ML090710059

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Initial Written Retake Examination, 2009-301 Draft Administrative Documents
ML090710059
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 02/10/2009
From:
NRC/RGN-II
To:
References
ES-401, Rev 9
Download: ML090710059 (20)
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Text

ES-401 1 Rev. 9 PWR Examination Outline Form ES-401-2 RE--rl\\<£'

Facility: NDr1h. A-V\.t\t.1 Date of Exam:  ?-I \0 \ .'2..Ub'1 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

2 2 1 1 2 1 2 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 4 5 4 5 27 5 5 10 1 2 2 3 3 3 3 3 2 3 2 2 28 3 2 5

2. 1 1 1 1 1 1 1 1 1 0 10 2 2 1 1 3 Plant Systems Tier Totals 3 3 4 4 4 4 4 3 4 3 2 38 5 3 8
3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 1 2
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (l.e., except for one category in Tier a of the SRO-only outline, the "Tier Totals" in each KIA 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 NRO revisions. The flnalRO exam must total 75 points and the SRO-only exam must total 25 points.

a. 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 that are not Included on the outline should be added. Refer to ES-401, Attachment 2. for guidance regarding the elimination of inappropriate KIA statements.
4. Select topicsfrom 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 KJAs 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 KIA categories.
7. *The generic (G) KlAs in Tiers 1 and 2 shaH be selected from Section 2 of the KIA Oatalog. but the topics must be relevant to the applicable evolution or system.

S. On the following pages, enter the KIA numbers. a brief description of each topic, the topics' Importance ratings (I Rs) 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 Oategory A2 or G* on the SRO-only exam, enter it. on the left side of Column A2 for Tier 2. Group 2 (Note

  1. 1 does not apply). Use duplicate pages for RO and SRO-ooly exams.
9. For Tier 3; select topics from Section 2 of the KIA catalog, and enter the KIA numbers. descriptions, IRs.

and point totals (#) on Form ES401.a. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO SRO 008AG2.4.30 Pressurizer Vapor Space Accident 1 3 2.7 4.1 D D D D D D D D D 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizatlons or outside This is a Generic,. no stem statement is agencies.

associated.

009EK1.02 Small Brea.k LOCA 13 3.5 4.2 ~. 0 DODD DODD 0 Use of steam tables Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLU110N):(CFR: 41.8t041.10 145.3) 015AA 1.22 RCP Malfunctions 1 4 4 4.2 DOD 0 D D ~ DOD 0 RCP seal failure/malfunction Ability to operate and 1 or monitor the follOWing ~ they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I 45.5 ,

45.6) 022AK1.01 Loss of Rx Coolant Makeup I 2 2.8 3.2 ~ 0 DOD DOD 0 0 0 Consequences of thermal shock to RCP seals Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.1 0/45,3) 025AK1.01 Loss of RHR System 14 3.9 4.3 ~ D DOD D D DODD Loss of RHRS during all modes of operation Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8t041.101 45,3) 026AA2.04 Loss of Component Cooling Water /8 2.5 2.9 DOD 0 DOD ~ 0 0 0 The normal values snd upper limits for the temperatures of the components cooled by CCW Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 , 43.5 I 45.13)

Page 1 of3 6113/2008 6:44 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO SRO 027AK3.02 Pressurizer Pressure Control System 2.9 3 0 0 ~ 0 0 0 0 0 0 0 0 Verification of altemate transmitter and/or plant computer Malfunction 13 priOr to shifting flow chart transmitters Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10 I 45.6/45.13) 029EK2.06 ATWSJ 1 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 Breakers. relays. and disconnects.

Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and Ihefoliowing:(CFR: 41.7 145.7/45.8)

O4OAA2.04 Steam Line Rupture - Excessive Heat 4.5 4.7 0 0 0 0 0 0 0 ~ 0 0 0 Conditions requiring ESFAS initiation Transfer 14 Ability to determine and interpret the following <is they <ipply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 I 43.51 45.13) 054AK3.04 Loss of Main Feedwater I 4 4.4 4.6 0 0 ~ 0 0 0 0 0 0 0 0 Actions contained in EOPs for loss of MFW KnoWledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5141.10 {

45.6 /45.13) 055EK2.04 Station Blackout f (5 O~ODOOOODDD Pumps Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7 145,7/45.8) 056AG2.4.8 Loss of Off-site Power 16 3.8 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of how abnormal operating procedul"e$ are used in conjunction with EOPS. .

This is a Generic, no stem statement is associated.

057AG2.2.38 Loss of Vital AC Inst. sus I 6 3.6 4.5 0 0 0 00 0 0 0 0 0 ~ Knowledge of CQnditions <ind Iimitatlol1ll in the facility license.

This is a Generic, no stem statement is associated.

Page 2 of3 8113/2008 6:44 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 062AA1.07 Loss of Nuclear Svc Water f 4 2.9 3 0 0 0 0 0 0 ~ 0 0 0 0 Flow rates to the components and systems that are serviced by the SWS: interactions among the components Abil.ity to operate and lor monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6) 065M201 Loss of Instrument Air / 8 2.9 3.2 0 0 0 0 0 0 0 ~ 0 DO Cause and effect of low-pressure instrument air Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 143.51 45.13) 077AA1.03 Generator Voltage and Electric Grid 3.8 3..7 000 OO~OOOD Voltatge regulator controls Disturbances I 6 Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION}:(CFR: 41.7/45.5/

45.6)

WE04EK3.2 LOCA Outside Containment I 3 3.4 4.0 OO~DOOOOOOD Normal, abnormal and emergency operating procedures associated with (LOCA Outside Containment).

Knowledge of the reasons fOf the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10 I 45.6/

45.13)

WE05EK2.1 Inadequate Heat Transfer - Loss of 3.7 3.9 O~O Components and functions of COntrol and safety systems, Secondary Heat Sin k 1 4 0000000 including instrumentation, Signals, interlocks, failure Knowledge of the interrelations between modes and automatic and manual features.

(EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7 145.71 45.8)

Page 3 ofS 8/1312008 6:44 AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO 8RO 001AK1.04 Continuous Rod Withdrawal 11 3.7 3.9 ~ 0 0 ODD 0 0 DO 0 Effect of continuous rod withdrawal on insertion limits and 8DM Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41,10/45.3) 005AK2.03 Inoperable/Stuck Control Rod 11 3.1 3,3 0 ~ 0 DODD Metroscope Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTiON) and the foliowing:(CFR: 41,7/45,7/45.8) 024AAUO Emergency Boration I 1 3.5 3.4 0 0 0 0 0 0 ~ 0 0 0 0 cvcs centrifugal charging pumps Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION}:(CFR: 41,7/45.51 45,6) 028AG2,2.39 Pressurizer Level Malfunction 12 3,9 4.5 DO 00000 O~ Knowledge of less than one hour technical specification action statements for systems.

This is a Generic, no stem statement is associated, 032AK3,02 Loss of Source Range Nl f 7 3.7 4,1 0 D ~ D D D DOD 0 0 Guidance contained in EOP for loss of source-range nuclear instrumentation Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41,5/41.10 1 45.6/45.13) 051 AG2A.35 Loss of Condenser Vacuum 14 3,8 4,0 0 D DOD 0 ODD 0 ~ Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects This is a GeneriC, no stem statement is associated, Page 1 of2 8/13/2008 6:44 AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 067AK1.01 Plant Fire On-site 19 8 2.9 3.9 ~ 0 0 0 D 0 0 D 0 0 0 Fire classifications by type Knowledge ofthe operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10 145.3)

WE08EA2.2 Res Overcooling - PTS 1 4 3.5 4.1 OOOOOOO~OOO to appropriate procedures and operation within the limitations in the facility's license and Ability to determine and interpret the amendments.

following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 43.5 145.13)

WE14EA1.3 Loss of CTMT Integrity 15 3.3 3.8 DOOO O~DOOO Desired operating results during abnormal and emergency situations.

Ability to operate and I or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION}:(CFR: 41.7/45.6)

Page 20f2 8/13/2008 6:44 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO oo3A2.02 Reactor Coda'lt Pump 3.7 3.9 0 0 DOD 0 0 ~ 0 D 0 Conditions which exist for an abnormal shutdown r;t an Rep iii canparison to a normal shutdown of an RCP Ability to (a) predict the impacts of the follcwing on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.51 4S.3/45.13) oo3A3.02 Reactor Coolant Pump 2.6 2.S 0 0 0 0 0 0 0 0 ~D 0 Maor current Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7 I 45.S}

oo4K6.12 Chemical and Volume Control 2.6 2.9 0 0 0 0 0 ~ 0 0 0 0 0 Principle of recirculation valve: (permit emergency flow even if vallIS is blocked by crystallized boric acid)

Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) oo5A4.04 Residual Heat Removal 3.1 2.9 0 0 0 0 0 0 0 0 0 .~ 0 Controls and indication for closed cooling water pumps Ability to manually operate and/or monitor in the control room:(CFR: 41.7 (45.5 to 45.8)

OOSKS.09 Residual Heat Removal 3.2 3.4 0 0 0 0 ~. 0 0 DOD 0 Dilutim and boration considerations Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM}:(CFR: 41.S/45.7) 00611.1.05 Emergency Core Cooling 2.9 3.3 0 0 0 0 0 0 ~ 0 0 0 0 CCW flow (establish flow to RHR heat exchanger prior to placing in service Ability to predict and/or monitor changes in parameters associated with Operating the (SYSTEM) controls including:(CFR: 41.5 J 45.5)

Page10fS 8/1312008 6:45AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2. A3 A4 G TOPIC:

RO SRO oo7A3.01 Pressurizer Relief/Quenc:h Tank 2.7 2.9 0 0 DOD 0 0 0 ~ 0 0 Components which discharge to the PRT Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7 I 45.5}

oo8G2.1.27 Component Cooling Water 3.9 4 D DDDDDDDD~ Knowla::lge of system purpose and or function.

This is a Generic, no stem statement is associGted.

OK5.01 Pressurizer Pressure Control 3.5 40 0 0 0 0 ~ 0 0 0 0 0 0 Determination of condition in PZR, using steam tables Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 012K5.02 Reactor Protection 3.1 3.3 DOD 0 ~ 0 0 0 0 0 0 Power dfls tty Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 013K6.01 Engineered Safety Features Actuation 2.7 3.1 DDDDD~DDDDD Sensors and detectors Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 022K4.03 Containment Cooling 3.6 4.0 DDD~DDDDDDD Automatic containment isolation Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 026K2.01 Containment Spray 3.4 3.6 D~DDDDDDDDD Containment spray pumps Knowledge of electrical power Supplies to the foilowing:(CFR: 41.7)

Page 2 of5 8/13/2008 6:45 AM

ES401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO SRO 026K3.02 Containment Spray 4.2 4.3 0 0 ~ 0 DOD DOD 0 Recirculation spray system KnOVllJedge of the effect that a loss or malfunction of the (SYSTEM) will have on thefoliowing:(CFR: 41.7/45.6) 039A2.04 Main and Rehea Steam 3.4 3.7 DOD D D DO Malfunctioning steam dump Abilityto (a) predict the impacts of the foliONing on the (SYSTEM) and (b) based on those pra:lictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5 (

45.3/45.13) 059A1.07 Main Feedwater 2.5 2.6 0 0 0 0 0 0 ~ D D 0 0 Feed Pump speed, including normal control speed for ICS Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 059K3.03 Main Feedwater 3.5 3.7. 0 0 ~ 0 0 DOD 0 0 0 SlGS Knowla:lge of the effect that a loss or malfunction of the (SYSTEM) will have on thefoliowing:(CFR: 41.7/45.6) 061K1.07 Auxiliary/Emergency Fea:iwater 3.6 3.8 ~ 0 0 0 0 0 0 0 0 0 0 Emergency water source KnOVllledge of the physical connections and/or caus&effect relationships between (SYSTEM) and thefoilowing:(CFR: 41.2 to 41.9 f 45.71045.8) 06iK6.02 Auxiliary/Emergency Fea:iwater 26 2.7 DOD 0 0 ~ 0 D 0 0 0 Pumps Knowledge of the effect that a loss Of malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7)

Page 3 of5 8/1312008 6:45 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 062K1.04 AC Electrical Distribution 3.7 4.2 ~DDDDDDDDDD Off*site power sources KnOlillle.dge of the physical connections ancVer cause-effect relatiqnships between (SYSTEM) and the following: (CFR: 41.2 to 41.9/45.7 to4S.8) 063A3.01 DC Electrical Distribution 2.7 3.1 DDDDDDD[J~DD MEters, annunciators, di<llS, recorders CInd indicating lights Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.S}

0631<4.02 .DC Electrical Distribution 2.9 3.2 DDD~DDDDODD Breaker interlocks. permissives, bypasses CInd cross-ties

  • KnOlillJedge of (SYSTEM) design feature(s}

and or interlock(s) which provide for the foliowing:(CFR: 41.7) 064A4.04 Emergency Diesel Generator 3.2 3.2 DDDDDDDDD~D .Rernote operation of the air comprassor switch (different modes)

Ability to manually operate and/or monitor in the control room:(CFR: 41.7 t 45.5 to 45.B}

073K3.01 Process Radiation Monitoring 3.6 4.2 DD~DDDDDODD .Radill3clive effulent releases KnOlillledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7 14S.6) 076K4.01 Service Water 2.5 2.9 DDD~DDDDDDD Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return valves KnOYlledgeof (SYSTEM) design feaWre(s}

and or interlock(s) which provide for the folIONing:(CFR: 41.7) 078K2.02 Instrument Air 3.3 3.5 D~DDDDDDODD Emergency air compressor KnOYlledge of electrical power supplies to the folIONing:(CFR: 41.7)

Page 4 ofS 8/1312008 6:45 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES*401*2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 103A 1.01 Containment 3.7 4.1 D D D D D D ~ 0 D D 0 Containment pressure, temperature and humidity Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 10302.4.2 Containment 4.5 4.6 DODD 0 DOD 0 D ~ Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

This is a Generic, no stem statement is associ<ied.

Page 5 of5 8/13/2008 6:45 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 KG Ai A2 A3 A4 G TOPIC:

RO SRO 002K1.11 Reactor Coolant 4.1 4.2 ~ 0 0 0 0 ODD DOD SIGS, feedwater systems Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9 J 45.7 to 45.8) 015A2.04 Nuclear Instrumentation 3.3 3.8 DOD DOD 0 ~ D 0 0 Effects on axial flux density of control rod alignment and sequencing, xenon production and d~ay, and boron vs.

Ability to (a) predict the impacts of the control rod reactivity changes following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 t 43.5 145.3 I 45.13) 0i6K3.03 Non-nuclear Instrumentation 3.0 3.1 DO ~ 0 DOD D 0 0 0 SDS Knowledge of the effect that a loss or malfunction oUhe (SYSTEM) will have on the foliowing:(CFR: 41.7 J 45.6) 027A4.01 Containment Iodine Removal 3.3 3.3 DOD ODD 0 D 0 ~ 0 CIRS controls Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 029A1.03 Containment Purge 3.0 3.3 0 0 ODD 0 ~ DODD Containment pressure. temperature and humidity Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 034K6.02 Fuel Handling Equipment 2.6 3.3 DODO 0 ~ 0 DODD Radiation monitoring systems Knowledge of the effect that a loss or malfunction ofthe following will have on the (SYSTEM):(CFR: 41.7/45.7)

Page 1 of2 8113/2008 6:45 AM

ES-401. REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5K6 A1 A2 A3 A4 G TOPIC:

RO SRO 035A3.02 Steam Generator 3.7 3.5 0 0 0 0 0 0 0 0 ~ 0 0 MAD valves Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 041K2.01 Steam DumplTurbine Bypass Control 2.B 2.9 0 ~ 0 0 0 0 0 0 DO 0 lCS. normal and alternate power supply Knowledge of electrical power supplies to the foUowing:(CFR: 41.7) 072K5.01 Area Radiation Monitoring 2.7 3.0 0 0 0 0 ~ 0 0 0 0 0 0 Radiation theory. inclUding sources, types, units and effects Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5 J 45.7) 075K4.01 Circulating Water 2.5 2.8 0 0 0 ~ 0 0 0 0 0 0 0 Heat sink Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the follawing:(CFR: 41.7)

Page 2 of2 8113/2008 6;45AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KG A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.28 Conduct of operations 4.1 4.1 D D D DOD D DOD ~ Knowledge of the purpose and fUnction of major system components and controls.

G2.1.4 Conduct of operations 3.3 3.8 DOD 0 0 0 0 0 0 0 ~ Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license statur, 10CFR55 etc.

G2.2.15 Equipment Control 3.9 4.3 DOD 0 0 DOD tJ 0 ~ Ability to determine the expected plant configuration using design and configuration control documentaion G2.2.43 Equipment Control 3.0 3.3 DODD 0 0 0 0 0 0 ~ Knowledge of the process used to track inoperable alarms G2.3.15 Radiation Control 2.9 3.1 D D D DOD DOD 0 ~ Knowledge of radiation monitoring systems G2.3.4 Radiation Control 3.2 3.7 DOD 0 DOD DOD ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.3.5 Radiation Control 2.9 2.9 0 0 0 0 DOD DOD ~ Ability to use radiation monitoring systems Page 1 of2 811312008 6:46AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2A.20 Emergency Procedures/Plans 3.8 4.3 0 0 0 0 0 DDDD~ Knowledge of operational implications of EOP warnings, cautions and notes.

G2A.37 Emergency Procedures/Plans 3.0 4.1 0 0 0 0 0 DOD 0 0 ~ Knowledge of the lines of authority during implamentation of an emergency plan.

G2AA5 Emergency Procedures/Plans 4.1 4.3 DOD DOD DDD~ Ability to prioritize and interpret the significance of each annunciator or alarm.

Page 20f2 8/13/2008 6:46 AM

E$-401 , REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME f SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 025AG2.4.11 Loss of RHR System 14 4.0 4.2 DOD D D DO 0 D [] ~ Knowledge of abnormal condition procedures.

This is a Generic, no stem statement is associated.

054AG2.1.27 Loss of Main Feedwater 14 3.9 4 DOODODODDD~ Knowledge of system purpose and or funct.ion.

This is a Generic, no stem statement is associated.

055EA2.03 Station Blackout 1 6 3.9 4.7 DDDDOOO~DDD Actions necessary to restore power Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 43.5/ 45.13) 058AA2.02 Loss of DC Power / 6 3.3 3.6 DODDDDO~DDD 125V de bus voltage, low/critical low, alarm Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION}:(CFR: 41.10 143.51 45.13) 077AA2.03 Generator Voltage and Electric Grid 3.5 3.6 DODODDD~DDD Generator current outside the generator capability curve Disturbances I 6 Ability to determine and interpret the following as they apply to AaNORMAL PLANT EVOLUTlON):(CFR: 41.10 143.51 45.13) we05EG2.4.6 Inadequate Heat Transfer - Loss of 3.7 4.7 DODDDDODDD~ Knowledge symptom based EOP mitigatJon strategies.

Secondary Heat Sink /4 This is a Generic. no stem statement is associated.

Page 1 of1 8113/2008 6:46 AM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 Ai A2 A3 A4 G TOPIC:

RO SRO OOSAG2.2.40 Inoperable/Stuck Control Rod 11 3.4 4.7 0 0 0 0 0 DD~ Ability to apply technical specifications for a system.

This is a Generic, no stem statement is associated.

024M2.04 Emergency Boration I 1 3.4 4.2 0 0 0 0 DD~DDD Availability of BWST Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTlON):(CFR: 41.10 143,5 f 4S.13) 032M2.06 Loss of Source Range NI/7 3.9 4.1 DOD DOD 0 ~ 0 0 0 Confirmation of reactor trip Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTtON}:(CFR: 41.10 143.51 45.13) 074EG2.i.23 Inad, Core Cooling 14 4.3 4.4 0 0 DOD 0 0 DOD ~ Ability to perform specific system and integrated plant procedures during all modes of plant operation, This is a Generic, no stem statement is associated.

Page 1 of 1 8/13/2008 6:47 AM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO SRO 003A2.05 Reactor Coolant Pump 2.5 2.8 0 0 0 0 0 0 0 ~ 0 0 0 Effects of VCT pressure on RCP sealleakoff flows Ability to (a.) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41,5/43.5/45.3 145.13) 005A2.02 Residual Heat Removal 3.5 3.7 0 DOD DOD ~ DOD Pressure transient protection during cold shutdown Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those al:)normal operation:(CFR: 41,5 r 43.5/45.3 J 45.13) 008G2.2.39 Component Cooling Water 3.. 9 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of less than one hour technical specification action statements for systems.

This is a Generic, no stem statement is associated.

039G2.1.25 Main and Reheat Steam 3.9 4.2 0 0 0 0 0 0 0 0 0 D~ Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

This is a Generic, no stem statement Is associated.

076A2.02 Service Water 2.7 3.1 DO 0 0 0 0 0 ~ DOD Service water header pressure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5 f 45.31 45.13}

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ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 016G2A6 Non-nuclear Instrumentation 3,7 4.7 D D DOD DO 0 0 0 ~ Knowledge symptom based EOP mitigation strategies, This is a Generic" no stem statement is associated, 045A2.17 Main Turbine Generator 2.7 2.9 D 0 0 0 ,DO 0 ~ D D 0 Malfunction of electrohydraulic control Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41,5/43.5 /45,3/45,13) 056A2.04 Condensate 2.6 2.8 0 DOD D 0 0 ~ 0 D 0 Loss of condensate pumps Ability to (8) predict the Impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43,5/45.3/45,13)

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ES-401. REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO SRO G2.i.28 Conduct of operations 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the purpose and function of major system components and (lontrols.

G2.1.32 Conduct of operations 3.8 4.0 DOD 0 0 0 0 0 DO ~ Ability to explain and apply all system limits and precautions.

G2.2.21 Equipment Control 2.9 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of pre- and post-maintenance operability requirements.

G2.2.5 Equipment Control 2.2 3.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process for making design or operating changes to the facility G2.3,4 Radiation Control 3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge o.t radiation exposure limits under normal and emergency conditions G2.4.28 Emergency ProcedureslPlans 3.2 4.1 0 0 0 .0 0 0 0 0 0 0 ~ Knowledge of procedures relating to emergency response to a security event (non-safeguards information).

G2.4.30 Emergency ProcedureslPlans 2.7 4.1 0 0 0 0 0 0 0 0 0 0

~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

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