ML101270338

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AN1-2010-03 Final Written Examination
ML101270338
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 03/16/2010
From:
NRC Region 4
To:
References
AN1-2010-03
Download: ML101270338 (20)
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{{#Wiki_filter:ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One-Unit I Date of Exam: 31512010 1---SRO-Only Points Tier Group KKKKKKAAAAG A2 G*Total 1 2 3 4 5 6 1 2 3 4*Total 1.1 333 33 3 18 6 Emergency&Abnormal 2 j N/A j_N/A 1.Evolutkrns Tier Totals 5 5 4 4 5 4 27 10 1 33233222233 28 5 2.Plant 2 011!10 3 Systems Tier Totals 3 43 4 4 3 3 3 3 4 4 38 8 3.Generic Knowledge and Abilities 1]2 3 4 10 1 2 3 4 7 Categories I I 1 2 1 4 Note: 1.Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO only outlines (i.e., except for one category in Tier 3 of the SRO-oniy outline, the"Tier Totals"in each K/A category shall not be less than two).2.The point total for each group and tier in the proposed outline must match that specified in the table.The final point total for each group and tier may deviate by+/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.3.Systems/evolutions within each group are identified on the associated oufline;systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added.Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements. 4.Select topics from as many systems and evolutions as possible;sample every system or evolution in the group before selecting a second topic for any system or evolution. 5.Absent a plant-specific priority, only those K/As having an importance rating (IR)of 2.5 or higher shall be selected.Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 7*The generic (G)K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.Refer to Section D.1.b of ES-401 for the applicable K/As.8.On the following pages, enter the K/A numbers, a brief description of each topic, the topics'importance ratings (IRs)for the applicable license level, and the point totals (#)for each system and category.Enter the group and tier totals for each category in the table above;if fuel handling equipment is sampled in other than Category A2 or G*on the SRO only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note#1 does not apply).Use duplicate pages for RO and SRO-only exams.9.For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#)on Form ES-401-3.Limit SRO selections to K/As that are linked to 10 CFR 55.43.ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 S-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group I (RO)E/APE#/Name/Safety K/A Topic(s)Function__________________________________________ 000007 (BW/E02&E10; EK3.O1-Actions contained in EOP for CE/E02)Reactor Trip-reactor trip Stabilization_-_Recovery /_1______________________________________ 2.2.37-Ability to determine operability 000008 Pressurizer Vapor and/or availability of safety related Space Accident/3 equipment 000009 Small Break LOCA/3 EAI.02-RB Sump level 000011 Large Break LOCA/3 EK2.02-Pumps 000015/17 RCP Malfunctions/ AK2.1O-RCP indicators and controls.4__________________________________________ 000022 Loss of Rx Coolant Not selected Makeup/2________________________________ AK1.01-Loss of RHRS during all modes of 000025 Loss of RHR System/operation. 4__________________________________________ 000026 Loss of Component Not selected Cooling Water/8_____________________________________ AK2.03-Controllers and positioners. 000027 Pressunzer Pressure Control System Malfunction /3 000029 ATWS/1 EA2.02-Reactor trip alarm.000038 Steam Gen.Tube 2.4.6-Knowledge of EOP mitigation upture/3 strategies. 00040 (BW/E05;CE/E05;AKI.01-Consequence of PTS.W/E12)Steam Line Rupture-Excessive_Heat Transfer/4__________________________________________ AA2.06-AFW adjustments needed to 000054 (CE/E06)Loss of Main maintain proper T-ave, and S/G level.Feedwater/4____________________________________ EAI.05-Battery, when approaching fully 000055 Station Blackout/6 discharged. AK3.01-Order and time to initiation of 000056 Loss of Off-site Power/power for the load sequencer. AA2.05-S/G pressure and level meters.000057 Loss of Vital AC Inst.Bus/6__________________________________ AKI.01-Battery charger equipment and 000058 Loss of DC Power I 6 instrumentation. 000062 Loss of Nudear Svc AK3.02-The automatic actions Water/4 (alignments) within the nucleai service water____________________________ resulting from the actuation of the ESFAS.000065 Loss of Instrument Air/Not selected 8_________________ W/E04 LOCA Outside Not selected Containment /3 I-I-I x x I-ES-401 Form ES-401-2-x ES-401 PWR Examination Outline Form ES-401-2 S-401 PWR Examination Outline Form ES-401-2 Emergencyc1 Abnormal Plant Evolutions -Tier 1/Group I (RO)E/APE#1 Name!Safety K/A Topic(s)Function______________________________________________ W/E1 1 Loss of Emergency Not selected Coolant Recirc./4_________________________________________ BW/E04;W/E05 Inadequate EAI.3-Desired operating results during Heat Transfer-Loss abnormal and emergency situations. of Secondary Heat Sink/4________________________________________________ 000077 Generator Voltage and Electric_Gild_Disturbances /6___________________________________________ K/A Category Totals: 2.1.25-Ability to interpret reference material, such as.ra.hs, curves, tables, etc.Group Point Total: ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 5-401 E/APE#I Name/Safety Function 000001 Continuous Rod Withdrawal /1 000003 Dropped Control Rod/1 000005 Inoperable/Stuck Control Rod/1 000024 Emergency Boration/1 000028 Pressurizer Level Malfunction /2 000032 Loss of Source Range NI/7 000033 Loss of Intermediate Range NI/7 000036 (BW/A08)Fuel Handling Accident/8 000037 Steam Generator Tube Leak/3 000051 Loss of Condenser Vacuum/4 000059 Accidental Liquid RadWaste Rel.!9 000060 Accidental Gaseous Radwaste Rel./9 000061 ARM System Alarms/7 000067 Plant Fire On-site/8 000068 BW/A06 Control Room Evac./8 000069 (W!E14)Loss of CTMT Integrity/5 000074 (W/E06&E07) Inad.Core Cooling'4 000076 High Reactor Coolant Activity!9 WIEO1&E02 Rediagnosis &SI Termination /3 W/E13 Steam Generator Over-pressure /4 W/E15 Containment Flooding/5 W/E16 High Containment Radiation/9 BW/A01 Plant Runback!1 BW!A02&A03 Loss of NNI-XIY!7 BW/A04 Turbine Trip/4 BW/A05 Emergency Diesel Actuation/6 BW/A07 Flooding/8 BW/E03 Inadequate Subcooling Margin/4 ES-401 Not selected Not selected Not selected Not selected AK1.01-PZR reference leak abnormalities. X AA2.04-Satisfactory source-range /intermediate-ran e overla Not selected AK2.1-Changed to randomly selected S stem 068 AK2.07 AAI.10-CVCS makeup tank level indicator Not selected Not selected AKI.04-Changed to randomly selected S tern 028 AKI.01 AK3.02-Guidance contained in alarm res onse for ARM s stem.AKI.02-Fire Fi htin AK2.07-ED/G Not selected Not selected Not selected Not selected Not selected Not selected Not selected Not selected Not selected Not selected AK2.1-Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.AA2.2-Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments Not selected PWR Examination Outline Emer enc and Abnormal Plant Evolutions -Tier 1!Grou 2 RO K K K A A G K/A Topic(s)12312 x x x Form ES-401-2 IR#QID Typ e NIA N!A N!A NIA 2.8*19 776 N 3.1 20 777 N N!A NIA 2.9 21 778 N N!A N/A N!A 3.4 22 634 D 3.1 23 695 DR 3.3 24 779 0 N/A NIA NIA NIA N!A N/A NIA NIA NIA NIA 4.0 25 349 D 3.3 26 780 N NIA x x 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 BW/E08;W/E03 LOCA Cooldown-e.ress./4 1E09;CE/A13;WIEO9&ElO Natural Circ./4 BW/E13&E14 EOP Rules and Enclosures CE/All;W/E08 RCS Overcooling -PTS/4 CE/Al 6 Excess RCS Leakage/2 CE/E09 Functional Recovery K/A Cate.o Point Totals: Not selected Not selected 2.2.22-Knowledge of limiting conditions for operations and safety limits.Not selected Not selected V Not selected Group Point Total: IV V x 121 ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 A2.08 changed to A2.01-Loss of CCW Pum.PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2/Group I (RO)K/A Topic(s)1(5.05-The dependency of RCS flow rates upon the number of operating RCP's A4.08-RCP cooling water supplies 2.1.34 changed to 2.2.38-Knowledge of conditions and limitations in the facility license 1(4.03-Protection of ion exchangers (high letdown temperatures will isolate ion_______________________________ exchangers) _______________________ 1(2.01-RHR Pumps 1(6.10-Valves 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 10 Pressurizer Pressure ontrol 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 1(5.02-Method of forming a steam bubble in the PZR K3.02-RPS K6.10-Permissive circuits 2.1.32-Ability to explain and apply system limits and precautions K4.10-Safeguards equipment control reset A3.01-Initiation of safeguards mode of operation Not Selected 1(1.01-ECCS A2.04-Malfunctioning steam dump A3.03-Feed water pump suction flow pressure 1(4.16-Automatic trips for MFW pumps Al.04 changed to Al.01-S/G level I: ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 2 PWR Examination Outline Form ES-401-2 Plant S stems-Tier 2/Grou I RO K K K K K K A A A A G KIA Topic(s)IR#ID Ty 1 234561234 e 062 AC Electrical Distribution X 2.4.35-Knowledge 3.8 46 790 N of local auxiliary operator tasks during an emergency and the resultant operational effects.3.3 47 316 D K2.01-Major s stem loads 063 DC Electrical Distribution 1(3.02-3.5 48 86 D Components using DC control ower 064 Emergency Diesel Generator X 1(2.01-Air 2.7 49 791 N compressor X 3.4 50 792 N 1(1.05-Starting air 5 stern 073 Process Radiation Monitoring X 1(5.01-Radiation 2.5 51 672 R theory, including sources, types, units, and effects 076 Service Water X A4.02-SWS valves 2.6 52 793 D X Al.02-Reactor and 2.6 53 794 N turbine building closed cooling water tern eratures 078 lnstrumentAir X Kl.03 changed to 2.7 54 535 D KI.02-Service air 103 Containment X A4.06-Operation of 2.7 55 795 D the containment ersonnel airlock K/A Catego Point Totals: 3 3 2 3 3 2 2 2 2 3 3 Grou Point Total: 28 ES-401 Form ES-401-2 m C')C-n 0-'3 m C')C 1%)-(fl-D CD o L C)CD , 0=g.CD W'CD.i r rTI 0 C 0 m x 3 0 0 C (D-T, 0..3 m C-. -4 CD C)1, 0 D-1 0 B DOCD CD 0.CDC 00*D 0.-o ci)C 0*0 0 om 0.0 DC 2.3 CD D C')C C 0 0*00.CDC 0 D Ci)C)0 CD CD 0 Cl, C C.0 SQ.-n 0 C, 0 C')C')C')m C,, 0--n 0 3 m C,)0 C,.)C,)C C.0 C')D 0 CD 0.CD CD 0 m 0-U 3 CD C')0 D Ci)C')CD CD CD U,>C 0 0.CD D-o 0 Ci)C')C)0.0 CD D C,)3 CD D C')0 D D 0 CD 0.CD CD 0 CD CD D CD 0 (0 C 0.CD D CD C,)m 0-o C Cn C')CD C'C C)CD C')-I 0 CD 3D CD 0.CD CD 8.5 j D CD'C-C 0 C,)C 3 C D 0.CD D 0 C')0 CDO D o.CD 3 CD.5.CD 0 CD C')C.C')D 0.0 C')0 0 C*0 Ci)C')00>0-C C*C CD=-'0:i.CDc,)O 00 a 00 0 CDCD 0.0.00.0-CC')*2: 5 CD>C*0 CD'C*0 0 D C')D 0.C')0)CD 3 3 C')D 0.C)C')C 0 D C,)>CD-0 CO 5.DC')3C)O 0.Ci)3 00 DD 0-.D O CD DO*0.0 D=0>C-.p o'*C)3_CD 00 0-CDO*<0 CD CD5 CDO gg CD-0.-CD SQ.D 0.D C')-0 D C')CD ci 0 CD 0 m'C C')3 CII 0-a 0-1 0 0 C)m Cl)0-m x 3 I.0 0 CD-n 0-'3 m Cl)0 C.)C.).C.)C.).D r C.)..-J 0)0-J 0): ,...'-------------F)co 0)0)0 C.)--.J-4---0)0)0)0)0 C..fl.C.)I)-.0 CD 0)-4 0)ci z ci z 0)z CD CD 0)0 0 z 0)F'.)ci 0 ci z z ci-I CD ES-401 PWR Examination Outline Form ES-401-4 036 Fuel Handling Accident-AK2.01 Fuel Handling Equipment. 'J4i 1/2 1/2 2/1 Randomly Selected K/A Reason for Rejection Could not write a credible question since only RO action is to suspend fuel movement and exit.Randomly selected new system 068 Control Room Evacuation -AK2.07 ED/G.060 Accidental Gaseous The RO would not perform this function.Radwaste Release-AK1.04 Calculation of Randomly selected new system 028 Pressurizer Level Malfunction -AKI.01 Pressurizer reference Offsite Doses due to leak abnormalities. release from the power plant.004 Chemical and Volume Could not write a credible question to match the K/A Control-2.1.34 and tie to that system.Knowledge of primary and secondary chemistry Randomly selected-2.2.38 Knowledge of conditions and limitations in the facility license.limits.008 Component Cooling No credible tie for this K/A exists for the System.Water-A2.08 Effects of Randomly selected A2.01-Loss of CCW Pump.shutting (automatically or otherwise) the isolation valves of the letdown cooler.061 Emergency/Auxiliary Not possible to prepare a psychometrically sound Feedwater-Al.04 AFW question related to the subject K/A.source tank level Randomly selected-Al.01 S/G level.078 Instrument Air System Not possible to prepare a psychometrically sound (lAS)-Ki.03 question related to the subject K/A.Containment Air.Randomly selected-KI.02 Service Air.001 Control Rod Drive-No credible tie for this K/A exists for the System.K2.05 M/G Sets Randomly selected-1(2.02 One-line diagram of power supply to trip breakers.A 2/1 2/1 2/2 3ES-401 Form ES-401-4 m Cl)C--F'0-I 3 m Cl)C c.)F'., F'., F')F')F')01 0 F')F')F')I F', C--m x 3'-I.0 0 (D-I, 0 3 m Cl)C ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One-Unit I Date of Exam: 31512010--RO K/A CatpoyPoints SRO-Only_Poipts Tier Group KKKKKKAAAAG A2 G*Total 1 2 3 4 5 6 1 2 3 4*Total 1.1 3 3 6 Emergency&------Abnormal Plant 2 3 1 4 Evolutions

Tier Totals N/A N/A 6 4 10 1 3 2 5 2.Plant Systems 2 0 1 2 3 Tier Totals 4 4 8 3.Generic Knowledge and Abilities I 2 3 4 1 2 3 4 7 Categories 2 2 1 2 Note: 1.Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals"in each K/A category shall not be less than two).2.The point total for each group and tier in the proposed outline must match that specified in the table.The final point total for each group and tier may deviate by+/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.3.Systems/evolutions within each group are identified on the associated outline;systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added.Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements. 4.Select topics from as many systems and evolutions as possible;sample every system or evolution in the group before selecting a second topic for any system or evolution. 5.Absent a plant-specific priority, only those K/As having an importance rating (lR)of 2.5 or higher shall be selected.Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 7*The generic (G)K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.Refer to Section D.1.b of ES-401 for the applicable K/As.8.On the following pages, enter the K/A numbers, a brief description of each topic, the topics'importance ratings (IRS)for the applicable license level, and the point totals (#)for each system and category.Enter the group and tier totals for each category in the table above;if fuel handling equipment is Sampled in other than Category A2 or G on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note#1 does not apply).Use duplicate pages for RO and SRO-only exams.9.For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#)on Form ES-401-3.Limit SRO selections to K/As that are linked to 10 CFR 55.43.ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 1 (SRO)K/A Topic(s)E!APE#/Name/Safety Function 000007 (BW/E02&E10; CE/E02)Reactor Trip-Stabilization -Recovery/1 000008 Pressurizer Vapor Space Accident/3 000009 Small Break LOCA/3 000011 Large Break LOCA/3 000015/17 RCP Malfunctions/4 000022 Loss of Rx Coolant Makeup/2 000025 Loss of RHR System/4 000026 Loss of Component Cooling Water/8 000027 Pressurizer Pressure Control System Malfunction /3 EA2.1-Facility conditions and selection of appropriate procedures during abnormal and emergency operations Not selected Not selected Not selected Not selected AA2.04-How long PZR level can be maintained within limits 2.4.31 Knowledge of annunciator alarms, indications, or response procedures. AA2.O1-Location of a leak in the CCWS Not selected Not selected 2.4.18-Knowledge of the specific bases for EOP5.2.4.6-Knowledge of symptom based EOP mitigation strategies Not selected Not selected Not selected Not selected Not selected Not selected 2.4.18-Knowledge of the specific bases for EOP5 Rejected system to 038 Steam Gen Tube Rupture Not selected 00029 ATWS/I 000038 Steam Gen.Tube Rupture/3 000040 (BW/E05;CE/E05;W/E12)Steam Line Rupture-Excessive Heat Transfer/4 000054 (CE/E06)Loss of Main Feedwater/4 000055 Station Blackout/6 000056 Loss of Off-site Power/6 000057 Loss of Vital AC Inst.Bus/6 000058 Loss of DC Power/6 000062 Loss of Nuclear Svc Water/4 000065 Loss of Instrument Air/8 W/E04 LOCA Outside Containment /3 ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Em encv and Abnormal Plant Evolutions -Tier 1/Group 1 (SRO)---E/APE#/Name/Safety Function K K K A: A G K/A Topic(s)IR#OlD T 123 12V.y V p V e W/E1 1 Loss of Emergency Coolant V V Not selected NIA Recirc./4 V BW/E04;W/E05 Inadequate Heat V Not selected NIA Transfer-Loss of Secondary Heat Sink/4------000077 Generator Voltage and Electric Not selected N!A Grid Disturbances /6=-=V V--K/A Category Totals:==1 3 j Group Point Total: 6 ES-401 Form ES-401-2 '.1 0-I 3 m Cl)0 m 3 0 0'-I.z 0-I 3 m Cl)0 m Cl)0 m Cl)0 m Cl, 0-.-n 0 3 m Cl).0-***m Cl)0-m x 3 0 0 z 0 CD-I, 0-I 3 m Cl)0-0 00 C-.'0 g g-a D)3(0(0 CD V Cl)0 0*g 0.0.(0 g 0.0 CD CD CD CD CD'0 Cn5fl CD CD 0 0.Z V Q)Cl).0 0.CD.CD*0*.p.(-'I ('I CD (0 ci ES-401 PWR Examination Outline Form ES-401-2 PWR Examination Outiine Form ES-401-2 Pntystsms-Trpf(RO) --K K K K K K A A A A G K/A Topic(s)IR#QID T 1234561234 y p e 003 Reactor Coolant Pump X A2.02-Conditions which 3.9 86 809 N exist for an abnormal shutdown of a RCP in comparison to a normal shutdown of RCP 004 Chemical and Volume Not Selected N/A Control 005 Residual Heat Removal Not Selected N/A 006 Emergency Core Cooling--Not Selected N/A--007 Pressurizer Relief/Quench Not Selected N!A Tank 008 Component Cooling Water Not Selected N/A 010 Pressurizer Pressure Control X A2.02-Spray failures 3.9 87 762 R 012 Reactor Protection Not Selected N/A 013 Engineered Safety Features X A2.06-Inadvertent ESFAS 4.0 88 812 N Actuation actuation 022 Containment Cooling Not Selected NIA 025 Ice Condenser Not Selected N/A 026 Containment Spray--Not Selected N/A--039 Main and Reheat Steam Not Selected N/A 059 Main Feedwater Not Selected N/A 061 Auxiliary/Emergency X 2.2.22-Knowledge of 4.7 89 811 N Feedwater limiting conditions for--operations and safety limits----062 AC Electrical Distribution Not Selected N/A 063 DC Electrical Distribution X 2.2.42-Ability to recognize 4.6 90 810 N system parameters that are entry-level conditions for---------Technical Specifications

064 Emergency Diesel Generator--Not Selected N!A--073 Process Radiation Not Selected N/A Monitoring 076 Service Water Not Selected N!A 078 Instrument Air Not Selected N/A 103 Containment Not Selected N/A K/A Category PointTotals:

3 2 Group PointTotal: 5---ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2--ystems-Tier 2/Group 2 (SRO)--System#/Name K K K K K K A A A A G K/ATopic(s) IR#QID TYPO 1234561234 001 Control Rod Drive Not selected NIA 002 Reactor Coolant Not selected NIA 011 Pressurizer Level Control Not selected N/A 014 Rod Position Indication Not selected N/A 015 Nuclear Instrumentation Not selected NIA 016 Non-nuclear Instrumentation X 2.2.40-Ability to apply 4.7 91 599 D technical specifications for a system 017 In-core Temperature Monitor Not selected N/A---027 Containment Iodine Removal Not selected NIA 028 Hydrogen Recombiner 2.4.23-Knowledge of the NIA and Purge Control bases for prioritizing emergency procedure implementation during emergency operations. Rejected system replaced with 016 Non-Nuclear Instrumentation 029 Containment Purge Not selected N!A 033 Spent Fuel Pool Cooling Not selected N/A 034 Fuel Handling Equipment X 2.1.40-Knowledge of 3.9 92 600 0 refueling administrative requirements. 035 Steam Generator X A2.01-Faulted or ruptured 4.6 93 813 N S/Gs.041 Steam Dumplrurbine Not selected NIA Bypass Control----------045 Main Turbine Generator Not selected NIA 055 Condenser Air Removal Not selected N!A 056 Condensate Not selected N/A 068 Liquid Radwaste Not selected N/A---071 Waste Gas Disposal Not selected N!A 072 Area Radiation Monitoring Not selected N/A 075 Circulating Water Not selected N/A 079 Station Air Not selected NIA 086 Fire Protection Not selected NIA K/A Category PointTotals: =[=i[[2[Group PointTotal: 1 ES-401 Form ES-401-2 d)C>I-z D z z 0 0 Ei CD 0'a*CD C)CD CD 4 0)0)0)0)0)0)4 CD CD F-CD 0)F--0.c'*a-.Q-.C')'a*C')C')0 Cl)LU E 0 LL 0 0 E x LU a 0'I.0 LU C C C'4 In C')E Co x Iii 0 a)Co C a)..>.-o o 0.U)C 5-Q).92 a)-Co C)G)9"-°E.-0.C...0 a)a)0 D CU ci*N V.-V E 10 C a)0 Q).Ca)0 Q._.*C o 0 cU CU-S C aE5 E-.a 0=C (U 0.-->.C a)Co C)0*'-C)..C a)Ci)(U.S 0).C)0 0CC.5 Ca)00 0_V 0jCU CU*D C O-C (U CCU-CU C.2 th.50 DC)C-0).-0.5-0 0).2 a)C.C C--j 0)0 0.-0 0 000 O>E a)0 (1)a)E a)2 0)Cl)0)0 0'-0)0 0 C-V V V V C V V 0)0 a)0)0 a)a)0 a)0)---c..0CU 0)0):;.OVC C C 0 C CD CDD CC<2.co C)SV Eci, co 44 a.-<C-C-1---C')C')---r-e Cl)r'c-Cl)c-a 0 c-a Ci)0 I CU 0)C)C?0'f.0 LU E I...0 U 0 0 LU 0 (0 0 C (0 C.)CU L1 Cl)-g->,_;;;I-5 C)-'a)_0...a.C'.SQ 5C 0C Q)OC C')CU*0 o coo E2.!0)C.)-Qo c.LIJO.jW0..Q..jZ ES-401 PWR Examination Outline Form ES-401-4 Tier I Randomly Selected K/A Reason for Rejection Group 1/1 065 Loss of Instrument Air Could not write a credible SRO level question.-2.4.18 Knowledge of the specific bases for Randomly selected new system 038 Steam Generator Tube Rupture 2.4.18 EOPs 1/2 001 Continuous Rod Could not write a credible SRO level question.Withdrawal -AA2.05 Uncontrolled Rod Randomly selected new system 005 Inoperable stuck control rod-AA2.03 Required actions if more than withdrawal from available one rod is stuck or inoperable. indications 2/2 028 Hydrogen Could not write a credible SRO level question.Recombiner and Purge Control-2.4.23 Randomly selected new system 016 Non-Nuclear Instrumentation -2.2.40 Ability to apply Technical Knowledge of the bases for prioritizing emergency Specifications for a system.procedure implementation during emergency operations. ES-401 Form ES-401-4}}

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