ML101970327

Initial Exam 2008-301 Final Administrative Documents

ML101970327
Person / Time
Site:	Robinson
Issue date:	06/28/2010
From:	Progress Energy Carolinas
To:	NRC/RGN-II
References
50-261/08-301
Download: ML101970327 (20)

Text

ES-401 ES-401 PWR Examination PWR Examination Outline Outline - RO - RO Form Form ES-401-2 ES-401-2 II j. Facility: 4*8. Rob Facility: ~.S. gQiYSOA lV\soY'\ Date of Date Exam:

of Exam:

RO KJA Catecorv Points SRO-Only SPO-Only_P Points oints Tier Tier Group Group 1 KK KK KKIK K KK KKAAAA A A A A G G A2 A2 G*

G* Total Total 11 22 331 4 55 66 11 22 33 44 ** Total Total 1.

1. 11 2222 2 2 44 44 44 18 18 66 Emergency &&

Emergency Abnormal Abnormal 22 2 12 i. 1 N/A N/A I1 1 N/A N/A 2 9 4 Plant Plant Evolutions TierTotals Tier Totals 44 44 33 55 55 66 27 27 10 10 Evolutions 11 333322 3 3 2 2 32232 3 2 2 3 2 33 28 28 55 2.

2.

Plant Plant 22 I 3 1 1 1 0 1 0 1 0 2 0 111Q 10 10 33 Systems Systems Tier Totals Tier Totals 6 4 4 3 22 4 22 3 3 4 3 38 38 88 Generic Knowledge and Abilities

3. Generic 11 2 3 4 10 10 11 2 3 44 77 Categories Categories 2 2 3 3 Note:

Note: 1.

1. Ensure that at least two topics from every applicable KJA 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 Tier Totals" Totals in each KJAK/A category shall not be less than two).

2.

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.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply Systems/evolutions at the facility should be deleted and justified; operationally important, site-specific systems/evol systems/evolutions utions that are not included on the outline should be added. added. Refer to Section D.1 D.1.b

.b of ES-401 for guidance regarding the elimination of of inappropriate K/A KJA statements.

4.

4. Select topics from as many many systems and and evolutions as possible; sample every every system or evolution in the group group before selecting a second topic for any any system system or evolution.

evolution.

5.

5. Absent Absent aa plant-specific priority, only those priority, only those K/As KJAs having having an an importance importance ratingrating (IR)

(IR) of of 2.5 2.5 oror higher higher shall shall be be selected.

Use Use the RO RO and SRO ratings for the RO and and SRO and SRO-only SRO-only portions, portions, respectively.

6.

6. Select SRO topics Select SRO for Tiers topics for Tiers 11 and from the and 22 from the shaded shaded systems systems and and K/AKJA categories.

categories.

7.

7.* The The generic generic (G) KJAs in (G) K/As in Tiers Tiers 11 and and 22 shall shall bebe selected selected fromfrom Section Section 22 of of the the K/A KJA Catalog, Catalog, butbut the the topics topics must must bebe relevant relevant toto the the applicable applicable evolution evolution or or system.

system. ReferRefer toto Section Section D.1.b D.1.b ofof ES-401 ES-401 for for the the applicable KJAs.

applicable K/As.

8.

8. On On the the following pages, enter following pages, enter the KJA numbers, the K/A numbers, aa briefbrief description description of of each each topic, topic, the the topics topics' importance importance ratings ratings (IRs)

(IRs) for the for the applicable applicable license level, and license level, and thethe point totals (#)

point totals (#) for for each each system system and and category.

category. Enter Enter the the group group and and tier tier totals totals for each category for each category in in the table above; the table above; ifif fuel fuel handling handling equipment equipment is is sampled sampled in in other other than than Category Category A2A2 or or G G* onon the the SRO-only SRO-only exam, exam, enter enter itit on the left on the side of left side Column A2 of Column for Tier A2 for 2, Group Tier 2, Group 22 (Note (Note #1#1 does does notnot apply). Use duplicate apply). Use duplicate pages for RO pages for RO and and SRO-only SRO-only exams. exams.

9.

9. For For Tier Tier 3, select topics 3, select topics fromfrom Section Section 22 of of the the K/A KJA catalog, catalog, andand enter enter the the K/A KJA numbers, numbers, descriptions, descriptions, IRs, IRs, and point and totals (#)

point totals (#) onon Form Form ES-401-3.

ES-401-3. Limit Limit SROSRO selections selections to to K/As KJAs that are linked that are linked toto 10 10 CFR CFR 55.43.

55.43.

ES-401 ES-401 2 RO 2-RO

- Form ES-401-2 Form ES-401-2 ES-401 ES-401 PWR PWR Examination Examination Outline Outline Form Form ES-401-2 ES-401-2 Emergenc Emergency and and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier

- Tier 1/Group 1/Group 11 (RO (RO II SRO)

SRO)

E/APE #

E/APE # I/ Name Name I/ Safety Safety Function Function KK KK* KK A A A A GG K/A Topic(s)

KIA Topic(s) IR ##

lR 112312 2 3 1 2 000007 000007 (BW/E02&E10; (BW/E02&E1 0; CElE02)

CE/E02) Reactor Reactor Trip Trip - Stabilization

- Stabilization - Recovery

- Recovery! I 11 r1] [1]

000008 000008 Pressurizer Pressurizer Vapor Vapor Space Space X X AK1 .01 Knowledge AKI.OI Knowledge of of the the operational operational implications implications of of 3.2 3.2 11 Accident/3 Accident / 3 [2]

[2] the the following following concepts concepts as as they they apply apply toto aa Pressurizer Pressurizer 3.7 3 7 Vapor Vapor SpaceSpace Accident:

Accident Thermodynamics Thermodynamics and and flow flow characteristics of characteristics of open open oror leaking leaking valves.

valves.

000009 000009 Small Small Break Break LOCALOCA I/ 33 r3]

[3]

000011 000011 Large Break LOCA I/ 3 Large Break 3 [4]

[4] X EA1.12:

EA1.12: Ability Ability to to operate operate and and monitor monitor the the following following 4.1 4.1 22 as as they they apply apply to to a a Large Large Break Break LOCA:

LOCA: Long-term Long-term 4.4 4.4 containment containment of of radioactivity.

radioactivity.

000015/17 000015/17 RCP Malfunctions I/ 4 RCP Malfunctions 4 [5]

[5] X AK2.10:

AK2 10 Knowledge Knowledge of of the the interrelations interrelations between between thethe 2.8 2 8 33 Reactor Coolant Coolant Pump Pump Malfunctions Malfunctions (Loss (Loss ofof RC RC 2.8 2 8 Flow) and and the the following:

following: RCP RCP indicators indicators andand controls.

controls.

000022 000022 LossLoss of of Rx Rx Coolant Makeup Makeup! I 22 [6]

[6] X X AA1.OI:

AA1.01: Ability Ability to to operate operate and and! / or or monitor monitor the the 3.4 3.4 44 following following as as they apply to the Loss of Reactor Coolant 3.3

3.3 Makeup

CVCS letdown and charaing. charging.

000025 Loss of RHR System System I/4 4 [7]

[7] X AA2.06: Ability to determine and interpret the 3.2 5 following as they apply to the Loss of Residual Heat 3.4 3.4 Removal System: Existence of proper RHR overpressure protection.

000026 Loss of Component Cooling X AAI.02:

AAI 02 Ability to operate and and!/ or monitor momtor the the 3.2 3 2 66 Water I/ 8 [8] followmg as they apply to the Loss of Component following 3.3 3 3 Cooling Water: Loads on the CCWS in the control room.

000027 Pressurizer Pressure 000027 Pressurizer Pressure Control Control System Malfunction I/ 3 System Malfunction [9]

000029 A ATWS/

TWS I 11 [10] X Knowledge of the 2.1.28: Knowledge the purpose purpose and function function of 4.1 4.1 7 7

major major system components and controls. 4.1 000038 Steam Gen. Tube Rupture 13 Steam Gen /3 [1 [111 )) X X 22.1.20:

1 20 Ability to interpret and execute procedure 4.6 46 88 steps steps. 4.6 46 000040 (BW/E05; CE/E05; W!E1 000040 W/E12) 2) X AA1 AA1.02:.02: Ability to operate and! and / or monitor the 4.5 4.5 9 9

Steam Line Rupture - Excessive Heat

- following as they apply to the Steam Line Rupture: 4.5 4.5 Transfer!

Transfer I 44 [12] Feedwater isolation.

000054 000054 (CE/E06) Loss of (CE/E06) Loss of Main Main XX AA1.02: Ability AA1.02: Ability to to operate and! and / oror monitor monitor the 4.4 4.4 10 10 Feedwater Feedwater I 44 [13] following as as they apply apply to to the the Loss Loss of of Main Feedwater Feedwater 4.4

4.4 (MFW)

Manual startup of of electric electric and and steam-driven steam-driven AFW pumps.

AFWpumps.

000055 Station Blackout/6 000055 Station Blackout I 6 [14][14]

000056 Loss 000056 Loss of Off-site Power of Off-site Power /I 66 [15]

[15] X X AA2.67: Ability AA2.67: Ability to to determine determine and and interpret interpret thethe 2.9 2.9 11 11 following following as as they they apply apply to to the the Loss Loss of of Offsite Offsite Power:

Power: 3.1 3.1 Seal Seal injection injection flow (for the RCPs).

(for the RCPs).

000057 000057 LossLoss of of Vital AC Inst.

Vital AC Inst. Bus/6[16]

Bus I 6 [16] X X 2.2.22: Knowledge 2.2.22: Knowledge of of limiting limiting conditions conditions for 4.0 4.0 12 12 operations operations and and safety safety limits.

limits. 4.7 4.7 000058 Loss 000058 Loss of DC Power!

of DC Power 166 [17]

[17] X X 2.2.36: Ability 2.2.36: Ability to analyze the to analyze the effect effect ofof maintenance maintenance 3.1 3.1 13 13 activities, such activities, such asas degraded degraded power power sources, sources, onon the the 4.2 4.2 status status ofof limiting limiting conditions conditions for for operations.

operations.

000062 Loss 000062 Loss of NuclearSvc of Nuclear SvcWater/4 Water/4 [18] [18 1 XX AK3 02 Knowledge AK3.02: Knowledgeof ofthe thereasons reasonsfor forthethefollowing followmg 3.6 3 6 14 14 responses responsesas asthey they apply apply to to the theLoss Lossof ofNuclear Nuclear Service Service 3.9

3.9 Water

Water: TheThe automatic automaticactions actions (alignments)

(alignments) withinwithin thethe nuclear nuclearservice service water waterresulting resultingfrom from thethe actuation actuation ofthe of the ESFAS.

ESFAS.

AA2.05: Ability to AA2.05: Ability to determine determine and and interpret interpret the the 000065 Loss 000065 Loss of Instrument Air of Instrument Air!

I 88 [19]

[19) XX 3.44 15 following following as as they they apply apply to to 15 the the Loss Loss ofofInstrument Instrument Air: Air When When to to commence commence plant plant 4.1 41 shutdown if shutdown ifinstrument instrument air air pressure pressure is is decreasin decreasing.cr

• W/E04 LOCA W/E04 LOCA Outside Outside ContainmenV3 Containmentl3 [20] XX EK3.1:

EK3. 1: Knowledge Knowledge of ofthe the reasons reasons for

[20] for thethe following following 3.2 3.2 1616 responses responses as as they they apply apply to to the the (LOCA (LOCA OutsideOutside 3.5

3.5 Contaimnent)

Containment): Facility Facility operating operating characteristics characteristics during during transient transient conditions, conditions including including coolant coolant chemistry chemistry and and the the effects of effects of temperature, temperature pressure, pressure and and reacti vity changes reactivity changes and and operating operating limitations limitations and and reasons reasons for for these these operating operating characteristics.

characteristics.

EKI.2: Knowledge of EKI .2: Knowledge of the the operational operational implications implications of of W/E1 1 Loss W/E11 Loss of of Emergency Emergency Coolant Coolant XX 3.6 17 the the following following concepts concepts as as they they apply apply to to the the (Loss (Loss of of 3.6 17 Recirc. I/ 4 Recirc. 4 [21]

[21] 4.1 Emergency Emergency Coolant Coolant Recirculation):

Recirculation): Normal, Normal, abnormal abnormal 4.1 and and emergency emergency operating operating procedures procedures associated associated withwith (Loss of (Loss of Emergency Emergency Coolant Coolant Recirculation).

Recirculation)

BW!E04; W/E05 BW/E04; W!E05 Inadequate Inadequate Heat Heat Transfer - Loss Transfer - Loss of of Secondary Secondary Heat Heat Sinkl4 Sink/4

[22]

[22J 000077 Generator 000077 Generator Voltage Voltage and and Electric Electric X X AK2.06: Knowledge of the interrelations interrelations between between 3.9 18 18 Grid Disturbances I/ 6 Grid Disturbances 6 [23]

[23] Generator Generator Voltage and and Electric Grid Grid Disturbances Disturbances 4.0 and the following: Reactor J.lower. power.

II KJA Category KIA Category Totals:

Totals: 22 2 2 5 I 3 4 I Group Point Total: 118

ES-401 ES-401 3- RO 3 RO Form Form ES-401-2 ES-401-2 ES-401 ES-401 PWR PWR Examination Examination Outline Form Outline Form ES-401-2 ES-401-2 Emergency Emergency and and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier

- Tier 1/Group 1/Group 22 (RO (P0/ / SRO)

SRO) =

E/APE ##1 E/APE Name // Safety

/ Name Safety Function Function KK KK KK AA AA G G KIA K/A Topic(s)

Topic(s) IR ##

IR 11 223123 1 2 000001 Continuous Rod 000001 Continuous Rod Withdrawal Withdrawal // 11 [1] [1] X X AK2.08:

AK2.08: Knowledge Knowledge of of the the interrelations interrelations 3.1 19 3.1 19 between between the the Continuous Continuous Rod Rod Withdrawal Withdrawal and and 3.0 3 0 the the following:

following Individual Individual rod rod display display lights lights and and indications.

indications.

000003 Dropped 000003 Dropped Control Rod /I 1 Control Rod 1 [2]

[2]

000005 Inoperable/Stuck 000005 inoperable/Stuck Control Control Rod Rod // 11 [3] [3] X X AK3.0l:

AK3.01: Knowledge Knowledge of of the the reasons reasons for for the the 4.0 4.0 20 20 following following responses responses as as they they apply apply to to the the 4.3 4.3 Inoperable II Stuck Inoperable Stuck Control Control Rod:Rod: Boration Boration andand emergency emergency boration boration in in the the event event ofof aa stuck stuck rod rod during during trip trip or or normal normal evolutions.

evolutions.

000024 Emergency 000024 Boration /I 1 Emergency Soration 1 [4]

[4]

000028 Pressurizer 000028 Pressurizer Level Level Malfunction Malfunction // 2 2 [5]

[5] X 2.4.4:

244 Ability Abthty to to recognize recogmze abnormal abnormal 4.5 4 5 21 21 indications for system system operating operating parameters parameters 4.7 47 that that are are entry-level conditions for for emergency emergency and abnormal operating procedures.

000032 Loss of 000032 Loss of Source Range NI /7 Source Range / 7 [6] X AK1.Ol:

AKI.01: Knowledge of of the the operational operational 2.5 22 22 implications of the following following concepts concepts as as they they 3.1 3.1 apply to Loss of Source Range Range Nuclear Nuclear Instrumentation: Effects of voltage changes changes on performance.

000033 Loss 000033 Loss of of Intermediate Intermediate Range Range NI NI /7[7]

/ 7 [7]

000036 (SW/A08) 000036 (BW/A08) Fuel Fuel Handling Handling Accident /8 [ 8]

/ 8 [8]

000037 Steam 000037 Generator Tube Steam Generator Tube LeakLeak / 3 3 [9]

[9] X AA1.06:

AA1 Ability to

.06: Ability to operate operate and and I/ or or monitor monitor 3.8 3.8 23 23 the following as the as they apply apply to to the Steam the Steam 3.9 3.9 Generator Generator Tube Leak: Main steam line rad monitor meters.

000051 LossofCondenserVacuum/4 000051 Loss of Condenser Vacuum /4 [10]

[10]

000059 000059 Accidental Accidental Liquid RadWaste Rel.

Liquid RadWaste ReI. /9 / 9 [11]

000060 Accidental Gaseous Radwaste ReI. / 9 000060 Accidental Gaseous Radwaste ReI / 9 [12]

[12]

000061 ARM 000061 System Alarms ARM System Alarms / 7 [13]

/ 7 [13]

000067 Plant 000067 Plant Fire Fire On-site On-site // 88 [14]

[14]

000068 (SW/A06) Control 000068 (BW/A06) Control Room Room Evac.Evac. // 88 [15] [15] X X AA2.05: Ability AA2.05: Ability toto determine determine and and interpret interpret 4.2 4.2 24 24 the following the following as as they they apply apply to to the the Control Control 4.3 4.3 Room Evacuation:

Evacuation: Availability Availability of of heat heat sink.

sink.

000069 (W/E1 000069 (W/E14) Loss of

4) Loss of CTMT CTMT Integrity Integrity // 55 [16]

[16] X X AK1.0l:

AKI .01: Knowledge of Knowledge ofthe operational the operational 2.6 2.6 25 25 implications of implications of the the following following concepts concepts as as they they 3.1 3.1 apply to apply to Loss Loss ofof Contaimnent Contaimuent Integrity Integrity: Effect Effect of pressure pressure on on leak leak rate rate.

000074 (W/E06&E07) 000074 (W/E06&E07) mad.Inad. Core Core Cooling!

CoolinQ / 44 [17]

[17]

000076 High 000076 High Reactor Reactor Coolant Coolant Activity!

Activity / 99 [181 [181 W/E01 & E02 W!EO1 & E02 Rediagnosis && SI Rediagnosis SI Termination Termination //3[19] 3 [19)

W/E1 3 Steam EK2.2: Knowledge EK2.2: Knowledge of of the the interrelations interrelations W/E13 Steam Generator Generator Over-pressure!

Over-pressure /4 4 [20]

[20] XX 3.0 3.0 26 26 between the between the (Steam (Steam Generator Generator Overpressure)

Overpressure) 3.2 and the following:

and the following: Facility*s Facility*s heat heat removal removal systems, including systems, including primary primary coolant, coolant, emergency emergency coolant, the coolant the decay decay heat heat removal removal systems systems, andand relations between relations between thethe proper proper operation operation of ofthese these systems to systems to the the operation operation of ofthe the facility.

facility.

m - 01 C)

W/E15 Containment Flooding I 5 [21] 01 X 2.2.38: Knowledge of conditions and L.)

0 CD 0 >< (Cl 3.6 27 E

0

3 :3 0 Cl)

CD CD limitations in the facility license. 4.5 L

m>>mm>>>>>

o3rT CD 1)

W/E16 High Containment Radiation I 9 [22] 3 0

BW/A01 Plant Runback 11 [23]

0 BW/A02&A03 Loss of NNI-X/Y I 7 [24] -, f\)

5o r

0 .

BW/A04 Turbine Trip I 4 [25]

0 01 BW/A05 Emergency Diesel Actuation I 6 [26] 0) Ics

°<

3 0

BW/A07 Flooding I 8 [27]

-J 0

J0___

BW/E03 Inadequate Subcooling Margin 14[281 C.) CD

_ooo0 m>G 0

BW/E08; W/E03 LOCA Cooldown -

CD D~ess. 14[29]

0) 0 C) S BW/E09; CElA13; W/E09&E10 Natural Circ. I 4 [30] z CD CD

- m 0 00 BW/E13&E14 EOP Rules and Enclosures [31]

CI)

C.)

0 CEIA 11; WIE08 RCS Overcooling - PTS I 4 [32] 3 C-;

mm D

CE/A16 Excess RCS Leakage I 2 [33]

>< Cl)

C,>

CE/E09 Functional Recovery [34]

0 1J o

KIA Category Point Totals:

o I 2 F) F.)

2 1 1 1 2 F) G)

Group Point Total:

- D :3 ,

9 CD

ES-401 ES-401 4 RO 4-RO- Form Form ES-401-2 ES-401-2 ES-401 PWR PWR Examination ExaminationOutline Form r;;:01 Outline Form ES-401-2 ES-401-2 PlantSSystems Plant stems - Tier

- Tier21Group 2/Group 11(RO (RO / ISRO)

SRO)

System ##1 System Name

/ Name KK KK KK KK KK KK AA AA AA AA KIA GG K/A Topic(s)

Topic(s) IR IR ##

112345 2 3 4 5 61234 6 1 2 3 4 003 Reactor 003 Reactor Coolant Coolant Pump Pump [1] [11 XX K6.04:

K6.04: Knowledge Knowledge of 2.8 28 ofthe the effect effectof ofaaloss loss or or 2.8 28 malfunction malfunctionon on the the following following will will have have onon 3.1 3.1 the the RCPS:

RCPS: Containment Containmentisolationisolation valves valves affecting RCP affecting RCP operation.

operation.

004 Chemical 004 Chemical andand Volume Volume XX Al.05:

A1.05: Ability Ability to to predict predict and/or and/or monitor 2.9 29 monitor 2.9 29 Control [2] changes changes inin parameters parameters (to 3.2 Control [2] (to prevent prevent 3.2 exceeding exceeding design design limits) limits) associated associated with with operating operating thethe CVCS CVCS controls controls including:

including:

S/G S/G pressure pressure and and level.

level.

005 Residual 005 Residual Heat Heat Removal Removal [3] [3] X X Kl.06:

K1.06: Knowledge Knowledge of of the the physical 3.5 30 physical 3.5 30 connections connections and/or and/or cause-effect cause-effect 3.6 3.6 relationships relationships between between the the RHRS RURS and and thethe followin2 following systems:

systems: ECCS.ECCS.

006 Emergency Core 006 Emergency Core Cooling Cooling [4][4] XX K2.01:

K2.01: Knowledge Knowledge of of bus bus power power supplies supplies 3.6 31 3.6 31 to the followin2:

following ECCS pumps. pumps 3.9 39 007 Pressurizer Relief/Quench 007 Pressurizer Relief/Quench X K4.01: Knowledge ofPRTS of PRTS design 2.6 32 2.6 32 Tank [5]

Tank [5] feature(s) and/or interlock(s) which 2.9 2.9 provide for the following: Quench tank tank cooling.

008 Component Cooling 008 Component Cooling Water Water [6][6] X A4.05: Ability to manually operate operate and/or and/or 2.7 33 2.7 33 monitor in the control room: Normal Normal 2.5 2.5 CCW-header total flow rate rate and and the the flow flow rates to the components cooled by by the the CCWS.

CCWS.

010 010 Pressurizer Pressurizer Pressure Pressure Control Control X X K5 .01: Knowledge K5.Ol Knowledge of of the the operational operational 3.5 3.5 34 34

[7]

[7] implications of implications of the the following following concepts concepts as as 4.0 4.0 the apply the apply to to the the PZRPZR PCS:PCS: Determinatio Determination n of condition of condition of of fluid fluid inin PZR PZR, using using steam steam tables.

tables.

012 012 Reactor Reactor Protection[8]

Protection[8] X X K6.01: Knowledge K6.01: Knowledge of of the the effect effect ofof aa loss loss or or 2.8 2.8 35 35 malfunction of malfunction of the the following following will will have have on on 3.3 3.3 the RPS:

the RPS: Bistables Bistables and and bistable bistable test test equipment.

equipment.

013 Engineered 013 Engineered Safety Safety Features Features XX 2.2.38: Knowledge 2.2.38: Knowledge of ofconditions conditions and and 3.6 3.6 36 36 Actuation Actuation [9] [9] limitations in limitations in the the facility facility license.

license. 4.5 4.5 022 Containment 022 Containment Cooling Cooling [10]

[10] XX A3.01:

A3 Ability to 01 Ability to momtor monitor automatic automatic 44.1 1 37 37 operationof operation ofthe the CCS, CCS, including:

including: Initiation Initiation 4.3 4.3 ofofsafeguards safeguards mode mode of ofoperation.

operation.

025 025 Ice Condenser [11)

IceCondenser [11]

REJECTED REJECTED AlAI.01:

.01: Ability Abilityto to predict predictand/orand/ormonitor monitor 026 Containment 026 ContainmentSpraySpray[12]

[12] XX changesin changes inparameters parameters(to (toprevent prevent 3.9 3.9 3838 exceedingdesign exceeding designlimits) limits)associated associatedwith with 4.2 4.2 operatingthe operating theCSSCSScontrols controlsincluding:

including:

Containmentpressure.

Containment pressure.

039 Mainand 039 Main and Reheat ReheatSteam Steam [13][13] XX 242.4.20: Knowledgeof 20 Knowledge ofthe theoperational operational 33.88 3939 implicationsofofEOP implications EOPwarnings, warnings,cautions, cautions, 4.3 4.3 andnotes.

and notes.

059 Main Feedwater [14] X A2.05: Ability to (a) predict the impacts 3.1 40 of the following malfunctions or 3.4 operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in the MFW suction or discharge line.

061 Auxiliary/Emergency X A3.01: Ability to monitor automatic 4.2 41 Feedwater [15] operation of the AFW, including: AFW 4.2 startup and flows.

062 AC Electrical Distribution [16] X K2.01: Knowledge of bus power supplies 3.3 42 to the following: Major system loads. 3.4 K3.02: Knowledge of the effect that a loss 063 DC Electrical Distribution [17] X or malfunction of the DC electrical 3.5 43 system will have on the following: 3.7 Components using DC control power.

064 Emergency Diesel Generator X 2.1.7: Ability to evaluate plant 4.4 44

[18] performance and make operational 4.7 judgments based on operating characteristics, reactor behavior, and instrument internretation.

073 Process Radiation X A4.01: Ability to manually operate and/or 3.9 45 Monitoring [19] monitor in the control room: Effluent 3.9 release.

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078 Instrument Air [21] X K1.03: Knowledge ofthe physical 3.3 47 connections and/or cause-effect 3.4 relationships between the lAS and the following systems: Containment air.

K3.01: Knowledge of the effect that a loss 103 Containment [22] X or malfunction of the containment 3.3 48 system will have on the following: Loss of 3.7 containment integrity under shutdown conditions.

004 Chemical and Volume X K3.08: Knowledge of the effect that a loss 3.6 49 Control [23] or malfunction of the CVCS will have on 3.8 the following: RCP seal injection.

007 Pressurizer Relief/Quench X K5.02: Knowledge of the operational 3.1 50 Tank [24] implications of the following concepts as 3.4 the apply to PRTS: Method of forming a steam bubble in the PZR.

Kl.Ol: Knowledge of the physical 039 Main and Reheat Steam [25] X connections and/or cause-effect 3.1 51 relationships between the MRSS and the 3.2 following systems: S/G.

062 AC Electrical Distribution [26] X A3.05: Ability to monitor automatic 3.5 52 operation of the ac distribution system, 3.6 including: Safety-related indicators and controls.

039 Main and Reheat Steam [27] X K3.06: Knowledge of the effect that a loss 2.8 53 or malfunction of the MRSS will have on 3.1 the following: SDS.

026 Containment 026 Spray [28]

Containment Spray [28] XX A2 04 Ability A2.04: Ability to to (a)

(a) predict predictthetheimpacts impacts of of 3.9 39 54 54 the the following following malfunctions malfunctions or or operations operations 4.2 42 on on the the CSS; CSS; and and (b)

(b) based based on on those those predictions, predictions, use use procedures procedures to to correct, correct, control, or control, or mitigate mitigate the the consequences consequences of of those those malfunctions malfunctions or or operations:

operations: Failure Failure of spray pump.

064 Emergency 064 Emergency Diesel Diesel Generator Generator XX K6 07 Knowledge K6.07: Knowledge of ofthe the effect effect of ofaa loss loss or or 2.7 27 55 55

[29]

[29] malfunction of malfunction ofthe the following following willwill have have onon 2.9 29 the the ED/G EDIG system:

system Air Air receivers.

receivers K/A Category KJA Category Point Point Totals:

Totals: 33 33 33 22 I I 22 33 zzz________

22 22 33 22 33 Group Point Group Point Total:

Total: 28 28

ES-401 ES-401 5 RO 5-RO

- Form Form ES-401-2 ES-401-2 ES-401 ES-401 PWR Examination PWR Examination Outline Outline r.

Form ES-401-2 Plant Plant SSystems stems - Tier

- 2/Group 22 (RO Tier 21Group (P0// SRO)

SRO)

System ##1 System Name

/ Name KK KK KK KK K K K K A A A A A A A A GG KIA K/A Topic(s)

Topic(s) IR IR ##

11234561234 2 3 4 5 6 1 2 3 4 001 Control 001 Control Rod Rod Drive Drive [1] [1]

002 Reactor 002 Reactor Coolant Coolant [2] [2] XX K6.07:

K6.07: Knowledge Knowledge of of the the effect effect or or aa loss loss or or 2.5 2.5 56 56 malfunction malfunction on on the the following following RCSRCS 2.8

2.8 components

components; Pumps.

Pumps.

01 1 Pressurizer 011 Pressurizer Level Level Control Control [3] [3]

014 Rod 014 Rod Position Position Indication Indication [4] [4] X X Kl.Ol:

Kl.0l: Knowledge Knowledge of of the the physical physical 3.2 3.2 57 57 connections and/or connections and/or cause-effect cause-effect relationships relationships 3.6 3.6 between the between the RPIS RPIS andand thethe following following systems:

systems:

CRDS.

CRDS.

015 Nuclear 015 Instrumentation [5]

Nuclear Instrumentation [5] XX K4.01:

K4.0l: Knowledge of of NIS design design feature(s) feature(s) 3.1 3.1 58 58 and/or and/or interlock(s) provide for for the following:

following: 3.3 3.3 Source-Range Source-Range detector power shutoff shutoff at high powers.

016 Non nuclear Instrumentation 016 Non-nuclear Instrumentation

[6]

[6]

017 In-core 017 In core Temperature Monitor X K3.01:

K3 01 Knowledge of the effect that a a loss loss or or 3.5 3 5 59 59

[7]

[7] malfunction of the ITM system will will have have on on 3.7 3.7 the following: Natural circulation indications.

the_following;_Natural_circulation_indications.

027 Containment 027 Containment Iodine Removal X Kl.OI:

Kl.0l: Knowledge of the physical 3.4 3.4 60 60

[8]

[8] connections and/or cause-effect relationships relationships 3.7 3.7 between the CIRS and the the following systems:

CSS.

cSS.

028 Hydrogen Recombiner and Purge and Purge Control Control [9]

[9]

029 029 Containment Containment Purge Purge [10] [10]

033 033 Spent Spent Fuel Fuel Pool Pool Cooling Cooling [11] [11]

034 Fuel 034 Fuel Handling Handling Equipment Equipment [12] [12] X A4.02:

A4 Ability to 02 Ability to manually manually operate and/or and/or 3.5 35 61 61 monitor in monitor in the the control control room:

room: Neutron Neutron levels.

levels. 3.9 3.9 035 Steam 035 Steam Generator Generator [13] [13] X X A2.06: Abllity A2.06: Ability toto (a)

(a) predict predict the the impacts impacts of of 4.5 4.5 62 62 the following the following malfunctions malfunctions or or operations operations on on 4.6 4.6 the SG; the SG; and and (b)

(b) based based onon those those predictions, predictions, use procedures use procedures to to correct, correct, control, control, oror mitigate the mitigate the consequences consequences of of those those malfunctions or malfunctions or operations:

operations: Small Small break break LOCA.

LOCA.

041 Steam 041 Steam Dump/Turbine Dump/Turbine X X A4.06: Ability A4.06: Ability to to manually manually operate operate and/or and/or 2.9 2.9 63 63 Bypass Bypass Control Control [14]

[14] monitor in mointor in the the control control room:

room: Atmospheric Atmospheric 3.1 3.1 relief valve relief valve controllers.

controllers.

K1.I8: Knowledge K1.18: Knowledge of of the the physical physical 045 Main 045 Main Turbine Generator [15]

Turbine Generator [15] X X connections and/or connections and/or cause-effect cause-effect relationships relationships 3.6 3.6 64 64 between the between the MT/G system and MT/G system and the the following following 3.7 7

systems: RPS.

055 Condenser 055 Condenser AirAir Removal Removal [16] [16]

056 Condensate 056 Condensate [17][17]

068 Liquid 068 Liquid Radwaste[18]

Radwaste [18] = = = = = =

071 Waste 071 Waste Gas Disposal [19]

Gas Disposal [19]

072 Area 072 Area Radiation Radiation Monitoring Monitoring

[20]

[20]

075 Circulating 075 Circulating Water Water [21]

[211 XX K2.03: Knowledge K2.03: Knowledge ofofbus bus power power supplies supplies to to 2.6 2.6 65 65 the following:

the following: Emergency/essential Emergency/essential SWS SWS 2.7 2.7 pumps.

pumps 079 Station 079 Station Air Air [22]

1221 086 Fire Protection 086 Fire Protection [23]

[23]

K/A Category Point Totals:

VIA 1"'.

33 11 I1 I1 00 I1 00 11 00 22 Group Group Point Point Total:

Total: 10 10

ES-401 ES-401 Generic Generic Knowledge Knowledge and and Abilities Abilities Outline Outline (Tier(Tier 3)3) - RO

- RO Form Form ES-401-3 ES-401-3 Facility~J1*B.

Facility: oIoiiiovi 2

1 RoloiflsOVl Date of Date of Exam:

Exam:

Category Category KJA ##

KIA Topic Topic RO RO SRO-Only SRO-Only IR IR ## IR IA ##

2.1.26 2.1.26 Knowledge of industrial safety procedures (such as rotating Knowledge of industrial safety procedures (such as rotating 3.4 3.4 66 66 3.6 3.6 equipment, equipment, electrical, electrical, high high temperature, temperature, high high pressure, pressure, 1.

1.

caustic, caustic, chlorine, chlorine, oxygen oxygen and and hydrogen).

hydrogen).

Conduct Coflduct 2.1.28 2.1.28 Knowledge Knowledge of of the the purpose purpose and and function function of of major major system system 4.1 4.1 67 67 4.1 4.1 of Operations components components and and controls.

controls.

2.1.

2.1.

2.1.

2.1.

2.1.

2.1.

Subtotal Subtotal 2.2.6 2.2.6 Knowledge Knowledge of of the the process process for for making making changes changes to to 3.0 3.0 68 68 3.6 3.6 procedures.

procedures.

2.

2.

2.2.40 2.2.40 Ability Ability to to apply apply Technical Technical Specifications Specifications for for a a system.

system. 3.4 3.4 69 69 4.7 4.7 Equipment Equipment 2.2.

Control Control 2.2.

2.2.

2.2.

2.2.

Subtotal Subtotal 2.3.4 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 3.2 70 3.7 3.7 emergency conditions.

2.3.13 2.3.13 Knowledge of radiological safety procedures pertaining to 3.4 3.4 71 3.8 3.8 3.

3 Radiation licensed operator duties, such as response to radiation Radiation Control monitor alarms, containment entry requirements requirements,, fuel Control handling responsibiliti responsibilities,es, access to locked high-radiatio high-radiation n areas, aligning filters, etc.

2.3.7 2.3.7 Ability Ability to comply comply with radiation work permit requirements 3.5 3.5 72 72 3.6 3.6 during normal or abnormal conditions.

2.3.

2.3.

2.3.

2.3, Subtotal Subtotal Knowledge Knowledge of of EOP implementati implementation hierarchy and on hierarchy and 2.4.16 2.4.16 3.5 73 73 4.4 4.4 coordination with coordination with other other support support procedures procedures or or guidelines guidelines such as, such operating procedures, as, operating procedures, abnormal abnormal operating operating 4.

4 procedures, and procedures, and severe severe accident management guidelines.

accident management guidelines.

Emergency E

Procedures //

Knowledge of Knowledge of the bases for the bases for prioritizing safety functions prioritizing safety functions 2.4.22 2.4.22 during 3.6 3.6 74 74 4.4 4.4 Plan during abnormal/em abnormaVemergency ergency operations.

operations.

Plan Knowledge Knowledge of of the for prioritizing bases for the bases prioritizing emergency emergency 2.4.23 2.4.23 3.4 34 75 75 4.4 44 procedure implementat procedure implementation during emergency ion during emergem:y operations.

operations.

2.4.

2.4.

2.4.

2.4.

Subtotal Subtotal Tier Tier 33 Point Point Total Total 10 10

ES-401 ES-401 Record of Record of Rejected Rejected KI K/As As Form Form ES-401-4 ES-401-4 Tier // Group Tier Group Randomly Randomly Selected Selected Reason Reason for for Rejection Rejection K/A KIA 1/1 1/1 000029.G2.3. 13 0OOO29.G2.3.13 Cannot Cannot write write aa quality quality question question concerning concerning radiological radiological actions actions for for an an ATWS ATWS event.

event.

1/1 1/1 000057.G2.1.41 OOOOS7.G2.1.41 Does Does not not meet meet NUREG NUREG 1021, 1021, ES-401, ES-401, D.l.b D.1.b guidelines.

guidelines.

1/2 1/2 000028.G2.4.39 0OOO28.G2.4.39 Does Does not not meet meet NUREG NUREG 1021, 1021, ES-401, ES-401, D.l.b D.1.b guidelines.

guidelines.

1/2 1/2 W/E IS.

WIE 15. G2.2.38 G2.2.38 RNP has RNP has no no LCO actions actions for for Containment Containment Sump Sump high high level level addressed addressed in in Technical Technical Specifications.

Specifications.

2/1 2/1 026.Al .04 026.Al.04 RNP RNP does does not not have have the the capability capability to to monitor monitor Containment Containment Humidity Humidity remotely.

2/1 211 059.A2.07 OS9.A2.07 RNP does not have Turbine Driven Feed RNP Feed Pumps.

2/1 061.A3.04 RNP does not have automatic isolation features for AFW to the S/Gs.

2/1 211 076.K4.03 RNP does not have any automatic isolation for the CCW heat exchangers.

2/2 212 014.K2.02 RNP does not correct the NIS for power. RPI is an independent system which is temperature corrected only.

2/1 211 007.K5.02 007.KS.02 RNP does not use the PRT when forming a Steam bubble in the PZR.

ES-401 ES-401 PWR Examination Outline PWR Examination Outline - SRO - SRO Form Form ES-401-2 ES-401-2 Facility:

Facility: 4 .S. (2.o~it1 H.~. RIitvi ~OY) SOY) Date of Date of Exam:

Exam:

ROK/ACooy RO KIA CateqoryPohits Points SRO-Only SRO-Only_P Points oints Tier Tier Group Group KK KKK K KKKKA K K A AAAG A A A G A2 A2 G*

G* Total Total 11 22 33 44 55 66 11 22 33 44 ** Total Total 1.

1. 11 18 18 33 33 66 Emergency &&

Emergency Abnormal Abnormal 22 N/A N/A N/A N/A 99 22 22 44 Plant Plant Evolutions TierTotals Tier Totals 27 27 55 55 10 10 Evolutions 11 28 2 3 55 2.

2.

Plant Plant 22 10 10 00 33 33 Systems Systems Tier Totals 38 2 6 8

3. Generic Knowledge and Abilities 11 2 3 4 10 10 11 2 3 4 7 Categories Categories I J___ 11 3 0 3 Note:

Note: 1. Ensure that at least two topics from every applicable KIA 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 Tier Totals" Totals in each KIA K/A category shall not be less than two).

2.

2. point total for each group and tier in the proposed outline must match that specified in the table.

The pOint 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 Systems/evolutions at the facility should be deleted and justified; operationally important, site-specific systems/evol systems/evolutionsutions that are not included on the outline should be added. Refer to Section D.1 D.1.b.b of ES-401 for guidance regarding the elimination of inappropriate K/A KIA statements.

4. Select topics from as many many systems and evolutions as possible; sample every system or evolution in the group group before selecting a second topic for any any system system or evolution.

evolution.

5. Absent a plant-specific plant-specific priority, only those K/As KlAs having an importance rating (IR) of of 2.5 or higher shall shall be selected.

Use the RD RO and SRO ratings for the RD RO and SRO-only portions, respectively.

6.

6. Select Select SROSRO topics for for Tiers Tiers 11 and and 22 from from thethe shaded shaded systems systems and and K/A KIA categories.

categories.

7* The generic 7.* generic (G) K/AsKlAs in in Tiers Tiers 11 and and 22 shall be be selected selected from from Section 22 of of the K/A KIA Catalog, but but the topics must must be be relevant to to the applicable evolution evolution or or system.

system. Refer Refer to to Section Section D.1 D.1.b

.b ofof ES-401 ES-401 for the the applicable applicable K/As.

KlAs.

8.

8. On the following On the following pages, pages, enter enter the KIA numbers, the K/A brief description numbers, aa brief description of of each each topic, topic, the the topics topiCS' importance importance ratings ratings (IRs)

(IRs) for the applicable for the applicable license level, and license level, and thethe point totals (#)

point totals (#) for for each each system system andand category.

category. Enter Enter the the group group and and tier tier totals totals for for each each category category in in the the table table above; above; ifif fuel fuel handling handling equipment equipment is is sampled sampled in in other other than than Category Category A2 or G*

A2 or G* on on the the SRO-only SRO-only exam, enter itit on exam, enter the left on the left side side of Column A2 of Column A2 for for Tier Tier 2, 2, Group Group 22 (Note (Note #1 #1 does does notnot apply). Use duplicate apply). Use duplicate pages pages forfor RO and SRO-only RO and SRO-only exams.

exams.

9.

9. For Tier For Tier 3, 3, select select topics topics fromfrom Section Section 22 of of the KIA catalog, the K/A catalog, and and enter enter the the K/A KIA numbers, numbers, descriptions, descriptions, IRs, IRs, and and point totals (#)

point totals (#) onon Form Form ES-4o1 ES-401-3. -3. Limit SRO selections Limit SRO selections to to K/As KlAs that that are are linked linked to to 1010 CFR CFR 55.43.

55.43.

ES-401 ES-401 2- SRO 2-SRO Form Form ES-401-2 ES-401-2 ES-401 ES-401 Form PWR Form EC' PWR Examination Examination Outline Outline ,,"H "

ES-401-2 EmerQenc Emergencyand Abnormal Plant and Abnormal Pnt Evolutions Evolutions - Tier

- Tier 1/Group 1/Group 11 (RO (ROI / SRO)

SRO)

E/APE ##I / Name ElAPE NameI / Safety Safety Function Function KK KK KK AA AA GG KIA K/A Topic(s)

Topic(s) IR IR ##

2 3 1 2 112312 000007 (BW/E02&E10; 000007 (BW/E02&E1 0; CElE02)

CE/E02) ReactorReactor Trip - Stabilization Trip Stabilization - Recovery Recovery! I 11 [1] [1]

000008 Pressurizer 2.4.11:

24.11: Knowledge Knowledge of ofabnormal abnormal condition condition procedures.

procedures.

000008 Pressurizer Vapor Vapor Space Space XX (CFR: 41.10/43.5/45.13)

(cFR:41.101 43.5/45.13) 4.0 4.0 76 76 Accident I/ 33 Accident [2]

[2] 4.2 4.2 000009 Small Break LOCA / 3 000009 Small Break LOCA I 3 [3]

(3]

000011 Large Break LOCA I 3 000011 Large Break LOCA / 3

[4]

[4]

000015/17 RCP 000015/17 RCP Malfunctions Malfunctions I /4 4 [5)

[5]

000022 Loss 000022 Loss of of Rx Rx Coolant Makeup I/ 2 Coolant Makeup 2 [6]

(6] X X AA2.03: Ability AA2.03: Ability to to determine determine and and interpret interpret the 3.1 77 the 3.1 77 following as following as they they apply apply toto the the Loss Loss of of Reactor Reactor Coolant Coolant 3.6

3.6 Makeup

Makeup Failures Failures of of flow flow control control valve valve or or controller controller 43.5/ 45.13)

(CFR: 43.5/45.13)

(CFR:

000025 Loss 000025 Loss of of RHR RHR System System I/ 44 [7]

[7] X X AA2.07:

AA2.07: Ability Ability to to determine determine and and interpret interpret thethe 3.4 78 3.4 78 following as following as they they apply apply toto the the Loss Loss of of Residual Residual Heat Heat 3.7 3.7 Removal System:

Removal System: Pump Pump Cavitation.

Cavitation. (CFR (CFR 43.5/45.13) 2.2.3 8: Knowledge 2.2.38: Knowledge of conditions and limitations limitations inin the the 000026 Loss 000026 Loss of Component Cooling X X 3.66 79 facility license (CFR:

facility license. (CFR 41.7/41.10/43.1/45.13) 41 7/41 10/43 1/45 13) 79 Water/8 Water 18 . [8]

(8] 4.5 4.5 000027 Pressurizer 000027 Pressurizer Pressure Control System Malfunction System Malfunction I/ 3 (9]

[91 000029 ATWS 000029 A1WS!1 I 1 [10]

000038 Steam 000038 Steam Gen. Tube Rupture 13 /3 [11 (11 1 J 000040 000040 (BW/E05; (BW/E05; CE/E05; W!E12)

CE/E05; W/E12)

Steam Line Steam Rupture - Excessive Heat Line Rupture -

Transfer!4 Transfer I 4 [12]

000054 000054 (CE/E06)

(CE/E06) Loss Loss ofof Main Main Feedwater/

Feedwater I 4 [13]

[13]

EA2.01:

EA2.01: Ability Ability to to determine determine or or interpret interpret the the 000055 000055 Station Station Blackout!

Blackout I 6 [14] X 3.4 34 80 80 following following as as they they apply apply to aa Station Station Blackout:

Blackout: Existing Existing valve positioning valve positioning on on aa loss loss of of instrument instrument air air system system 3.7 (CFR: 43.5/

(CFR: 43.5 145.13) 45.13) 000056 000056 LossLoss of of Off-site Off-site Power Power /16 6 [15)

[15]

000057 000057 LossLoss of of Vital Vital AC AC Inst.

Inst. Bus!

Bus I 66 [16] [16]

2.1.32: Ability 2.1.32: Ability to to explain explain andand apply apply system system limits limits and and 000058 000058 LossLoss of of DC DC Power!

Power 16 6 [17][17] X X 3.8 38 81 81 precautions. (CFR:

precautions. (CPR: 41.10/45.5 41.10/45.5/45.12/45.13)

/45.12/ 45.13) 4.0 000062 000062 LossLoss of of Nuclear Nuclear SvcSvc Water!4 Water/4 (18] [18]

000065 000065 LossLoss of of Instrument Instrument Air!Air I 8(19]

8 [19]

W!E04 W/E04 LOCALOCA Outside Outside Containment Containment/3 /3 [20]

[20]

W/E1 W/E11 1 Loss Loss of of Emergency Emergency Coolant Coolant Recirc. /I 44 Recirc. [21]

[211 BW/E04 BW/E04; W!E05W/E05 Inadequate Inadequate Heat Heat Transfer Transfer -Loss LossofofSecondary SecondaryHeat HeatSink/4 Sinkl4

[22]

[22]

000077 000077Generator GeneratorVoltage Voltage andand Electric Electric Grid Disturbances/I 66 Grid Disturbances [23]

[23]

KIA Category K/A CateQoryTotals:

Totals: J = = 33 33 I Group Point Group PointTotal:

Total: 6

~

ES-401 ES-401 3 SRO 3-SRO

- Form Form ES-401-2 ES-401-2 ES-401 ES-401 PWR PWR Examination Examination Outline Outline Form Form ES-401-2 ES-401 -2 Emergencyand Emergency and Abnormal Plant Evolutions Abnormal Plant Evolutions- Tier

- Tier1/Group 1/Group22 (RO (RO/ /SRO)SRO)

E/APE ##// Name E/APE Name//Safety Safety Function Function KK KK KK AA AA GG KIA K/ATopic(s)

Topic(s) IR IR ##

112312 2 3 1 2 000001 Continuous 000001 Continuous RodRod Withdrawal Withdrawal // 11 [1] [1]

000003 Dropped Control Rod / 1 000003 Dropped Control Rod / 1 [2)

[2]

000005 Inoperable/Stuck 000005 lnoperable)Stuck Control Control Rod Rod // 11 [3][3]

000024 Emergency Boration / 1 000024 Emergency Boration / 1 AA2.02:

AA2.02: Ability Ability to to determine determine and and interpret interpret the

[4]

[4] X the 3.9 82 82 following following asas they they apply apply to to the the Emergency Emergency 3.9

4.4 Boration

Boration When When use use ofofmanual manual boration boration valve valve is is needed.

needed. (CFR:

(CFR: 43.5 43.5 /45.13)

/ 45.13) 000028 Pressurizer 000028 Pressurizer Level Level Malfunction Malfunction /2J5]/ 2 [5]

000032 Loss of Source Range NI /7 [6]

000032 Loss of Source Range NI /7 [6]

000033 Loss Loss of of Intermediate Intermediate Range /7 [7] AA2.1O:

AA2 10 Ability Ability to to determine determine and and interpret mterpret 000033 Range NI NI /7[7) XX 3.1 3 1 83 83 the the following following as as they they apply apply to to the the Loss Loss of of 3.8 Intermediate Intermediate Range Range Nuclear Nuclear Instrumentation:

Instrumentation: 3 8 Tech-Spec Tech-Spec limits limits ifif both both intermediate intermediate range range failed. (CFR: 43.5 /45.13) channels have failed. / 45.13) 000036 (BW/A08) 000036 (BW/A08) Fuel Fuel Handling Handling Accident Accident! / 88 f[ 8]

8]

000037 Steam 000037 Steam Generator Generator Tube Tube Leak Leak / 3 3 [9]

000051 Loss 000051 Loss of of Condenser Condenser Vacuum Vacuum /4

/ 4 [10)

[10]

000059 Accidental Accidental Liquid Liquid RadWaste RadWaste ReI. 2.2.14: Knowledge Knowledge of of the the process process for for 000059 Rel. // 9 [11] X 3.9 39 84 84 controlling controlling equipment equipment configuration configuration or or status.

4.3 (CFR: 41.10/43.3/4 41.10/43.3/45.13) 5.13) 000060 Accidental 000060 Accidental Gaseous Gaseous Radwaste Radwaste ReI. Rel. // 9 [12]

000061 000061 ARM System Alarms ARM System Alarms /7 / 7 [13]

[13]

000067 000067 Plant Plant Fire Fire On-site On-site // 88 [14]

[14]

000068 000068 (BW/A06)

(BW/A06) Control Control Room Room Evac.

Evac. // 88 [15]

[15]

000069 000069 (W/E1 (W/E14)4) Loss Loss of of CTMT CTMT Integrity Integrity // 55 [16]

[16]

000074 2.4.21: Knowledge 2.4.21: Knowledge of of the the parameters parameters and and logic logic 000074 (W/E06&E0 (W/E06&E07) 7) mad.

Inad. Core Core Cooling Cooling // 44 [17]

[17] X X 4.0 4.0 85 85 used to used to assess assess the the status status ofof safety safety functions, functions, such as such as reactivity reactivity control, control, core core cooling cooling and and 44.6 6

heat removal, heat removal, reactor reactor coolant coolant system system integrity, integrity, containment conditions, containment conditions, radioactivity radioactivity release release control, etc.

control, (CFR: 41.7/43.5/45 etc. (CFR: 41.7/43.5/45.12).12) 000076 000076 High High Reactor Reactor Coolant Coolant Activity Activity // 99 [18]

[18]

W/EO1 W/E01 &

& E02 E02 Rediagnosis Rediagnosis &&SI SI Termination Termination // 33 [19] [191 W/E13 Steam W/E13 Steam Generator Generator Over-pressur Over-pressure e // 44 [20]

[20]

W/E15 Containment Flooding/5 W/E15 Containment Flooding / 5 [21] [21]

W/E16 W/E16 High High Containment Radiation // 99 Containment Radiation [22]

[22]

K/A KIA Category Category Point PointTotals:

Totals: I I J

= = 2 22 2, J Group Point Group PointTotal:

Total: 44

ES-401 ES-401 4 SRO 4-SRO

- Form Form ES-401-2 ES-401-2 ES-401 ES-401 PWR PWR Examination Examination Outline Outline Form Form ES-401-2 ES-401-2 Plant SSystems Plant Tier 2/Group stems - Tier

- 2/Group 1*(RO 1 (RO // SRO)

SRO)

System ##1/ Name System Name KK KK KK KK K K K K AA AA AA AA GG KIA K/A Topic(s)

Topic(s) IR IR ##

11234561234 2 3 4 5 6 1 2 3 4 A2.03: Ability A2.03: Ability toto (a)

(a) predict predict the the impacts impacts of of 003 Reactor 003 Reactor Coolant Coolant Pump Pump [1] [1] XX the following malfunctions 2.7 86 the following malfunctions or or operations operations 2.7 86 on on the PS; and the PSi and (b)

(b) based based on on those those 3.1 31 predictions, predictions, useuse procedures procedures to to correct, correct, control, control, or or mitigate mitigate the the consequences consequences of of those malfunctions or those malfunctions or operations:

operations:

Problems Problems associated associated withwith RCP RCP motors, motors, including including faulty faulty motors motors andand current, current, and and winding andand bearing temperature temperature problems.

problems.

(CPR:

(CFR: 41.5 41.5 // 43.5 43.5 // 45.3/45.13) 45.3 / 45.13) 004 Chemical 004 Chemical and and Volume Volume Control [21 Control [2]

005 Residual 005 Residual Heat Heat Removal Removal [3] [3]

006 Emeraency 006 Emergency Core CoolinQ Cooling [4][4]

007 Pressurizer 007 Pressurizer Relief/Quench Relief/Quench Tank[5]

Tank [5]

008 Component Cooling 008 Component Cooling Water [6]

A2.03: Ability to to (a)

(a) predict predict the the impacts impacts ofof 010 Pressurizer 010 Pressurizer Pressure Pressure Control X the following malfunctions or 4.1 89 89 or operations operations

[7]

[7]

on on the the PZR PCS; and (b) based on those 4.2 predictions, use procedures to correct, predictions, use procedures to correct, control, or control, or mitigate mitigate the consequences of the consequences of those those malfunctions malfunctions or or operations:

operations: PORV Failures.

Failures.

012 012 Reactor Reactor Protection[8]

Protection(8]

Ability to 2.1.7: Ability 2.1.7: to evaluate evaluate plant plant 013 Engineered Safety Features 013 Engineered Safety X performance and performance and make make operational operational 4.4 87 Actuation Actuation [9]

[9]

judgments based on operating judgments based on operating 4.7 characteristics, characteristic reactor behavior s, reactor behavior and and instrumentation instrumentat interpretation..

ion interpretation (CPR: 41.5/43.5/45.12/45.13)

(CFR: 41.5/43.5/45.12/45.13) 022 Containment 022 Containment Cooling CoolinQ [10]

[101 025 025 Ice Ice Condenser Condenser [11][11]

026 026 Containment Spray [12]

Containment Spray [121 039 039 Main Main and and Reheat Reheat Steam Steam [13][13]

O5gMainFee dwater [14]

059 Main Feedwater [14]

Knowledge of 2.1.27: Knowledge 2.1.27: of system system purpose purpose 061 Auxiliary/Emergency 061 Auxiliary/Emergency X X and/or function.

and/or function. (CFR:

(CPR: 41.7) 41.7) 3.9 3.9 88 88 Feedwater h Feedwater [15] 51 4.0 4.0 062 AC Electrical 062 AC Electrical Distribution Distribution [16]

[16]

063 DC Electrical 063 DC Electrical Distribution Distribution [17]

[17]

064 064 Emergency Emergency Diesel Diesel Generator Generator

[18]

[181 073 Process Radiation 073 Process Radiation Monitoring Monitoring [19]

[19] = = = = = = = =

076 Service 076 ServiceWater Water[201

[201 078 Instrument 078 Instrument Air [21]

Air [21]

103 Containment [221 103 Containment [22] XX 2.4.30: Knowledge 2.4.30: Knowledgeof ofevents eventsrelated relatedto to 2.7 2.7 90 90 system systemoperation/status operation/statusthat thatmust must be be 4.1 4.1 reported reported to to internal internalorganizations organizations or or external external agencies, agencies, such such as as the the State, State, the the NRC, or NRC, or the the transmission transmission system system operator.

operator. (CPR:

(CPR: 41.10/43.5/45.11) 41.10/43.5/45.11)

K/A Category KIA Category Point Totals Point Totals: =

= I I 221 i 33 I Group Group Point Point Total:

Total 55

=

ES-401 ES-401 5 SRO 5-SRO

- Form Form ES-401-2 ES-401-2 ES-401 ES-401 PWR Examination PWR Examination Outline Form Outline Form ES-401-2 ES-401-2 Plant SSystems Plant Tier 21GroLlp stems - Tier 2/Group 22 (RO (RO // SROt SRO)

System ##1 System Name

/ Name KK KK KK KK KK KK AA AA AA AA GG KIA K/A Topic(s)

Topic(s) IRIR ##

2 3 4 5 61234 112345 6 1 2 3 4 001 Control 001 Control Rod Rod Drive Drive [1] (1]

002 Reactor 002 Reactor Coolant Coolant [2] [2) XX 2.2.40:

2240: Ability Ability to to apply apply Technical Technical 3.4 3.4 91 91 Specifications Specifications for for aa system.

system. (CPR:

(CFR: 4.7 4.7 41.10/43.2/43.5/45.3) 41.10/43.2/43.5/45.3) 011 Pressurizer 011 Pressurizer Level Level Control Control [3] 13] XX 2.4.50:

2.4.50: Ability Ability toto verify verify system system alarm alarm 4.2 4.2 92 92 setpoints setpoints and and operate operate controls controls identified identified in in 4.0 40 the the alarm alarm response response manual.

manual. (CPR:

(CFR:

41.10/43.5/45.3) 41.10/43.5/45.3) 014 Rod 014 Rod Position Position Indication Indication [4] [4]

015 Nuclear 015 Nuclear Instrumentation Instrumentation [51 [5) 016 Non-nuclear 016 Non nuclear Instrumentation Instrumentation

[6]

[6]

017 In-core 017 In-core Temperature Temperature Monitor Monitor

[7]

[7]

027 Containment 027 Containment Iodine Iodine Removal Removal

[8]

[81 028 Hydrogen 028 Hydrogen Recombiner Recombiner and Purge and Purge Control Control [9] [9]

029 Containment 029 Containment Purge Purge [10] (10) 033 Spent 033 Spent Fuel Fuel Pool Pool Cooling Cooling [11]

034 034 Fuel Fuel Handling Handling Equipment Equipment (12] [12]

035 035 Steam Steam Generator Generator [13] [131 041 041 Steam Steam Dump/Turbi DumplTurbine ne Bypass Bvpass Control Control [141[14) 045 045 Main Main Turbine Turbine Generator Generator [15] [15]

055 055 Condenser Condenser Air Air Removal Removal (16] [16]

056 056 Condensate Condensate [17) [171 068 Liquid Radwaste 068 Liquid Radwaste [18] [18]

071 071 Waste Waste GasGas Disposal Disposal [19] [19] XX Knowledge of 2.2.25: Knowledge 2.2.25: of the the bases bases inin Technical Technical 3.2 93 3.2 93 Specifications Specification for limiting s for limiting conditions conditions for for 4.2 4.2 operations and operations and safety safety limits.

limits. (CFR:

(CPR:

41.5/41.7/43.2) 41.5/41.7/43 .2) 072 072 Area Area Radiation Radiation Monitoring Monitoring

[20]

[201 075 Circulating 075 CirculatingWater Water [21] [21]

079 Station Air 079 Station Air [22)

[22]

086 086 Fire Protection [23)

Fire Protection [23]

== J Jj K/A VIA Category

~ Point

.~ ..Totals:

~.

3 Group Group Point PointTotal:

Total: 33

ES-401 ES-401 Generic Knowledge and Abilities Generic Knowledge and Abiliti esOutline Outline(Tier (Tier3)3)- SRO

- SRO Form Form ES-401-3 ES-401-3 I Facility:

Facility: 1f*6.l2.objr'\~

(2.Oh((Y.,OYt DateofofExam:

Date Exam:

Category Category K/A##

KIA Topic Topic RO SRO-Only AC SRO-Only IR IA ## IR IA ##

2. 1.41 2.1.41 Knowledgeof Knowledge ofthetherefueling refuelingprocess.

process. 2.8 94 2.8 94 (CFR: 41.2/41.10/43.6/45.l3)

(CFR: 41.2/41.10/43.6/45.13) 3.7 1.1 Conduct Conduct 2.1.

2.1.

of Operations of Operations 2.1.

2.1.

2.1.

2.1.

2.1.

2.1.

Subtotal Subtotal 2.2.18 2.2.18 Knowledge of Knowledge the process of the process for for managing managing maintenance maintenance 2.6 2.6 95 95 activities during activities during shutdown shutdown operations, operations, such such as as risk risk 3.9 3.9 assessments, work assessments, work prioritization, prioritization, etc.

etc.

2.

2:

Equipment (CFR: 41.10/43.5/45.l3)

(CFR: 41.10/43.5/45.13)

Equipment Control Control 2.2.15 2.2.15 Ability to Ability to determine the the expected plant plant configuration using 3.9 96 using 3.9 96 design and configuration control documentation, design documentation, such as 4.3 4.3 drawings, line-ups, tag-outs, etc. (CFR: 41.10/ 43.3/45.l3) 43.3/45.13) 2.2.36 2.2.36 Ability to analyze the effect of maintenance activities, such 3.1 3.1 97 97 as degraded power sources, on the status of limiting 4.2 4.2 conditions for operations. (CFR: 41.10/ 3.2/45.l3) 3.2/45.13) 2.2.

2.2.

2.2.

2.2.

Subtotal Subtotal 2.3.

2.3.

2.3.

2.3.

3.

3. 2.3.

2.3.

Radiation Radiation Control 2.3.

2.3.

Control 2.3.

2.3.

Subtotal Subtotal 2.4.6 2.4.6 Knowledge Knowledge of ofEOP EOP mitigation mitigation strategies.

strategies. 3.7 3.7 98 98 (CFR:41.10/ 43.5/45.13) 4.7 4.7

4. (CFR: 41.10/43.5/45.l3) 4.

Emergency Emergency 2.4.8 2.4.8 Knowledge Knowledge of ofhow how abnormal abnormal operating operating procedures procedures are are used used 3.8 99 3.8 99 Procedures Procedures// in inconjunction conjunctionwithwithEOPs.

EOPs. (CFR:

(CFR: 41.10/43.5/4

41. 10/43.5/45. l3) 5.13) 4.5 4.5 Plan Plan Knowledge Knowledge of thespecific ofthe specificbases bases for for EOPs.

EOPs.

22.4.18 4 18 33.3 3 100 100 (CFR:41.10/ 43.1/45.13)

(CFR: 41.10/43. 1145. l3) 4.0 4.0 2.4.

2.4.

2.4.

2.4.

Subtotal Subtotal Tier3PointTo tal Tier 3 Point Total 77

ES-401 ES-401 Record of Rejected KI K/As As Form ES-401-4 Tier /I Randomly Selected Reason for Rejection Group K/A KIA RNP does not have indication of individual load amps for RHR Pumps.

111 1/1 000025.AA.2.01 480V loads are provided with bus amperage instead of individual load amperage readings.

1/1 111 000026.02.3.4 000026.G2.3.4 Does not meet NUREG 1021,1021, ES-401, D.l.b D.1.b guidelines.

1/1 III 000058.02. 1.9 000058.G2.1.9 Does not meet NUREG 1021, ES-401, D.l.bD. 1 .b guidelines.

1/2 112 000059.02.3.15 000059.G2.3.15 Does not meet NUREG NLTREG 1021, ES-401, D.l.b D.1.b guidelines.

1/2 000074.02.1.34 000074.G2.1.34 Does not meet NUREG 1021, ES-40 1, D ES-401, .1.b guidelines.

D.1.b

02. 1.40 013. G2.1.40 ESF is defeated when the plant enters Mode 5 and will not actuate during 211 2/1 refueling activities.

211 2/1 061.G2.2.18 Does not meet NUREG 1021, ES-401, D.l.bD.1.b guidelines.

211 2/1 103.G2.3.6 Does not meet NUREG 1021, ES-401, D.l.bD.1.b guidelines.

2/2 212 002.02.1.15 002.G2.1.15 Does not meet NUREG 1021, ES-401, D.l.bD.1.bJ~uidelines.

guidelines.

2/2 212 011.02.3.13 011.G2.3.13 Does not meet NUREG 1021, ES-401, D.l.bD.1.b guidelines.

Replaced by Chief Examiner during question discussion at Region. KA 1/2 112 000059.02.4.4 000059.G2.4.4 combination does not allow for a discriminating SRO level question.

(Replaced with 000059.G2.2.14) 000074.02.2.42 000074.G2.2.42 Replaced by Chief Examiner during question discussion at Region. KA 1/2 combination does not allow for a discriminating SRO level question.

(Replaced with 000074.G2.4.21) 000074.02.4.21) 007 A2.03 Replaced by Chief Examiner during question discussion at Region. KA 211 2/1 combination does not allow for a discriminating SRO level question.

(Replaced with 003.A2.03) 078 A2.01 Replaced by Chief Examiner due to high number of Instrument Air 211 2/1 questions on exam. (Replaced with 010.A2.03) 01O.A2.03)