ML103640250

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Final Outlines (Folder 3)
ML103640250
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/27/2010
From:
Constellation Energy Nuclear Group
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML101900599 List:
References
TAC U01790
Download: ML103640250 (33)
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Text

ES-401 Written Examination Outline (NRC)

Form ES-401-1 Facility: Nine Mile Point Unit 2 Date of Exam:

November 2010 RO KIA Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

Total A2 G*

Total 1

2 3

4 5

6 1

2 3

4

1.

Emergency Plant Evaluations 1

2 Tier Totals 2

1 3

4 2

6 4

2 6

4 1

5 3

0 3

3 1

4 20 7

27 4

2 6

3 1

4 7

3 10 1

2 2

3 3

2 2

2 3

2 2

3 26 3

2 5

2.

Plant Systems 2

Tier Totals 2

4 0

2 1

4 2

5 1

3 1

3 1

3 1

4 1

3 1

3 1

4 12 38 0

4 1

2 4

3 8

3. Generic Knowledge & Abilities 1

2 3

4 10 1

2 3

4 7

2 3

2 3

2 2

1 2

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 that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding 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 KAs 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 KIA's

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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 10CFR55.43

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function KIA Topic(s)

AA2.05-Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage GENERATOR VOLTAGE X

3.8 76 and Electric Grid AND ELECTRIC GRID Disturbances DISTURBANCES:

Operational status of offsite circuit AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL 295019 Partial or Total X

OR COMPLETE LOSS OF 3.6 77 Loss of Inst. Air /8 INSTRUMENT AIR:

Instrument air system pressure AA2.04 - Ability to determine and/or interpret the following as they apply to PARTIAL 295001 Partial or Complete OR COMPLETE LOSS OF Loss of Forced Core Flow X

3.1 78 FORCED CORE FLOW Circulation / 1 & 4 CIRCULATION: Individual jet pump flows: Not-BWR 1&2 2.2.38 - Equipment Control:

295021 Loss of Shutdown Knowledge of conditions and X

4.5 79 Cooling /4 limitations in the facility license.

2.4.34 - Emergency Procedures / Plan:

Knowledge of RO tasks 295016 Control Room X

performed outside the main 4.1 80 Abandonment / 7 control room during an emergency and the resultant operational effects.

295037 SCRAM Conditions 2.4.6. - Emergency Present and Reactor Power Procedures / Plan:

X 4.7 81 Above APRM Downscale or Knowledge of EOP Unknown /1 Mitigation strategies AA2.03 - Ability to determine and/or interpret the following 295023 Refueling as they apply to X

3.8 82 Accidents / 8 REFUELING ACCIDENTS :

Airborne contamination levels

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function 295024 High Drywell Pressure 15 295025 High Reactor Pressure 13 600000 Plant Fire On-site I

!8 295019 Partial or Total ILoss of Inst. Air 18 I

I

!295037 SCRAM Conditions i Present and Reactor Power Above APRM Downscale or

Unknown 11 295028 High Drywell Temperature I 5
295021 Loss of Shutdown

.Cooling 14 I

I I

X I

X X

X*

X i

I:X I

Xi I

KIA TopiC(S)

  • EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE:

Drywell integrity: Plant-Specific EA1.08 - Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:

  • RRCS AK3.04 - Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE:

Actions contained in the abnormal procedure for plant fire on site AK2.08 - Knowledge of the interrelations between PARTIAL OR COMPLETE

  • LOSS OF INSTRUMENT AIR and the following: Plant Ventilation EK2.09 - Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following: Reactor Water level EK2.03 - Knowledge of the interrelations between HIGH DRYWELLTEMPERATURE and the following: Reactor water level indication AK3.01 - Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING: RaiSing reactor water level 4.1 ! 39 3.3 40 I I

2.8.41 2.8 42 4.0 43 I

I I

3.6 44 I

  • 3.3.45 I

I

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#lName Safety Function KJA Topic(s}

Ix I AK3.03 - Knowledge of the reasons for the following

  • .295023 Refueling responses as they apply to 3.3 46 i Accidents I 8 REFUELING ACCIDENTS:

Ventilation isolation EK3.03 - Knowledge of the reasons for the following 295030 Low Suppression responses as they apply to X

3.6 47 Pool Water Levell 5 LOW SUPPRESSION POOL WATER LEVEL: RCIC operation: Plant-Specific AA1.01 - Ability to operate andlor monitor the following 700000 Generator Voltage as they apply to and Electric Grid X

GENERA TOR VOL TAGE 3.6 48 Disturbances AND ELECTRIC GRID DISTURBANCES: Grid frequency and voltage.

EA1.02 - Ability to operate andlor monitor the following as they apply to 295026 Suppression Pool SUPPRESSION POOL X

3.6 49 High Water Temp. I 5 HIGH WATER TEMPERATURE:

Suppression pool spray:

i.

Plant-Specific I

AA1.01 - Ability to operate andlor monitor the following i 295003 Partial or Complete as they apply to PARTIAL I

X 3.7 50 Loss of AC 16 OR COMPLETE LOSS OF AC. POWER: AC.

electrical distribution system AA2.03 - Ability to determine and/or interpret the following 295001 Partial or Complete

  • as they apply to PARTIAL Loss of Forced Core Flow X

OR COMPLETE LOSS OF 3.3 51 Circulation I 1 & 4 FORCED CORE FLOW i

CIRCULATION: Actual core flow AA2.04 - Ability to determine and/or interpret the following 295018 Partial or Total as they apply to PARTIAL X

2.9 52 Loss of CCW I 8 OR COMPLETE LOSS OF COMPONENT COOLING WATER: System flow I

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#lName Safety Function KIA Topic(s)

  • Imp.

Q#

AA2.03 - Ability to determine I and/or interpret the following.

295005 Main Turbine X

as they apply to MAIN 3.1 53 Generator Trip / 3 TURBINE GENERATOR

..... TRIP: Turbine valve position

' *. C AK2.03 - Knowledge of the i

I interrelations between 295004 Partial or Total X

PARTIAL OR COMPLETE 3.3 54 Loss of DC Pwr / 6 LOSS OF D.C. POWER and.

the following: DC Bus loads I

2.2.25 - Equipment Control:

I Knowledge of bases in 295038 High Off-site X

Technical Specifications for 3.2 55 IRelease Rate I 9 limiting conditions for I

operations and safety limits.

2.4.50 - Emergency i Procedures I Plan: Ability to verify system alarm setpoints!

295006 SCRAM I 1 X

4.2.56 and operate controls identified in the alarm response manual.

2.4.9 - Emergency I

Procedures I Plan:

Knowledge of low power I j295016 Control Room shutdown implications in X

3.8 57 Abandonment I 7

! accident (e.g., loss of coolant accident or loss of

. residual heat removal) mitigation strategies.

! EK1.01 - Knowledge of the operational implications of 295031 Reactor Low Water the following concepts as X!

4.6

  • 58 Level 12 they apply to REACTOR LOW WATER LEVEL:

Adequate core cooling 314 KIA CategoryTotals 2

4 4

4 i 313 Group Point Total:

I 20/7 i

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#/Name Safety Function KJA Topic(s)

AA2.02 - Ability to determine and/or interpret the following 295015 Incomplete SCRAM X

as they apply to 4.2 83

/1 INCOMPLETE SCRAM :

Control rod position 2.4.31 - Emergency 295014 Inadvertent Reactivity Addition / 1 X

Procedures / Plan:

Knowledge of annunciator alarms, indications, or 4.1 84 response procedures.

AA2.01 - Ability to determine 295007 High Reactor Pressure X

and/or interpret the following as they apply to HIGH REACTOR PRESSURE :

4.1 85 Reactor pressure AK1.01 - Knowledge of the operational implications of 295022 Loss of CRD Pumps /1 X

the following concepts as they apply to LOSS OF CRD 3.3 59 PUMPS: Reactor pressure vs. rod insertion capability AK2.03 - Knowledge of the 295009 Low Reactor Water Level/2 X

interrelations between LOW REACTOR WATER LEVEL and the following:

3.1 60 Recirculation system AK3.02 - Knowledge of the reasons for the following responses as they apply to 295020 Inadvertent Cont.

Isolation / 5 & 7 X

INADVERTENT CONTAINMENT 3.3 61 ISOLATION:

Drywell/containment pressure response EA 1.01 - Ability to operate and/or monitor the following as they apply to 295036 Secondary SECONDARY Containment High X

CONTAINMENT HIGH 3.2 62 Sump/Area Water Level / 5 SUMP/AREA WATER LEVEL : Secondary containment equipment and floor drain systems

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#/Name Safety Function KIA Topic(s) 295007 High Reactor Pressure / 3 295002 Loss of Main Condenser Vac / 3 295029 High Suppression Pool Water Level / 5 X

X X

AK3.04 Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE: Safety/Relief valve operation.

2.4.11 - Emergency Procedures / Plan:

Knowledge of abnormal condition procedures.

EK2.07 - Knowledge of the interrelations between HIGH SUPPRESSION POOL WATER LEVEL and the following :

Dryweillcontainment water level 4.0 63 4.0 64 3.1 65 KIA CategoryTotals 1

2 2

1 0/2 1/1 Group Point Total:

I 7/3

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

A2.05 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; 211000 SLC X

and (b) based on those predictions, use procedures to correct, 3.4 86 control, or mitigate the consequences of those abnormal conditions or operations: Loss of SBLC tank heaters A2.03 - Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based 218000 ADS X

on those predictions, use procedures to correct, 3.6 87 control, or mitigate the consequences of those abnormal conditions or operations: Loss of air supply to ADS valves:

Plant-Specific A2.05 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE 215005 APRM I LPRM X

MONITOR SYSTEM ;

and (b) based on those 3.6 88 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of recirculation flow signal

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 1 System #lName KJA Topic(s) 2.1.23 - Conduct of Operations: Ability to 400000 Component Cooling Water X

perform specific system and integrated plant procedures during all 4.4 89 modes of plant operation.

2.2.40 - Equipment 203000 RHR/LPCI:

Injection Mode X

Control: Ability to apply Technical Specifications 4.7 90 for a system.

K1.06 - Knowledge of the physical connections and/or cause-effect relationships between 239002 SRVs X

RELIEF/SAFETY VALVES and the 3.4 1

following: Drywell instrument air/ drywell pneumatics: Plant-Specific K1.05 - Knowledge of the physical connections and/or cause-effect relationships between 218000 ADS X

AUTOMATIC DEPRESSURIZATION 3.9 2

SYSTEM and the following: Remote shutdown system: Plant-Specific K2.02 - Knowledge of 212000 RPS X

electrical power supplies to the following: Analog 2.7 3

trip system logic cabinets K2.01 - Knowledge of 215004 Source Range Monitor X

electrical power supplies to the following: SRM 2.6 4

channels/detectors

ES-401 Form ES-401-1 System #lName 263000 DC Electrical Distribution 262002 UPS (ACIDC) 205000 Shutdown Cooling 211000 SLC 262001 AC Electrical Distribution Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 1 KIA Topic(s}

K3.03 - Knowledge of the effect that a loss or malfunction of the D.C.

ELECTRICAL X

DISTRIBUTION will have 3.4 5

on following: Systems with D.C. components (Le. valves, motors, solenoids, etc.)

K3.05 - Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE X

POWER SUPPL Y 2.9 6

(A.C.lD.C.) will have on following: Rod worth minimizer: Plant-Specific K4.02 - Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING X

MODE) design feature(s) 3.7 7

and/or interlocks which provide for the following:

High pressure isolation:

Plant-Specific K4.05 - Knowledge of STANDBY LIQUID CONTROL SYSTEM X

design feature(s) and/or interlocks which provide 3.4 8

for the following:

Dispersal of boron upon injection into the vessel K5.02 - Knowledge of the operational implications of the X

following concepts they apply to A.C.

as 2.6 9

ELECTRICAL DISTRIBUTION: Breaker control

ES-401 Form ES-401-1 System #/Name 2150031RM 259002 Reactor Water Level Control

  • 400000 Component Cooling Water 209001 LPCS 217000 RCIC I

Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 1 KiA Topic{s)

K5.03 - Knowledge of I

the operational implications of the following concepts as they apply to X

3.0 10 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM:

Changing detector position K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the X

3.2 11 !

REACTOR WATER LEVEL CONTROL SYSTEM : Plant air systems K6.01 - Knowledge of the effect that a loss or

)

X malfunction of the 2.7 following will have on the CCWS: Valves A 1.03 - Ability to predict and/or monitor changes in parameters associated I with operating the LOW X

3.8 13 PRESSURE CORE SPRAY SYSTEM controls including:

Reactor water level A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the X

REACTOR CORE 3.7 14 ISOLATION COOLING

. SYSTEM (RCIC)

  • controls including: RCIC I

I i flow I

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 1 System #lName KIA Topic(s)

A2.05 - Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those 261000 SGTS X

3.0 15 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fan trips A2.02 - Ability to (a) predict the impacts of the following on the RHRlLPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) 203000 RHRlLPCI:

X based on those 3.5 16 Injection Mode predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Pump trips A3.04 - Ability to monitor I

automatic operations of the EMERGENCY GENERATORS 264000 EDGs X

! (DIESEL/..IET) including:

3.1 17 Operation of the governor control system on frequency and voltage control A3.04 - Ability to monitor

! I automatic operations of the HIGH PRESSURE 209002 HPCS X

3.7 i 18 CORE SPRAY SYSTEM (HPCS) including:

System flow: BWR-5,6 I A4.04 - Ability to manually operate and/or 215005 APRM I monitor in the control X

3.2 19 LPRM room: LPRM back panel switches, meters and I

indicating lights I

I

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

A4.04 - Ability to I

manually operate and/or I

monitor in the 12150031RM X

3.1

20 control room: IRM back panel switches, meters, and indicating lights 223002 2.2.12 - Equipment PCIS/Nuclear X

Control: Knowledge of 3.7 21 Steam Supply surveillance procedures.

Shutoff I

2.1.28 - Conduct of I

I Operations: Knowledge

  • 205000 Shutdown of the purpose and X

4.1 22 COOling function of major system components and I

controls.

2.4.46 - Emergency Procedures / Plan: Ability 215004 Source X

to verify that the alarms 4.2 23 Range Monitor are consistent with the plant conditions.

A2.07 - Ability to (a) predict the impacts of the following on the A.C.

ELECTRICAL DISTRIBUTION; and (b) 262001 AC based on those Electrical X

predictions, use 3.0 24 Distribution procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Energizing a dead bus K3.09 - Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on following:

212000 RPS X

3.2 25 The magnitude of heat energy that must be absorbed by the containment during accident/transient I

I I

  • conditions

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 1 System #/Name KJA Topic(s) 300000 Instrument Air X

K4.03 - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following:

Securing of lAS upon loss of cooling water 2.8 26 KJA Category Totals 2

2 3

3 2

2 2

313 2

2 312 Group Point Total:

I 26/5

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 2 System #lName KIA Topic(s)

A2.04 - Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTERNALS ; and (b) based on those 290002 Reactor X

predictions, use 4.1 91 Vessel Internals procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Excessive heatup/cooldown rate 2.2.22 - Equipment 201003 Control Rod Control: Knowledge of and Drive X

limiting conditions for 4.7 92 Mechanism operations and safety limits.

2.1.19 - Conduct of 259001 Reactor Feedwater X

Operations: Ability to use plant computers to evaluate system or 3.8 93 component status.

K1.04 - Knowledge of the physical connections and/or cause-effect 271000 Off-gas X

relationships between 2.7 27 OFFGAS SYSTEM and the following:

Condensate system K1.02 - Knowledge of the physical connections and/or cause effect 216000 Nuclear Boiler Inst.

X relationships between NUCLEAR BOILER INSTRUMENTATION 3.8 28 and the following:

PCIS/NSSSS

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 2 System #lName KIA Topic(s)

K3.03 - Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL 201002 RMCS X

2.9 29 CONTROL SYSTEM will have on following: Ability to process rod block signals K4.06 - Knowledge of MAIN AND REHEAT STEAM SYSTEM design feature(s) and/or 239001 Main and interlocks which provide X

3.1 30 Reheat Steam for the following: Allows for removal or prevents escape of radioactive steam from systems that have leaky MSIV's K5.04 - Knowledge of the operational implications of the following concepts as 204000 RWCU X

2.7 31 they apply to REACTOR WATER CLEANUP SYSTEM : Heat exchanger operation K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the ROD WORTH 201006 RWM X

2.7 32 MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) : Steam flow input: P-Spec(Not BWR6)

A 1.07 - Ability to predict and/or monitor changes in parameters associated 233000 Fuel Pool with operating the FUEL X

2.7 33 iCooling/Cleanup POOL COOLING AND CLEAN-UP controls including: System I

I tem perature I

ES-401 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline (NRC)

Plant Systems - Tier 2 Group 2 System #/Name KJA Topic(s)

A2.08 - Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL 202002 SYSTEM ; and (b) based Recirculation Flow X

on those predictions, use 3.3 34 Control procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: FCV Lockup (BWR-5,6)

A3.03 - Ability to monitor automatic operations of 215001 Traversing In-core Probe X

the TRAVERSING IN CORE PROBE including: 2.5 35 Valve operation: Not BWR1 A4.02 - Ability to 201003 Control Rod manually operate and/or and Drive X

monitor in the control 3.5 36 Mechanism room : CRD mechanism position: Plant-Specific 2.1.20 - Conduct of 215002 RBM X

Operations: Ability to interpret and execute 4.6 37 procedure steps.

K4.03 - Knowledge of FUEL HANDLING EQUIPMENT design feature(s) and/or 234000 Fuel Handling Equipment X

interlocks which provide for the following :

3.4 38 Protection against inadvertently lifting radioactive components out of the water KJA Category Totals 2

0 1

2 1

1 1

1/1 1

1 1/2 Group Point Total:

I 12/3

ES-401 Nine Mile Point Unit 2 Form ES-401-3 Written Examination Outline (NRC)

Generic Knowledge and Abilities Outline (Tier 3)

Facility:

NMP2 N Date:

Category KA#

Topic RO SRO-Only IR Q#

IR Q#

2.1.41 Knowledge of the refueling process.

2.8 66 2.1.36 Knowledge of procedures and limitations involved in core alterations.

3.0 67

1. Conduct of Ability to use procedures related to shift Operations 2.1.5 staffing, such as minimum crew 3.9 94 complement, overtime limitations, etc.

2.1.32 Ability to explain and apply all system limits and precautions.

4.0 100 Subtotal 2

2 Ability to manipulate the console 2.2.2 controls as required to operate the facility between shutdown and 4.6 68 designated power levels.

2.2.13 Knowledge of tagging and clearance procedures.

4.1 69 2.2.38 Knowledge of conditions and limitations in the facility license.

3.6 74

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

Ability to analyze the effect of 2.2.36 maintenance activities, such as degraded power sources, on the status 4.2 99 of limiting conditions for operations.

Subtotal 3

2

ES-401 Nine Mile Point Unit 2 Form ES-401-3 Written Examination Outline (NRC)

Generic Knowledge and Abilities Outline (Tier 3) 2.3.14 2.3.12

3. Radiation Control 2.3.13 Subtotal 2.4.17 2.4.12 2.4.29
4. Emergency Procedures /

2.4.20 Plan 2.4.22 Subtotal Tier 3 Point Total:

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

Knowledge of EOP terms and definitions.

Knowledge of general operating crew responsibilities during emergency operations.

Knowledge of the emergency plan.

Knowledge of operational implications of EOP warnings, cautions, and notes.

Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

3.4 70 3.2 71 3.8 96 2

1 3.9 72 4.0 73 3.1 75 4.3 97 4.4 98 3

2 10 7

ES-401 Record of Rejected KIA's Form ES-401-4 Tier / Group Randomly Selected KA Reason for Rejection Question 41, Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Classifications by type. Low level of difficulty.

1 / 1 600000/ AK1.01 Randomly selected AK3.04 - Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE:

Actions contained in the abnormal procedure for plant fire on site Question 64, Equipment Control: (multi-unit license) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a 1 /2 295002 / 2.2.4 facility. (Loss of Main Condenser Vac). NMP2 is not a multi-unit license.

Randomly selected G2.4.11 - Emergency Procedures / Plan:

Knowledge of abnormal condition procedures.

Question 88, Equipment Control: (multi-unit license) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility. (APRMs). NMP2 is not a multi-unit facility.

2/1 215005/2.2.4 Randomly selected A2.05 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of recirculation flow signal Question 89, Conduct of Operations: Knowledge of system purpose and / or function (Component cooling water). Not discriminatory at the SRO level.

2/1 400000/2.1.27 Randomly selected G2.1.23 - Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Question 31, Knowledge of the operational implications of the following concepts as they apply to RADWASTE: Units of radiation, dose and dose rate. Low level of difficulty.

2/2 268000/ K5.01 Randomly selected 204000 K5.04 - Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER CLEANUP SYSTEM: Heat exchanger operation

ES-401 Record of Rejected KIA's Form ES-401-4 2/2 2010061 K6.02 Question 32, Knowledge of the effect that a loss or malfunction of the following will have on the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC): Reactor water level control input: P-Spec(Not-BWR6). NMP2 is not a not a BWR6.

Randomly selected K6.05 - Steam flow input: P-Spec(Not BWR6) 3/2 G2 1 2.2.17 Question 69, Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, coordination with the transmission system operator. This is an SRO function per NMP2 procedures.

Randomly selected G2.2.13 - Knowledge of tagging and clearance procedures 1 11 2950191 AK2.13 Question 42, Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following :

Isolation condenser: Plant-Specific. NMP2 does not have isolation condensers.

Randomly selected AK2.08 - Plant Ventilation 2/1 2950071 AA2.02 Question 85, Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor power.

Same KA as RO #63.

Randomly selected AA2.01 - Reactor pressure 2/1 3000001 A4.01 Question 20, Ability to manually operate and/or monitor in the control room : Pressure gauges. Instrument Air oversampled throughout exam. (42,77,87)

Randomly selected 215003 A4.04 - Ability to manually operate and/or monitor in the control room : IRM back panel switches, meters, and indicating lights Question 90, Equipment Control: Ability to apply Technical Specifications for a system. Nuclear Instrumentation is oversampled throughout exam.

2/1 215003/2.2.40 Randomly selected 203000 2.2.40- RHR/LPCI: Injection Mode, Equipment Control: Ability to apply Technical Specifications for a system

ES-401 Record of Rejected KiA's Form ES-401-4 I

  • Question 15, Ability to (a) predict the impacts of the following on

!the STANDBY GAS TREATMENT SYSTEM; and (b) based on

  • those predictions, use procedures to correct, control, or mitigate
  • the consequences of those abnormal conditions or operations:

2/1 261000/A2.04 High train moisture content. Low discriminatory value at the license operator level.

!Randomly selected A2.05 - Fan Trips Question 28, Knowledge of electrical power supplies to the

!following: Analog trip system: Plant-Specific. Analog trip system does not apply at NMP2 2/2 216000/K2.01

  • Randomly selected K1.02 - Knowledge of the physical connections andlor cause effect relationships between NUCLEAR BOILER INSTRUMENTATION and the following:

PCIS/NSSSS Question 34, Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or 2/2 2020021 A2.03 operations: Loss of D.C. DC control for system does not apply at NMP2.

Randomly selected A2.08 - FCV Lockup Question 43, Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following: Rod 1 /1 295037 / EK2.12 control and information system: Rod control and information system: Plant-Specific. RCIS does not apply at NMP2.

Randomly selected EK2.09 - Reactor water level I

Question 49, Ability to operate and/or monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Temperature monitoring. Low level of 1/1 295026 1 EA 1.03 difficulty.

Randomly selected EA1.02 - Suppression pool spray.

i Question 53, Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: Reactor water level. The tie between reactor level and turbine trip is the 1/1 2950051 AA2.07 high level trip to prevent moisture carryover and subsequent shrink/swell. This is a low level of difficulty topic.

Randomly selected AA2.03 - Turbine valve position I

ES-401 1 / 1 295004/2.2.38 1 11 700000/ AA2.06 1 / 1 295037 / 2.2.36 3/3 G2 / G2.3.6 1 /1 295025/ EK1.03 1 /2 295007/ AA2.02 Record of Rejected KIA's Form ES-401-4 Question 54, Equipment Control: Knowledge of conditions and limitations in the facility license. Although there are procedural and TS requ irements for this system there are no limitations in the facility license. Other KAs would address TS.

Randomly selected AK2.03 DC Bus loads (Partial or complete loss of DC)

Question 76, Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Generator frequency limitations. Topic similar to RO #48.

Randomly selected AA2.05 - Operational status of offsite circuit Question 81, Equipment Control: Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. An operationally valid question could not be written because the topic does not align with the APE, SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown, In this situation, EOP implementation is the concern, not LCO status.

Randomly selected 2.4.6 - Knowledge of EOP mitigation Strategies Question 99, Ability to approve release permits. This function is rarely done and is mainly performed thru chemistry and radwaste procedures.

Randomly selected G2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

Question 40, Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE: Safety/relief valve tailpipe temperature/pressure relationships. Topic resulted in a question not at a discriminating level for a licensed operator.

Randomly selected EA1.08 - Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE: RRCS Question 63, Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor power.

Original question resulted in distracters that were not plausible at the licensed level.

Randomly selected AK3.04 Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE : Safety/Relief valve operation.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:__---!N.!.!M.!..!.!...;P2!::...--N~R~C~__

Examination Level: RO Administrative Topic Type Code*

(see Note)

Conduct of Operations N,R Conduct of Operations D,R Equipment Control M,R Emergency Plan M,S Date of Examination: 11/10 Operating Test Number:

1 Describe activity to be performed Verification of License Requirements Given information related to maintenance of active license status for three operators, the candidate will determine which operator(s), if any, is(are) qualified to relieve the watch.

2.1.4 (3.3) Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

S-ODP-TOS-01 0i-R0050 Determine Core Thermal Power lAW N2-REP-11 The candidate will determine core thermal power using turbine first stage pressure in accordance with N2-REP-i1 KIA 2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Develop a Tagging Request for the "8" T8CLCW Pump The candidate will develop and document a tagging request for the "B" TBCLCW Pump.

KIA 2.2.13 (4.3) Knowledge of tagging and clearance procedures.

CNG-OP-1.01-1007 Actions For External Security Threats Given plant conditions, respond to a security threat per EPI P EPP-10, Attachment 2, Security Contingency Event (CSa Checklist) 2.4.28 (3.2) Knowledge of procedures relating to a security event (non-safeguards information).

EPIP-EPP-10 Attachment 2 SAME AS UNIT 1 EXAM

NOTE:

All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria:

(Clontrol room, (S)imulator, or Class(Rjoom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (.:::1)

(P)revious 2 exams (~1; randomly selected)

E5-301 Administrative Topics Outline Form E5-301-1 Facility:

NMP2-NRC Examination Level: SRO Administrative Topic (see Note)

Conduct of Operations Type Code*

M,R Conduct of Operations D,R Equipment Control N,R Radiation Control P,R Date of Examination: 11/10 Operating Test Number:

1 Describe activity to be performed Review Daily Checks Log lAW N2-0SP-LOG-D001 The candidate will review a completed portion of control room daily logs. Identify deficiencies and TS requirements.

KIA 2.1.18 (3.8) Ability to make accurate, clear, and concise logs, records, status boards, and reports.

Evaluate Plant Chemistry Report (GAP-CHE-01, TS)

Review plant daily status report, which includes plant chemistry, identify and determine required actions in response to out-of-specification reactor coolant chemistry parameters.

KIA 2.1.34 (3.5) Ability to maintain the primary and secondary plant chemistry within allowable limits.

Review of Completed Surveillance Test N2-0SP-CPS Q001, Primary Containment Purge System Valve Operability Test.

The candidate will review a completed surveillance test to determine acceptability KIA 2.2.12 (4.3) Knowledge of surveillance procedures Emergency Exposure Authorization Review and Approval The candidate will review the exposure status of personnel to determine expected radiation exposure and the need for an Emergency Exposure Authorization.

KIA 2.3.4 (3.7) Knowledge of radiation exposure limits under normal or emergency conditions.

SAME JPM ON UNIT 1 EXAM

Classify Emergency Event Emergency Plan Given plant conditions, evaluate emergency event D,R KIA 2.4.44 (4.4) Knowledge of emergency plan protective action recommendations.

NOTE:

All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

'" Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom

{D}irect from bank (::£3 for ROs;::£ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank t::1)

(P}revious 2 exams (::£1; randomly selected)

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Nine Mile Point Unit 2 Date of Examination:

November 2010 Exam Level: RO/SRO Operating Test No.:

1 Control Room Systems@ (8 for RO; 2 or 3 for SRO-U, including 1 ESF)

I e*

Safety Function System 1JPM Title Start the DIV1 H2I02 Monitoring from the Suppression D,EN,S 5

S-1 Chamber Post LOCA CONTAIMENT INTEGRITY The candidate will restart the H2/02 monitoring system post LOCA and sample from the suppression chamber lAW N2 OP-82 Sections F.1.0 and H.2.0 KIA 223001 A4.04 3.5/3.6 Add Air to a De-inerted Drywell M,L,S S-2 9

RADIOACTIVITY The candidate will raise drywell pressure using the RELEASE primary containment purge fan lAW N2-0P-61A Section I

H.3.0 KIA 261001 A4.04 3.3/3.4 I

Securing and Restart of Shutdown Cooling M,A,L,S S-3 4

HEAT REMOVAL The candidate will secure SDC for a short period of time and FROM RXCORE then restart the pump. During the restart, a failure of the throttle valve results in the inability to establish required flow and a pump trip is required lAW N2-0P-31 Sections H.3.0 &

4.0 i

KIA 205000 A4.01 3.7/3.7 I

1 Ii S-4 Return WCS to Normal D,A,S 2

I REACTOR WATER The candidate will return WCS to normal following INVENTORY feeedwater stratification operation lAW N2-0P-37. Actions CONTROL I

will be required due to an isolation signal lAW the ARP.

KIA 204000 A4.03 3.2/3.1 Start and Load Division I Diesel D,A,S S-5 6

ELECTRICAL The candidate will start and load the Division I Diesel lAW N2-0P-100A. Section F.4.0. A loss of SW will occur requiring a diesel shutdown.

KIA 264000 A4.04 (3.7/3.7)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S-6 Place Main Turbine Shell Warming in service M,L,S 3

RO REACTOR The candidate will place Main Turbine Shell Warming in PRESSURE ONLY service lAW N2-0P-21, Section E.3.0.

CONTROL KIA 241000 A4.18 2.9/2.8 S-7 Transfer Recirc Pumps from High to Low speed D,S 1

REACTIVITY CONTROL The candidate will transfer Recirc Pumps from high speed to low speed per N2-0P-29 section G.1.0.

KIA 202001 A4.01 3.7/3.7 S-8 Shift RBCLCW and TBCLCW Pumps P,A,S 8

PLANT SERVICE The candidate will shift RBCLCW Pumps from "A" to "C",

SYSTEMS then shift TBCLCW Pumps from "An to "Cn lAW N2-0P-13 &

14. Actions will be required due to a failure of the TBCLCW temperature controller KA 400000 A4.01 3.1/3.0 In-Plant Systems@ (3 for RO; 3 or 2 for SRO-U)

P-1 Start the Diesel Fire Pump Locally M

8 PLANT SERVICE SYSTEMS The candidate will start the Diesel Fire Pump locally lAW N2 OP-43 Section E.3.0.

KIA 2860002.1.304.4/4.0 P-2 Hydro Pump Boron Injection D,E,R 1

REACTIVITY CONTROL The candidate will Commence boron injection with the hydro pump lined up to 2SLS*P1A piping in accordance with EOP 6, Attachment 15.

KIA 295037 EA 1.103.7/3.9 Reset an EPA Breaker P-3 D,R 6

ELECTRICAL The candidate will Reset EPA Breaker 2VBS*ACB2A with an Overvoltage condition present lAW N2-S0P-97 KA 262001 2.1.234.3/4.4

II ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank s9/s8/$4 (E)mergency or abnormal in-plant
1/;
:1/;::1 (EN)gineered safety feature

- / -

/ ;::1 (control room system)

(L)ow-Power / Shutdown

1/;
:1/;::1 (N)ew or (M)odified from bank including 1 (A)
2/;
:2/;::1 (P)revious 2 exams s 3 / S 3 / s 2 (randomly selected)

(R)CA

1/;
:1/;::1

{S)imulator

Appendix 0 Scenario Outline Form ES-O-1 Facility: Nine Mile Point Unit 2 Scenario No.: NRC-01 Op-Test No.: 11/2010 Examiners:

Operators: __________

Initial Conditions: Simulator IC-21 or equivalent 1. Reactor Power 95%

Turnover:

1.

95% power.

2.

Add water to the su pool with CSH lAW N2-0P-33 Malf. No.

Event Descri on Add water to the suppression pool with CSH 2

CS08 EHC Oscillations - Power reduction requ 3

TC03A 4

5 Steam Line break in Drywell EOP-RPV, EOP-PC Loss of Line 6 SOP-03 (I)nstrument, (C)omponent, (M)ajor NRC Scenario 1

-1 November 2010

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 2 Scenario No.: NRC-02 Op-Test No.: 11/2010 Examiners:

Operators: __________

Initial Conditions: Simulator IC-21 or equivalent

1.

Reactor Power 100%

Turnover:

1.

100% power.

2.

Perform section 8.2 of N2-0SP-RPS-W002, Manual Scram Test Channel "A" Event Malf. No.

Event Event No.

Type*

Oescri Perform section 8.2 of N2-0SP-RPS-W002, Manual Scram Test Channel "A" only N (BOP) 1 Override N (SRO)

TS (SRO)

Indication Failure during test at step 8.2.11 remains in alarm Annunciator TS 3.3.1.1 Spurious start of HPCS 2

"A" Recirc pump high vibration requires a manual trip by operators. Subsequently the uBnRecirc pump trips requiring a RR46A 6

C (ALL) manual scram.

RR10B SOP~29.1, SOP~29, SOP-101C 8

EOP~C5

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 2 November 2010

6 Appendix 0 Scenario Outline Form ES-O-1 Facility: Nine Mile Point Unit 2 Scenario No.: NRC-OS Op-Test No.: 11/2010 Examiners:

Operators: __

Initial Conditions: IC-11 or equivalent

1. Reactor Power 4.5%

Turnover:

1. For a PMT, perform DW to SC Vacuum Bkr test N2-0SP-ISC-M@002 for 2ISC*RV33A &

2ISC*RV33B

1. Continue plant startup to place the reactor mode switch to RUN per N2-0P-101A. Currently complete th E.3.3 Event Loss of Power to Div II switchgear RCIC Steam Line Isolation Valve ICS*MOV128 breaker trips 7

Override TS (SRO) open TS 3.6.1.3 RCIC steam leak into reactor building fails to isolate 8

M (ALL)

EHC pumps trip C (BOP)

FW02A,B,C C (SRO)

EOP-RPV (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 5 November 2010 9

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