ML042730207

Draft Outlines (ES-401-1 to E-D-1) (Folder 2)

ML042730207
Person / Time
Site:	Susquehanna
Issue date:	08/09/2004
From:	Roush K PPL Generation
To:	Conte R NRC/RGN-I/DRS/OSB
References
50-387/04-302, 50-388/04-302 50-387/50-388/04-302
Download: ML042730207 (29)

Text

ES-401 BWR Examination Outline Form ES-401-1 1 Facility:-

Tier 1

1.

Emergency Abnormal Plant Evolutions

2.

Plant Systems

3.

Note:

1 1 4 l o Tier 4

Totals 2#

Totals

1.

2.

3.

4.

5.

6.

7.

8.

9.

Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the Tier Totals in each WA category shall not be less than two). Refer to Section D. I

.c for additional guidance regarding SRO sampling.

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 k l 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.

Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryher.

• The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

On the following pages, enter the WA 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA str.2ments.

NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Page 1 of 11 Susquehanna Facsimile

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11 ES-401 BWR Examination Outline Form ES-401-1 lant Evolutions - Tier I/Group I(R0)

WA Topic(s)

I 1

EIAPE # / Name / Safety Function I and I K

A 3

1 x

X IR -

3.1 AA2. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

AA2.02 Neutron monitoring 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 (01)

~

295003 Partial or Complete Loss of AC / 6 (02) 295004 Partial or Total Loss of DC Pwr / 6 (03)

AK3. Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :

AK3.01 Manual and auto bus transfer 3.3 3.1 AK2. Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C.

POWER and the following:

AK2.01 Battery charger 2.4.1 1 Knowledge of abnormal condition procedures.

295005 Main Turbine Generator Trip I 3 (041 3.4 -

3.8 3.7 295005 Main Turbine Generator Trip / 3 (05)

AK2. Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following:

AK2.01 RPS AK1. Knowledge of the operational implications of the following concepts as they apply to SCRAM :

AKI.03 Reactivity control

!95006 SCRAM / 1 (06)

AA2. Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT :

AA2.01 Reactor power AKI. Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :

AKI.01 Effects on component/system operations 4.1 3.5 29501 6 Control Room Abandonment I 7 (07) 295018 Partial or Total Loss of CCW / 8 (08)

AA1. Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :

AA1.02 Instrument air system valves:

29501 9 Partial or Total Loss of Inst. Air / 8 (09) 3.3 2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

295021 Loss of Shutdown Cooling I 4 (0101 3.3 AK3. Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS :

AK3.02 Interlocks associated with fuel handling equipment 3.4 295023 Refueling Accidents Cooling Mode

/ 8 (011)

~ a g e 2 of 11 NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

11 ES-401 BWR Examination Outline Form ES-401-I I

ElAPE # I Name I Safety Function lant Evolutions - Tier 1lGroup l(R0)

WA Topic@)

IR EK3. Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE :

295024 High Drywell Pressure 1 5 fQf2)

EK3.05 tRPV flooding EA1. Ability to operate andlor monitor the following as they apply to HIGH REACTOR PRESSURE:

295025 High Reactor Pressure 13 (Q13)

EAI.05 RCIC: Plant-Specific EK1. Knowledge of the operational implications of -

the SUPPRESSION following concepts POOL as HIGH they WATER apply to TEMPERATURE :

t 295026 Suppression Pool High Water Temp. I 5 fQ14)

EKI.02 Steam condensation EA1. Ability to operate andlor monitor the following as they apply to HIGH DRYWELL TEMPERATURE :

EAI.05 ADS 295028 High Drywell Temperature 15 fQl5) 2.4.48 Ability to interpret control room indications to verify the status and operation of system I and understand how operator action s and directives affect plant and system conditions.

295030 Low Suppression Pool Water Level 1 5 (Qf6) 3.5 I

EK1. Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL :

95031 Reactor Low Water Level 12

( ~ 1 7 )

3.8 1

EKI.02 Natural circulation: Plant-Specific I

I EK3. Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

3.2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 (Ql8) tr EK3.05 Cold shutdown boron weight: Plant-Specific EK2. Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following:

3.6 295038 High Off-site Release Rate / 9 (Q19) 600000 Plant Fire On Site I 8 (QW AA1 Ability to operate and I or monitor the AA1.06 Fire alarm 20 Group Point Total:

WA Category Totals:

~ a g e 3 of 11 Susquehanna Facsimile NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0

I ES-401 BWR Examination Outline F

o

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ES-401-1 Emergency and Abnormal Plant Evolutions - Tier l/Group 2(RO)

IR -

3.2 3.6 WA Topic(s)

E/APE # / Name / Safety Function AA2. Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM :

AA2.02 Reactor power: Plant-Specific 295002 Loss of Main Condenser Vacuum /

3 (QW

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AA2. Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL :

AA2.02 Steam flow/feed flow mismatch 295009 Low Reactor Water Level I 2 (Q22)

AK3. Knowledge of the reasons for the following responses as they apply to INADVERTENT CONTAINMENT ISOLATION:

AK3.05 Reactor water level response EK2. Knowledge of the interrelations between HIGH SUPPRESSION POOL WATER LEVEL and the following:

EK2.02 HPCI: Plant-Specific EK3. Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE :

EK3.03 Isolating affected systems EAI. Ability to operate and/or monitor the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS :

EA1.08 Control room ventilation: Plant-Specific EA2. Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:

EA2.02 t Off-site release rate: Plant-Specific 295020 Inadvertent Cont. Isolation / 5 & 7 (Q23) 3.8 3.4 295029 High Suppression Pool Water Level I 5 (024) 3.8 295032 High Secondary Containment Area Temperature I 5

'QZS) 295033 High Secondary Containment Area Radiation Levels / 9 (QW 3.6 2.8 T

295035 Secondary Containment High Differential Pressure / 5 (Q27)

Group Point Total:

WA Category Point Totals:

Page 4 of 11 NUREG-1021. Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

ll ES-401 BWR Examination Outline F

o

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ES-401-1 Plant Systems

- Tier 2/Group 1 (RO)

IR -

2.6 KIA Topic(s)

System #

K 1

~

~~~

2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

203000 RHWLPCI: Injection Mode c

( Q W 205000 Shutdown Cooling fQ29)

A3. Ability to monitor automatic operations of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including A3.03 Lights and alarms 3.5 3.4 3.8

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K4. Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.11 Turbine speed control: BWR-2,3,4 A4. Ability to manually operate andlor monitor in the control room:

A4.05 Manual initiation controls 206000 HPCl (Q30) 209001 LPCS (037) 31 1000 SLC 4 Q32)

K3. Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:

K3.02 Core spray line break detection system: Plant-Specific 3.0 3.5 I

K6. Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR PROTECTION SYSTEM :

K6.05 RPS sensor inputs 212000 RPS (Q33)

A3. Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including:

A3.04 System status lights and alarms 212000 RPS (Q34) 3.9 4.0 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

K3. Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM) SYSTEM will have on following:

K3.01 RPS 215003 IRM fQ35) 215004 Source Range Monitor I

(Q36) 3.4 NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Page 5 of 11 Susquehanna Facsimile

II BWR Examination Outline Form ES-401-1 II ES-401

{stems

- Tier 2/Groul Plant IR 3.6 4.1 2.8 3.4 System #

A4. Ability to manually operate and/or monitor in the control room:

A4.06 Verification of proper functioning/ operability 21 5005 APRM / LPRM (Q37)

A4. Ability to manually operate and/or monitor in the control room:

A4.05 Reactor water level 21 7000 RClC (Q38) 217000 RClC (Q39)

K4. Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) design feature@) and/or interlocks which provide for the following:

K4.01 Prevent water hammer: Plant-Specific AI. Ability to predict and/or monitor changes in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including:

A I.01 ADS valve tail pipe temperatures 21 8000 ADS (040)

K3. Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR STEAM SUPPLY SHUT-OFF will have on following:

K3.21 Traversing in-core probe system 2.1.27 Knowledge of system purpose and or function.

223002 PCIS/Nuclear Steam Supply Shutoff (041) 2.6 2.8 4.2 223002 PClSlNuclear Steam Supply Shutoff (Q44 239002 SRVs tQ43)

K3. Knowledge of the effect that a loss or malfunction of the RELlEFlSAFETY VALVES will have on following:

K3.02 Reactor over pressurization K6. Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES 1 K6.02 Air (Nitrogen) supply: Plant-Specific 239002 SRVs (Q44) 3.4 NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 page 6 of 11 Susquehanna Facsimile

I ES-401 BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2IGroup 1 (RO)

System #

WA Topic@)

K6. Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM :

K6.04 Reactor feedwater flow inDut 259002 Reactor Water Level Control (045) 3.1 A2. 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:

A2.11 High containment pressure A3. Ability to monitor automatic operations of the A.C. ELECTRICAL DISTRIBUTION including:

A3.04 Load sequencing 261 000 SGTS (046) 3.2 3.4 262001 AC Electrical Distribution (Q47)

K4. Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature@) and/or interlocks which provide for the following:

K4.01 Transfer from preferred power to alternate Dower sutmlies 262002 UPS (ACIDC)

(048) 3.1 A2. Ability to (a) predict the impacts of the following on the D.C.

ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.02 Loss of ventilation during charging A4. Ability to manually operate and/or monitor in the control room:

A4.03 Transfer of emergency control between manual and automatic K1 Knowledge of the connections and / or cause effect relationships between INSTRUMENT AIR SYSTEM and the following:

K1.04 Cooling water to compressor 263000 DC Electrical Distribution (049) 2.6 3.2 2.8 264000 EDGs (050) 300000 Instrument Air (051)

~ a g e 7 of 11 NUREG-1021, Drafi Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

ll System #

I I

300000 Instrument Air 400000 Component Cooling Water fQ53)

WA Category Point Totals:

1 0

NUREG-I 021, Draft Rev 9 2004 NRC Exam Rev. 0 BWR Examination Outline Form ES-401-1 Plant Systems Page 8 of 11

- Tier 2IGroup 1 (RO) r T

G WA Topic(s)

A2. Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

I A2.01 Air dryer and filter malfunctions 1

AI. Ability to predict and / or monitor changes in parameters associated with operating the CCWS controls including:

A I.01 CCW flow rate Group Point Total:

Susquehanna Facsimile

I1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2IGroup 2(RO)

IR -

3.6 -

3.7 System #

WA Topic(s) 201001 CRD Hydraulic (Q54)

K2. Knowledge of electrical power supplies to the following:

K2.02 Scram valve solenoids AI. Ability to predict andlor monitor changes in parameters associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including:

A I.01 Reactor power K5. Knowledge of the operational implications of the following concepts as they apply to ROD BLOCK MONITOR SYSTEM :

K5.01 Trip reference selection: Plant-Specific 201003 Control Rod and Drive Mechanism (Q55) 215002 RBM (Q56) 2.6 223001 Primary CTMT and Auxiliaries (057)

A3. Ability to monitor automatic operations of the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES including:

A3.04 Containmenffdrywell response during LOCA 4.2

?26001 RHWLPCI: CTMT Spray Aode (Q58)

A2. Ability to (a) predict the impacts of the following on the RHWLPCI:

CONTAINMENT SPRAY SYSTEM MODE ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.13 Valve logic failure 2.8 230000 RHWLPCI: Torus/Pool Spray Mode (Q59)

K2. Knowledge of electrical power supplies to the following:

K2.02 Pumps AI. Ability to predict and/or monitor changes in parameters associated with operating the REACTOWURBINE PRESSURE REGULATING SYSTEM controls including:

AI.01 Reactor pressure 2.8 -

3.9 241000 Reactor Turbine Pressure Regulating System

( Q W 245000 Main Turbine Gen. and Auxiliaries (Q67)

K3. Knowledge of the effect that a loss or malfunction of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on following:

K3.07 Reactor protection system 3.6 NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Page 9 of 11 Susquehanna Facsimile

Form ES-401-1 WA Topic(s)

IR ES-401 BWR Examination Outline Plant Systems

- Tier 2/Group 2(RO)

K5. Knowledge of the operational implications of the following concepts as they apply to PLANT VENTILATION SYSTEMS :

K5.02 Differential pressure control 3.2 Svstem #

I K ( K ( K 1

1 1 1 2 1 3 WA Category Point Totals:

I I 13 286000 Fire Protection 1

2 2

K K

A 5

6 1

X X

K1. Knowledge of the physical connections andlor cause effect relationships between RADIATION MONITORING SYSTEM and the following:

K1.06 Reactor building ventilation system: Plant-Specific K3. Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on following:

K3.01 The ability to detect fires K6. Knowledge of the effect that a loss or malfunction of the following will have on the SECONDARY CONTAINMENT :,

K6.04 Primary containment system 12 Group Point Total:

NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Page 10 of 11 Susquehanna Facsimile

Generic Knowledge and Abilities Outline Tier 3 Form ES-40 1-3 Date of Exam 8/09-8113 2004 I ES 401 icility SUSOUEHANNA 1

RC Topic I

Category IR 2.1.1 Knowledge of conduct of operations requirements.

3.7

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control 2.1 2 8 Knowledge of the purpose and function of major system components and controls.

3.2 2.1.33 Ability to recognize indications for system operating parameters vhich are entry-level conditions for technical specifications.

3.4 3.0 Subtc a1 2.2 (Q69) 2.2 fQ70) procedures.

2.2.1 2 Knowledge of surveillance procedures.

2.2.13 Knowledge of tagging and clearance 3.6 Subtotal 2.7 2.6 Subtotal 2.4 (Q73) 2.4 fQ74) 2.4 (Q75) 3.0 2.9 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

2.4.48 Ability to interpret control room indications to verify the status and operation of system I and understand how operator action s and directives affect plant and srjtem conditions.

3.5 Page 11 of 11 NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

ES-401 BWR Examination Outline Form ES-401-1

/I Facility:-

Tier

1.

Emergency Abnormal Plant Evolutions

2.

Plant Systems

3.

Note:

1.

2.

3.

4.

5.

6.

7.

8.

9.

SUSOUEHANNA Date of Exam 8/09-8113 2004 Ensure that at least two topics from every KIA category are sampled within each tier of the RO outline (Le., the Tier Totals in each WA category shall not be less than two). Refer to Section D.l.c for additional guidance regarding SRO sampling.

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 &I 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.

Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryher.

• The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

NUREG-I 021, Draft Rev 9 2004 NRC Exam Rev. 0 Page 1 of 6 Susquehanna Facsimile

BWR Examination Outline Form ES-401-1 ES-401

' and Abnormal Plant Evolutions - Tier I/Group 1 (SRO)

II Emc WA Topic@)

EIAPE # I Name / Safety Function 295005 Main Turbine Generator Trip / 3 2.2.1 Ability to perform pre-startup procedures for the facility / including operating those controls associated with plant equipment that could affect reactivity.

(IOCFR 55.43) 3.6 AA2. Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT :

AA2.06 Cooldown rate (IOCFR 55.43) 11 295016 Control Room Abandonment / 7 tQ77) 3.5 AA2. Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :

AA2.02 Status of safety-related instrument air system loads (IOCFR 55.43)

AA2. Ability to determine andlor interpret the following as they apply to LOSS OF SHUTDOWN COOLING :

AA2.07 Reactor recirculation flow (IOCFR 55.43)

AA2. Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS :

AA2.05 tEntry conditions of emergency plan (IOCFR 55.43) 2.1.32 Ability to explain and apply system limits and precautions.

(IOCFR 55.43) 3.7 3.1 4.6 3.8 295019 Partial or Total Loss of Inst. Air / 8 tQ78) 295021 Loss of Shutdown Cooling / 4 (079) 295023 Refueling Accidents Cooling Mode 18 (QW 295024 High Drywell Pressure / 5 (987)

EA2. Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

EA2.03 Reactor pressure (1 OCFR 55.43) 295026 Suppression Pool High Water Temp. I 5 (982) 4.0 2.4.25 Knowledge of fire protection procedures.

(1 OCFR 55.43) 600000 Plant Fire On Site / 8 (Q83) 3.4 T 8 Group Point Total:

WA Category Totals:

Page 2 of 6 Susquehanna Facsimile NUREG-I 021, Draft Rev 9 2004 NRC Exam Rev. 0

ES-401 Em ElAPE # / Name / Safety Function 295014 Inadvertent Reactivity Addition (084)

K 1

295032 High Secondary Containment Area Temperature / 5 295036 Secondary Containment High SumplArea Water Level / 5 (QW 500000 High Containment Hydrogen Conc.

15 (Q87)

I z --

WA Category Point Totals:

0 NUREG-I 021, Draft Rev 9 2004 NRC Exam Rev. 0 BWR Examination Outline Form ES-401-1 lency and Abnormal Plant Evolutions - Tier l/Group 2(SRO)

~

KIA Topic($

AA2. Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION :

AA2.03 Cause of reactivity addition (1 OCFR 55.43) 2.1.20 Ability to execute procedure steps.

(10CFR 55.43)

EM. Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL :

EA2.03 Cause of the high water level (IOCFR 55.43)

EA2 Ability to determine and / or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:

EA2.03 Combustible limits for drywell (1 OCFR 55.43)

Group Point Total:

4.3 4.2 3.8 3.8 T 4 Page 3 of 6 Susquehanna Facsimile

BWR Examination Outline ES-401 Form ES-401-1 Plant Systems

- Tier 2IGroui IR -

3.4 WA Topic(s)

A2. Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 A.C. power failures (1 OCFR 55.43) 21 1000 SLC fQW

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A2. Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.16 Changing mode switch position (IOCFR 55.43) 4.1 3.6 3.3 212000 RPS

((289) 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations.

(IOCFR 55.43) 2.2.6 Knowledge of the process for making changes in procedures as described in the safety analysis report.

(IOCFR 55.43) 239002 SRVs (Q90) 262001 AC Electrical Distribution (Q9.I)

T4

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Group Point Total:

ll WA Category Point Totals:

Page 4 of 6 Susquehanna Facsimile NUREG-1021. Draft Rev 9 2004 NRC Exam Rev. 0

BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2IGroup 2(SRO)

System #

201001 CRD Hydraulic (Q92) 216000 Nuclear Boiler Instrumentation (Q93)

WA Category Point Totals:

NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Page 5 of 6 K/A Topic(s)

A2. Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM :

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

A2.13 Low cooling water flow (I

OCFR 55.43)

A2. Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.04 Detector diaphragm failure or leakage (IOCFR 55.43)

Group Point Total:

IR -

2.8 3.0

i=

I

• Susquehanna Facsimile

ES 401 Generic Knowledge and Abilities Outline Tier 3 Form ES-40 1-3 1

Category

1.

Conduct of Operations

2.

Equipment Control

3.

Yadiation

..__= Control

4.

Emergency Procedures/

Plan Tier 3 Point 'I 2.2 (095) 2.2 (096) 2.4 (099) 2.4 (0100)

NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Page 6 of 6 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Group Randomly Selected WA Reason for Rejection NIA N/A As per letter PIA005439 PLA14-13 from Jeff Helsel (PPL) to Alan Blamey (NRC) dated Feb. 4'h 2002 all WAS that are not applicable to SSES design were suppressed. A copy of this letter and the specific WAS involved is available upon request.

1 I1 2.4.28 RO Importance rating is less than 2.5 1 /2 1 I2 295002 AA21.03 29501 7 RO Importance rating is less than 2.5 High Offsite Release already addressed with 295038 in Tier 1 Group 1.

For purposes of a balanced exam, another Tier 1 Group 2 system would be more appropriate.

Not applicable to SSES. Filter Building does not exist.

212 272000 K1.I 5

2t2 290001 K6.06 RO Importance rating is less than 2.5 3

2.1.26 RO Importance rating is less than 2.5 3

2.2.6 RO Importance rating is less than 2.5 RO Importance rating is less than 2.5

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2.2.7 3

3 2.2.1 0 RO Importance rating is less than 2.5 3

2.2.1 1 RO Importance rating is less than 2.5 3

2.2.14 RO Importance rating is less than 2.5 RO Importance rating is less than 2.5 2.2.8 3

3 2.2.9

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RO Importance rating is less than 2.5 RO Importance rating is less than 2.5 3

3 2.3.6 2.3.3 RO Importance rating is less than 2.5 GET knowledge level; knowledge of permissible levels in excess of those authorized is SRO knowledge.

For the SRO only questions, only A2, AA2, EA2, and G WAS were used in the selection process. A2, AA2, EA2, and G WAS were used as these are the only WAS that have 10CFR 55.43 direct connections.

3 2.3.4 N/A All Tiers and groups except Tier 3 211 239002 Generic section 2.3 (All)

Cannot apply Generic Radiation Control topics to SRV system.

211 21 2000 A2.17 Main Steam line high radiation signal inputs to MSlV closure have been removed, Main Steam line high radiation signal will now give alarm only.

3 2.2.30 Not SRO level knowledge Page lof 2 Susquehanna Facsimile NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0

ES-401 Record of Rejected WAS Form ES-401-4 2/1 1 I2 212 212 212 21 1 216000 A2.14 295010 AA2.02 239001 A1.O1 226001 A2.16 290001 K6.01 205000 A3.02 NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Design not applicable to Susquehanna; Recirculation Flow instrumentation does not provide any control signal inputs to the Nuclear Boiler Instrumentation System.

Too similar to 295024 2.1.32 used in question 81 This WA is not directly applicable to Susquehanna and parallels system 241000 WAS. Susquehanna has no direct reheater controls, and reactor pressure is controlled by EHC (system 241 000).

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Loss of RHR cooling water flow during the containment spray mode has no affect on containment spray mode. RHR cooing water is a long-term decay heat removal issue. Therefore it is difficult to construct a question that will have an answer other than there is no affect. If there is no affect, then the second part of the WA (based on predicted impact use procedures to mitigate) can never be evaluated since there isnt any procedural guidance to address No affect.

Deleted to achieve exam balance. There are already several Reactor Building ventilation topics covered on this exam.

Deleted from the exam. Question was too close to the same knowledge and ability that is being tested in question # 79.

Page 20f 2 Susquehanna Facsimile

S-301 Administrative Topics Outline Form ES-301-1 Facility:

SUSQUEHANNA -

Date of Examination:

08109-08/13 2004 Examination Level (circle one): (RO)

Operating Test Number:

N/A Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Describe activity to be performed 2.1.20 4.3 NEW JPM Fill Out An Aborted Emlution Control Form.

2.1.33 3.4 NEW JPM Perform Drywell sump calculation and determine if leakage is less than Tech. Spec LCO.

2.2.12 3.0 NEW JPM Determine Jet pump operability.

2.3.10 2.9 NEW JPM Determine Radiological blocking points for a planned containment entry with the plant at 10% powx.

NIA NOTE: All items (5 total) are required br SROs. RO applicants require only4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

S-301 Administrative Topics Outline Form ES-301 -I Facility:

SUSQUEHANNA -

Date of Examination:

08/09-08/13 2004 Examination Level (circle one):

Operating Test Number: N/A Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control

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Radiation Control Emergency Plan Describe activity to be performed 2.1.25 3.1 NEW JPM EvaluateNalidate Seismic Monitor System Trigger (SSE leading to Alert E-plan Classification) 2.1.33 4.0 NEW JPM Perform Drywell sump calculation and determine if leakage is less than Tech. Spec LCO.

2.2.22 4.1 NEW JPM Determine Tech Spec required actions for single loop operations at 28% power AND additional Tech Spec actions to raise powr under these conditions 2.3.10 2.9 NEW JPM Determine Radiological blocking points for a planned containment entry with the plant at 10% powr. Identify additional power restrictionskontrols for the entry.

2.4.44 4.0 NEW JPM Complete ENS and PAR State notification forms (requires PAR determination).

NOTE: All items (5 total) are required br SROs. RO applicants require only4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-1021. Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:

SUSQUEHANNA Date of Examination: 8/09-8/13 2004 System / JPM Title 11 Exam Level (circle one): RO Type Safety Code*

Function Operating Test No.:

N/A 202002 A205 3.113.1 64.0P.007.151 Reset the Fluid Drive Scoop Tube Lock (OP-I 64-001) 261000 A3.01 3.2/3.3 Perform a Manual Startup of the SGTS in Accordance With OP-070-001 D, A, s 1

N, E, A, S 9

264000 A4.04 3.713.7 Manually Synchronize Diesel Generator "A' to 4.16KV Bus 1A from Panel 02653 in Accordance With OP-024-001 295028 EA1.03 3.913.9 Reset Drywell Cooling Isolation and Restore Drywell Cooling IAW ES-134-001 (Control Room Actions) 295037 EA1. I 1 3.513.6 Bypass MSlV and CIG Interlocks During An ATWS And Restore CIG (OP-I 84-001) 259001 A2.07 3.713.8 Perform Switching Feedwater Level Control 45.0P.013.151 (OP-145-001) 29501 8 AA1.01 3.313.4 Respond to loss of RBCCW IAW ON-I 14-001 D'A' 1

N, S I 206000 A4.13 4.U4.0 Recovery from a Manual Closure of HPCl Isolation Valves With an Initiation Signal Present With a Steam Leak Developing. (OP-152-001)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 262002 A4.01 2.8/3.1 Place The Vital AC Uninterruptible Power Supply AC System In Service In Accordance With OP-157-001 212000 A I.01 2.8/2.9 Start RPS MG Set 1S237A from Local Control Panel 1G201A IAW OP-158-001 l

7 E M, R, A 201002 K1.06 323.3 Bypass Control Rod at Rod Drive Control Cabinet (RDCC) (OP-156-001) l 1

E/A, M

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, I

(L)ow-Power, (R)CA, (E/A)Emergency/Abnormal, (E)SF NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:

SUSQUEHANNA Date of Examination: 8/09-8/13 2004 Exam Level (circle one): SR0-I Operating Test No.:

N/A D, E, S Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) 6 System / JPM Title D, E, L, s 202002 A2.05 3.1/3.1 64.0P.007.151 Reset the Fluid Drive Scoop Tube Lock (OP-164-001) 7 261000 A3.01 3.213.3 Peflorm a Manual Startup of the SGTS in Accordance With OP-070-001 D, E, A, S 264000 A4.04 3.713.7 Manually Synchronize Diesel Generator A to 4.16KV Bus I A from Panel OC653 in Accordance With OP-024-001 4

295028 EA1.03 3.913.9 Reset Drywell Cooling Isolation and Restore Drywell Cooling IAW ES-134-001 (Control Room Actions) 295037 EA1.I 1 3.5/3.6 Bypass MSlV and CIG Interlocks During An ATWS And Restore CIG (OP-I 84-001) 29501 8 AA1.01 3.3/3.4 Respond to loss of RBCCW IAW ON-I 14-001 206000 A4.13 4.114.0 Recovery from a Manual Closure of HPCl Isolation Valves With an Initiation Signal Present With a Steam Leak Developing. (OP-152-001)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Safety Code*

Type I Function 1

D,A,S I I

g N, E, A, S I

262002 A4.01 2.8/3.1 Place The Vital AC Uninterruptible Power Supply AC System In Service In Accordance With OP-I 57-001 M

6 212000 A I.01 2.8129 Start RPS MG Set 1S237A from Local Control Panel lG201A IAW OP-158-001 I

I I

E/A1 I

201002 K1.06 3.U3.3 Bypass Control Rod at Rod Drive Control Cabinet (RDCC) (OP-156-001)

• 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/A)Emergency/Abnormal, (E)SF NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:

SUSQUEHANNA Date of Examination: 8/09-8/13 2004 Exam Level (circle one): SR0-U Operating Test No.:

N/A Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title 261000 A3.01 3.2/3.3 Perform a Manual Startup of the SGTS in Accordance With OP-070-001

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295037 EA1.I 1 3.5/3.6 Bypass MSlV and CIG Interlocks During An ATWS And Restore CIG (OP-184-001)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Type Code*

N, E, A, S D, E, A, L, S

262002 A4.01 2.8/3.1 Place The Vital AC Uninterruptible Power Supply AC System In Service In Accordance With OP-157-001 M

212000 AI.01 2.8E.9 Start RPS MG Set 1 S237A from Local Control Panel 1G201A IAW OP-158-001 I

I E/A, M 201 002 K1.06 323.3

'= -11 Bypass Control Rod at Rod Drive Control Cabinet (RDCC) (OP-156-001)

Safety Function 9

5 6

7 1

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, ll (L)ow-Power, (R)CA, (E/A)Emergency/Abnormal, (E)SF NUREG-1021, Draft Rev 9 2004 NRC Exam Rev. 0 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Facility: Susauehanna Scenario No.: ILO-301 Op-Test No.:

N/A Event No.

Malf. No.

Examiners:

Operators:

N I

C C

Initial Conditions: IC-15, Unit 1 at 30% power EOL, Unit 2 at 100% Dower EOL

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Remove Extraction Steam from C RNHTR String MTLO Temperature Element Failure Control Rod Drifts In Loss of (Reactor Building) Zone 1 HVAC Turnover: Unit 1 is at 30% Dower with the startup on hold for a Feedwater heater drain valve solenoid replacement. Control rod sequence 82 is currentlv at steD 450. A small leak in the RWCU Dump room is beinq monitored with a video monitor. The leak is on B RWCU pump suction valve 144-F005B.

Extraction steam is to be removed from C Feedwater heater strinq immediatelv after assuming the shift to avoid spurious valve closures durinq replacement of relav LSHHX-10419C in Dane1 1 C103.

C M

C

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RWCU Pump Room High Temperature Rapid Depressurization 2 ADS SRVs Fail to Open 2

1 Event Type*

Event Description C

I Loss of Main Condenser Vacuum C

I RPS A Scram Failure M

I RClC Steam Line Break C

I RClC Isolation Failure I

I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2004 NRC Exam Rev. 0 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Facility: Susquehanna Scenario No.: ILO-302 Op-Test No.:

N/A Examiners:

Operators:

Event No.

Initial Conditions: IC-18, Unit 1 at 80% power EOL. Unit 2 in Mode 4 Malf. No.

Turnover: CRD pump 16 is out of service for breaker maintenance and is not expected to return this shift. Condensate pump 1B has a possible qround, requirinq the crew to remove 1B Condensate pump from service for inspection. No surveillance activities are planned or due during the shift.

Chemistrv and Reactor Engineering are investiqatina a spike in Off-Gas activitv durinq the last control rod sequence exchange.

I 2

1 Event Type*

N C

I C

I C

C M

M I

2004 NRC Exam Rev. 0 Event Description Shutdown 1 B Condensate Pump Condensate Minimum Flow Recirc Valve Failure

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A Narrow Range Level Instrument Fails Upscale Fuel Clad Failure RPS A Failure to Trip/AlV/S D Main Steam Line Failure to Isolate D Main Steam Line Leak in Turbine Building Radioactivity Release Rapid Depressurization

imponent, (M)ajor Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Facility: Susquehanna Scenario No.: ILO-401 Op-Test No.:

N/A Examiners:

Operators:

Event Malf. No.

No.

Initial Conditions: IC-17, Unit 1 at 69% power EOL, Unit 2 at 100% power EOL Event Event Type*

Description C

l 7

I N

8 C

9 C

10 C

11 M

Drywell Unit Coolers/Fans Surveillance I

C Trip of Drywell Fan 1V414A

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Condensate Pump C Trip / RFPT A Control Signal Failure Containment Instrument Gas Leak at PT-12643 Recirc Flow Unit A Fails Downscale

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Outboard MSlV Closure

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Two SRVs Stick Open Bottom Head Drain Line Leak HPCl Auto-start Failure ADS Auto Logic Failure Rapid Depressurization iomponent, (M)ajor 2004 NRC Exam Rev. 0 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Event Malf. No.

Event No.

Type*

I N

Facility: Susquehanna Scenario No.: ILO-501 Op-Test No.:

N/A Examiners:

0 perators:

Event Description Transfer Bus 1A202 to Normal Source Initial Conditions: IC-1 1, Unit 1 in Mode 2 at 9% power EOL, Unit 2 at 100% power EOL M

C I

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Loss of Coolant Accident 1 Control Rod Fails to Insert B RHR Pump Auto Logic Failure I

I I Main Steam Tunnel Temperature Detector Failure I

I M

M 3

1 Breaker 1A20404 Auto Logic Failure Rapid Depressurization RPV Flooding 4

1 5

1 7

1 8

1 9

1 lo I l1 I l2 I l3 I C

1 Reactor Feed Pump A High Bearing Temperature I

I IRM G Fails Upscale I

I IRM Division I Bypass Failure c

I ~ o s s of offsite Power C

1 B Core Spray Pump Trip 1

I I

h * (N)ormal, (R)eactivity, (1)nstrument (C)omponent, (M)ajor 2004 NRC Exam Rev. 0 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Event No.

11 Facility: Susquehanna Scenario No.: ILO-601 Op-Test No.:

N/A Examiners:

Operators:

Malf. No.

Event Type*

Initial Conditions: IC-20, Unit I at 90% power EOL, Unit 2 at 100% power EOL 1

Turnover: 1B EHC pump is out of service for breaker maintenance and will not be returned to service this shift. RHR Loop A has iust been secured from Suppression Pool Coolinq and 1A RHRSW pump is running for vibration data, which is complete. The crew will shutdown RHRSW followinu shift turnover. ESW pumps A and 6 are in service to support Suppression Pool Coolinq operation.

Chemistw and RX Ennineerina are investiqatinq a spike in Off-Gas activity durinq the last control rod seauenceexchanqe.

N

-3 4

R 5

1 I

C 7

1 I

C 8

1 I

C I

I

_. (N)ormal, (R)eactivity, (I)nstrument, (C Event Description

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Secure 1A RHRSW Pump RHRSW Radiation Monitor Fails Upscale Loss of Stator Cooling Power Reduction Generator Lockout / Turbine Trip RPS B Failure to Trip /ARI Failure / ATWS SLC System Squib Valves Fail 1A EHC Pump Trip

imponent, (M)ajor 2004 NRC Exam Rev. 0 Susquehanna Facsimile