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 PWR Examination Outline -RO Form ES-401-2 II Facility:

Rob lV\soY'\ Date of Exam: RO KJA Catecorv 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 2 2 2 4 4 4 18 6 Emergency

& Abnormal 2 2 2 1 N/A 1 1 N/A 2 9 4 Plant Evolutions Tier Totals 4 4 3 5 5 6 27 10 1 3 3 3 2 2 3 2 2 3 2 3 28 5 2. Plant 2 3 1 1 1 0 1 0 1 0 2 0 10 3 Systems Tier Totals 6 4 4 3 2 4 2 3 3 4 3 38 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 Note: 1. Ensure that at least two topics from every applicable KJA 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 KJA 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 KJA 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 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 KJA categories.

7.* The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJAs. 8. On the following pages, enter the KJA 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 KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KJ As that are linked to 10 CFR 55.43.

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

-Tier 1/Group 1 (RO I SRO) E/APE # I Name I Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000007 (BW/E02&E10; CElE02) Reactor Trip -Stabilization

-Recovery I 1 r1] 000008 Pressurizer Vapor Space X AKI.OI Knowledge of the operational implications of 3.2 1 Accident/3

[2] the following concepts as they apply to a Pressurizer 3.7 Vapor Space Accident:

Thermodynamics and flow characteristics of open or leaking valves. 000009 Small Break LOCA I 3 r3] 000011 Large Break LOCA I 3 [4] X EA1.12: Ability to operate and monitor the following 4.1 2 as they apply to a Large Break LOCA: Long-term 4.4 containment of radioactivity.

000015/17 RCP Malfunctions I 4 [5] X AK2.10: Knowledge of the interrelations between the 2.8 3 Reactor Coolant Pump Malfunctions (Loss of RC 2.8 Flow) and the following:

RCP indicators and controls.

000022 Loss of Rx Coolant Makeup I 2 [6] X AA1.OI: Ability to operate and / or monitor the 3.4 4 following as they apply to the Loss of Reactor Coolant 3.3 Makeup: CVCS letdown and charaing.

000025 Loss of RHR System I 4 [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 Removal System: Existence of proper RHR overpressure protection.

000026 Loss of Component Cooling X AAI.02: Ability to operate and / or monitor the 3.2 6 Water I 8 [8] following as they apply to the Loss of Component 3.3 Cooling Water: Loads on the CCWS in the control room. 000027 Pressurizer Pressure Control System Malfunction I 3 [9] 000029 A TWS I 1 [10] X 2.1.28: Knowledge of the purpose and function of 4.1 7 major system components and controls.

4.1 000038 Steam Gen. Tube Rupture 13 [11 ] X 2.1.20: Ability to interpret and execute procedure 4.6 8 steps. 4.6 000040 (BW/E05; CE/E05; W/E12) X AA1.02: Ability to operate and / or monitor the 4.5 9 Steam Line Rupture -Excessive Heat following as they apply to the Steam Line Rupture: 4.5 Transfer I 4 [12] Feedwater isolation.

000054 (CE/E06) Loss of Main X AA1.02: Ability to operate and / or monitor the 4.4 10 Feedwater I 4 [13] following as they apply to the Loss of Main Feedwater

4.4 (MFW)

Manual startup of electric and steam-driven AFWpumps.

000055 Station Blackout I 6 [14] 000056 Loss of Off-site Power I 6 [15] X AA2.67: Ability to determine and interpret the 2.9 11 following as they apply to the Loss of Offsite Power: 3.1 Seal injection flow (for the RCPs). 000057 Loss of Vital AC Inst. Bus I 6 [16] X 2.2.22: Knowledge of limiting conditions for 4.0 12 operations and safety limits. 4.7 000058 Loss of DC Power 16 [17] X 2.2.36: Ability to analyze the effect of maintenance 3.1 13 activities, such as degraded power sources, on the 4.2 status of limiting conditions for operations.

000062 Loss of Nuclear Svc Water/4 [18] X AK3.02: Knowledge of the reasons for the following 3.6 14 responses as they apply to the Loss of Nuclear Service 3.9 Water: The automatic actions (alignments) within the nuclear service water resulting from the actuation ofthe ESFAS. 000065 Loss of Instrument Air I 8 [19] X AA2.05: Ability to determine and interpret the 3.4 15 following as they apply to the Loss of Instrument Air: When to commence plant 4.1 shutdown if instrument air pressure is decreasin cr* W/E04 LOCA Outside ContainmenV3

[20] X EK3.1: Knowledge of the reasons for the following 3.2 16 responses as they apply to the (LOCA Outside 3.5 Contaimnent):

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

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

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

BW/E04; W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sinkl4 [22J 000077 Generator Voltage and Electric X AK2.06: Knowledge of the interrelations between 3.9 18 Grid Disturbances I 6 [23] Generator Voltage and Electric Grid Disturbances 4.0 and the following:

Reactor J.lower. II KIA Category Totals: 2 2 2 5 3 4 Group Point Total: 1 ES-401 3-RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2 (RO / SRO) E/APE # / Name / Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 [1] X AK2.08: Knowledge of the interrelations 3.1 19 between the Continuous Rod Withdrawal and 3.0 the following:

Individual rod display lights and indications.

000003 Dropped Control Rod / 1 [2] 000005 Inoperable/Stuck Control Rod / 1 [3] X AK3.0l: Knowledge of the reasons for the 4.0 20 following responses as they apply to the 4.3 Inoperable I Stuck Control Rod: Boration and emergency boration in the event of a stuck rod during trip or normal evolutions.

000024 Emergency Soration / 1 [4] 000028 Pressurizer Level Malfunction / 2 [5] X 2.4.4: Ability to recognize abnormal 4.5 21 indications for system operating parameters 4.7 that are entry-level conditions for emergency and abnormal operating procedures.

000032 Loss of Source Range NI /7 [6] X AK1.Ol: Knowledge of the operational 2.5 22 implications of the following concepts as they 3.1 apply to Loss of Source Range Nuclear Instrumentation:

Effects of voltage changes on performance.

000033 Loss of Intermediate Range NI /7[7] 000036 (SW/A08) Fuel Handling Accident /8 [8] 000037 Steam Generator Tube Leak / 3 [9] X AA1.06: Ability to operate and I or monitor 3.8 23 the following as they apply to the Steam 3.9 Generator Tube Leak: Main steam line rad monitor meters. 000051 Loss of Condenser Vacuum /4 [10] 000059 Accidental Liquid RadWaste ReI. / 9 [11] 000060 Accidental Gaseous Radwaste ReI. / 9 [12] 000061 ARM System Alarms / 7 [13] 000067 Plant Fire On-site / 8 [14] 000068 (SW/A06) Control Room Evac. / 8 [15] X AA2.05: Ability to determine and interpret 4.2 24 the following as they apply to the Control 4.3 Room Evacuation:

Availability of heat sink. 000069 (W/E14) Loss of CTMT Integrity / 5 [16] X AK1.0l: Knowledge ofthe operational 2.6 25 implications of the following concepts as they 3.1 apply to Loss of Contaimuent Integrity:

Effect of pressure on leak rate. 000074 (W/E06&E07)

Inad. Core CoolinQ / 4 [17] 000076 High Reactor Coolant Activity / 9 [181 W/E01 & E02 Rediagnosis

& SI Termination

/3[19] W/E13 Steam Generator Over-pressure

/4 [20] X EK2.2: Knowledge of the interrelations 3.0 26 between the (Steam Generator Overpressure) and the following:

Facility*s heat removal 3.2 systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

W/E15 Containment Flooding I 5 [21] X 2.2.38: Knowledge of conditions and 3.6 27 limitations in the facility license. 4.5 W/E16 High Containment Radiation I 9 [22] BW/A01 Plant Runback 11 [23] BW/A02&A03 Loss of NNI-X/Y I 7 [24] BW/A04 Turbine Trip I 4 [25] BW/A05 Emergency Diesel Actuation I 6 [26] BW/A07 Flooding I 8 [27] BW/E03 Inadequate Subcooling Margin 14[281 BW/E08; W/E03 LOCA Cooldown -

14[29] BW/E09; CElA13; W/E09&E10 Natural Circ. I 4 [30] BW/E13&E14 EOP Rules and Enclosures

[31] CEI A 11; W IE08 RCS Overcooling

-PTS I 4 [32] CE/A16 Excess RCS Leakage I 2 [33] CE/E09 Functional Recovery [34] KIA Category Point Totals: 2 2 1 1 1 2 Group Point Total: 9 ES-401 4-RO Form ES-401-2 r;;:01 PWR Examination Outline Plant S stems -Tier 21Group 1 (RO / SRO) Form ES-401-2 System # / Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump [1] X K6.04: Knowledge of the effect of a loss or 2.8 28 malfunction on the following will have on 3.1 the RCPS: Containment isolation valves affecting RCP operation.

004 Chemical and Volume X Al.05: Ability to predict and/or monitor 2.9 29 Control [2] changes in parameters (to prevent 3.2 exceeding design limits) associated with operating the CVCS controls including:

S/G pressure and level. 005 Residual Heat Removal [3] X Kl.06: Knowledge of the physical 3.5 30 connections and/or cause-effect 3.6 relationships between the RHRS and the followin2 systems: ECCS. 006 Emergency Core Cooling [4] X K2.01: Knowledge of bus power supplies 3.6 31 to the followin2:

ECCS pumps. 3.9 007 Pressurizer Relief/Quench X K4.01: Knowledge ofPRTS design 2.6 32 Tank [5] feature(s) and/or interlock(s) which 2.9 provide for the following:

Quench tank cooling. 008 Component Cooling Water [6] X A4.05: Ability to manually operate and/or 2.7 33 monitor in the control room: Normal 2.5 CCW-header total flow rate and the flow rates to the components cooled by the CCWS. 010 Pressurizer Pressure Control X K5 .01: Knowledge of the operational 3.5 34 [7] implications of the following concepts as 4.0 the apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables. 012 Reactor Protection[8]

X K6.01: Knowledge of the effect of a loss or 2.8 35 malfunction of the following will have on 3.3 the RPS: Bistables and bistable test equipment.

013 Engineered Safety Features X 2.2.38: Knowledge of conditions and 3.6 36 Actuation

[9] limitations in the facility license. 4.5 022 Containment Cooling [10] X A3.01: Ability to monitor automatic 4.1 37 operation of the CCS, including:

Initiation 4.3 of safeguards mode of operation.

025 Ice Condenser

[11] REJECTED AI .01: Ability to predict and/or monitor 026 Containment Spray [12] X changes in parameters (to prevent 3.9 38 exceeding design limits) associated with 4.2 operating the CSS controls including:

Containment pressure.

039 Main and Reheat Steam [13] X 2.4.20: Knowledge of the operational 3.8 39 implications of EOP warnings, cautions, 4.3 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. 3.4 063 DC Electrical Distribution

[17] X K3.02: Knowledge of the effect that a loss 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

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.. t h.; .* I';.' ; .. ;sw. '; I. 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. 103 Containment K3.01: Knowledge of the effect that a loss 48 [22] X or malfunction of the containment 3.3 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 3.1 51 039 Main and Reheat Steam [25] X connections and/or cause-effect 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 Spray [28] X A2.04: Ability to (a) predict the impacts of 3.9 54 the following malfunctions or operations 4.2 on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of spray pump. 064 Emergency Diesel Generator X K6.07: Knowledge of the effect of a loss or 2.7 55 [29] malfunction of the following will have on 2.9 the ED/G system: Air receivers. I I KJA Category Point Totals: 3 3 3 2 2 3 2 2 3 2 3 Group Point Total: 28 ES-401 5-RO Form ES-401-2 ES-401 PWR Examination Outline r. Plant S stems -Tier 21Group 2 (RO / SRO) System # / Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive [1] 002 Reactor Coolant [2] X K6.07: Knowledge of the effect or a loss or 2.5 56 malfunction on the following RCS 2.8 components:

Pumps. 011 Pressurizer Level Control [3] 014 Rod Position Indication

[4] X Kl.Ol: Knowledge of the physical 3.2 57 connections and/or cause-effect relationships 3.6 between the RPIS and the following systems: CRDS. 015 Nuclear Instrumentation

[5] X K4.01: Knowledge of NIS design feature(s) 3.1 58 and/or interlock(s) provide for the following:

3.3 Source-Range detector power shutoff at high powers. 016 Non-nuclear Instrumentation

[6] 017 In-core Temperature Monitor X K3.01: Knowledge of the effect that a loss or 3.5 59 [7] malfunction of the ITM system will have on 3.7 the following:

Natural circulation indications.

027 Containment Iodine Removal X Kl.OI: Knowledge of the physical 3.4 60 [8] connections and/or cause-effect relationships 3.7 between the CIRS and the following systems: CSS. 028 Hydrogen Recombiner and Purge Control [9] 029 Containment Purge [10] 033 Spent Fuel Pool Cooling [11] 034 Fuel Handling Equipment

[12] X A4.02: Ability to manually operate and/or 3.5 61 monitor in the control room: Neutron levels. 3.9 035 Steam Generator

[13] X A2.06: Ability to (a) predict the impacts of 4.5 62 the following malfunctions or operations on 4.6 the SG; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Small break LOCA. 041 Steam Dump/Turbine X A4.06: Ability to manually operate and/or 2.9 63 Bypass Control [14] monitor in the control room: Atmospheric 3.1 relief valve controllers.

K1.I8: Knowledge of the physical 3.6 64 045 Main Turbine Generator

[15] X connections and/or cause-effect relationships between the MT/G system and the following

3.7 systems

RPS. 055 Condenser Air Removal [16] 056 Condensate

[17] 068 Liquid Radwaste [18]

071 Waste Gas Disposal [19] 072 Area Radiation Monitoring

[20] 075 Circulating Water [21] X K2.03: Knowledge of bus power supplies to 2.6 65 the following:

Emergency/essential SWS 2.7 pumps. 079 Station Air [22] 086 Fire Protection

[23] VIA 1"'. 3 1 I I 0 I 0 1 0 2 Group Point Total: 10 ES-401 Generic Knowledge and Abilities Outline (Tier 3) -RO Form ES-401-3 RoloiflsOVl Date of Exam: Category KIA # Topic RO SRO-Only IR # IR # 2.1.26 Knowledge of industrial safety procedures (such as rotating 3.4 66 3.6 equipment, electrical, high temperature, high pressure, 1. caustic, chlorine, oxygen and hydrogen).

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

2.1. 2.1.

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

2. 2.2.40 Ability to apply Technical Specifications for a system. 3.4 69 4.7 Equipment 2.2. Control 2.2. 2.2. Subtotal 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 70 3.7 emergency conditions.

3. 2.3.13 Knowledge of radiological safety procedures pertaining to 3.4 71 3.8 Radiation licensed operator duties, such as response to radiation Control monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. 2.3.7 Ability to comply with radiation work permit requirements 3.5 72 3.6 during normal or abnormal conditions.

2.3. 2.3. Subtotal 2.4.16 Knowledge of EOP implementation hierarchy and 3.5 73 4.4 coordination with other support procedures or guidelines

4. such as, operating procedures, abnormal operating Emergency procedures, and severe accident management guidelines.

Procedures

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

2.4.23 Knowledge of the bases for prioritizing emergency 3.4 75 4.4 procedure implementation during emergem:y operations.

2.4. 2.4. Subtotal Tier 3 Point Total 10 ES-401 Record of Rejected KI As Form ES-401-4 Tier / Group Randomly Selected Reason for Rejection KIA 1/1 0OOO29.G2.3.13 Cannot write a quality question concerning radiological actions for an ATWS event. 1/1 OOOOS7.G2.1.41 Does not meet NUREG 1021, ES-401, D.l.b guidelines.

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

1/2 WIE IS. G2.2.38 RNP has no LCO actions for Containment Sump high level addressed in Technical Specifications.

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

211 OS9.A2.07 RNP does not have Turbine Driven Feed Pumps. 2/1 061.A3.04 RNP does not have automatic isolation features for AFW to the S/Gs. 211 076.K4.03 RNP does not have any automatic isolation for the CCW heat exchangers.

212 014.K2.02 RNP does not correct the NIS for power. RPI is an independent system which is temperature corrected only. 211 007.KS.02 RNP does not use the PRT when forming a Steam bubble in the PZR.

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

Date of Exam: RO KIA Cateqory 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 18 3 3 6 Emergency

& Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier Totals 27 5 5 10 1 28 2 3 5 2. Plant 2 10 0 3 3 Systems Tier Totals 38 2 6 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 1 3 0 3 Note: 1. Ensure that at least two topics from every applicable KIA 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 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 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 KIA 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 KlAs 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 shall be selected from Section 2 of the KIA 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 KlAs. 8. On the following pages, enter the KIA 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401 2-SRO Form ES-401-2 ES-401 PWR Examination Outline Form EC' ,,"H " EmerQenc and Abnormal Plant Evolutions

-Tier 1/Group 1 (RO I SRO) ElAPE # I Name I Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000007 (BW/E02&E10; CElE02) Reactor Trip -Stabilization

-Recovery I 1 [1] 000008 Pressurizer Vapor Space X 2.4.11: Knowledge of abnormal condition procedures.

4.0 76 Accident I 3 [2] (CFR: 41.10/43.5/45.13) 4.2 000009 Small Break LOCA I 3 [3] 000011 Large Break LOCA I 3 [4] 000015/17 RCP Malfunctions I 4 [5] 000022 Loss of Rx Coolant Makeup I 2 [6] X AA2.03: Ability to determine and interpret the 3.1 77 following as they apply to the Loss of Reactor Coolant 3.6 Makeup: Failures of flow control valve or controller (CFR: 43.5/45.13) 000025 Loss of RHR System I 4 [7] X AA2.07: Ability to determine and interpret the 3.4 78 following as they apply to the Loss of Residual Heat 3.7 Removal System: Pump Cavitation. (CFR 43.5/45.13) 000026 Loss of Component Cooling X 2.2.38: Knowledge of conditions and limitations in the 3.6 79 Water 18 . [8] facility license. (CFR: 41.7/41.10/43.1/45.13) 4.5 000027 Pressurizer Pressure Control System Malfunction I 3 [91 000029 ATWS I 1 [10] 000038 Steam Gen. Tube Rupture 13 [11 1 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture -Excessive Heat Transfer I 4 [12] 000054 (CE/E06) Loss of Main Feedwater I 4 [13] [14] EA2.01: Ability to determine or interpret the 3.4 80 000055 Station Blackout I 6 X following as they apply to a Station Blackout:

Existing valve positioning on a loss of instrument air system 3.7 (CFR: 43.5 145.13) 000056 Loss of Off-site Power 16 [15] 000057 Loss of Vital AC Inst. Bus I 6 [16] 000058 Loss of DC Power 16 [17] X 2.1.32: Ability to explain and apply system limits and 3.8 81 precautions. (CPR: 41.10/45.5/45.12/45.13) 4.0 000062 Loss of Nuclear Svc Water/4 [18] 000065 Loss of Instrument Air I 8 [19] W/E04 LOCA Outside Containment/3

[20] W/E11 Loss of Emergency Coolant Recirc. I 4 [211 BW/E04; W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sinkl4 [22] 000077 Generator Voltage and Electric Grid Disturbances I 6 [23] KIA CateQory Totals: 3 3 Group Point Total:

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

-Tier 1/Group 2 (RO / SRO) E/APE # / Name / Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 [1] 000003 Dropped Control Rod / 1 [2) 000005 Inoperable/Stuck Control Rod / 1 [3] 000024 Emergency Boration / 1 [4] X AA2.02: Ability to determine and interpret the 3.9 82 following as they apply to the Emergency

4.4 Boration

When use of manual boration valve is needed. (CFR: 43.5 /45.13) 000028 Pressurizer Level Malfunction

/2J5] 000032 Loss of Source Range NI /7 [6] 000033 Loss of Intermediate Range NI /7[7) X AA2.1O: Ability to determine and interpret 3.1 83 the following as they apply to the Loss of 3.8 Intermediate Range Nuclear Instrumentation:

Tech-Spec limits if both intermediate range channels have failed. (CFR: 43.5 /45.13) 000036 (BW/A08) Fuel Handling Accident / 8 f 8] 000037 Steam Generator Tube Leak / 3 [9] 000051 Loss of Condenser Vacuum / 4 [10) 000059 Accidental Liquid RadWaste ReI. / 9 [11] X 2.2.14: Knowledge of the process for 3.9 84 controlling equipment configuration or status. (CFR: 41.10/43.3/45.13) 4.3 000060 Accidental Gaseous Radwaste ReI. / 9 [12] 000061 ARM System Alarms / 7 [13] 000067 Plant Fire On-site / 8 [14] 000068 (BW/A06) Control Room Evac. / 8 [15] 000069 (W /E14) Loss of CTMT Integrity / 5 [16] 000074 (W/E06&E07)

Inad. Core Cooling / 4 [17] X 2.4.21: Knowledge of the parameters and logic 4.0 85 used to assess the status of safety functions, 4.6 such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7/43.5/45.12) 000076 High Reactor Coolant Activity / 9 [18] W/E01 & E02 Rediagnosis

& SI Termination / 3 [191 W/E13 Steam Generator Over-pressure / 4 [20] W/E15 Containment Flooding / 5 [21] W/E16 High Containment Radiation / 9 [22] KIA Category Point Totals: 2 2 Group Point Total: 4 ES-401 4-SRO Form ES-401-2 ES-401 PWR Examination Outline Plant S stems -Tier 2/Group 1*(RO / SRO) Form ES-401-2 System # / Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 A2.03: Ability to (a) predict the impacts of 2.7 86 003 Reactor Coolant Pump [1] X the following malfunctions or operations on the PSi and (b) based on those 3.1 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems. (CPR: 41.5 / 43.5 / 45.3/45.13) 004 Chemical and Volume Control [21 005 Residual Heat Removal [3] 006 Emeraency Core CoolinQ [4] 007 Pressurizer Relief/Quench Tank [5] 008 Component Cooling Water [6] A2.03: Ability to (a) predict the impacts of 4.1 89 010 Pressurizer Pressure Control X the following malfunctions or operations

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

PORV Failures.

012 Reactor Protection(8]

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

[9] judgments based on operating 4.7 characteristics, reactor behavior and instrumentation interpretation. (CPR: 41.5/43.5/45.12/45.13) 022 Containment CoolinQ [101 025 Ice Condenser

[11] 026 Containment Spray [121 039 Main and Reheat Steam [13] 059 Main Feedwater

[14] 2.1.27: Knowledge of system purpose 3.9 88 061 Auxiliary/Emergency X and/or function. (CPR: 41.7) Feedwater h 51 4.0 062 AC Electrical Distribution

[16] 063 DC Electrical Distribution

[17] 064 Emergency Diesel Generator

[181 073 Process Radiation Monitoring

[19]

076 Service Water [201 078 Instrument Air [21] 103 Containment

[221 X 2.4.30: Knowledge of events related to 2.7 90 system operation/status that must be 4.1 reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CPR: 41.10/43.5/45.11)

KIA Category Point Totals: I I 2 3 Group Point Total: 5 ES-401 5-SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems -Tier 21GroLlp 2 (RO / SROt System # / Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive [1] 002 Reactor Coolant [2] X 2.2.40: Ability to apply Technical 3.4 91 Specifications for a system. (CPR: 4.7 41.10/43.2/43.5/45.3) 011 Pressurizer Level Control [3] X 2.4.50: Ability to verify system alarm 4.2 92 setpoints and operate controls identified in 4.0 the alarm response manual. (CPR: 41.10/43.5/45.3) 014 Rod Position Indication

[4] 015 Nuclear Instrumentation

[51 016 Non-nuclear Instrumentation

[6] 017 In-core Temperature Monitor [7] 027 Containment Iodine Removal [81 028 Hydrogen Recombiner and Purge Control

[9] 029 Containment Purge [10] 033 Spent Fuel Pool Cooling [11] 034 Fuel Handling Equipment

[12] 035 Steam Generator

[131 041 Steam DumplTurbine Bvpass Control [141 045 Main Turbine Generator

[15] 055 Condenser Air Removal [16] 056 Condensate

[171 068 Liquid Radwaste [18] 071 Waste Gas Disposal [19] X 2.2.25: Knowledge of the bases in Technical 3.2 93 Specifications for limiting conditions for 4.2 operations and safety limits. (CPR: 41.5/41.7/43.2) 072 Area Radiation Monitoring

[201 075 Circulating Water [21] 079 Station Air [22] 086 Fire Protection

[23] VIA .. ! 3 Group Point Total: 3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) -SRO Form ES-401-3 Facility:

Date of Exam: Category KIA # Topic RO SRO-Only IR # IR # 2.1.41 Knowledge of the refueling process. 2.8 94 (CFR: 41.2/41.10/43.6/45.l3) 3.7 1. Conduct 2.1. of Operations 2.1. 2.1. 2.1. Subtotal 2.2.18 Knowledge of the process for managing maintenance 2.6 95 activities during shutdown operations, such as risk 3.9 assessments, work prioritization, etc. 2: (CFR: 41.10/43.5/45.l3)

Equipment Control 2.2.15 Ability to determine the expected plant configuration using 3.9 96 design and configuration control documentation, such as 4.3 drawings, line-ups, tag-outs, etc. (CFR: 41.10/ 43.3/45.l3) 2.2.36 Ability to analyze the effect of maintenance activities, such 3.1 97 as degraded power sources, on the status of limiting 4.2 conditions for operations. (CFR: 41.10/ 3.2/45.l3) 2.2. 2.2. Subtotal 2.3. 2.3. 3. 2.3. Radiation Control 2.3. 2.3. Subtotal 2.4.6 Knowledge of EOP mitigation strategies.

3.7 98 (CFR: 41.10/43.5/45.l3) 4.7 4. Emergency 2.4.8 Knowledge of how abnormal operating procedures are used 3.8 99 Procedures

/ in conjunction with EOPs. (CFR: 41. 10/43.5/45.

l3) 4.5 Plan 2.4.18 Knowledge of the specific bases for EOPs. 3.3 100 (CFR: 41.10/43.

1145. l3) 4.0 2.4. 2.4. Subtotal Tier 3 Point Total 7 ES-401 Record of Rejected KI As Form ES-401-4 Tier / Randomly Selected Reason for Rejection Group KIA 111 000025.AA.2.01 RNP does not have indication of individual load amps for RHR Pumps. 480V loads are provided with bus amperage instead of individual load amperage readings.

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

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

112 000059.G2.3.15 Does not meet NUREG 1021, ES-401, D.l.b guidelines.

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

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

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

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

212 002.G2.1.15 Does not meet NUREG 1021, ES-401, D.l.b 212 011.G2.3.13 Does not meet NUREG 1021, ES-401, D.l.b guidelines.

Replaced by Chief Examiner during question discussion at Region. KA 112 000059.G2.4.4 combination does not allow for a discriminating SRO level question. (Replaced with 000059.G2.2.14) 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) 007 A2.03 Replaced by Chief Examiner during question discussion at Region. KA 211 combination does not allow for a discriminating SRO level question. (Replaced with 003.A2.03) 211 078 A2.01 Replaced by Chief Examiner due to high number of Instrument Air questions on exam. (Replaced with 01O.A2.03)