ML20199K081
| ML20199K081 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/21/1999 |
| From: | Hurley L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9901260331 | |
| Download: ML20199K081 (82) | |
Text
I
- SA "'4g UNITED 8TATES y k NUCLEAR REGULATORY COMMISSION
- ,e
) REGION IV 511 RYAN PLAZA DRIVE, SUITE 400
, ARLINGTON, TEXAS 76011-8064 January 21,1999
{
NOTE TO: NRC Document Control Desk Mall Stop O-5-D-24 FROM: Laura Hurley, Licensing Assistant Operations Branch, Region IV
SUBJECT:
OPERATOR LICENSING WRITTEN RETAKE EXAMINATION ADMINISTERED ON DECEMBER 18,1998, AT ARKANSAS NUCLEAR ONE, UNIT 1.
DOCKET #50-313 On December 18,1998, an Operator Licensing Retake Examination was administered at the referenced facility. Attached you will find the following information for processing I through NUDOCS and distribution to the NRC staff, including the NRC PDR:
Item #1 - Facility submitted outline and the initial exam submittal for distribution under RIDS Code A070.
Item #2 - Examination Report with the as given written examination attached, designated for distribution under RIDS Code IE42.
If you have any questions, please contact Laura Hurley, Licensing Assistant, Operations Branch, Region IV at (817) 860-8263.
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. i l i L i l PWR RO Examination Outline Worksheet Based on NUREG-1021 Form ES-401-4 Pg 30 of 30 trdertm Rev.8, January 1997
! KIA Category Points Tier Group N Average i
Totai Total Dev. :
' K1 K2 K3 K4 K5 MS A1 A2 A3 A4 G ,
i Tier 1 1 3 3 16 16 2 3 2 16 f6 ,
Pant,l 5 5 Evolidions 1 _0_1 1 6 6 9 7 6 3 37 37 -6.17 f.94 T
Ter2 1 3 0 1 3 -1 0 1 2 3 2 1 17 17 Plant 2 3 1 3l3l1 l2l1 l3l2 l3 l1 l 23 23 .
i systems 3 2 1 1 l1 l0 l1 l0l0l1 l2l1 l 10 10 B 2 5 7 2 3 2 5 6 7 3 50 50 4.55 2.25 Tem Tier 3 cati cata c Generic 3 4' 3 3 13 13 j Total 100 100 l
K/AIG/ Totals 14 8 14 7 2 3 9 11 6 7 19 100 9 09 5 07 b
< o .
4 Cr
%> ~
m ,
Emergency and Atmormal Plant Evolutions -TierifGroup1 -
EAAPE # # Namei Safety Function K1 K2 K3 A1 A2 G K1A Toper 4s) Imp. Points 005 AK3.06 KnoMedge of the reasons for the fogowing responses as they apply to the 000005 Inoperable / Stuck Control Rod I1 0 0 1 0 0 0 InaperstdarstuckControlRod Actions contained in EOP for inoperablektuck control i rod. 3.9 1 017 AK1.02 Knowledge of the opershonal 000015f17 RCP Marunchons /N 1 0 0 0 0 0 "D i apply to RCP Matunchons. Consequences of an RCPs faRure. 3.7 1 l
B&W E09 EK3.2 Knowledge of the reasons for the follomng responese as they apply to BWE09; CE/A13; WE09&E10 Natural Cire.1 N O O 1 0 0 0 the (Natural Circulebon Cooldown): Normal, abnormal and energency operating procedures W with Natural Carculation Cooldown. 3.0 1 000024 Emergency Be abon /I O O O 1 0 0 13 % b W 9 h the fonowing as they apply to the w -y Boretion: Boric acid flow controller 3.2 1 ocooze Less or componece c ans wenn s we 0 0 0 0 0 0 0 027 AK2.03 Knowledge of the irterreimbons 000027 Proseurizer Pressure Control SW D 1 0 0 0 0 Matunchon /ll1 Melfunctone and the following Controllers and poolhonors 2.6 1 040 AK3.04 Knowledge of the reesons for 000040 (BWE05; CEE05; WE12) Steam Line *E""""
0 0 1 0 0 0 >
Rupture- Excessive Heat TransferIN Steam Line Rupture: Acbons contamed in EOPs for steem line rupture 4.5 1 ;
caratt vweos mes omenano-Ptsiiv 0 0 0 0 0 0 -
o 000051 Lores of Condenser Vacuum IIV O O O O O 1 2.1.20 Ability to execute procedure steps. 4.3 1 000055 Station BlockoutIVI O O O 1 0 0
^
follomng as they apply to a Stubon Blackout Restorehon of power with one ED/G. 4.1 1 ococen .rvestme sise. inst eustvi 0 0 0 0 0 0 0 062 AA2.02 Ately to determee and interpret 000062 Loes d Nucieer Service Water f lV 0 0 0 0 1 0 possible SWS loss. 2.9 1 Justified due to impor;ance of understanding how fires are 067 AK2.01 Knowledge of the interrelabons 000067 Plant Fire OreIIX 0 1 0 0 0 0 between the Plant Fire on Site and the N P"*""#"
followmg
- Sensors, detectors, and valves.
Kh e,u,.e,m not - .
2.3 1 property i
PWR RO Examination Outline Emeritency and Abnormal Plant Evolutions -TierilGroupi -
EfAPE 8i Namei Safety Funcuen K1 K2 K3 I A1 A2 G Kl4 Topic (s) Imp. Points nnnnna (BWIA06) Control Room Evac. IVIII O O O O 1 0 068 M M % e h W W the fokming as they apply to the Control Room Evacushon: Avelimb5ty of heat sinic. 4.2 1 069 AK3.01 Knowledge of the remoons for s the fokming roeptm as they apply to the 000069 (W/E14) Loss of CTMT Integrity IV O O 1 0 0 0 Laos of Containmentintegrty Guidance cortained in EOP for loss of conhunment ,
integrity 3.8 1 074 EK1.03 Knowledge of the opershonal i unplicebens of the following concepts as they 000074 (W/E06&E07) Inad. Core Cooling i V 1 0 0 0 0 0 apply b the IrW=8= Core Cooling-.
Processes for removing decay heat from core. 4.5 1 B&W E03 EK2.1 Knowledge of the enerreimeans between the W=s=
Subcooling Margin) and the followinir BW/E03 Inedequate Subcooling MarginIN O 1 0 0 0 0 Components, and fundions of control and safety systems, including instrumentshon, ;
signals, intertocks, failure modes, and automshe and manuelfeatures 3.4 1 076 AA1.04 Ability to operate ander montior i 000076 High Reector Coolert ActMty llX 0 0 0 1 0 0 p
monitonna equipment. 3.2 1 B&W A03 AK1.3 Knowledge of the opersoonalimplications of the folloung BW/A02&A03 Loes of NN1-XtY1Vil 1 0 0 0 0 0 Annuncistors and condihons, indicshng sognels, and remedal schons ===ar-s=rt with ,
the NNI-Y. 3.0 1 l 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KIA Category Totmis: 3 3 4 3 2 1 Group Point Total = 16 16 l
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PWR RO Extmination OutHne Emergency rnd Abnormal Plant Evolutions -Tier 1/ Group 2 ,
EIAPE # # NameiSafety Function K1 K2 K3 A1 A2 G KlATopic(s) Imp. Points ococot coeween noe wees=d te 0 0 0 0 0 0 0 ,
003 AK3.04 Knowkdge of the reasons for 000003 Dropped Contrd Rodi1 0 0 1 0 0 0 Dropped Control Rod: Achons contained in EOP for dmpped control rod. 38 1 B&W E02 EA2.1 Atwhty to determns and eterpret the fotowirig as they apply to the 000007 (BW/E02&E10; CE/E02) Reactor Trip -
0 0 0 0 1 0 # ;
Statszation- Recovery /l condibons and selecbon of appropnate procedures during abnormal and emergency conditions. 2.5 1 B&W A01 AK2.2 Knowledge of the nterrelations between the Plant Runbeck and i BW/A01' Plant Runbeck /l 0 1 0 0 0 0 ricluding pnmary coolant, emergency coolant.
the decay heat removal systems, and reishone between the proper opershon of these systems to the opershon of the faciNty. 3.5 1 i B&W A04 AK1.3 Knowledge of the opershonalimplicehone of the foRowng BW/A04 Turbine Trip / N 1 0 0 0 0 0 Annunciators and condinons, mdicabng ssgnals, and remedia! acbons associated with the Turbine Trip. 3.2 1 occoos P= www v.per spec.ws a 0 0 0 0 0 0 0 009 EA1.18 Arnhty to operate and monitor the 000009 Smal Break LOCAlil! O O O 1 0 0 followng as they apply to a SmaR Breek LOCA: Balancog of HPIloop flows. 3.4 1 coocit tes.se toca t a 0 0 0 0 0 0 0 wEo4 LeCA oues.Comewwatr a 0 0 0 0 0 0 0 B&W EOS EK1.2 Knowledge of the BW/E08; W/E03 LOCA Cooldown/ Depress. IIV 1 0 0 0 0 0 , g Cooidown. Normal, abnormel, and emergency procedures associated with LOCA Cooldown. 3.5 1 l
weii teen er em.m.acy cem-o.cee. ilv 0 0 0 0 0 0 0 user si Teme=s.a s s 0 0 0 0 0 0 0 022 AK1.01 Knowledge of the opershonal rnpncehons of the fonowmg concepts as they 000022 Loss of Reactor Coolant Makeup Ill 1 0 0 0 0 0 apply to Loss of Reector Cooient Makeup:
Cor sequences of thermal shock to RCP seals. 2.8 1 025 AK2.02 Knowledge of the interrelatoons 000025 Loss of RHR System / IV O 1 0 0 0 0 fonowmg: LPI or Decay Heat Removal /RHR pumps. 3.2 1 .
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PWR RO Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1/ Group 2 EIAPE #1 NameiSafety Functkm K1 K2 K3 A1 A2 G KIA Topic (s) Imp. Points 000029 Anbespeted Transient Wb Scram 11 0 0 0 0 0 1 W 0% e w immediate action steps. 4.3 1 032 AK3.01 KnoMedge of the reasons for the foiiowing responses as they apph to the 000032 Loss of Source Range NIIVil 0 0 1 0 0 0 Loos of Source Range Nuclear instrumentation: Startup termnation on source 4ange loss. 3.2 1 otoon tese er - mease se a vii O O O O O O O 037 AA2.16 Ability to determine and interpret 000037 Steam Generator Tube LeekIm 0 0 0 0 1 0 the fokwng as they apply to the Steam Generator Tube Leelt Pressure at which to mentain RCS during SK3 cooldown 4.1 1 038 EK3.06 Krm4 edge of the reasons for the followmg responses as they apply to the 000038 Steem Generator Tube Rupture 11!! O O 1 0 0 0 SGTR: Achons contained in EOP for RCS water inventory belance, S/G tube rupture, and plant shutdown procedures. 4.2 1 cocos 4 tesmtm to ervemross eieraw 0 0 0 0 0 0 0 B&W E04 EA2.1 Ability to determine and BW/E04; W/EOS Inndequate Heat Transfer - Loss **
0 0 0 0 1 0 of Secondary Heat Sink flV Inadegate Heat Transfec Facility w-J6.
and seiechon of appropnote procedures during abnormal and -w ,cy procedures 32 1 058 AK3.02 Knowledge of the reasons for
059 AA1.01 Ab&ty to operate and/or monitor 000059 Accidentalliquid RadWaste ReL ilX 0 0 0 1 0 0
- WI Liquid Redweste Reisese: Radioactrve bquid ;
monitor 3.5 1 ococeo acemeniet oe== eve noe esmo not a m 0 0 0 0 0 0 0 061 AA1.01 Abihty to operate and/or more the following as they apply to the Aree 000061 ARM System AlarmsIVII O O O 1 0 0 Rh W (ARW SW h Automshe actuation 36 1 VWE16 MgM centsewnent Reemem s m 0 0 0 0 0 0 0 cEEoD Funesecel Reawary 0 0 0 0 0 0 0 KIA Category Totals: 3 2 4 3 3 1 Group Point Total = 16 16
PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1tGroup3 '
E/ APE # / Name / Safety Function K1 K2 K3 A1 A2 'G N/A Topic (s) Imp. Points 2.1.28 Knowledge of the purpose and 000028 Pmssurizer Level Malfunction / ll 0 0 0 0 0 1 function of major system components and controls. 3.2 1 036 AK2.02 Knowledge of the intenelations 000036 (BW/A08) Fuel Handling Accident / Vill 0 1 0 0 0 0 between the Fuel Handling Incidents and the following: Radiation monitoring equipment (portable and installed). 3.4 1 056 AK3.02 Krc.W of the reasons for 000056 Loss of Off-site Power / VI O O 1 0 0 0 the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for Loss of Offsite Power. 4.4 1 065 AA2.08 Ability to determine and "I **
- 000065 Loss ofInstrument Air / Vill 0 0 0 0 1 0 Loss of instrument Air: Failure modes of air-operated equipment. 2.9 1 B&W E13 EA1.1 Ability to operate and monitor the following as they apply to the EOP Rules: Components, and functions of BW/E13&E14 EOP Rules and Enclosures 0 0 0 1 0 0 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. 3,4 1 ewrA08 Emergency Diseul Amuseon tvt 0 0 0 0 0 0 0 SW/A07 Roomne iVM 0 0 0 0 0 0 0 cs/Aiseno mcsteahme in 0 0 0 0 0 0 0 weis sesem oenorsoor o==r-pe===ur. I w 0 0 0 0 0 0 0 wets conishwnere naamne rv 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 K/A Category Totals: 0 1 1 1 1 1 Group Point Total = 5 5
Plant Systems. Tier 2/my1 System Numbert Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4' 4 KIA Topic (s) Imp. Points ;
001 K4.03 Knowledge of CRDS design feature (s) 001 Control Rod Drive 0 0 0 1 0 0 0 0 0 0 0 and/or interiock(s) which provide for the folowing:
Rod Contol @ 3.5 1 001 A2.14 Abilityto(a)predicttheimpacts of the foRowmg malfunction or operations on the CRDS i
- and (b) based on those predicbons, use procedures to correct, control, or mitigate the l 001 Control Rod Drive 0 0 0 0 0 0 0 1 0 0 0 consequences of those maffunctions or operations: Urgent failure alarm, induding rod-out-of-sequence and motion 4nhibit alarms. !
t 3.7 1 003 K1.03 Knowledge of the physical connections ,
and/or cause effect relationships between the '
003 Reactor Coolant Pump 1 0 0 0 0 0 0 0 0 0 0 RCPs and the foRowing systems: RCP seal system. 3.3 1 2.1.7 Ability to evaluate plant performance and
- make operationaljudgements based on operating 003 Reactor Coolant Pump 0 0 0 C 0 0 0 0 0 0 1 characteristics, reactor behavior, and instrument interpretation.
3.7 1 004 A3.09 Ability to monitor automatic operation of 004 Chemical and Volume Control 0 0 0 0 0 0 0 0 1 0 0 the CVCS induding: VCT ievel. ;
3.3 1 013 K1.01 Knowledge of the physical connnections and/or cause effect relationship l 013 Engineered Safety Features Actuation 1 0 0 0 0 0 0 0 0 0 0 between the ESFAS and the foRowing systems: l Initiation signals for ESF circuit logic.
4.2 1 013 A4.02 Ability to manuauy operate and/or 013 Engineered Safety Features Actuation 0 0 0 0 0 0 0 0 0 1 0 monitor in the control room: Reset of ESFAS channels. 4.3 1 015 K5.02 Knowledge of the operational implications of the foRowing concepts as they apply 015 Nudear instrumentation 0 0 0 0 1 0 0 0 0 0 0 to the NIS: Discriminator / compensation operation. ,
2.7 1 !
015 A1.01 Ability to predet and/or monitor changes in parameters (to prevent exceeding I 015 Nuclear Instrumentabon 0 0 0 0 0 0 1 0 0 0 0 design limits) associated with operating the NIS controls induding: NIS calibration by heat balance.
3.5 1 I
017 K3.01 Knowledge of the effect that a loss or i 1 017 In-core Temperature Monitor 0 0 1 0 0 0 0 0 0 0 0 malfunction of the ITM system will have on the I following: Natural circulation indications.
3.5 1
PWR RO Examination Outline Plant Systems -Tier 2/ Group 1 System Number / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic (s) Imp. Points 022 K4.03 Knowledge of CCS design feature (s) 022 Containment CooEng 0 0 0 1 0 0 0 0 0 0 0
""# ' I" I* * * "I Automatic containmentisolation.
3.6 1 025 w ca- 0 0 0 0 0 0 0 0 0 0 0 0 056 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those 056 Condensate 0 0 0 0 0 0 0 1 0 0 0 predictions, use procedures to correc's control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.
2.6 1 059 K1.07 Know' edge of the physical connections 059 Main Feedwater 0 0 0 0 0 0 1 0 0 0 0 MFW and the following systems: ICS.
3.2 1 059 A3.03 Atsty to monitor automatic operation of 059 Main Feedwater 0 0 0 0 0 0 0 0 1 0 0 the MFW, including: Feedwater pump suction flow pressure. 2.9 1 061 K4.02 Knowledge of AFW design feature (s) and/or interiock(s) which provide for the following:
061 Auxiliary /EmergencyFeedwater 0 0 0 1 0 0 0 0 0 0 0 AFW automatic start upon loss of MFW pumps, S/G level, Blackout, or Safety injection.
4.5 1 ose tw nea. 0 0 0 0 0 0 0 0 0 0 0 0 071 A4.25 Atsty to manually operate and/or 071 Waste Gas Disposal monitorin the control room: Setting of process 0 0 0 0 0 0 0 0 0 1 0 radiation monitor alarms, automatic functions, and adjustment of setpoints.
3.2 1 072 A3.01 Atsty to monitor automatic operation of 072 Area Radiation Monitoring 0 0 0 0 0 0 0 0 1 0 0 the ARM system, including: Changes in ventilation alianment. 2.9 1 0 0 0 0 0 0 0 0 0 0 0 0 i 0 0 0 0 0 0 0 0 0 0 0 0 K/A Category Totals: 3 0 1 3 1 0 1 2 3 2 1 Group Point Total = 17 37
PWR RO Eximinati n Outlina j Plant System 3 - Tier 2/ Group 2 .
] l System Number / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G M/A Topic (s) Imp. Pointe 002 A1.02 Atety to predict and/or monitor !
changes in parameters (to prevent exceeding 002 Reactor Coolant 0 0 0 0 0 0 1 0 0 0 0 design Emits) mesociated wnh operating the ,
RCS controle including: PZR and makeup tank !
level. 3.6 1 006 K3.02 Knowledge of the effect that a lose ,
006 Emergency Core Cooling 0 0 1 0 0 0 0 0 0 0 0 or malfunction of the ECCS will have on the !
following: Fuel. 4.3 1 006 K5.02 Knowledge of the operatumat !
006 Emergency Core Coolrg 0 0 0 0 1 0 0 0 0 0 0 sethey apply to ECCS: Relationship between accurnulator volume and pressure. 2.8 1 010 K4.01 Knowledge of PZR PCS design ;
010 Presourtrer Pressure Control 0 0 0 1 0 0 0 0 0 0 0 feature (s) and/or intertock(s) which provide for the followins' Spray volve warmup 2.7 1 011 A2.11 Ately to (a) predict the impacts of j the following malfunctions or opershone on the i PZR LCS; and (b) bened on those predidions, [
011 Pressurtzer Level Control 0 0 0 0 0 0 0 1 0 0 0 use procedures to correct, control, or mitigste l the consequences of those malfunctions or operations. Failure of PZR levellnetrument-
- low. 3.4 1 012 K4.01 Knowledge of RPS design feature (s) [
012 Reactor Protection 0 0 0 1 0 0 0 0 0 0 0 *I following: Trip logic when one channel OOC or ,
in test. 3.7 1 l 012 KS.04 Knowledge of the effect of a loss or 1 012 Reactor Protection 0 0 0 0 0 1 0 0 0 0 0 malfunction of the following will have on the RPS: C._ M circulte 3.3 1 014 Rod Poolhon Indicahon 0 0 0 0 0 0 0 0 0 0 0 0 !
016 A3.01 Ately to monitor automatic opershon ,
016 Nonmuclear Instrumentation 0 0 0 0 0 0 0 0 1 0 0 of the NNIS, including Automatic selection of !
NNIS Inputs to control systems 2.9 1 !
026 K1.01 Knowledge of the physical 026 Conteenment Spray 1 0 0 0 0 0 0 0 0 0 0 !;
between the CSS and the following eyetems.
ECCS. 4.2 1 !
026 A3.01 Ability to monitor automatic opershon l 026 Contmenment Spray 0 0 0 0 0 0 0 0 1 0 0 of the CSS, including: Pump starts and correct i MOV positionino 4.3 1 l
029 K1.03 Knowledge of the physical ;
connections and/or cause-effect relationehlps L 029 Containment Purge 1 0 0 0 0 0 0 0 0 0 0 between the Containment Purge System and !
the follov*g systems Engineered safeguards 3.6 1 '
033 A2.03 Atillity to (a) predact the impacts of
[
l the following malfunctions or operations on the r Spent Fuel Pool Cooling System; and (b) booed 033 Spent Fuel Pool Cooling 0 0 0 0 0 0 0 1 0 0 0 " '"
control, or mihgate the consequences of those ,
malfunchone or opershone Abnormal opent fuel pool water level or loss of water levet.
3.1 1 i l
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l PWR RO Examination Outline Plant Systems -Tier 2/ Group 2 l
, System Number / Nome K1 K2 K3 K4 K5 K4 A1 A2 A3 A4 G KIA Topic (e) Imp. Pointe s
035 K4.01 Knoudedge of S/GS design i 035 Steam Generator 0 0 0 1 0 0 0 0 0 0 0 feature (s) andh Intertock(s) which provide fbr
, the followinr S/G level contml. 3.6 1 l 039 K3.05 Knoudedge of the effect that a loss ;
l 03g Mein and Rehest Steam 0 0 1 0 0 0 0 0 0 0 0 or malfunction of the MRSS wlR have on the l l folloudna RCS. 3.6 1
- 039 A4.04 Atduty to manuspy operate and/or ,
030 Mein and Rehest Steam 0 0 0 0 0 0 0 0 0 1 0 monitor in the control room: Emergency ,
j feedwater pump turt Ines 38 1 i l 055 Condenser Air Removal 0 0 0 0 0 0 0 0 0 0 0 0 l 062 AC Electrical Distribution 0 1 0 0 0 0 0 0 0 0 0 062 not W N poww suppnes to the following' Maior system loade 3.3 1 062 AC Electrical Distribution 0 0 0 0 0 0 0 0 0 0 1 2222 W W W m W l operatione and esfety Hmits. 3.4 1 ;
I 063 K3.02 Knowledge of the effed that a lose ;
063 DC Electrical DistrilNtion 0 0 1 0 0 0 0 0 0 0 0 w d the DC 6 W wlR ,
have on the following componente using DC ;
control power. 3.5 1 ;
064 K6.06 Knoudedge of the eMeet of a loss or
! 064 Emergency Diesel Generator 0 0 0 0 0 1 0 0 0 0 0 malfunction of the following wlR have on the '
ED/G system: Fuel oR storene tanks. 3.2 1 064 A4.06 AtWilly to menuesy operate endtor 064 Emergency Diesel Generator 0 0 0 0 0 0 0 0 0 1 0 monitor in the contral room: Monuel eter*, ,
loadina. and stopping of EDIG. 3.9 1 !
073 K1.01 Knowledge of the physical 073 Process Radiation Monitoring 1 0 0 0 0 0 0 0 0 0 0 between the PRM system and the fenowing eyelems: Those systems served tw PRMs. 3. 6 1 075 A2.02 Atdutyto(e)predlettheimpactsof the following malfunctions or operations on the circulating water system; and (b) bened on 075 Circulating Water 0 0 0 0 0 0 0 1 0 0 0 those predictione, use procedures to correct, contml, or mittgete *he conesquences of those maffunctions or operations.: Loos of circulating ;
water pumps. 2.5 1 079 Stat 6cn Air 0 0 0 0 0 0 0 0 0 0 0 0 086 Fire Protection 0 0 0 0 0 0 0 0 0 1 0 086 A4.06 M k W W mw
, monitor in the control room: Halon system. 3.2 1
, 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O O O O O O O O O O O O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 K/A CologoryTotola: 3 1 3 3 1 2 1 3 2 3 1 Group Point Total = 23 23 i
PWR RO Examination Outline Plant Systems - Tier 2/ Group 3 System Number / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic (s) Imp. Points 005 R:sidual Heat Removal 0 2.1.28 Knowledge of the purpose and function of major 0 0 0 0 0 0 0 0 0 1 system components and controls 3.2 1 007 A4.10 Ability to manually operate and/or monitor 007 Pressurizer Relief / Quench Tank 0 0 0 0 0 0 0 0 0 1 0 in the control room: Recognition of leaking PORV/ code safety. 3.6 1 008 A3.08 Ability to monitor automatic operation of the
, in ng: mak adons assodatM Wm 008 C:mponent Cooling Water 0 0 0 0 0 0 0 0 1 0 0 ;
the CCWS that occur as a result of a Safety inject. ion signal. 3.6 1 I
027 K1.01 Knowledge of the physical connections 027 Containment Iodine Removal 1 0 0 0 0 0 0 0 0 0 0 and/or cause-effect relationships between the CIRS and the following systems: CSS. 3.4 1 028 K3.01 Knowledge of the effect that a loss or 028 Hydrogen Recombiner and Purge 0 0 1 0 0 0 0 0 0 0 0 malfunction of the HRPS will have on the following- -
Control Hydrogen concentration in containment. 3.3 1 034 Fuel Hantmng Equipment 0 0 0 0 0 0 0 0 0 0 0 0 041 K6.03 Knowledge of the effect of a loss or 041 Steam Dump / Turbine Bypass Control 0 0 0 0 0 1 0 0 0 0 0 malfunction of the following will have on the SDS:
Controller and positioners, including ICS, S/G, CRDS. 2.7 1 A4.06 AbMy to manuaHy omate and/or monnor j 045 Miin Turbine Generator 0 0 0 0 0 0 0 0 0 1 0 in the control room: Turbine stop valves. 2.8 1 076 K2.01 Knowledge of bus power supplies to the 076 S:rvice Water 0 1 0 0 0 0 0 0 0 0 0 following: Service water. 2.7 1 ,
078 K4.02 Knowledge of IAS design feature (s) and/or 078 Instrument Air 0 0 0 1 0 0 0 0 0 0 0 intertock(s) which provide for the following: Cross-over to other air systems. 3.2 1 103 K1.02 Knowledge of the physical connections and/or cause-effect relationships between the 103 Containment 1 0 0 0 0 0 0 0 0 0 0 containment system and the following systems ,
Containment isolation / containment integrity. 3.9 1 K/A Category Totals: 2 1 1 1 0 1 0 0 1 2 1 Group Point Total = 10 10 t
PWR RO Ex: min;ti:n Outline Generic - Tier 3 -
Generic K&A # / Name C1 C2 C3 C4 K/A Topic (s) Imp. Points 2.1 Conduct of Operations 1 0 0 0 2.1.29 Knowledge of how to conduct and verify valve lineups. 3.4 1 2.1 Conduct of Operations 1 0 0 0 9' "" E" "*
requirements.
3.7 1 2.1 Conduct of Operations 2.1.11 Knowledge of less than one hour technical 1 0 0 0 specification action statements for system- 3.0 1 2.2 Equipment Control 0 1 0 0 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 2.2.32 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel 2.2 Equipment Control 0 1 0 0 handling area, c mmunication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. 3.5 1 2.2.1 Ability to perform pre-startup procedures for 2.2 Equipment Control 0 1 0 0 '# ' YI" I" "U I"U ***"
associated with plant equipment that could affect reactivity. 3.7 1 2.2 Equipment Control 0 1 0 0 2.2.12 Knowledge of surveillance procedures. 3.0 1 2.3.10 Ability to perform procedures to . educe i 2.3 Radiation Control 0 0 1 0 excessive levels of radiation and guard against personnel exposure. 2.g 1 2.3 Radiation Control 0 0 1 0 2.3.2 Knowledge of facility ALARA program.
2.5 1 2.3.4 Knowledge of radiation exposure limits and 2.3 Radiation Control 0 0 1 0 contamination control, including permissible levels in excess of those authorized- 2.5 1 2.4 Emergency Procedures / Plan 0 0 0 2.4.3 Ability to identify post-accident 1
instrumentation-3.5 1 2.4.34 Knowledge of RO tasks performed outside 2.4 Emergency Procedures / Plan 0 0 0 1 ge main mn mm u ng mergency operadons including system geography and system implications.
3.8 1 2.4.4 Ability to recognize abnormal indications for 2.4 Emergency Procedures / Plan 0 0 0 1 system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. 4.0 K/A Category Totals: 3 4 3 3 Group Point Total = 13 13
i INITIAL LICENSE EXAM BANK QUESTION REVIEW AND APPROVAL FORM Onginator John W. Cork CAUTION!
PEER Beviewer and ANO NRC Contact SHALL be signed as the security agreement BEFORE their review of any Inkial T hwane Exasa amaterial Number tvunnweds sequentially.
No. Comment Resolution 1 Answer "c" is also true ifinterlock fails. Changed distracter "c" to: "The B channel would go to bypass and the A channel would be 0131 removed froni bypass. " EFIC works in this fashion so it's a plausible distracten.
5 Channels 5 & 6 are repeated in answers "c" and Changed distracter "d" to channels 1 & 2.
"d", possibly cucing canthdate 0135 6 Arsw "a" is not consistent with stem, says Revised "a" to state " loop II Senice Water "both" when stem states that one monitor is in monitoris also in alarm."
0136 alann.
13 Distracter "a" not credible, all of Controlled Revised "a" to state "High Padw== Areas" Access is too broad of an area to be believed. and changed "normally" to "always" since 0143 waiving of verdicaeian is routinely done for High Rad areas.
14 Too low level, enhance stem or distracter. Replaced question.
0144 PElmReviewer Date M '//' E8' Signature abgve irvheates all comments resolved to the matternetian of the reviewer.
Ano unc Contact oateirluhr Signature a)(ove indiafttes question ready to be used in an initial limase exam.
Ao2D
.- 2. ... - 5_ w= ..u _ , , __ .-. 2.. - +,m.4.._. . _. m. . _m -
4 h
INITIAL LICENSE EXAM BANK QUESTION REVIEW AND APPROVAL FORM !
j Onginator John W. Cork l
i CAUTION!
PEER Reviewer and ANO NRC Contact SHALL be signed on the security agreement BEFORE their review of any Initial fle===* Exam material Number comments %4 No. Comment Resolution l
15 Stem and answer "d" both contam the term "In- Changed "d" to read " Allow driving in Grp.1 ,
limits." thru 7 rods to angage roller nuts with lead l 0145 screws " l l
18 Doesn't match K/A. K/A is for LCO's, question Question stem revised, all answers changed to only asks what is on the 161KV ring bus, be possible combinations of Tech Spec i 0152 compliance.
21 "A" RPS is in stem and the correct answer, "b". Removed "A RPS cabinet imm stem. Added "RCS" prior to " narrow range" to help define 0155 instrument. Added "inetantaneanaly" to ensure candidate has the information to determine if SASS will detect fadure.
24 Too hard from memory for RO's. This is directly from symptoms section of AOP 1203.005, which is required knowledge for l 0158 RO's.
29 Only "c" and "d" contain term "CET's", Changed "c" to "T-hot rising above 580 deg F possibly cuemg candidate. and subcooling margm is lost."
0163 Minor change to answer "d".
PEERRenewer Date A2-//- Y l Signature abo (e indicates all comments resolved to the satisfaction of the reviewer.
! ANO NRC Contact Date II/N/iI
- j. Signature he indiep question ready to be used in an initial license exam.
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, e INITIAL LICENSE EXAM BANK QUESTION REVIEW AND APPROVAL FORM Onginator John W. Cork CAUTION!
PEER Reviewer and ANO NRC Contact SHALL be signed on the security agreement BEFORE their review of any Initial tie == Exam material Number comments sequentially.
No. Comment Resolution 31 Answers "c" and "d" do not match stem, they Changed " equipment status" in stem to " plant are not an" equipment status." condition "
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36 Are alb/c credible? Changed "c" to " Restore P-75", "a" and "b" are credible. i 0l?0 J
37 1s this question too similar to 0161 (#27)? 0161 -Tests knowledge of runback, i.e.,
n= hut will not occur.
0171 0171 -Tests knowledge of T.S., modified "a" distracter. i 39 In answer "b", "999999" is a visual cue. Removed "(999999)" from answer "b",
modified "a" and "b" slightly.
- 0173 40 Answer "a" is not complete - it takes more than Added " and all other feeder breakers to its just an EDG start for the output breaker to close, respective bus" to "a".
0174 Added " to restore essential loads" to "d" for better credibility.
PEERReviewer Date 42-//-Y .
Signature abovf indicates all comments resolved to the satisfaction of the resiewer.
ANO NRC Contact Date /2[//h Signaturepe'indiep q.ucstion ready to be used in an initial license exam. l
INITIAL LICENSE EXAM BANK QUESTION REVIEW AND APPROVAL FORM Originator John W. Cork CAUTION!
PEER Reviewer and ANO NRC Contact SHALL be signed on the security agreement BEFORE their review of any Initial Ucense Exam material Number comments sequentially.
No. Comment Resolution 41 Capitalize "least erruri.ic." Done.
0175 42 Give only one answer for "a" or two for "b" and Replaced with new question.
"C".
0176 43 is "b" credible? Yes, this is acceptable as is.
0177 44 WilUih 4 be ped.ded? Yes, added "(See attached Figure 4)" below stem and attached figure.
0178 47 1s "a" credible? Yes, this is acceptable as is.
0182 PEERReviewer Date /8 ~O'Y Signature abo (e indicates all comments resolved to the satisfaction of the reviewer.
ANO NRC Contact Date N N Signature affove indicatp(r question ready to be used in an initial license exam.
. I INITIAL LICENSE EXAM BANK l QUESTION REVIEW AND APPROVAL FORM Ongmator John W. Cork l
CAUTION! l PEER Reviewer and ANO NRC Contact SHALL be signed on the secadty agreement BEFORE their i review of anyImidalThe Exam matedal '
Number comments sequentially.
No. Comment Resolution l 52 Conect answer "d" is too specific in comparison Modified distracters. !
to d % a s.
0188 Replace distracter"b".
]
56 Stem needs to be more specific. Added "With above conditions, " to beginning i 0192 I
i 58 Are "a" and "d" credible? Yes, this is @ as is.
0194 61 Is this too difficult for a memory only question? Changed given level for T-2B to 11.9 to make it clear that it is low out of spec.
0197 63 Distracter "a" can be ehmmated by cue from Changed "I & 2" in "a" to "5 & 6".
question #60(0196).
0199 l
PEER Reviewer Date O-//-97 Signature abm4 indmen all comments resolved to the satisfacuon of the reviewer.
4 ANO NRC Contact Date /2 I i SignatureAove yquestion ready to be unc J in an initial license exam.
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INITIAL LICENSE EXAM BANK !
QUESTION REVIEW AND APPROVAL FORM l
Ongmator John W. Cork l CAUTION!
PEER Reviewer and ANO NRC Contact SHALL be signed on the security agnement BEFORE their J avview of any InitialIJcense Exama material Number comments sequentially.
No. Comment Resolution 68 Typo in distracter "d". Fixed.
0204 69 Are "c" and "d" credible? Added " causing reduced flow" to "c".
0205 In "d", changed "with only 3 putaps in senice" to "and temperatures will return to normal l within 30 minutes."
70 Answer cued by Q#42 (0176)? Replaced Q#42 (0176).
0206 l
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72 14w disenmmation value, a/c/d not credible. Modified question.
0208 74 Answer "d", replace " maximum" with actual " Maximum" replaced with "1450*F."
temperature value.
0210 1
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PEER Reviewer Date /d -/b Signature atme/ndicates all comments resolved to the satisfaction of the reviewer.
ANO NRC Contact Date M # I Signature alfove indicapdis question ready to be used in an initial license exam.
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INITIAL LICENSE EXAM BANK QUESTION REVIEW AND APPROVAL FORM Originator John W. Cork CAUTION!
PEER Reviewer and ANO NRC Contact SHALL be signed on the secadty agstement BEFORE their review of any InitialIJcease Exam saatedal Number cornments sequentially.
No. Comment Resolution 80 Grammar error in distracter "d". Corrected.
0216 83 Is "d" credible? Changed " rises" on both parameters in "d" to
" drops".
0220 89 Move common phrase to stem. Removed common phrase from all answers and placedin the stent 0226 95 " Fill in the Blank" questions not allowed. Used table format. Revised stem.
Revise in table format.
0232 97 Isn't "a" also true? Added "specifically" to stem.
0234 PEER Reviewer d Date 42-8-9[
Signature abov(indicates all comments resolved to the satisfaction of the reviewer.
ANO NRC Contact Date /Sh 97 Signature a)6ve W~pquestion ready to be used in an initial license exam.
INITIAL LICENSE EXAM BANK QUESTION REVIEW AND APPROVAL FORM Originator John W. Cork CAUTION!
PEER Reviewer and ANO NRC Contact SHALL be signed on the security agreement BEFORE their review of any InitialIJcense Exam material Number comments sequentially.
No. Comment Resolution 98 Stem asks yes/no but distracters answer why. Changed stem to ask which time given will be i--* y to exceed ADCL 0235 Changed allanswers to time units.
99 Is this required knowledge for an RO? Changed stem to ask for RO action vs. CRS.
Changed "c" to " Trip the turbine.", a SS action.
0236 Changed "d" to " Align steam to EFW pump P-7A.", this is an RO action.
PEERReviewer Date N -//- 7#
Signature abovf indicates all comments resohtd to the satisfaction of the resiewer.
ANO NRC Contact Date Signature a@fov6ifidiep question ready to be used in an initial license exam.
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ES401 Site-Specific Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific .
Written Examination l
ApplicantInformation Name: Region: IV j Date: Facility / Unit ANO UnitOne i Ucense Level: RO ReactorType: BW StartTime: FinishTime: j instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the I answer sheets. The passing grade requires a final grade of atleast 80.00 percent. Examination papers l will be collected four hours after the examination starts.
i Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicanfs Signature Results Examination Value /00 Points ;
l Applicant's Score Points Applicant's Grade Percent L
NUREG-1021 39of39 InterimRev.8 January 1997 0
ANO Unit 1 - December 1998 Reactor Operator License Exam Question No.1 QID: 0131 Polet Value: 1 If channel A of the RPS is currently in channel bypass, what would result af the channel bypass switch for channel B was then placed in the bypass position?
- a. The RPS would be placed in a 2 out of 2 coincidence logic.
- b. Interlock would cause both channels to drop out of bypass.
- c. A violation of Tech. Spec. would occur when the accend channelis placedinbypass. ,
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- d. The channel B bypass is prevented by an interlock from the channel alreadyin bypass Question No. 2 QID: 0132 Point Value: 1 i Tbc makeup tank has decreased fiom 81 inches to 73 inches. Assuming that the level decrease was due to a l
loss of RCS inventory, how much has been lost? j l
- a. 220 to 229 gallons
- b. 230 to 239 gallons
- c. 240 to 249 gallons
- d. 250 to 259 gallons l
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. J QID: 0133 Point Value: 1 Which of the following are the two purposes for maintaining a one gpm continuous spray flow bypassing the pressurtzer sprayvalve?
- a. Assists in pressurizer level contiel and maintains pressurizer heaters at minimalfiring rate.
- b. Minimizes surge and spray line temperature differentials and maintains pressurizer boron concentration near that in the RCS.
- c. Assists in maintaining pressurizer level and maintains pressurizer boron concentration near that in the RCS.
- d. Minimizes surge and spray line temperature differentials and raises the differential pressure across the spray valve.
Question No. 4 QID: 0134 Point Value: 1 The Gamma Metrics system uses discrimination circuitry to provide accurate indication of source range power levels. Why is discrimination necessary in source range nuclear instrumentation and what is the result ofincorrect discrimination?
- a. Discrimination separates out alpha and neutron pulses to provide a true gamma pulse.
With the discrimination set too high power will indicate higher than actual power.
- b. Discrimination separates out gamma and neutron pulses to provide a true alpha pulse.
With the discrimination set too low, power will indicate higher than actual power.
- c. Discrimination separates out gamma and alpha pulses to provide a true neutron pulse.
With the discrimination set too high, power will indicate lower than actual power.
- d. Discrimination separates out beta and gamma pulses to provide a true neutron pulse.
With the discriminator set too low, power will indicate lower tlan actual power.
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1 ANO Unit 1 - December 1998 Reactor Operator License Exam l
Question No. J QID: 0135 Point Value: 1 l
I A LOCA has occurred which has resulted in an ESAS actuation of channels I through 10. ]
Which ESAS channels have actuated the RB cooling units and what is the correct RB j
cooling alignment?
to the moling coils. '
- b. ES channels 3 & 4, VSF-1 A, IB, IC, ID, & IE running with chilled water aligned to the moling coils. j
- d. ES channels 5 & 6, VSF-1 A, IB, IC, ID, & IE running with chilled water aligned to the cooling coils. ,
Question No. 6 QID: 0136 Point Value: 1 During a LOCA inside the Reactor Building, RE-3814, Senice Water Loop I Radiation Monitor alarms.
SW Loop IIindications are normal.
Which of the mnditions below when combined with the above condition would make it necessary to isolate the "A" & "B" RB Emergency coolers?
- a. Both Senice Water monitors are in alarm.
- b. Instnunent Airislost.
- c. Discharge Flume monitor is also in alarm.
- d. RB area monitors are also in alarm.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 7 QID: 0137 Point Value: 1 Which one of the following is NOT a function of the Rapid Feedwatet Reduction feature ofICS?
- a. Iow Load and Startup Control Valve demands are reduced to zero.
- b. Main Feedwater Pump speed goes to minimum.
- c. Both Main Feedwater Block Valves close in slow speed.
- d. Both Loop Feedwater demands are reduced to zero.
Question No. 8 QID: 0138 Point Value: 1 During the performance ofMain *Ibsbine Governor Valve testing, while governor valve #1 was closed in the test position governor valve #3 fails closed. What turbine problems does this impose?
- a. Moisture impingement on the turbine blading.
- b. Thermal shock to the turbine rotor.
- c. 'Ibrbine will trip due to low load.
- d. Turbine overspeed condition.
Question No. 9 QID: 0139 Polet Value: 1 Which of the following systems are isolated to the Reactor Building by ESAS?
- a. RCP motor cooling, chill water, RB service water cooling.
- c. Seal ispection, RCP motor cooling, RB service water cooling.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No.10 QID: 0140 Point Value: 1 Initialconditions:
-100% power with P-36C supplying normal makeup and seal injection. ICW pumps P-33A and P-33C in senice.
What RCP support system would be most affected by a loss of bus A47
- a. SealInjection
- b. Motor Cooling
- c. SealBleedoff
- d. OilLift Pressure Question No.11 QID: 0141 Point Value: 1 Running with 'A' & 'B' RCP's on and 'C' & 'D' RCP's off with RCS pressure below 260 psig should be minimized to prevent:
- a. excessive seal wear and cavitation.
- b. excessive motor winding temperatures and casitation.
- c. cxcessive seal wear and shaft cracking. .
Q
- d. excessive thrust bearing wear arui shaft cracking.
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. ANO Unit 1 - December 1998 Reactor Operator License Exam Question No.12 QID: 0142 Point Value: 1 Under what conditions can the Control Board Operator bypass or defeat a component automatically actuated by ESAS?
l a. Bypassing or defeating a component automatically actuated by ESAS is not
- b. The Control Board Operator, aAer careful consideration, determines that the
! componentis nolonger required.
l l c. ONLY when procedurally directed by the Emergency Operating or the Abnormal Operatang procedures.
l d. AAer it is determmed that the component is no longer needed and approval is obtainad from the CRS/SS.
l Question No.13 QID: 0143 Polat Value: 1 The plant is shut down for Refueling. A letdown system valve alignment is being done inside Controlled Access Two of the valves are in a locked high radiation area and i l have no remote position indication. The first check was made, but the Shin Superintendent decided to waive the second check to reduce the exposure to high radiation.
Which one of the following statements most accurately describes why the Shia Superintendent's decison is acceptable or unacceptable?
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! a. Acceptable, inhadaat verifications are normally waived for valve alignments inside Controlled Access.
- b. Unacceptable, independent verification cannot be waived if NO remote valve position indication is provided.
! c. Acceptable, ir '- g-: '- at verification can be waived for valve alignments on a case-by-case basis with the Superintendent's approval. j
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- d. UaW&le, ir +i- = '=t verifications cannot be waived for valve alignments without the approval of the Manager of Plant Operations.
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I ANO Unit 1 - December 1998 Reactor Operator License Exam ;
Question No.14 QID: 0144 Point Value: 1 l During reactor vessel law aa,i the radsation detector readtag on the !
main refueling bridge increases by about 30 mR/hr over the course of ,
an hour. With respect to ALARA, what action is required? '
- a. Notify Health Physics to increase the allowable l
exposure.
- b. Continuetheinspection.
- c. Leave the area and notify Health Physics. ,
- d. Monitor exposure and notify Health Physics when limit l
. is reached. t l
Question No.15 QID: 0145 Point Value: 1 The purpose of the LATCH (in-limit bypass) switch on the Diamond panel is to: ,
- a. Apply power to the CRD motor which will engage the latching mechanism.
- b. Reset a fault condition provided the fault has cleared. !
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- d. Disable all group in-limits except Group G. ,
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No.16 QID: 0146 Point Value: 1 The plant is operating at 100% power, when annunciator K07-C1, REACTOR FEEDWATER LIMITED, alarms. The following conditions exist: l l
- RCS pressure and temperature are increasing. I 1
- OTSG levels = 60% and decreasing. j l i I
-Main feedwaterflow is decreasmg. i What procedure contains the required rnitigating operator actions? I l a. 1203.027, " Loss of Steam Generator Feed" l b. 1203.001, "ICS Abnormal Operating" L c. 1203.018, "nubine Trip Below 43% Power"
- d. 1202.001, " Emergency Operations Procedure" Question No.17 QID: 0147 Point Value: 1 Given the following conditions:
- 100% power 1
- ICS in fullautomatic
- Im Load Limit set at 60%
Annunciators "CRD WithdrawalInhibited" and " Control Rod Asymmetric" are received as a result of Group 2, i Rod 3 dropping and fully inserting into the core. Which of the following best desenh:s plant response?
- a. ICS will run the plant back at 30%/ min and power will stabilize at 40%. !
- b. ICS will run the plant back at 50%/ min and power will stabilize at 40%.
! c. ICS will run the plant back at 30%/ min and power will stabilize at 60%.
- d. ICS will run the plant back at 50%/ min and power will stabilize at 60%.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No.18 QID: 0152 Point Value: 1 The plant is operating at 100% power. A loss of the 161 KV ring bus occurs (deenergized). A review of Tecimical Specifications indicates an entry into a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time clock is r-eary. The loss of what component has caused this entry?
- a. Loss of Startup Transformer #1
- b. Loss of Startup Transformer #2 c.14ss of the Autotransformer
- d. Iess of Unit Auxiliary Transformer Question No.19 QID: 0153 Point Value:1 Actuation of any Control Room isolation radiation monitor will cause:
- a. Both emergency Recire Fans to start, all isolation dampers close
- b. Either emergency Recire Fan will start, only the isolation dampers for that CR close
- c. Neither emergency Recire Fan will start, only isolation dampers close
- d. One emergency Recist Fan will start, all isolation dampers close Page 9
ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 20 QID: 0154 Point Value: 1 Given, only ONE failure caused the following.:
-Plant running back
- A" main feedwater flow rapidly increasing
- B" main feedwater flow rapidly decreasing
- Feedwater pumps discharge crosstic valve shut Which one of the following equipment / component responses produced this plant condition?
- a. RCP trip
- b. "A" loop RCS flow transmitter failure
- c. MFWP trip
- d. "B" loop RCS flow transmitter failure Question No. 21 QID: 0155 Point Value: 1 The plantis steady at 100% power.
Loop "A" narrow range pressure instrument, PT-1021, to "A" RPS cabinet fails high.
What effect will this failure have on plant equipment?
- a. The ERV will open.
- b. "A" RPS channel will trip.
- c. Pressunzer heaters will go off.
- d. PZR spray valve will open.
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ANO Unit 1 - December 1998 Reactor Operafor License Exam :
Question No. 22 QID: 0156 Point Value: 1 Given:
- A reactor trip has occurred.
- RCS pressure !s 1800 psig, ,
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- RCS T. cold is 512 degrees F, !
- "A" OTSG pressure is 650 psig,
- "B" OTSG pressure is 970 psig, l
- Reactor Building pressure is 6 psig.
Which emergency operating procedure contains the specific steps to mitigate the consequences of this event.
- a. ESAS 1202.010 l
- b. Overcooling 1202.003
- c. HPI Cooldown 1202.011
- d. Loss of Subcooling Margin 1202.002 i
i Question No. 23 QID: 0157 Point Value: 1 Given: The plant is at 500 MWe and you are the CBOT.
If condenser vacuum dropped from 27" to 25.5", you would see indications of:
- a. Increasing main turbine load (MWe).
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- b. Condenser vacuum pump shifting to hogging mode.
l l c. Automatic main turbine trip.
i d. Condenser vacuum pump auto starting.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 24 , QID: 0158 Point Value: 1 The outside door of the personnel lock was opened to replace a seal gasket 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago. How long does operations have to perform an LLRT on the penonnel lock before a loss of containment integrity will exist?
- a. Ihour b.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ,
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- c. 6 days l I
d.13 days l I
Question No. 25 QID: 0159 Point Value: 1 l
l Given. 1
- A LOCA has occurred
- All RCPs are running.
- SPDS ATOG display indicates " Loss of Subcooling Margin Elapsed Time 00:04:15" Which of the following actions should be taken?
- a. Stop all RCPs.
- b. Stop one RCP in each loop.
- d. Continue to keep all RCPs running.
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s ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 26 QID: 0160 Point Value: 1 During a Rx trip transient, all nine of the + or - 24v DC NNUICS power supply status lights go out.
The mostlikely causeis:
- a. IAss of Offsite Power ,
- b. Loss ofDC Bus D11
- c. Loss of YO2
- d. Ioss of DC Bus D21 Questlom No. 27 QID: 0161 Point Value: 1 Given:
- Power esenlation is in progress following a shutdown.
- Reactor power is 30%. .
- Rod 4 of Group 5 drops.
Which of the following actions should be taken?
- a. Insert all regulating rods in sequential mode.
- b. Trip the reactor and go to Reactor Trip,1202.001,
- c. Verify plant stabilizes at 320 MWe after ICS runback.
- d. Refer to Tech Specs and recover the dropped rod.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 28 QID: 0162 Point Value: 1 Reactor power is 90% and generated megawatts is 800. After a runback for loss of one main feedwater pump, theICS should stabilize the plant at
- a. 360 MWe
- b. 340 MWe
- c. 45%ReactorPower
- d. 40%ReactorPower Question No. 29 QID: 0163 Point Value: 1 After a reactor trip with all required actions perfonned, which of the following requires an entry into 1202.004 " OVERHEATING"?
- a. T-hot is rising above 560 deg F with the "C" RCP running.
- b. Both main feedwater pumps tripped, aux feed pump 00S.
- c. CETs rising above 580 deg F and subcooling margin is 28 deg F.
Question No. 30 QID: 0164 Point Value: 1 An outage is in progress. The RCS is drained to 371.5 feet as indicated by RCS hot leg level. Decay heat remm31 flow becomes erratic. Indicated flow is ~2500 gpm. Which ONE of the following actionsis correct?
- a. Reduce decay heat removal flow below 2000 gpm.-
- b. mp the operating decay heat removal pump.
- c. Raise RCS level.
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- d. Raise decay heat remmal flow.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 31 QID: 0165 Point Value: 1 Given:
-Reactor tripped !
- OTSG pressures 830 psig and decreasing
-Tave 536 degrees F l Which equipment status below correlates to these plant ;
parameters? )
- a. All rods not on bottom
- b. Turbine did not trip
- c. Al did not transfer to SUI j
- d. RCS is saturated !
Questlom No, 32 QID: 0166 Point Value: 1 During an OTSG tube rupture with RCS temperature at $25' F, which of the following would !
require using the emergency cooldown rate? I
- a. Bad OTSG level 410"and rising !
- b. BWSTlevel28'and dropping !
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- c. Projected activity at the site boundary is at NUE critena. '
- d. Tube-to-shell differential temperature 60*F tubes hotter.
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-- . . = . . . .. . .. . . _ -- -
t ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 33 QID: 0167 Point Value: 1 What immediate action is required upon remipt of Liquid Radwasta Process Monitor (RI-4642) high alarm?
- a. Start another cire water pump to increase dilution flow,
- b. Verify no release in progress at Disch Flow to Flume (FI-4642) on C19.
- c. Verify with Unit 2 no other release is in progress _
- d. Have chemistry sample discharge flume for radionuclides.
Question No. 34 QID: 0168 Point Value: 1 A high radiation condition has resulted in the Unit I and Unit 2 Control Room Radiation Detectors actuating the Control Room Emergency Ventilation System. Both VSF-9 and 2VSF-9 are operating. i
- Which of the following is correct concerning this alignment?
- a. The control room will become overpressurized which will result in 2VSF-9 tripping.
- b. The alignment can result in conditions that may cause excessive radiation exposure.
- c. The alignment should be maintained as is since it is an allowable configuration.
- d. The control room will become overpressurized which will result in VSF-9 tripping.
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'ANO Unit 1 - December 1998 Reactor Operator License Eram Question No. 35 QID: 0169 Point Value: 1 Given:
-Plant is at 100% power.
- PZR level transmitter LT-1001 selected via HS-1002 on C04.
- PZR temperature element TE-1001 A selected via HS-1000 on C04.
The PZR temperature indicator, TI-1000, on C04 drops suddenly to 50*F (bottom of scale).
Without operator action, what will be the effect on the PZR Imel Control System?
- a. PZR Imel Control Valve, CV-1235, will open to establish a higher steady-state PZR level.
- b. PZR Imel Control Valve, CV-1235, will maintain the same steady-state PZR level.
- c. PZR Level Control Valve, CV-1235, will ciose to establish a lower steady-state PZR level.
- d. PZR Level Control Valve, CV-1235, will fail open to continuously raise PZR level.
Question No. 36 QID: 0170 Point Value: 1 During a loss of offsite power with a SG tube leak, the A2 bus is re-energized from the A4 bus.
The A4 busis supplied by #2 EDG.
What is the key reason for this action?
- a. To start P-7B EFW pump and secure P-7A.
- b. To restart cire. water and establish condenser vacuum.
- c. To allow the #1 EDG load to be reduced.
- d. To re-establish instrument air and ICW.
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- ANO Unit 1 - December 1998 Reactor Operator License Exam :
s i I i Question No. 37 QID: 0171 Point Value: 1 l Given: Reactor power is stable at 85% with ICS in full automatic mode.
A group 6 control rod dropped into core.
What are the required Operator actions that should be taken as a result of this condition?
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- a. Recover the dropped rod within one hour. I
- b. Declare the rod inoperable and verify a 1.5% available shutdown margin exists. :
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- c. Exercise remaming rods within I hour per CRD System Operating Procedure 1105.009. :
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- d. Shutdown the reactor by inserting all regulating control rods in sequence. !
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i Question No. 38 QID: 0172 Polet Value: 1 l t
Which of the following conditions would require that a Natural Circulation Cooldown be performed? -
- a. A plant moldown is required and normal offsite' power is NOT available.
- b. A steam genemtor tube leak exist post reactor trip and P-7B EFW pump is NOT available. l
'c. EFW CST (T-41B) level has dropped to less than 3' during a Blackout condition. ;
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- d. A loss of offsite power has occured and both DGs are tied to their respective busses with an adequate SCM and SU Transformer #1 becomes available.
l Question No. 39 QID: 0173 Point Value: 1 ;
l l Dunng an E-gy Boration condition, as directed by Repetitive Task 1202.012, the batch mntroller is set:
- a. As direcm to maintain makeup tank level.
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- b. For maximum batch size (999999).
- c. To a value obtained from the Emergency Boration graph. j
- d. To batch in 100 gallons of acid at 15 minute late:vals. !
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ANO Unit 1 - December 1998 Reactor Operator License Eram Questlom No. 40 QID: 0174 Point Value: 1 When recovering from a Station Blackout condition with no offsite power available and only one DG, which of the following is true?
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- b. The DG output breaker must be momentarily held in the 'close" position to override the ES bus undervoltage relay.
- c. The A3-A4 crosstic breakers are closed prior to closing the DG output breaker.
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- d. The DG should be used to backfeed A2 i I
l Question No. 41 QID: 0175 Point Value: 1 Given: )
- ICW system is in a normal alignment with P-33A & C in operation.
- Non-Nuclear Loop flow is 1950 gpm.
- Nuclear Loop flow is 1550 gpm. i
- Annunciator K12-B4 (ICW Flow Lo) is in solid.
-No ESAS signalis present.
Which of the following would be the least appropriate action for tic ControlRoom Operator to take?
- a. Verify ICW Pump (P-33C or P-33B) is operating.
- b. Verify ICW for Letdown Coolers and RCP Seal Coolers Outlets (CV-2214 & CV-2215) are open. g
- c. Verify ICW for RCP Air and Lube Oil Coolers and Control Rod Drive Outlets (CV-2220 & CV-2221) are open.
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- d. Verify ICW for Letdown Coolers and RCP Seal Coolers Inlet (CV-2233)is open.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 42 QID: 0176 Point Value: 1 Which of the following descCucs the method for manually actuating the Control Room Halon system?
- a. Release the manual actuator on the main pilot cylinder or use the manual trip switch located on the associated switch module on panel C-463.
- b. Depress the SPURT button located on C-420.
- c. Reposition the local three-way valve to the actuation position of the in-senice Halon system.
- d. Depress the trip button located on the smoke detectors located in control room ceiling or floor.
Question No. 43 QID: 0177 Point Value: 1 During the performance of an Alternate Shutdown, RO #2 is directed to throttle EFW TURB K3 Tripffhrottle Valve (CV-6601 A) as necessary to maintain P-7A discharge pressure at ~1400 psig. What would be the initial effect on RCS parameters if P-7A discharge pressure was maintained at ~700 psig?
Question No. 44 QID: 0178 Point Value: 1 After entering Inadequate Core Cooling EOP (1202.005), RCS temperature and pressure indicate entry into Region 4 of Figure 4.
What RCP action is appropriate to restore core cooling?
- b. Restore RCP senices and start one RCP/ loop.
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' ANO Unit 1 - December 1998 Reactor Operator License Exam :
Questlom No. 45 - QID: 0180 Polet Value: 1 ;
A reactor trip hasjust occurred Which of the following would NOT cause a i
. transition to the overcooling procedure (1202.003)?
- a. MSLI actuates automatically causing both MSIVs to go closed.
j j b. 'A' SG pressure 1000 psig,'B' SG pressure 800 psig, Toold 550 degrees. ,
d.' Tave 560 degrees, SCM 25 degrees, RCS pressure 2100 psig. -
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l Questlos No. 46 QID: 0181 Point Value: 1 Dunng a small break IDCA, which of the following would require manual
- - action to balance HPI flow? l
- a. Both trains ofHPI operating and RCS pressure >600 psig.
- b. Both trains ofHPI operstmg and RCS pressure <600 psig.
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Questica No. 47 QID: 0182 Point Value: 1 A LOCAisin progress. i Which one of the following actions is required to be performed prior to theBWSTlevel reaching 6 feet? l l
- l. a. Secure running Reactor Coolant Pumps.
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- b. AlignPressunzer AUX SpraytoLPIsystem.
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. c. Secure running High Pressure Injection Pumps.
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ANO Unit 1 - December 1998 Reactor Operator License Exam l
1 Question No. 48 QID: 0183 Polet Value: 1 During restoration of normal makeup and seal injection, which of the following is true?
- a. If PZR level is <55", normal makeup is restored before seal mjection.
- b. If RCP seal bleedoff temperatures are >180 degrees, seal injection control valve (CV-1207) is quickly opened to establish previous flow rate.
- c. If RCP seal bicedoff temperatures are >l80 degrees, CV-1207 is slowly opened to minimize thermal shock to the RCP seals. I
- d. BWST outlet valve ac-ated with the operating HPI pump must be closed
- prior to opening CV-1207.
l Question No. 49 QID: 0184 Point Value: 1 l l During a reactor startup with source range NI-2 and reactor power wide range recorder NR-502 inoperable, source range NI-1 fails to 10 E5.
Intermediate range NI-3 indicates 5 E-11 amps and intermediate range NI-4 is off scale low. i What is required of the CBOR7
- a. Continue the startup utilizing NI-3 until NI-4 comes on scale. i
- b. Perform a plant shutdown in accordance with normal operating procedures due tolack ofprope overlap
- c. Trip the reactor due to no on-scale indication of neutron flux available.
- d. Hold power constant and perform an N1 calibration.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 50 QID: 0186 Point Value: 1 Given:
- Reactor tripped with Thot temperatures 590 degrees and rising.
- A' & 'B' SG levels 13".
- All 4 RCPs are operating with RCS pressure 2200 psig.
-Botti DGs are in emergency standby.
Which of the following procedures prosides appropriate guidance?
- a. Loss of Subcooling Margin (1202.002)
- b. Overheating (1202.004)
- c. Inadequate Core Cooling (1202.005)
- d. DegradedPower(1202.007)
Question No. 51 QID: 0187 Point Value: 1 The reactor hasjust tripped from 100% power. The turbine trip solenoid light is on. Breaker position lights on the RIGHT side of C10 are off.
What are the actions required of the CBOTl
- a. Trip the main generator output breakers.
- b. Transfer D11 to emergency supply D02.
- c. Trip all RCPs.
- d. Transfer D21 to emergency supply D01.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 52 QID: 0188 Point Value: 1 Given: Fuel handling is in progress in the Reactor Building.
A new fuel assembly is in the Main Bridge mast.
Reactor Building Fuel Handling Area (RI-8017) area radiation monitor has a Failure alarm in solid.
What actions should be taken by the refueling team?
- a. Place the assembly in the core and then secure refueling activities.
- b. Continue refueling activities as long as an HP with a portable survey meter is at the Personnel Hatch.
- c. Continue refueling activities as long as two suberitical core neutron flux monitors are available.
- d. Secure fuel handling activities until RI-8017 is operable or a portable survey instrument having the appropriate ranges and sensitivities is obtained.
Question No. JJ QID: 0189 Point Value: 1 The plantis operating at 100% power.
During pre-outage scaffolding construction in Lower North Piping Room (LNPR), 4 the instrument air line to the Pressurizer Ixvel Control Valve (CV-1235) is inadvertently severed. I With no operator action, which of the following describes the expected system response? ,
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- a. CV-1235 fails open and Fis- :m level will rise.
- b. CV-1235 fails closed and Pressurizer level will lower.
- c. CV-1235 fails open and Pressurizer level will lower.
- d. CV-1235 fails closed and Pressurizer level will rise.
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4 ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 54 QID: 0190 Point Value: 1 Given- I
-Plant is at 100% power.
- On C13, the RCP Seal i enkage Collecting Tank (T-111) Fill Timer "A" reads 20.0 and ' TIMER ON" light is ON.
- Fill 'Ilmer "B" reads 25.0 and " TIMER ON" light is OFF.
What is the cunent total RCP seal leakage?
a.1.1gpm b.1.6 spm
- c. 2.0 gpm
- d. 2.5 gpm t
Question No. 55 QlD: 0191 Point Value: 1
'IN level setpoint at which the Makeup Tank Vent Valve (CV-1257) automatically opens is:
- a. 86 inches
- b. 55 inches c.18 inches d.10 inches a
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 56 QID: 0192 Point Value: 1 Reactor Building Pressure Transmitter (PT-2407) has failed high causing an ES CH3 Trip (analog 3) and the ESAS Partial Trip annunciator (K11-F6) to come into alarm.
A power loss to which of the following would cause an ESAS actuation?
- a. RSI
- b. B11
- c. RS3 d.B21 Question No. 57 QID: 0193 Point Value: 1 Several plant parameters can be monitored to ensure accurate indications of reactor power are available. Which of the following sets of parameters would be indicative of 60% reactor power'/
- a. Tave 579 degrees, Thot 593 degrees, Tcold 564 degrees, total FW flow 6.5 million Ibm /hr.
- b. Tave 580 degrees, Thot 599 degrees, Tcold 560 degrees, total F N flow 8.4 million Ibm /hr.
- c. Tave 579 degrees, Thot 588 degrees, Tcold 570 degrees, total FW flow 6.5 million Ibm /hr.
- d. Tave 581 degrees, Thot 590 degrees, Tcold 565 degrees, total FW flow 9.8 million Ibm /hr.
Question No. 58 QID: 0194 Point Value: 1 During a natural circulation cooldown, which of the following indicate that head voids have formed in the reactor vessel due to an excessive cooldown rate? j
- a. Pressurizer level dropping while depressurizing.
- b. Thot tracking CET temperatures.
- c. Difficulty in reducing RCS pressure.
- d. Tcold rising with associated SG Tsat dropping.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 59 QID: 0195 Point Value: 1 Unit 1 is operating at 100% power with no abnormal conditions or alignments.
'B' MFP SUCT PRESS I.D (K07-C8) annunciator is received.
Where can the Control Room Operators read the 'B' MFW pump suction .
pressure WTIHOUT leaving the contml room? l
- a. The 'B' MFP Lovejoy Operator Control Station (OCS).
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- b. 'B' MFP Suction Pressure (PI-2830) indicator. l l
- c. 'B' MFP Suction Pressure computer point (P2830) ,
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- d. The Operator Information Touchscreen (OIT). s ]
l Question No. 60 QID: 0196 Point Value: 1 I
While performing a reactor building purge evolution, the operator notes all four RB Purge Isolation Valves go closed. What is the most likely cause?
- a. An ESAS actuation of channels I and 2 has closed the valves.
- b. A loss ofload center B-5 has occurred causing the valves to fait closed,
- c. A high radiation setpoint has been exceeded on SPING 1.
- d. RB Purge Exhaust Fan (VEF-15) has tripped causing the valves to close.
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ANO Unit 1 - December 1998 Reactor Operator License Exam l'
Question No. 61 QID: 0197 Point Value: 1 ne plant is operating at 100% power. The Core Flood system is properly -
aligned with the following CFT parameters:
T-2A level - 12.9 feet T-2B level - 12.5 feet
, . T-2A pressure - 605 psig T-2B pressure - 610 psig l
l The Core Flood system parameter are unacceptable because?
- a. Levels may preclude having sufficient N2 pressure to fully inject the CFT contents into the vessel.
- c. Levels may not be sufficient to reflood the vessel following a LOCA.
Question No. 62 QID: 0198 Point Value: 1 Why must Reactor Building Spray flow be throttled to 1050-1200 gpm when on Reactor Building sump suction?
- a. To prevent inadequate pump suction pressure on ECCS pumps.
- b. To prevent pump runout on the spray pumps.
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- c. To lower load on the vital electrical buses.
- d. To limit reactor building cooldown rate.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 63 QID: 0199 Point Valoc: 1 Identify the correct response concerning the Reactor Building Purge Isolation Valves (CV-7401,7402,7403, & 7404).
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- d. The valves do not receive an ESAS actuation signal. j Question No. 64 QID:0200 Point Value: 1 1
A break has occuTed on the discharge line downstream of the discharge valve ofin service Spent Fuel Cooling Pump (P-40A). The pump is stopped and the discharge valve is c3osed.
Which of the following statements is correct concerning the Spent Fuel Pool inventory?
- a. The SFP will drain to ~ 2 feet above the spent fuel assemblies.
- b. Emergency makeup from service water will be needed to prevent the SFP level from reaching the spent fuel assemblics.
- c. The SFP level will stay relatively constant due to siphon holes in the discharge piping.
- d. The SFP level will drop ~3 feet to the bottom of the pipe.
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~ ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 65 QID: 0201 Point Value: /
Startup Transfonner #1 has locked out following a reactor trip from 100% power. !
Steam generator levels will be fed up to which of the following levels (assume no operator actions)?
- a. 20-40 inches. l l
b.100-150 inches. i
- c. 300-340 inches. 1
- d. 370-410 inches.
Question No. 66 QID: 0202 Point Value: 1 i A plant startup is in progress with the reactor critical below the point of adding heat.
'B' SG Turbine Bypass Valve (CV-4688) fails full open and is unable to be closed with !
the k--djd Given the following plant conditions:
-Tave 526 degrees and dropping
- Pressunzer level 205 inches and dropping .
-RCS pressure 2120 psig and dropping l What is the proper course of action? )
1 a.' Initiate MSLI for the 'B' SG and maintain the reactor critical using 'N SG TBV to I control RCS temperature and pressure.
- b. Continue the reactor startup maintaining startup rate <1 DPM while continuing to monitor primary and secondary plant parameters.
- c. Go directly to the Overcooling tab (1202.003) of the EOP for actions to mitgate the oversteaming of the 'B' SG.
- d. Trip the scactor and go to Reactor Trip tab (1202.001) of the EOP.
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l ANO Unit 1 - December 1998 Reactor Operator License Exam Questlos No. 67 QID: 0203 - Toint Value: 1 Red powered EFW Pump Turbine (K-3) Steam Admission Valve Bypass Valve (SV-2663) !
has failed to open during regularly scheduled surveillance testing. What are the required operator actions? - i l
- a. Decnergize SV-2663 closed and declare P-7A inoperable. ]
- b. Declare SV-2663 inoperable and manually open the valve.
- c. Declare SV 2663 inoperable and deenergize CV-2663 closed.
- d. Deenergize SV-2617 open and declare P-7B inoperable.
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Question No. 68 QID: 0204 Point Value:1 The #1 DG monthly surveillance is in progitss with the DG on-line and fully loaded. t EDG-1 Non critical Trouble (K01-D2) has been in solid for ~3 minutes. ;
EDG Critical frouble (K01-C2) comes into alarm. The laside AO reports that the :
T-30A day tank level is ~150 gallons and going down slowly.
l The outside AO reports that Emergency Storage Tank T-57A level is >165 inches.
Which of the following is correct with regard to #1 DG status 7 - !
- a. #1 DG is operable because fuel oil can be supplied from #2 DG transfer pump P-16B. i l
- b. #1 DG is inoperable due to the level in T-30A being <160 gallons. I
setpoint as long as the emergency storage tank (T-57A) is full. I
- d. #1 DG is inoperable due to Emergency strorage tank level >l60 inches.
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ANO Unit 1 - December 1998 Reactor Operator License Exam' Question No. 69 QID: 0205 Point Value: 1 During 3 circulating water pump operation, the 'A' circ water pump trips.
The standby cire pump was started and plant conditions have been stabilized.
It is noticed that the condenser waterbox discharge temperature is 2 to 3 degrees higher and plant efficency has dropped. Which of the following is the most likely cause of this condition?
- a. The stopping and starting of a circ pump caused fouling to be removed from the tube shoct. promoting better heat transfer capabilities.
- b. The discharge valve on the tripped pump did not go completely closed and circulating wateris short cycling.
- c. The debris on the bar grates of the circulating water bays was stirred up during the cire pump swap.
- d. These are no' mal conditions following rotation of circulating pumps with only three pumps t senice. ,
Question No. N QID: 0206 Point Va'lue: 1 The Main Control Room Ceiling Halon system has been propeJrly placed in Inhibit by taking the switch on the right side of Module B3-2L to the down position in Fire Protection Panel (C463). ,
Select the best statement below concerning the actuation capability of the Main Control Room Ceiling Halon system.
- a. It will automatically actuate if both detector strings have valid detection signals present.
- b. It can ONLY be actuated locally from the Halon bottles in the Auxiliary Building.
- c. It can NOT be actuated with the system in Inhibit.
- d. It can be actuated locally or by placing the MAN TRIP switch on C463 to the OPERATED position.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 71 QID: 0207 Point Value: 1 Given:
- Refueling outage is in progress with the Decay Heat Removal System in service.
- RCS pressure is 100 psig.
-I&C wants to de-energize ESAS Analog Channel 2.
What would be the effect on plant operations ifIAC is allowed to continue?
- a. Auto start of"A" Decay Heat pump.
- b. Opening of ERV.
- c. Loss of RCS level indication on ICCMDS.
- d. Loss of decay heat removal.
Question No. 72 QID: 0208 Point Value: 1 Given:
- The Main Tmbine tripped from 100% power
- Relief Valve Open (K09-A1) is in solid with the audiable accoustic monitor alarming on panel C486.
- RCS pressure is 2000 psig and going down.
- ERV (PSV-1000) indicates open on C04.
What actions should be performed by the control room operators?
- a. Close the Spray Line Isolation Valve (CV-1009).
- b. Close the ERV Isolation Valve (CV.1000).
- c. Actuate ESAS channels I through 6.
- d. Maximize letdown flow.
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. ANO Unit 1 - December 1998 Reactor Operator License Eram Q=*=ela= No. 73 QID: 0209 Point Value: 1 Dunng the performance of a plant shutdown, cooldown and his ization of the RCS, the following valves are required to be closed at one point during these evolutions:
-NaOH to P-34A/P-35A Section (CA41) '
- - NaOH to P-34B/P-35B Suction (CA42)
- NaOH Storage Tank (T-10) Outlet (CA-49) '
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..What is the reason for this action? <
- a. Prevent mataminatian of the NaOH Tank from RCS back leakage during decay heat removaloperations l
- b. Pievent NaOH from leaking into the DH system and causing chemical matamination of the RCS. i
- c. To prevent NaOH from being sprayed into containment when access is open to RB.
- d. Prevent overpressunzing the NaOH tank outlet piping from backleak during decay heat removal operations. )
i Questions No. 74 ~ QID: 0210 Point Value: 1 l i
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- A LOCA has been in progress for eight hours. '
- Hydrogen Recombiner M-55B is in standby and M-55A is in senice. '
When would it be necessary to place Hydrogen Recombiner M-55B in service?
- a. When M-55A average thermocouple temperature reaches 1225"F.
- b. When H2 conantration >2% with a ramp increase in M-55A temperature.
' c. When M-55A power indw= tion reaches 60 KW and is at steady state.
- d. When Hydrogen concentration exceeds 3% with M-55 A tesp..ims at maxunum.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 75 QID: 0211 Point Value: 1 1
The unitis operating at 100% power.
Service water pumps P-4A and P 4B are in service, l A loss of P-4A occuss.
What is required of the operator to restoic service water to the j required Technical Specifications configuration?
- a. Swap P-4B MOD (A6) to the A3 supply and start P4C. 1 I
b.' Start P-4C, stop P-4B, swap P-4B MOD (A6) to the A4 supply and start P-4B. j
- c. Stop P-4B, swap P-4B MOD (A6) to the A.) supply and start P-4B and P-4C.
- d. Start P-4C, stop P-4B, swap P-4B MOD (A6) to the A3 supply and start P-4B.
Question No. 76 QID: 02/2 Point Value: 1 With regard to Technical Specification Limiting Conditions for Operations, which one of the following conditions would require that the condition be corrected within one hour to avoid performing the LCO contingencies?
- a. The Boric Acid Addition Tank (BAAT) temperature drops to a temperature that is 5 degrees above crystallization temperature.
- b. The Q CST (T-41B) level has dropped to a level of 8 feet.
- c. A Pressurizer Code Safety valve becomes inoperable.
- d. One circuit of the control room emergency air conditioning and isolation system becomes inoperable. ,
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ANO Unit 1 - December 1998 Reactor Operator License Eram Question No. 77 QID: 0213 Point Value: 1 Given:
- PaA=h outage in progress.
- Fuel hanniters are moving fuel from core to Spent Fuel Pool.
- You are assigned to perform Att. B, Refueling Boron, Temperature, Tritium, and Ixvel Check i from 1502.004, Contml of Unit 1 Refueling.
While performing Att. B you discover the Spent Fuel Ventilation Exhaust Fan VEF-14A flow rate is less than the minimum requirement.
What should your first action be to ensure procedural and Tech Spec compliance?
- a. Notify fuel handlers to stop fuel movement in the Spent Fuel Pool area
- b. Staat Spent Fuel Ventilation Exhaust Fan VEF-14B. !
- c. A4just ventilation dampers to restore flow rate above minimum. !
- d. Request I & C to verify validity of flow indication.
Questlos No. 78 QID: 0214 Point Value: 1 i i
Which of the following Control Room control panels does NOT have post accident ;
components that are verified per Repetitive Task (RT-10) following an ESAS actuation? !
- a. ControlPanelC26
- b. ContmlPanelC16
- c. ControlPanel C10
- d. Control Panel C13 l
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 79 QID: 0215 Point Value: 1 Process monitor Failed Fuel Gross (RI-1237) indication has changed from 1.8 E5 to 4.5 E6 due to a crud burst that was. caused by the starting of an RCP. Assuming the change in RI-1237 indication is from gross actisity alone, describe the failed fuel ratio change that should be seen on plant computer point R1237R7
- a. A slight rise in the indicated ratio on R1237R will be observed,
- b. A slight drop in the indicated ratio on R1237R will be obsened. l
- c. A marked rise in the indicated ratio on R1237R will be observed. i
- d. A marked drop in the indicated ratio on R1237R will be obsened.
Question No. 80 QID: 0216 Point Value: 1 Given:
- A 15 gpm Steam Generator tube leak cooldown is in progress
- Normal cooldown limits are being used with the good OTSG.
- RCS pressure is 1000 psig, Tave is 405'F.
- The CBOR is maintaining the RCS at about 140'F subcooled.
What is the primary reason the CDOR's actions are incorrect for this accidend
- a. Tube to shell Delta T limits are being exceeded.
- b. A high primary to secondary Delta P is increasing primary coolant loss.
- c. Excessive thermal stresses are being imposed on the Rx vessel.
- d. Overfill could cause the ruptured SG main steam safeties could lift.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 81 QID: 0218 Point Value: 1 Given the following plant conditions:
- 100% power
- Condensate Pumps P-2A and P-2C are in senice
- Startup Xfmr #2 Feed to A1 (A-111) is inadvertently closed.
What is the expected condensate pump response and necessary operator response to this condition?
- a. Condensate Pump P-2C will trip leaving only P-2A running; trip reactor and cany out immediate actions of 1202.001, Reactor Trip.
- b. Condensate Pump Start /Stop responses are not affected by Startup Transformer operations; no operator action is required.
- c. Condensate Pump P-2A will trip, P-2B will auto start; verify MFW pump suction pressure :ccovers to normal.
- d. Heater Drain Pump P-8A will trip causing P-2B to auto start; verify plant runs back to 40% of 902 MWe.
Question No. 82 QID: 0219 Point Value: 1 Given:
- LOCA in progress with Degraded Power conditions
- EDG #2 did NOT start
-RCS pressure stabilized at 140 psig ;
- SCM is 5 degrees With these accident conditions, which of the following would pose the greatest challenge to core cooling? l l
- a. Tube Leak in the 'N Steam Generator l
- b. EDG #1 critical trouble alarm l
- c. BWSTlevel at 15 feet
- d. P-35A Reactor Building Spray Pump trip Page 38
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1 ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 8.7 QID: 0220 Point Value: 1 Given:
- 1. Reactor power steady at 80%. l
- 2. PZR Ixvel Control selected to LT-1001 on C04 !
- 3. A break in LT-1001's reference leg causes it to drain completely.
How will Makeup Tank (T-4) level be affected by this faihire? ,
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- a. Makeup flow drops, Makeup Tank level will rise.
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- b. No effect, SASS will auto select LT-1002.
- c. Makeup flow rises, Makeup Tank level will drop.
- d. Letdown flow rises, Makeup tank level also rises.
Question No. 84 QID: 0221 Point Value: 1 Given:
- A" RPS has been placed in Channel Bypass due to RCS pressure transmitter (PT-1021) failedlow
, - Plant is at 100% power and stable
- A lightning strike by the Reactor Building has resulted in the trip of 120V Vital AC distribution panel RS-3.
What is the status of the reactor and the RPS following the trip of RS-3?
- a. Reactor has tripped due to I channel of RPS tripped.
- b. Reactor is at 100% power with one channel of RPS tripped.
- c. Reactor has tripped due to 2 channels of RPS taipped.
- d. Reactor is at 100% power with no RPS channels tripped.
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-ANO Unit 1 - December 1998 Reactor Operator License Exam j l
Question No. 85 QID: 0222 Point Value: 1 l I
Initial Conditions: Reactor power 75%
RCS pressure 2160 psig j RCS Taveis 580 degrees What would be the immediate response of the Pressurizer Spray Valve (CV-1008) upon an 'A' MFW pump trip? .
- a. Initially remain closed and then responds to pressure changes.
- b. Initially to 40% open and then responds to pressure changes. l
- c. Initially to 75% open and then responds to pressure changes.
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- d. Initially to 100% open and then responds to pressure changes.
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. Question No. 86 QID: 0223 Point Value: 1 j
\
Given-
-Plant is in cold shutdown.
- All new y co'mponents have been aligned per 1305.006, Integrated ES System Test.
- All ES EVEN Digital Channels actuated per procedure using RB pressure transmitters.
Which of the following is a properly actuated ES component for this test? j
- a. P-35A RB Spray pump flow ~1500 gpm. l l
- b. Red Train BWST Outlet valve (CV-1407) open. I
- c. P-35B RB Spray Block valve (CV-2400) open.
- d. P-35B NaOH Tank Outlet valve (CV-1617) open.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Questlom No. 87 QID: 0224 Point Value: 1 [
Given: The plantisin cold shutdown.
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> endurance run on #1 DG in progress.
'B' Decay Heat Imp in senice.
RCS is intact.
HPI pumps P-36A & P-36B are makeup flow sources.
Electricians have requested that D-11 be transferred to the emergency ;
power supply to check out the transfer switch.
Should this evolution be allowed?
- a. Yes, the swap to the emergency source does not disrupt any power
- b. No, the swap will result in a loss of decay heat.
- c. Yes, the swap will result in a momentary loss of DC control power to a makeup source, however, the source is still available.
- d. No, the swap will result in tripping the #1 DG.
i Question No. 88 QID: 0225 Polat Value: 1 During the performance of the normal DG1 monthly surveillance test, while the CBOT is paralleling the diesel to the grid, he accidentally goes to closed on the output breaker with the syncivoscope at the 15 minute past position. What would be the consequences of this action?
- a. The output breaker will close in and inunediately trip back open. I
- b. The output breaker will close in and the diesel will automatically trip.
- c. A protective feature will prevent the output breaker from closing in.
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- d. Breaker will remain open due to a lockout relay trip. I l
1 Page 41 o ;
ANO Unit 1 - pecember 1998 Reactor Operator License Exarn ,
Questlom No. 89 QID: 02.?6 Point Value: 1 Given: Reactor has tripped.
Soon aAct the trip a loss ofDC bus D01 occurs which [
resulted in an actuation of all ES even digital channels.
What is the status of the ICW cooling for the RCPs? l
- a. Results in loss ofICW cooling to all RCP coolers except for scal coolers.
- b. Results in loss ofICW cooling to all RCP coolers exapt for seal return coolers.
I
- d. Re::ults in loss ofICW cooling to all RCP coolers except for motor coolers.
Question No. 90 QID: 0227 Point Value: 1 Instrument Air pressure has dropped to 75 psig.
Which of the following is the appropriate response for the given plant conditions to restore or conserve Instrument Air pressure?
- a. Verify Service Air to Instrument Air cross-connect automatically opens.
- b. Open Unit I to Unit 2 Instrument Air cross-connect.
- d. IfICW available, isolate Seal Injection by closing CV-1206.
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j ANO Unit 1 - December 1998 Reactor Operator License Exam l
Question No. 91 Q1D: 0228 Point Value: 1 ,
Given:
l -Unit at 100% power ,
! - Due to a failure, "A" Low SG level initiate bistable is tripped in the "A" EFIC cabinet i
- I&C has the 'B' EFIC channel in bypass for monthly testing with an EFW trip signal l present on the initiate module,
- IAC inadvertantly places the 'C' RPS channel in manual bypass.
What willthe EFIC response be?
i
Plant startup in progress with reactor power at 10%.
Condenser E-11 A Vacuum Pressure Switch (PS-2850) fails to 0 "Hg.
What effect will this have on Turbine Bypass Valve (TBV) and Atmospheric Dump Valve (ADV) operations?
- a. All TBVs will remain open, both ADV isolations will open and both ADV control valves will remain closed.
- b. Only TBVs for E-11 A will close, both ADV isolations open and
'A' SG ADV will begh controlling 'A' SG pressure
- c. All TBW will close, ooth ADV control valves will open and both ADV isolaticas will remain closed.
- d. Only TBVs for E-II A will close, both ADV control valves and l both ADVisolations will open.
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ANO Unit 1 - December 1998 Reactor Operator License Exam Question No. 93 QID: 0230 Point Value: 1 While responding to the " RCS PRESSURE HI-LO" alarm, the CBOR obsen es RCS pressure at 1650 psig and falling rapidly.
Which of the following actions would be appropriate for the CBOR7
- a. Obtain concurrence from CBOT, then manually actuate ESAS and make announcement.
- b. Announce parameter and imminent ESAS actuation, then verify proper automatk
- actuation.
- d. Simultaneously announce action while manually actuating ESAS.
i Question No. 94 QIn: 0231 Point Value: I Which of the following conditions is correct with regard to preparation and installation authorization of a common unit tagout?
l b. Preparers and reviewers from both units must be licensed operators. ;
- c. Installation shall be authorized by both the Unit I and the Unit 2 CRS.
- d. Preparer and Verifier may be non-licensed if the opposite unit verifier is licensed.
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ANO Unit 1 - December 1998 Reactor Operator License Eram Question No. 95 QID: 0232 Point Value: 1 Complete the following statement:
During a Reactor Startup, the licensed Control Room Operators performing / supervising the startup shall not conduct shift relief until the reactor is critical and or shutdown by except during physics
testing. ,
- a. >= 1.0% power 1.5% delta k/k
- b. >= 5.0% power 5.0% delta k/k
- c. >= 1.0% power 5.0% delta k/k
- d. >= 5.0% power 1.5% delta k/k !
Question No. 96 QID: 0235 Point Value: 1 An NI calibration was performed yesterday. Due to a problem with a Condenser Vacuum pump, reactor power had to be lowered to 89% and has subsequently been returned to 100%. When is the next NI calibration required to be performed?
- a. Within the next 7 days. I
- b. Within the next 3 days.
- c. Within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. Within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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ANO Unit 1 - December 1998 - Reactor Operator License Exam )
I Question No. 97 QID: 0234 Point Value: 1 l During a SGTR, which of the following actions is performed to reduce plant personnel exposure?
- a. Maintaining RCS pressure low within limits of Fig. 3.
- b. Steaming bad SG to mamtain tube-to-shell DT <l50'F.
- c. Aligning HPI to provide PZR Aux Spray.
'd. Renwving all but C & D condensate polishers from service. 1 Question No. 96 QID: 0235 Point Value: 1 A reactor building entry is required at power to investigate a potential leak on the RCP Seal Cooling Pump (P-114).
You have been assigned to perform the entry and assigned a stay time of 30 minutes. ,
The dose rate in area of P-114 is 1.6 rem /hr.
Your yearly exposure to date is 1.75 rem.
Do you agree or disagree with tie stay time that has been assigned to you for this task? :
I
- a. Agree, I will NOT receive a dose sufficient to exmed the Administrative Dose ControlIxvel. I
- b. Agree, I am allos ' to exceed the Administrative Dose Control Level with HP Supervisor approval.
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- c. Disagree, I will exceed the Administrative Dose Controllevel aAer 10 minutes.
- d. Disagree, I will exceed the Administrative Dose Controllevel aAer 28 minutes.
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i ANO Unit 1 - December 1998 Reactor Operator License Exam l Questlos No. 99 QID: 0236 Polet Value: 1 i Given:
- Alternate Shutdown in pmgress due to fire in the Cable Spreading Room.
- An iminarhete control room evacuation was required. ,
Which of following is performed by the Control Room Supervisor (CRS)? ;
- a. Manually trip both Main FW pumps locally. .
- b. Start and stop HPI pump to maintain PZR level.
Question No.100 QID: 0237 Point Value: 1 It is known that elevated containment temperatures and radiation levels can affect instrurnent readings.
How are allowances for these effects made when par =Mer values are required in EOP steps? !
- a. Transmitters inside containment are environmentally qualified for these effects.
- b. The SE uses a set ofin Loird,r.t tables during accident conditions.
- c. SPDS displays alternate values when these conditions are reached.
- d. EOP parameter values for these conditions are inside brackets
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ANO Unit 1 - December 1998 Initial RO Exam Key i
Question No.1 QID: 0131 Point Value: 1 Answen
- d. The channel B bypass prevented by an interlock from the channelalreadyin bypass.
Question No. 2 QID: 0132 Point Value: 1 Answen
- c. 240 to 249 gallons Question No. 3 QID: 0133 Point Value: 1 Answen
- b. Minimizes surge and spray line temperature differentials and maintains pressurizer boron concentration near that in the RCS.
Question No. 4 QID: 0134 Point Value: 1 Answen
- c. Discrimination separates out gamma and alpha pulses to provide a true neutron pulse.
With the discrimination set too high, power will indicate lower than actual power.
Question No. 5 QID: 0135 Point Value: 1 ,
Answen
Question No. 6 QID: 0136 Point Value: 1 Answen-
- c. Discharge Flume monitor is also in alarm.
Question No. 7 QID: 0137 Point Value: 1 Answen
- c. Both Main Feedwater Block Valves close in slow speed.
Question No. 8 QID: 0138 Point Value: 1 L: Answer:
- b. Thermal shock to the turbine rotor.
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ANO Unit 1 - December 1998 IDitial RO Exam Key l Question No. P QID: 0139 Point Value: 1 Answen
Question No.10 QID: 0140 Point Value: 1 Answen
- a. SealInjection Question No.11 Q1D: 0141 Point Value: 1 Answen
- a. excessive seal wear and cavitation.
Question No.12 QID: 0142 Point Value: 1 Answen
- d. AAct it is determined that the component is no longer needed and approval is obtained from the CRS/SS.
Question No.13 QID: 0143 Point Value: 1 Answen . i
- c. Acceptable, independent verification can be waived for valve alignments on a case-by-case basis with the Superintendent's approval.
Question No.14 QID: 0144 Point Value: 1 Answen-
- c. Leave the area and notify Health Physics.
Question No,15 QID: 0145 Point Value: 1 Answen
- d. Disable all group in-limits except Group 8.
Question No.16 QID: 0146 Faint Value: 1 ;
Answen l
- a. 1203.027,
- Loss of Steam Generator Fee f j
ANO Unit 1 - December 1998 Initial RO Exam Key I i
Question No.17 QID: 0147 Point Value: 1 i Answer: l
- a. ICS will run the plant back at 30*Nmin and power will stabilize at 40%
Question No.18 QID: 0152 . Point Value: 1 Answen
- b. Loss of Startup Transformer #2 Question No.19 QID: 0153 Point Value: 1 Answen
- d. One emergency Recirc Fan will start, all isolation dampers close l
Question No. 20 QID: 0154 Point Value: 1 Answer:
- a. RCP trip Question No. 21 QID: 0155 Point Value: 1 Answer:
b,"A" RPS channel will trip.
Question No. 22 QID: 0156 Point Value: 1 Answer:
- b. Overcooli y .202.003 Question No. 23 QID: 0157 Point Value: 1 Answer:
- d. Condenser vacuum pump auto starting.
Question No. 24 QID: 0158 Point Value: 1 <
Answer:
- c. 6 days .
ANO Unit 1 - December 1998 Initial RO Exam Key i
Qsestion No. 23 QID: 0159 Point Value: 1 i Answen
- b. Stop one RCP in each loop. !
i Question No. 26 QID: 0160 Point Value: 1 Auswen
- b. Loss ofDC Bus D11 I
Question No. 27 QID: 0161 Point Value: 1 Answen
- d. Refer to Tech Specs and recover the dropped rod. ;
Question No. 28 QID: 0162 Point Value: 1 Answen
- a. 360 MWe Question No. 29 QID: 0163 Point Value: 1 Answen d). CET is rising above 610 deg F and subcooling margin is 28 deg F.
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Question No. 30 QID: 0164 Point Value: 1 Answen
- a. Reduce decay heat removal flow below 2000 gpm.
l Question No. 31 QID: 0165 Point Value: 1 Answen
- b. Turbine did not trip s
Question No. 32 QID: 0166 Point Value: 1 Answen
- a. Bad OTSG 1evel 410" and rising l
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ANO Unit 1 - December 1998 Initial RO Exam Key Question No. 33 QID: 0167 Point Value: 1 Answen
- b. Verify no release in progress at Disch Flow to Flume (FI-4642) on C19.
Question No. 34 QID: 0168 Point Value: 1 Answen
- b. The alignment can result in conditions that may cause excessive radiation exposure I
Question No. 33 QID: 0169 Point Value: 1 Answen
- a. PZR Level Control Valve, CV-1235, will open to establish a higher steady-state PZR level.
Question No. 36 QID: 0170 Point Value: 1 Answen
- d. To re-establish instrument air and ICW.'
Question No. 37 QID: 0171 Point Value: 1 Answen
- b. Declare the tod inoperable and verify a 1.5% available shutdown margin exists.
Question No. 38 QID: 0172 Point Value: 1 l Answen
- a. A plant cooldown is required and normal offsite power is NOT available.
Question No. 39 QID: 0173 Point Value: 1 Answer:
- b. For maximum batch size (999999).
Question No. 40 QID: 0174 Point Value: 1 Answen
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'ANO Unit 1 - December 1998 Initial RO Exam Key Question No. 41 QID: 0175 Point Value: 1 Answen
- c. Verify ICW for RCP Air and Lube Oil Coolers and Control Rod Drive Outlets (CV-2220 & CV-2221) are open.
Question No. 42 QID: 0176 Point Value: 1 Answen
- a. Release the manual actuator on the main pilot cylinder or use the manual trip switch located on the associated switch module on panel C-463.
Question No. 43 QID: 0177 Point Value: 1 Answen
- c. RCS Tave would rise, RCS pressure would rise, Pressurizer level would rise Question No. 44 QID: 0178 Point Value: 1 Answen
Question No. 45 QID: 0180 Point Value: 1 Answen
- d. Tave 560 degrees, SCM 25 degrees, RCS pressure 2100 psig Question No. 46 QID: 0181 Point Value: 1 Answen
Question No. 47 QID: 0182 Point Value: 1 Answen
- b. Align Pressurtzer AUX Spray to LPI system.
- Question No. 48 QID: 0183 Point Value: 1 Answen
- c. If RCP seal bleedoff temperatures are >180 degrees, CV-1207 is slowly opened to minimize thermal shock to the RCP seals.
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ANO Unit 1 - December 1998 Initial RO Exam Key Question No. 49 QID: 0184 Point Value: 1 Answer:
- c. Trip the reactor due to no on-scale indication of neutron flux available.
Question No. 50 QID: 0186 Point Value: 1 Answen
- b. Overheating (1202.004)
Question No. 51 QID: 0187 Point Value: 1 I Answen
- d. Transfer D21 to emergency supply D01.
Question No. 52 QID: 0188 Point Value: 1 Answen l
- d. Secure fuel handling activties until RI-8017 is operable or a po: table su:vey instrument having the appropriate ranges and sensitivities is obtained.
l Question No. 55 QID: 0189 Point Value: 1 Answen
- b. CV.1235 fails closed and Pressurizer level will lower.
Question No. 54 QID: 0190 Point Value: 1 Answen b.1.6 gpm 40 / 25 = 1.6 Question No. 55 QID: 0191 Point Value: 1 Answen c.18 incies Question No. 56 QID: 0192 Point Value: 1 Answen i- a. RSI l
ANO Unit 1 - December 1998 Initial RO Exam Key Question No. 57 QID: 0193 Point Value: 1 Answen
- a. Tave 579 degrees, Thot $93 degrees, Tcold 564 degrees, total FW flow 6.5 million Ibm /hr.
Question No. 58 QID: 0194 Point Value: 1 Answen
- c. Difliculty in reducing RCS pressure. j l
a Question No. 59 QID: 0195 Point Value: 1 Answen
- c. 'B' MFP Suction Pressure computer point (P2830) l Question No. 60 QID: 0196 Point Value: 1 Answen
- c. A high radiation setpoint has been exceeded on SPING 1.
Question No. 61 QID: 0197 Point Value: 1 Answen
- c. Incis may not be sufficient to reflood the vessel following a LOCA.
Question No. 62 QID: 0198 Point Value: 1 i Answen
- a. To prevent inadequate pump suction pressure on ECCS pumps.
Question No. 63 QID: 0199 Point Value: 1 I
.Answen
)
Question No. 64 QID: 0200 Point Value: 1 Answen j
- c. The SFP level will stay relatively constant due to siphon holes in the discharge piping.
ANO Unit 1 - December 1998 Initial RO Exam Key Question No. 65 QID: 0201 Point Value: 1 l Answen
- c. 300-340 inches.
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Question No. 66 QID: 0202 Point Value: 1 l Answen
- d. Trip the reactor and go to Reactor Trip tab (1202.001) of the EOP.
Question No. 67 QID: 0203 Point Value: 1 Answen
- c. Declare SV-2663 inoperable and doenergize CV-2663 closed.
Question No. 68 QID: 0204 Point Value: 1 Answen
- b. #1 DG is inoperable due to the level in T-30A being <160 gallons. !
Question No. 69 QID: 0205 Point Value: 1 Answen l
- b. The discharge valve on the tripped purnp did not go completely closed and circulating water is short cycling.
I Question No. 70 QlD: 0206 Point Value: 1 Answer:
- d. It can be actuated locally or by placing the MAN TRIP switch on C463 to the OPERATED position.
Question No. 71 QID: 0207 Point Value: 1 Answen
- d. Loss of decay heat removal Question No. 72 QID: 0208 Point Value: 1 Answer:
- b. Close the ERV Isolation Valve (CV-1000).
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ANO Unit 1 - December 1998 Initial RO Exam Key Questlom No. 73 QlD: 0209 Point Value: 1 Answer:
- b. Prevent NaOH from leaking into the DH system and causing chemical contamination of the RCS.
Questlos No. 74 QID: 0210 Point Valuci 1 Answer:
- d. When H2 concentration exceeds 3% with M-55A temperature at traximum..
Question No. 75 QID: 0211 Point Value: 1 Answer:
- d. Start P-4C, stop P-4B, swap P-4B MOD (A6) to the A3 supply and start P-4B.
Question No. 76 QID: 0212 Point Value: 1 Answer:
- c. A Pressurizer Code Safety valve becomes inoperable.
Question No. 77 QID: 0213 Point Value: 1 Answer:
- a. Notify fuel handlers to stop fuel movement in the Spent Fuel Pool area.
Question No. 78 QID: 0214 Polet Value: 1 Answer:
- d. Control Panel C13 Question No. 79 QID: 0215 , Point Value: 1 Answer:
- c. A starked rise in the indicated ratio on R1237R will be obsen'ed.
Question No. 60 QID: 0216 Point Value: 1 Answer:
- b. A high primary to secondary DP is increasing primary coolant loss.
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l ANO Unit 1 - December 1998 Initial RO Exam Key l
Question No. 81 QID: 0218 Point Value: 1 Answen
- a. Condensate Pump P-2C will trip leaving only P-2A running; trip mactor and cany out unmediate actions of j 1202.001, Reactor Trip. ,
Question No. 82 QID: 0219 Point Value: 1 Answer:
- b. EDG #1 criticaltrouble alarm
)
Question No. 83 QID: 0220 Point Value: 1 Answen
- a. Makeup flow drops, Makeup Tank level will rise.
Question No. 84 QID: 0221 Point Value: 1 Answen
, b. Reactor is at 100% power with one channel of RPS tripped.
Question No. 85 QID: 0222 Point Value: 1
- Answen
- a. Initially remain closed and then respond to pressure changes.
Question No. 86 QID: 0223 Point Value: 1 .
Answer:
- d. P-35B NaOH Tank Outlet valve (CV-1617) open.
Question No. 87 QID: 0224 Point Value: 1 Answer:
- d. No, the swap will result in tripping the #1 DG.
Question No. 88 QID: 0225 Point Value: 1 Answer:
- c. A protective feature will prevent the output breaker from closing in.
ANO Unit 1 - December 1998 Initial RO Exam Key Question No. 89 QID: 0226 Point Value: 1 Answen
- b. Results in loss ofICW cooling to all RCP coolers except for seal return coolers.
Question No. 90 QID: 0227 Point Value: 1 Answen
- b. Open Unit I to Unit 2 Instrument Air cross-connect.
Question No. 91 QID: 0228 Point Value: 1 Answen
- b. Only TBVs for E-11 A will close, both ADV isolations open and
'A' SG ADV will begin controlling 'A' SG pressure.
Question No. 93 QID: 0230 Point Value: 1 Answen
- d. . Simultaneously anounce action while manually actuating ESAS.
Question No. 94 QID: 0231 Point Value: 1 Answen
- c. Installation shall be authorized by both the Unit I and the Unit 2 CRS.
Question No. 95 QID: 0232 Point Value: 1 Answen
- a. >= 1.0% power 1.5% delta k/k Question No. 96 QID: 0233 Point Value: 1 Answen
- c. Within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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ANO Unit 1 - December 1998 Initial RO Exam Key Question No. 97 QID: 0234 Point Value: 1 Answen
- d. Removing all but C & D condensate polishers from service.
Question No. 98 QID: 0235 Polhi Value: 1 Answen
- c. Disagree, I will exceed the Administrative Dose Control Level after 10 minutes.
Question No. 99 QID: 0236 Point Value: 1 Answen
- b. St4rt and stop HPI pump to maintain PZR level.
Question No.100 QID: 0237 Point Value: 1 Answen
- d. EOP parameter values for these conditions are inside brackets.
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