

1BwOS 1.1.1.1.e-1, ew ad

. SHUTDOWN K--

'TW j

.VERIFICATIch DURING

~ SHUTDOWN (1BwOSR 3.1.1.1).

.~

l APPRQVED UUN 101998 BHAIDWOOD ON SITE Review Page 7 of 27

l J

Rocct:r Oper;t:r Ap3w r Ksy 1.d 26.c 2.c 27.d 3.c 28.d 4.a 29.a 5.c 30.c 6.a 31.d 7.b 32.c 8'.a 33.b 9.b 34.c j

10.d 35.d 11.d 36.d 12.b 37.c 13.c 38.c 14.a 39.c 15.c 40.d 16.c

41. d 17.b 42.c 18.a 43.b 19 d 44.a 20.c 45.d 21.c 46.c 22.c 47.c 23.a 48.c 24. d 49.d 25.b 50.b Page 1

t RIcct:r Operator Artw(r Kiy 51.c 76.b 52.b 77.b 53.a 78.d 54.b 79.d j

55.a 80.b 56 b 81.d 57.c 82.b 58.d 83.a 59.a 84.b 60.b 85.a

61. b 86.a 62.d 87.a 63.b 88.b 64.d 89. b j

65.a 90.b 66.a

91. b 67.c 92.d 68.a 93.c 69.d 94.a 70.a 95.b
71. a 96.b 72.a 97.a 73.d 98.c 74.d 99.a 75.b 100.c Page 2

=- --.. _...

Question Evaluation of requirem:nt far" active' license An operctor sits for the NRC Licens3 Oper: tor Ex:mination (Initirl), successfully pass:s ths Examination and is granted an NRC Senior Operator License or Reactor Operator license this month. What are the requirements for having the license on ACTIVE STATUS?

a. The individual must meet the time on shift requirements of SEVEN 8-hour shifts before the license is in ACTIVE STATUS.
h. The license is considered in ACTIVE STATUS for the current quarter ONLY.
c. The individual must meet the time on shift requirements of SEVEN 8-hour shifts to have a license lh ACTIVE STATUS for the next quarter.
d. The license is considered in ACTIVE STATUS for the current and next quarter.

l Answer d Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98

- KA: 2.1.1 RO Value:

3.7 SRO value:

3.8 Section

PWG RO Group:

1 SROGroup:

1 l

Systemevolution MA i

Knowledge of conduct of operations requirements.

l Explanation of l

Answer Reference Title /FacNity Reference Number Revisio L.O.

Braid wood Ops Memo #2 87 issued 5/1/97 rev. O Swd Tsk List Task P1-AM-TK-180 I

Material Required for Examination Question Source:

New Question Modincation Method:

3uestion Source Comments:

i Comment Type Comment f

A,.

l l

l l

l eMay, July 24,1996 4:33:45 PM Page 1 of 127 Prepared by WD Associates, Inc.

l Question Directi:n of NLO personn:l The following conditions on Unit 1.

- Reactor power 45%

- 1 A and 1C Feedwater pumps are operating

- FW PUMP TURB BRNG OIL LEVEL HIGH LOW annunciator (1-16-D3) alarms and the SER monitor indicates a low level.

l

- An EA is dispatched and confirms a low level exists.

. In performing actions to correct the condition (per BWOP TO-08 " Filling a Turbine Feed Pump Oil R:servoir"), what is the normal relationship between the US, the NSO and the EA?

1 i

l

a. The US will direct the EA's activities, but will inform the NSO before the job commences.
n. The US will direct the EA's activities, and need NOT inform the NSO unless unit controls are affected.
c. The NSO will direct the EA's activities, but will inform the US before the job commences.
4. The NSO will direct the EA's activities, and need NOT inform the US unless unit load is affected.

Answer C Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate.

9/14/96 KA: 2.1.1 RO Value:

3.7 SRO Value:

3.8 Section

PWG RO Group:

1 SROGroup:

1 SystenWEvolution KA Knowledge of conduct of operations requirements.

Explanation of Answer Reference Title / Facility Reference Number Revisio L O.

aidwood Task List Task P1B-AM-TK-130 Material Required for Examination Question Source:

New Question Modification Method:

. Question Sou'ce Comments:

r Comment Type Comment Friday, July 24,1996 4:33:46 PM Page 2 of 127 Prepared by WD Associates, Inc.

. - _ = _ - -

1 Question Operating Daily Ord:rs How is a procedura ch*ng2, which significantly chinges normal processes, procedurclly conysynd to Licensed members of the operating crew?

a. The SM places the applicable information in the Daily Order Book, and issues an additional memo to all crew personnel that is initialed.
b. The SM is informed by memo of the addition to the Daily Order Book, and makes an announcement of the addition during the shift briefing.
c. The SOS places the applicable information in the Daily Order Book, and the individual operator is responsible for reviewing the Daily Order.
d. The US places the applicable information in the Daily Order Book, and makes an announcement of the addition during the shift briefing.

Answer C Exam Level B Cognitive Level Memory Faciuty: Braidwood ExamDate:

9/14/98 KA: 2.1.2 RO Value:

3.0 sRo value:

4.0 section

PWG RO Group:

1 SROGroup:

1 systemIEvolution KA Knowledge of operator responsit2 ties during all modes of plant operation.

Explanation of Answer b

Reference Title / Facility Reference Number Section Page Revisio L. O.

BwAP 340-2 rev. 8 C.7.b.4) 14 Intro ta Main Control Room Ops Lesson Plan 5

Braidwood Task Ust Task P1-AM.TK.026 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment l

l iday, July 24,1998 4:33:46 PM Page 3 of 127 Prepared byWD Associates,Inc.

ouestion Procedure required usa 03 An cxampla of a licensed operator cvolution th t can be performed WITHOUT eith:r referring to en operations procedure or having a procedura in-hrnd is...

a. Adjusting rod position following a boration.
m. Starting the 1A Heater Drain Pump.
c. Placing excess letdown in service.

d.1.atching and rolling up the main turbine.

Answer a Exam Level B.

Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: 2.1.23 RO Value:

3.9 SRO Value:

4.0 Section

PWG RO Group:

1 SROGroup:

1 Systemevolution MA Ability to perform specific system and integrated plant procedures during all modes of plant operation.

sr.

s-- f - _ og Answer Reference Title / Facility Reference Number Section Page Revisio L O.

~pg 4,5 rev.12 Use Of Procedures For Operating Department BwAP 340-1 C.1.f.3)

Braidwood Task Ust Task P1-AM-TK-022 C

MaterialRequired for Examination Question Source:

New Question Modification Method.

Question Source Comments:

Comment Type Comment Friday, July 24,1996 4:33:47 PM Page 5 of 127 Prepared by WD Associates, Inc.

Question Use cf electrical pdnis Assuming en auto-close signal is continuously pres nt in th3 circuit for ths 1 A Si pump, which contact will be maintained open in order to prevent the starting relay (SR) from attempting repeated breaker closures onto a faulted bus?

(E 1-4030-Sl01 is provided for use.)

a. LC SW n.52/b
c. Y
c. LS Answer c Exam Level B

~ Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 2.1.24 Ro value:

2.8 sRo value:

3.1 section

PWG Ro oroup:

1 sRooroup:

1 systan/ Evolution KA -

Ability to obtain and interpret station electrical and mechanical drawings.

Explanation of "Y"is an antipump relay that when prevented from energizing interru' pts the circuit that energizes the START Answer relayin tne AUTO mstart circuit C

Reference Title /Facally Reference Number section/Page Revisio L o.

Schematic Diagram Safety injection Pump 1A 20E-1-4030Sl01 Print Reading Lesson Plan Chap 3 pg 23 rev. 5 2c,3

~

Material Required for Examination Question source:

Facility Exam Bank Question Modification Method:

Editorially Modified Question sourca Comments:

Braidwood requal bank Comment Type Comment 4

tiday, July 24,1996 4:33.48 PM Page 6 of 127 Prepared by WD Associates, Inc.

Questien MOV taCout An operator is preptring en OOS th t d:signit:s 1CC685, RCP Therm I Barri:r CC Rsturn CNMT isolation valve, as an isolation point.

What is the acceptability of using this isolation point?

1; The OOS is...

a. acceptable only if the MOV is tagged at its control switch, power supply and valve handwheel.

b, acceptable only if the MOV is tagged at its control switch, power supply and a blocking device is placed on the valve.

c. NOT acceptable because the MOV fails to meet isolation requirements.
d. NOT acceptable because the valve fails open on a loss of power.

l Answer a Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 l

.m: 2.2.13 RO value:

3.6 sRo value:

3.8 section

PWG Ro oroup:

1 sROGroup:

1 l

systemevolution KA Knowledge of tagging and cieerance procedures. f Explanation of Valve is MOV and requirements include tagging control switch, electrical power supply and local handwheel if Answer accessible.

Reference Title / Faculty Reference Number Section/Page Revisio L O.

SWAP 330-1 Out of Service Process D.4.a pg 12 l

D.4.c.1) pg 14 l

Naidwood Task List Task P1.AM-TK-010 Material Required for Examination I

Question Source:

New Question Modificati m Method:

Question Source Comments:

~ ' CommentType Comment l

l I

tiday, July 24,1996 4:33.49 PM Page 8 of 127 Prepared by WD Associates. Inc.

l Question RCS level discrepancy during refu ling Tha following conditions exist for Unit 1:

- Unit shutdown and cooldown initiated 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> ago

- Lowering of RCS level to the reactor vessel flange is underway 95*

- RCS temperature

- RCS level Control Room indicators: 1LI-RYO46 - 401' 0" 4

'1 LI-RYO49 -

402'1"

- RH loop 1 A in operation with " normal" indications What is the appropriate action for these conditions?

- c. The lowering of RCS level can continue.

n. The level change must be stopped until the cause for the level discrepancy is determined.
c. When temperature correction is applied to the highest Control Room level indication, the running RHR pump must be stopped to prevent cavitation,
d. When temperature correction is applied to the lowest Control Room level indication, the available S1 Pump aligned for hot leg injection must be started.

Answer b Exam Level B c:...^ a Level Comprehension Faculty: Braidwood ExamDate:

9/14/98 KA: 2.2.26 RO Value:

2.5 sao value:

3.7 section

PWG Ro oroup:

1 sROGroup 1

SystemEvolution KA Knowledge of refuenng administrative requirements Explanation of With any level discrepancy, the reason for the discrepancy must be determin'ed before further draining can Answer continue.

steforence Title / Faculty Reference Number section/Page Revisio L 0.

BwoP RC4 Reactor Coolant System Drain D.1 12E1 12 2

SWOP 100 4 Refueling Outage lesson plan MaterialRequired for Examination Question Source:

Faculty Exam Bank Question ModBAcation Method.

Significar.tly Modified Question Source Comments:

Zioa exam ' bank Comment Type comment NRC Significant industry Event-s Frid y, July 24,1998 4:33:51 PM Page 11 of 127 Prepared by WO Associates, Inc.

Question RO duties in C::ntrol Room during refueling

.- Whatis a responsibility of tha NSO during rcfueling operctions?

l

a. Checking source range counts while a fuel assembly is being placed in the core.
n. Ensuring water level in spent fuel pool is at least 23' above the fuel,
e. Maintaining a 1/M plot while reloading fuel during a core shuffle.
d. Monitoring the manipulator crane position by updating the Control Room tag board.

AnIwer 8 Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: 2.2.32 RO Value:

3.5 SRO Value:

3.3 Section

PWG RO Group:

1 SROGroup:

1 Syr.'em/ Evolution KA Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage f acility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

Explanation of Answer Reference Title / Facility Reference Number Section/Page Revisio L0 BwAP 200048 Reactivity Management F.2.h.8) pg 11 2E2 Braidwood Task Ust Task P1-QG-TK 051 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

+

Comment Type Comment Fridiy, July 24,1998 4:33.52 PM Page 12 of 127 Prepared by WD Associates, Inc.

.~

.... - -. ~.

. -. _. -.~ -. - -. -

Quesmon Radiition exposure detIrmin:ti:n

- An operctor h:s the following exposurs history this year until todty:

l Ocop Dose Equivalent (DDE) 210 mrem i

Jommitted Effective Dose Equivalent (CEDE) 45 mrem Shallow Dose Equivalent (SDE) 33 mrem Committed Dose Equivalent (CDE) 28 mrem i

l Today the operator was required to make two entries into containment:

Entry 1:

Gamma dose - 52 mrem; Neutron dose - 24 mrem Entry 2

Gamma dose - 124 mrem i

I i

How much radiation exposure is available to the operator if he has to make additional entries?

His available margin based on the routine Administrative Exposure Control Levels is...

l a.100 mrem for that day; 2484 mrem for the year.

b.100 mrem for that day; 2545 mrem for the year.

c.124 mrem for that day; 2569 mrem for the year.

- d.124 mrem for that day; 2614 mrem for the year.

l Answer b Esam Level B Cognieve Level Comprehension Faculty: Braidwood UsamDate:

9/14/98

KA: - 2.3.1 RO Value:

2.6 SRO Value:

3.0 Section

PWG Ro oroup:

1 SROGroup:

1 1

SystenWEvolution l

A f

Knowledge of 10 CrR: 20 and related facility radiation control requirements.

l Explanation of Limits are 300 mrem routine DDE/ Day and 3000 mrem routine cumulative TEDE/ year. C. Neutron rad not 4

j Answer counted for delly & yearly; A. All counted for yearty; d. previous DDE+ CEDE only counted for year.

Reference Title /FacNity Reference Number Section/Page Revisio L O.

+

Selected SwRPs Lesson Plan Rev. 00 2,3A i

i Material Required for Examination j;

Question Source.

New Question Modification Method.

l Question Source Comments:

I Comment Type '

Comment i

I l

5 -

! Friday, July 24,1996 4:33:52 PM Page 13 of 127 Prepared by WD Associates, Inc.

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Question Fu:1 H:ndling Accident R:spons3 f

The following conditions exist on Unit 1:

- Refueling operations in progress I

- A HIGH alarm received on radiation monitor 1RE-AR012, Containment Fuel Handling incident When should the NSO initiate action and what action should he/she take from the control room?

Indication of a fuel handling accident is considered when a...

a.' report is received from personnel in containment. The operator starts the containment charcoal filter fans.

b. report is received from personnel in containment. The operator actuates Unit 1 CNMT evacuation alarm.
c. corroborating rise is indicated on monitor 1RE-AR011. The operator starts the containment charcoal filter fans.
d. corroborating rise is indicated on monitor 1RE-AR011. The operator actuates Unit 1 CNMT evacuation alarm.

C Anewer d Exam I.svoi R Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 2.3.10 RO Value:

2.9 sRO Value:

3.3 section

PWG RO Group:

1 SROGroup:

1 systemevoluson KA Abimy to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

Empianation of Answer

.aference Title / Facility Reference Number Section/Page Revisto L O.

BwOA REF-1 Lesson Plan Rev.0 2,3,4 Material Required for Examination

~

rhdimi Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Friday, July 24,1996 4:33.53 PM Page 14 of 127 Prepared by WD Associates, Inc.

t l

euest&:n PIrf:rmance of Status Trees / Function Rist:rttiin 1

~

l The following conditions exist on Unit 1-

- A reactor trip has occurred and both reactor trip breakers are verified open

-The turbine has tripped

- BwEP-0 " Reactor Trip OR Safety injection" has been entered.

- BUS 141 ALIVE light is NOT lit with bus voltage at ZERO volts

- BUS 142 AllVE light is lit with bus Voltage at 4149 volts.

Which of the following describes the actions the operators are required to take?

a. Continue with next step of BwEP-0.
b. Turn on the synchroscope and manually close ACB 1412, SAT 142-1 feed breaker, l
c. Manually start 1 A D/G and verify ACB 1413, D/G output breaker, closes.
4. Initiate actions of BwOA ELEC-3 and continue with next step of BwEP-0.

Answer d Esam Level B Cognitive Level Memory Facety: Braidwood ExamDate:

9/14/98 KA: 2.4.16 RO Value:

3.0 SRO Value:

4.0 Section

PWG RO Group:

1 SROGroup:

1 O

SystemEvolution KA Knowledge of EOP implementation hierarchy and coordineUon with other support procedures.

Explanation of Answer l

Reserence Title /Factity Reference Number section/Page Revisio L. O.

Reactor Trip or Safety Irgection BwEP 0 Step 3.b. RNO MP 8 Rx Trip or si Lesson Plan rev.11 1,3 MaterielRequired for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Friday, July 24,1998 4:33:53 PM Pape 15 of 127 Prepared by WD Associates. Inc.

r

m ouestion Applicability of EOP Foldout Paga l

From ths list of procedures id:ntified below, which h s(havo)" Transfer to Cold Leg Recirculation" on ths Operator Action Summcry Page?

(NOTE: The following procedures are in the E-ior CA-1 series:

BwEP-1 " Loss Of Reactor Or Secondary Coolant" i

BwEP ES-1.1 "Sl Termination" BwEP ES-1.2 " Post-LOCA Cooldown And Depressurization" BwEP ES-1.3 " Transfer To Cold Leg Recirculation" BwEP ES-1.4 " Transfer To Hot Leg Recirculation" l

BwCA-1,1 " Loss Of Emergency Coolant Recirculation" BwCA-1.2 "LOCA Outside Containment")

I

a. BwEP-1, BwEP ES-1.1 through ES-1.4, and BwCA-1.1 through BwCA-1.2 procedures,
n. BwEP-1, BwEP ES-1.1 and ES-1.2 procedures ONLY.
c. BwEP-1 and BwEP ES-1.2 procedures ONLY.
d. BwEP-1 procedure ONLY.

Answer b Exam Level B Cognitive Level Comprehension Facistty: araidwood ExamDate.

9/14/98 KA: 2.4.20 RO Value:

3.3 sRo value:

4.0 section

PWG Ro oroup:

1 sROGroup:

1 system 4 Evolution KA Knowled08 of OP* rational implications of EOP warnings, cautions, and notes.

Explanation of Answer staference Title / Faculty Reference Number section/Page Revisio L O.

AP-1 Loss of Reactor or Secondary Coolant Lesson Plan rev.11 1,10 Material Required for Examination Question source:

New Question Modification Method:

l Question source Comments:

Commett Type Comment Friday, July 24,1998 4:33:54 PM Page 16 of 127 Prepared by WD Associates, Inc.

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Question Id:ntification of in:perabia CR annunciators The following conditions exist on Unit 1:

- Reactor trip breakers status - OPEN

- RCS Tave - 557'F

- Pzr pressure - 2235 psig Annunciator RCFC VIBRATION HI (1-3-C5) has been in alarm for the past 1 % shifts due to a faulty vibration probe. While maintenance troubleshoots the vibration probe on RCFC.1C which of the following cctions is appropriate for this alarm window?

a. The alarm should be acknowledged for each actuation and the SER monitored for valid alarm inputs.
h. The alarm should be acknowledged for each actuation and operators stationed locally at each RCFC to monitor vibration.
c. The alarm should have been silenced without acknowledgement after obtaining Unit Operating l

Engineer's permission and the SER monitored for valid alarm inputs.

4. The alarm should have been silenced without acknowledgement with US permission and operators stationed locally at each RCFC to monitor vibration.

1 An ww C Exami. eve B e; x t.svw : Comprehension Facety: Braidwood ExamDate' 9/14/98 l

KA: 2.4.31 RO Vdue:

3.3 sRO vehm:

3.4 section

PWG RO Group:

1 SROGroup:

1 sy.enwEveution MA Knowledge of annuncistors alarms and indications, and use of the response instructions Explanation of l

Answer l

Reference Titse/FacNety Reference Number Section/Page Revisio L 0.

RCFC VIBRATION HI /BwAR 1-3-C5 E.

1 51 HANDLING OF MAIN CONTROL BOARD and

~

RADWASTE PANEL ANNUNCIATOR ALARMS /

l BwAP 380-2 C.3 C.4 l

Braidwood Task List Task P1-AM-TK-033 i

Malertal Required for Examination l

Question Source:

New Question Modification Method.

Question Source Comments:

Comment Type Comment l

d y, July 24,1996 4:33:55 PM Page 18 of 127 Prepared byWD Associates,Inc.

Question Effect of XInon Transient & compensation A feed pump trip occurred r:sulting in a rapid power reduction on Unit 1. Pow:r was r:duced from 100%

st ady-stits conditions using a combin tion of rods end boration.

The following conditions exist for Unit 1 following stabilization-

- Reactor Power

.60%

- Delta-l target value - +2.0

- Control Bank D position - 160 steps withdrawn

- Tave - 572*F

-Delta-l - -10.5%

-Core Age - MOL What actions will be required to maintain t'he current power level and maintain Delta-l within its normal operating band over the next FIVE hours?

l

a. Boration and control rod withdrawal, followed by dilution.
n. Boration and control rod insertion, followed by dilution.
c. Dilution and control ro'd withdrawal, followed by boration
4. Dilution and control rod inseftion, followed by boration.

Answer a Exam Level B C:.J ;; Level Application Facility: Braidwood ExamDate:

9/14/96 KA: 001 A2.06 RO Value:

3.4 sRO value:

3.7-section: SYS RO Group:

1 sROGroup:

1 sysionWEvolution Control Rod Drive System KA Ability to (a) predict the impacts of the following on the Control Rod Drive system and (b) based on those predictions, use procedures to correct, control, or miti0 ate the consequences of those abnormal operation:

Effects of transient xenon on reactMty Explanation of With delt-l near the negative limit of the band, boration would be initiated to to allow rod withdrawal and hence Answer shifting of power poduction toward positive delta-l (power shift toward top of core). Later as Xenon (neutron poison) builds in, dilution will be initiated to maintain power level

'heference Tkle/ Facility Reference Number section/Page Revisio L O.

DELTA I CONSIDERATIONS F.3,5,6 3,4-7 BwGP 100-8 BwGP 100-8 Lesson Plan rev 4 1

Material Required for Examination Question source:

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Comment Type Comment Friday, July 24,1998 4:33:56 PM Page 19 of 127 Prepared by WD Associates, Inc.

- _ _ _ _ _.. _ _. ~... - _ _.. _ _ ~.

A problem with the rod control syst:m requires checking ssvercl rod bank circuits. Tha affected pow r cabinet repiirs are to be m ds by supplying pow r from thn DC hold supply cabin:t.

Nhat is the capacity of the DC Hold Supply Cabinet under'these circumstances?

a. ONE control rod bank group can be placed on DC HOLD, and these rods will drop ONLY if the controls are taken to OFF at the DC. Hold cabinet.
b. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, and these rods will drop ONLY if the controls are taken to OFF at the DC Hold cabinet.
c. ONE control rod bank group can be placed on DC HOLD, and these rods will automatically drop.

l

d. ONE control rod bank group and ONE shutdown bank group can be placed on DC HOLD, and these rods will automatically drop.

Answer C Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: 001 K1.03 -

RO value:

3.4 sRo value:

3.6 section

SYS RO Group:

,1 sRO Group:

1 systemevolution Control Rod Drive System

' ;,;, between Control Rod Drive System and the following' KA Knowledge of the Physical connections and/or cause-effect -

0 j

CROM

  • = - - t et Only one GROUP of control mds can be placed on HOLD at a time in order to ensure the rods are held without Answer falling. Opening the reador trip breakers interrupts power to the power cabinet and DC Hold cabinet, so that power to the CRDM is intenupted when the breakers open Reference Title /FacNity Reference Number section/Page Revisio L O.

Rod Control System Chap 28 A.S.e pg 40 12 1,9 Material Required for Examination Question source:

New Question ModlAcation Method.

Question source Comments:

  • CommentType Comment l

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Friday, July 24,1996 4:33:57 PM Page 20 of 127 Prepared byWD Associates,Inc.

4

W Question RIlationship oflevels during refueling operations The following conditions exist for Unit 1:

- Mode 5

- RCS is draining to Pzr level of 40%

-lM calibrations have been completed for LT-RYO48, Refuel Cavity level, in preparation for further draining What is the relationship between Pzr level instrument LT-459, Pzr level instrument LT-462 and LI-RYO487 At epproximately 40% level indicated on LI-462, level on...

1

)

a. Ll-459 and Ll-RYO48 will be offscale high.
6. LI-RYO48 will be just onscale and LI-459 will be offscale low.
c. LI-4'39 will read higher than 40% and Ll-RYO48 will just be onscale.
4. Ll-RYO48 will be offscale high and LI-459 will read lower than 40%

Answer c Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98

)

j KA: 002 A1.11 RO Value:

2.7 SRO value:

3.2 Section

SYS RO Group:

2 SROGroup:

2 SystenWEvolution Reactor Coolant System

)

KA Ability to predict and/or monitor chan0es in parameters associated with operating the Reactor Coolant System controls including:

Relative level indications in the RWST, the refue8ng cavtty, the PZR and the reactor vessel during preparation for refueling 4-Explanation of Ll-462 is the cold calibrated Pzr level instrument and will read lower (but more accurately) than the hot Answer calibrated level instruments (LI 459/460/461) at lower RCS temperatures. The refueling cavity level instrument j

Just comes onscale at 40% Pzrlevel.

l

' maiorence Title / Facility Reference Number Section/Page Revisio L O.

REACTOR COOLANT SYSTEM DRAIN BWOP RC-4 D.2 pg 4 rev.12E1 Swop RC-4A5 BwCB % fig 31 BwGP 100-6 Refuel Outage lesson plan rev.12 1,2 MaterialRequired for Examination Question Source:

New Question Modification Method:

l Question Source Comments:

Comment Type Comment t

Friday, July 24,1998 4:33:57 PM Page 21 of 127 Prepared byWD Associates,Inc.

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-~w

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Question '

RCS leak Det::cthn Systems

~

ThD following conditions cxist for Unit 1:

- Reactor power - 100%

- RCS activity is elevated, but below Technical Specification (CTS) levels

- Pzr pressure - 2225 psig l

- Pzr level - 44%

- PORV 1RY453 - dualindication

- Leak rate - 6 gpm in en attempt to isolate the leakage past the PORV, the Block Valve 1RY8000B was taken to close. The vrive failed to close and the operator placed 1RY456 in the CLOSE position. When conditions stabilize:

- Reactor power - 100%

- Pzr pressure - 2228 psig j

- Pzr level - 44%

How would the operator be able to tell if the PORV has closed?

\\

Position lights for PCV-456 showing CLOSE indication ONLY.

j

n. PORV downstream temperature indication 1TI-463 dropping.

1

c. Level change in RCDT.
d. Lower readings for containment radiation monitors RE-0011N0012A.

%swer b Esam Level R c:.- ^ ;; Leves Comprehension Faclety: Braidwood ExamDate:

9/14/98 KA: 002 A3.01 RO Value:

3.7 sRO Value:

3.9 section

SYS no oroup:

2 sRooroup:

2 system / Evolution Reactor Coolant System KA ANuty to monitor automatic operations of the heactor Coolant System including:

Reactor coolant leak detection system 8=7'm :. of Answer Reference Title /Facsity Reference Number section/Page Revisio L O.

rev51E2 1EwAR 12 C 4 task P1-OA-TK 058 Caldwood Task Ust Material Required for Examination Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment Friday, July 24,1998 4.33:58 PM Page 22 of 127 Prepared by WD Associates, Inc.

4

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Question Us3 of Loop Isolati:n Valvis The following conditions exist on Unit 1:

- RCS Loop C is isolated for maintenance

- RCS Loop A had been isolated for maintenance

- RCS Loop A Hot Leg Stop Isolation Valve (LSIV) was opened at 1001

- RCS Loop A Bypass Stop Valve was opened at 1005 with relief line flow of 115 gpm verified

- RCS Loop A Cold Leg LSIV is closed

-RCS temperature - 110*F

- RCS Hot Leg Loop temperatures - 108'F (A); 119'F (B); 110*F (C); 125'F (D)

- RCS Cold Leg Loop temperatures - 103'F (A); 108'F (B); 90*F (C);

115'F (D)

- S/G levels (Narrow Range) - 20% (A); 30% (B); 15% (C); 32% (D)

What will occur when the operator takes the control switch for MOV-RC8002A (RCS Loop A Cold Leg LSIV) to OPEN at 15097 l

The valve...

s. will travel fully open with NO automa' tic actu'ations.

i

b. will travel fully open, and the AFW pumps get a start signal.
c. remains closed because the temperature difference interlock remains active.

j

d. remains closed because the timer interlock is still active.

Answer 8 Exam Level R cognitive i.evel Comprehension Facility: Braidwood Exam 0 ate:

9/14/98 u: 002 K4.09 RO Value:

3.2 SRO value:

3.2 section

SYS RO Group:

2 SROGroup:

2 systemIEvolution Reactor Coolant System KA Knowledge of Reactor Coolant System design feature (s) and or interiock(s) which provide for the following:

Operation ofloop Isolation valves.

Explanation of

. Answer Reference Title / Facility Reference Number Section/Page Revisio L O.

Simplified RCS/RC-1 valve interlocks /1 3

R: actor Coolant system lesson plan 8

9 Chipter 12 Material Required for Examination Question Source:

Facility Exam Bank Question Modification Method:

Signifcantly Modified Question Source Comments:

Question 30/35 on Braidwood 1996 NRC exam is about LSIV interlocks. Premise and answers signifcantly different. Question asked about interlock for opening HL LSIV.

Comment Type Comment day, July 24.1998 4:33.59 PM Page 24 of 127 Prepared by WD Associates. Inc.

~ - -.. -. - - -

.-... - -. - ~. -

Question RCP and Pzr spray cperations The following Unit 1 conditions exist:

140*F

- RCS temperature (Average CETC) 365 psig

- RCS pressure

- A bubble has just been drawn in the Pressurizer

- Allloops are filled and vented

- Preparations are in progress to start the first RCP for continuous run What is the effect of selecting the 1C RCP to start?

a. Both Pzr Sprays will function normally for Pzr pressure control.
b. Manual cycling of the Pzr heaters will be required for Pzr pressure control.
e. PORV RY456 will open on high pressure from high pressure bistable PB456E.
d. Normal Pzr spray will deliver minimal spray flow for Pzr pressure control.

Answer d Exam level B C.. a Level Memory Faculty: Braidwood ExamDate:

9/14/98 MA: 003 A1.06 Ro value:

2.9 SRO Value:

3.1 Section
SYS RO Group:

1 SROGroup:

1 Systemevolution Reactor Coolant Pump System T KA AbiRy to predict and/or monitor chan0es in parameters associated with operating the Reactor Coolant Pump System controls PZR spray flow Explanation of Answer Reference Title / Facility Reference Number Section/Page Revisio L 0.

BwGP 100-1 Plant Heat up

f. 57 pg 20

. rev 11 RwGP 100-1 Plant Heat up eson plan 12.,

1,2,3 MaterialRequired for Examination Question Source:

New Question Modification Method:

. Question Source Comments:

Comment Type Comment

  • e

' day, July 24,1998 4:34:00 PM Page 25 of 127 Prepared by WD Associates. Inc.

.__m Question RCP Breaker &intrriocks The following conditions exist on Unit 1:

- Reactor power 26%

- Pzr pressure -2235 psig

- Pzr level - 35%

RCP 1 A breaker trips due to sensed undervoltage from bus 157. What is expected as a result of the trip of the RCP7 The reactor will trip due to the open RCP breaker,

b. The reactor will trip due to RCS loop low flow condition.
c. The reactor will be manually tripped by the operator.
d. A normal plant shutdown will be initiated.

Answer c Exam Level R Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 003 K2.01 RO Value:

3.1 SRo value:

3.1 Section

SYS RO Group:

1 SROGroup:

1 SystemEvolution Reactor Coolant Pump System MA Knowled9e of electrical power supplies to the following;'

RcPS Explanation of No AUTO idp is expected due to power < P-8. Administrative direction for a RCP trip in these condiitons is a Answer manualtrip will be initiated.

Reference Title / Facility Reference Number Section/Page Revisio L O.

Chp 13, Reactor Coolant Pump lesson plan C. 4.a 2)/ pg 16 9

8 AC Electrical Distribution lesson plan chp 4 8

10b

'os Memo / special Op Order Material Required for Examination Question Source:

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Question Source Comments:

Comment Type Comment l

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l 4

i iday, July 24,1998 4:34:01 PM Page 27 of 127 Prepared byWD Associates,Inc.

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.a.

Question Chrrging & letdown flows (including sell inj;cti:n)

The following conditions exist on Unit 1:

- Reactor power - 100%

~ - PZR pressure - 2235 psig

- PZR level - 44% stable

- CV121 - In MANUAL

- CVCS letdown - Isolated due to leak in Letdown Hx

- CVCS Excess Letdown - In service with maximum flow of 20 gpm

- RCP seal injection - 1 A CV pump aligned to all RCPs

- RCP seal leakoff flow - 3 gpm (1 A); 3.5 gpm (18); 3 gpm (1C); 2.5 gpm (1D) l What flow is indicated on Charging Header Flow indicator, F1-1217 a 5 gpm

b. 25 gpm c 32 gpm
d. 65 gpm

.e An:wer c Exam Level R Cognitive Level Application Facility: Braidwood ExamDate:

9/14/98 KA: 004 A3.11 RO Value:

3.6 SRO Value:

3.4 Section

SYS RO oroup:

1 SROGroup:

1 system / Evolution Chemical and Volume Control System KA Ability to monitor automatic operations of the Chemical and Volume Control System including:

Charging / letdown Explanation of F1-121 Indicates total charging flow (chg header + RCP seal flow, less Chg pump recirc (60 gpm)), Flow An wor balance - Letdown: 20 + 12 = 32 & Chg: 0 + 20 + 12 = 32.

..nference Title / Facility Reference Number

.Section/Page Revisto L O.

CVCSI Schematic CV-1 Chp 15a Chemical VolumeControl System lesson plan 10 4,5,9,15

~ Materli Required for Examination Question Source:

New Question Modification Method:

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Comment Type Comment r v.

l Friday, July 24,1998 4:34:02 PM Page 28 of 127 Prepared by WD Associates, Inc.

l

_.m Quesuon Cilculation of diluti::n The following conditions exist on Unit 2:

- Unit is in MODE 5

- Unit burnup is 5700 EFPH in Cycle 7

- SDM - 1.3% DeltaK/K

- RCS pressure - 400 psig

- RCS average temperature - 195'F

- RCS boron concentration - 1006 ppm

- Differential boron worth - -10.75 pcm/ ppm

- PZR level - 32.3%

- SR NIS countrate - 10 cps, BOTH channels stable background levels

- An inadvertent dilution at 70 gpm begins at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> Assuming NO operator action is taken and PZR level remains constant over the time period, when would ths HIGH FLUX AT SHUTDOWN alarm actuate?

a. Never, because BDPS will actuate prior to actuation.

b.1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.

c c.1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />.

d.1734 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.59787e-4 months <br />.

Answer C Enam Level B c:.-

a Level Application FacNity: Braidwood ExamDate:

9/14/96 KA: 004 A4.07 RO Value:

3.9 SRO Value:

3.7 section

SYS RO Group:

1 SROGroup:

1 SystenWEvoluuon Chemical and Volume Control System KA Ability to manually operate and/or monitor in the control room:

sorstion/ dilution Explanation of Dilution rate dc/dt = (500)(C)(Y)/M where M is the RCS mass at the given temperature (200*F). M = 745,537 Answer Ibm; C = 1006 ppm (given); Y=70 gpm (given). The dil rate = 47.2 ppm /hr. HIGH FLUX AT SHUTDOWN alarms at 5 x background = 50 cps. With K1= 0.987 dK/K (p1=-0.01317), calculate K2 = 0.9974 DKr/K (p2=-0.00261). Delta-P = 1056 pcm.1056/-10.75=-98.2 ppm change required. Therefore the time required for the 98.2 ppm dilution is 98.2/47.2 = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5 min. Difference in time based on use of Nomograph for RCS at normal pressure & temperature conditions. 'd' would only occur if count rate doubled in any 10 minute period. Assuming count rate increase is linear, for given dilution rate counts would change by 3 every 10 minutes.

Reference Titio/ Faculty Reference Number Section/Page Revisio L o.

RIactor Makeup Control system lesson plan 8

4,7,11 Source Range Nuclear instrumentation 6

6,10,11 Lesson plan Braidwood Curve Book Boron dilution rate nomograph Material Required for Examination Braidwood CURVE BOOK Figure 12.

Question Source.

New Question Modification Method:

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Comment Type Comment day, July 24.1998 4:34:02 PM Page 29 of 127 Prepared by WD Associates, Inc.

Topic Question B:ron mixing The fallowing conditions e.xist on Unit 1:

Reactor power was 95% prior to the event 4

- A turbine runback resulted in rod insertion with control rods in AUTOMATIC

- Annunciator ROD BANK LO-2 INSERTION LIMIT (1-10-A6) is lit Tha operators initiated an emergency boration per BwOA PRI-2 " Emergency Boration" and have verified control rods are now withdrawing. Why does the operator energize the Pzr Backup Heaters?

a This action...

c. ensures Pzr boron concentration equalization with RCS by increasing normal spray flow,
n. counteracts RCS cooldown due the boration by the additional heat from the backup

- heaters.

c. prevents loss of Pzr level by increasing the volume of fluid maintained in the Pzr.
d. guarantees adequate subcooling margin is maintained by raising the saturation temperature of the Pzr.

e 4

Answer a Exam Level R Cognitive Level Comprehension Faclety: Braidwood ExamDate:

9/14/98 KA: 004 K6.01 RO Value:

3.1 sRO Value:

3.3 section

SYS RO oroup:

1 sROoroup:

1 systemevolution Titie:

Chemical and Volume Control System KA Statement.

Knowled0e of the of the effect of a loss or malfundion on the following wM have on the Chemical and Volume Control System:

Spray / heater combination in PZR to assure uniform boron concentration Explanation of ta***r Reference Title /FacNety Reference Number Section/Page Revisio L O.

BwoA Prk2 Emergency Boration lesson plan 6

6 Reactor Makeup control system lesson plan 8

12 Material Required for Enamination Number (s) n Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment

.?

Friday, July 24,1998 4:34:03 PM Page 30 of 127 Prepared by WD Associates, Inc.

1

,r

Question R: circ intratirs to St Pumps & CV Pumps The following conditions exist on Unit 1:

- A LOCA has occurred

~ - Actions of 1BwEP ES-1.3, ' Transfer To Cold Leg Recirculation, have been completed.

l

- During alignmsnt,1CV8804A, RH HX to CENT CHG Pumps isolation Valve, l

failed to open and could NOT be manually opened.

l What is the status of the ECCS system?

a. The RHR discharge headers are cross-tied with only RHR Pump 1B running and supplying suction to the SI pumps and Centrifugal Charging pumps from the B train connection.
b. The RHR discharge headers are cross-tied with both RHR pumps running and supplying suction to the SI pumps only from the B train connection. The Centrifugal Charging pumps are stopped.

l

c. RHR Pump 18 is discharging through the B Train cold leg injection headers and supplying suction to the SI Pumps. RHR Pump 1 A and the Centrifugal Charging pumps are stopped.

l

4. RHR Pump 1B is discharging through the B Train cold leg injection headers and supplying suction to the Si pumps and Centrifugal Charging pumps. RHR Pump 1 A is discharging through the A Train cold leg injection headers.

Answer d Exam Level B CognitiveLevel. Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 005 K1.12 RO Value:

3.1 sRO Value:

3.4 section

SYS RO Group:

3 sRoGroup:

3 systemevolution

. Residual Heat Removal System KA Knowled0e of the physical connections and/or cause-effect relationships between Residual Heat Removal System and the following:

safeguard pumps i

E-;

^m of CL recirc lineup has any ONE running RHR pump aligned to provide suction path to all other ECCS pumps (SI l

Answer

& CENT CHG). The discharge headers between RH trains are required to be separate so that the ONE running RH pump does not operate in runout condition.

Reference Title /FacNity Reference Number section/Page Revisio L C.

E.mtrgency Operating Procedures Less of Reactor or secondary coolant /

BwEP 1, BwEP ES 1.1-1.4 11 10 Chp 58 Emergency Core Cooling system Lesson plan 10 5,7,8,14 Material Required for Examination Question source:

New Guestion Modification Method:

- Question source Comments:

Comment Type Comment "id:y, July 24,1998 4:34:o4 PM Page 32 of 127 Prepared byWD Associates,Inc.

i 1

. -. -.. ~ - - ~-

- -. ~.. -. - -.... - - -.

cmeetion Fellure of Hx Outlet Vtiva The following conditions exist on Unit 1

- Unit is in MODE 4 during cooldown per 18wGP 100-5.following unit shutdown 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> ago

- RCS temperature - 340*F

- RCS pressure - 345 psig

- PZR level - 33%

- RHR pump 1 A is operating in Shutdown Cooling mode

- RH-618 A Hx Bypass Flow Control Valve is in MAN at 3000 gpm

- RH406 A HX Flow Control Valve controller demand is at 20%

- CV-128 RHR Ltdn Flow Contr Valve demand is at 100%

- PCV-131 is in AUTOMATIC set to maintain 350 psig A signal failure from the controller causes RH-606 to go fully closed. What is the system response to this frilure without operator action?

PCV-131 will throttle open due to lower RH discharge pressure.

b. RCS pressure will increase due to RCS $eatup.
c. Pressurizer level will decrease due to increased letdown flow.
d. RH-610 will throttle open due to lower ~ RH flow.

Answer b Exam Level R Coennive Levd ' Application Faclety: Braidwood ExamDate.

. 9/14/96 KA: 005 K4.1o RO Value:

3.1 sRo value:

3.1 section

SYS RO Group:

3 sROGroup:

3 systenWEvolution ResidualHeat Removal System MA

. Knowled0e of Residual Hes* Removal System design feature (s) and or interlock (s) which provide for the followiry Control of RHR heet enchen0er outlet flow explanemon of RCS pressure will rise as fluid temperature increases due to loss of cooling flow through HX. IF flow Answer decreases system pressure downstream may decrease this will cause PCV-131 to throttle close in an attempt to raise pressure Reference Title /FacNity Reference Number section/Page Revisio L O.

~

RHR Cooldown/ RH-1 Schematic RH-1 1

Chp 18 Residual Heat Removal system 7

3,4,5,9 MaterialRequired for Examination Question source:

New Ometion Modification Method:

Question source Comments:

Comment Type Comment Friday, July 24,1998 4:34:o5 PM PeGe 33 of 127 Propered by WD Associates, Inc.

Question Syst!ms response is SI/Acti ns The following conditions exist on Unit 1:

- A plant heatup is underway

-MODE 3 has just been entered

- RCS pressure 450 psig l

SI Accumulator 1C was drained below required level during the outage for repair work. System configuration has NOT allowed refilling the Accumulator until now. The SI Accumulator line is being flushed in accordance with BWOP SI-14 "Si Accumulator Fill Line Flush" (Valve lineup includes: 1S1-8964, 1

SI Test Lines to Radwaste Isolation Valve, and SI-8888, S1 Pps to Accumulator Fill Valve, are open.1SI 8821 A, S1 Pump to Cold Leg Isolation Valve, and 1SI 8802A, Si to Hot Leg 1 A & 1D isol valve are l

closed). Si pump 1 A running. During the flushing, an inadvertent SI signal is generated.

What is the status of the ECCS based on the current alignment without operator action?

e.1B Si pump ONLY is running with injection flow to the RCS cold legs and to the Accumulator 1C fill line flush.

b.1 A Si pump ONLY is running with flow directsd to the Accumulator fill line flush ONLY.

c. BOTH Si pumps are running with injection flow to the RCS cold legs and to the Accumulator 1C fili line flush.
d. BOTH SI pumps are running with flow directed to the Accumulator 1C fill line flush ONLY.

Answer C Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 006 A2.13 RO Value:

3.9 SRO Value:

47 section: SYS RO Group:

2 sROGroup:

2 JystemEvolution Emergency Core Cooling System MA Ability to (a) prodk:t the impacts of the fo8owing on the Emergency Core Cooling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

Inadvertent SIS actuation Explanation of Si pumps are operable; Sl8821 A remains closed; Sl8888 and Sl8964 remain open.

- Answer Reference Title / Facility Reference Number Section/Page Revisio L O.

Plant Heatup BwGP 100-1 F.49 pg 30 11 SI Accumulator Fill Line Flush BwOP Sl-14 6

Chp 58 Emefgency Core Cooling system Lesson plan 10 6,9 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment day, July 24,1998 4:34:06 PM Page 34 of 127 Prepared by WD Associates, Inc.

euestion 10CFR50.46 Design Crittris To meet ths 10CFR50.46 crittrin, ths ECCS Systam is d5 signed such that und:r cccident conditions it will maintain...

a. total hydrogen production from zirconium-water reaction below maximum value of 5%.
b. maximum fuel temperature at the inside surface of the cladding less than 2000*F.
c. the core at least 5% shutdown to prevent an inadvertent return to criticality.
d. fuel clad oxidation less than 17% of total clad thickness anywhere within the core.

Answw d Exam Level B Cognitive t.evel Memory FacMity: Braidwood ExamDate:

9/14/98 KA: 006 K3.02 RO Value:

4.3 SRO Value:

4.4 Section

SYS RO Group:

2 SROGroup:

2 systanIEvolution Emergency Core Cooling System KA-Knowledge of the effect that a loss or malfunction of the Emergency Core Cooling System wlR have on the following:

Fuel Explanation of Third selection addresses design criteria for reactivity control per CTS.

?

'Aeference Title /FacMity Reference Number

- Section/Page Revisio L O.

10CFR50/ 47 Chp 58 Emergency Core Cooling system

",.4 Lesson plan 10 2

Material Required for Examination Question Source:

FacAlty Exam Bank Question Modification Method:

Editorially Modified Question Source Comments:

Corrment Type Comment Friday, July 24,1998 4:34:06 PM Page 35 of 127 Prepared by WD Aasociates, Inc.

. ~..

a+

Evalu: tion of flow ECCS pumps The following conditions exist on Unit 1 i

' A LOCA has occurred

-Transfer to Cold Leg recirculation is required

- RCS pressure is approximately 50 psig l

What is the approximate total Si pump flow indicated on the main control board and how will this value l

change following transfer of BOTH trains of ECCS to cold leg recirculation?

Total Flow Flow Change 650 gpm Decrease

n. 800 gpm Increase e.1050 gpm Decrease 1

4.1300 gpm increase i

Anewer d Exam Level B Cognitive Levd Comprehension Facety: Braidwood ExamDate:

9/14/96 KA: 006 K8.03 RO Value:

3.6, sRo value:

3.9 section

SYS Ro oroup:

2 000 oroup:

2

)

- systemevoluson Emergency Core Cooling System l

KA knowledge of the of the effect of a loss or malfunction on the following wm have on the Emergency Core tkW System:

safetyletection Pumps l

Explanation of Si pump design values provid e for 650 gpm flow per pump @ 1300 psig and 1300 gpm O 600 psig (or less).

Anewer The flow from the pumps increases since the RH pumps are now providing a suction pressure of approximately l

250 psig to the pumps instead of the lower pressure (30 psig or less) provided by the head associated with i

RWST Ievel.

~

J L

', Reference Time /Facielty Referen:e Number section/Page Revielo L O.

Chp 58, Emergency Cors cooling System Lesson plan 10 3,8a l

MaterialRequired for Examination Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment i

l l

l

~iday, Juh 24,1998 4:34:07 PM Page 36 of 127 Prepared byWD Associates,Inc.

I i

1

. _ ~

- Question PRT conditions causing ticrm/ response During shift turnover for Unit 1, the NSO not::s th3 following partmit:rs:

l RCS Tave. - 566.5*F Dzr pressure - 2235 psig Pzrlevel - 38.3%

PRT pressure - 4 psig PRT level - 74%

l PRT temperature - 98'F One hour later when annunciator 1-12-A7, PRT LEVEL HIGH LOW alarmed, the NSO notes the following parameters:

I RCS Tave - 566.2*F Pzr pressure - 2233 psig Pzrlevel - 38%

PRT pressure - 5.9 psig PRTlevel - 81%

PRT temperature - 96*F.

O What condition resulted in the change in parameters?

i l

PRT PW Supply inside Cnmt isol Valve RY-8030 opened,

b. PRT to GW Comp Isol Valve RY-469 failed closed.
c. CVCS letdown relief valve CV-8117 lifted.
d. PORV RY-455A opened and reclosed.

Answer a Exam t.evel R Cognitive i.evel Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 2.4.50 RO Value:

3.3 SRO Value:

3.3 section

SYS

. RO Group:

3 SROGroup:

3

- system / Evolution Pressurizer Relief TanivQuench Tank System KA Ability to verify system alsrm setpoints and operate controls identified in the alarm response manual.

Explanation of The only input provided that would give a levelincrease and a temperatue decrease is the makeup from PW.

Answer Reference Title / Facility Reference Number Section/Page Revisio L. O.

Pressurizer Relief Tank Filling and Venting SWOP RY-3 3

PRT1.evel High law / SwAR 1-12-A7 51E1 Chp 14 Pressurizerlesson plan 9

13,14 Material Required for Examination Question Source:

New Question Modification Method:

Eddorially Modified Question Source Comments:

Ginna 9/90 NRC Exam Comment Type Comment Friday, July 24,1998 4:34:08 PM Page 37 of 127 Prepared by WD Associates, Inc.

Topic t.

j ouesuon Determination of effect of valve positioning Unit 1 is operating at 100% power in MOL conditions. All systems are functioning normally with rod

.:ontrol in manual.

What is the effect on plant operations if instrument air supplied to the CVCS letdown Hx component cooling water outlet valve, CV-130 is lost?

TCV-130 goes fully...

a. shut and reactor power decreases due to boration in the CVCS demineralizers.
n. shut and the CVCS demineralizers are automatically bypassed on temperature signal, l
c. open and reactor power incret.ses due to deboration in the CVCS domineralizers.
d. open and the CVCS demineralizers are automatically bypassed on temperature signal.

Anewer C Exam Level R Cognitive Level Comprehension Facility: greldwood ExemDete.

9/14/98 NA: 008 A2.05 RO Value:

3.3 sRo valur

3.5 section

SYS Ro oroup:

3 sRooraup:

3 synenmevosunon Component Cooling Water System MA Abity to (e) prodot the impacts of the following on the Component Cooling Water splom and (b) bened on thoes predictions, use precedures to correct, control, or mitl0ste the consequences of those obnormal operation-Essot of loss of instrument end control air on the poeWoa of the CCW valves that are air operated Explaneson of The CVCS letdown flow is overcooled and will give up boron to the resins in the CVCS demins (until a new Answer equilibrium value of boron reached in domins).

Reference T18e/iteceity Reference Number Section/Page Revisio L O.

ss of Instrument Air /10wOA Sec-4 Table A Component clo 2

_o Ch15a CVCS lesson ' lan 10 10,14 p

Service Air / Instrument Air Lesson plan review quest 14 8

9 MeterialRequired for Examination Question source:

New Question Modification Method:

Number (s) n i

Question source Comments:

Comment Type Comment

'May, July 24,1998 4:34:08 PM Page 38 of 127 Prepared by WD Associates, Inc.

Question Spray using Norm;lcnd Aux Spray What cra the partmrt:rs cnd vrlues used by tha operntor to ensure tho t:mperatura diff:rance betwun the PZR and ths spr y fluid cro within tho specified limit (s)in the PRESSURE AND TEMPERATURE LIMIT REPORT when initiating PZR spray?

a. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor space temperature limit is 50*F, and for aux spray, the difference between Regenerative Hx charging inlet temperature and PZR vapor space limit is 320*F.
n. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 50*F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is 320*F.
c. For normal spray, the difference between RCS hot leg loop temperature an'd PZR vapor space

~

temperature limit is 320*F, and for aux spray, the difference between Regenerative Hx charging inlet temperature and PZR vapor space limit is 320*F.

d. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 320*F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is'320*F.

Answer d Exam Level B

' CognWye Level -Memory 0 Facility: Braidwood ExamDate:

9/14/96 KA: 010 A1.08 RO Value:

3.2 sRO value:

3.3 section

SYS,y RO Group:

2 sROoroup:

2 systemEvolution Pressurizer Pressure Control System r-KA Ability to predict and/or monitor changes in parameters associated with operating the Pressurtzer Pressure Control System cont ois including:

Spray nozzle DT Explanation of Answer Wence Title / Facility Reference Number section/Page Revisio L O.

PressurizerTemperature Umit Surv/

18wOS 4.9.2-1 Pressurizer Spray Water Temperature

' Differential Umit surv/18wOS 4.9.2-2 1BwGP 100-1 Plant heat up lesson plan 12 1,2,3 Chp 14 Pressurizerlesson plan 9

7,8 Material Required for Examination Question Source:

New Question Modification Method:

significantly Modified

' Question source Comments:

Kewaunee 2/94 NRC Exam Comment Type Comment 1ay, July 24,1998 4 34:09 PM Page 39 of 127 Prepared by D Associates, Inc.

\\

l Question Evaluation of Pzr conditi:ns

~

i The following conditions exist on Unit 1:

- A load reject from 100% power has occurred

- Reactor power - 80%

i

- Pzr level - 56%

- Pzr vapor temperature - 655'F

- Pzr liquid temperature - 653*F

- RCS Tave - 578'F l

What is the current status of the Pressurizer based on given conditions?

Backup and proportional heaters are fully on.

h. Proportional heaters are modulated on.
c. Pzr sp[ay valves have modulated open.
4. Pzr spray valves and Pzr PORVs are open.

Answer C'

Exam Level B Cognitive Level Comprehension Faciety: Braidwood ExamDate:

9/14/98 KA: 010 K5.01 RO Value 3.5 sRO Value:

4.0. lsection

SYS Ro oroup:

2 sROGroup:

2 systenWEvolution Pressurizer Pressure Control System KA Knowledo' of th* OPerstionalimW of the fonowing concepts as they apply to the Pressurtzer Pressure Control System:

Determination of condition of fluid in PZR, using steam tables Explanation of At 655'F, saturation pressure is 2272 psig. At this pressure, with current PZR level deviation <5% of program Answer level (53%), the sprays are the only component "on".

Reference Title / Faculty Reference Number section/Page Revisto L. o.

'tr Pressure Control / RY-2 Pzr Pressure Setpoints 9

5,6,7 Chp 14 Pressurizerlesson plan St:am tables Saturation table Material Required for Examination Steam Tables uestion source:

FaciHty Exam Bar.k Question Modification Method.

Concept Used Q

Question source Comments:

Braidwood 1997 NRC exam Comment Type Comment Friday. July 24,1998 4:34:10 PM Pa0e 41 of 127 Prepared by WD Associates, Inc.

4

Question Pzr Lcvel React::r Trip The following conditions exist on Unit 1 with all controls in normal linaup:

- Reactor power - 30% stable

- RCS Tave - 564.5'F

- Pzr pressure - 2230 psig

- Pzr level - 36%

Th3 pressurizer level controller 1LK-459 output fails low. What automatic actions result assuming NO operator action taken?

a. The reactor will trip on high pressurizer level ONLY.
b. Letdown will isolate on low pressurizer level and then the reactor will trip on high pressurizer level.
c. The reactor will trip on high pressurizer pressure ONLY.
d. Letdown will isolate on low pressurizer level and then the reactor will trip on RCS low pressure.

An:wer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/96 KA: 011 K1.04 RO Value:- 3.8 sRO Value:

3.9 section

SYS RO Group:

2 sROGroup:

2 systerrWEvolution Pressurizer Level Control System KA Knowledge of the physical connections and/or cause-effect relationships between Pressurizer Level Control System and the RPS Explanation of NOTE that this failure is like the failure of the controlling level channel high in that charging flow falls to Answer minimum. At 17% level, letdown isolates charging continues at minimum (52 gpm) and Pu level sises to high level trip setpoint.).

Reference Title / Facility Reference Number Section/Page Revisio L O.

zr Level Control schematic RY-3 Pzrlevel setpts 2

Chp14 Pressurizerlesson plan 9

21 Material Required for Examination

~ Question Source:

Facility Exam Bank Question Modification Method:

Significantly Modified Question Source Comments:

Comment Type Comment Friday, July 24,1998 4:34:11 PM Page 42 of 127 Prepared by WD Associates, Inc.

Question Operatirn of BOTH Bypass Trip Breakers Th3 following conditions exist on Unit 1:

- Mode 3 NOT NOP with reactor trip breakers (RTA and RTB) closed

- Testing of reactor trip bypass breakers underway

- Reactor bypass breaker B (BYB) is racked in and closed

- An operator begins to perform test with reactor bypass breaker A (BYA).

What occurs as the operator operates the breaker BYA7 When reactor bypass breaker BYA is...

e. locally closed, ONLY breaker BYB will trip.
b. racked in to the CONNECT position, DNLY breaker BYB will trip.

l

c. locally closed, all reactor trip and bypass breakers will trip.
4. is racked in to the CONNECT position, all reactor trip and bypass breakers will trip Answer C Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: 012 A3.07 RO Valuer 4.0 sRO Value:

4.0 section

SYS RO Group:

2 SROGroup:

2 system / Evolution Reactor Protection System KA Ability to monitor automatic operations of Me Reactor Protection System including:

Trip breakers Explanation of Closure of the second BYB results in SPSS generating a GENERAL WARNING on both trains which would Answer open all trip and bypass breakers.

Reference Title / Facility Reference Number Section/Page Revisio L 0, 3F setpoints Schematic EF-2 Rx Trip Byp brkr trips 5

wh 60a SSPS lesson plan 3

6,9 Material Required for Examination Question Source:

Facility Exam Bank Question ModlScation Method:

Editorially Modified Question Source Comments:

Comment Type Comment l

l Frid:y, July 24,1998 4:34:11 PM Page 43 of 127 Prepared byWD Associates,Inc.

-...-~-

Question

_ Input that can be bypass & conditi:n The following conditions exist on Unit 2:

- Unit shutdown is in progress

-Reactor power - 20%

- RCS Tave - 562*F

- Pzr pressure - 2235 psig

- Pzr level - 32%

l

- First stage turbine pressure channel PT-506 fails high l

l What affect does this failure have on operations as unit shutdown is continued, if NO action is taken for the failure?

a. At 10% power, the reactor will trip if the Source Range Block RESET pushbuttons are depressed.
b. At 9% power, the reactor will trip if an RCP trips.
c. At 7% power, the reactor will trip if the TURBINE TRIP pushbuttons are depressed.
d. At 5% power, the reactor will be manually tripped as during a normal shutdown by BwGP 100-5.

l Answer d Exam Level B Cognitive Levet Comprehension Facility: Braidwood ExamDate:

9/14/96 MA: 012 A4.03 RO Value:

3.6 sRO Value:

3.6 section

SYS RO Group:

2 SROGroup:

2 systemIEvolution Reactor Protedion System KA Ability to manually operate and/or monitor in the control room:

Channet blocks and bypasses l

Explanation of PT-506 failure results in P13 interlock NOT cleadng when turbine power falls below 10%. This also feeds into Answer P7 "AT POWER TRIPS" intedock also remains active. Tdps affected: 1) 2 loop loss of flow,2) Pu low press, l

3) Pu high level,4) RCP brkr open,5) RCP UV,6) RCP UF. At 10% power, the SR NIS should still be auto i

blocked by P-10 (active). The turbine is normally tripped from ~65 Mwe at 5% power per BwGP.

Reference Title / Facility Reference Number Section/Page Revisio L O.

Power Descension /1BwGP 100-4 note step F.27 16 j

l

~ESF Setpoints/ Schematic EF-1/ Permissive Rx Tdp 4

f Ch60b/ Reactor Protection system 6

4 l

Material Required for Examination l

Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Conwnent Friday, July 24,1998 4:34:12 PM Page 44 of 127 Prepared by WD Associates, Inc.

4 i

_.. - - - _....- - ~. - -

1

~

Topic ouestion OTdT inputs & sffect of changis The fcilowing conditions exist on Unit 1:

- Power range NIS reading - 100%

- Tcold - 553*F

- Thot - 608'F

- RCS total flow - 372,000 gpm j

- Pzr pressure -2215 psig

- Pzr level - 69%

How does the setpoint for Over Temperature Delta-T (OTdT) change when a listed parameter is chinged? (Consider each change individually)

Tha setpoint...

a. increases if Power range NIS output rises to 102%.
n. increases if total reactor flow decreases to 370,000 gpm.
c. decreases if pressurizer pressure increasesjo 2235 psig.
4. decreases if the Thot rises to 612*F.

Answer d ExamLevel R cognitiveLevel Comprehension Facility: Braidwood ExamDate:

9/14/98 MA: 012 K5.01 Ro Value:

3.3 sRo value:

3.8 section

SYS Ro oroup:

2 sRooroup:

2 Time:

system / Evolution Reactor Protection System statement:

KA Knowledge of the operationalimplications of the following concepts as they apply to the Reactor Protection System:

DNB

  • ,"- -'; of a - NIS input is only for exceeding +/- delta-l; b - Flow affects when DNB occurs, but is NOT an input to OTdT; Answer c - Pressurize rise increases OTdT. That input to dT power for OTdT detefmination Number (s) n Reference Title / Facility Reference Number section/Page Revisio L o.

i!SF Setpoints/ EF-2 OTDT 5

l 6

3,4 CH 60b/ RPS lesson plan MaterialRequired for Examination Question source:

New Question Modification Method.

Question source Comments:

Comment Type Comment Friday, July 24,1998 4:34:14 PM Page 46 of 127 Prepared byWD Associates,Inc.

Quesuon CNMT Spray /Phise B The following conditions exist on Unit 1:

- Mode 3 with unit cooldown in progress

- RCS temperature - 520'F

- Pzr pressure - 1750 psig

- Pzr level - 33%

- MSIVs open What would directly happen if the operator were to take CONTAINMENT SPRAY & PHASE B ISOL switches for both trains to the ACTUATE position?

NO ESF actuations would occur.

b. Containment Phase B isolation and Containment Ventilation isolation ONLY would be actuated.
c. Containment Phase B isolation and Containment Ventilation isolation, and Containment Spray ONLY would be actuated.
d. Containment Phase B isolation and Containment Ventilation isolation, Containment Spray, and Main Steamline isolation would be actuated.

c,-

Answer C Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 013 A3.01 RO Value:

3.7 sRO Value:

3.9 section

SYS RO Group:

1 sROGroup:

1 systenWEvoludon Engineered Safety Features Actuation System KA Ability to monitor automatic operations of the Engineered Safety Features Actuation System including:

l Input chant eis andlogic Explanation of Phase B, CS actuation and CNMT vent directly actuated. Main Steam isolation comes in auto on a rate CNMT Answer Hi-2 pressure (or manual MSLI) only.

Reference Title / Facility Reference Number section/Page Revisio L O.

ESF Setpoints/ EF-2 CS/ Phase B sig 5

CS/ MCB indications / CS-1, CS-2 CS Actuation sig 3

5 7,8

.4hp 61 ESF !ssson plan

~

Material Required for Exa.aination Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment Friday, July 24,1998 4:34:14 PM Page 47 of 127 Prepared by WD Associates, Inc.

Question FWlsolation - P14 The following conditions cxist on Unit 2:

- RCS temperature - 340*F i

- RCS pressure - 900 psig

- All MSIVs for the S/Gs are closed

- The MSIV Bypass _ valves are open

- The FW-035s, Feedwater Tempering Isolation Valves, are open

- The FW434s, Feedwater Tempering Flow Control Valves, are closed

- (opened periodically for level control) l

- Feedwater pump 2C is reset and latched on turning gear

- The Start Up Feedwater pump is running The level in the S/G 2B rises to 90%. How is the plant affected?

a. No actuation occurs because of the position of the MSIVs.
b. The 2C Feedwater pump and Start Up Feedwater pump trip.
c. The 2C Feedwater pump trips and FW-035 v,alves c;ose.
4. The 2C Feedwattr pump and Start Up Feehater pump trip, the FW-035 valves close, and the MSIV Bypass valves close.

Answer C Exam Level R Cognieve Level Comprehension FacWty: Brakhvood ExamDate:

9/14/98 KA: 013 K4.13 RO value:

3.7 sRo value:

3.9 Secuen

SYS RO Group:

1 SROGroup:

1 SyseenWEvolution Engineered Safety Features Actuation System KA-Knowledge of Engineered Safety Features Actuation system design feature (s) and or interlock (s) which provide for the following:

MFWisoistion/ reset Explanation of Having Loop Isolation Stops closed does not defeat P-14.

Answer Reference Twe/FacMMy Reference Number Section/Page Revisto L O.

"Feedwater simple / FW-1 FWI signalt.

4

- SGWLC/ FW-2 S/U Flowpaths O

Chp61 ESF lesson plan 5

7 Materiel Required for Examination Question Source:

New Question ModWication Method

  • Question Source Comments:

Comment Type Comment iday, July 24,1998 4.34:15 PM Page 48 of 127 Prepared byWD Associates,Inc.

Question ROD BOTTOM Alirm cper;ti n During a r :ctor startup, whzn does ths ROD AT BOTTOM alarm becoma activa for each control bank?

The alarm will actuate for a dropped rod for...

c. any Control Bank whenever Control Bank A DRPI output is above 9 steps.
b. each Control Bank ~whenever that Control Bank demand position is above 3 steps,
c. each Control Bank whenever that Control Bank DRPI output is above 9 steps.
d. Control Banks A, B and C whenever their Control Bank demand position is above 9 steps, and for Control Bank D whenever Control Bank D demand position is above 3 steps.

j Answer C Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: 2.4.31 RO Value:

3.3 sRO value:

3.4 section

SYS RO Group:

2 SROGroup:

1 systenWEvolution Rod Position Indication System MA

- Knowled0e of annunciators alarms and indications, and use of the response instructions.

Empianation of Note that the ROD BOlTOM comes direfctly from the DRPI unit with a setpoint of 9 steps; the alann actuates Answer when rod position is detected at 3 steps (or,less).

j Reference Title / Facility Reference Nunber SectiordPage Revisio L O.

ROD at Bottom /1BwAR 1-10-E6 2

Chp 29 rod Position Indication sys Lesson plan 9

4,5 i

Material Pequired for Examination Question dource:

New Question Modification Method:

Signifcantly Modified Question Source Comments:

Millstone 311/90 NRC Exam -

Comment Type Comment

?

i l

l iday, July 24,1998 4:34:16 PM Page 50 of 127 Prepared by WD Associates, Inc.

l l

Queenon SR NIS discriminat::rfailure How woul'd ths frilurs of tha pulse h::ight discriminator to a low valus affret the indication of tho affected Source Range channel?

The output would...

c. decrease due to electronic filtering which narrows the pulse height window.
b. decrease due to failure in counting the higher amplitude neutron generated pulses,
c. increase due to counting of the gamma generated pulses ONLY.
4. increase due to counting of the gamma generated pulses and decay alpha generated pulses.

Answer d-Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: 015 A2.02 RO Value:

3.1 SRO Value:

3.6 Section

SYS RO Group:

1 SROGroup:

1 System /Evoludon Nuclear Instrumentation System MA Ability to (a) predict the impacts of the folkWng on the Nw: lear Instrumentation system and (b) based on those predictions, use procedures to correct, control, or mitigste the consequences of those abnormal operatiort Fauty or erratic operation of detectors or compensaung w...r.-

Explananon of Pulse height discriminator used to set window to detect those pulses with en'ergy level high enough to be from Answer event associated with neutron detection. Gamma and other interactions such as the alpha decay of fission product daughters is of lower heigth (energy) and disciminator normally electronically removes.

Reference Tine / Facility Reference Number Section/Page Revision L O.

Source Range Detector schematic N14 4

Chp 31 Source Range Nuclearinst 6

3 Material Required for Examination Question Source:

New Question Modification Method:

Queouon Source Comments:

Comment Type Comment l

Frid2y, July 24,1998 4:34:17 PM Page 52 of 127 ~

Prepared by WD Associates, Inc.

1

Quesuon SR NIS -loss of control power The following conditions exist on Unit 1:

- RCS at NOT NOP

- Reactor trip breakers - closed

- Source Range readings:

N31 - 18 cps N32-22 cps What indication would the operator observe if Control Power was lost to the N31 Drawer?

The N31 meter would read...

c. downscale, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.
n. downscale, the associated drawer bistable lamps lit, and reactor trip breakers open.

c.18 cps, the associated drawer bistable lamps NOT lit, and reactor trip breakers closed.

4.18 cps, the associated drawer bistable lamps lit, and reactor trip breakers open.

Answer d Exam Level B C.- ^W Level Comprehension Facility: Braidwood ExamDate:

9/14/98 3

KA: o15 K2.01 RO Value:

3.3 sRO Value:

3.7 section

SYS RO Group:

1 SROGroup:

1 systemevolution NuclearInstrumentation System KA Knowledge of electrical power supplies to the following:

Nis channels, components, and interconnections Explana6cn et Control power loss affects bistables which trip but NOT drawer instrument indication which is from Instrument

. Answer Power source.

Reference Time /FacNity Reference Number Section/Page Revision L O.

Source Range Detector Schematic N1-4 loss of Control power 4

Ch 31 Source Range NuclearInst 6

8.b Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Friday, July 24.1996 4:34.18 PM Page 53 of 127 Prepared by WD Associates, Inc.

m+

Evd for 1M - Eightfold incroise The f:llowing conditions exist on Unit'1:

- A reactor startup is about to be performed

- All shutdown banks are fully withdrawn

- All control banks are fully inserted

- An ECC records the following:

Predicted Critical Position (ECP) '- 130 steps on'CBD Max rod position - 231 steps on CBD Min rod position - 58 steps on CBD The following parameters were recorded during the rod withdrawal:

ROD HEIGTH N31 cps N32 cps 0 on CBA 25 23 178 on CBA 34 31 178 on CBB 58 62.

178 on CBC 116 106

~

80 on CBD 200 182 92 on CBD 237 225 When was the first time the operator was required to determine the Predicted Critical Position?

e. At 50 steps on CBA, with N32 as the designated Source Range detector.
b. At 113 steps on CBC, with N31 as the designated Source Ra'nge Detector.
c. At 80 steps on CBD, with N31 as the designated Source Range detector.
d. At 92 steps on CBD, with N32 as the designated Source Range detector.

Answer c Exam Level R cognitive Level Comprehension Faciuty: Braidwood ExamDate:

9/14/98 KA: 015 K5.06 RO Value:

3.4 sRO Value:

3.7 section

SYS Ro oroup:

1 sRooroup:

1 systanevolution Nuclearinstrumentation System J

1 KA Knowledge of the operationalimplicatione of the following concepts as they apply to the Nuclear instrumentation System:

Suberttical multiplications and NIS Indications E C - " of During reactor SU, hold point for ICRR determination is performed for each Control Bank at 50 steps and 113 steps withdrawn. The actual detemination of Predicted Critical Position is required at the eight-fold count An:wer increase holdpoint.

' Reference Title /Factity Reference Number section/Page Revision L O.

1BwGP 100-2 Reactor Startup 18wGP 100-2A1 12 13 2

1BwGP 100-2A1 Lesson plan Material Required for Examination Question source:

New Question Modification Method.

Question source Comments:

Frid y, July 24,1998 4:34:19 PM Pa0e 55 of 127 Prepared by WD Associates, Inc.

4

Question NR RTD Failure cffects The following conditions exist on Unit 1:

~

- Reactor power - 50%

- RCS Tave - 570*F (A); 569'F (B); 569'F (C); 570'F (D)

- RCS Thot - 585'F (A); 584*F (B); 583*F (C); 585'F (D)

- RCS Tcold - 555'F (A) 554*F (B); 555'F (C); 555'F (D) c

- Pzr pressure - 2235 psig

- Pzr level - 43 %

If loop B Thot output channel fails LOW, what is the response of Pzr level ?

Pr:ssurizer level will...

a. Increases to 60%.

- b. remains the same.

e. decreases to 25%.
d. decreases to the letdown isolation setpoint.g Answer b Exam Level B Cognitive Loves Comprehension Facliity: Braidwood ExamDate:

9/14/98 KA: 016 K3.02 RO Value:

3.4 sRO Value:

3.5 section

SYS RO Group:

2 sROoroup:

2 systemevolution Non-Nuclear Instrumentation System KA Knowled9e of the effect that a loss w malfunction of the Non Nuclear instrumentation System will have on the fogowing:

PZR LCS Explanation of Thot fails to 510*F. With loop Tcold of 537'F, loop Tave is now 524'F. Auctioneered HIGH Tave is used Answer level program.

..eserence Title /FacMity Reference Number section/Page Revision L O.

PZR Level Control Schematic RY-3 2

18wCA Inst-2 leston plan 15 1

.,chp 12 RCS lesson plan 8

13 Material Required for Examination Question source:

Facility Exam Bank Question Modi 6 cation Method:

Concept Used Question source Comments:

Zion 2/92 NRC Exam (along with several others). Change includes failure of Thot loop, failure low and conditions Instead of dual condition.

Comment Type Comment Friday, July 24,1996 4:34:20 PM Page 56 of 127 Prepared by WD Associates, Inc.

. ~ -

l Question CETC failure effect cn Subcooling Monit:r/lconic Display With Unit'1 ct 100% pow:r end with normal operating parcmeters, how would th3 fritura of the HOTTEST Cora Exit Thermocoupin effect the rciding of subcooling margin on the SPDS leonics (CETC/SMM display) for each of the two situations below:

l Situation 1 - The CETC output fails high slowly 1

Situation 2 - The CETC output fails low slowly

a. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and retum to normal when CETC output reaches 2300*F.

Situation 2: Subcooling margin will increase, then stabilizes when the CETC output is smaller than TEN other TCs.

n. Situation 1: Subcooling margin will decrease to saturation then rise in superheat, and retum to normal when CETC output reaches 1200*F.

Situation 2: Subcooling margin will remain constant.

c. Situation 1: Subcooling margin will increase to saturation then rise in superheat, and retum to normal when CETC output reaches 1200*F.

Situation 2: Subcooling margin will decrease, then stabilizes when the CETC output is smaller than TEN other TCs.

C

4. Situation 1: Subcooling margin will increase to saturation then rise in superheat, and retum to normal when TC output reaches 2300'F.

Situation 2: Subcooling margin will remain constant.

Answer a Exam Level R ca-!M Level Comprehension Faciety: Braidwood ExamDate:

9/14/98 KA: 017 K4.01 RO Value:

3.4 Sao value:

3.7 Section

"SYS RO Group:

1 SROGroup:

1 systemevolution

' In-Core Temperature Monitor System KA Knowledge of in Core Temperature Montor System design feature (s) and or interlock (s) which provide for the following:

Input to subcooling monitors Explanation of Fall high - Since it is initially tha highest, its input will remain active in average until high setpoint reached at An:wer 2300*F. Falllow. subcooling margin will slightly increase as temperature falls and input to average remains valid. When it reaches the 11th highest value, the subcooling margin will stabilize and reamin constant (assuming other 10 inputs do not change),

Reference Title / Facility Reference Number Section/Page Revision L. O.

j Ch pter 34b inadequate Core Cooling Detection 7

5,6 l

I Material Required for Examination 3-l Question Source:

Facility Exam Bank Question Modification Method Significantly Modified I

Question Source comments:

Braidwood 1997 NRc Exam. Difference in el answer choices similar promise in theory, but different wording.

l

. Comment Type comment hy, July 24,1998 4:34:21 PM Page 57 of 127 Prepared by WD Associates, Inc.

I

Question RCFC cperati:ns requirem:nts The following conditions exist on Unit 2:

- RCS Temperature - 342*F

- Pzr pressure - 375 psig

- 2A,2B, and 2D RCFCs are operating in high speed

- Unit 2 RCFC Dry Bulb temperatures are recorded as follows:.

-2A RCFC - 119'F

-2B RCFC - 118'F

-2C RCFC - 127'F

-2D RCFC - 121*F Which of the following identifies the equipment status and actions for the above conditions?

I-What are the MINIMUM requirements for operation for the Reactor Containment Fan Coolers (RCFCs)?

l l

l

c. An additional RCFC must be started because the average of ALL the RCFC temperatures exceeds

~

l the limit.

b. An additional RCFC must be started because ONE of the operating RCFCs temperatures is above l

the limit.

c. NO action is necessary because ALL temperatures are within their appropriate limit.

d.'NO action is necessary because the average temperature of ALL operating RCFCs is below the limit.

Answer d Exam Levd R Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 l

KA: 2.1.32 RO Value:

3.4 sRO value:

3.8 section

SYS RO Group:

1 SRO Group:

1 systemevolution Containment Cooling System

  • KA Ability to explain and apply a5 system limits and precautions.

l '

E;'--

- of Limits on CNMT temperature determined by average of temperatures for OPERATING RCFC outlet temps'.

I Answer Reference Title /Fecility Reference Number Section/Page Revision L O.

RCFC Start up 1BwOP VP-5 U2 Mode 1,2,3 shiftly daily Op surv 2BwCS-0.1-1,1.3 -

l chp 42 Containment Vent system lesson plan 4

6,10a Material Required for Examinatiorn i

l Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Friday, July 24,1998 4:34:21 PM Page 58 of 127 Prepared byWD Associates,Inc.

. Topic j

Question Sequence f:r securing CNMT Spray The following conditions exist on Unit 1:

- A LOCA has occurred

- Transition has been made to BwEP ES-1.3 " Transfer To Cold Leg Recirculation"

- Containment Spray actuated due to high containment pressure

- All systems and components operating as expected What conditions allow for termination of Containment Spray?

a. ONE pump is stopped when containment pressure is less than 15 psig. The other pump is stopped when RWST LO-3 level is reached.
n. ONE pump is stopped when containment pressure is less than 20 psig. The other pump is stopped after it has operated for a period of at least T'WO hours
c. BOTH pumps are stopped when containment pressure is less than 15 psig and have operated for a

~

period of at least TWO hours.

d. BOTH pumps are stopped when contininmek pressure is less than 20 psig and RWST LO-3 level is reached.

Answer c Exam Level B Co9nitive Level Comprehension ~ Faculty: Braidwood ExamDate:

9/14/98 KA: 026 A2.08 RO Value:

3.2 sRO Value:

3.7 Section

SYS RO Group:

2 sROGroup:

1 systenWEvolution Containment Spray System KA Ability to (a) predict the impacts of the following on the Containment Spray' System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation.

Safe securing of containment sprey when t can be done)

Explanation of Answer

Title:

Reference Title / Faculty Reference Number Section/Page Revision L O.

C:ntiinment Spray Schematic CS-1/ CS tefm 3

Loss cf Reactor or Sec Coolant /1BwEP-1 18 WOG-1B Ch 59 Containment Spray sys Lesson plan 6

14 Material Required for Examination Question Source:

New Question Modification Method.

Question Source Comments:

Comment Type Comment te

  • I Friday, July 24,1998 4 34:22 PM Page 59 of 127 Prepared by WD Associates, Inc.

e e

e

~. _.

Question Pumpcperati:nintsrt cks The following conditions exist on Unit 1:

- LOCA is in progress 4

- Containment pressure - 15 psig

- Containment Spray actuated due to high containment pressure

- Containment Spray signal has been reset

-The actions of BwEP ES-1.3 " Transfer To Cold Leg Recirculation" have been completed

- Offsite power is then lost and the D/G output breakers have just closed i

onto ESF buses How are the Containment Spray Pumps re-started?

e. The pumps will auto start 15 seconds following closure of the D/G output breakers.
n. The pumps will auto start 40 seconds following closure of the D/G output breakers.

j i

c. If the operator immediately places the CS & PHASE B ISOL switches for both trains to ACTUATE, the pumps will auto start 15 seconds following closure of the D/G output breakers.

c 4.-If the operator immediately places the PP 1_ TEST switches for both pumps in TEST, the pumps will auto start 40 seconds following closure of the D/G output breakers.

Answer C Esam Level R

% _ a Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 026 A4.01 Ro value:

4.5 Sao value:

4.3 Section

SYS RO Group:

2 SROGroup:

1 Systemevoludon Containment Spray System KA Ability to manually operate and/or monitor in the control room:

CSS controis Explanation of ' if the AUTO aduation input signal is absent and actuation input has been reset, manaul actuation is required Answer to get equiptment restarted following a LOSP.

Reference Title / Facility Reference Number Section/Page Revision L 0.

-Chp 59 Containment spray sys lesson plan 6

8,9 Material Respared for Examination Question Source:

New Question Modification Method:

i Question Source Comments:

Comment Type Comment t

Frid y, July 24,1998 4:34:23 PM Page 60 of 127 Prepared byWD Associates,Inc.

4

Question Charco11 Fitt:rs responsa ta d: lug)

Annunci; tor 0-33-C3, FILTER 1VP05FA TEMPERATURE HIGH, cl rms in thn Control Room whila 1VP02CA CNMT Charcoal Filter Fan is operating. The alarm condition is verified locally.

Which of the following describes the actions taken and/or the system response for the Containment Ventilation System?

a. The deluge valve FP244A will automatically open and the fan will automatically stop.
n. The control room operator will open the deluge valve FP244A and the local operator will then stop the fan.
c. The local operator v/ill open the deluge valve FP244A and the fan will automatically stop.
4. The local operator will open the deluge valve FP244A and the control room operator will then stop the fan.

Answer c Exam Level R cognitive Level Memory Facility: Brakhvood ExamDate:

9/14/98 KA: 027 A4.03 RO Value:

3.3 SRO Value:

3.2 Section

SYS RO Group:

3 SROGroup:

2 SystemEvolution Containment lodine Removal System KA Abihty to manually operate and/or monitor in the control room:

CIRS fans g

Explanation of Operation of fp components associated with charcoal filter is local. But fan trips when deluge system An:wer activated.

Reserence Tme/FacNity Reference Number Section/Page Revision L O.

Filt:r 1VP05FA Temperature High

/18 war 1VP01J-1-A1 1

chp 42 Containment vent 7 purge 4

8 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

- CommentType Comment Friday, July 24,1998 4:34.24 PM Page 62 of 127 Prepared byWD Associates,Inc.

___.___.m Question RWST Purificati:n Loops The following conditions exist:

- Unit 1 - 20% power with load increase in progress

- Unit 2 - MODE 5 following refueling outage

- Unit 2 Spent Fuel Pool Cooling Loop is in service.

- Spent Fuel Pool Pump 1FC01P is OOS.

Which of the following is allowed under this situation?

Alignment and operation of...

a. both Unit 1 PWST purification and Unit 2 RWST purification with flow through the Unit 2 Spent Fuel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.
b. Spent Fuel Pool purification and Unit 1 RWST purification with flow through the Unit 1 Spent Fuel Pool i Demineralizer and Unit 1 Spent Fuel Pool Filter.
c. Unit 2 RWST purification with flow through the Unit 1 Spent Fuel Pool Filter ONLY.
d. Unit 2 RWST purification with flow through the Unit 2 Spent Fuel Pool Demineralizer and Unit 2 Spent Fuel Pool Filter.

j Answer d Exam Level R t. c..; Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: 033 K1.05 RO Value:

2.7 SRO Value:

2.8 Section

SYS RO Group:

2 SROoraup:

2 Systemevolution Spent Fuel Pool Cooling System KA Knowledge of the physical connections and/or cause-effect relationships between Spent Fuel Pool Cooling System and the RWsT Explanation of The lineup allows Unit 2 only to be used for Unit 2 RWST cleanup. Only one unit RWST can be aligned at Answer time due to common input path via Refueling Water Purification Pumps. With the cooling loop inservice only, the Unit's RWST may be aligned through the same Unit's, demin and filter train. Simultaneous use of Demin/ filter for the same Unit's SFP and RWST is NOT allowed due to concems of draining RWST.

Reference Title /Factitty Reference Number Section/Page Revision L O.

S/U purification sys to purify or Reciculate the RWST/ BwOP FC-7 7

Fuel Pool Cooling Schematic FC-1 3

Chp 51 Spent Fuel Pool Cooling And Cleanup 5

3 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment

. ridIy, July 24,1998 4:34:25 PM Page 64 of 127 Prepared byWD Associates,Inc.

f v

r-

Question St:am Dumpinput malfunctirn The following conditior.s exist on Unit 1 L

- Reactor power was 65% when the turbine tripped

- An ATWS occurred

- The reactor tripped 15 seconds later when B reactor trip breaker was locally opened l

- Reactor trip breaker A is failed closed

- RCS Tave - 559'F l

- Pzr pressure - 2255 psig l

- Steamline header pressure - 1100 psig

- No controls other than control rods and boration controls have been operated l

What is the status of the Steam Dump valves?

Stzm Dumps are...

a. modulated open due to steam header pressure.
b. modulated open due to Tave above no-load T' ave.
c. closed because Tave is NOT greater than 3*F above Tref.
d. closed because the dumps are NOT armed.

Answer b Exam Level B Cognieve Level Comprehension Faciuty: Braidwood ExamDate:

9/14/98 MA: o41 A3.02 RO Value:

3.3 sRo value:

3.4 section

SYS no oroup:

3 sRooroup:

3 systenvEvolution Steam Dump System and Turbine Bypass Control MA.

AtMty to monitor automatic operations or the Steam Dump System and Turbine Bypees Control including:

l RCS pressure, RCS temperature, and reactor power

(

s=;' - t of The "A" reactro trip breaker provides the arming signal for dumps on normal reactor trip. Since "A" RTB is still Answer closed, the steam dumps respond to event like load rejection, with C-7 load rejection (10% load decrease in 2 minutes sensed on PT-506) arming the dumps. Since the "B" RTP was opened, the steam dump controller l

does operate on the plant trip controller (No load Tave compared to Auct Hi Tave),

l

' Reference Title / Facility Reference Number section/Page Revisin L 0.

l Steam Dumpst Schematic MS-4 4

Chp 24 Steam Dumps Lesson Plan 7

3,4 Material Required for Examination Question source:

New Question Modification Method I

Question source Comments:

Comment Type Comment l

l t

day, July 24,1998 4:34:26 PM Page 65 of 127 Prepared by WD Associates, Inc.

4

)

ouwton Turbina C;ntrol response to Failed impuls3 Chinn11 The following conditions exist on Unit 1:

- Reactor power 28%

- All systems normal

-Turbine EHC Panel settings:

Turbine REFERENCE DEMAND - 580 MW l

Turbine REFERENCE -330 MW'

-The GO pushbutton is LIT What would be the DEHC System response to a slow failure to ZERO for the turbine impulse pressure chinnel that feeds into the DEHC7 L

- Turbine load will...

i decrease until the difference between REFERENCE and impulse pressure exceeds 30%, the operator would then be alerted to select MANUAL control.

n. decrease until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%,

then load will stabilize in MANUAL control. J

c. increase until the difference between REFERENCE and impulse pressure exceeds 30%, then load will stabilize in MANUAL control.
4. increase until the difference between REFERENCE DEMAND and impulse pressure exceeds 30%,

the operator would then be alerted to select MANUAL control.

Answer c Eaam Level R cognieve Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 045 K1.20 RO Value:

3.4 sRO Vasue:

3.6 section

SYS RO Group:

3 sROoroup:

3 systemevolution Main Turbine Generator System KA Knowledge of the physical connections and/or cause effect relationships between Main Turbine Generator System and the Protection system

. r-4anation of When the difference between actual load and turbine impulse pressure (IMP IN) channel exceeds, circuit Answer AUTO transfer impulse feedback to IMP OUT Reserence Tme/Facally Reference Number section/Page Revision L 0.

TV/GV Control / schematic EHC-3/ Impulse 1

Chp 37a Main turbine Control And Protection 5

52 Material Required for Examination Question source:

New Question Modification Method:

Question source comments:

Comment Type Comment

. Friday, July 24,1996 4:34.26 PM Page 66 of 127 Prepared byWD Associates,Inc.

l

-~

i Question S/G L', vel program -low power The following conditions cxist on Unit 1:

l

- Reactor power 35%

l

- All systems normal What failure would cause a decrease in feedwater flow to all S/Gs?

a. ONE condenser steam dump ONLY fails open.
b. Main steamline pressure PT-507 fails low.
c. ONE HD pump flow control valve ONLY fails open.
4. Main feedwater header pressure PT-508 fails low.'

Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 2.1.7 RO Value:

3.7 SRO Value:

4.4 Section

SYS RO Group:

1 SROGroup:

1 System / Evolution Main Feedwater System j

KA Ability to evaluate plant performance and make operational jud0ments based on operating characteristics, reactor behavior, and instrument Irderpretation.

Explanation of PT-507 fails lovi causes feed pump speed Io decrease which reduces FW pressure. This would initially result Answer 5 a decrease of flow to all S/Gs.

Reference Title / Facility Reference Number Section/Page Revision L 0.

Fw EH controls / schematic EHC-6/ DP 1

6 16 Chp 27 SGWLC MaterialRequired for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Friday, July 24,1998 4:34:27 PM Page 67 of 127 Prepared by WD Associates, Inc.

Question Eff:ct of f:.ilure of S/G stum pressura chann:l The following conditions exist on Unit 1:

- Reactor power 100%-

f

- All systems normal

- FT-512 selected for steam flow input into SGWLC for S/G 1 A What is the initial effect of the pressure transmitter associated with FT-512 failing low?

a. S/G 1 A level will decrease and feed pump speed will decrease,
b. S/G 1 A level will decrease ONLY.
c. S/G 1 A level will increase and feed pump speed will increase.
d. S/G1 A level will increase ONLY.

Answer a - Exam Level R Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 059 K1.04 RO Value:

3.4 sRO Value:

3.4 section

SYS RO Group:

1 sROGroup:

1 systemevolution Main Feedwater System KA Knowledge of the physical connections and/or cause-effect relationships between Main Feedwater System and the following:

S/GS waterlevelcontrol system Explanation of Steam flow is output to summator for FW control system program Delta-P. Delta-P program will decrease Answer causing feed pump speed and FW header pressure to decrease.

Reference Title / Facility Reference Number section/Page Revision L O.

FW EH controls / schematic EHC-6/DP 1

SGWLC schematic FW-2/ 512 loop 0

Chp 27 SGWLC lesson plan 6,

16 MaterialRequired for Examination.

Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment 4

Friday, July 24,1998 4:34:27 PM Page 68 of 127 Prepared byWD Associates,Inc.

'e+

uty m,

vn e-

- - _ = _ _ -.

Questien AFW Startup The following conditions exist on Unit 1:

-The reactor tripped from 40% power

- The trip was caused by RCS loop 1C low flow condition due to undervoltage for RCP 1C bus

- Power Range NIS. channel N42 failed at 100% on the trip

- ESF bus 141 undervoltage occurred

- 1 A D/G automatically started and ACB 1413 is closed

- S/G levels lowest readings were - 19% (A); 25% (B); 22% (C); 20% (D)

What is the status of the Auxiliary Feedwater (AF) Pumps on Unit 1 for these conditions at ONE minute following the trip?

a. Both AF pumps are running.
b. ONLY the 1 A AF pump is running
c. ONLY the 1B AF pump is running.

s;

d. Neither AF Pump is running e

Answer b Exam Leel B Cognmn Level Comprehension FaciNty: Braidwood ExamOate:

9/14/98 KA: 061 A3.01 RO Value:

4.1 SRO Value:

4.2 Section

SYS no oroup:

1 sRooroup:

1 j

SystenvEvolution Auxiliary / Emergency Feedwater System KA Ability to morutor automatic operations of the AuxRiary / Emergency Feedwater System including:

AFW startup and flows Esplanation of SG levels are above AF actuation setpoints and the motor driven AF pump starts on the deteded undervoltage.

Answer

.eforence Title /FacuMy Reference Number Section/Page Revision L 0.

Aux Feedwater System 2

5 Chp 26 AFW sys lesson plan 9

3,5 Chp 9 EDG lesson plan 7

7

~

Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Friday, July 24,1998 4:3428 PM Page 69 of 127 Prepared by WD Associates, Inc.

t

.m.

i l-Question AFW flow requirements ftr cooldown W hich of tha following d:scribss the d: signed MINIMUM AFW pump cnd S/G configurttion necessiry to remova cll of th3 rsector decay hett lord following a re ctor trip from 102% power?

a. The 1 A AF pump supplying 500 gpm to at least ONE S/G with S/G blowdown manually isolated.
h. The 18 AF pump supplying 740 gpm to at least ONE S/G with S/G blowdown in service
c. The 1 A and 1B AF pump supplying 500 gpm total flow to at least TWO S/Gs with S/G blowdown in service.

)

d. The 1 A and 1B AF pump supplying 740 gpm total flow to at least TWO S/Gs with S/G blowdown manually isolated.

Answer a Exam Level B cognitive Level Memory Facility: Braidwood ExamDate:

9/1498 KA: 061 K5.02 RO Value:

3.2 SRo value:

3.6 Section

SYS RO Group:

1 SROGroup:

1 i

System / Evolution Auxiliary / Emergency Feedwater System KA Knowledge of the operationalimplications of the following concepts as they apply to the Auxiliary / Emergency Feedwater System:

Decay heat sources and magnitude

_y - m - _ og j

Answer

' Reference Title / Facility Reference Number

. Section/Page Revision L o.

AFW system lessson plan ch26 9

1,11 MaterialRequired for Examination Question Source:

New Question Modification Method:

Significantly Modified Question Source Comments:

Comanche Peak 11/93 NRC Exam Comment Type Comment Friday, July 24,1996 4:34:29 PM Page 70 of 127 Prepared by WD Associates, Inc.

. - -. -. -.. ~.. -.

. -. ~.

Questson DC bus battiry chirg:r l

The following conditions exist on Unit 1:

l l

- Reactor power - 100%

l l

Investigation has located a ground on the 125 VDC Normal supply to the 1 A D/G from DC iii, What cction is required to transfer DC Control Power to the reserve source?

Tha Reserve power breaker from...

c. DC 111 will be closed after opening the Normal power breaker and the Reserve power l

breaker at the D/G control panel.

n. DC 111 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks at the D/G control panel.
c. DC 112 will be closed after opening the Normal power breaker and the Reserve power breaker at the D/G control panel.
d. DC 112 will be closed after swapping the no-blow link at the Normal and Reserve power fuse blocks l

at the D/G control panel.

Answer b Exam Level B Cognitive Level Memory Faculty: araidwood ExamDate:

9/14/98 KA: 2.1.3o RO Value:

3.9 SRO Value:

3.4 Section

SYS RO Group:

2 SROGroup:

1 SystenWEvolution D.C. Electrical Distribution KA j

Ability to locate and operate components, including local controls.

Explanation of Answer

..aference Title / Faculty Reference Number section/Page Revision L. O.

125 VDC system / schematic DC-1 0

DC Control powertransferfrom Normal to reserve source / BwoP-DC-6A1 51

~Chp 8a 125 VDC lesson plan 6

4,6 Material Required for Examination Question Source:

New Question Modification Method-Question Source Comments:

Comment Type Comment l

l I

I

'4 day, July 24,1996 4:34:30 PM Page 72 of 127 Prepared byWD Associates,Inc.

l Question Sequ:ncing of ESF pumps - SI & SI w LOP l

Unit 1 was being synchroniz:d to the grid wh n tha following occurred:

)

- Trip of 345 KV breakers resulted in deenergizing the SATs

- A steamline break occurred that resulted in containment pressure reaching 20 psig 20 seconds after the D/Gs output breakers have closed l

l When would the 1 A SX pump re-start?

a. Always following start of the 1 A CS Pump.
b. Between the start of the 1 A CV pump and the 1 A RH pump on the SDRA contacts (UV).

l

c. Between the start of 1 A CC Pump and the 1 A AF Pump on the SARA contacts (SI).
d. Coincident with the starting of the 1 A and 1C RCFCs.

Answer C Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:

g/14/98 KA: 064 A3.07 RO Value:

3.6 sRo value:

3.7 section

-SYS RO Group:

2 sRO Group:

2 system / Evolution Emergency Diesel Generators KA Ability to monitor automatic operations of the Emergency Diesel Generators including:

Load sequencing Explanation of The SX pump would be started in this case by the Si signal which is ovenides the UV condition. The SX pump Answer starts in following sequence: CV (0 sec); SI ((5 sec); RH (10sec); CS (15-18 secs, if actuation signal present); CC pumps (20 sec); SX pumps (25 sec); AF 1 A pump (35 sec); CS pump (40 sec, if acutalon signal

)

now present but not present at 18 sec) i i

Reference Title /FacMity Reference Number section/Page Revision L O.

'/G Relayin0/ schematic DG-2/ sequencing order 1

ap 9 EDGs and Aux sys lesson plan 7

7 Chp 20 Essential Service Water sys L::sson plan 7

8 Material Required for Examination

.., Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment I

i "riday, July 24,1996 4:34:31 PM Page 73 of 127 Prepared by WD Associates, Inc.

w%

RCDT operation - effect of CNMT isolati:n The following conditions cxist on Unit 1:

- Unit is in MODE 3

- A cooldown had just been initiated l

- Steam Dump Bypass Interlock control switches have just been taken to BYPASS l

- No other operator actions have been performed l

- The Steam Dump valves fail open and the following parameters are observed:

- RCS temperature - 537'F (A); 539'F (B); 538'F (C); 538'F (D)

.- Pzr pressure - 1820 psig l

- Pzr level - 10%

- S/G pressure - 850 psig (A); 740 psig (B); 800 psig (C); 715 psig (D)

- S/G flow - 1.0 Mlb/hr (A); 1.5 Mlb/hr (B); 1.1 Mlb/hr (C); 1.6 Mlb/hr (D)

- The level in the RCDT has risen to the alarm setpoint (80%) for REACTOR COOLANT DRAIN TANK UNIT 1 LEVEL Hi-LO

. Assuming all systems are functioning correctly, what is the status of the RCDT system?

a. BOTH RCDT pumps are running and flow is, directed to the Holdup Tanks.

u

b. BOTH RCDT pumps are running and flow is recirculated back to the RCDT.
c. ONE RCDT pump is running and flow is directed to the Holdup Tanks, i
d. NEITHER RCDT pump is running and NO flow exists for the system.

Answer d Exam Level B Cognitive Level Comprehension FacWty: Braidwood ExamDate:

9/14/98 KA: 068 A4.04 RO Value:

3.8 sRO value:

3.7 section

SYS' RO Group:

1 sRO Group:

1 i

systenmosution

. Liquid Radwaste System KA Ability to manualy operate and/or monitor in the control room:

Automatic leciation

~

;'--t : of Conditions for steam flow & low RCS temp. actuate Sl. The coincident CNMT Phase A isolation signal Answer isolates RCDT valves out. Closure of valve RE9170 cuses pumps to stop.

Reference Tm/ Facility Reference Number section/Page' Revision L 0.

PRT and RCDT/ schematic RY-4 2

Chp 48a Liquid Red Waste lesson plan 6

11 Ch61 ESFlesson plan 5

7 Malertal Required for Examination Question source:

New Question Modification Method.

Question source Comments:

Comment Type Comment Iday, July 24,1998 4:34:32 PM Page 74 of 127 Prepared by WD Associates, Inc.

. _. _ _ _, ~ _ _ _.. _ _ _ _ _ _ _.

Question CNMT Sump sources of input during n:rmtl operations During et-power operations with systems in th::ir normul clignm:nt, what is a normal source of water to the Containment Floor Sump?

a. Output from the reactor cavity sump.
h. Leakoff from the #2 RCP seals.
c. Leakoff from the reactor vessel flange.
d. Valve packing leakage from the CVCS letdown isolation valves.

Answer a Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:

9/W98 KA: 068 K1.07 Ro Value:

2.7 sRo value:

2.9 section

SYS Ro Qroup:

1 sRooroup:

1 systenWEvolution Liquid Radwaste System KA-Knowledge of the physical connections and/or cause-effect relationships between Uquid Radweste System and the following:

Sources ofliquid wastes for LRS Explanation of Rx cavity sump output to CNMT Floor sump, #2 seals directed to RCDT, RV flange to RCDT, valve leakoffs Answer directed to PRT Reference Title / Facility Reference Number

~ section/Page Revision L o.

Chp 46a Liquid Radwaste System 6

12

~

Material Required for Examination Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment Friday, July 24,1996 4:34:32 PM Page 75 of 127 Prepared byWD Associates,Inc.

Question W:ste Gas Decay Tank Operati:ns When cligned for norm:I op:rztion (BWOP GW-1), how does ths Wrsta Ggs System respond to high pressure sensed at the in-service Gas Decay Tank?

An alarm is generated that...

a. alerts the operator to place an alternate Gas Decay Tank in service.

t:. indicates auto swap of in-service Gas Decay Tank to selected backup Gas Decay Tank, and alerts the operator to align another standby Gas Decay Tank.

c. indicates auto swap of in-service Gas Decay Tank to selected standby Gas Decay Tank and auto swap of standby Gas Decay Tank to new standby Gas Decay Tank.
d. shuts down the Waste Gas Compressors and isolates the in-service Gas Decay Tank.

An:wer b Exam Level R Cognitive Level Memory FacNity: Braidwood ExamDate:

9/14/98 KA: 071 A4.05 RO Value:

2.6 sRO Value:

2.6 section

SYS RO Group:

1 SROGroup:

1 systemevolution Waste Gas Disposal System MA Abitty to manualy operate and/or monitor in the control room:

Gas decay tanks, including valves, indicators, and sample Bne

  • . M n of Indicates auto swap to standby WGD Tank at 95 psig.

Answer Reference Title /FacNity Reference Number Section/Page Revision L O.

Gas waste sys S/U & Operation /

BwOP GW-6 5

GDT sel sw reposition req'd/ OGWO2J-A1 51 Chgp 46 Gas Radwaste syslesson plan 6

6 Material Required for Examination Question source:

New Question ModlScation Method-Question source Comments-Comment Type Comment t

Friday, July 24,1998 4.34:33 PM Page 76 of 127 Prepared by WD Associates, Inc.

Queouen Check Srurce (perati:n Arem Radiation Monitor for Fuel Bldg Fuel Handling incid:nt (ORE-AR055) is being munuzily Chuck Source tested. What is the response when the monitor's CHECK SOURCE (C/S) pushbutton ~is depressed at the RM-23 panel?

The alarm and automatic action output will be blocked, and the RM-23 amber INTLK LED will be lit.

b. The alarm and automatic action output will be blocked, and the RM-23 green AVAIL LED will be lit.
c. The alarm will be actuate when value is reached, and the RM-23 amber INTLK LED will be lit.
4. The alarm will be actuate when value is reached, and the RM-23 red HIGH LED will be lit.

Answer b Exam Level R Cognitive Level Memory Facility: erakiwood ExamOate:

9/14/96 KA: o72 A4.03 RO Value:

3.1 sRo vehm:

3.1 section

SYS RO Group:

1 sROGroup:

1 systemEvolution Area Radiation Monitor'ng System KA AtMty to manually operate and/or monitor in the controi room:

Check source for operability demonstration Explanation of Depressing the C/S blocks the alarm and auto function of the minitor' but the AVAlllitght remains lit.

Answer Reference Tine /Factity Reference Number

/Page Revision L O.

Control Function Channel Check Source Energized /BwOP Mt/PR-11A26 B.1 1

~ Rad Monitor Sys lesson plan chp 49 7

3, 8 Material Required for Examination Question sowce:

New Question Modification Method.

mW source Comments:

Comment Type Comment

~

l Friday, July 24,1996 4:34:33 PM Page 77 of 127 Prepared by WD Anacciates, Inc.

.m Quesmon Less of FHB Overhead Crane rad m:nitor The following conditions exist on Unit'2:

- Refueling operations are in progress While using the Fuel Handling Building Crane to move new fuel into the Spent Fuel Pool, the radiation monitor ORE-AR039, Fuel Handling Building Crane Monitor, goes into alarm. What action is affected?

a. Traverse of the Fuel Handing Building Crane bridge and trolley,
n. Both lowering and raising the Fuel Handing Building Crane hoist.
c. Traverse of the Fuel Handing Building Crane trolley and raising the hoist.
d. Raising the Fuel Handing Building Crane hoist.

Anewer ' d Exam Levd B Cognitive Level Comprehension FacWty: Braidwood ExamDate:

grW98 KA: 072 K3.02 Ro Value:

3.1 sRo value:

3.5. - nan: SYS Ro oroup:

1 sRooroup:

1 systemevduuon Area Radiation Monitoring System j KA Knowledge of the effect that a lose or malfunc60n of the Area Radelion MontortnB System wls have on the following Fuel henden0 operatione g

sc- "n of Rad monitor prevents raisin 0 holst.

Answer 1

Reserence Title / Faculty Reference Number Section/Page Revision L. o.

Chp 49, Radiation Monitors lesson plan 7

4.a.3)

Meterial Required for Examination Question Source:

New Quesuon ModtAcation Method:

Question Source Comments:

Comment Type Comment e4 Nay, July 24,1996 4:34:34 PM Pope 78 of 127 Prepared by V D Associates. inc.

f Question Ev:.luation of eqpt (ffected far slow loss The following conditions exist on Unit 1:

- A unit startup is in progress with reactor power raised above 18%.

- Turbine is at 1800 rpm ready to be synchronized to grid.

- Motor driven feedwater pump is supplying the SIGs with Feed Reg Bypass valves in AUTO.

l

- Steam Dump demand in AUTO at 12%.

l

- Instrument air header pressure begins to slowly drop due to a leak l

f if the leak CANNOT be isolated and instrument air pressure continues to drop, which of the following l

would occur?

l (Assume NO operator action taken.)

l l

a.' AF recirculation flow to the CST would be lost due to AF recirc failing closed, i

b. Pressurizer level would increase due to 1CV121 failing open.
c. The main turbine would auto runback due to Diaphragm Interface Valve.(DIV) opening.
d. RCS temperature would drop to 550*F due to steam dumps failing open.

l Antwer b Exam Level B Cognitive Level Compreh,ension Facility: Braidwood ExamDate:

9/14/98 MA: 078 K3.02 RO Value:

3.4 sRO Value:

3.6 section

SYS RO Group:

3 sRooroup:

3

- systemevolution instrument Air System KA Knowledge of the effect that a loss or malfunction of the Instrument Air System will have on the following:

Systems having pneumatic valves and controle Emptanation of Charging flow goes to maximum due to 1CV121 failing open, and letdown isol 1CV459 & 1CV460 fail closed.

l Answer

'a' is incorrect because both 1 A & 1B AF pump recirc valves fall open. 'c' main turbine not directly affected. 'd' not occur because steam dumps fait closed.

Jerence Title /FacMity Reference Number section/Page Revision L O.

Loss cfinstrument Air Lesson Plan 18woA SEC-4 Table A 52 8

9 l

Chp 53 lA/SAlesson plan Material Required for Examination Question Source:

New Question Modification Method:

l Question Source Comments:

Comment Type Comment i

i

,1 day, July 24,1998 4:34:35 FM Page 80 of 127 Prepared byWD Associates,Inc.

I

Question Eff;ct ofloss of DC - CO2 actuation With the fira prot:ction syst:ms in th:ir norm I clignm:nt, wh:1 is the eff:ct of a loss of DC power?

Loss of DC control power to the...

a. halon control cabinet will cause halon release in the OA Control Room HVAC Room.
b. battery control panel will cause automatic start of the diesel driven fire pump.
c. fire detection system will cause start of the motor driven fire pump.
d. carbon dioxide system will cause the master discharge valve to fail open pressurizing the CO2
header, Answer d Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 086 K4.06 RO Value:

3.0 sRO Value:

3.3 Section

SYS RO Group:

2 SRO Group:

2 system / Evolution Fire Protection System KA Knowledge of Fire Protection System design feature (s) and or interlock (s) which provide for the following:

CO2 Explanation of EMPCs uses DC control power. On loss of power, the master EMPC valves fail open which in turn cause the Answer master discharge / selector valve to open, charging the affected header.

Reference Title / Facility Rsference Number

' Section/Page Revision L O.

Chp 57, Fire Protection System lesson plan 5

8 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Nay, July 24,1998 4:34:36 PM Page 81 of 127 Prepared by WD Associates, Inc.

. - -. -... ~ ~. _. -..

Quesuon Evaluita conditi:ns - unwarranted rod withdrawil The following conditions exist on Unit'1:

- Reactor power is 30%.

)

- Rod controlis in Automatic

- Tref-564*F

- Tave values - 564*F (A); 565'F (B); 565'F (C); 564*F (D)

- Power Range N1 - 31% (N41); 29% (N42),30% (N43); 30% (N44) 1

- Control bank D is at 156 steps.

Which condition would result in continuous rod withdrawal?

Turbine first stage pressure PT-505 fails upscale.

1

b. Power Range channel N41 fails upscale.
c. Loop A Tcold fails downscale.

. 4. Tref signal fails downscale.

Answer a Exam Level B Cognieve Level Comprehension FacMity: Braidwood ExamDate:

9/14/96 KA: 001 AA2.oS RO Value:- 4.4 SRO Vaiue:

4.6 lSection

EPE RO Group:

2 sROGroup:

1 Systemevolution Continuous Rod Withdrawal KA Ability to determine and interpret the fotowin0 as they apply to Continuous Rod Withdrawal:

Uncontrolled rod withdrawal, from available indications Explanation of Input to rod contiel Tref, auctioneered HIGH Tave & Auctioneered high PRNis: PT-505 provides input signal for development of Tref. If it fails high Tref goes to maximum value (581*F) and results in rods being withdrawn to Answer match Tave to Tref. PR failure high compares the rate of change of reactor power to the rate of change of turbine power. Initially high rate of change during failure but rapidly the rate of change falls to zero and so rods may initei!!y begin to insert but quickly stop motion with no more rate of change. Auctioneered high Tave is j

used and Tcold failing low will remove this input (if prevolusly auctioneered high). Tref falling low will cause rods to move inward to match Tave to Tref.

Reference Title / Faculty Reference Number Section/Page Revision L 0.

. Rod control Unit / Schematic RD-2 2

12 20 Chp 28 Rod control sys Lesson Plan Uncontrolled Rod Motion /18wCA ROD -1 6

3 Lcsson plan Malertal Required for Examination Question Source-New Question Modification Method.

Question Source Comments:

Comment Type Comment Friday, July 24,1996 4:34:36 PM Page 62 or 127 Prepared byWD Associates,Inc.

f w

w

Question P/A vs. Group St p C untIrs A Control B:nk D rod w:s dropped from 156 st:ps. Th3 P-A conv:rter w:s NOT z:roed wh n dirccted by the procedure.

S: lect the effect of NOT performing this action?

l

a. While performing the procedure, the C-11 Rod Stop will be received prior to realigning the rod.
n. While performing the procedure, the Rod Insertion Limit Alarm will be received et a lower rod position than required.
c. After the procedure is complete, Bank C control rods will begin insertion at a lower value of Control Bank D.
d. After the procedure is complete, Bank C control rods will begin insertion at a higher value of Control Bank D.

Ansme a Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:

9/1498 KA: 003 AK3.10 RO Value:

3.2 sRo value:

4.2 section

EPE RO Grc up:

2 sROGroup:

1 systenWEvolution Dropped Control Rod

~

KA Knowledge of the reasons for the fo#owing responses as they apply to Dropped Control Rod:

RlL and PDIL g

Explanation of The bank overlap units are bypassed when rods are moved with individual bank selector positions. The P to A Answer converter provides step information to rod position indication including the C-11 circuit. As the individual rod was withdrawn to approximately 67 steps the C11 circuit would sense that bank D was at 223 steps and block outward motion.

Reference Title / Facility Reference Number Section/Page Revision L O.

RD Data logging / rod stops schematic RD-5/RD-1 P/A & C-11 rod stop 0/0 ap 28 Rod Control sys lesson plan 12 1g,10 MaterialRequired for Examination Question Source:

New Question Modification Method:

Editorially Modified Question Source Comments:

D.C. Cook 6/13/1995

- CommentType Comment Friday, July 24,1998 4:34 38 PM Page 84 of 127 Prepared byWD Associates,Inc.

Strbilized RCS t' mperature with fIllure of St:am Dumps e

essetten l

~ On Unit 1, a loss of cli circuliting wit:r pumps his rcsult:d in a racctor trip. All control syst:ms respond cs expected. Significant decay heat causes RCS temperature to increase following the trip.

At what RCS temperature should temperature stabilize?

Tcmperature should stabilize at the saturation temperature for...

L 1030 psig..

n.1092 psig.

c. _1115 psig.

i

. d.1175 psig.

I Answer C Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:

9/14/98 l

NA: 007 EA1.03 RO Value:

4.2 SRO Value:

4.1 Section

EPE

' RO Group:

2 SROGroup:

2 SystenWEvolution '

Reactor Trip

]

.KA Ability to operate and / or monitor the following as they apply to Reactor Trip:

RCs pressure and temperature Explananon of The condenser would NOT be available for steam dumps (either on trip controller or load rejection controller).

Th S/G pressurti would stabilize based on the seocndary PORV opening setpoint normally set at 1115 psig.

. Answer The Main Steam safety valve setting is 1175 psig.

Reference Tuse/ Facility Reference Number Section/Page Revision L 0.

' Steam dumps / schematic MS-4/ C-9 4

Chp 24 Steam dumps lesson plan 7

4 Chp 23 Main steam lesson plan 8

3 Material Required for Examination Question Source?

New Question Modincation Method:

Question Source Comments:

Comment Type Comment I

Friday, July 24,1996 4:34:39 PM Page 86 of 127 Prepared by WD Associates, Inc.

4 l

. - - ~ _ -. - ~.. -

Topic Question Reactor Trip requirements if Unit 2 is operating at full load, which group of conditions will result in an autornatic reactor trip either directly or indirectly?

RCP bus frequency (Hz):56.9 (Bus 156) 57.1(Bus 157) 56.9 (Bus 158) 57.2 (Bus 159)

n. Power range (%):

107 (N41)

'108 (N42) 108 (N43) 109 (N44)

c. PZR pressure (psig): 2375 (PT-455) 2380 (PT-456) 2385 (PT-457) 2380 (PT-458)
d. S/G C NR level (%): 35 (LT-537) 38 (LT-538) 38 (LT-539) 37 (LT-558) l Answw a Exam Level R Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 1

KA: 007 EK2.03 Ro Value:

3.5 sRo value:-

3.6 section

EPE Ro oroup:

2 saooroup:

2 systensvolution Reactor Trip MA Knowledge c"5e interrelations between Reactor Trip and the following:

Reactor trip status panel Explanation of Trp condition RCP UF - 2/4 RCP buses < 57.0 Hz. Other trip setpoints: Rx power - 2/4 >109%; Pzr pressure Answw Titse: 2/4 > 2385 psig Reference Title /FacNity Reference Number sbion/Page Revision L o.

ESF Setpoints/ schematic EF-1/Rx trip 4

2BwEP-0 Reactor Trip or Si lesson plan 3

6 Chp 60b RPS lesson plan 6

4 Material Required for Examination

)

Question source:

New Question Modification Method:

signircantly Modified Question source Comments:

Cornanche Peak 11/94 i

'omment Type Comment Friday, July 24,1998 4:34:40 PM Page 88 of 127 Prepared by WD Associates, Inc.

t

Question Tail-Pipe conditions j

With the RCS ct normal opercting prassure arid t:mperaturo, what la the condition of tha st::am cntaring the PRT at normal conditions, if a PORV opens? (Assume an ideal thermodynamic process).

a. Superheated steam at 239'F.
b. Superheated steam at 222*F.
c. Saturated steam-water mixture at 239'F.

l

d. Saturated steam-water mixture at 222*F.

AnIww d Exam Level R Cognitive Level Application Facility: Braidwood ExamDate:

9/14/98 KA: 008 AK1.01 RO Value:

3.2 SRO Value:

3.7 Section

EPE Ro oroup:

2 SROGroup:

2 Systemmvolution Pressurizer Vapor Space Accident j

KA Knowledge of the operationalimplications of the following concepts as they apply to Pressurtzer Vapor Space Accident:

i Thermodynamics and flow characteristics of open or leaking valves l

Explanation of Nominal PRT pressure 3 psig; Hg = 1154 BTUAb. Saturation temperature 221.9'F. At NOP Pzr pressure 2235 Answw psig with Hg = 1117.7 BTUAb. Therefore PRT conditions are within saturation parameters.

Reference Title / Facility Reference Number

~ Section/Page Revision L O.

Stram Tables 9

25e Chp 14, Pressurizer lesson plan 7

Material Required for Examination Steam Tables Question Source:

New Question Modification Method:

Signircantly Modified Question Scurce Comments:

South Texas 9/95 Comment Type Comment Frid:y, July 24,1998 4:34 41 PM Page 90 of 127 Prepared byWD Associates,Inc.

_~...-e l

l Question Cilculati:n of subcooled mirgin en iconics l:

What tro ths parcmet::rs used to calculata Subcooling Mygin in ths SPDS leonics if only ths 1C RCP cnd 1D RCP are running?

a. RCS wide range pressure from loop C hot leg and core exit thermocouple temperatures.
b. Pressurizer pressure and core exit thermocouple temperatures.
c. RCS wide range pressure from loop A and loop C hot leg, and RCS loop A and loop C hot leg temperatures.
d. Pressurizer pressure and RCS loop A hot leg temperature.

Answer.a Exam Level B C :... la Level Comprehension Facility: Braidwood ExamOate:

9/14/98 KA: 009 EA1.10 RO Value:

3.8 sRO Value:

3.9 section

EPE RO Group:

2 sROGroup:

2 I

systemIEvolution Small Break LOCA KA Ability to operate and / or monitor the following as they apply to Small Break LOCA:

Safety parameter display system Explanation of Answer Reference Title /FaciHty Reference Number Sedion/Page Revision L O.

SPDS Display schematic CX-1/subcooling 1

Ch34b inadequate Core Cooling' O

Lesson plan 7

6 Material Required for Examination Question source:

New Question Modificatlan Method:

Question source Comnents:

Comment Type Comr.wnt 1

iday, July 24,1998 4:34.42 PM Page 91 of 127 Prepared by WD Associates, Inc.

_n. _

Question RCP trip critiria ev-_luiti:n The following conditions exist during performance of BwEP-0.

- Train A ECCS pumps failed to start.

- RCS pressure is 1350 psig.

- Containment pressure of 7 psig.

- Bus 142 has an overcurrent trip on the normal feeder breaker.

Si actuated due to High Containment Pressure.

- The highest critical safety function is Yellow on Heat Sink.

- All other equipment and components operated as expected.

Based on the RCP Trip Criteria, the RCPs should...

a. NOT be stopped because NO Si pumps or Charging Pumps are running.
6. NOT be stopped because RCS pressure is above the trip setpoint.
c. be stopped because Si flow is established to the RCS.
d. be stopped because CC flowpath to the RCP motor oil coolers is isolated.

Answer a Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:

9/14/98 KA: 011 EA1.03 RO Value:

4.0 sRO Value:

4.0 section

EPE RO Group:

2 sROGroup:

1 systanevolution Large Break LOCA KA Ability to operate and / or monitor the following as they apply to Large Break LOCA:

Securing of RCPs Explanation of The trip caiteria is < 1425 psig, with No cooldown in progress, and HHSI flow > 50 gpm or Si flow > 100 gpm.

Answer

'forence Title / Facility Reference Number section/Page Revision L O.

,AS for 1BwEP-0 Trip RCPs 1C 18wEP-0 lesson plan RCP trip criteria 11 2,5 Material Required for Examination

  • Question source:

New Question Modification Method:

Signifcantly Modirled Question source Comments:

Watts Bar 3/3/1995 Comment Type Comment Friday, July 24,1998 4:34:43 PM Page 93 of 127 Prepared by WD Associates, Inc.

.. ~.

. ~ _.

Question Eval 1:ss of cooling flow On a loss of se:I injection to tha RCPs, whnt criteri2 is ustd to d:t:rmina if tha RCPs should be tripped?

a. High temperatures on the RCP seal or bearing outlet temperatures.
b. Time elapsed since loss of seal injection.
e. RCP Thermal Bearing Cooling Water low flow alarms.
d. #1 seal leakoff flow rate decreases to zero.

Answer a Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:

g/14/98 KA: 015 AA2.10 RO Value:

3.7 SRO Value:

3.7 Section

EPE RO Group:

1 SROGroup:

1 Systemevolution Reactor Coolant Pump Malfunctions KA Ability to determine and interpret the following as they apply to Reactor Coolant Purnp Malfunctions:

When to secure RCPs on loss of cooling or sealinjection Explanation of Seal & bearing temperatures are monitored for trip setpoint.

Answer Reference Title / Facility Reference Number Section/Page Revision L O.

Loss cf seal cooling 18wOA RCP-2 54 Losss of Seal Cooling lesson plan 6

4 0

Material Required for Examination Question Source:

New Question Modification Method.

Question Source Comments:

Comment Type

- Comment l

L i

Friday,.!uty 24,1998 4:34:45 PM Page 96 of 127 Prepared byWD Associates,Inc.

4 i

Question Evil of RCP se:1 f'ilure Unit 1 is oper: ting et 100% pow:r whtn ths following clarm is receiv d:

- - RCP SEAL LEAKOFF FLOW LOW (1-7-C3)

. The NSO investigates and reports the following additional information:

- RCP 1 A seal injection flow is 10.7 gpm

- #1 Seal Leakoff Flow on 1 A RCP is 0.4 gpm

- RCP 1 A Seal Water Outlet Temperature is 140*F and STABLE

- RCP 1 A Bearing Outlet Temperature is 145'F and STABLE B sed on the above information, which of.the following events has occurred?

a. RCP 1 A #1 Seal has failed closed
b. RCP 1 A #1 Seal has failed open.
c. RCP 1 A #2 Seal has failed closed.
d. RCP 1 A #2 Seal has failed open.

Answer d Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 MA: 015 AK2.07 RO Value:

2.9 SRO Value:

2.9 Section

EPE RO Group:

1 SROGroup:

1 Systemevolution Reactor Coolant Pump Malfunctions j

KA Knowledge of the interrelations between Reactor Coolant Pump Malfunctions and the following:

RCP seals Explanation of j

i Answer aforence Title / Facility Reference Number Section/Page Revision L. O.

RCP seal Failure /1BwoA RCP-1 SSB 18woA RCP-1 lesson plan 7

5

- MaterialRequired for Examination Question Source:

Facility Exam Bank Question Modification Method:

Editorially Modified Question Source Comments:

Braidwood bank Comment Type Comment I

Friday, July 24,1998 4.34 45 PM Page 97 of 127 Prepared byWD Associates,Inc.

i i

i Question.

VCTlev;ltransmitt:r malfunction Given ths following:

The plan't is'at 90% power with ALL controls in AUTO.

VCT level transmitter, LT-112, fails HIGH causing a letdown diversion.

What will occur if NO operator action is taken?

,VCT level decreases...

a. until Auto makeup starts and maintains VCT level.
b. with NO auto makeup capability and charging suction shifts to RWST.
c. faster than auto makeup input and charging suction shifts to RWST.
d. until charging pumps lose suction and start to cavitate.

Answer d Exam Level B Cognitive Level Application Faclety: Braidwood ExamDate:

s/14/98 KA: 022 AA1.08 Ro Value:

3.4 sao value:

3.3 section

EPE no oraup:

2 saooroup:

'2 systemevolution Loss of Reactor Coolant Makeup 1

KA Ability to operate and / or monitor the fotowmg as they apply to Laos of Reactor Coolant Makeup:

VCT level E ' --n of LT 112 provides for AUTO makeup to the VCT. If No operator action taken, then level will continue to fall until

)

Answer NPSH is lost to the CENT CHG pump (s). Transfer will NOT occur to RWST since both channels are required for swap. An alarm will be generated from LT-185 at 20% level.

Reserence Titie/FacNety Reference Number section/Page Revision L o.

CVCS notes / schematic CV-2/ LT 112 table 3

10 11,14

hp 15a CVCS lesson plan Material Required for Examination Question source:

New Question ModlAcation Method:

Question source Comments:

" CommentType Comment

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4 Friday, July 24.1998 4:34:46 PM Page 98 of 127 Prepared byWD Associates Inc.

Question Tim:;/ amount E-borati:n f:r condition Given the'following efter a racetor trip:

- THREE rods remain withdrawn.

- Due to equipment malfunctions boration is only available from the RWST,

- Charging flow rate 132 gpm.

- RCS boron concentration was 1050 prior to the trip.

- 120 gpm letdown in service.

Of the listed times, which would be minimum acceptable time that boration from the RWST would have to l

occur?

l a.1 Hour

b. 2 Hours
c. 3 Hours l
d. 4 Hours Answer b Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:

9/14/98 j

MA: 024 AA2.06 RO Valuer 3.3 sRO Value:

3.9 7section

EPE RO Group:

1 sROGroup:

1 systemIEvolution Emergency Boration KA Ability to determine and interpret the following as they apply to Emergency Boration:

Amount of boron to add to achieve required SDM Explanation of 1BwEP ES-0.1 requires 3600 gallons boration from RWST for each rod not fully inserted, therefore requiring Answer 10,800 gallons. If net change over is 120 gpm, then required time is 10,800/120 = 90 minutes. Other answers based on counting 2 rods and/or borating from CV-8104 @ 57 gpm with total of 1200 gallons.

Nforence TitleIFaculty Reference Number -

section/Page Revision L O.

JwCA Pri-2 emefgency Boration SSB 1BwoA Pri-21esson plan 1

4,6 H

1BwEP-0 lesson plan 11 3

Material Required for Examin.cJon 1BwEP ES-0.1, page 6 (step 5)

. Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment Friday, July 24,199) 4:34:47 PM Page 99 of 127 Prepared by WD Associates, Inc.

Quesuon Cile of tims(3 saturatirn/ core boiling The following conditions exist on Unit 1

- The plant was shutdown 8% days ago to repair a steam generator tube leak.

- Reactor vessel level is at 397' 1" with Thot at 212*F.

- A loss of RHR. pumps due to cavitation has occurred Which of the following is the smallest aniount of flow that meets the minimum makeup flow required to m:intain current RCS level?

a. 80 gpm i
b. 72 gpm
c. 59 gpm
4. 45 gpm Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 025 AK1.01 RO Value:

3.9 _ sRO Value:

4.3 section

EPE RO Group:

2 sROGroup:

2

)

systemevoluuon Loss of Residual Heat Removal System KA Knowled0e of the operationalimplications of the followi[lg concepts as they apply to 1 aos of Residual H0st Removal System.

i Loos of RHRS during all modes of operation s 'mrn of : 81/2 days is 204 afters shutdown. The curve shows minimum flw at approximately 70 gpm.

1 Answer Reference Title / Facility Refeu.nce Number Section/Page Revleion L. O.

Loss of RH cooling /1BwOA Pfi-10 56 4

1BwOA Pri-10 Lesson plan Material Required for Examination Figure 1BwCA PRI10-1 Question Source:

New Question Modl6 cation Method:

Question Source Comments:

Comment Type Comment 1

Friday, July 24,1998 4:34:47 PM Page 100 of 127 Prepared by WD Associates, Inc.

w.

-_ _-.. -. _ -.. _.. _ ~

I

- Question Alt: mate RCS Cooling The following conditions exist on Unit 2:

MODE 5 operation during normal cooldown RCS temperature - 195* F RCS pressure - 325 psig Train A RH in service, train B RHR tagged out for repairs What is the preferred method of core cooling if a loss of RH cooling occurs?

Alt mate RCS cooling using...

e. bleed and feed using reactor head vents.
b. the S/Gs.
c. normal charging and RHR letdown.
e. Si Pump cold leg injection Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 4

KA: 025 AK3.01 RO Value:

3.1 SRO Value:

3.4 Section

EPE RO Group:

2 SROGroup:

2 Systemevolution Loss of Residual Heat Removal System KA Knowledge of the reasons for the following responses as they apply to Loss of Residual Heat Removal System-

. Shift to altemate flowpath Explanation of Steaming intad/nor,-isolated SGs is the preferred attemate decay heat removal method if the RCS is intact.

Answer Reference Title /FacNity Reference Number SectSn/Page Revision L. O.

s cf RHR Cooling /1BwOA Pri-10 Table A 56 I

.swOAPrl-10 Lesson Plan 4

Material Required for Examination

- Question Source:

New Question Modification Method:

- Question Source Comments:

Comrnent Type Comment l

i Friday, July 24,1998 4:34:48 PM Page 101 of 127 Prepared byWD Associates,Inc.

i

.~

.-,m Question Evaluati n of CCWIrik The following conditions exist on Unit 1:

- The reactor is shutdown.

- RHR is in shutdown cooling.-

l

- RCS temperature is 300*F.

RCS pressure is 160 psig.

- CCW surge tank levelis decreasing What leak locations will produce these indications?

l l

RHR Heat Exchanger

n. Thermal Bearing Heat Exchanger
c. Letdown Heat Exchanger
d. Seal Water Heat Exchanger Answer d Exam Level B Cognitive Levd Comprehension Faciuty: Braidwood ExamDate:

9/14/98 xA: 026 AA1.05 Ro Vdue:

3.1 sRo value:

3.1 section

.EPE Ro Qroup:

1 sRooroup:

1 systenvEvolution Loss of Component Cooling Water; KA Ability to operate and / of monitor the followin0 as they apply to Loos of Component Cooling Water.

The CCWS surge tank, including level control and level alarms, and radiation alarm Emptanation of The seal water HX would be the only location where the CC pressure would be lower than the process fluid Answer pressure. RHR HX approx.165 psig; UD Hx pressure should be approximately 160 psig; & Thermal barrier pressure should be about 160 psig.

Reference Title / Faculty Reference Number section/Page Revision L o.

CCW malfs/1BwCA Pri-6 Att B 56 3wOA Pri-6 lesson plan Att B 6

3 Material Required for Examination Question source:

Facility Exam Bank Question Modification Method:

Significantly Modified Question source Comments:

Zion 7/13/92 Comment Type Comment Friday, July 24.1998 4:34.48 PM Page 102 of 127 Prepared by WD Associates, Inc, l

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f Question Pressure controll:r stIp chInge The following conditions exist on Unit 2:

- Reactor power is 100%

- Pressurizer pressure control is in automatic.

- What is the immediate response of the pressure control system if the Master Pressure Controller setpoint is inadvertently changed to 2330 psig (step change)?

a. PORV RY455A operi and spray valves open.
n. PORV RY455A opens, spray *;alves open, and all heaters energize.
e. Spray valves open and proportional heaters go to minimum.

L

d. Spray valves close and proportional heaters go to maximum.

Answer d Exam Level B Cognidve Level Application Facility: Braidwood ExamDate:

9/1N98

[

KA: 027 AA1.01 RO Value:

4.0 SRO Value:

3.9 Section

EPE RO Group:

1 SROGroup:

2 system / Evolution Pressurizer Pressure Control Malfunction KA Ability to operate and / or monitor the following as they apply to Pressurizer Pressure Control Malfunction:

PZR heaters, sprays, and PORVs

- Explanation of Setting the pot setting higher reduces the ' 'utput from the controller and raises the demanded pressure o

Answer setpoint. This reduction results in spray valve closure & heaters turning fully on.

Reference Title / Facility Reference Number Section/Page Revisio L O.

l Pzr Pressure Controll schematic RY-2/PK.456A in Auto 3

9 30 Chp 14 Pressurizerlesson plan I

MaterialRequired for Examination Question Source:

New Question Modification Method:

Signircantly Modified Question Source Comments:

Calvert Cliffs 11/97 Comment Type Comment l

l t

c iday, July 24,1998 4:34:50 PM Page 104 of 127 Prepared by WD Associates,Inc.

r

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l l

1 Question N:n-Controlling chinn:1 fiilure The following conditions exist on Unit'1:

- Reactor power is 100%.

- All systems are in automatic

- Channel i Pressurizer Pressure Channel (PT-455) was declared inoperable and taken out of service with the appropriate bistables placed in the tripped condition.

- Controlling pressurizer pressure channel (PT-457) fails high Assuming NO operator action, what is the plant response to the channel failure?

e. Both PORVs and both spray valves open resulting in a reactor trip from low pressurizer pressure l

followed by Si actuation.

b. The reactor will trip immediately on high pressure, and safety injection will actuate on low pressure due to spray valve operation.
c. Pressurizer proportional heaters will de-energize and spray valves will open resulting in an OTdT runback prior to tripping, and safety injection will actuate due to low pressurizer pressure.
d. Both PORVs and both spray valves remain closed while pressurizer heaters de-energize.

Answer b Exam t.evel B Cognitive Level Application FacWty: Braidwood ExamDate:

9/14/98 KA: 027 AA2.15 RO Value:

3.7 sRO Value:

4.0 section

EPE RO Group:

1 SROGroup:

2 systmWEvolution Pressurizer Pressure Control Malfunction KA Ability to determine and interpret the folowing as they apply to Presourtter Pressure Control Malfunction-Actions to be taken if PZR preneure instrument falls high Explanadon of TWO PZR pressure channels will have HIGH PZR PRESSURE bistables actauted resulting in the reactor trip.

Anawer The sparys wil have modulated fully open resulting in actual pressure decreasing (PORV 1RY455A would have also opened on the failure of PT-457, but would close when the PZR pressure fell to 2185 psig PT-458 will actaute the low pressure interlock closing the PORV) until Si occurs at 1829 psig.

Reference Title / Facility Reference Number Section/Page Revision L O.

,Pzr Pressure Control / schematic RY-2/ PZR press 3

9 30 Chp 14 Pressurizerlesson plan Material Required for Examination Question Source:

New Question Modification Method:

signiricantly Modird Question Source Comments:

BV 8/91 Comment Type Comment Friday, July 24,1998 4:34:50 PM Page 105 of 127 Prepared byWD Associates,Inc.

~.. - -

..~.-. n - - - - _..- -. -

Quescon Failed lev;l channellow.

The plant is operating et 100% power with cll control syst*ms in AUTO. The following piremsters are noted:

- Letdown Hx outlet flow (FI-132) - 75 gpm

--Charging Headerflow(FI-121) - 87 gpm

- Total seal injection flow (FI-142 -Fi -45) - 33 gpm What is the effect on total seal injection flow initially if controlling Pzr level channel LT-459 fails LOW?

Total sealinjection flow will...

. decrease to O gpm.

a

n. decrease to approximately 20 gpm.
c. remain approximately 33 gpm
4. increase to greater than 40 gpm.

Answer d Enam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 028 AK3,05 -

RO Value:

3.7 sRO value:

4.1 section

EPE RO Group:

3 SROGroup:

3 syseenwevolumen Pressurizer Level Control Malfunction KA Knowledge of the reasons for the following responses as they apply to Pressurtzer Level Control Malfunction:

Adions contained in EOP for PZR level malfunction Empianation of The failure of the level instrument low increases charging flow and charging dicharge header pressure. Since i

' Answer seal injection flow is normally increased by throttling close on CV182 to increase backpressure, the result is the same and seal injection flow will increase.

..sierence TitiefacNity Reference Number section/Page Revision L 0.

CVCS notes / schematic CV-2/cycs ratings 2

18woA inst 2 Att C lesson plan -

9 1

Material Required for Examination

-- Question source:

Facility Exam Bank Question Modification Method:

Significantly Modified Question source Comments:

Braidwood 1996'NRC exam. Modified premise from failed controller to failed level channel. Changed location of correct answer based on different response (increasing flow Instead of decreasing flow).

Comment Type Comment Friday, July 24.1998 4:34:51 PM Page 106 of 127 Prepared by WD Associates, Inc.

I

~ ouestion :

AMS conditi:ns The following conditions exist on Unit 1:

- At t= 0 'sec, Turbine load was decreased below 352.MW (30% power)

At t=240 sec, The running main feedwater pump tripped.

The reactor did NOT trip due equipment malfunction.

- At t=250 sec,. All feedflow indications decrease to 0% flow

- At t=320 sec, All steam generatorlevels dec. ase below 15%.

B* sed on this information, AMS would...

l

a. initiate at t=320 sec.
b. initiate at t=345 sec.
c. initiate at t=360 sec.
4. NOT initiate because C-20 is cleared.

-- Answer _ b Exam Level B C-:. ^ a Level Application Faciuty: Braidwood ExamDate:

9/14/98 KA: 2.4.48 RO Value:

3.5 sRO Value:

3.8 section

EPE RO Group:

2 sROGroup:

1 SystemIEvolution Anticipated Transient Without Scrarc l

i g

Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

Explanation of AMS remains armed for 6 minutes (360 sec) following decrease below 30%(C-20). The actuation sigan! is Answer _

generated after 3/4 SGs level have fallen 3% below the LO-2 (reactor trip) setpoints of 18% for a period of 25 l

seconds. C-20 would clear @ t=360sec. AMS actuation occurs at 320 + 25.= 345 sec.

I Reference Title /FacMity Reference Number Section/Page Revision L O.

'AS/ schematic PN-3/ logic 1 schem.

2 ofip 60b 6

7 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

- Comment Type Comment l

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I I

l Frid y. July 24,1998 4:34:51 PM Page 107 of 127 Prpared by WD Associates. Inc.

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ouestion Ev11uiti:n of SR NIS voltags failure The following conditions exist on Unit 1:

- Reactor startup in progress

-Intermediate power range indication: 2.5E-5 amp N35 & 2.8E-5 amp N36

- SOURCE RANGE PERMISSIVE P-6 permissive light clear

- SOURCE RANGE TRIP ACTIVE permissive light clear

- Source Range Channel N31 High voltage power supply fails to half its normal value What indication (s) would be available to alert the operator to this failure?

a. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate lower than expected.
b. None, until power is lowered below the P-6 setpoint, and then the Source Range N31 indication will indicate higher than expected.
c. Annunciator SR HIGH VOLTAGE FAILURE (1-10-81) will alarm when power exceeds P-10.
d. Annunciator SR HIGH VOLTAGE FAILURE (1-10-B1) will re-flash when the voltage source fails.

An:wer a Exam Level B

' Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 032 AK1.01 RO Value:

2.5 sRO Value:

3.1 section

EPE RO Group:

2 SROGroup:

2 systenWEvolution Loss of Source Range Nuclear Instrumentation KA Knowledge of the operationallmplications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:

Effects of voltage changes on performance

]

Explanation of Based on Gas filled detector curve (Region lil), the number of events collected would drop (counts drop).

)

Answer Alarm and voltage input to SR detector is blocked until both IR NIS fall below the P-6 setpoint.

]

forence Title /FacMity Reference Number Section/Page Revision L O.

sR High Volt Failure /18 WAR 1-10-B1 setpts/ notes 1

Source Range detector / schematic NI-4 4

Chp 31 source range nuclearInst

{

6 2,3,11,12 L:sson plan

- Material Requited for Examination j

Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment Friday, July 24,1998 4:34:52 PM Page 108 of 127 Prepared byWD Associates,Inc.

=.

Question Eval of failed IR chtnn;l on SU The following conditions exists on Unit 2:

- Plant shutdown is in progress.

- All power range channels indicate 6% reactor power.

- Intermediate range channel N-36 fails HIGH.

What is the plant response to this failure?

n. The reactor will trip on high IR flux, and source range trip will reinstate when N-35 decreases below P-6.
b. The reactor will trip on high IR flux, and source range trip will NOT be reinstated.
c. The reactor will NOT trip imrnediately, but will trip when the source range trip is reinstated when N-35 decreases below P-6
d. The reactor will NOT trip, and source range trip will NOT be reinstated.

Answer b Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:

9/14/98 KA: 033 AA2.04 RO Value:

3.2 SRO Value:

3.6 Section

EPE RO Group:

2 SROGroup:

2 System / Evolution Loss of Intermediate Range Nuclear Instrumentation KA Ability to determine and interpret the following as they apply to Loos of intermediate Range Nuclear instrumentation:

Satisfactory overlap between source 4ange, intermediate-ranDe and power-range instrumentation Explanation of Since reactor power is < P-10 setpoint (10% power), the IR trip setpoint at 25% ElCAwill be exceeded Answer resulting in reactor tiip. SR will NOT be reinstated automatically because only one IR channel will fall below P-6 and Two are required to remove P-6.

Reference Title / Facility Reference Number Section/Page Revision L O.

' termediate Rangelschematic NI-3 4

a32 Intermediate range nuclearinst Lesson plan 6

4,8,9,10 Material Required for Examination

. Question Source:

New Question Modification Method:

Signirica'ntty Modified Question Source Comments:

Watts Bar 8/94

  • Comment Type Comment Friday, July 24,1998 4:34:53 PM Page 109 of 127 Prepared by WD Associates, Inc.

i Question Monit:rs f:r S/G Tube leakags The following conditions cxist on Unit 1:

- Reactor power is 75%

-Troubleshooting has commenced due to reduced condenser vacuum with the air ejectors out of service.

- Hogging vacuum pumps are aligned to the main condenser to aid in maintaining vacuum.

What would be an indication of a Steam Generator Tube Leak under these conditions?

a. Increasing radiation level on 1RE-PR027, "SJAE/Giand Steam Exhaust Monitor".
b. Decreasing S/G level for ONE S/G.
c. Increasing feedwater flow to ONE S/G.

i

d. Decreasing charging header flow to RCS.

Answer a Exam Level R Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 037 AA1,02 rto Value:

3.1 SRO Value:

2.9 Section

EPE RO Group:

'2 SROGroup:

2 System /Evoiution Steam Generator Tube Leak KA Ability to operate and / or monitor the following as they Apply to Steam Generator Tube Leak:

Condensate exhaust system Explanation of The Hogger discharge is aligned thmugh the Off Gas header which is monitored by 1RE-PR027.

Answer Reference Title /Fac34ty Reference Number Section/Page Revisio L O.

SGTRlesson plan / BWOA Sec 8 6

4 Ch 49 rad monitors lesson plan 7

14 l

Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment l

Frid:y, July 24,1998 4:34.53 PM Page 110 of 127 Prepared,byWD Associates,Inc.

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Question Loss cf subcooling BwEP-3 "Stum G:nerator Tube Rupture" is being performrd in responsa to a tube rupturo on 20 S/G.

The cooldown has just been completed but the target temperature value selected by the operators was l

higher than that stipulated in the procedure.

What condition could result because of this error?

a. Loss of'RCS subcooling before RCS and ruptured S/G pressures are equalized.

l

b. Increase in pressure of the ruptured S/G with resultant lifting of the S/G Safety Valve.
c. Increase in pressure of the non-ruptured S/Gs with resultant lifting of their S/G Safety Valves.

l

d. Filling the Pressurizer solid during the subsequent depressurization.

Answer a Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:

' g/14/98 KA: 038 EK3.06 RO Value:

4.2 SRO Value:

4.5 Section

EPE RO oroup:

2 SROGroup:

2 system / Evolution Steam Generator Tube Rupture KA Knowledge of the reasons for the following responses as they apply to Steam Generator Tube Rupture:

Actions contained in EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures Explanation of An:wer C

Reference Title / Facility Reference Number Section/Page Revision L O.

SGTR lesson plan 1BwEP-3 12 1

ERG basis Material Required for Examination Question Source:

New Question Modification Method:

Editorially Modified Question Source Comments:

Salem 6/94 Comment Type Comment o

FridIy, July 24,1998 4:34:55 PM Page 112 of 127 Prepared by WD Associates, Inc.

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-..-.~.- -.- -

Question Stiamlin3 isolati:n i

The following conditions cxist on Unit 1;

- The Unit was in MODE 3 at normal operating temperature and pressure prior to the event.

- A faulted steam generator has occurred.

- RCS hot leg temperatures - 547'F (A),544*F (B), 545'F (C), 547'F (D)

- RCS cold leg temperatures - 545'F (A), 530*F (B), 543*F (C),- 545*F (D)

- S/G pressures - 700 psig (A), 635 psig (B),690 psig (C), 705 psig (D)

- S/G flow - 0.85 MLB/hr (B)

-_ Containment pressure (Channel) - 8 psig (1), 7.5 psig (2), 7.5 psig (3), 8 psig (4)

Based on these conditions, a main steam line isolation should..

have occurred because of the low pressure in at least ONE S/G.

m. have occurred because the steamline high negative rate occurred in SIG 18.
c. NOT have occurred because Containment pressure is below the setpoint for the CNMT High-2 pressure signal.
d. NOT have occurred because THREE S/Gs have pressures above the isolation setpoint and do NOT indicate high steam flow.

Answer a Exam Level B Cognitive Levei ~ Application.

Facility: Braidwood ExamDate:

9/14/98 KA: 040 AA1.01 RO Value:

4.6 SRO Value:

4.6 Section

EPE RO Group:

1 SROGroup:

1 SystanfEvolution Steam Une Rupture KA Ablilty to operate and / or monitor the following as they apply to Steam Une Rupture:

Manual and automatic EsFAs initiation Explanation of The steamline isolation signalis generated by the low pressure sensed on 2/3 pressure transmitters in any Answer one SG. CNMT pressues is below the MSLI setpoint of 8.2 psig and steamline negative rate is blocked since initial condition has PZR pressure > P-11.

noserence Tuse/FacNity Reference Number Section/Page Revision L. O.

.ESF SetpointS/ schematic EF-2/ Simline isol 5

Ch 23 Main steam Sys lesson plan 8

5,13,15,16 Ch 61 ESFlesson plan 5

7 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type comment l

Friday, July 24,1998 4:34:55 PM Page 113 of 127 Prepared byWD Associates,Inc.

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

Question Eval of Lsek The following conditions exist on Unit 1 following a trip from 100% power l

- - Pressurizer levelis 0%

l

- Pressurizer pressure is 1500 psig Containment Pressure is 16 psig.

L

- Tcold is 420*F for all loops.

Where is the location of the leak?

a. On one loop RCS cold leg.
n. On a Main Steam Line inside containment.
c. In a Steam Generator Tube.
4. On a feedwater line between FWRV and Associated FWlV,1FWOO9.

Answer b Exam Level B C:. J'.; Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: o40 AK1.06 RO Value:

3.7 sRO Value:

3.8 section

EPE RO Group:

'1 sROGroup:

1 l

systemevolution Steam Line Rupture KA Knowledge of the operationalimplications of the following concepts as they apply to Steam Llne Rup'ture:

High-energy steam line break considerations Explanation of Secondary LOCA not indicated since Tcold is the same in all loops and RCS tcold is not consistent wth given An:wer CNMT pressure for steam / feed break. SGTR notindicated since CNMT pressure is elevated. LOCA condiiton indcated by consistent Tcold, and CNMT pressure increase.

Reference Title / Facility Reference Number section/Page Revisio L O.

1BwEP-0 Reactor Trip or Si lesson plan 3

6,7 1BwEP2 Faulted S?g isolation lesson plan 7

2,4 Material Required for Examination Question source:

New Question Modification Method:

Editorially Modified

' Question source Comments:

St. Lucie 10/13/97

-- Comment Type Comment l

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Friday, July 24,1998 4:34:56 PM Page 114 of 127 Prepared by WD Associates, Inc.

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l eueenen Eval cf conditions l

In cccorda'nce with BwOA SEC-3, " Loss of Condensar Vacuum", which of the following sets of conditions requires the operator to trip the reactor?

I

a. LOW POWER TRIP BLOCKED P-8 annunciator - LIT.

l Turbine load -200 MW Condenser pressure - 5.2 " HgA

b. LOW POWER TRIP BLOCKED P-8 annunciator - LIT Turbine load - 300 MW Condenser pressure - 6.3" HgA
c. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 600 MW Condenser pressure - 7.2" HgA
4. LOW POWER TRIP BLOCKED P-8 annunciator - CLEAR Turbine load - 900 MW Condenser pressure - 7.8" HgA Answer b Exam Level B Cognitive Level Application Facility: Braidwood ExamDate:

9/14/98 MA: 051 AA2.02 RO Value:' 3.9 SRO Value:

4.1 7Section

EPE Ro Group:

1 SROGroup:

1 l

Syelemevoluson Loss of Condenser Vacuum MA Ability to determine and interpret the fotowing as they apply to Loss of Condenser Vacuum:

l Conditions requiring reactor and/or turbine trip P-8 pennissive active below 30% power (annunciator lit). At 480 MW and below, the minimum acceptable Explanation of Answer condenser pressure is 5.5 in HgA. At 600 MW minimum acceptable pressure is 7. 8 in HgA. At 610 MW and greater, minimum acceptable pressure is 8.0 in HG l-

  • ence Titse/ Faculty Reference Number Section/Page Revision L o.

JwCA Ses-3 loss of condenser vaC lesson plan 6

5 Meterial Required for Examination Figure 1BwCA SEC 3-1 Question Source:

New Question Modification Method:

rh=aesant Source Comments:

Comment Type Comment I

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Friday, July 24,1996 4:34:56 PM Page 1155 of 127 Prepared by WD Associates, Inc, t,

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Question identificati:n cf RCP sell LOCNcooldown Select the primtry basis for r pidly depressurizing ths st=m g:nnr:ttors during a Loss of All AC.

l

a. To provide maximum core cooling until power can be restored,
b. To minimize RCS inventory loss from RCP seals.
c. To enhance restoration of S/G level from the diesel driven AF pump.

- c. To increase subcooling of the RCS..

An:wer b Exam Level B Cognitive Level Mernory Facility: Braidwood ExamDate:

9/14/98 KA: 065 EK3 02 RO Value:

4.3 SRO Value:

4.6 Section

EPE RO Group:

1 SROGroup:

1 systemIEvolution Station Blackout KA Knowledge of the reasons for the following responses as they apply to Station Blackout:

Actions contained in EOP for loss of offsite and onsite power Explanation of The rapid cooling allows depressuring the RCS reducing the leak rate via the RCP seals An:wer I

Reference Title / Facility Reference Number Section/Page Revision L O.

I Loss of All AC Power /18wCA 0.0 Caution 2 1B Wog 1B 1BwCA 0.0 lesson plan 4

1

)

l Material Required for Examination C

l Question Source:

New Question Modification Method:

(

Question Source Comments:

l Comment Type Comment i

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I Friday, July 24.1998 4:34.58 PM Page 117 of 127 Prepared by WD Associates, Inc.

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Question '

R: set of sequ ncer l

How would tha sequ:ncer operats if a Safsty injtetion (SI) acturtion occurs whils tha s:quencar is l

sequencing loads in response to an ESF bus undervoltage condition?

l

a. There will be no change in operation; the undervoltage sequence overrides the SI sequence.

y b.' The undervoltage sequencing stops, the sequencer immediately resets and Si loads NOT already running will sequentially start.

e. The undervoltage sequencing stops, all started loads are shed, and Si loads will sequentially start.

i

d. The undervoltage sequencing completes its cycle, then resets to Si mode, and Si loads NOT already l

running will sequentially start.

Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 056 AA1.21 RO Value:

3.3 sRO value:

3.3 section

EPE RO Group:

3 sROGroup:

3 l

system / Evolution Loss of Off-Site Power KA Ability to operate and / or monitor the following as they apply to Loss of Off-Site Power:

Roset of the ESF load sequencers Explanation of The UV sequence is stopped and the SARA sequencing is initiated from step 1.

Answer Reference Title / Facility Reference Number section/Page Revision L O.

DIG Relaying schematic DG-21 SARA 8 SDRA 1

Ch 9 EDG and Aux sys lesson plan 7

7 Ch 4 AC Electrical distribution lesson plan 8

10,16 Ch 61 ESF lesson plan 5

7,8 Material Required for Examination Question source:

New Question Modification Method:

Signiricantly Modified Question source Comments:

Vogtle 5/91 Comment Type Comment Friday, July 24,1996 4:34.58 PM Page 118 of 127 Prepared by WD Associates. Inc.

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Question Eval of clIctric bus status The following conditions exist on Unit 1:

- Bus 141 is powered from its normal source

- D/G 1 A surveillance is being performed with the D/G paralleled to the bus What would occur if a failure of the undervoltage relay results in a sensed undervoltage condition on Bus 1417 l

1

c. SAT feeder breaker ACB 1412 and D/G feeder breaker ACB 1413 remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.
b. SAT feeder breaker ACB 1412 and D/G feeder breaker ACB 1413 will open. After a 10-second delay, ACB 1413 will close and the Safe Shutdown loads will sequence.
c. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The 1

Safe Shutdown loads will sequence normally.

d. SAT feeder breaker ACB 1412 will open but D/G feeder breaker ACB 1413 will remain closed. The Safe Shutdown loads will NOT sequence and CANNOT be manually started from the control room.

Answer d Exam Leve4 B Cognitive Level Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 056 AA2.46 RO Value:

4.2 SRO Value:

4.4 Section

EPE RO Group:

3 sROGroup:

3 systenWEvolution Loss of Off-Site Power A

Ability to determine and interpret the following as they apply to Loss of Off. Site Power:

That the ED/Gs have started automatically and that the bus tie breakers are closed Explanation of On sensed UV, the SAT feeder breaker opens (and alternate feeder breaker would also have opened if closed)

Answer and the control switches for the safe shutdown loads will be locked out.

Reference Title / Facility Reference Number Section/Page Revision L O.

Ch 4 AC Electrical Distribution 8

10,16 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment l

Frid:y, July 24.1998 4:34:59 PM Page 119 of 127 Prepared by WD Associates. Inc.

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i Eqpt affected cn bus loss On Unit 1 power is lost to 120 VAC Instrum::nt Bus 111 How are the ESF and Safe Shutdown loads affected?

a. "A" Train ESF loads will NOT load on an SI signal, but Safe Shutdown loads will load on a UN signal.

"B" Train loads are NOT affected,

b. A" Train ESF loads will load on an SI signal, but Safe Shutdown loads will NOT load on a UN signal.

"B" Train loads are NOT affected.

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c. "A" Train ESF loads will NOT load on an SI signal, and Sa% Shutdown loads will NOT load on a UN signal.

"B" Train loads are NOT affected.

d. "A" Train AND "B" Train ESF loads will NOT load on an SI signal, but Safe Shutdown loads will load on a UN signal.

Answer C Exam Level B C: lxLevel Comprehension Facility: Braidwood ExamDate:

9/14/98 KA: 067 AA2.19 RO Value:

4.0 sRO Value!

4.3 ~ Section: EPE RO Group:

1 SROGroup:

1 systemevolution Loss of Vital AC Instrument Bus KA Ability to determine and interpret the following as they apply to Loss of Vital AC instrument Bus:

The plant automatic actions that wit occur on the loss of a vital ac electricalinstrument bus Explanation of Answer Reference Title / Facility Reference Number Section/Page Revision L. O.

'9woA Elec 2 Loss ofinst bus Table A 7

sti 60a SSPS lesson plan 3

11 18woA elec 2 lesson plan 6

3,5 I and C system notes I&C1 Material Required for Examination

  • Question Source:

New Question Modification Method:

- Question Source Comments:

Comment Type Comment i

Asy, July 24,1998 4:34.59 PM Page 120 of 127 Prepared byWD Associates,Inc.

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

Question Operati:ns required for transfIr S:: lect the method used for transfcrring controls to tha remots shutdown pin:Is PLO4/05J.

Placing applicable transfer switches in LOCAL on RSP.

b. Opening the isolation switches in the Auxiliary Electric Room.
e. Deenergizing normal control power to individual controls.
d. Taking local controls out of the PULL-TO-LOCK position.

Answer a Exarn Level B cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 KA: osa AA1.21 RO Value:

3.9 SRO Value:

4.1 Section

EPE RO Group:

1 SROGroup:

1 SystenWEvolution Control Room Evacuation KA Ability to operate and / or monitor the following as they apply to Control Room Evacuation:

Transfer of controls from control room to shutdown panel or local control Explanation of An:wer Reference Title / Facility Reference Number Section/Page Revisio L O.

RSP PLO4/5J/ schematic PN-1 2

Control Room Inaccessbility 18wOA Pri-5 lesson plan Att. A 578 Ch 62 Remote shutdown Panel Lesson plan 3

3,4 Material Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comment J

Friday, July 24,1998 4:35.00 PM Page 121 of 127 Prepared by WD Associates,Inc.

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euestion M: Jar ccti:n categories j

When ina'dequ;.ta cor:3 cooling exists', which of tha following sats of cctions ststr

% nrop:r s:quence of the major action categories to be performed in accordance with BwFR-C.1, "Ph Y E TO INADEQUATE CORE COOLING", for removing decay heat from the core?

a. Reinitiation of safety injection; RCP restart; rapid secondary depressurization.
m. Reinitiation of safety injection; rapid secondary depressurization; RCP restart.

l.

' e. RCP restart; reinitiation of safety injection; rapid secondary depressurization.

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d. RCP restart; rapid secondary depressurization; reinitiation of safety injection.

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Answer b Exam Level B Cognitive Level Comprehension Facility: Braidwood ExamDate:

IW14/98 l

KA: 074 EK1.03 RO Value:

4.5 SRO Value:

4.9 Section

EPE RO Group:

1 SROGroup:

1 systenWEvolution inadequate Core Cooling KA Knowledge of the operationallmplications of the following concepts as they apply to inadequate Core Cooling:

Processes for removing decay heat from the core I

. Explanation of An:wer j

1 Reference Title / Facility Reference Number

  • Section/Page.

Revisio L O.

Function Restoration Procedures BwFR-C.1, C.2, b.

5 2,3 T

C.3 lesson plan Material Required for Examinatbn Question Source:

New Question Modification Method:

Editorially Modified Question Source Comments:

VC Summer 5/94 Comment Type Comment l.-

l c iday, July 24,1996 4:35:00 PM Page 122 of 127 Prepared by WD Associates, Inc.

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Question Actions for reducing activity High coolint activity his been d:t ct:d and ch:mistry has d:termin:d that it is dus to corrosion product cctivation.

dentify the effect of placing the cation demineralizer in service.

i The cation demineralizer..

c. will remove lithium so it should NOT be used in this condition.

j

b. will cause the activity level to decrease as soon as it is placed in service.
e. is NOT efiective in removing corrosion product activity.
d. is less offective than the mixed bed demineralizer so it is placed in ser. ice ONLY if decontamination factor is less than 10.

Answer b Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate 9/14/98 KA: 076 AA2.02 RO Value:

2.8 SRO Value:

3.4 Section

EPE RO Group:

1 SRO GroNp:

1 system / Evolution High Reactor Coolant Activity KA Ability to determine and interpret the following as tney apply to High Reactor Coolant Activity:

Corrective actions required for high fission product activity in RCs Explanation of The cation demin is highly effective in removing corrosion products from the coolant.

Answer Reference Title / Facility Reference Number hection/Page Revision L O.

i BwOP CV-8 1BwOA Pri-4 High coolant Activity lesson plan 1

4,5 ch 15a CVCS lesson plan 10 4

.aterial Required for Examination Question Source:

New Question Modification Method:

Question Source Comments:

Comment Type Comnwnt Friday, July 24,1998 4:35:01 PM Page 123 of 127 Prepared byWD Associates,Inc.

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intirlocks affecting reestiblishm nt of feed The following conditions exist on Unit ~1:

- Reactor power was 8% prior to the event below.

A failure in the feedwater control system caused ONE S/G level to exceed P-14.

-The main turbine tripped.

- S/G levels have returned to their normal level range

-The Startup FW Pump is running What are all the conditions that would have to be met to feed the S/Gs using the FWO34's Feedwater Tempering Flow Control valves?

a. The FW lsolation Aux Relays would have to be reset and FWO35 Feedwater Tempering isol valves

. opened.

b. The reactor trip breakers would have to be cycled, the FW lsolation Aux Relays would have to be l

reset and FWO35 Feedwater Tempering isol valves opened.

l

c. The FW lsolation Main Relays and Aux Relays would have to be reset and FWO35 Feedwater Tempering Isol valves opened.
4. The reactor trip breakers would have to be cycled and FW isolation Main Relays and Aux Relays reset and FWO35 Feedwater Tempering isol valves opened.

i Answer a Exam Level B Cog tiveLevel Application Facility: Braidwood ExamDate:

9/14/98 KA: E05 EK2.1 RO Value:~ 3.7 sa0 value:

3.9 section

EPE RO Group:

2 sROGroup:

2 l

systenWEvolution Loss of Secondary Heat Sink KA Knowledge of the interrelations between Loss of Secondary Heat Sink and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic j

and manuel features.

f Explanation of The P-14 dpei, once clear, only malnaltns FWI signal via the FW lsol Aux relays if NO reactro trip signalis Answer present. So reseting the FW lsolation Aux relay allows opeing of FWO35s (normal feed path at low power) and i

throttling of FWO34s

~

l Reference Title /Facally Reference Number section/Page Revision L O.

ESF setpoints/ schematic EF-2/ reset FWI 5

l Feedwater Simple /SGWLC FW-1,2/ reset FWI O

6 4,7,8 Ch 61 ESF lesson plan Material Required for Examination Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment l

Friday, July 24,1996 4-35:02 PM Pa0e 124 of 127 Prepared by WD Associates. Inc.

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Topic th M Identification of heat rem: val process The following conditions exist on Unit 1:

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- A leak developed on the RCS loop C flow instrument piping.

~

- Coincident with the RCS leak, on the reactor trip a S/G PORV failed open and was later isolated.

- FR-P.1 was entered to due to an ORANGE PATH condition.

l

- Si actuated and has been reset.

- All RCPs are stopped

- Conditions required to support an RCP start are met.

l What is the basis for operation of a RCP7 Under the current conditions starting the RCP will...

a. cause excessive thermal stresses in the stagnant loops.
6. cause a pressure surge that will aggravate the PTS condition.
e. provide mixing of the ECCS injection flow thsreby decreasing the likelihood of PTS.

l

d. increase the RCS cooldown rate thereby increase the likelihood of PTS.

Answer C Exam Level B c:. ^'..Levet Comprehension ~ Facility: Braidwood ExamDate:

9/14/96 KA: E06 EK2.2 RO Value:

3.6 sRO Value:

4.0. section

EPE RO Group:

1 sROGroup:

1 systanIEvolution

Title:

Pressurized Thermal Shock KA statement:

Knowledge of the interrelations between Pressurtzed Thermal Shock snd the following:

Facility's heat removal systems, including primary coolant. emergency coolant. the decay heat removal systems. and relations between the proper operation of these systems to the operation of the facility.,

Explanation of Answer Reference Title / Facility Reference Number section/Page Revisin L O.

FRP 1BwFR P.1,2, lesson plan 4

3,4 Status Trees ST-l/ Integrity l

Material Required for Examination Question source:

New Question Modification Method:

(

Question source Comments:

Comment Type Comment "e

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' day, July 24.1996 4:35:02 PM Page 125 of 127 Prepared by WD Associates, Inc.

Question Natural Circ conditi:ns and limits Why is it import nt to run the CRDM Wnt frns wh n performing a natural circuintion cooldown?

a. Aids the operator in maintaining subcooling in the ~ reactor vessel head.

I

b. Aids in' natural circulation flow through the RCS head region.
c. Minimizes stresses on the reactor vessel heaci due to uneven cooldown.
d. Aids in natural circulation flow through the RCS.

Answer a Exam Level B Cognitive Level Memory Facility: Braidwood ExamDate:

9/14/98 MA: E00 EK3.1 RO Value:

3.3 sRo value:

3.6 section

EPE Ro oroup:

1 sRooroup:

1 systenWEvolution Natural Circulation Operations KA Knowledge of the reasons for the followin0 responses as they apply to Natural Circulation Operations:

Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating firnitations and reasons for these operating characteristics.

Explanation of Answer Reference Title / Facility Reference Number section/Page Revision L O.

18wEP -0 Reactor Trip or SI Lesson plan 11 3,4,6 C

Material Required for Examination Question source:

New Question Modification Method:

Question source Comments:

Comment Type Comment l

i Friday, July 24,1998 4.35:03 PM Page 126 of 127 Prepared by WD Associates, Inc.

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Question RIsson forrapid S/G d:pressurizati n Why are the S/Gs d:pr:ssurized to less thin 670 psig according to BwCA-1.1, " Loss of Em:rg:ncy Coolant Recirculation'"?

To allow maximum AFW flow to the S/Gs.

b. To ensure adequate subcooling for restart of the RCPs.

l

c. To set up conditions for controlled injection to the RCS from the accumulators.
4. To decrease RCS temperature and pressure which reduces break flow in a LO'CA condition.

Answw C Exam Level B Cognitive Level Memory Facety: eraidwood ExamDate:

9/14/98 KA: E11 EA1.1 RO Value:

3.9 sRo value:

4.0 section

EPE RO Group:

2 sRooroup:

2 systenWEvolution Loss of Emegency Coolant Recirculation KA Ability to operate and / or monitor the followith as they apply to Loss of Emergency Coolant Recirculation:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

  • - ' :":: of The concem is maximizing cooling volumes that supply water to RCS. By cooling RCS, depressurization of Answer RCS ca'i be initiated (while maintaining,subcooling) to the point where the Si accumulators inject their volumes into the RCS.

).

' M ion /Page Revision L. O.

Reference Title /FacMity Reference Number Loss of Emergency Coolant Recirc/1BwCA 1.1 1B WOG 1B 18wCA 1.1 and 1.2 lesson plan

.7 3

2 Material Required for Examination Question source:

New Question Modification Method:

Editorially Modified Question source Comments:

South Texas 9/92 comment Type Comment

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E Friday, July 24,1998 41.o4 PM Page 127 of 127 Prepared byWD Associates,Inc.

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