ML20195H796
| ML20195H796 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/14/1999 |
| From: | Rauch K SOUTHERN CALIFORNIA EDISON CO. |
| To: | Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20195H730 | List: |
| References | |
| NUDOCS 9906170125 | |
| Download: ML20195H796 (145) | |
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$ OUI 54tRN CAllf 0RNIA EDISON .
An EDISON INTIENATIOL 'empany January 14,1999 i
John Pellet USNRC !
Region IV
. Division of Reactor Safety Chief, Operations Branch 611 Ryan Plaza Drive
, Suite 400 Arlington, TX 76011-8064 l
Dear Mr. Pellet:
Please find, enclosed in a separate sealed envelope, the sample plans for the RO and SRO retake exam scheduled to be administered on March 12,1999. When you are ready to make any comment, please call me at 949-368-8201.
Sincerely, U.A.'X Kurt Rauch Supervisor Operators Training San Onofre Nuclear Generating Station j
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9906170125 990611 PDR ADOCK 05000361 V PDR .,
cc: J. Murray P. O. Ilox 128 San Clemente CA 92674-0128
Facility San Onofre 2 & 3 Date of Exam 03/12/99 Exam Level: SRO Tier Group K/A Category Points Point Total K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
- 1. 1 5 4 5 1l$$il ihiii i@!!! 5 5 _ , J 24 Emergency 2 3 3 3 $$$ $$$$ i!@$ 2 5 6%3!!!$2 16
& Abnormal 3 1 1 Es$N N!!!ili N!!!sA 1 1 EAfM$$iif 4 Plant sig gang sRF "dt g Evolutions Tier Totals 8 8 9 hh @hih 8 11 hhhh 44 1 2 1 2 2 3 1 2 2 2 2 19
- 2. Plant 2 2 1 2 2 2 1 2 1 2 2 17 3 1 1 1 3 Systems Tier Totals 4 2 5 5 5 2 4 4 4 4 39
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 4 4 4 5 17 i
Note: Attempt to distribute topics among all K/A Categories: select at least one topic from every K/A category within each tier. i Actual point totals must match those specified in the table.
Select topics from many systems: avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
Systems / evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category / tier.
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San Onofre . .
Exam t Fccility 2&3 Date: March 12,1999 Level: SRO
! CateDory KA # KA Topic Imp. Points
! C:nduct of Operations 2.1.1 Knowledge of conduct of operations requirements. 3.8 1 l 2.1.11 Knowledge of <1 hr Tech Spec action statements 3.8 1 l l
2.1.24 Ability to obtain and interpret electrical and mechanical drawings. 3.1 1 Ability to recognize indications for system operating parameters 2.1.33 which are entry-level conditions for Tech Specs. 4.0 1 Total 4 Equipment Control 2.2.12 Knowledge of sunreillance procedures. 3.4 1 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 1 2.2.27 Knowledge of the refueling process. 3.5 1 2.2.31 Knowledge of SRO fuel handling responsibilities. 3.8 1 Total 4 Knowledge of 10 CFR: 20 and related facility radiation control Radiation Control 2.3.1 requirements. 3.0 1 2.3.2 Knowledge of facility ALARA program. 2.9 1 2.3.9 Knowledge of the process for performing a containment purge. 3.4 1 2.3.11 Ability to control radiation releases. 3.2 1 Total 4 Emergency Procedures 2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.6 1 and Plan 2.4.14 Knowledge of general guidelines for EOP flowchart use. 3.9 1 2.4.29 Knowledge of the emergency plan. 4.0 1 2.4.46 Ability to verify that the alarms are consistent with plant conditions. 3.6 1 Ability to perform without reference to procedures those actions that 2.4.49 require immediate operation of systems component and controls. 4.0 1 Total 5 Tirr 3 TarDet Point Total (RO/SRO) 17 I
I
Facility San Onofre 2&3 Date of Exam: 03/12/99 Exam Level: RO Tier Group K/A Category Points Point Total K1 K2 K3 K4 K5 K6 A1 A2 A4 G 1.
Emergency 2 3
4 1
4 3
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TT!? 3 Evolutions Tota s 7 6 7 6 10 36 1 2 2 2 2 3 2 2 3 3l2l 23
- 2. Plant 2 2 2 3 2 2 1 2 3 1 l2l 20 Systems 3 Tier 1 1 1 1 2 1 l1 l 8 Totals 5 4 6 5 5 3 5 '8 5 5 51
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 l Cat 4 3 3 3 l 4 13 l
Note: -
Attempt to distribute topics among all K/A Categories: select at least one topic from every K/A category within each tier.
Actual point totals must match those specified in the table.
Select topics from many systems: avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
Systems / evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category / tier.
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ES-401 G:n:ric Knowledg3 c.nd Abilitlis Outlins (Tier 3) ES-401-5 San Onofre Exam FIcility 2&3 Date: March 12,1999 Level: RO Category KA # KA Topic imp. Points Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements. 3.8 1 2.1.11 Knowledge of <1 hr Tech Spec action statements. 3.8 1 2.1.24 Ability to obtain and interpret electrical and mechanical drawings. 3.1 1 Total 3 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3.4 1 2.2.22 Knowledge of limiting conditions for operations and safety hmits. 4.1 1 2.2.27 Knowledge of the refueling process. 3.5 1 Total 3 Knowledge of 10 CFR: 20 and related facility radiation control Radiation Control 2.3.1 requirements. 3.0 1 2.3.2 Knowledge of facility ALARA program. 2.9 1 2.3.9 Knowledge of the process for performing a containment purge. 3.4 1 Total 3 Emergency Procedures 2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.6 1 and Plan 2.4.14 Knowledge of general guidelines for EOP flowchart use. 3.9 1 2.4.29 Knowledge of the emergency plan. 4.0 1 2.4.46 Ability to verify that the alarms are consistent with plant conditions. 3.6 1 Total 4 Tier 3 Target Point Total (RO/SRO) 13 l
49
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1 I
I COMPOSITE XRC EXAM KEY kOib
COMBINEDEXAMINA TION ANSWER KEY.
1999 NRC RE-TAKENRC EXAM' Date Administered... .... 4/16/99 Prepared By................. ' Lynn Sanders . . .
Training Program.......... License Operator initial !
Encode Number..........
Approved By..............
CATEGORY POINTS .
- NRC Re-take . . Total 100.0 '
t' Question #1 Given the following plant conditions:
. Unit 2 is operating at 100% power All CEAs are fully withdrawn to the Upper Electrical Limit RSPT#1 for CEA 46 to CEAC #1 reads 140" Which CPC/CEAC annunciator display light should be illuminated?
. A. CEAC FAIL.
B. CEA DEV.
C. CEAC INOP.
D. CEAC SENS FAIL Answer B Exam Level ' B Cognitive Level Memory Facihty San Onofre 2 & 3 Exam Date 4/107 Tier: (1) 001 ak2 05 Rod moton lights RO Group: 2 SRO Grouo- 1 RO K/A 2.9 SRO K/A 31 Reference Title Facihty Reference Number Sector Page Revision Learning Obj.
Core Protection /CEAC SO23-3-2.13 Att 10 107 10 Reference Title Operation Material Required for Examination Ouestion Source: New l
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Question #2 The following plant conditions exist:
- The plant has tripped All systems actuated as expected with the exception of the following:
- CEAs 40 and 41 are stuck fully withdrawn
- The operating charging pump has inpped on a loss of suction pressure
- Operators are unab:e to start any charging pumps Which of the following operator actions is procedurally required under these conditions?
A. Lower RCS pressure and borate via HPSt.
B. Borate via gravity feed suction path.
O initiate RCS cooldown and initiate SIAS.
D. Use auxiliary spray and borate.
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 001 k4.05 Boration and Dilution RO Group: 1 SRO Group- 1 RO K/A 3.9 SRO K/A3.9 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Emergency Boration 8 023-13-11 5 4 6552 Material Required for Examination .
Question Source: New l 1
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l Question #3 l i
1 Which one of the following is the reason for not starting the fourth Reactor Coolant Pump until RCS temperature is greater than 500 degrees Fahrenheit?
I 4
A. To prevent exceeding RCS heatup rate limits.
B. To prevent excessive RCP starting currents.
C. To prevent Steam Generr. tor tube stresses.
D. To prevent core uplift.
Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:( 2) 002 K6.02 RCP RO Group: 2 SRO Group: 2 RO K/A 3.6 SRO K/A 3.8 Reference Title Facility Reference Number Section Page Revision Learning Obj.
- Plant S/U from CSD to HSB SO23-5-1.3 Att.16 118 19 664g 1
Material Required for Examination Question Source: New j I
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r-Question #4 he following conditions exist:
Unit 2 at 850'o power.
Recovery of a dropped CEA (#20) is in progress.
Group 6 is at 149 inches withdrawn.
CEA #20 (a Group 6 CEA) is at 100 inches withdrawn.
CEA #1 (a Group 2 CEA) drops fully into the core.
Which of the following is/are the correct required action (s)?
A. Continue realigning CEA # 20, then align CEA # 1.
B. Realign CEA # 1, then continue aligning CEA # 20.
- C. Manually trip the reactor.
D. Initiate a Rapid Downpower.
Ans.rr C E <am Level D Cognit.ve Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/1699 Tier:(1) 003 ak t.03 Relationship of reactivity and reactor power to RO Group. 2 SRO Group: 1 rod rnotion.
RO K/A 3.5 SRO K/A 3.8 Reference Title Facihty Reference Number Section Page Revision Learning 00.
Misaugned CEA SO2313-13 4 4 6565 Material Requin d for Examination Question Source: New
' Question #5 Given the following Unit 2 conditions:
Reactor tripped from 100% power Pressurizer pressure - 1870 psia
- Containment pressure - 3.8 psig To where is RCP bleedoff Dow being directed?
A. The VCT.
B. De Quench Tank.
C. The Containment Sump.
D. The RCDT.
Answer 8 Exarn Level B CognitiveLevel Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 003 ke 04 Containment isolation valves af f acting RO Group: 1 SRO Group: 1 ogsatvin.
RO K/A 2.8 SRO K/A 3.1 Reference Title Faciht'/ Reference Number Secten Page Revision Learning Obj.
CVCS PalD 40124A 23 9210 Material Required for Examination Question Source: NRC 11/98 1
Question #6 Given the following plant conditions on Unit 3:
- Plant is in a normal full power alignment Pressurizer levelis 43% !
Pressurizer level setpoint is 48%
Which of the following is the expected automatic response of the CVCS system?
A. Three charging pumps in service and letdown flow at maximum.
B. One charging pump in service and letdown flow at minimum.
C. One charging pump in service and letdown flow at maximum.
D. Three charging pumps in service and letdown flow at minimum.
Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2; 004 At 14 Ptr pressure and level RO Group: 1 SRO Group: 1 i RO K/A 39 SRO K/A 4.1 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Pressunzer Pressure SO23-3-1.10 Att. 2 18 8 and Level Control 6706
~
l Material Required for Examination Question Source: Bank 1
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Question #7 The plant is at 75% power when a new Purification Demineralizer is placed in service. Which of the following will occur if the baron saturation of this demineralizer is incomplete?
A. T-ave will increase.
B. Reactor power will decrease.
C. Lithium concentration will go up.
l D. Ixtdown flowrate will decrease.
Answer A Exam Level B Cognitive Level Ccmprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 l
Tier: (2) 004 k5.15 Boron and control reactivity etfacts as they RO Group: 1 SRO Group: 1 l relate to MTC, RO K/A 3.3 SRO K/A 3.5 Reference Title Facility Reference Number Section Page Revisicn Learning Obj.
RCS Fonfication av.d SO23 3-2.4 Att. 6 36 10 Deborating lon 67}7 1 j
Enchanger Operation
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l Material Required for Examination ,
Question Source: New 1
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1 Question #8
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[. Given the following plant conditions: I Plant is at 100% power, all rods out 1 Subsequently, CEA 3 (SD Bank A) drops into the core
)
Which of the following is the reason for reactor power to be reduced below 90% within one I hour?
A. To minimize radial power peaking.
B. -To prevent adverse Axial Shape index. ,
l C. To prevent a CPC generated Reactor Trip.
D. To ensure Transient insertion Limits are not exceeded.
Answer A Exam Level 6 Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (11 0".0 akt06 Bases for power hmit for rod misalignment. RO Group: 1 SRO Group: 1 RO K/A 2.9 SRO K/A 3.6
]
Reference Title Facihty Reference Number Section Page Revision Learning Ott Technical Reactivity Control Systems LCS 3 3-1.105,7 Specifications 105 6565 Material Required for Examination Question Source: New
Question #9 A_ hot leg vent is required whenever the Steam Generator Nozzle Dams are installed. Which of the following states a reason for this if a loss of Shutdown Cooling (SDC) were to occur?
A. To prevent steam buildup in the hot leg which could cause a loss of natural circulation.
B. To prevent steam buildup in the hot leg which will ultimately collapse, causing severe water hammer.
C. To prevent RCS pressurization leading to a failure of the cold leg nozzle dam and potential core uncovery.
D. To prevent RCS pressurization from causing an erroneous Draindown 12 vel Monitoring System (DLMS) indication.
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 005 k3.01 RCS RO Group: 3 SRO Group: 3 RO K/A 39 SRO K/A 3.0 Reference Title Fac ht', Reference Number Section Page Revision Learning Cbj.
Oraining the RCS SO23-31.8 Att. 71 159 13 3366 Material Required for Examination Question Source: New 1
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Question #10 ,
, i An RCS HOT LEG break has just occurred on Unit 2.
l What would be the result if the EOI steps to initiate simultaneous hot / cold leg injection were performed immediately following the LOCA diagnosis? i A. Inadequate Core Cooling due to the loss of Safety injection flow out of the break.
B. The HPSI pumps would reach mnout conditions.
C. Boration flow would be inadequate to maintain Shutdown Margin requirements. l D. Injection flow through the core would be stopped. l l
l Answer A- Exam !.evel 8 Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 i Tier: ( 2) 006 K.S.01 RCS RO Group: 2 SRO Group: 2 RO K/A 4.1 SRO K/A 4 2 !
I Roterence Title FacMy Refers nee Numtser Set (n Page Revision Learninq 014 l l
LOCA Bases SC2314-3 Att.1 74 4 6gg3 l
Material Required for Examination Question Source: Bank i i
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Question #11 The reactor has tripped from full power due to a Pressurizer Safety Valve being stuck open.
When will a rise in containment pressure be indicated?
A. When Pressurizer level reaches 100%
B. Immediately following the safety valve opening.
C. When Quench Tank pressure exceeds 124 psig.
D. When SIAS actuation occurs.
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 007 a2.01 Stuck open safety. RO Group: 3 SRO Group: 3 RO K/A 3.9 SRO K/A 3.9 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Reaclor Coolant DBD-SO23-300 47.3 110 2 Sam 6511 Material Required for Examination Question Source: New l
g Question #12 -
Given the following:
Component Cooling Water (CCW) Pumps P-024 and P-026 are operating
- . P-025 is aligned to Train A and is in standby A Safety Injection Actuation Signal (SIAS) and a loss of Voltage Signal (LOVS) occurred on both safety related buses.
Both safety related buses have been reenergized from their respective Emergency Diesel Generators (EDGs).
Which of the following correctly describes how the CCW pumps automatically respond to the conditions described?
A. All CCW pumps start.
B. P-024 and P-026 start; P-025 does not start.
C. P-024 and P-025 start; P-026 does not start.
D. P-025 and P-026 start: P-024 does not start.
Answer D Exam Level B Cognitive Level Apohcation Facility San Onofro 2 & 3 Exam Date 4/16/99 Tier: (2) 008 a2.01 ~ Loss of CCW Pump RO Group: 3 SRO Group: 3 RO K/A 3.3 SRO K/A 3.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Lossof CCW/SWC SO23-13-7 3.5 5 3 5370
-Material Required for Examination Question Source: NRC 6/98 -
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I Question #13 l
Which of the following Design Basis Accidents would generate the GREATEST amount of hydrogen and the reason why?
A. SMALL BREAK LOCA, due to increased heat input from the running RCPs.
B. LARGE BREAK LOCA, due to greater steam voiding in the core.
C. SMALL BREAK LOCA, due to less steam voiding in the core.
D. LARGE BREAK LOCA, due to hydrogen coming out of solution.
Answer B Exam Level B Cognitive Level Memory Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 009 2.4.21 Small Break LOCA RO Group: 2 SRO Group: 2 RO K/A 3.7 SRO K/A 4.3 Reference Title Facility Reference IJumber Section Page Revision Learning Obj.
UFSAR 6.2.5.3 6.2.77 13 65II Material Required for Examination Question Source: New
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Question #14 Given the following plant conditions:
~
Plant tripped 30 minutes ago Pressurizer Safety Valve is lifting RCS pressure is 1900 psia RCS Tu is 545 F -
Quench Tank rupture disk has ruptured Containment Pressure is I psig What is the expected temperature in the tailpipe downstream of the affected Pressurizer Safety Valve?
A. 215 degrees F.
B. 300 degrees F.
C. 545 degrees F.
D. 628 degrees F.
Answer A Exam Level B Cognitive Level Applicabon Facility San Onofre 2 a 3 Exam Date 4/1rW9 Tier: (2) PPCS 010~ A1.09 Tall Pipe Temperature and acouste RO Group: 2 SRO Group: 2 monitors.
RO K/A 3.4 SRO K/A 3.7 Facility Reference Number Section Page Revision Learning Obj.
Reference T*{
Steam Tables Mollier Olagram 4068 Material Required for Examination Steam Tables
_ Question Source: New
)
Question #15 Given the following plant conditions:
Unit 2 is in MODE 3 Pressurizer Level Control System is in automatic Which of the following would cause letdown flow to increase?
A. Loss of instrument air to the inservice letdown flow control valve.
B. The pressurizer level transmitter equalizing valve has vibrated open.
' C. Volume Control Tank level has dropped to less than 10%
D. SBCS controller setpoint has failed low with 2 valves in manual permissive.
)
I Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 011 A3.03 Charging and letdown. RO Group: 2 SRO Group: 2 RO K/A 3.2 SRO K/A 3 3 9eterence Title Famfity Reference Number Section Page Revision Learning Obj.
PZR Pressure and SO23-3-1.10 Att. 2 18 8 Level Control 10596 Material Required for Examination Question Source: New O
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i Question #16 A LOCA occurred 90 minutes ago and SO23-12-3 is being implemented. You are monitoring the Floating Step for "Two-phase heat removal established."
Which of the following temperature indications is required to be monitored during implementation of this floating step?
A. Hot leg temperature.
I B. Cold leg temperature. i C. Core exit temperature.
D. Heated junction thermocouples, Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & { Exarn Date 4/16/99 Tier: (1) 011 ekt.01 Natural circulation and cooling, including reflux RO Group: 2 SRO Group: 1 boiling.
RO K/A 4.1 SRO K!A' 4.4 Redwe: ice Talo Fant ty Reference Number Section P ige Revision Learning Otal LOCA SO23-12-3 FS-4 37 15 2537 Material Required for Examination !
Question Source: NRC 6/98 l
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' Question #17 Given the following' conditions:
A large loss of coolant accident is in progress
- SIAS, CIAS, MSIS, CSAS, and RAS have actuated RWST levelis 16%
Emergency sump level is 20' Containment Spray " Train A" valves are in the following positions:
RWST Suction valve HV9300 OPL4
' Containment sump isolation valve HV9303 OPEN ;
Containment sump isolation valve HV9305 OPEN Si pumps combined recirc valves HV9306/HV9307 OPEN Which of the following valve (s) has failed to automatically reposition to its Recirculation Actuation Signal position?
i A. HV9303. ;
)
B. HV9300. i C. IIV9303/HV9305.
D. HV9306/HV9307.
Answd D - Exam Level B Cogniilve Level Cotoprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 .
- 1 Tier
- '(2) 013 a2.01 LOCA RO Group: 1 SRO Group: 1 RO K/A 46 SRO K/A 4.8 Reference Title Facility Reference Number Section Page Revision Learning Obj.
ESFAS Operation SO23-3-2.22 Att.15 102 12 6221 Material Required for Examination Question Source: Bank l
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f Question #18 The plant is in normal operation at 100% power, when one CEA drops fully into the core.
Which of the following statements correctly describes the plant response to this event, assuming no operator action?
A. Reactor power decreases and RCS temperature decreases below program.
B. Turbine MWs lower and RCS temperature stays on program.
C. Reactor power decreases and RCS temperature stays on program.
D. Turbine MWs constant and RCS temperature decreases below program.
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 8 3 Exam Date 4/16/99 Tier:' (2) 014 A2.03 Dropped Rod. RO Group: 2 SRO Group: 1 RO K/A 3.6 SRO K/A 4.1 Reference Title Faclidy Reference Number Section Page Revision Learning Obj.
IA'a.wned CEA S0231113 2 4 4362 Material Required for Examination Question Source: Bank
4 Question #19 .
A reactor stanup is in progress and the reactor is approaching criticality.
Which set of parameters correctly describes the indications used to declare criticality?
A. Neutron count rate increasing, SUR positive, rods being withdrawn. )
i B. Neutron count rate decreasing, SUR negative, rods being inserted.
C. Neutron count rate increasing, SUR positive, rod motion stopped.
D. Neutron count rate decreasing, SUR zero, rod motion stopped.
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 015 k5.05 Criticality and its indications. RO Group: 1 SRO Group: 1 RO K/A 4.1 SRO K/A 4.4 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Reactor Startup So23-3-1.1 All. 2 31 19 439}
Material Required for Examination ,
Question Source; Bank !
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l Question #20 The plant has just tripped from 100% power. What effect will a rise in containment temperature (i.e. from 80 F to 250 F) have on the Steam Generator Narrow Range level instruments?
A. Actual level will be higher than indicated level due to voiding in the variable leg.
B. Actual level will be higher than indicated level due to reference leg temperature increase.
C. Indicated level will be higher than actual levt 1 due to voiding in the variable leg. ,
i D. Indicated level will be higher than actual level due to reference leg temperature increase.
Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 016 2.4.48 Non-Nuclear instrumentaton RO Group: 2 SRO Group: 2 System RO K/A 3.5 SRO K/A 3.8 I Refere< ice Title Facikh Rotorente Number Saton Paqo Revision Learning Obj instrunmntat' "
- 1915 Genenc Fundamentals i
Material Required for Examination l
Question Source: Bank
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Question #21 Which of the following could be an indication of core uncovery?
(Assume instruments are accurate)
CET Temperature equal to.
1 A. 555 degrees Fahrenheit with RCS Pressure equal to 1200 psia.
J B. 585 degrees Fahrenheit with RCS Pressure equal to 1350 psia.
C. 595 degrees Fahrenheit with RCS Pressure equal to 1500 psia.
D. 605 degrees Fahrenheit with RCS Pressure equal to 1650 psia.
Answer B Exam Level B Cognitive Level Applicaton Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 017 k5.03 Indcationof Superheating. RO Group: 1 SRO Group: 1 RO K/A 3.7 SRO K/A 4.1 Reference Title Facility Reference Number Secton Page Revision Learning Obj.
LOC A 6.Lses SO23-14-3 Att.1 51 4 4()59 Material Required for Examination Question Source: New i
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Question #22 Unit 2 was operating at full power when a plant trip occurred. The operators have initiated j SO23-12-1, Standard Post Trip Actions.
J Plant conditions are as follows:
)
' One CEA is not fully inserted j Pressurizer levelis 20% and rising !
Pressurizer pressure is 1950 psia and rising S/G narrow range water levels are at 29% with MFW RTO actuated Containment average temperature is 125 F Containment average pressure is 1.0 psig What is the correct operator action to be taken at this time, per the SPTAs?
A. Ensure nonnal containment cooling is functioning properly.
B. Emergency borate the RCS,
{
l C. Reenergize P7r heaters to raise pressurizer pressure.
D. Override AFW system to feed both S/Gs at greater than 200 gpm. '
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 022 Generic 2.4.21 Knowledge of the parameters used to RO Group: 1 SRO Group: 1 )
asses the status of safety functions, i l
RO K/A 3.7 SRO K/A 4.3 l Reference Title Facility Reference Number Section Page Revision Learning Obj.
SPTA SO23-12-1 11 15 5359 1 1
Material Required for Examination Question Source: Bank l
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N' Question #23 l Plant is operating in a normal full power alignment.
Which of the following will cause a loss of letdown?
A. Temperature of 150 F leaving the letdown heat exchanger.
B. Volume Control Tank outlet valve LV-02278 fails closed.
4 I;
C. Loss of instrument air to FV203 Boronometer/ Rad Monitor control valve.
D. 80 gpm letdown flow with only one charging pump running.
Answer B Exam Level B Cognitive Level Comprehension Facility San Onotre 2 & 3 Exam Date 4/16/99 j Tier: (1) ~ 022 AK3.04 Isolating letdown' RO Group: 2 SRO Group: 2 RO K/A 3.2 SRO K/A 3.4 Reference Title Facility Reference Number Secten Page Revision Learning Obj.
CVCS DBD-SO23-390 Fig. D-1 160 5 8992 1
Material Required for Examination l Question Source: New !
Question #24 Which of the following is a condition requiring emergency boration?
A. Part length CEAs inserted to 138 inches withdrawn with Unit at 90% power. l B. 12)ss of all CEA Reed Switch Position indication during a reactor startup. !
C. Regulating Group 6 CEAs inserted to 100 inches withdrawn with the Unit at 100% power.
D. I2)ss of Plant Monitoring System computer during a reactor startup.
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 ak3.01 When emergency boraton is required. RO Group: 1 SRO Group: 1 RO K/A 4.1 SRO K/A 4.4 Reference Title Facility Reference Number Section Page Revision Learning Obj.
- Emergency Boration of SO23-13-11 2 4 i
the RCS 6552 i l
Material Required for Examination '
Question Source: New 1
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4 Question #25 Given the following plant conditions:
HPSI Pump 2P-018 is aligned to Train B Large Break LOCA inside Containment has occurred on Unit 2 Pressurizer pressure is 900 psia Containment pressure is 13 psig l l
Which of the following Train B pumps should be running due to ESFAS actuations?
\ A. LPSI Pump P-016, HPSI Pump P-019, HPSI Pump P-018.
B. CS Pump P-013, HPSI Pump P-019, HPSI Pump P-018. l l
C. CS Pump P-013, LPSI Pump P-016 HPSI Pump P-019.
. D. CS Pump P-013, LPSI Pump P-016, HPSI Pump P-018.
Answer D Enam Level 8' Cognitive Level Comprehension Facility San Onofro 2 & 3 Exam Date 4/16/99 Teer. ( ?) On h2.01 Contw niunt Spray Pumps RO Group: 2 SRO Group: 1 !
RO K/A 34 SRO K/A - 3.6 Peterence Titio Facility Reference Number Section Page Revision Learning Obj. 1 Safety injection, D90-SO23-740 1.1.1.1 40,41.43 2 Containment Spray and 1,1.1.2 7328 Shutdown Cooling Systems j
Material Required for Examination Question Source: New
i' Question #26 Which of the following Pressurizer Pressure / Level parameters would require entry into a Technical Specification actio, statement with Unit 3 at 100% power?
A. levelof 28%.
B. Level of 56%.
C. Pressure of 2030 psia.
D. Pressure of 2280 psia.
Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 027 AA2.04 Technical Specification limits for RCS pressure. RO Group: 1 SRO Group: 2 RO K/A 3.7 SRO K/A 4.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Tec !,nical Reactur Coolant System 3.4.1 34-i Spuit..at.ons 6710 hlaterial Required for Examination Question Source: New j I
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Question #27 Given the following:
A Large Break LOCA occurred 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago A Recirculation Actuation Signal (RAS) has actuated ,
Which of the following will ensure a pH of between 7.0 and 8.0 in the Containment Sump?
A. Trisodium phosphate.
B. Trisodium sulfate.
C. Trisodium acetate.
1 D. Trisodium borate.
l Answer A Exam Level 8 Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 027 kl.01 CSS RO Group: 3 SRO Group: 2 RO K, A 34 SRO K/A 3.7 Reference Title FacMy Reference Section Page Revision Learning Obj.
Number Safety injecton, Containment Spray DBD-SO23-740 1.1.1.2 43 2 and Shutdown Cooling Systems 3285 Material Required for Examination Question Source: Bank s
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Question #28 Given the following plant conditions:
Reactor Trip has just occurred Pressurizer levelis 19% and rising Pressurizer pressure is 1950 psia and lowering Which of the following actions is required per SO23-12-1, Standard Post Trip Actions, for these conditions? -
A. Verify all available charging and HPSI Pumps are running.
B. Ensure all available charging pumps are running.
C. Verify all pressurizer heaters are ON.
D. Ensure Pressurizer normal and auxiliary spray valves closed.
Answer D Exam Level B Cognitive Level Memory Facility San Onofro 2 & 3 Exam Date 4/16/99 nor: (1) 028 an305 Actons contained in EOP for Pzt level RO Gbup: 3 SRO Group: 3 malfunction, RO K/A 3.7 SA O K/A 3.7 Reference Title Facility Reference Number Section Page Revision Learning Obj.
SPTA. SO2312-1 5 15 622 Material Required for Examination Question Source: Bank
Question #29 Given the following plant conditions:
An inadvertent MSIS has occurred The Reactor trip circuit breakers have NOT opened The Anticipated Transient Without SCRAM / Diverse SCRAM System (ATWS/ DSS)has caused a reactor trip Which of the following has automatically occurred to mitigate the event?
A. SIAS is initiated.
B. CEDMCS MG set output breakers open.
C. CEDMCS MG set output contactors op a.
D. 480V Buses BIS and B16 deenergized.
Answer C Exam Level B Cogndive Level Memory Facility San Onotre 2 & 3 Exam Date 4/10/99 Tit;c (t) 009 .A101 Ventying a reector tria: metnods RO Group: 2 SRO Group: 1 RO K/A 42 SRO K/A 4.5 Reference Title Facihty Reference Number Secton Page Revision Learning Obj.
Plant Protection DBD-SO23-710 22.4 107 2 System 733g Material Required for Examination Question Source: New l
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. Question #30 Given the following plant conditions:
Unit 2 tripped 25 minutes ago A Steam Generator Tube Rupture has been diagnosed and RCS cooldown has been initiated .
Hot leg temperature is 529 F RCPs 2P001 and 2P004 have been secured S/G levels are 27% in E089 and 31 % in E088 and slowly rising Pressurizer level is 20% and slowly rising Pressurizer pressure is 1480 psia Which of the following actions should be performed at this time?
- A. Perform HPSI throttle stop.
B. Override and feed both steam generators.
C. Secure 2 charging pumps.
D. Isolate the affected steam generator.
Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 035 A2.01 Fau' ed or ruptured S/Gs RO Group: 2 SRO Group: 2 RO K/A 4.5 SRO K/A 4.6 Reference Title Facility Reference Number Secton Page Revision Learning Obj.
SGTR SO23-12-4 11 16 6g74
' Material Required for Examination Question Source: New I
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Question #31 -
Given the following plant conditions:
Unit 2 tripped 18 minutes ago Steam Generator Tube Rupture has been diagnosed and SO23-12-4 has been implemented All Reactor Coolant Pumps were secured 12 minutes ago Natural Circulation Criteria has been verified HPSI throttle /stop has been completed; all HPSI and charging pumps are secured RCS pressure is 1000 psia M slowly lowering Pressurizer level is 66% M slowly rising Which of the following conditions would explain the pressurizer level response?
A. Pressurizer level instrument variable leg has broken.
B. Voiding is occurring in the RCS head region.
C. Pressurizer level setpoint has failed high.
1 D. RCS heatup is occurring.
Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 038 ek1.03 Natural Circulation RO Group: 2 SRO Group: 2 RO K/A 3.9 SRO K/A 4.2 Reference Title Facility Reference Number Section Page Revision Learning Obj.
SGTR Bases SO23-14-4 Att.1 52 3 4140 Material Required for Examination Question Source: New i
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Question #32
- l. Unit 3 is at 17% power and the operator has just applied Block lead when a generator trip I
occurs.
Describe the expected response of the Main Steam Safety Valves (MSSVs) and the Steam Bypass Control System (3BCS) to this event.
A. MSSVs will initially open, then rescat; SBCS valves will open as required to control main steam pressure.
B. MSSVs will not open; SBCS valves will open as required to control main steam pressure.
C. MSSVs will initially open, then rescat; SBCS valves receive a " quick-open" block signal due to low Tave.
D. MSSVs and SBCS valves will be unaffected.
Answer B Exam Level B Cognitrve Level Cornprehension Facdity San Onofre P & 3 Exam Date 4/16/99 T.cf D'; 041 6 i : ,' P actor Trip RO Group: 3 GRO Group: 3 RO K/A 3.7 SRO K/A 3.7 Reference Title Facihty Reference Number Secten Page Revison Learning Obj.
S/G and Secondary DBD-SO23-365 6.2.5 133 1 Side 6455 ;
i Material Required for Examination Question Source: New I
o Question #33 -
While performing a heat treat on Unit 3, the condenser low vacuum alarm is received. You note that main condenser backpressure is 5.8" Hg abs.
What effect should this have on Steam Bypass Contml System (SBCS) operation?
A. SBCS is disabled due to low condenser vacuum.
B. The SBCS " Emergency Off" push button should be pushed to prevent system operation during the low vacuum condition.
. C. . Vacuum is not degraded enough to have an effect or require any actions.
D. SBCS " quick-open" actuation is blocked but modulate operation is still enabled.
Answer C Exam Level Cognitive Level Memory Facility San Onofre / & 3 Exam Date 4/16/99 Tier: (1) 051 ak3.01 Loss of steam dump capability upon loss of RO Group: 1 SRO Group: 1 condenser vacuum.
RO K'A 2.8 SRO K/A 3.1 F,efemta Titt.s Facahty Relerenco Number Secto Pagu Revision Learning Obj.
Steam Bypass System SO23-3-2.18 3.0 3 12 Operaton 6455 Material Required for Examination Question Source: New l
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L 1-l Question #34 Given the following plant conditions:
Unit 2 tripped 45 minutes ago An Excess Steam Demand Event is in progress E089 is about to reach dryout Which of the following conditions could occur if steaming is not commenced on the unaffected S/G?
A. _ Loss of natural circulation in the affected RCS loop resulting in stabilization of
, RCS temperatures.
B. Loss of RCS subcooling resulting in a loss of natural circulation in both RCS loops.
C. Loss of inventory in the affected S/G resulting in a loss of natural circulation in that loop.
D. less of natural circulation in both RCS loops resulting in RCS repressurization.
Answer D Exam Level B Cognitive Level Memory Faciisty San Onofro 2 a 3 Exam Date 4/1n99 Tier: (1) 054 ak3.04 Actions contained in EOP's for loss of MFW. RO Group: 2 SRO Group: 2 RO K/A 4.4 SRO K/A 4.6 Reference Title Facility Reference Number Section Page Revision Leaming Obj.
ESDE Bases SO23-14-5 Att.1 21 4 6805 Material Required for Examination Question Source: New i
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Question #35 l
Plant conditions are as follows:
)
A Loss of Offsite Power caused a reactor trip 30 minutes ago l MSIVs have been manually closed ;
Atmospheric Dump Valves were placed in automatic and set at 1000 psia l
immediately following the reactor trip l
Which of the following conditions would be expected for the above conditions? j A. Hot leg temperature of 550 F and rising.
Cold leg temperature of 530 F and lowering. I B. Hot leg temperature of 570 F and lowering.
Cold leg temperature stable at 545 F.
1 C. Hot leg temperature of 587'F and rising.
Cold leg temperature stable at 545 F.
D. Ilot lec temperature of 570 F and lowering. l Cold leg temperature of 540 F and lowering. l J
Answer . 8 Exam level B: Cognitive Level Comprehension Facility San Onotre 2 & 3 Exam Date 4/1699 Tier:(1) 055 akt.02 Natural Circulatioin Cooling RO Group: 1 SHO Group: 1 RO K/A 4.1 SRO K/A 4.4 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Loss of Offsite Power SO23-12-7 8 15 (gg Material Required for Examination Question Source: New-w a
1 Question #36 l
1 The plant was initially operating at 100% power.
L l
t A complete loss of Offsite Power occurred 5 minutes ago. HQ operator actions have been taken and all systems functioned as designed. -
1 How are the S/Gs maintaining RCS heat removal?
A.- AFW supplying S/Gs; steaming out Main Steam Safety Valves. )
3 B. AFW supplying S/Gs; steaming using the Atmospheric Dump Valves.
C. MFW. supplying S/Gs; no steaming required.
D. MFW supplying S/Gs; steaming using the SBCS.
1 Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier- (1) 056 AA2.56 RCS T-ave. RO Group: 3 SRO Group: 3 RO KIA 36 SA O K/A 3.7 Reifurrmce Title Facility Reference Number Section - Paco Revision Learning Ott SPTA SO23-12-1 8 15 6gl6 Material Required for Examination Question Source: Bank I
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Question #37 l
Given the following plant conditions:
Channel"A" RCS hot leg temperature Tr-0122-1 has failed and the affected functional units have been bypassed Channel"C" RCS hot leg temperature TT-0122-3 has also failed and the affected
. functional units have been placed in trip - l
' A loss of vital bus inverter 2Y004 occurs and the Reactor does HQI trip - (
All other plant conditions are normal Which of the following action is required?
l A. Vital bus 2YO4 must be placed on its alternate source within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I B. Manually trip the reactor, i C. Initiate a Rapid Downpower per SO23-5-1.7, Power Operations.
D. Initiate a normal plant shutdown per SO23-5-1.7, Power Operations.
l Answer C Exan Level B Cognitive Level Comprehension Facihty San Onotre 2 & 3 Exam Date 4/16 99 Tier:. (1) 057 aa2.03 RPS panel alarm annunciators and RO Group: 1 SRO Grot.p: 1 I
trip indicators RO K/A 3.7 SRO K!A 3.9 Reference Title Facility Reference Number Secton Page Revision Learning Obj.
RPS/ Loss of Vital Bus SO23-1318 Att 2 12 2 6593 Inverter Material Required for Examination !
Question Source: New l
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Question #38 Given the following plant conditions: !
Unit 2 tripped 40 minutes ago Both Main Steam isolation Valves (MSIVs) have failed closed
' All Auxiliary Feedwater has been lost and could not be restored ;
The crew has rediagnosed a Loss of Feedwater and entered SO23-12-9, i Functional Recovery 1
i Which of the following methods should be used to recover the RCS Heat Removal Safety Funcdon? l A. Establish HPSI flow to the cold legs for once-through core cooling.
B. Reestablish Main Feedwater flow to the S/Gs. ,
1 C. Establish LPSI flow to the cold legs for once-through core cooling. ]
D. Establish low pressure attemate feedwater flow using condensate pumps.,
Answer D Exam Level B Cognitive Level Appleation Facility San Onofre 2 & 3 Exam Date 4'1C'99 Tier; (2) 059 k304 RCS RO Group: 1 SRO Group: 1 RO K/A . 3.6 SRO K/A 3.8 Reference Tdie Facility Reference Number Secton Page Revision Learning Obj.
Functional Recovery SO23-12-9 Att. 8 330 18 69[6 Material Required for Examination Question Source: Bank l'
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. Question #39 Given the following plant conditions:
Unit 2 is at 355 F.
A cooldown is in progress using the S/G's j Which of the following is required to be OPERABLE per Technical Specification 3.7.5, Auxiliary Feedwater System?
A. All three AFW Pumps.
B. Two motor driven AFW Pumps.
C. One motor driven and one steam driven AFW Pump. I D. One motor driven AFW Pump.
Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16S9 Tier: (2) 061 Generic 2.1.12 Ability to apply Techncal Speciteatons to a RO Group: 1 SRO Group: 1 sys'em RO K/A 2.9 SRO K/A 4.0 i
Reference Title Facility Reference Number Section Page Revision Leaming Obj. l Technical Auxiliary Feedwater System 3.7.5 3.r-11 Specifications 6642 Material Required for Examination Question Source: New 1
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Question #40 Given the following information:
The unit tripped from 100% power 20 minutes ago Both Steam Generator levels lowered to 17% NR and recovered to 26% NR The operator has depressed the " Override" pushbuttons for the AFW valves and is feeding each steam generator at 450 gpm Subsequently:
Steam Generator E088 pressure decreases to 700 psia with level at 25% NR.
Steam Generator E089 pressure decreases to 850 psia with level at 27% NR Which of the following describes the status of the AFW system (assume no other operator actions have occurred)?
A. Both steam generator E088 and E089 are being fed.
B. E088 is being fed and E089 is isolated.
C. Neither steam generator E08b nor EOS9 is being fed.
D. E089 is being fed and E088 is isolated.
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 061 a3.04 Automatic AFW tsolation RO Group: 1 SRO Group: 1' RO K/A 4.1 SRO K/A 42 Reference Title Facility Reference Number Section Page Revision Learntng Obj.
Plant Protection DBD-SO23-710 2.12.7 99 2 4726' System Material Requ-ired for Examination Question Source: Bank i
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K Question #41 .
l Given the following:
Both Units 2 and 3 are at full power
- Unit 2 is preparing to shift Train' A SWC pumps
' The operator assigned to perform 4KV breaker manipulations goes to the wrong unit and turns off DC control power to 3P112, which was running at the time i
~
What effect does this have on the operation of SWC 3P1127.-
A. . SWC pump low flow alarms are received, due to 3P112 pump trip.
B. ' SWC pump 3P112 breaker opens, no alarms are received due to the loss of ,
control power. I C. SWC pump 3P112 breaker stays closed, no remote operation or automatic tripping is available.
. D. SWC pump 3P112 breaker stays closed, no remote operation is possible but automatic trips are functional. !
1 Answer C Exam Level B Cognitive Level Memory Facility San onofre 2 & 3 Exam Dato 4/16/99 Tier: ( 2) 063 K3.02 Components using DC control RO Group: 2 SRO Group: 1 Power I
RO K/A 3.5 SRO K/A 3.7 Reference Title Facility Reference Number Section .Page Revision Learning Obj.
Elementary Diagram 30795 18 5220 Material Required for Examination Question Source: New I
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1 Question #42
- l. Plant conditions are as follows:
I Unit 2 tripped 10 minutes ago on low pressurizer pressure A loss of offsite power occurred 6 minutes ago Pressurizer pressure is now 1430 psia Bus 2A04 is energized 20003 has just tripped and bus 2A06 is deenergized Which of the following diesel generator trips could have caused the loss of 2G0037 1
1 A. High crankcase pressure. !
B. High jacket water cooling temperature. .
C. less of excitation.
D. Generator differential. l 1
i Am.v.er D E tan Les ei 0 Cowv.. Levd Co1:ruchension Famlity San Onofre 2 & 3 E cim Date 41u 99 l Tier: (2) 064 k4.02 Trips for ED/G while RO Group: 2 SRO Group: 2 I operating (normal or emergency) RO K/A 3.9 SRO K/A 4.2 Reference Title Facility Reference Number . Section Page Revision Learning Obj.
Elementary Diagram 30330 22 5346 I
Material Required for Examination
. - Question Source: New _ I l- ,
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c Question #43 i
I Given the following plant conditions: l Plant is operating at 100% power Alarm 61 A15 (Fire Detected) is received in the Control Room !
l The Fire Computer indicates the fire is in the Unit 2 computer room 4
Which of the following explains the expected conditions for a fire in the computer room?
'A. - Supply and exhaust dampers open, for 'once through' air flow.
B. Supply and exhaust dampers close, isolating the computer room.
C. Stipply damper closes, exhaust damper opens to exhaust smoke.
D. Supply damper opens, exhaust damper closes to allow fresh air in.
Ana s/er B E4am Level B Coonitive Level Momery Facility San Onofre 2 & 3 Exam Date +16'99 Tier: (1) 067 aa1.05 Plant and Control Room Ventilation System 90 Group: 1 SRO Group: 1 PO K'A 3.0 SRO K/A 3.1 Reference Title - Facility Reference Number Section Page Revision Learning Obj. ;
Halon Fire Protection SO23-7-4 6.3.5 5 2 System Operation 8356 Material Required for Examination Question Source: New ,
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Question #44 i
A release of one of the Radwaste Secondary Tanks is in progress. Liquid Rad Waste Monitor (RE-7813) fails low. I Which of the following will allow the release to recommence?
A. He Plant Superinte.. dent must approve the release permit.
B. Two independent samples, release rate calculations, and valve lineup verifications must be performed.
C. The sample flowrate must be estimated at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. t i
D. De liquid release cannot recommence until RE-7813 is determined to be OPERABLE.
Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 068 k6.10 Radiation monitors RO Group: 1 SRO Group: 1 R O K/A 2.5 SRO K/A 2.9 Afdarerv;e Title Facility Reference Number Section Page Revision Learning Obi Lioud Radioactive SO23-8-7 Att. 6 95 10 Waste Release 9068 Operations l
Material Required for Examination Question Source: New l
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Given the following:
Wide Range Gas Monitor (WRGM),3RE-7865, is aligned to the Plant Vent Stack A Waste Gas Decay Tank release is in progress Alarm 61 A27. " Plant Vent Stack Radiation Hi", is received due to high radiation on 3RE-7865 I
Which of the following best describes the automatic action (s) caused by the WRGM for the above set of conditions?
A. He monitor realigns to containment purge to sample that flow path. .
l B. Sample flow control shifts from Isokinetic flow control to manual flow control. !
l C. De waste gas discharge flow control valve FV-7202 closes.
D. He outside containment mini-purge isolation valve HV9825 closes.
Answer C Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4J16/99 l l
Tier: (2) 071 k4 04 isolation of waste gas release tanks RO Group: 1 SRO Group: 1 RO K/A 2.9 SR O K/A 3.4 Reference Title Facility Reference Number Section Page Revision Leaming Obj.
Radwaste Gas SO23-815 4.4 3 11 Discharge 94l3 Material Required for Examination Question Source: NRC 6/98 I
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n Question #46 l Unit 2 is in MODE 6. During fuel inspection activities, the fuel inspection device was raised out
! of the Spent Fuel Pool.
Airborne radiation levels as sensed by the Fuel Handling Building Vent Airborne Monitors RE-7822 & RE-7823 have exceeded the alarm / trip setpoint.
RE-7822 is in bypass RE-7823 is in normal operation Based on these conditions, which of the following statements represents correct system response?
A. FHIS actuation, Train 'A'.
B. FHIS actuation, Train 'B'.
C. FHIS actuation, Trains 'A' and 'B'.
D. No FHIS actuation occurs.
Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 072 kl.03 Fuel Building isolation RO Group: 1 SRO Group: 1 RO K/A 3.6 SRO K/A 3.7 Reference TiJe Facility Reference Section Page Revision Learning Obj.
Number Fuel Handling Area Vent airborne Process SO23-3-2.24.5 6.1.4 3 6 Radiation Monitoring System Operation 6302 Material Required for Examination Question Source: Bank
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. Question #47 4
l Given the following plant conditions:
A Waste Gas Decay Tank release using 2/3 RT-7808, Plant Vent Stack Airbome I Radiation Monitor,is in progress.
_ Rad monitor 3RT-7865, Containment / Plant Vent Stack Radiation Monitor, becomes INOPERABLE.
What additional action must be performed to allow the release to continue?
A.' Process flow rate must be estimated at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i B. Two independent samples must be drawn at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. i C. Reverify valve alignment, sample and recalculate release rate calculations. l D. Verify composite samplers are operational for the gaseous radwaste system.
l Answer A' Emaer. Level B Cognitive Level Memory Fadlity San Onotre 2 & 3 Exam Date 41E99 I Tier: (2) 073- Generic 2.1.20 Ability to execute procedure steps. RO Group: 2 SRO Group: 2-RO K/A 4.3 SRO K/A 4.2 !
Reference Title Facility Reference Number . Section Page Revision Leaming Obj. l Radwaste Gas so23-8-15 4.11 4 11 Discharge 10103 i
Material Required for Examination Question Source: New l
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Question #48
'Ihe plant has just tripped from 100% power operation, the SPTAs are being carried out and l plant conditions are as follows:
All CEAs are fully inserted PZR level is 20%
RCS Subcooling is 88 F i RCS pressure is 1410 psia l
-' RCS cold leg temperature is 490 F )
CNTMT pressure is 0.5 psig 1
. All ESFAS Systems have actuated as required l l
Which of the following is required per the SPTAs for Reactor Coolant Pump operation? l A. Trip four RCPs. j j
B. Trip two RCPs.
C. leave all four RCPs rudning.
D. Trip one RCP. ,
Answer B Exam Level B Cognatwe Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 074 ek304 Tripping RCPs RO Group: 1 SRO Group: 1 RO K/A 3.9 SRO K/A 4.2 Reference Title Facility Reference Number Secton Page Revision Learning Obj. I SPTA SO23-121 5 15 622 !
Meterial Required for Examination Question Source: New I
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F-i Question #49 Which of the following electrical buses supply power to the 4 Saltwater Cooling Pumps located in the Unit 2 Saltwater Cooling Pump Room?
A. One (I) pump from each of 2B04,3B04,2B06, and 3B06.
B. Two (2) pumps from each of 2B04 and 2B06.
C. One (1) pump from each of 2A04,3A04,2A06, and 3A06. j D. Two (2) pumps from each of 2A04 and 2A06.
Answer C Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 j Tier: (2) 075 K2.03 Circ Water System Emergency RO Group: 2 SRO Group: 2 Essental SWS pumps RO K/A 2.6 SRO K/A 2.7 Reference Title Facility Reference Number Secten Page Revision Leaming Obj.
Saltwater Cooling DBD-SO23-410 Table C-1 98 2 6727 System Alaterial Required for Examination Question Source: New
Question #50 A fire has been detected in Containment. As the Fire Brigade Technical Advisor working with the Fire Department, you are asked what type of automatic water suppression system is used in the 3 immediate vicinity of RCP P001. !
l Which of the following is the correct response?
A. A deluge water spray sprinkler.
B. A wet pipe sprinkler.
C. Automatic pre-action sprinkler. I D. No suppression system is located in the area.
Answer A Exarn Level B Cognitive Level Memory i Facility San Onofre 2 & 3 Exam Dale 4/16/99 Tier: (2) 086 KS.03 Effact of H,0 spray on electrical components RO Group: 2 SRO Group: 2 RO K/A 3.1 SRO K/A 3.4 F if rence Title Fr.ht/ Reference Sect'on Pale Revision Learning Otj.
Number Fire Suppresson Water System SO23-7-1 Att. 7 53 18 93g6 Operal;on l
Material Required for Examination j Question Source: Bank i 1
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Question #51 l
y With Unit 2 in MODE 1, an inadvertent CIAS occurs.
Which of the following describes the BRSIactions required to be perforrned per the AOI?
i A. Initiate SO23-13-7, Loss of CCW/SWC. '
B. Trip the Reactor Coolant pumps.
C. Trip the Reactor and Turbine.
D. Override /Open CCW NCL isolation valves. I Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 103 a3.01 Containment isolaton RO Group 3 SRO Group: 2 i
RO K/A 3.9 SRO K/A 4.2 Reference Title Facility Reference Section Page Revision Leaming Obj.
Number 4*ct. < ', From inadverted S ifety SO23-13-17 3.1.1 2 2 e -nst i. contamnisn.t isoLMn
- 6584 Material Required for Examination !
Question Source: Bank i
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I Question #52 The unit is operating at 100% power. He following conditions exist on Reactor Coolant Pump P002:
l Vapor Seal Cavity Pressure 78 psig )
Upper Seal Cavity Pressure 2240 psig Middle Seal Cavity Pressure 2250 psig Which of the following actions are required for the stated conditions?
A. Full power operations may continue, trend P002 parameters.
B. Initiate a normal plant shutdown.
C. Initiate a Rapid Downpower.
D. Immediately trip the reactor and 5 seconds after the CEAs are inserted, trip RCP l P002.
l An me r B Esa n Lt ye B Cop it so Level A; phcation Faci'it, hn Omfro 2 & 3 Exarn Date 4%99 l
Tier: (1) 015/17 aa2.01 Causeof RCP fe. dure RO Group: 1 SRO Group: 1 j 1
RO K/A 3.0 SRO K/A 3.5 Reference Title Facility Reference Number Section Page Revision Learning Obj.
RCP Seal Failure SO23-13-6 3.3 3 2 I 6516 Material Required for Examination Question Source: Bank
1 Question #53 l l
During normal plant operations, while performing actions outside of the Control Room, what is the relationship between the Control Room Operators and the PEO? l l
A. The PEO will take direction from the CRS, but is responsible to the CO.
B. The ACO will direct the PEO's activities, but will inform the CRS before action is taken. I C. The CO will direct the PEO's activities, but only with SM concurrence. I D. He CO will direct the PEO's activities under the supervision of the CRS. j 1
1 Answer D Exam Level B Cognitive level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 i Tier: 2.1.1 Knowled0e of conduct of operations requirements RO Group: SRO Group:
RO K/A 3.7 SRO K/A 3.8 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Conduct of Operaton SO23-0-46 6.16.5 18 0 gg4l7 Material Required for Examination Question Source: NRC 1 U98 l
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Question #54 Giv'en the following plant conditions on Unit 2:
RCS average temperature is 295 F. j Maintenance is being conducted in the switchyard.
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At 9:00 am the switchyard foreman reports a crane operator lost control and tripped open the Unit 2 switchyard Reserve Auxiliary Transformer breakers.
Substation personnel on the scene have conducted a visual inspection and report that the breakers will be OPERABLE at 10:30'am.
What actions are required by Technical Specifications? '
A. No further action is required since the LCO will be met within the Required Action Completion Time.
B. Within I hour, perform surveillance test on both DGs. ,
i C. . Take action to suspend any positive reactivity additions until the second offsite circuit is energized.
D. Within I hour, verify correct breaker and power availability for the offsite circuit that was not deenergized. j l
Answer D Exam Level 8 Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.11 Knowledge of <1 hr Tech Spec action statements. RO Group: SRO Group:
RO K/A 3.0 SRO K/A 3.8 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Technical Electric Power Systems 3.8.1 3.8- 1 Specifcations 9964 Material Required for Examination ,
Question Source: NRC 6/98 i
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Question #55 -
Which of the following sets of conditions will allow a start (breaker closure) of Circulating Water l Pump P115 (Assume 2A0308 breaker racked in with DC on)?
2HV5288 - CW Pl15 Discharge Valve 2HV5100 - TPCW supply valve from P115 to TPCW IlX A. _2HV5288 open,2HV5100 closed.
B. 2HV5288 open,2HV5100 open.
1 C. 2HV5288 closed,2HV5100 open. !
D. 2HV5288 closed,2HV5100 closed.
Answer A Exam Level B Cognitive Level Comprehension Facility San Onotre 2 a 3 Exam Date 4/16/99 Tier: 2.124 Abihty to obtain and interpret electrical and mechanical RO Group: SRO Group:
drawings.
RO K/A 2.8 SRO K/A 3.1 Peterence Title Facility Reference Number Section Page Revision Learninq Obj.
Elementar/ Diagrams 31001,31005,31009, 17,9,4.8 31061 4862 l
Material Required for Examination . prints: 31001,31005,31009,31061 Question Source: Bank
Question #56 When observing a Motor Operated Valve (MOV) during stroke testing, it is important to stand clear of the handw'.cel plane.
This is because the handwheel will rotate at high speed and could disintegrate if:
A. The limit switch fails to actuate.
B. He clutch does not disengage.
C. The motor phase rotation is incorrect.
D. The torque switch fails to actuate.
Answer B Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exarn Date 4/16/99 Tier: 2.2.12 Knowledge of Surveillance Procedure RO Group: SRO Group:
RO K/A 3.0 SRO K/A 3.4 Reforence Title Faciltv Reference Number Section Page Revision t. earning Obj.
Valve Operation SO23-O-23.1 4.13 5 5 6362 Material Required for Examination Question Source: Bank
Question #57 Which of the following items CANNOT be revised without prior NRC approval?
A. Licensee Controlled Specification Bases.
B. Licensee Controlled Specifications.
C. Technical Specification Bases.
D. Technical Specification Surveillance Requirements.
Answer - D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2222 Knowledge of limiting conddions for operations and safety RO Group: SRO Group:
limits.
RO K/A 3.4 SRO K/A 4.1 Reference Title Facility Reference Number Secten Page Revision Learning Obj.
Technical Administrative Controls 5.4 5.0-1 7270 Specifications hlaterial Required for Examination Question Source: Bank
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i Question #58 i i
Why must a MODE 6 EDMR be issued if the Spent Fuel Pool boron concentration drops below 2600 ppm?
A. The SFP water could dilute the refueling cavity when the fuel transfer tube is opened.
B. The addition of spent fuel assemblies to the spent fuel pool could cause spent fuel pool criticality. .
C. The RCS water could dilute the Spent Fuel Pool when the fuel transfer tube is opened.
D. The movement of a new fuel assembly out of a high density fuel rack could cause spent fuel pool criticality.
Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier. 2.2.27 Knowledge of the refueling process. RO Group: SRO Group:
RO K/A 26 SRO K A 17 Reference Title Facility Refererce Number Section Page Revision Learning Obj.
LOCAR and EDMR SO123-0-13 6.2.2 10 6 4582 Material Required for Examination 3
Question Source: Bank I
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Question #59 A worker has been assigned the task of unbolting incore detector flanges. l The following is the dose history for this worker.
Deep Dose Equivalent - 0.5 REM Committed Effective Dose Equivalent - 0.2 REM Dose Rate for this task is 0.9 R/HR gamma radiation Which of the following is the maximum stay time for this worker per SONG's Administrative Limits?
~ A. 20 minutes.
B. 33 minutes.
C. 53 minutes.
D. 66 minutes.
l Answer A Exam Level B Cognitive Level Apphcation Facility San Onofre 2 & 3 Exam Date 4/16/99 !
Tier: 2.3.1 Know! edge of 10 CFR;20 and related facility radiation RO Group: SRO Group:
control requirements,
{
l Reference T!tle Facility Reference Number Section Page Revision Learning Obj. I Health Physics SO123 Vil-20 6.4.1.4 20 Program 5 96g}
Material Required for Examination i Question Source: New 1
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l Question #60 Which of the following statements describes the relationship between dose rate and distance for a point source of 1000 mrem?
A. The dose rate varies inversely to the square of the distance.
B. The dose rate varies inversely to distance.
C. The dose rate does not drop off appreciably with distance.
l D. The dose rate is insignificant at a distance of three feet.
Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/f 699 Tier: 2.3.2 Knowledge of facility ALARA program. RO Group: SRO Group:
RO K/A 2.5 SRO K/A 2.9 Reference Title Facildy Reference Number Secton Page Revision Learning Obj.
Generic Fundamentals 9681 !
hlaterial Required for Examination Question Source: Bank i
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Question #61 Given the following: l i
1 The unit is in MODE 1 '
2RT-7865 'is aligned to the Plant Vent Stack Containment Mini Purge is in progress Which of the following would require immediate securing of the Containment Mini-Purge?
A. 2RT-7865, Containment / Plant Vent Stack Radiation Monitor becomes INOPERABLE.
B.- 2RT-7804, Containment Airborne Radiation Monitor becomes ;
INOPERABLE. '
C. 2RT-7828, Containment Purge Stack Radiation Monitor becomes INOPERABLE.
D. 2FR-7826, Containment Purge Stack Process Flow Recorder becomes I INOPERABLE.
l Answei C Exam Level Cognitive L evel Comprehension Facility San Onofre 2 & 3 cixam Date 4'16/99 !
Tier: 2.3.9 Knowledge of the process for performing a containment RO Group: SRO Group:
purge.
RO K/A 2.5 SRO K/A 3.4 Reference Title - Facility Reference Number Section Page Revision Learning Obj.
Containment Purge and SO23-1-4.2 Att 13 70 22 Recirculation Filtration System 7576 Material Required for Examination Question Source: Bank i
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Question #62 A major earthquake occurred ten minutes ago. The Reactor has tripped and the following conditions exist on Unit 2: 1 A loss of the switchyard has occurred Both S/Gs are at 17% NR level and no AFW flow can be established to either S/G Pressurizer Level is 12% and decreasing l Main Steam Line Radiation Monitors are trending upscale i
Which of the following is the appropriate Emergency Operating Instruction to mitigate the Unit 2 event?
A. SO23-12-4, Steam Generator Tube Rupture.
.i B. SO23-12-6, Loss of Feedwater. !
C. SO23-12-7, less of Forced Circulation / Loss of Offsite Power. I D. SO23-12-9, Functional Recovery.
Answer D Enam Level B Cognitwe Leve21 Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.1 Knowledge of EOP entry conditions and immediate action RO Group: SRO Group:
steps, RO K/A 4.3 SRO K/A 4.6 l Referenco Title Facility Reference Number Section Page Revision Learning Obj.
SPTA SO23-12-1 Att. 2 19 15 4845 Material Required for Examination Question Source: Bank i
' Question #63 A Reactor Trip has occurred. The crew is ready to report Standard Post Trip Actions.
Reactivity Control and Vital Auxiliaries have been reported.
Which of the following states the correct sequence for the next four (4) safety functions to be reported?
A. RCS Inventory Control RCS Pressure Control RCS Heat Removal Core Heat Removal B. RCS Inventory Control RCS Pressure Control Core Heat Removal RCS Heat Removal C. RCS Pressure Control RCS Inventory Control Core Heat Removal RCS Ileat Removal D. RCS Pressure Control RCS Inventory Control RCS Heat Removal Core Heat Removal Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.14 Knowledge of general guidelines for EOP flowchart use. RO Group: SRO Group:
RO K/A 3.0 SRO K/A 3.9 Reference Title Facihty Reference Number Section Page nevision Learning Obj.
SPTA SO23-12-1 Att.1 17 15 622 Material Required for Examination Question Source: Bank i
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p-l Question #64 Quench Tank temperature has been rising slowly.
Which of the following annunciators would assist the operator in determining why this is occurring?
A. 50A22, PZR I.cvel Error lii.
B. 50A32, PZR Spray Valve Bellows Seal Failure.
C. 50A31, PZR Relief Valve Outlet Temp Hi.
D. 50A35, Reactor Vessel Seal Leakage.
Answer . C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.46 Ability to verify that the alarms are consistent with plant RO Group: SRO Group:
condstions.
RO K/A 3.5 SRO K/A 3.6 Rew-an( N e Faciht/ Reference Nuniber Section Pa<ie
, Revision Learniaq Obi.
Annunciator Panel 50A SO23-15-50.A2 50A31 9 5 6569 Material Required for Examination Question Source: New i
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Question #65 Which of the following conditions will result in staning the LP Turbine Exhaust Hood Emergency Spray Water Pump following a Turbine Trip from 100% power?
A. Condensate supply press to the LP Spray system <100 psig and the LP Spray valve is open.
B. Depressing the " START" handswitch with a SIAS present.
C. LP Exhaust Temperature >l60 F on one or more exhaust hoods.
D. Depressing the " OVERRIDE" handswitch with a MSIS present.
Answer A Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier:(1) BW/A04 aa2.2 Adherence to appropriate procedures and RO Group: 2 SRO Group: 2 operation within the limitations in the facility's license and amendment.
RO K/A 3.7 SRO K/A 4.4 R- ferenca Tde Facilt/ Relvmre Number Section Page Revision Learning Obj.
Tutoine Protex:tive SO23-10-4 6.4 14 6 Device Testing 5377 Material Required for Examination Question Source: Bank ,
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i Question #66 I
l f Given the following:
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I An unisolable ESDE has occurred outside Containment The affected S/G has blown dry RCS temperature is 350 F RCS pressure is 1290 psia The crew should: i
)
i A. Secure all running RCPs.
B. Stabilize RCS temperature and depressurize the RCS. ,
I C. Reduce RCS temperature to establish 20 F subcooling.
1 D. Stabilize RCS pressure and temperature at current values.
Answer B Exam Level B Cognitive Level Comprehensen Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) BWiE03 ea2.2 AJherence to appicpriate procedures and RO Grcup. 1 SRO Group: 1 operation within the limitations in the facihty's hcense and amendments.
RO K/A 3.5 SRO K/A 4.0 Reference Title Facihty Reference Number Section Page Revision Leaming Obj.
ESDE Sd23-12-5 12 15 6906 Material Required for Examination Steam Tables Question Source: New 1
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r-Question #67 Given the following plant conditions:
A small break LOCA is in progress and SIAS has actuated All systems are operating as expected Per the stated conditions, which of the following is the basis for maintaining a secondary heat sink?
A. To minimize boron stratification of the RCS.
B. RCS pressure may remain so high that cooling from the injection flow alone is inadequate to remove decay heat.
C. Reflux boiling is the primary means of heat removal prior to voiding in the hot legs.
D. To provide an attemative method of RCS pressure control.
A> . war B Een Level B Corinv t Le.el Mon nry Faul4y Saa 01ofre 2 & 3 Exam Da e l'IEM9 Tier: (1) BWiE04 ea2.1 Facility conditions and selection of RO Group: 2 SRO Group: 2 approprote procedures during abnormal and emergency operations.
RO K/A 3.2 ' SRO K/A 4.4 Reference Title Facility Reference Number . Section Page Revision Learning Obj.
LOCA Bases SO2314-3 Att.1 10 4 4732 Material Required for Examination Question Source: New l
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Question #68 )
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Given the following:. I The unit tripped 30 minutes ago due to a LOCA i RCS temperature is 525 degrees F
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RCS pressure is 1600 psia J
Power has been lost to the switchyard j 1E power is being supplied by the diesel generators J Voids have formed in the head For the given conditions, which of the following actions will be required to promcte greater cooling in the reactor vessel head?
A. Start a CEDM Cooling Unit.
B. Vent the head to the quench tank.
C. Start a Reactor Coolant Pump.
D. . Alternately raise, then lower, RCS pressure.
I Answer D Exam Lovel B Cognitive Level Application Facihty San Onotre 2 & 3 Exam Date 4/16/99 Tier:(1) BW/E01 ek3 3 Manipulation of controls required to obtain RO Group: 2 SRO Group: 2 desired operating results during abnormal and j emergency situations, RO K/A 4.0 SRO K/A 3.9 Reference Title Facility Reference Number Section Page Revision Learning Obj.- I LOCA Bases SO23-14-3 Att.1 52 4 4732 Material Required for Examination
-Question Source: NRC 6/98 i
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I Question #69 Unit 3 is at 100% steady state power. The following data has been gathered concerning RCS leakage:
3.9 gpm leakage into the Quench Tank from RCGVS 3.1 gpm leakage into the Reactor Drain Tank from 3PV0100A 1.8 gpm- leakage past all check valves from RCS to SI system 700 gpd E088 S/G primary to secondary leakage 10 gpd E089 S/G primary to secondary leakage 0.8 gpm leakage into Containment Sump Which of the following is true concerning the above RCS leakage per Technical Specifications? -
A. No Technical Specification entry required.
B. Identified leakage has exceeded the limit.
C. Unidentified Leakage has exceeded the limit.
D. Primary to Secondary Leakage has execeded the limit.
Answer A Eram Level B Cognitive Level Comprehension Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier: (1) CE/A16 Generic 2.1.12 Ability to apply Technical Specificatens RO Group. 3 SRO Group: 3 ,
for a system, i RO K/A 2.9 SRO K/A 4.0 Reference Title Facility Raference Number Section Page Revision Learning Obj.
Technical RCS Operatonal Leakage 3.4.13 3.4-37 Specifications 6574 Material Required for Examination Question Source: New i
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1 Question #70 ;
The following conditions exist on Unit 2: 1 l
A LOCA has occurred
- SIAS, CIAS, and CCAS have actuated The STA reports that the Safety Function Status Check has failed on Inventory Control Which of the following Containment Isolation Valve (s) FAILUREIQ CLOSE would cause a flowpath to outside of containment? .-
A. HV-5388 Instrument Air to Containment isolation Valve.
i B. HV-6223 Train' A CCW Supply Isolation Valve.
J C. HV-9217 and HV-9218 RCP Bleed-off to VCT Isolation Valves. I D. HV-5434 Nitrogen Supply to SIT Isolation Valves.
Aas 4e' C Eum Lev ti B Cogn6ve Level Application Facility San Onatro 2 & 3 Exam Dale 116h Tier: (1) CE/E09 generc 2.4.21 ~ Knowledge of the parameters and RO Group: 2 SRO Group: 2 logic used to assess the status of safety functions.
RO K/A 3.7 SRO K/A 4.3 Reference Title Facmty Reference Number Section Page Revision Learning Obj.
LOCA Bases SO2314-3 Att.1 17 4 Functional Recovery SO23-14-9 Att.1 32 6 6932 '
Bases Material Required for Examination Question Source: New i:
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l Question #71 I l A Shutdown From Outside the Control Room is being performed per SO23-13-2. Plant ;
l conditions are as follows: i RCS pressure is 2050 psia and slowly lowering T-hot is 575 F and slowly lowering T-cold is 555 F and stable !
Pressurizer level (actual) is 21 % and slowly lowering Charging is NQIestablished S/G E089 level (actual) is 58% narrow range l Which of the following statements is correct concerning Natural Circulation for the current plant conditions?
A. Natural Circulation is not established because the plant parameters are outside the guidehnes. !
l B. Natural Circulation is established but cannot be verified until Pressurizer level is I greater than 40%.
C. Natural Circulation cannot be verified until manual control of the ADV's is !
established and T-cold is lowering.
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D. Natural Circulation is established and may be verified. 1 i
I Answer D Exam Level B Cognitive Level Application Facihty San Onofre 2 & 3 L'uam Date 4/16/99 Tier: (1) CEiA13 aa2.1 Facility conditions and selection of appropnate RO Group: 1 SRO Group: 1 l procedures during abnormal and emergency l operations.
RO K/A 2.7 SRO K/A 37 Reference Title Facility Reference Number Section Page Revision Learning Obj.
shutdown Frorn outs
- SO23-13-2 Att.15 103 5 the Control Room 6774 l
Material Required for Examination: Steam Tables Question Source: NRC 6/98 i
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Question #72 j Unit 2 has experienced a loss of offsite power. Following the subsequent Reactor Trip both S/G pressures are noted to be 760 psia and lowering.
What action should be taken?
A. Override and stop the turbine driven AFW pump. )
i B. Declare a cooldown in progress and reset the MSIS setpoints.
C. Shut the MSIVs. l t
D. Shut the MSIVs and reset the MSIS setpoints.
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/A11 ak2.1 Components and functions of control and RO Group: 1 SRO Group: 1 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual features.
RO KIA 3.2 SRO KIA 3.4 Reierence Title Facility Roterence Number Section Page Revision Learning Ooj.
SPTA SO23-12-1 8 15 473l l
Material Required for Examination Question Source: New 1
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- Question #73 i i
1 The following conditions exist:
{
A small break loss of Coolant Accident has occurred HPSI Pumps P018 and P019 have been stopped upon meeting HPSI l Throttle /Stop Criteria '
All three charging pumps are running Pressurizer pressure is 1400 psia and steady i Core exit subcooled margin is 25'F ;
RCS cooldown is in progress Pressurizer level is 28% and slowly lowering Which of the following is an appropriate action for these conditions?
A. Start HPSI Pump P019, and throttle open HPSI Injection valves to restore Pressurizer level. ,
B. Start HPSI Pump P018 and P019 in preparation for reinitiating injection if ,
Pressurizer level continues to decrease. l C. Reduce the RCS cooldown rate to allow Pressurizer level to recover.
D. Start HPSI Pumps P018 and P019, and fully open all llPSI Injection valves until subcooled margin is restored.
Answer A Exam Level B Cognitive Level fy,lication Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) ' W/E02 ek2.2 Facihty's heat removal systems, including RO Group: 2 SRO Group: 1 primary coolant, emerDency coolant, the decay beat removal systems and relations between the proper operation of these systems to the opstration of the facility.
RO K/A 3.5 SRO K/A 39 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
LOCA SO23-12-3 Att. 2 45 15 6511 Material Required for Examination '
Question Source: New
Question #74 Given the following plant conditions:
-. The plant is at 100% power 2FI-0212, charging flow indication is reading 15 GPM Radwaste Operator reports a leak in the charging header between Charging Header Isolation valve, S21208MUO91, and Containment Isolation valve 2HV.9200 Which of the following flow paths could provide flow using a charging pump to the Reactor Coolant System?
C. Auxiliary Spray Flow header.
D. Charging Header Spring leaded Check Valve 2XCV9219.
Answer B Exam Level B Cognitive Level Apphcaton Facihty San Onotre 2 & 3 Exam Date 4/1M4 Ter; (1) W/E04 EK2.1 Components and functions of control and RO Group: '2 SRO Group: 1 safety systeme, including instrumentation, signals, interlocks, failure inodes, automatic ,
and manual features.
)
Reference Title Facility Reference Number Section Pa0e Revision Learning Obj.
RCS Leak SO23-13-14 3.3.2 8 2 j 2907 Material Required for Examination Question Source: New l
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Question #75 Given the following plant conditions:
A Loss of Coolant Accident is in progress RCS pressure is 1600 psia ,
Containment pressure is 12 psig Containment Hi Range Radiation monitors read 13 R/hr and increasing
' No operator actions has been performed Given these conditions, which of the following ESFAS Actuations should NQIhave automatically initiated?
A. CRIS.
B. SIAS. i i
C. CIAS.
D. 'CSAS. ,
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Answer D Exam Level B Cognitive Levol Comprehension Facility San Onofre 2 & 3 Enam Date 4/16/99 Tier:(1) W/E 16 Ek2,1 Components and functions of control and RO Group: 2 SRO Group: 2 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual features.
Reference Title ' Facility Reference Number Section Page Revision Learning Obj. '
Annunciator Panel 57A SO23-15-57A 57A03 13 4 5375 Material Required for Examination Question Source! New i
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l Question #76 A plant startup is in progress and the following conditions exist:
%e reactor is critical at SE-5% power Tave is at 545 degrees F RO inadvertently withdraws Gmup 5 CEAs from 35" to 55" No reactor trip occurs Which of the following describes the effect that this event will have on reactor parameters over the NEXT MINUTE?
A. Reactor Power will rise, Tave will be unaffected.-
B. Reactor Power and Tave will both rise.
C. Reactor Power will be unaffected, Tave will rice.
D. Reactor Power will rise, the response of Tave will depend upon core life.
A.nw. 4 A' Exam Level R Cogratse Level Comprehension Faahty Sar Cniofre 2 & 3 Exam Cat t 416 99 Tier: (2) 001 a1.06 Reoctor Power RO Group: 1 SRO Group:
RO K/A 4.1 SR O K/A
-e Relescoce Title Facility Reference Number Section Page Revision Learning Obj.
Generic Fundamentals-793i Material Required for Examination Question Source: New l-l l
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. Question #77 Given the following: ,
. A less of Coolant Accident has occurred at Unit 2 SO23-12-3 is being implemented The ACO has been directed to STOP all Reactor Coolant Pumps (RCPs)
RCP 2P001 fails to stop when the STOP pushbutton is depressed which of the following is the most appropriate action for stopping 2P00l? -
A. Dispatch an operator to open the breaker to 2P001 locally, at the bus.
B. Dispatch an operator to verify locally that DC power is aligned to 2P001 breaker.
1 C. Deenergize 2A01 by opening the supply breaker from the Reserve Auxiliary ]
Transformer. 1 D. Decnergize Reserve Auxiliary Transformer 2XR3 by opening the breakers from the switchyard.
Answer C Eiam Level R Cognitive Level Apphcation Facdsty San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 003 k2.01 RCPS Ro Group: 1 SRO Group:
RO K/A 3.1 SRO K/A Reference Title Facility Reference Number Sectio Page Revision Leaming Obj.
n Conducts of Operations SO23-0-46 6.16.3 18 0 74gg Transferring 6.9 KV Buses SO23-6-1 6.8 11 4 Material Required for Examination Question Source: NRC 6/98 l
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Question #78 The following conditions are present:
Channel A low DNBR trip is bypassed RCP P001 flow input to CPC Channel B has failed low Which of the following conditions will result in a reactor trip?
A. Loop I hot leg temperature input to Channel B CPC fails high.
B. Loop 1 hot leg temperature input to Channel A CPC fails low.
C. Pressurizer pressure input to Channel B CPC fails high.
D. Pressurizer pressure input to Channel C CPC fails low.
Answer D Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 3/13/99 Tier: (2) 012 RPS K4 02 Automatic Reactor Trip when RPS RO Group: 2 GRO Group:
setto.ats ei n excet2. led for each RPS funcuon; basis for eacn RO K/A 3.0 SROK;A Reference Title Facility Reference Number . Section Page Revision LearninD Obj.
Plant Protecton DBD-SO23-710 2.1.1 70 2 l System 4936 '
Material Required for Examination :
. Question Source: New , I l
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. Question #79 The following sequence of events occurs: l 1
' A LOCA has occurred , I A Safety injection Actuation Signal (SIAS) has started all required ECCS pumps l De diesels are running unloaded i 5 minutes after the SIAS, offsite power is lost l l
Which of the following describes the expected response of the ECCS pumps subsequent to the loss of Offsite Power?
A. All required ECCS pumps restart immediately after their train's EDO output breaker closes.
B. He SIAS will need to be manually actuated to allow all the required ECCS pumps to automatically start.
C. All required ECCS pumps willr/
estart in time delayed sequence.'
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D. The SlAS will han to be reset and the required ECCS pumps started by operator action.
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Answer C Exam Level R Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 i Tier; (2) 013 kl.01 Initiation signals for ESF circuit logic RO Group: 1 SRO Group:
l RO WA 42 SRO WA Reference Title Facility Reference Number Section Page Revision Learning Obj.
Elementary Diagram 30643 7 10397 Material Required for Examination
' Question Source: New i
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- Question #80
( Which of the following statements accurately describes the Power Trip Test Interlock (PTTI) in
!- the Excore Safety Channel System?
A. Simulates a 200% linear power output causing a PPS high linear power trip in the affected channel.
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B. Actuates the LO DNBR and HI LPD CPC trips for the affected channel. !
1 C. Prevents more than one channel of log power being simulated greater than 1.0E-4% power during testing.
D. Gives permissive to manually bypass the LO DNBR and HI LPD CPC trips when reactor power lowers to less than 1.0E-4%.
i Answer B Enm Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/164e Tier: (2) 015 k3.01 RPS RO Group: 1 SRO Group:
RO K/A 3.9 SRO K/A Eenh '.ttion of AT .ser Reference Title Facihty Reference Number Secton Page Revision Learnmg Obj.
Reactor Protective SO23-3-2.12 6.8.6 17 7 System Operaton 7175 Material Required for Examination Question Source: New
Question #81 l Which of the following is an indication that Natural Circulation flow may be lost during EOl implementation?
A. RCS pressure greater than Saturation pressure of the Steam Generator. 1 B. T-hot rising with constant T-cold.
C. Delta-T(Core Exit Thermocouple minus T-hot) equal to 10 F.
1 D. Delta-T (T-hot minus T-cold) of 28 F.
Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 017 a3.01 Indications of normal, natural, and interrupted RO Group: 1 SRO Group: 4 circulationof RCS.
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RO K/A 3.6 S*lO K/A' l Reference Title Facility Reference Number Section Page Revision Learning Obj.
SPTA SO23-12-1 6 15 2536 Alaterial Required for Examination Question Source: Bank I
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Question #82 Given the following plant conditions:
- Unit 2 is at 100% power when an inadvenent SIAS occurs Reserve Auxiliary Transformer 2XR1 relays on sudden pressure Diesel Generator 20002 started and is loaded on bus 2A04 Diesel Generator 2G003 started and tripped 15 seconds later Which of the following is performing the containment cooling function?
A. Containment Normal and Emergency Coolers.
B. Containment Normal and Train "A" Emergency Coolers.
C. Both Train "A" and "B" Containment Emergency Coolers.
D. Only Train "A" Containment Emergency Coolers.
Answer D Exam Level R Cognitive Level Comprehension Facility San Onofre 2 a 3 Exam Date 4/16AJ9 Tier: (2) 07;: K'. 01 cont &nmcot coci.ng system cooluig fans RO Group: 1 SRO Group:
RO WA 30 SRO WA Reference Title Facihty Reference Number Section Page Revision Learning Obj Elementary Diagrams 31248,31249,31250, 14,15,14,15,7 31251,31269 7367 l
Material Required for Examination <
' Question Source: New I
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. Question #83 Given the following plant conditions:
Unit 2 operating at 100% power CCW pump 2P-025 in service and aligned to Train B for single train operation ,
' A ground fault causes a loss of 4KV Bus 2A06 What operator actions are required to restore CCW to the RCPs?
A. ' Ensure start of CCW pump 2P-024 and SWC pump 2P-307.
B. Ensure start of CCW pump 2P-026 and SWC pump 2P-114.
C. Ensure start of CCW pump 2P-024 and transfer Non-critical Loop.
D. Ensure start of CCW pump 2P-026 and transfer Non-critical loop.
Answer C Exam Level R CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Ter: (1) 0?6 aa202 The cause of possible CCW loss RO Group: 1 SRO Grnon:
RO K,A 29 SRO KIA Referenco Title Facihty Reference Number Section Page Revision Leaming Obj.
Lossof CCW/SWC SO23-13-7 3.5 6 3 6739 Material Required for Examination
. Question Source: New t
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L Question #84 l
Given the following:
- Unit 2 is in MODE 6.
- The core is being off loaded to the SFP. j
- Containment Purge valve, HV-9949, is determined to be INOPERABLE.
l What action is required per Technical Specifications LCO 3.9.3, Containment Penetrations?
A. Immediately place containment mini-purge in operation.
B. Isolate the affected purge flowpath within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. I l
C. Deenergize the affected valve in the open position within I hour. l D. Immediately suspend core alterations and movement of irradiated fuel.
Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tser. (2) 028 Generic 2.1.12 Ability to apply Technical Specificatons RO Group: 3 SRO Group:
to a sysWn j
RO K/A 2.9 SRO K/A Reference Title Facility Reference Number Section - Page Revision Learning Obj.
Technical - Containment Penetratons LCO 3.9.3 3.lM 7375 Specificatons Material Required for Examination Question Source: New
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Question #85 Which of the following will cause an actuation that closes the containment main purge isolation valves?
A. liigh Containment Pressure.
B. liigh Containment Temperature.
C. Iligh Containment Radiation.
D. Iow Pressurizer Pressure.
Answer C Exam Level R Cognitive Level Memory Facility San Onofre T. & 3 Eum Date 4/16/99 Tier: (2) 029 K103 Engineered Safeguards RO Group: 2 SRO Group:
RO K/A 3.6 SRO K/A Reference Title Facility Reference Number Secton Page Revision Learning Obj.
Containment Airbome Radiation SO23-3-2.24.11 4.3 4 12 Monitor System Operation 7303 Material Required for Examination Question Source: New
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Question #86 Which of the following is the LEAST preferred source of makeup to the Spent Fuel Pool?
A. Primary Makeup Water (PMW). l B. Boric Acid Makeup Tanks (BAMU).
C. Refueling Water Storage Tanks (RWST).
D. Nuclear Service Water (NSW). I l
Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 033 SFPCS A2.01 Inadequate SDM RO Group: 2 SRO Group:
RO K/A 3.0 SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Obj.
Spent Fuel Purification SO23-3-2.11.1 6.1 3 6 Cross-tie Operation 4582 hlateri.d Required for Exar ination Question Source: New l
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F-Question #87 Given the following plant conditions on Unit 3:
SG Generator E-088 has a known Primary to Secondary leak of 0.3 gpm SG Generator E-089 has a known Primary to Secondary leak of 0.4 gpm Which of the following actions is required by Technical Specifications?
A. No action required.
B. Commence a controlled plant shutdown.
C. Commence a rapid plant shutdown.
D. Manually trip the reactor and perform SPTAs.
Answer A Exam Level R Cognitive Level Comprehension Facility Sa.:Omtre 2 & 3 Exam Date 4/16/99 Tier: (1)' 037 aa220 Tech Spec limits for RCS leakage. RO Group: 2 SRO Group:
RO K'A 3.2 SRO K/A Reference Title Facihty Reference Number Sechon Page Revision Leaming Obj.
Technical RCS Operahonal Leakage 3.4.13 3.4-37 Specihcahons g3g Material Required for Examination Question Source: New i
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Question #88 Given the following:
Unit 3 is at 5% power Temperature is being maintained by the Steam Bypass Control System The Isothermal Temperature Coefficient (iTC) is positive-A total loss of condenser vacuum occurs j All systems are in automatic Which statement correctly describes Reactor response?
A. Positive reactivity will be added, reactor will eventually trip on VOPT.
B. Negative reactivity will be added, reactor power will stabilize above the point of adding heat.
C. Negative reactivity will be added. reactor power will stabilize below the point of adding heat.
D. Positise reactivity will be added, reactor power will increase until the Main Steam Siety Valves lift.
l Answer D Exam Level R Cognitive Level Appleation Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 039 k5.08 Etfeet of steam removal on reactivity. RO Group: 2 SRO Group:
R O K/A 3.6 SRO K/A
- Facility Reference Number Reference Title Section Page Revision Leaming Obj.
Generic Fundamentals 4354 Material Required for Examination Question Source: Bank j
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1 Question #89 De reactor trips from 100% power. The operators verify that the reactor is tripped and immediately note that the turbine has not tripped and the generator breakers remain closed.
Which of the following statements describes the potential conseqtiences of this event?
A. A loss of subcooling, resulting in the need to trip all RCPs.
B. An uncontrolled cooldown of the RCS, resulting in less shutdown margin.
C. A decrease in RCS inventory, resulting in core uncovery.
D. An increase in RCS pressure, possibly resulting in the Pressurizer safety valves lifting.
Answer B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/1&99 Tier: (2) 045 al.05 Expected response of primary plant RO Group: 3 SRO Group: l parameters (temperature and pressure) following T/G inp.
RO K'A 38 SAO K'A Reference Title Facility Reference Number Sectson Page Revision Learning Obj.
SPTA Bases SO23-14-1 Att.1 16 4 8026 Material Required for Examination Question Source: New
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l Question #90 l
l Given the following:
(-
2RT-7870 Condenser Air Ejector Radiation Monitor setpoint is 1.05E-0 Secondary Radiation HI alarm actuates 5 minutes later 2RT-7870 indicates 2.20E-0 Which of the following actions is required for the above conditions?
1 A. Manually trip the reactor and cany out the SPTAs.
B. Commence a controlled plant shutdown and insert rods below 5% reactor power.
C. Commence a rapid plant shutdown and trip the unit at 35% reactor power.
l D. Remain at power, sample all SG's and perform a leakrate calculation.
Answer C Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (?) 055 K 1.Or- PRM system RO Group: 2 SRO Group:
RO K, A 2.6 S AO i< 'A Reference Title Facihty Reference Number Section Page Revision Learning Obj.
1 Reactor Coolant Leak SO23-13-14 3.4.7.4 15 2 i 8201 Material Required for Examination
, Question Source: NRC 6/98 l
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Question #91 Given the following plant conditions:
Unit is initially operating at 100% power
. Condensate Pumps P050, POSI and P052 are initially running Condensate Pump P050 trips Which of the following automatic actions should occur?
A. Heater Drain Pumps will trip on low HDT level B. Condensate Pump P053 will auto start.
C. Recirculation valve for Condensate Pump P050 will auto close.
D. Main Feedwater Pumps will trip on low suction pressure.
Answer B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: O 056 a? 04 Loss of condensatc pumps RO Group: 1 SRO Groun:
RO K, A 2.6 SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Condensate Pump SO23-2-2 Att. 2 23 9 Operation 5364 Material Required for Examination Question Source: New
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j Question #92 l
l Given the following plant conditions:
Unit 2 is operating at 100%
Vital Bus inverter 2Y002 has just failed, deenergizing vital bus 2YO2 Which of the following is correct concerning Auxiliary Feedwater Flow to the steam generators?
A. Only one S/G is being fed. -
B. No AFW components change state.
C. Both S/Os are being fed.
D. P-140 running, neither S/G is being fed.
Answer A Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 4/16/99 Tier; (1) .058 aa2.03 DC loads lost: impact on ability to operate and RO Group: 2 SRO Group:
muib plaat sy<tums.
RO K/A 3.5 SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Obl.
RPS FAILURE / LOSS OF VITAL SO12-13-18 ATT 2 17 of 24 2 BUSINVERTER - 13644 Material Required for Examination Question Source: New L
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' Question #93 A loss of all Feedwater has occurred. Upon restoring Feedwater, the operator opens the MFW Regulator Bypass Valves to 20% for 5 minutes.
Why are these actions necessary?
A. . Ensures S/G feedring is slowly refilled.
B. Allows equalizing temperatun across the S/G.
C. Minimize the possibility of a water hammer event to the tubesheet.
D. Prevents rapid cooldown of the RCS.
Answer A Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exarn Date 4/16/99 Tier:(2) 059 a2.04 Feeding a dry S/G RO Group: 1 SRO Group:
RO K/A 2.9 SRO K/A Reference Title Facihty Reference Number Section Page Rewision Learning Obj.
La* of Feed %ter SC23-14-6 Att. i 14 4 Bases 4734 Material Required for Examination Question Source: Bank
l Question #94 1
An Emergency Diesel Generator (D/G) monthly surveillance test is being performed. D/G load is i indicating 4.7 MWs. l l
Which of the following is correct?
A. D/G load is below the allowable range of the acceptance criteria, and above the minimum limit for dieselloading.
B. D/G load is within the allowable range of the acceptance criteria.
C. D/G load is above the allowable range of the acceptance criteria, and below the maximum limit for dieselloading.
D. D/G load is above the maximum limit for diesel loading.
Answer B Exam Level R Cognitive Level Memory facility San Onofro 2 & 3 Exam Date 4/16/99 Tier: (2) 062 A1.01 Significanceof D/Gloadlimits RO Group: 2 SRO Group:
POlt'a 34 SPO K/A Reference Title Facility Reference Number Secton Page Reviwn Leaming Obj.
Dieset Generator SO23-3-3.23 At'.1 21 14 Monthly Test 6697 Material Required for Examination Question Source: New
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- 1 Question #95 The Control Room was evacuated 15 minutes ago due to dense smoke. A shutdown from outside the control room is in progress.
l Which of tiie followir.g lists the PREFERRED components to be used to establish auxiliary feedwater to steam generator E0897. .
(Assume all AFW components are available) '
A. 1) HV-4763 P141 discharge bypass valve
- 2) HV-4731 AFW isolation valve
- 3) P141 motordriven AFW pump j B. 1) HV-4706 P140 discharge to E089
- 2) HV-4731 AFW isolation valve ;
- 3) Pl40 steam driven AFW pump C. 1) HV-4713 P141 discharge valve
- 2) HV-4731 AFW isolation valve
- 3) Pl41 motor driven AFW pump D. I; ilV-4706 Pl40 discharge to E089 l
- 2) HV-4715 AFW isolation valve
- 3) Pl40 steam driven AFW pump Answer C Exam Level R Cogndive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 068 aat.03 S/G lovel RO Group: 1 SRO Group:
RO K/A 4.1 SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Obj. i Shutdown from Outside So23-13-2 Att. 6 47 5 the Control Room 9444 Material Required for Examination Question Source: New
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Question #96 Which of the following would be the PREFERRED discharge path when performing a radioactive liquid effluent release?
A. Unit 2 with Circulating Water pumps P115 and Pl 17, and Saltwater Cooling pump 2P307 running.
B. Unit 2 with Circulating Water pumps Pl 15, Pl 16 and Pl 18 running.
C. Unit 3 with Circulating Water pumps Pl 15, Pl16, and Pl17 running.
D. Unit 3 with Circulating Water pumps Pl 16 and Pl 18, and Saltwater Cooling pump 3P112 running.
Answer C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 068 Generic 2.1.32 Ability to explain and apply all system RO Group: 1 SRO Group:
limits and precautions RO K/A 3.4 SRO K/A !
Rnforeru:9 Title Facilev Reference Numter . Section Page Revision Le.1rning Otd.
Liquid Radioactive W.iste Release SO23-8-7 Att. 9 127 10 Operations 9066 Material Required for Examination Question Source: New
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Question #97 l Which of the following conditions represents a violation of Containment Systems as described in Technical Specifications?
l A. While at 100% power, a mechanic blocks open the outer containment airlock door for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform maintenance scrivities on the INOPERABLE inner containment door.
B. While performing OPERABILITY tests on the redundant containment loop i Hot leg Sample valves (HV-0508 and HV-0509) at 100% power, one of the two valves (HV-0508) fails to completely close.
C. While at 100% power, the nitrogen supply isolation valve to the Safety Injection Tanks isolation valve (HV-5434) fails its required stroke time.
D. While at 100% power, the outer containment airlock door fails its leak rate test and has to be opened to facilitate repairs that will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Answer A Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date d'16,99 Tier: (1) 069 aa1.01 Isolation vatves. dampers and Ro Group: 1 SRO Group:
electropneumatic devices.
RO K'A 3.5 SRO K/A Reference Title Facility Reference Number Secten Page Revision Learning Obj.
Technical Containment Air Locks 3.62 3.6-3 Specifications 6235
. Material Required for Examination Question Source: New I
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l Question #98 j 1
What is the Instrument Air header pressure at which the Respiratory and Service Air System (RSAS) backup supply will automatically begin to supply the instrument air header?
A. 75 - 80 psig.
1 B. 80 - 85 psig.
l C. 85 - 90 psig.
D. 90 - 95 psig Answer C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/1999 1
Tier: (2) 079 A4.01 Cross-tie valves with IAS. RO Group: 2 SRO Group:
RO K/A 2.7 SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Obj.
Instrument Air System SO23-1-1 6.12 14 12 Operation 6531 I hiaterial Required for Examination Question Source: New I
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I Question #99 ,
I The FIRST action that the Operations Leader performs after ar Alert has been declared is:
A. Station someone on the Ivory Phone. ;
l B. Evacuate personnel from Hazardous areas. !
C. Activate the Emergency Response Data System.
D. Perform siren and PA coordination.
Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date N16/99 4/1&99 Tier: 2.4.29 Knowledge of the emergency plan. RO Group: SRO Group:
RO K/A 2.6 SRO K/A Referenco Title Facility Reference Number Section Page Revision Learning Obj.
Operations Leader SO23-Vill-30 6.1.1.1 4 3 Duties gg7 Material Required for Examination Question Source: Bank j
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4 Question #100 A Main Steam Line Break inside Containment has occurred.
Assuming proper operation of ESFAS Systems and equipment, what is the maximum expected Containment pressure by design?
A. Approximately 37 psig.
B. Approximately 47 psig.
. C. Approximately 57 psig. j D. Approximately 67 psig.
Answer - C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/EOS ok12 Normal, abnormal and emergency F.O Group: 1 SRO Group:
operating procedures associated I with Excess Steam Demand.
RO NA' 32 SRO K/A Refere:te Title Facoity Ruletonco Numaar Secton Page Ra e.41. Learning Obj. 1 Technical Containment B3.6.1 B3.6.1 Specifcatons - 7530 Material Requin d for Examination Question Source: NRC 6/98 i
j Question #101 After securing a Reactor Coolant Pump, what positive indication is available in the Control Room of the RCP being completely stopped?
l l A. Zero speed light on.
B. Green stop light on.
C. Zero (0) amps indicated.
1 D. RCS flow low alarm.
Answer A Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 011 EA1.03 Securing of RCPs RO Group: SRO Group: 1 RO K/A SRO K/A 4.0 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Reactor Coolant Pump SO23-3-1.7 6.3.6 8 21 Operat on 5389 hlaterial Required for Examination
! Question Source: Bank l
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Question #102 l l
l Plant conditions are as follows: ; I l
Unit 2 at 100% power Channel A 2PI-0101-1 Narrow Range Pressure has failed high Channel B 2PI-0102-2 Wide Range Pressure has failed low j_
All actions of SO23-13-18, Reactor Protection System Failure, have been j completed '
Which of the following correctly states the existing coincidence logic to trip the reactor on high I Pressurizer. Pressure?
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! A. 1 out of 2.
B. I out of 3.
. C. 2 out of 3. I D. 2 out of 4.
Answer C Exam Level S Cognitive Level Comprehenskan Facshty San Onofro 2 & 3 Exam Data 4'1699 Tier; (2) 012 K4.02 Automate reactor trp when RPS setpoints are RO Group: SRO Group: 2 exceeded for each RPS function; basis for each.
RO K/A SRO K/A 4.3 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
1 Technical RPS Instrumentation B3.3.1 B3.3-3 Specifcations 7297 !
i Material Required for Exarnination Question Source: New I
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. Question #103 Given the following information on Unit 3:'
1 Reactor power- 100%
- 92 day ESFAS logic matrix relay testing is in progress Control Room airborne radiation monitor RE-7824 is in BYPASS for maintenance-During the performance of the logic matrix test, the trip matrix being tested was prematurely de-energized, resulting in Trains "A" & "B" SIAS and CCAS actuation Which of the following is the expected systems response to the above conditions?
I A.- CRIS actuation is blocked.
B. CRIS occurs on Train "A" only.
C. CRIS occurs on Train "B" only.
D. CRIS occurs on both Trains.
I Answer D Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 013- kl.01 initation signals for ESF circuit logc. RO Group: SRO Group: 1 RO K/A SRO K/A 4.4 l
Reference Title Facility Reference Number Section Page Revision Learning Obj. l Control Room Airborne Process SO23-3 2-24.6 46 4 5 Radiation Monitoring System Operation 6999 Material Required for Examination Question Source: NRC 11/98 I
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Question #104 )
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l- .What is the basis for the Shutdown Margin requirement of 3% Delta K/K with T-ave less than ;
200 F?
l A. Removal of the CEAs during refueling.
B. Reactivity effect from further cooldown to Mode 6.
C. A potential dilution event.
D. Allow for errors in enrichment of the new fuel load. I Answer C Exarn Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 AA2.06 When boron dilution is taking place. RO Group: SRO Group: 1 RO K/A SRO K/A 3.7 Reference Title Facility Reference Number Section Page Revision Learning Obj.
l Technical Shutdown Margin B3.1.2 B3.1-7 Specifcations 6957 Material Required for Examination Question Source: Bank
Question #105 Which of the following valves would be throttled open by the operator to increase the RCS cooldown rate with Shutdown Cooling in service?
A. Shutdown Cooling Heat Exchanger inlet valve.
B. Shutdown Cooling Heat Exchanger outlet valve.
t C. Shutdown Cooling Heat Exchanger CCW outlet valve. l D. Shutdown Cooling Heat Exchanger CCW inlet valve. )
Answer B Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 025 AA1.01 RCS/RHRS cooldown rate. RO Group: SRO Group: 2 l
RO K/A SRO K/A 3.7 Reference Title Facdity Reference Number Section Page Revision Learning Obj.
SDC System Operation SO23-3-2.6 6.2.8.2 8 15 8036 Material Required for Examination Question Source: Bank l
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o L ' Question #106 he plant has just tripped from 50% power operation, the SPTAs are being carried out and plant conditions are as follows:
Pressurizer pressure is 650 psia Containment average temperature is 251 F Both S/G levels 40% NR Both S/G pressures 800 psia Which ESFAS signal combinations should have automatically actuated?
A raw - B E als Levci 5 Ccgnibv. LunJ Comprel4 u.on Fac.let Sat.Os%* e 2 & 3 Exam Dato 1/16/tc Tier:(2) 026 A1.01 Containment pressure RO Group: SRO Group: 1 RO K/A SRO K/A 42 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Technical ESFAS Instrumentation 3.3.5 3.3-26 Specifications 7303 Material Required for Examination Question Source: New i
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Question #107 Bo'th trains of CCW/SWC are in operation.
What is the reason for aligning the letdown Heat Exchanger to the Critical loop that is supplying the Non-Critical Loop? i A. Reduces the potential for RCP seal deterioration by minimizing the temperature differential in the Non-Critical Loop.
l B. Maintains heat load requirements distributed evenly between the loops.
C. Sets loop flows to match operating pressures of the loops to minimize cross train leakage. l l
D. Ensures that CCW process radiation monitor is aligned to detect any 12tdown l Heat Exchanger tube leakage.
Answer D Esam iavel S CognitiveLevel Memory Facility San Onofre 2 & 3 Exam Date C16/99 Tier; it) 026 AA:: u2 Tt.9 cause of pt ss ble CCW loss. RO Group: SRO Giocp: 1 !
R O K/A SRO K/A 3.6 l i
Reference Tdle Faciisty Reference Number Section Page Revision Learning Obj. j CCW System ' SO23-2-17 Att. 7 56 12 Operation 6257 l Material Required for Examination Question Source: NRC 11/98 i
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l E ~ Question #108 The following conditions exist:
A large break LOCA occurred on Unit 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> ago SO23-12-3, " Loss of Coolant Accident"is being implemented.
Hydrogen Monitors initially indicated 0.7%.
Following calibration Hydrogen concentration indicates 2.6%.
All ESFAS equipment is available and functioning normally.
Which of the following actions is required to satisfy the Containment Combustible Gas Control safety function of SO23-12-37 A. Ensure both Hydrogen Recombiners energized and Containment Spray in service. ,
B. Ensure the Hydrogen Purge System in service and all Containment Dome Air j Circulating Fans operating. l C. Ensure both Hydrogen Recombiners energized and all Containment Dome Air ;
Circulating Fans operatmg. !
D. Ensure both Hydrogen Recombiners energized and Hydrogen Purge System in !
service, j
l Answer C - Exam Level S CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2)- 028 Generic 2.120 Ability to execute procedure steps RO Group: SRO Group: 2 RO K/A SRO K/A 42 l Reference Title Facility Referenca Number Section Page Revis'an Learning Obj. I LOCA SO2312-3 Att.1 26 15 2548 Material Required for Examination Question Source: New i
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Question #109' Which of the following radiation monitors will cause the initiation of the Containment Purge Isolation Signal (CPIS)?
A. RE-7828 Containment Purge Stack Rad Monitor.
B. RE-7820 Containment High Range Rad Monitor.
C. RE-7808 Plant Vent Stack Rad Monitor.
D. RE-7804 Containment Airbome Rad Monitor.
Answer D Exam Level S Cogndive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 4 Tier: (2) 029 K1.03 Engineered safeguards RO Group: SRO Group: 2 RO K/A SRO K/A 3.8 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Containment Purge and SO23-1-4.2 Att.13 73 22 Recirculation Filtration 7550
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Material Required for Examination Question Source: Bank
Question #110 Given the following:
- - The plant is in MODE 3 A reactor startup is in progress Reactor power is at 2E-7%
CEAs are being withdrawn Subsequently BOTH startup channels fail to zero Which of the following describes the action (s) to be taken?
A. Continue approach to criticality using safety channel power indication.
B. Immediately' trip the Reactor.
C. Immediately stop all positive reactivity additions.
D. Commence a reactor shutdown.
Answer C Exam Level S CognitiveLevel Comprehension Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier. (1) 032 Gerw;ric 2.1.12 Ability to apply Technical Specifications to RO Group. SRO Group: 2 a syt, tern.
RO K/A SRO K/A , 4.0 Reference Title Facility Reference Number Section Page Revision Leaming Obj.
Technical . Doron Dilution Alarm 3.3.111 3.3-111-1
- 3182 Specifications Material Required for Examination Question Source: New t
p Question #111 The following conditions exist on Unit 3:
Reactor power is 100%
At 1200 a known tube leak of 0.05 gpm exists in E089 At 1300 the leak increases to 0.075 gpm At 1400 the leak increases to 0.090 gpm At 1500 the leak increases to 0.12 gpm Secondary radiation monitor response confirms increases What action, if any, is required as a result of the increasing S/G tube leak as directed by SO23-13-14" Reactor Coolant leak"?
A. - Operation of the unit can continue.
B. The reactor should be tripped immediately.
C. A rapid shutdown must be initiated.
D.- A controlled shutdown must be completed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Answer D Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Cate 4/1&99 4 Tier:(1) 037- AA2.05 Past history of leakage with current problem RO Group: SRO Group: 2 RO K/A SRO K/A 3.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Reactor Coolant Leak SO23-13-14 3.4.7.5 15 2 6574 I
Material Required for Examination Question Source: NRC i1/98 l
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1 Question #112 During coastdown prior to a refueling outage, system frequency increases to 60.5 hertz. How will the RCS respond?
A. Temperature increases, pressure increases.
B. Temperature increases, pressure decreases.
C. Ter r.iature decreases, pressure decreases, q l
i D. Temperature decreases, pressure increases, j Answer A Exam Level S CognitiveLevel Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 039 A5.08 Effect of steam removal on reactivity RO Group: SRO Group: 2 l
RO K/A SRO K/A 3.6 Reference Title Facility Reference Number Section Page Revision Learning Obj. j Generic Fundamentals 4354 l hlaterial Required for Examination Question Source: New
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. Question #113 ,
Unit 2 is operating at full power when a loss of 125VDC Bus 2D5 occurs.
I What effect does this have on the Unit 2 Turbine / Generator? !
A. A main generator automatic trip will occur.
I B. The turbine will trip on overspeed. l i
C. De turbine emergency oil pump motors will lose power.
D. The Turbine Stop and Governor valves will go closed.
Answer D- Exam Lovel S Cognitive Lovel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 058 AA2.03 DC loads lost; impact on ability to operate and RO Group: SRO Group: 2 rnonitor plant systems.
RO K/A SRO K/A 3.9 Reference Title Facility Reference Number Section Page Revision Learning Obj. l Operation of 125 VDC SO'?3-6-15 Att.13 71 13 glgg l Syst;ms Material Required for Examination Question Source: NRC 11/98 I
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Question #114 i i
Which'of the following is the correct response if an Emergency Diesel Generator (EDG) is !
paralleled to the grid and both the governor and voltage control pushbuttons are taken to
" Raise"?
i A. EDG KW increases and EDG speed increases.
B. EDG reactive load increases and EDG KW increases.
C. EDG frequency increases and EDG reactive load inen ases.
D. EDG speed increases and EDG frequency increases.
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Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 8 3 Exam Date 4/16/99 i l
Tier. (2) 062 A1.01 Significanceof D/Gloadlimits RO Group: 2 SRO Group: 2 RO K/A 3.4 SRO KIA 3.8 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Diesel Generator SO23-3-323 Att.1 21 14 Voettil. Test 7152 Material Requi.ed for Examination '
Question Source: New I
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Question #115 The Control Room has been evacuated due to a toxic chemical hazard inside the Control Room envelope. Shutdown from outside of the Control Room, SO23-13-2 is in progress: ;
At the EPPM L-411:
SG E-088 Wide Range T2 vel, L1-1106 indicates 55%
- RCS Teold, indicates 530 F
- RCS Thot, indicates 548 F S/G pressure indicates 900 psia Determine the actual water level in steam generator E-088.
A. 35%.
B. 48%.
C. 58%.
I D. 75 %
Answu C Enam Lovel S Cognitive Level Apphcation Facility San Onofre 2 & 3 Enam Date 4/16/99 Tier: (1) 068 1.03 S G level RO Group: SRO Group: 1 RO K/A SRO K/A 4.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Shutdown from Outside SO23-13-2 Att. 4 35 s the Contro! Room 63025 Material Required for Examination SO23-13-2, Attachment 4 Question Source: Bank l
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- Question #116 Tie following conditions exist during a Unit 2 refueling:
Core offload is in progress Steam Generator E089 is being sludge lanced An operator repons that Main Steam Relief Header Drain Valve, S2130lMU394, on S/G E089 is removed Which of the following actions is required?
A. Restore Containment integrity within one hour.
B. Suspend Core Alterations.
C. Initiate Manual Containment Purge isolation Signal.
D. Verify containment leakage is within specifications.
Answer B Exam Level S Cognitive Level Comprehension - Facility San Onofre 2 & 3 Exam Date 4/1fi/99 Titsr. (1) 009 aal.01 Isolation valves, dampers and RO Group: SRO Gtuup: 1 l clectropneumate devces l RO K!A SRO K/A 3.7 Reference Title Facristy Reference Number Section Page Revision Learnirm Obj.
Technical Containment Penetrations 3.9.3 3.9-4 Specifications 7773 _,
Material Required for Examination ,
Question Source: Bank l 1
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p Question #117 Given the following plant conditions:
Unit 2 is at 20% power Tc is currently at 534 F Which of the following does the Technical Specifications require?
A. Perform SR 3.4.2.1.
B. Enter LCO 3.4.1 Condition C.
C. Enter LCO 3.4.2 Condition A.
D. Perform SR 3.4.3.1 Answer A Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.33 Ability to recognize indications for system operating parameters RO Group: SRO Group:
which are entry level conditons for Technical Specificatons.
RO K, A SRO K/A 4.0 Reierence Title FaC4y Reference Number Section Page Revision Learning Ott Technical RCS k'eoimum Temperature 3.4.2 3.44 g3g Specifications for Cntulity Material Required for Examination: T.S.s 3.4.1,3.4.2,3.4.3 (Bases not required)
Question Source: Bank
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1 Question #118 !
The Unit is in MODE 1. The Spent Fuel Pool Boron Concentration is 1825 ppm. 1 Which of the following states the required actions for this condition?
l A. Immediately suspend movement of fuel in the spent fuel pool and initiate action to restore boron concentration. e B. Within I hour install local Criticality Accident Radiation Monitor and initiate ,
action to restore boron concentration.' !
C. Immediately initiate a Fuel Handling Isolation Signal and action to restore boron I concentration.
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D. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> suspend movement of fuel in the spent fuel pool and initiate action ;
to restore boron concentration. I Answer A Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Ta ': 2.2 31 Knowtmin of SRO fuel handkng responsituhhen Ro Group: SRO Group:
l Ro KlA SRO K/A 3.8 Reference Title Facihty Reference Number Section Page Revision Leaming Obj.
Techrncal Fuel Storage Pool Boron 3.7.17 3.7-30 I Specifcations Concentration 7949 Material Required for Examination Question Source: Bank
L Question #119 A Gaseous Effluent Reiease Permit requires a Weather Evaluation prior to the release. The following meteorological conditions exist:
Wind direction is 210 degrees Temperature difference between 10 and 40 meters is minus 0.26 C X/Q value is <4.8E-6 Determine the MINIMUM wind speed which would allow the release to be commenced.
A. 44 mph.
B. 69 mph.
C. 82 mph.
D. 100 mph.
Answer B Exam Level S Coqnitive Level Apphcation Facihty San Onofre 2 & 3 Exam Date 4/1689 Tier: - 2.3.11 Abd.ry to controi radiatior, eesmsm RO Group. SRO Group:
RO K/A SRO K/A 3.2 Ref erence Tale Facihty Reference Number Section Page Revision Learning Obj.
Radwaste Gas SO23-8-15 Att 4 35 11 Discharge 6268 Material Required for Examination: SO23-8-15 Attachment 4 Question Source: NRC 6/98 1
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Question #120 Unit 2 is in MODE 5 on Shutdown Cooling.
- While maintenara was being performed on LTOP isolation valve 2HV9339, the valve packing failed.
- Pressurizer level is lowering with the only available charging pump running.
The less of SDC AOI has been entered and a HPSI pump has been started to restore level. !
- HPSI pump flow required to maintain Pressurizer level is 150 gpm. !
Which of the following is the correct Emergency Event Classification?
l A. None apply. i B. B3- 1.
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^ D. B2- 1. <
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Answer C Exarn Level S Cognitwo Lewd Apt..:ral on Faility Sat. Coe:rc 2 & 3 E.am Dato 4 :sta l l
Tier: 2.4.29 Knowledge of the emergancy plan RC Group: SRO Group: j RO K/A SRO K/A 4 0
{
Aeference Title Facility Reference Number . Section Page Revision Learning Obj. l l
EPIP SO123-Vill-1 Att,2 50 11
]7479 i Material Required for Examination: SO123-Vill-1 Attachment 2 Question Source: New l
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! ' Question #121 Unit 2 reactor has tripped. The Control Room is being evacuated due to dense smoke.
Which of the following correctly identifies the order in which the "lMMEDIATE ACTIONS" for l Shutdown From Outside the Control Room AOi, SO23-13-2 are to be completed?
A. 1.) Manually initiate MSIS ;
2.) Stop all RCPs j 3.) Select manual and stop all Charging Pumps i
B. 1.) Select manual and stop all Charging Pumps l 2.) Manually initiate MSIS 3.) Stop all RCPs C. l.) Manually initiate MSIS 2.) Select manual and stop all Charging Pumps 3.) Stop all RCPs D. 1.) Stop all RCPs 2.) Manually initiate MSIS 3.) Select manual and stop all Charging Pumps l l
Answer C Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Dato 4/16,99 Tier: 2.4.49 Abihty to perform without reference to procedures those RO Group: SRO Group:
actions that require immediate operation of system components and controls RO K/A SRO K/A 4.0 j Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Shutdown from Outside SO23-13-2 2.0 2 5 the Control Room 6460 Material Required for Examination Question Source: Bank
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Question #122 Given the following:
A reactor trip has occurred from 100% power All systems have responded normally No operator actions have occurred The following conditions are observed:
Pressurizer levelis 28%, and rising RCS pressure is 2225, and rising RCS temperature is 545'F, and stable Both S/G levels are 35%, and rising Both S/G pressures are 1000 psia, and stable l k
Given these conditions, which of the following statements correctly describes the feedwater configuration to the S/Gs?
A. MFW only is supplying feedwater to both S/Gs.
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B. AFW only is supplying feedwater to both S/Gs.
1 C. ' MFW and AFW are both supplying feedwater to both S/Gs.
D. No feedwater is being supplied to the S/Gs. A; % will have to be manually ,
aligned to supply feedwater.
Answer A Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) CE/E02 ok2.2 Facility's heat removal systems, including RO Group- SRO Group: 2 primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operaton of these systems to the operationof the facihty RO K/A SRO K/A 40 Reference Title ' Facihty Reference Number Section Page Revision Learning Obj.
Reactor Trip Recovery SO23-12-2 5 13 6509 I
Material Required for Examination Question Source: Bank 1
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Question #123 An Excess Steam Demand Event is in progress. The affected Steam Generator has just boiled !
dry. I Which of the following actions must be taken to ensure RCS pressure control is satisfied?
A. Ensure Emergency Feedwater Actuation Signal is actuated.
B. Establish maximum Safety injection Flow.
I C. Initiate Safety Injection HPSI Throttle /Stop.
D. Ensure letdown system in service.
Answer C Exam Level S Cognnive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 l
Tier: (1) CE/EOS ekt.2 Normal, abnormal and emergency cperating RO Group: SRO Group: 1 )
procedures associated with Excess Steam Demand.
RO K/A SRO K/A 3.8 Feference Title Facil.ty Petereace Nunibe, Section Paqo Revision Learning Guj.
ESDE Bases SO23-14-5 Att 1 11 4 6905 Material Required for Examination Question Source: New 1 l
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Question #124 l
Which of the following is NOT a direct advantage of forced circulation during recovery from an Excess Steam Demand Event (ESDE)?
A. Instrument response to operator actions.
B. Reactor vessel head cooling.
C. Pmssurizer pressure control.
D. Pressurizer level control. 1 Answer D Exam Level Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/EOS ek3.2 Normal, abnormal and emergency operating RO Group: SRO Group: 1 ;
procedures associated with Excess Steam i Demand. I l
RO K/A SRO K/A 3.8 j Reference Title Facility Reference Number Secton Page Revision Learning Obj.
ESDE B tres SO23-14-5 Att.1 39 4 6q)6 )
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- Question #125 Given the following plant conditions:
Per SO23-12-1, SPTAs, a LOCA has been identified Pressurizer pressure is 1250 psia Pressurizer level is 100% -
HPSI injection valves are fully open RCS is 17 F subcooled RVLMS indicates 100% in plenum and 48% in upper head No RCP's are running Containment temperature and pressure are 195 F and i I psig, respectively
- SIAS, CIAS, MSIS and CSAS have actuated A cooldown is in progress using steam generators
.Which of the following actions should be directed by the CRS?
A. Throttle HPSI flow to allow depressurization of the primary system.
B. 'llirottle HPSI flow to restore pressurizer level to program.
C. Continue maximum injection flow until subcooling is restored.
D. Continue maximum injection flow until the RVLMS indicates the upper head is full.
Answer C Exam Level S Cognitive Level Applicaton Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) W/E11 ek22 Facility's heat removal systems, including RO Group: SRO Group: 2 primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the f acility.
RO K/A SRO K/A 4.3 Reference Title - Facility Reference Number Section Page Revision Learning Obj.
LOCA Bases SO23-14-3 Att.1 48 4 6511 Material Required for Examination:
Question Source: Bank 1
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