ML101270338

AN1-2010-03 Final Written Examination

ML101270338
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/16/2010
From:	NRC Region 4
To:
References
AN1-2010-03
Download: ML101270338 (20)

Text

{{#Wiki_filter:PWR Examination Outline Form ES-401-2 ES-401 Facility: Arkansas Nuclear One Unit I Date of Exam: 31512010 1 SRO-Only Points Tier Group G* KKKKKKAAAAG A2 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. Tier Totals 5 5 4 4 5 4 27 10 Evolutkrns 1 33233222233 28 5 2. 2 011  ! 10 3 Plant Systems 3 4 4 38 8 Tier Totals 3 43 4 4 3 3 3

3. Generic Knowledge and Abilities Categories 1 ]I 2 I

3 4 10 1 2 3 4 7 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 G* on the SRO for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or 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 -x 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 I - 000026 Loss of Component I - Not selected Cooling Water / 8 AK2.03 Controllers and positioners. 000027 Pressunzer Pressure Control System Malfunction /3 000029 ATWS / 1 I x 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 x 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 I-AKI .01 Battery charger equipment and 000058 Loss of DC Power I6 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 ES-401 Form ES-401-2

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 2.1.25 Ability to interpret reference material, Electric_Gild_Disturbances /6 such as .ra.hs, curves, tables, etc. K/A Category Totals: Group Point Total: ES-401 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 5-401 PWR Examination Outline Form ES-401 -2 Emer enc and Abnormal Plant Evolutions Tier 1!Grou 2 RO E/APE # I Name / Safety Function K K K A A G K/A Topic(s) IR # QID Typ 12312 e 000001 Continuous Rod Withdrawal /1 Not selected NIA 000003 Dropped Control Rod /1 Not selected N!A 000005 Inoperable/Stuck Control Rod /1 Not selected N!A 000024 Emergency Boration /1 Not selected NIA 000028 Pressurizer Level Malfunction /2 x AK1 .01 PZR reference leak 2.8* 19 776 N abnormalities. 000032 Loss of Source Range NI /7 X AA2.04 Satisfactory source-range / 3.1 20 777 N intermediate-ran e overla 000033 Loss of Intermediate Range NI / 7 Not selected N!A 000036 (BW/A08) Fuel Handling Accident AK2.1 Changed to randomly selected NIA

/8                                                            S stem 068 AK2.07 AAI.10 CVCS makeup tank level 000037 Steam Generator Tube Leak /3                                                                          2.9   21    778      N indicator 000051 Loss of Condenser Vacuum / 4                           Not selected                                  N!A 000059 Accidental Liquid RadWaste Rel.!                       Not selected                                  N/A 9

000060 Accidental Gaseous Radwaste AKI .04 Changed to randomly N!A Rel./9 selected S tern 028 AKI .01 000061 ARM System Alarms / 7 x AK3.02 Guidance contained in alarm 3.4 22 634 D res onse for ARM s stem. 000067 Plant Fire On-site / 8 x AKI.02 Fire Fi htin 3.1 23 695 DR 000068 BW/A06 Control Room Evac. /8 x AK2.07 - ED/G 3.3 24 779 0 000069 (W!E14) Loss of CTMT Integrity / Not selected N/A 5 000074 (W/E06&E07) Inad. Core Cooling Not selected NIA 4 000076 High Reactor Coolant Activity! 9 Not selected NIA WIEO1 & E02 Rediagnosis & SI Not selected NIA Termination / 3 W/E13 Steam Generator Over-pressure / Not selected N!A 4 W/E15 Containment Flooding / 5 Not selected N/A W/E16 High Containment Radiation / 9 Not selected NIA BW/A01 Plant Runback!1 Not selected NIA BW!A02&A03 Loss of NNI-XIY! 7 Not selected NIA BW/A04 Turbine Trip / 4 Not selected NIA BW/A05 Emergency Diesel Actuation /6 x AK2.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual 4.0 25 349 D features. AA2.2 Adherence to appropriate BW/A07 Flooding / 8 procedures and operation within the 3.3 26 780 N limitations in the facilitys license and amendments BW/E03 Inadequate Subcooling Margin / Not selected NIA 4 ES-401 4 Form ES-401 -2

ES-401 PWR Examination Outline Form ES-401-2 BW/E08; W/E03 LOCA Cooldown - Not selected e.ress. /4 1E09; CE/A13; WIEO9&ElO Natural V Not selected Circ./4 IV 2.2.22- Knowledge of limiting conditions BW/E13&E14 EOP Rules and Enclosures x for operations and safety limits. CE/All; W/E08 RCS Overcooling PTS /

                               -                  Not selected 4

CE/Al 6 Excess RCS Leakage / 2 Not selected V CE/E09 Functional Recovery Not selected K/A Cate.o Point Totals: 121 Group Point Total: ES-401 Form ES-401 -2

Form ES-401-2 ES-401 PWR Examination Outline PWR Examination Outline Form ES-401-2 Plant Systems Tier 2/Group I (RO) K/A Topic(s) 1(5.05 The dependency of 003 Reactor Coolant Pump RCS flow rates upon the number of operating RCPs A4.08 RCP cooling water supplies 2.1.34 changed to 2.2.38 004 Chemical and Volume Knowledge of conditions and Control limitations in the facility license 1(4.03 Protection of ion exchangers (high letdown temperatures will isolate ion exchangers) 005 Residual Heat Removal 1(2.01 RHR Pumps 006 Emergency Core Cooling 1(6.10 Valves 007 Pressurizer Relief/Quench 1(5.02 Method of forming a Tank steam bubble in the PZR 008 Component Cooling Water A2.08 changed to A2.01 - Loss of CCW Pum. 10 Pressurizer Pressure K3.02 RPS ontrol 012 Reactor Protection K6.10 Permissive circuits 2.1.32 Ability to explain and apply system limits and precautions 013 Engineered Safety Features K4.10 Safeguards Actuation equipment control reset 022 Containment Cooling A3.01 Initiation of safeguards mode of operation 025 Ice Condenser Not Selected 026 Containment Spray 1(1.01 - ECCS 039 Main and Reheat Steam I: A2.04 dump Malfunctioning steam 059 Main Feedwater A3.03 Feed water pump suction flow pressure 1(4.16 Automatic trips for MFW pumps 061 Auxiliary/Emergency Al .04 changed to Al .01 Feedwater S/G level ES-401 Form ES-401 -2

PWR Examination Outline Form ES-401 2 ES-401 PWR Examination Outline Form ES-401 -2 Plant S stems Tier 2/Grou I RO KIA Topic(s) IR # ID Ty K K K K K K A A A A G e 1 234561234 X 2.4.35 Knowledge 3.8 46 790 N 062 AC Electrical Distribution of local auxiliary operator tasks during an emergency and the resultant operational effects. 3.3 47 316 D K2.01 Major s stem loads 1(3.02 3.5 48 86 D 063 DC Electrical Distribution Components using DC control ower 1(2.01 Air 2.7 49 791 N 064 Emergency Diesel Generator X compressor N 3.4 50 792 X 1(1.05 Starting air 5 stern 1(5.01 Radiation 2.5 51 672 R 073 Process Radiation Monitoring X theory, including sources, types, units, and effects X A4.02 SWS valves 2.6 52 793 D 076 Service Water Al .02 Reactor and 2.6 53 794 N X turbine building closed cooling water tern eratures Kl.03 changed to 2.7 54 535 D 078 lnstrumentAir X KI .02 Service air X A4.06 Operation of 2.7 55 795 D 103 Containment the containment ersonnel airlock 3 2 2 2 2 3 3 Grou Point Total: 28 K/A Catego Point Totals: 3 3 2 3 Form ES-401-2 ES-401

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ES-401 PWR Examination Outline Form ES-401-4 Randomly Selected K/A J4i Reason for Rejection 1/2 036 Fuel Handling Could not write a credible question since only RO Accident AK2.01 Fuel action is to suspend fuel movement and exit. Handling Equipment. Randomly selected new system 068 Control Room Evacuation AK2.07 ED/G. 1/2 060 Accidental Gaseous The RO would not perform this function. Radwaste Release AK1 .04 Calculation of Randomly selected new system 028 Pressurizer Offsite Doses due to Level Malfunction AKI .01 Pressurizer reference release from the power leak abnormalities. plant. 2/1 004 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 limits. and limitations in the facility license. 008 Component Cooling No credible tie for this K/A exists for the System. Water A2.08 Effects of shutting (automatically or Randomly selected A2.01 Loss of CCW Pump. otherwise) the isolation valves of the letdown A cooler. 2/1 061 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. 2/1 078 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. 2/2 001 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. 3ES-401 Form ES-401-4

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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 2 0 1 2 3 Systems 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) E!APE # / Name / Safety Function K/A Topic(s) 000007 (BW/E02&E10; CE/E02) Reactor EA2.1- Facility conditions and selection of Trip Stabilization Recovery /1 appropriate procedures during abnormal and emergency operations 000008 Pressurizer Vapor Space Not selected Accident / 3 000009 Small Break LOCA /3 Not selected 000011 Large Break LOCA / 3 Not selected 000015/17 RCP Malfunctions/4 Not selected 000022 Loss of Rx Coolant Makeup /2 AA2.04- How long PZR level can be maintained within limits 2.4.31 Knowledge of annunciator alarms, 000025 Loss of RHR System / 4 indications, or response procedures. 000026 Loss of Component Cooling AA2.O1- Location of a leak in the CCWS Water / 8 000027 Pressurizer Pressure Control Not selected System Malfunction / 3 00029 ATWS / I Not selected 000038 Steam Gen. Tube Rupture /3 2.4.18 Knowledge of the specific bases for EOP5. 000040 (BW/E05; CE/E05; W/E12) 2.4.6- Knowledge of symptom based EOP Steam Line Rupture Excessive Heat

                    -                                             mitigation strategies Transfer / 4 000054 (CE/E06) Loss of Main                                       Not selected Feedwater / 4 000055 Station Blackout /6                                         Not selected 000056 Loss of Off-site Power / 6                                  Not selected 000057 Loss of Vital AC Inst. Bus / 6                              Not selected 000058 Loss of DC Power /6                                         Not selected 000062 Loss of Nuclear Svc Water / 4                               Not selected 000065 Loss of Instrument Air / 8                                  2.4.18 Knowledge of the specific bases for EOP5 Rejected system to 038 Steam Gen Tube Rupture W/E04 LOCA Outside Containment /3                                  Not selected ES-401                                                                                           Form ES-401-2

Form ES-401-2 ES-401 PWR Examination Outline PWR Examination Outline Form ES-401-2 ES-401 Em encv and Abnormal Plant Evolutions Tier 1/Group 1 (SRO) K K K A: A G K/A Topic(s) IR # OlD T E/APE#/Name/Safety Function y 123 12V. V p V e NIA V W/E1 1 Loss of Emergency Coolant V Not selected V Recirc. /4 Not selected NIA BW/E04; W/E05 Inadequate Heat V Transfer Loss of Secondary Heat Sink / 4 Not selected N!A 000077 Generator Voltage and Electric = V Grid Disturbances / 6 = V K/A Category Totals: =

                                            =  1               3j Group Point Total:                             6 ES-401                                                                                   Form ES-401-2

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PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outiine Form ES-401-2 Pntystsms-Trpf(RO) K/A Topic(s) IR # QID T K K K K K K A A A A G 1234561234 y p e X A2.02 Conditions which 3.9 86 809 N 003 Reactor Coolant Pump exist for an abnormal shutdown of a RCP in comparison to a normal shutdown of RCP Not Selected N/A 004 Chemical and Volume Control Not Selected N/A 005 Residual Heat Removal Not Selected N/A 006 Emergency Core Cooling Not Selected N!A 007 Pressurizer Relief/Quench Tank Not Selected N/A 008 Component Cooling Water X A2.02 Spray failures 3.9 87 762 R 010 Pressurizer Pressure Control Not Selected N/A 012 Reactor Protection X A2.06 Inadvertent ESFAS 4.0 88 812 N 013 Engineered Safety Features Actuation actuation Not Selected NIA 022 Containment Cooling Not Selected N/A 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 X 2.2.22 Knowledge of 4.7 89 811 N 061 Auxiliary/Emergency Feedwater limiting conditions for operations and safety limits Not Selected N/A 062 AC Electrical Distribution X 2.2.42 Ability to recognize 4.6 90 810 N 063 DC Electrical Distribution system parameters that are entry-level conditions for Technical Specifications Not Selected N!A 064 Emergency Diesel Generator Not Selected N/A 073 Process Radiation Monitoring Not Selected N!A 076 Service Water Not Selected N/A 078 Instrument Air Not Selected N/A 103 Containment 3 2 Group PointTotal: 5 K/A Category PointTotals: ES-401 Form ES-401-2

Form ES-401-2 PWR Examination Outline ES-401 Form ES-401-2 ES-401 PWR Examination Outline ystems Tier 2/Group 2 (SRO) TYPO G K/ATopic(s) IR # QID System#/Name K K K K K K A A A A 1234561234 Not selected NIA 001 Control Rod Drive Not selected NIA 002 Reactor Coolant Not selected N/A 011 Pressurizer Level Control Not selected N/A 014 Rod Position Indication Not selected NIA 015 Nuclear Instrumentation X 2.2.40 Ability to apply 4.7 91 599 D 016 Non-nuclear Instrumentation technical specifications for a system Not selected N/A 017 In-core Temperature Monitor Not selected NIA 027 Containment Iodine Removal 2.4.23 Knowledge of the NIA 028 Hydrogen Recombiner bases for prioritizing and Purge Control emergency procedure implementation during emergency operations. Rejected system replaced with 016 Non-Nuclear Instrumentation Not selected N!A 029 Containment Purge Not selected N/A 033 Spent Fuel Pool Cooling X 2.1.40 Knowledge of 3.9 92 600 0 034 Fuel Handling Equipment refueling administrative requirements. A2.01 Faulted or ruptured 4.6 93 813 N 035 Steam Generator X S/Gs. Not selected NIA 041 Steam Dumplrurbine Bypass Control Not selected NIA 045 Main Turbine Generator Not selected N!A 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 NIA 079 Station Air Not selected NIA 086 Fire Protection K/A Category PointTotals: = [ = i [[2[ Group PointTotal: 1 Form ES-401-2 ES-401

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PWR Examination Outline Form ES-401-4 ES-401 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 Randomly selected new system 038 Steam the specific bases for Generator Tube Rupture 2.4.18 EOPs 1/2 001 Continuous Rod Could not write a credible SRO level question. Withdrawal AA2.05 Randomly selected new system 005 Inoperable stuck Uncontrolled Rod 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 Randomly selected new system 016 Non-Nuclear Control 2.4.23 Instrumentation 2.2.40 Ability to apply Technical Knowledge of the bases Specifications for a system. for prioritizing emergency procedure implementation during emergency operations. ES-401 Form ES-401-4}}