IR 05000528/1995015
| ML17312A559 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/02/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17312A558 | List: |
| References | |
| 50-528-95-15, 50-529-95-15, 50-530-95-15, NUDOCS 9602270114 | |
| Download: ML17312A559 (18) | |
Text
EitCLOSURE ATTACHlCENT 4
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comiorrmIIL APS Arizona Public Service Company P.o. SCX %800
~ PHOEMX,hRROHA b50724QS 054-02339-RAN/TEM August 2, 1995 Nuclear Regulatory Commission - Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 ATTN:Ryan Lantz SUBJECT:
NRC Sample Plan Enclosed is the NRC Sample Plan for the October 1995 NRC Exam at Palo Verde Nuclear Generating Station.
Ifyou have any question please contact myselfRobert A. Nunez at 602-393-6580.
Sincerely,
)7~'obert A. Nunez Dept. Leader OPS 8: Eng. Training RAN/TEii/cgc t
9602270114 960220 PDR ADQCK 05000528 V
Knowledge and Abilities Record Form PLANT-%IDEGENERIC RESPONSIBILITIES PWR - Senior Reactot'Operator - 17/o
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K1.01 Knowledge ofhow to conduct and v'erifyvalve 3.7 lineu s.
K1.02 K1.03 K1.04 K1.07 K1.13 K1.15 Kl.16 A1.02 A1.05 A1.10 A1.11 A1.13 A1.15 A1.16 Knowled e of
'nd clearance rocedures Knowledge of 10 CFR 20 and related facility radiation control r uirements.
Knowled eoffacili ALARA ro ram Knowledge ofsafety procedures related electrical ui ment.
Knowledge ofsafety procedures related to o
en-deficient environment.
Knowledge ofsafety procedures related to h dro en.
Knowledge offacilityprotection requirements, including fire brigade and portable Qre-fighting ui ment usa e.
Abili to execute rocedural ste s.
AbiTityto make accurate, clear, and concise verbal re orts.
Abilityto coordinate personnel activities inside the control room.
Abilityto direct personnel activities inside the control room.
Abilityto locate control room switches, controls, and indications, and to determine that they are correctl reQectin the desired lant lineu
.
Abilityto use plant computer to obtain and evaluate parametric information on system and corn onent status.
Abilityto take actions called for in the Facility Emergency Plan, including (ifrequired)
su rtin oractin asaEmer en Coordinator.
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Knowledge and Abilities Record Form PLANTSYSTEMS PWR - Senior Reactor Operator -
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~i~j'.,!.:i:.;::-".i:::-.'-'-="-::i. i '"'.'.::;::i 001 Control Rod Drive S stem 003 Reactor Coolant Pum S stem 004 Chemical and Volume Control S stem 026 Containment S ra S stem 056 Condensate S stem 059 Main Feedwater S stem 013 Engineered Safety Features Actuation S stem 061 Auxiliary/Emergency Feedwater S stem 014 Rod Position Indication System 015 Nuclear Instrumentation Svstcrn 017 In-Core Tem erature Monitor Svstem 022 Containment Coolin S stem 063 DC Electrical distribuuon S stem 068 Li uidRadwasteS stem 071 Waste Gas Dis osal S stem 072 Area Radiation Monitorin Svstem
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001 K5.08 Reasons for rod insertion limits and affect on S/D 4.4 Mar 'n 003 004 013 K4.04 Knowledge ofadequate cooling ofRCP motor and seals K1.15 Knowledge ofphysical connection between CVCS and ECCS A4.03 Abilityto manually operate and/or monitor ESFAS initiation 3.1 4.0
013 SG15 Abilityto recognize abnormal indications for 4.2 system operating parameters which are entry-level conditions for EOPs/AOPs 014
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A1.02 Predict/monitor changes in parameters assoc with control rod position indication or control room anels 3.6 015 017 022 026 056 059 061 K3.01 Effect ofloss ofNIS on NIS on RPS AZ.02 Predict im act ofcore dama e or ITMs stem K2.01 Knowledge ofpower supplies to the CTMT Coolin Fans A3.01 Monitor automatic operation ofCSS/pump starts and correct MOV osition A2.04 Predict the impact ofloss ofcond pumps or cond s stem K4.16 Knowledge ofsystem features which provide for MFP tri s A3.04 Monitor auto operation ofA&Vsystem for auto AFW isolation 4.1 3.1 4.5 2.8 3,2 4.2 Exmuncrs'aodbook
Knowledge and Abilities Record Form PLANTSYSTEMS PWR-Senior Reactor Operator - 40%
068 071 072 004 026 K6.10 Performance and design attributes ofradiation monitors A4.09 Operate/monitor in the control room Waste Gas Release rad monitor SG1 Knowledge ofsystem status which require notification of lant ersonnel K6.09 Knowled eoffiow athsforemer en boration SG9 Abilityto locate and operate controls including local controls 2.9 3.5 3.6 3,6 Gr'up O'Hant Systems -"17%'.i! "" ':.::.'.::::"=-:. -::"-;.::=
002 006 010 011 012 016 028 029 033 Reactor Coolant S stem Emer enc Core Cooling Svstem Pressurizer Pressure Control Svstem Pressurizer Level Control System Reactor Protection System Non-Nuclear Instrumentation S stem Hydrogen Recombiner and Purge Control S stem Containment Pur e S stem S ent fuel Pool Coolin S stem 035 039 055 062 073 075 079 086 103 Steam Generator S stem Main and Reheat Steam S stem Condenser AirRemoval S stem'C Electrical Distribution Svstem Process Radiation Monitorina S sterr.
Circulatin Water S stem Station Aire System Fire Protection S stem Containment S stem 034 Fuel Handlin E ui ment S stem Sys fern/"..:.:; ':".'KfA'8'..","":KtA'Topic...- "> '" "::.=:.."..::.. '.=:.,'" ";::..'."'.-:--~""'~"-'acting;.'.
002 006 010 011 K5,05 Why PZR level should be kept within the
~.8 ro ammed band
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A1.02 Abilityto predict change in parameters associated 4.4 with operating ECCS controls including subcoolin K2.01 Knowled e ofbus ower su lies to PZR heaters 3.4 K1.01 Kno'wledge ofphysical connections or 4.0 cause/effect relationships between PZR LCS and PZR PCS 012 016 028 K4.02 Basis for RPS set oints K3.04 Effect a loss ofNNIS willhave on MFW svstem K6.01 Knowledge ofperformance/design attributes of H2 Reconbiners 4.3 2.7 3.1 Euunincts',Handbook
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Knowledge and Abilities Record Form PLANTSYSTEMS PWR - Senior Reactor Operator - 40%
029 033 034 035 039 055 062 064 073 075 086 103 SGl 5 Abnormal indications for system operating parameters which are entty level condition for EOPs A2.03 Predict 'ct ofabnormal s ent fuel ool level A3.02 Abilityto monitor auto operator ofCHES load limits A4.06 Abilityto manually operate/monitor S/G isolation on steam leak or tube ru ture/leak K4.05 Design features/interlocks which provide for auto isolation t.w~S ~
A3.03 Monitor auto diversion ofCARS exhaust K3.03 Knowled e ofeffect a loss ofAC has on ED/G K4,02 Trips for ED/G which operating (normal or emer en K3.01 Knowledge ofloss ofPRM willhave on rad eff releases A4.01 Abilityto manually operate/monitor Emer en
/essential SWS K5.04 Hazards to personnel as a result ofGre type and methods of rotection K1.02 Knowledge ofrelationship between containment and Cl 3.6 3.5 4.6 3I7
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4.2 4.2 3,2 3.5 4.1 Examines'andbook
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Knowledge and Abilities Record Form PLANT SYSTEMS P%R - Senior Reactor Operator - 40%
005 007 008 Residual Heat Removal S stem Pressurizer ReliefTank/Quench Tank S stem Com onent Coolin Water S stem Steam Dump System/Turbine Bypass Control 076 078 Main Turbine Generator S stem Service Water System Instrument AirS em
'.-..System'0;;.'-..'",:.K/A:¹, ',-'K/Q.Togie:".:: -'.- '.:. :;,,::.:I:::-', '-',:::::::.'.:-: -';.-':-'::;:;:--~"i R'itirij.=
I 005 A2.02 Pressure transient protection during cold
shutdown 0007 045 078 K3.01 Knowled e. loss ofPRTS willhave in CTMT K4.12 knowled e ofAutomatic Turbine Runback A3.01 Abilit tomonitorautoo sincludin air ressure 3.6
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Knowledge and Abilities Record Form EMERGENCY PLANTEVOLUTIONS PWR - Senior Reactor Operator - 43%
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~4 000001 000003 000005 000011 000015 000024 000026 000029 000040 Continuous Rod Withdrawal Dro ed Control Rod Inoperable/Stuck Control Rod Large Break LOCA RCP Motor Malfunction-Emeraenc Boration Loss ofCom onent Coolin Water Anticipated Transient Without Scram Steam Line Ru ture 000051 Loss ofCondenser Vacuum 000055 Loss ofCMsite and Onsite Power.
000057 Loss ofVitalAC Electrica Instrument Buss 000059 Accidental Liquid Radioactive-Waste Release 000067 Plant Fire On Site 000068 Control Room Evacuation 000069 Loss ofCon::mnent Int 000074 Inadequate Core Cooling 000076 Hi h Reactor Coolant Activit
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000001 EA2.03 Proper actions to be taken ifauto safety function 4.8
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J have not taken lace 000003 EK3.08 Criteria for ino erable control rods 4.2 000005 000011 000015 SG8 Recognize indications for system operating 3.8 parameters which are entry-level conditions for TechS ec EK1.01 Natural circulation and cooling, including reQux boilin EK3.03 Sequence ofevents for manually tripping reactor and RCP as a result ofan RCP malfunction 000026 EA1.03 Essential Cooling Water as a backup to Nuclear Coolin Water 000029 EK2.02 Knowled e ofsensors and detector ppp040 EA2.03 Difference between steamline ru ture and LOCA 000051 EK3.01 Loss oF steam dum abili on loss ofvacuum 000055 EA1.04 Reduction oFloadsonthebatte 000057 EK3.01 Action in EOP for loss ofvital AC pppp59 EK2.01 Knowled e ofRadioactive li uid monitors 000067 EA2.04 Fires extent ofpossible operational damage to lant ui
.
000068 000069 EA1.21 Transfer ofcontrols Gom CR to Remote Shutdown Panel EA2.02 Veri6cation ofautomatic & manual means of festorlll lnte 000024 EK3.02'ctions contained in AOP for emer enc boration
3.6 4.4 2.8 4,3 4.1
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Knowledge and Abilities Record Form F'MKRGENCYPLANTEVOLUTIONS PWR - Senior Reactor Operator - 43%
000074 EK1.03 Knowledge ofprocesses for removing decay heat from the core 000076
'SG4 Knowledge ofbases in technicalspeciflcations for LCOS and safet limits 000011 EK3.12 ActionscontainedinEOPforl ebreakLOCA 000040 EA1.09 Set oints ofmain steam safe valves 000055 EK3.02 Actions contained in EOP for station blackout 000029 EK3.12 Actions contained in EOP for ATWS 000051 EA2.02 Conditions r uirin reactor and/or turbine tri 000074 EA2.01 Determine/Inte ret Subcoolin Mar
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000007 Reactor Tri 000008 Pressurizer Va or S ace Accident 000009 Small Break LOCA 000022 Loss ofReactor Coolant Makeu 000025 Loss ofResidual Heat Removal S stem 000027 Pressurizer Pressure Control System Malfunction 000032 Loss ofSource-Range Nuclear Instrumentation 000037 Steam Generator Tube Leak 000038 Steam Generator Tube Ru ture 000054 Loss ofMain Feedwater 000058 Loss ofDC Power 000060 Accidental Gaseous-Waste Releasn 000061 Area Radiation Monitoring Systcrr.
Alarms 000065 Loss ofInstrument Air
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,000007 EK1.06 Relationship ofemergency feed flow to S/6 and '.1 decay heat removal followin a reactor tri I
000007 EK3.01
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Actions contained in EOP for reactor tri 4.6 000008 000009 000009 000009 000022 000025 EA2.23 Criteria for throttlin HPSI after a small LOCA EK2,03 Knowled e ofSGs 4.3 3.3 EK3;23 RCP tri in r uirements (n~-mJMckuv )
4.3 EK3.21 Actions contained in EOP for small break LOCA/leak 4.5 EK3.03 Immediate actions in EOP for loss ofSDC 4.1 EA2.02 Abilityto determine/interpret Charging Pump
roblems 000025 EAl.l2 Abilit to monitor RCS tern erature indicators 3.5 000027 SG5 Knowled e ofannunciation alarms and indications 3.3 000032 EA2.06 Conflrmation ofreactor tri 4.1 Exanuncra'andbook
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Knowledge and Abilities Record Form.
EMERGENCY PLANTEVOLUTIONS PWR - Senior Reactor Operator - 43%
000037.
000038 000054 000058 000060 000061 000065 EA1.06 Abilityto monitor/interpret main steamline rad monitors EK3.06 Actions contained in EOP for SGTR SG7 Abili to a I all em limits and recautions EA2.03 Determine/interpret impact or ability to o crate/monitor EK2.02 Knowled e ofaux bid ventilation stem EA1.01 Abili to o crate/monitor automatic actuation EA2.06
'When to tri reactor iflA ressure is decreasin 3.9 4.5 3.0 3.9 r
3.1 3.6 Grou'p';1IL'.Emergent'and Abnoinial.Plant Evaftiations'<<;3':!.':...-.:;.:='-':-::::.;--"'::,'!
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000028 Pressurizer Level Malfunction 000036 Fuel Handlin Incident 000056 Loss ofOffsite Power 000028 EK2.03 Knowledge ofcontrollers and ositioners 000036 EK3.03 Guidance contained in AOP for Rel handling 4.1 incident 000056 EA2.44 Abilitvto determine/inte ret indications ofLOOP 4.5
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