ML031210716

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Final - Outlines (Change Summaries - Optional)
ML031210716
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 04/01/2003
From: Wilson F
Entergy Nuclear Northeast
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-286/03-301 50-286/03-301
Download: ML031210716 (37)
v • d • e


Text

IP3 written changes 2/12 C4 Corrected right answer, changed distractor B C6 Stem wording enhance C9 Stem wording enhance C13 Replaced with new KA. Too easy. Used Vendor Bank Modified Comprehension level question.

C19 Minor stem enhance C20 Minor stem enhance C21 Minor stem enhance C22 Minor stem enhance C24 Minor stem enhance C25 Minor stem enhance C26 Minor stem enhance C30 Enhance C32 Modified to increase knowledge required C37 Enhance C45 Enhance C47 Enhance C51 Enhance C56 Enhance R74 Enhance distractor A R78 Enhance distractor A R80 Enhance distractor D R81 Replaced, too easy, used modified bank question

R84 Replaced KA. New question is facility bank memory R88 Enhance R93 Replaced question, same KA R100 Enhanced S73 Enhanced distractor C S78 Enhanced S81 Change stem and add full ref for handout S95 Enhance S97 Enhance distractor A S99 Enhance distractor B S100 Changed due to being too close to Audit written question. Premise is same, answer is different IP3 Written changes completed 2/27/2003 Cl Modified stem to change answer C2 Changed all distractors and correct answer C3 Changed conditions in stem to change correct answer C4 Changed question. Used Vendor Bank question C5 Changed question. Used Vendor Bank question C6 Changed question. Used Vendor Bank question C7 Changed conditions and distractors to yield different answer C8 Changed question. Used Modified Facility Bank question C9 Changed question. Developed new question CIO Changed conditions to change answer

CH1 Changed context of question, same topic C12 Changed distractors and answer. Same topic C13 Changed question based on NRC feedback. This item was NOT compromised and was not replaced with the 2/27 changes.

C14 Changed conditions to change answer C15 Changed context. Same topic C16 Changed correct answer to another selection C17 Changed question. Used Modified Facility Bank question C 18 Changed question. Changed context same topic C 19 Changed conditions to change correct answer C20 Changed conditions to change correct answer C2 1 Changed conditions and distractors to change correct answer C22 Changed context. Same topic C23 Changed question. New question C24 Changed question. Used IP2 same topic C25 Changed question. New KA topic selected, used Vendor Bank question

ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Indian Point 2 & 3 Date of Exam: 3/8/2003 Exam Level: RO K/A Category Point Point Tier Group K l K K K IK A A A A G Total l1 2 3 4 5 l6 1 2 3 4 *l 1 4 0 3 4 5 0 16 1.

Emergency & 2 1 2 3 _ 5 4 2 17 Abnormal Plant 3 0 0 1 0 1 1 3 Evolutions Tier Totals 5 2 7 9 10 3 36 1 3 02 3 11 1 4 3 1 23 Plant 2 4 2 3 2 1 13 1 1 1 2 20 Systems 3 0 1 2 0 0 1 1 1 1 1 0 8 Totals 7 3 5 7 4 5 5 3 6 5 3 51

3. Generic Knowledge and Abilities Cat 1l Cat2 { Cat3 Cat4 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by

+/- 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/A's below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

IP 2 & 3 - RO Outline Rev O.doc Page 1 of 14 NUREG-1021, Revision 8, Supplement 1

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE#/NamelSafetyFunction K1 K2 K3 Al A2 G Number K/A Topic(s) Imp. Q#

00005 Inoperable/Stuck Control Rod /I X AK1.03 Knowledge of the operational implications of the following 3.2 41 concepts as they apply to the stuck rod: Xenon transient.

000015/17 RCP Malfunctions / 4 X AA1.22 Ability to operate and/or monitor the following as they apply to 4.0 52 the RCP malfunctions: RCP seal failure/malfunction BW/E09; CE/Al 3; W/E09 & 10 Natural Circ./ 4 X EK3.1 Knowledge of the reasons for the following responses as they 3.3 42 apply to the (Natural Circulation Operations): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

000024 Emergency Boration /1 X AA2.04 Ability to determine and interpret the following as they apply to 3.4 43 the Emergency Boration: Availability of BWST.

000026 / Loss of Component Cooling Water / 8 X AK3.03 Knowledge of the reasons for the following responses as they 4.0 44 apply to the Loss of Component Cooling Water: Guidance and actions contained in EOP for Loss of CCW/Nuclear Service Water.

000027 / Pressurizer Pressure Control System _X A2. 15 Ability to determine and interpret the following as they apply to 3.7 45 Malfunction / 3 the Pressurizer Pressure Control Malfunctions: Actions to be I taken if PZR pressure instrument fails high.

000040 (BW/E05; CE/E05; W/E12) / Steam Line X AK1.06 Knowledge of the operational implications of the following 3.7 46 Rupture - Excessive Heat Transfer / 4 concepts as they apply to Steam Line Rupture: High-energy steam line break considerations.

000040 (BW/E05; CE/EO5; W/E12) / Steam Line X EA1.2 Ability to operate and/or monitor the following as they apply to 3.6 47 Rupture - Excessive Heat Transfer / 4 the (Uncontrolled Depressurization of all Steam Generators):

Operating behavior characteristics of the facility.

CE/Al 1; W/E08 / RCS Overcooling - PTS /4 000051 / Loss of Condenser Vacuum / 4 X AA1.04 Ability to operate and / or monitor the following as they apply to 2.5 48 the Loss of Condenser Vacuum: Rod position.

000055 / Station Blackout / 6 X EA2.01 Ability to determine or interpret the following as they apply to a 3.4 49 Station Blackout: Existing valve positioning on a loss of instrument air system.

000057 / Loss of Vital AC Elec. Inst. Bus / 6 X AK3.01 Knowledge of the reasons for the following responses as they 4.1 50 apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.

000062 / Loss of Nuclear Service Water /4 X AA2.01 Ability to determine and interpret the following as they apply to 2.9 51 the Loss of Nuclear Service Water: Location of a leak in the CCWS.

000067 / Plant Fire On-site / 9 _ _ . .___

000068 (BW/A06) / Control Room Evac. /8 _ _ _ ..

000069 (W/E14) / Loss of CTMT Integrity /5 _ _ e _ _ _

NUREG-1021, Revision 8, Supplement 1 Page 2 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # Name / Safety Function KI K2 K3 Al A2 G Number K/A Topic(s) Imp.

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EK1.05 Knowledge of the operational implications of the following 2.8 53 concepts as they apply to the Inadequate Core Cooling:

Definition of saturated liquid.

000074 (W/EO6 & E07) /Inad. Core Cooling / 4 X EK1.3 Knowledge of the operational implications of the following 3.7 54 concepts as they apply to the (Degraded Core Cooling):

Annunciators and conditions Indicating signals, and remedial actions associated with the (Degraded Core Cooling).

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EA1.2 Ability to operate and/or monitor the following as they apply to 3.2 55 the (Saturated Core Cooling): Operating behavior characteristics of the facility.

BW/E03 / Inadequate Subcooling Margin /4 =4=_=_=_=_=

000076 / High Reactor Coolant Activity /9 X AA2.02 Ability to determine and interpret the following as they apply to 2.8 56 the High Reactor Coolant Activity: Corrective actions required for high fission product activity in RCS.

BW/A02 & A03 / Loss of NNI-X/Y /7 K/A Category Point Totals: 4 0 3 4 5 0 Group Point Total: 16 NUREG-1021, Revision 8, Supplement 1 Page 3of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE #Name / Safety Function KI K2 K3 Al A2 G Number lKA Topic(s) Imp. l 000001 Continuous Rod Withdrawal /1 _ X AA1.05 Ability to operate and I or monitor the following as they apply to 4.3 57 l_ _ _the Continuous Rod Withdrawal: Reactor trip switches.

000003 / Dropped Control Rod / 1 X AK2.05 Knowledge of the Interrelations between the Dropped Control 2.5 58 Rod and the following: Control rod drive power supplies and logic circuits.

000007 (BW/E02 & El0; CE/EO2) / Reactor Trip -

Stabilization - Recovery / 1 BW/A01 / Plant Runback / 1 BW/A04 / Turbine Trip / 4I 000008 / Pressurizer Vapor Space Accident /3 X AK2.02 Knowledge of the interrelations between the Pressurizer Vapor 2.7 59 Space Accident and the following: Sensors and detectors.

000009 / Small Break LOCA / 3 X EA1.18 Ability to operate and monitor the following as they apply to a 3.4 60 small break LOCA: Balancing of HPI loop flows.

000011 / Large Break LOCA 13 X EA1.01 Ability to operate and monitor the following as they apply to a 3.7 61 Large Break LOCA: Control of RCS pressure and temperature to avoid violating PTS limits.

W/E04 / LOCA Outside Containment /3 X EK1.3 Knowledge of the operational implications of the following 3.5 97 concepts as they apply to the (LOCA Outside Containment):

Annunciators and conditions indicting signals, and remedial

__ actions associated with the (LOCA Outside Containment).

BW/E08; W/E03 / LOCA Cooldown / Depress. / 4 _

W/E1 1 / Loss of Emergency Coolant Recirc. /4 WE/01 & 02 / Rediagnosis & SI Termination /3 X EK3.2 Knowledge of the reasons for the following responses as they 3.0 62 apply to the Reactor Trip or Safety Injection/Rediagnosis:

Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection/Rediagnosis).

WEI01 & 02 / Rediagnosis & SI Termination / 3 X EA2.2 Ability to determine and interpret the following as they apply to 3.3 98 the (St Termination): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

000022/ Loss of Reactor Coolant Makeup / 2 X MA1.08 Ability to operate and/or monitor the following as they apply to 3.4 63 the Loss of Reactor Coolant Pump Makeup: VCT level.

000025 / Loss of RHR System / 4 X AA2.07 Ability to determine and interpret the following as they apply to 3.4 64 the Loss of Residual Heat Removal System: Pump cavitation.

000029/ Anticipated Transient w/o Scram / 1 000032 /Loss of Source Range NI / 7 X AA2.04 Ability to determine and interpret the following as they apply to 3.1 72 the Loss of Source Range instrumentation: Satisfactory Source

__ __ Range/Intermediate Range overlap 000033 / Loss of Intermediate Range NI /77 000037 / Steam Generator Tube Leak / 3 NUREG..Reiso 8, Supemn 1.ae4f1.21 Page 4 of 14 NUREG-1 021, Revision 8, Supplement 1

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 EIAPE #/ Name / Safety Function K l K2 K3 Al A2 G Number KJA Topic(s) Imp. l 1 000038 / Steam Generator Tube Rupture / 3 X EK3.01 Knowledge of the reasons for the following responses as they 4.1 69 apply to the Steam Generator Tube Rupture: Equalizing pressure on primary and secondary sides of ruptured SG 000054 (CE/E06) / Loss of Main Feedwater / 4 X 2.4.2 Emergency Procedures/Plan: Knowledge of system setpoints, 3.9 65 interlocks, and automatic actions associated with EOP entry conditions BW/E04; W/E05 / Inadequate Heat Transfer - X 2.4.6 Emergency Procedures/Plan: Knowledge of symptom based 3.1 100 Loss of Secondary Heat Sink / 4 EOP mitigation strategies 000058 / Loss of DC Power / 8 X AA2.03 Ability to determine and interpret the following as they apply to 3.5 67 the Loss of DC Power: DC loads lost. Impact on ability to operate and monitor plant systems 000058 / Loss of DC Power /8 X AK3.02 Knowledge of the reasons for the following responses as they 4.0 99 apply to the Loss of DC Power: Actions contained in EOP for loss of DC power.

000059 / Accidental Liquid Radwaste Rel. / 9 000060 / Accidental Gaseous Radwaste Rel. /9 000061 / ARM System Alarms / 7 X AA1.01 Ability to operate and/or monitor the following as they apply to 3.6 68 the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation.

W/E16/ High Containment Radiation / 9 CE/E09 / Functional Recovery K/A Category Point Totals: 1 2 3 5 4 2 Group Point Total: 17 NUREG-1021, Revision 8, Supplement 1 Page 5 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 EIAPE#/NameISafetyFunction KI K2 K3 Al A2 G Number l K/A Topic(s) Imp- Q#

000028 / Pressurizer Level Malfunction / 2 X AK3.02 Knowledge of the reasons for the following responses as they 2.9 70 apply to the Pressurizer Level Control Malfunctions:

Relationships between PZR pressure increase and reactor makeup/letdown imbalance.

000036 (BW/A08) / Fuel Handling Accident /8 000056 / Loss of Off-site Power /6 X AA2.51 Ability to determine and interpret the following as they apply to 3.3 71 the Loss of Offsite Power: AT, (core, heat exchanger, etc.)

000065 / Loss of Instrument Air /8 X 2.1.2 Conduct of Operations: Knowledge of operator responsibilities 3.9 66 during all modes of plant operation.

BW/E13 & E14 / EOP Rules and Enclosures BW/A07 / Flooding /8 _ . _.

CE/Al 6 / Excess RCS Leakage / 2 W/E13 / Steam Generator Over-pressure / 4 W/E15 / Containment Flooding / 5 K/A Category Point Totals: I 0 0 i 1 0 1 1 Group Point Total: 3 j NUREG-1021, Revision 8, Supplement 1 Page 6of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G l Numberl K/A Topic(s) Imp. l Q 001 Control Rod Drive X K4.02 Knowledge of CRDS design feature(s) and/or 3.8 73 interlock(s) which provide for the following:

Control rod mode select control (movement control).

001 Control Rod Drive X A3.05 Ability to monitor automatic operation of the 3.5 78 CRDS, including: Individual versus group position 003 Reactor Coolant Pump X A3.04 Ability to monitor automatic operation of the 3.6 1 RCPS, including: RCS flow.

003 Reactor Coolant Pump X K4.04 Knowledge of RCPS design feature(s) and/or 2.8 2 interlock(s) which provide for the following:

Adequate cooling of RCP motor and seals.

004 Chemical and Volume Control X K5.19 Knowledge of the operational implications of 3.5 74 the following concepts as they apply to the CVCS: Concept of SDM.

004 Chemical and Volume Control X K6.17 Knowledge of the effect of a loss or malfunction 4.4 3 of the following will have on the CVCS: Flow paths for emergency boration 013 Engineered Safety Features Actuation X A2.01 Ability to (a) predict the impacts of the following 4.6 75 malfunctions or operations on the ESF Actuation System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: LOCA 013 Engineered Safety Features Actuation X A1.01 Ability to predict and/or monitor changes in 4.0 4 parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including: RCS pressure and temperature.

015 Nuclear Instrumentation X K5.02 Knowledge of the operational implications of 2.7 5 the following concepts as they apply to the NIS:

Discriminator/compensation operation.

015 Nuclear Instrumentation X K4.03 Knowledge of NIS design feature(s) and/or 3.9 76 interlock(s) provide for the following: Reading of source range/intermediate range/power range outside Control Room.

017 In-Core Temperature Monitor X K1.01 Knowledge of the physical connections and/or 3.2 77 cause/effect relationship between the ITM system and the following: Plant computer 017 In-Core Temperature Monitor X A4.01 Ability to manually operate and/or monitor in 3.8 6 the Control Room: Actual in-core temperatures.

NUREG-1021, Revision 8, Supplement 1 Page 7of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System #1 Name l K1 LK2 K3 K4 K5 K6 A1 EA2 A3 A4[G Number,, K/A Topic(s) lmp.l Q#

022 Containment Cooling X A4.04 Ability to manually operate and/or monitor in 3.1 7 the Control Room: Valves in the CCS.

025 Ice Condenser SUPPRESSED 056 Condensate X K1.03 Knowledge of the physical connections and/or 2.6 83 cause-effect relationships between the Condensate system and the following systems:

MFW 056 Condensate X 2.1 .2 Conduct of Operations: Knowledge of operator 3.3 79 responsibilities during all modes of plant operation.

059 Main Feedwater X K4.19 Knowledge of MFW design feature(s) and/or 3.2 8 interlock(s) which provide for the following:

Automatic feedwater isolation of MFW.

059 Main Feedwater X A4.03 Ability to manually operate and monitor in the 2.9 9 Control Room: Feedwater control during power increase and decrease.

061 Auxiliary / Emergency Feedwater X K6.02 Knowledge of the effect of a loss or malfunction 2.6 10 of the following will have on the AFW components: Pumps.

061 Auxiliary / Emergency Feedwater X K4.04 Knowledge of AFW design feature(s) and/or 3.1 80 interlock(s) which provide for the following:

Prevention of AFW runout by limiting AFW flow.

068 Liquid Radwaste X A3.02 Ability to monitor automatic operation of the 3.6 81 Liquid Radwaste System including: Automatic isolation.

068 Liquid Radwaste X K1.07 Knowledge of the interrelations and/or cause- 2.7 82 effect relationships between the Liquid Radwaste System and the following: Sources of liquid waste for LRS.

071 Waste Gas Disposal X K5.04 Knowledge of the operational implication of the 2.5 11 following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.

072 Area Radiation Monitoring X A3.01 Ability to monitor automatic operation of the 2.9 12 ARM system, including: Changes in ventilation alignment.

K/A Category Point Totals: 3 0 0 5 3 2 1 1 4 3 1 Group Point Total: 23 NUREG-1021, Revision 8, Supplement 1 Page 8 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System #/Name l 1 1<2 K3 lK4 K K6 Al A2 A3 A4 G Number K/A Topic(s) Imp Q#

002 Reactor Coolant X K4.02 Knowledge of RCS design features and/or 3.5 84 interlocks which provide for the following:

Monitoring reactor vessel level 002 Reactor Coolant X K6.02 Knowledge of the effect of a loss or malfunction 3.6 86 on the following will have on the Reactor Coolant System (RCS): RCP 006 Emergency Core Cooling X K2.04 Knowledge of bus power supplies to the 3.6 13 l __I_ following: ESFAS-operated valves.

010 Pressurizer Pressure Control X A3.02 Ability to monitor automatic operation of PZR 3.6 14 PCS, including: PZR pressure.

011 Pressurizer Level Control X K2.02 Knowledge of bus power supplies to the 3.1 15 following: PZR heaters.

012 Reactor Protection X K5.01 Knowledge of the operational implications of 3.3 16 the following concepts as they apply to the RPS: DNB.

012 Reactor Protection X 2.4.12 Emergency Procedures/Plan: Knowledge of 3.4 27 general operating crew responsibilities during l _ _ __ emergency operations 014 Rod Position Indication X A4.01 Ability to manually operate and/or monitor in 3.3 17 the Control Room: Rod selection control.

016 Non-nuclear Instrumentation X _K3.04 Knowledge of the effect that a loss or 2.6 85 malfunction of the NNIS will have on the following: MFW system.

026 Containment Spray X A1.01 Ability to predict and/or monitor changes in 3.9 18 parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment pressure.

029 Containment Purge 033 Spent Fuel Pool Cooling X A2.02 Ability to (a) predict the impacts of the following 2.7 19 malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based those predictions, use procedures to correct, control, or mitigate the consequences of those I malfunctions or operations: Loss of SFPCS.

035 Steam Generator X 2.4.4 Emergency Procedures/Plan: Ability to 2.5 20 recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

NUREG-1021, Revision 8, Supplement 1 Page 9 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System# / Name K1 K2 K3 K4 K5 K6 Al A27 A3 A4 G Numberl K/A Topic(s) Imp. Q#

039 Main and Reheat Steam X K1.06 Knowledge of the physical connections and/or 3.1 21 cause-effect relationships between the MRSS and the following systems: Condenser steam dump.

055 Condenser Air Removal X K3.01 Knowledge of the effect that a loss or 2.5 22 malfunction of the CARS will have on the l__ following: Main condenser.

062 AC Electrical Distribution X K1.03 Knowledge of the physical connections and/or 3.5 26 cause-effect relationships between the AC distribution system and the following systems:

DC Distribution 063 DC Electrical Distribution X K1.03 Knowledge of the physical connections and/or 2.9 23 cause-effect relationships between the DC distribution system and the following systems:

Battery Charger and battery 063 DC Electrical Distribution X K3.02 Knowledge of the effect that a loss or 3.5 24 malfunction of the DC Electrical System will have on the following: Components using dc control power.

064 Emergency Diesel Generator X A1.08 Ability to predict and/or monitor changes in 3.1 25 parameters associated with operating the Emergency Diesel Generator (ED/G) System controls including: Maintaining minimum load on ED/G (to prevent reverse power) 073 Process Radiation Monitoring 075 Circulating Water 079 Station Air X K1.01 Knowledge of the physical connections and/or 3.0 28 cause-effect relationships between the SAS and the following systems: IAS.

086 Fire Protection X K4.07 Knowledge of design feature(s) and/or 2.5 29 interlock(s) which provide for the following:

MT/G and T/G protection.

K/A Category Point Totals: 4 2 3 1 1 1 3 1 1 1 2 Group Point Total: 20 NUREG-1021, Revision 8, Supplement 1 Page 10 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401 -4 Plant Systems - Tier 2/Group 3 System /Name K K2 3 K4 K5 K6 Al~ A2 A3 A4 G Number K/A Topic(s) Im. Q#

005 Residual Heat Removal X A2.02 Ability to (a) predict the impacts of the following 3.5 30 malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.

007 Pressurizer Relief/Quench Tank 008 Component Cooling Water X K3.01 Knowledge of the physical connections and/or 3.4 90 cause-effect relationships between the CCWS

_______________________________and the following: Loads cooled by CCWS 027 Containment Iodine Removal X A4.01 Ability to manually operate and/or monitor in 3.3 32 the Control Room: CIRS controls.

028 Hydrogen Recombiner and Purge Control X K6.01 Knowledge of the effect of a loss or malfunction 2.6 31 of the following will have on the HRPS:

Hydrogen recombiners.

034 Fuel Handling Equipment 041 Steam Dump/Turbine Bypass Control X A3.03 Ability to monitor automatic operation of the 2.7 33 SDS, including: Steam flow.

045 Main Turbine Generator X Al1.06 Ability to predict and/or monitor changes in 3.3 88 parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: Expected response of secondary plant parameters following T/G trip.

076 Service Water X K2.01 Knowledge of bus power supplies to the 2.7 89

_______________________________following: Service water.

076 Service Water X K3.07 Knowledge of the effect that a loss or 3.7 87 malfunction of Service Water will have on the following: ESF loads 078 Instrument Air 103 Containment

~Aaeoyoint Totals:2 0 12 0 0 1 1 1 1 1 0 Group Point Total:8 NUREG-1021, Revision 8, Supplement 1Pae1of4 Page 1 1 of 14

Plant-Specific Priorities System / Topic Recommended Replacement for.... Reason Points APE 054 G2.4.2 (Question 65) EPE 038EK1.04 High PRA importance; Event as well as mitigating system 1 APE 058 AA2.03 (Question 67) APE 060AK2.01 High PRA importance; Loss of high importance system I EPE E05 G2.4.6 (Question 100) APE 059AA2.02 High PRA importance; Event as well as mitigating systems 1 SYS 004 K6.17 (Question 3) SYS 004K2.04 High PRA importance; Risk significant post-accident human error 1 APE 015/017 M1.22 (Question 52) APE 068 MAA.20 High PRA importance; Risk significant post-accident human error 1 EPE 038 EK3.01 (Question 69) EPE E16 EK3.4 High PRA importance; Event as well as risk significant post- 1 accident human error SYS 008 K3.01 (Question 90) SYS 103 A4.01 High PRA importance; Risk significant post-accident human error 1 SYS 012 Generic 2.4.12 (Question 27) SYS 075 Generic 2.4.30 High PRA importance; Event as well as mitigating systems 1 Plant-Specific Priority Total: (limit 10) 8 NUREG-1 021, Revision 8, Supplement 1 Page 12 of 14

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5

[Facility: Indian Point Units 2 & 3 Date of Exam: 3/8/2003 Exam Level: RO Category K/A # Topic Imp. Q#

2.1.2 Knowledge of operator responsibilities during all 3.0 91 modes of plant operation.

2.1.18 Ability to make accurate, clear and concise logs, 2.9 93 records, status boards, and reports.

Conduct of 2.1.8 Ability to coordinate personnel activities outside 3.8 34 Operations the Control Room.

_ Total 3 2.2.12 Knowledge of surveillance procedures. 3.0 92 Equipment 2.2.13 Knowledge of tagging and clearance procedures. 3.6 35 Control 2.2.33 Knowledge of control rod programming. 2.5 36 2.2.2 Ability to manipulate the console controls as 4.0 37 required to operate the facility between shutdown and designated power levels.

Total 4 2.3.4 Knowledge of radiation exposure limits and 2.5 94 contamination control, including permissible levels in excess of those authorized.

Radiation 2.3.9 Knowledge of the process for performing a 2.5 38 Control containment purge. _

Total 2 2.4.14 Knowledge of general guidelines for EOP 3.0 95 flowchart use.

Emergency 2.4.34 Knowledge of RO tasks performed outside the 3.8 96 Procedures / main control room during emergency operations Plan including system geography and system implications.

2.4.19 Knowledge of EOP layout, symbols, and icons. 2.7 39 2.4.29 Knowledge of the emergency plan. 2.6 40 Total 4 Tier3 PointTotal RO 13 NUREG-1021, Revision 8, Supplement 1 Page 13 of 14

ES-401 Record of Rejected K/As Form ES-401-10 Tier/ Group Randomly Selected K/A Reason for Rejection 1/2 (Question 72) 054 G2.2.25 No connection to 10CFR55.41 for RO. Replaced with randomly generated 032 AA2.04 2/2 (Question 23) 063 A4.03 No indication available for applicable topic in control room at facility. Replaced with l __ _ randomly generated 063 K1.03.

2/1 (Question 78) 056 G2.2.22 No connection to 10CFR55.41 for RO and no TS connection to system. Replaced with l_ _ _ randomly generated 001 A3.05 2/1 (Question 83) 071 A4.27 No indication or control available in control room. Replaced with randomly generated 056 K1.03 2/1 (Question 75) 013 K4.17 Operation not performed at facility. Replaced with randomly generated 013 A2.01 2/1 (Question 74) 004 K5.02 Potential Double Jeopardy with 071 K5.04. Replaced with manually selected 004 K5.19.

(Manually selected the next topic with same KA importance value) 2/2 (Question 26) 073 A1.01 Controls of PRM system are not operated in a manner that will cause change in the plant condition required by the topic. Replaced with randomly generated 062 K1.03 3 (Question 93) 2.2.6 Not RO level topic. Replaced by trading topic with SRO 2.1.18 (SRO 82) 2/1 (Question 4) 013A1.09 No suitable test item. Manually selected closest suitable KA to the selected topic (013A1.01) 1/1 (Question 41) 005 AK2.01 No suitable test item. Randomly selected topic in 005 area (005 AK1.03) 2/1 (Question 77) 0017 K4.02 No suitable test item. Randomly selected topic in area (017 K1.01) 2/3 (Question 87) 007A2.06 No suitable test item. Randomly selected topic in area (076 K3.07) 2/2 (Question 86) 029 Al.02 No suitable test item. Randomly selected topic in area (002 K6.02) 2/3 (Question 32) 034 K6.02 Related item on exam. Randomly selected topic in area (027 A4.01) 2/1 (Question 82) 068 A2.04 Related item on exam. Randomly selected topic in area (068 K1.07) 2/3 (Question 31) 028 A4.01 No suitable test item. Randomly selected topic in area (028 K6.01) 2/2 (Question 13) 006 K2.02 No suitable test item >LOD 1. Replaced per NRC Review comment. (006 K2.04) 2/2 (Question 84) 002 K5.19 No suitable test item operationally oriented. Replace d per NRC review comment (002 K4.02) l 2/2 (Question 25) 064 K3.03 Post - review removal. No suitable replacement. Replaced with 064 A1.08 NUREG-1021, Revision 8, Supplement 1 Page 14of 14

ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: Indian Point Unit 3 Date of Exam: 3/8/2003 Exam Level: SRO K/A Category Point Point Tier Group K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 *l 1 4 1 4 6 8 1 24 Emergency & 2 1 1 1 4 4 5 16 Abnormal Plant 3 0 0 1 0 1 1 3 Evolutions l Totals 5 2 6 10 13 7 43 1 1 0 1 2 2 2 2 2 2 4 1 19 Plat l 2 3 2 1 1 1 1 1 1 1 1 4 17 Systems 3 00 00 0 0 02 1 0 1 4 Tier ] ll l l _ _ Totalse 4 2 2 3 3 3 3 5 4 5 6 40

3. Generic Knowledge and Abilities Cat 1 3 [ Cat2 6

Cat 3 3

Cat4 5 17 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by

+/- 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/A's below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

Page 1 of 14 NUREG-1021, Revision 8, Supplement 1

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 EIAPE#/Name / Safety Function Ki K2 K3 Al A2 lG Number K/ATopic(s) Imp- l 000001 / Continuous Rod Withdrawal / 1 X AA1.05 Ability to operate and / or monitor the following as they apply to 4.2 57 the Continuous Rod Withdrawal: Reactor trip switches.

000003 / Dropped Control Rod / 1 X AK2.05 Knowledge of the interrelations between the Dropped Control 2.8 58 Rod and the following: Control rod drive power supplies and logic circuits.

000005 / Inoperable/Stuck Control Rod / 1 X AK1.03 Knowledge of the operational implications of the following 3.6 41 concepts as they apply to the stuck rod: Xenon transient.

000011 / Large Break LOCA / 3 X EA1.01 Ability to operate and monitor the following as they apply to a 3.8 61 Large Break LOCA: Control of RCS pressure and temperature to avoid violating PTS limits.

W/E04 / LOCA Outside Containment / 3 W/EO1 & E02 / Rediagnosis & SI Termination/ 3 X EK3.2 Knowledge of the reasons for the following responses as they 3.9 62 apply to the (Reactor Trip or Safety Injection/Rediagnosis):

Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection/Rediagnosis).

000015 / 17 RCP Malfunctions /4 X AA1.22 Ability to operate and/or monitor the following as they apply to 4.2 52 the RCP malfunctions: RCP seal failure/malfunction BW/E09; CE/A13; W/E09 & El0 / Natural Circ. /4 X EK3.1 Knowledge of the reasons for the following responses as they 3.6 42 apply to the (Natural Circulation Operations): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

BW/E09; CE/Al 3; W/E09 & El0 / Natural Circ. /4 X 2.4.50 Emergency Procedures/Plan: Ability to verify system alarm 3.3 90 setpoints and operate controls identified in the alarm response manual.

000024 / Emergency Boration /1 X AA2.04 Ability to determine and interpret the following as they apply to 4.2 43 the Emergency Boration: Availability of BWST.

000026 / Loss of Component Cooling Water / 8 X AK3.03 Knowledge of the reasons for the following responses as they 4.2 44 apply to the Loss of Component Cooling Water: Guidance and actions contained in EOP for Loss of CCW/nuclear service water.

000029 / Anticipated Transient w/o Scram / 1 X EA2.02 Ability to determine or interpret the following as they apply to 4.4 91 ATWS: Reactor trip alarm.

000040 (BW/E05; CE/E05; W/E1 2) / Steam Line X AK1.06 Knowledge of the operational implications of the following 3.8 46 Rupture - Excessive Heat Transfer / 4 concepts as they apply to Steam Line Rupture: High-energy steam line break considerations.

000040 (BW/E05; CE/E05; W/E12) / Steam Line X EA1.2 Ability to operate and/or monitor the following as they apply to 3.7 47 Rupture - Excessive Heat Transfer / 4 the (Uncontrolled Depressurization of all Steam Generators):

I Operating behavior characteristics of the facility.

NUREG-1021, Revision 8, Supplement 1 Page 2of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE #I Name I Safety Function K1 K2 K3 Al A2 G I Number K/A Topic(s) Imp.

CE/A1l; W/E08 / RCS Overcooling - PTS /4 X EA2.1 Ability to determine and interpret the following as they apply to 4.2 92 the (Pressurized Thermal Shock): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

000051 / Loss of Condenser Vacuum / 4 X AA1.04 Ability to operate and / or monitor the following as they apply to 2.5 48 the Loss of Condenser Vacuum: Rod position.

000055 / Station Blackout / 6 X EA2.01 Ability to determine or interpret the following as they apply to a 3.7 49 Station Blackout: Existing valve positioning on a loss of instrument air system.

000057 / Loss of Vital AC Elec. Inst. Bus / 6 X AK3.01 Knowledge of the reasons for the following responses as they 4.4 50 apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.

000059 / Accidental Liquid Radwaste Rel. / 9 X AA2.02 Ability to determine and interpret the following as they apply to 3.9 93 the Accidental Liquid Radwaste Release: The permit for liquid radioactive-waste release.

000062 / Loss of Nuclear Service Water / 4 X AA2.01 Ability to determine and interpret the following as they apply to 3.5 51 the Loss of Nuclear Service Water: Location of a leak in the CCWS.

000067 / Plant Fire On-site / 9 000068 (BW/A06) / Control Room Evac. /8 000069 (W/E14) / Loss of CTMT Integrity / 5 X AA2.02 Ability to determine and interpret the following as they apply to 4.4 94 the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity.

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EK1.05 Knowledge of the operational implications of the following 3.2 53 concepts as they apply to the Inadequate Core Cooling:

Definition of saturated liquid.

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EK1.3 Knowledge of the operational implications of the following 3.9 54 concepts as they apply to the (Degraded Core Cooling):

Annunciators and conditions indicating signals, and remedial actions associated with the (Degraded Core Cooling).

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EA1.2 Ability to operate and/or monitor the following as they apply to 3.7 55 the (Saturated Core Cooling): Operating behavior characteristics of the facility.

BW/E03 / Inadequate Subcooling Margin / 4 000076 / High Reactor Coolant Activity / 9 X AA2.02 Ability to determine and interpret the following as they apply to 3.4 56 the High Reactor Coolant Activity: Corrective actions required for high fission product activity in RCS.

BW/A02 & A03 / Loss of NNI-X/Y / 7 K/A Category Point Totals: 4 1 4 6 8 1 Group Point Total: 24 NUREG-1021, Revision 8, Supplement 1 Page 3 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/AIPE #IName I Safety Functionr 1lK 3lA 2lG lNme K/A Topic(s) l m. l Q#

000007 (BW/E02 & El 0; CE/E02) / Reactor Trip - X 2.1.14 Conduct of Operations: Knowledge of system status criteria, 3.3 95 Stabilization - Recovery / 1 which require the notification of plant personnel.

BW/A0l I Plant Runback /1 _____

BW/A04 / Turbine Trip / 4 000008 I Pressurizer Vapor Space Accident I 3 X AK2.02 Knowledge of the interrelations between the Pressurizer Vapor 2.7 59 Space Accident and the following: Sensors and detectors.

000009 / Small Break LOCA / 3 X EA1 .18 Ability to operate and monitor the following as they apply to a 3.2 60 small break LOCA: Balancing of HPI loop flows.

BW/E08; W/E03 / LOCA Cooldown - Depress. /4 X EA1.02 Ability to operate and/or monitor the following as they apply to 3.9 96 the (LOCA Cooldown and Depressurization): Operating behavior characteristics of the facility.

WIE1 1 / Loss of Emergency Coolant Recirc. / 4 X EK1.2 Knowledge of the operational implications of the following 4.1 99 concepts as they apply to the (Loss of Emergency Coolant Recirculation): Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).

000022 / Loss of Reactor Coolant Makeup / 2 X AA1.08 Ability to operate and/or monitor the following as they apply to 3.3 63 the Loss of Reactor Coolant Pump Makeup: VCT level.

000025 / Loss of RHR System / 4 X AA2.07 Ability to determine and interpret the following as they apply to 3.7 64 the Loss of Residual Heat Removal System: Pump cavitation.

000027 / Pressurizer Pressure Control System X AA2.15 Ability to determine and interpret the following as they apply to 4.0 45 Malfunction / 3 the Pressurizer Pressure Control Malfunctions: Actions to be taken if PZR pressure instrument fails high.

000032 / Loss of Source Range NI / 7 000033 / Loss of Intermediate Range NI / 7 X AA2.10 Ability to determine and interpret the following as they apply to 3.8 97 the Loss of Intermediate Range NI: Tech Spec limits if both IR channels have failed 000037 / Seam Generator Tube Leak / 3 X 2.2.22 Equipment Control: Knowledge of limiting conditions for 4.1 98 operations and safety limits.

000038 / Steam Generator Tube Rupture / 3 X EK3.01 Knowledge of the reasons for the following responses as they 4.3 69 apply to the Steam Generator Tube Rupture: Equalizing pressure on primary and secondary sides of ruptured SG 000054 (CE/E06) / Loss of Main Feedwater / 4 X 2.4.2 Emergency Procedures/Plan: Knowledge of system setpoints, 4.1 65 interlocks, and automatic actions associated with EOP entry conditions 000054 (CE/E06) / Loss of Main Feedwater / 4 X 2.2.25 Equipment Control: Knowledge of bases in technical 3.7 72 specifications for limiting conditions for operations and safety limits.

BW/E04; W/E05 / Inadequate Heat Transfer -

Loss of Secondary Heat Sink / 4 NUREG-1021, Revision 8, Supplement 1 Page 4 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # I Name / Safety Function lK K2 K3 Al A2 G Number7 K/A Topic(s) l Imp.

000058 / Loss of DC Power / 8 X AA2.03 Ability to determine and interpret the following as they apply to 3.9 67 the Loss of DC Power: DC loads lost, impact on ability to

_. ._ operate and monitor plant systems 000060 / Accidental Gaseous Radwaste Rel. / 9 000061 / ARM System Alarms / 7 X AA1 .01 Ability to operate and/or monitor the following as they apply to 3.6 68 the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation.

W/E1 6 / High Containment Radiation / 9 000065/ Loss of Instrument Air /8 X 2.1.2 Conduct of Operations: Knowledge of operator responsibilities 4.0 66

. during all modes of plant operation.

CE / E09 / Functional Recovery K/A Category Point Totals: 1 1 1 4 4 5 Group Point Total: 16 NUREG-1021, Revision 8, Supplement 1 Page5 of 14

t INDIAN POINT UNITS 2 & 3 lES-401 PWR SRO Examination Outline Form ES-401-3 l Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE#1Name/Safety Function K1 K2. K3 Al A2 G I Number K/ATopic(s) 000028 / Pressurizer Level Malfunction / 2 X AK3.02 Knowledge of the reasons for the following responses as they 3.2 70 apply to the Pressurizer Level Control Malfunctions:

Relationships between PZR pressure increase and reactor makeup/letdown imbalance.

000036 (BW/A08) / Fuel Handling Accident / 8 X 2.2.28 Equipment Control: Knowledge of new and spent fuel 3.5 100 movement procedures 000056 / Loss of Off-site Power / 6 X AA2.51 Ability to determine and interpret the following as they apply to 3.4 71 the Loss of Offsite Power: AT, (core, heat exchanger, etc.) l BW/El 3 & El 4 / EOP Rules and Enclosures BW/A05 / Emergency Diesel Actuation / 6 CE/Al 6/ Excess RCS Leakage / 2 W/El3 / Steam Generator Over-pressure /4 W/El5 / Containment Flooding / 5 K/ aeoyPitTtl:0 0 + 11 0 1 1 Group Point Total: 3 NUREG-1021, Revision 8, Supplement 1 Page 6 of 14

INDIAN POINT UNITS 2 & 3 ES-40 1 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System I1Name Ki K 3 K 5 K l A 3 A uber K/A Topic(s) Imp. Q 001 Control Rod Drive X A2.03 Ability to (a) predict the impacts of the following 4.2 73 malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of stuck rod or Misaligned rod.

003 Reactor Coolant Pump X A3.04 Ability to monitor automatic operation of the 3.6 1 RCPs, including: RCS flow.

003 Reactor Coolant Pump X K4.04 Knowledge of RC Ps design feature(s) and/or 3.1 2 interlock~s) which provide for the following:

Adequate cooling of RCP motor and seals.

004 Chemical and Volume Control X K6.17 Knowledge of the effect of a loss or malfunction 4.6 3 of the following will have on the CVCS: Flow paths for emergency boration 01 3 Engineered Safety Features Actuation X Al1.01 Ability to predict and/or monitor changes in 4.2 4 parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: RCS pressure and temperature.

01 4 Rod Position Indication X A4.01 Ability to manually operate and/or monitor in 3.1 17 the control room: Rod selection control.

01 5 Nuclear Instrumentation X K5.02 Knowledge of the operational implications of 2.9 5 the following concepts as they apply to the NIS:

Discriminator/compensation operation.

01 7 In-Core Temperature Monitor X A4.01 Ability to manually operate and/or monitor in 4.1 6 the control room: Actual in-core temperatures.

022 Containment Cooling X A4.04 Ability to manually operate and/or monitor in 3.2 7 the control room: Valves in the CCS.

025 Ice Condenser SUPPRESSED___

026 Containment Spray X Al1.01 Ability to predict and/or monitor changes in 4.2 18 parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment pressure.

056 Condensate x A2.04 malfunctions or operations on the Condensate 2.b 14 System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.

__ _ ___ ___ __ _ __ ___ _ ___ ____ ___ ___ L.. ... J ... ... ~1 _ ___ L_ ___ .1_ _ _ _~ _ ___

NUREG-1021, Revision 8, Supplement 1 Pg 7 off114 Page

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System #/Name l K l4 lK lK6 3 A4 lG umber l K/ATTopic(s) Imp. Q#

059 Main Feedwater X K4.19 Knowledge of MFW design feature(s) and/or 3.4 8 interlock(s), which provide for the following:

Automatic feedwater isolation of MFW.

059 Main Feedwater X A4.03 Ability to manually operate and monitor in the 2.9 9 control room: Feedwater control during power increase and decrease.

061 Auxiliary / Emergency Feedwater X K6.02 Knowledge of the effect of a loss or malfunction 2.7 10 of the following will have on the AFW components: Pumps.

063 DC Electrical Distribution X K3.02 Knowledge of the effect that a loss or 3.7 24 malfunction of the DC electrical system will have on the following: Components using DC control power.

063 DC Electrical Distribution X K1.03 Knowledge of the physical connections and/or 3.5 23 cause-effect relationships between the DC distribution system and the following systems:

Battery Charger and battery 068 Liquid Radwaste X 2.4.31 Emergency Procedures / Plan: Knowledge of 3.4 75 annunciators alarms and indications, and use of the response instructions.

071 Waste Gas Disposal X K5.04 Knowledge of the operational implication of the 3.1 11 following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.

072 Area Radiation Monitoring X A3.01 Ability to monitor automatic operation of the 3.1 12 ARM system, including: Changes in ventilation alignment.

K/A Category Point Totals: 1 0 1 2 1 ru on oa: 19 NUREG-1021, Revision 8, Supplement 1 Page 8 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 System #Name K1 I K2 K3 K4 KS K6 Al A2 A3 A4 G Number K/A Topic(s) Imp. Q#

002 Reactor CoolantI 006 Emergency Core Cooling X K2.04 Knowledge of bus power supplies to the 3.8 13 following: ESFAS-operated valves.

010 Pressurizer Pressure Control X A3.02 Ability to monitor automatic operation of the 3.5 14 PZR PCS, including: PZR pressure.

011 Pressurizer Level Control X K2.02 Knowledge of bus power supplies to the 3.2 15 following: PZR heaters.

012 Reactor Protection X K5.01 Knowledge of the operational implications of 3.8 16 the following concepts as they apply to the RPS: DNB.

012 Reactor Protection X 2.4.12 Emergency Procedures/Plan: Knowledge of 3.9 27 general operating crew responsibilities during emergency operations 01 6 Non-nuclear Instrumentation X 2.1.28 Conduct of Operations: Knowledge of the 3.3 76 purpose and function of major system components and controls.

027 Containment Iodine Removal X A4.01 Ability to manually operate and/or monitor in 3.3 32 the Control Room: CIRS controls.

028 Hydrogen Recombiner and Purge Control X K6.01 Knowledge of the effect of a loss or malfunction 3.1 31 of the following will have on the HRPS:

Hydrogen recombiners.

029 Containment Purge _______

033 Spent Fuel Pool Cooling X A2.02 Ability to (a) predict the impacts of the following 3.0 19 malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SFPCS.

034 Fuel Handling Equipment ____.__

035 Steam Generator X 2.4.4 Emergency Procedures/Plan: Ability to 4.3 20 recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

039 Main and Reheat Steam X K1.06 Knowledge of the physical connections and/or 3.0 21 cause-effect relationships between the MRSS and the following systems: Condenser steam dump. __dup-_

NUREG-1021, Revision 8, Supplement 1 Page 9 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 System # I Name Ki 1l2 K6 lK lK4 (3 Al A 3 A4 G Number K/A Topic(s) Imp. Q#

055 Condenser Air Removal X K3.01 Knowledge of the effect that a loss or 2.7 22 malfunction of the CARS will have on the following: Main condenser.

062 AC Electrical Distribution X 2.1.33 Conduct or Operations: Ability to recognize 4.0 77 indications for system operating parameters which are entry level conditions for Technical Specifications 062 AC Electrical Distribution X K1.03 Knowledge of the physical connections and/or 4.0 26 cause-effect relationships between the AC distribution system and the following systems:

DC Distribution 064 Emergency Diesel Generator X A1.08 Ability to predict and/or monitor changes in 3.4 25 parameters associated with operating the Emergency Diesel Generator (ED/G) System controls including: Maintaining minimum load on ED/G (to prevent reverse power) l 073 Process Radiation Monitoring ____ l 075 Circulating Water 079 Station Air X K1.01 Knowledge of the physical connections and/or 3.1 28 cause-effect relationships between the SAS and the following systems: lAS.

086 Fire Protection X K4.07 Knowledge of design feature(s) and/or 2.8 29 interlock(s) which provide for the following:

MT/G and T/G protection.

103 Containment __ .... _

K/A Category Point Totals: 3 2 1 1 1 1 1 1 1 1 4 Group Point Total: 17 NUREG-1021, Revision 8, Supplement 1 Page 10 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 System # Name K1 l l 4 l5 K6 Al l A2 A3 A4 G Number K/A Topic(s) Imp. Q#

005 Residual Heat Removal X A2.02 Ability to (a) predict the impacts of the following 3.7 30 malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.

007 Pressurizer Relief / Quench Tank 008 Component Cooling Water X A2.02 Ability to (a) predict the impacts of the following 3.5 78 malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequences of High/Low Surge Tank Level 041 Steam Dump/Turbine Bypass Control X A3.03 Ability to monitor automatic operation of the 2.8 33 SDS, including: Steam flow.

045 Main Turbine Generator I 076 Service Water 078 Instrument Air X 2.1.23 Conduct of Operations: Ability to perform 4.0 79 specific system and integrated plant procedures during all modes of plant operation.

K/A Category Point Totals: 0 O 0 0 0 l0 l0 2 1 0 1 1 [ Group Point Total:

NUREG-1021, Revision 8, Supplement 1 Page 11 of 14

Plant-Specific Priorities System / Topic Recommended Replacement for.... Reason Points APE 054 G2.4.2 (Question 65) EPE 038EK1.04 High PRA importance; Event as well as mitigating system 1 APE 058 AA2.03 (Question 67) APE 060AK2.01 High PRA importance; Loss of high importance system 1 SYS 004 K6.1 7 (Question 3) SYS 004K2.04 High PRA importance; Risk significant post-accident human error 1 APE 015/017 AA1.22 (Question 52) APE 068 AA1.20 High PRA importance; Risk significant post-accident human error 1 EPE 038 EK3.01 (Question 69) EPE E16 EK3.4 High PRA importance; Event as well as risk significant post- 1 accident human error SYS 012 Generic 2.4.12 (Question 27) SYS 075 Generic 2.4.30 High PRA importance; Event as well as mitigating systems 1 Plant-Specific Priority Total: (limit 10) ] 6 NUREG-1021, Revision 8, Supplement 1 Page 12 of 14

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Indian Point Units 2 & 3 Date of Exam: 3/8/2003 Exam Level: SRO Category K/A # Topic Imp. Q#

2.1.11 Knowledge of less than one hour technical 3.8 80 specification action statements for systems.

Conduct of 2.1.20 Ability to execute procedure steps. 4.2 81 Operations 2.1.8 Ability to coordinate personnel activities outside 3.6 34 the control room. l Total 3 2.2.6 Knowledge of the process for making changes in 3.3 82 procedures as described in the safety analysis report.

2.2.22 Knowledge of LCOs and Safety Limits 4.1 83 2.2.34 Knowledge of the process for determining the 3.2 84 internal and external effects on core reactivity.

Equipment 2.2.33 Knowledge of control rod programming. 2.9 36 Control 2.2.2 Ability to manipulate the console controls as 3.5 37 required to operate the facility between shutdown and designated power levels.

2.2.13 Knowledge of tagging and clearance procedures. 3.8 35 Total 6 2.3.10 Ability to perform procedures to reduce excessive 3.3 85 levels of radiation and guard against personnel exposure.

Radiation 2.3.2 Knowledge of facility ALARA program. 2.9 86 Control 2.3.9 Knowledge of the process for performing a 3.4 38 containment purge.

Total 3 2.4.45 Ability to prioritize and interpret the significance 3.6 87 of each annunciator or alarm.

2.4.24 Knowledge of loss of cooling water procedures. 3.7 88 Emergency 2.4.12 Knowledge of general operating crew 3.9 89 Procedures / responsibilities during emergency operations.

Plan 2.4.29 Knowledge of the emergency plan. 4.0 40 2.4.19 Knowledge of EOP layout, symbols, and icons. 3.7 39 Total 5 Tier 3 Point Total SRO 17 NUREG-1021, Revision 8, Supplement 1 Page 13 of 14

ES-401 Record of Rejected K/As Form ES-401-10 Tier/ Group Randomly Selected K/A Reason for Rejection 2/1 (Question 23) 063 A4.03 No indication available for applicable topic in control room at facility. Replaced with randomly selected 063 K1.03.

1/2 (Question 97) 033 AA2.11 Redundant Topic (Double Jeopardy) with SYS 015K5.02 (Question 5). Replaced with manually selected 033 AA2.10.

1/3 (Question 100) 036 AA1.04 Would not yield 10CFR55.43(b) question for SRO. Replaced with manually selected Generic topic 2.2.28 to ensure coverage of 10CFR55.43(b) item 6 and/or 7 for SRO. (Was not randomly selected as part of generic tier 3).

2/2 (Question 26) 073 A1.01 Controls of PRM system are not operated in a manner that will cause change in the plant condition required by the topic. Replaced with randomly generated 062 K1.03 3 (Question 82) 2.1.18 Topic switched for RO 2.2.6 (RO 93) for SRO Only application 2/1 (Question 4) 013 A1.09 No suitable test item. Manually selected closest suitable KA to the selected topic (013A1.01) 1/1 (Question 41) 005 AK2.01 No suitable test item. Randomly selected topic in 005 area (005 AK1.03) 2/2 (Question 77) 062 A2.12 No suitable test item. Manually selected Generic topic 2.1.33 to ensure 10CFR55.43(b) coverage for SRO 2/3 (Question 78) 008 A2.07 No suitable test item. Manually selected 008 A2.02 in same topic area 1/2 (Question 98) 037 G2.1.30 Not suitable for SRO. Manually selected Generic topic 2.2.22 to ensure 10CFR55.43 (b) coverage for SRO 1/2 (Question 99) E05 G2.1.27 Too many similar topics. Randomly selected El1 EK1.2 to replace 2/2 (Question 32) 034 K6.02 Too many similar topics. Randomly selected 027 A4.01 to replace 2/2 (Question 31) 028 A4.01 No suitable test item. Randomly selected 028 K6.01 to replace 2/2 (Question 13) 006 K2.02 No suitable test item >LOD 1. Replaced per NRC Review comment. (006 K2.04) 2/2 (Question 25) 064 K3.03 Post - review removal. No suitable replacement. Replaced with 064 A1.08 NUREG-1021, Revision 8, Supplement 1 Page 14 of 14

ES-301 Administrative Topics Outline Form-ES-301-1 Facility: Indian Point 3 Date of Examination: 3/10/2003 Examination Level: RO Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject Description 1. ONE Administrative JPM, OR l I2. TWO Administrative Questions A.1a Conduct of 2.1.7 Ability to evaluate plant performance and make operational Operations judgments based on operating characteristics, reactor behavior, and instrument interpretation. (3.7/4.4)

JPM: Perform QPTR Calculation A.1b Conduct of 2.1.18 Ability to make accurate, clear, and concise logs, records, status Operations boards, and reports. (2.9/3.0)

JPM: Perform a set of Control Room logs A.2 Equipment 2.2.12 Knowledge of surveillance procedures. (3.0/3.4)

Control JPM: Perform the RCS Leak Rate surveillance A.3 Radiation 2.3.2 Knowledge of facility ALARA program. (2.5/2.9)

Exposure Control JPM: Determine appropriate RWP and take action for High Area Radiation alarm A.4 Emergency Plan 2.4.43 Knowledge of RO responsibilities in E-Plan implementation.

(3.3/3.1) uestion: Duties of operations department personnel when site accountability is required 2.4.29 Knowledge of the Emergency Plan. (2.6/4.0)

Question: Emergency Response Facilities activated in a Site Area Emergency Form ES-301-1 RO ADM Outline NUREG-1021, Revision 8

ES-301 Administrative Topics Outline Form-ES-301 -1 Facility: Indian Point 3 Date of Examination: 3/17/2003 lExamination Level: SRO Operating Test Number: 1 lAdministrative TopictSubject Describe method of evaluation:l Descriptionl l~ 1. ONE Administrative JPIV, ORl l ~2. TWvO Administrative Questionsl ItA.1a Conduct of 2.1.7 Ability to evaluate plant performance and make operationall lOperations judgments based on operating characteristics, reactor behavior,l l ~and instrument interpretation. (3.714.4)l lJPIV: Review a QPTR calculation and direct appropriate actions lA.1 bConduct of 2.1.18 Ability to make accurate, clear, and concise logs, records, statusl lOperations boards, and reports. (2.9/3.0)l lJPIV: Review Control Room Log Entries lA.2 Equipment Control 2.2.17 Knowledge of the process for managing maintenance activitiesl l ~during power operations. (2.3/3.5)l lJPIV: Review (forapproval) a completed surveillance for Tech Spec l l required equipment lA.3 Non-Emergency 2.3.4 (3.1) Knowledge of radiation exposure limits and contaminationl ldose limits control, including permissible levels in excess of those l lquestion authorized.l lQUESTION: Given the plant in a SAE and a personnel exposurel l ~history, determine the exposure limit for a Non-Emergencyl l ~operation.l lEmergency 2.3.2 (2.9) Knowledge of facility ALARA program.l lExposure Limits QUESTION: Given a situation requiring valve alignment verification in al lQuestion radiation area, determine the waiver requirements for l l ~independent or concurrent verification of a locked valve l l ~and identify an alternate process for verification.l AA A Emergency Plan 2.4.41 Knowledge of the emergency action level thresholds andl l ~classifications. (4.1)l lJPIV: Classify the eventl Form ES-301-1 SRO ADM Outline NUREG-1021, Revision 8

Control Room Systems and Facility Walk-Through Test Outline Form-301-2 ES-301 Indian Point 3 Date of Examination: 3/17/2003 Facility:

Exam Level: RO/SROI Operating Test No.: 1 B.1: Control Room Systems JPM Description Type Safety System Code* Function Withdraw control rods for Tavg control NS,A 1 Si 001 Rod Control S2 006 Fill a Safety Injection Accumulator D,S2

_ ECCS (Repeat from last NRC exam)

S3 010 Depressurize the RCS following a SGTR D,S,A,E3 Pressurizer Pressure Control Start an RCP M,S,A,L 4P S4003 Reactor Coolant (Repeat from last NRC exam)

Pump Respond to PRT High Pressure NS,E 5 S 007 Pressurizer Relief I

Tank Restore 6.9KV Busses from off-site power. D,S 6 S6062 AC Distribution Return a Power Range Channel to service D,S 7 S7 015 Nuclear (Repeat from last NRC exam)

Instrumentation B.2 Facility Walk-Through Locally Emergency Borate R,D,E 1 P1 004 CVCS__

Local Operation of Atmospheric Steam Dumps DE,A 4S P2 041 Steam Dump Startup a Battery Charger D 6 P3 063 DC Distribution II

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA, (E)OPIAB NRCJPMOUTRev0.doc

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility: Indian Point 3 Date of Examination: 3/17/2003 Exam Level: SROU Operating Test No.: 1 lB.1: Control Room Systems System JPM Description Type Safety Code* Function Si S2 006 Fill a Safety Injection Accumulator D,S 2 ECCS (Repeat from last NRC exam)

S3 010 Depressurize the RCS following a SGTR D,S,A,E 3 Pressurizer Pressure Control S4 S5 007 Respond to PRT High Pressure N,S,E 5 Pressurizer Relief

_ Tank _ _ _ _ _

S6 S7 B.2 Facility Walk-Through P1 004 Locally Emergency Borate R,D,E 1 C V CS_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

P2 041 Local Operation of Atmospheric Steam Dumps D,E,A 4S Steam Dump P3

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA, (E)OP/AB IP2 NRCJPMOUTRevO.doc

Appendix D Scenario Outline Form ES-D-1 Facility: IP3 Scenario No.: 4 Op Test No.: 1 Examiners: Candidates: CRS RO PO0 Initial Conditions: 94% power EOL 32 Charging Pump OOS 31 AFW Pump OOS Small SG Tube Leak < 25 GPD Turnover: Main Condenser rupture disc is leaking. Reduce Power to 50 MWe at 200 MWe per hour and remove Main Turbine and Generator from service Critical Tasks: Manual Turbine Trip Initiate Emergency Boration Event Malf. Event No. No. Type* Event Description 1 R (RO) Reduce load N (BOP)

N (CRS) 2 TUR10B (CRS) First Stage Shell Pressure PT-412B fails low 3 MSS3 I (RO) Steam Pressure transmitter 404 fails high

'4 I (CRS) 4 CCW1A CCW Pump Trip.

5 RCS10C C (ALL) RCP TBHX leak. RCP vibration RCS7C 6 XMT38 M (ALL) RCP sheared shaft; ATWS XMT39 XMT40 7 TUR2A C (RO) Turbine Trip failure TUR2B 8 CVC16 C (ALL) Boration failure

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility: IP3 Scenario No.: 3 Op Test No.: 1 Examiners: Candidates: CRS RO POI Initial Conditions: 45% power BOL 32 Charging Pump OOS 32 Heater Drain Pump OOS Small SG Tube Leak < 25 GPD Turnover: Reduce Power and remove Main Turbine and Generator from service Critical Tasks: Restore AC Power Stop ECCS pumps Event Malf. Event No. No. Type* Event Description 1 R (RO) Reduce power.

N (BOP)

N (CRS) 2 NIS7D I (ALL) PR NI failure high 3 MSS4D C Steam Flow transmitter fails low (RO/CRS) 4 EPS4F C Loss of 6.9 KV bus 6 (BOP/CRS) DG output breaker fail to auto close 5 EPS6 M (ALL) Loss of Off Site power.

EPS4C Loss of 6.9 KV bus 3. Reactor trip.

6 DSG1 B C (ALL) Two Running DGs trip. 480 volt bus 3A tie breaker trips open.

DSG1C OVR EPS29 7 SIS7A C (ALL) Inadvertent SI

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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