ML053210406

Draft - Operating Exam Outlines (Folder 2A)

ML053210406
Person / Time
Site:	Susquehanna
Issue date:	08/19/2005
From:	Roush K Susquehanna
To:	Todd Fish Operations Branch I
Conte R
References
ES-401-1
Download: ML053210406 (39)

Text

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

3. Generic Knowledge and Abilities Categories Facility: Susc Tier 1

2 3

4 1

2 3

4 2

3 2

3

~2 2 2 1 10 7

1.

Emergency

& Abnormal Plant Evolutions

2.

Plant Systems uehanna Steam Electric Station Date of Exam: 12 to 22 December 2005 I

Note:

1.

Ensure that at least two topics from every applicable WA 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 WA category shall not be less than two).

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.

Systems/edutions 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, sitespecific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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.

e.

Absent a plant-specific priority, only those WAS 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 WA categories.

7.

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.

8.

On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.

2.

3.

9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

.S-401 BW R Examination Outline Form ES-401-1

.her -

SRO-ONLY Points A I A2 I G* I TOTAL 4

3 7

2 1

3 6

4 10 3

2 5

I Note:

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 (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 *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.

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 categoryhier.

• 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 statements.

NUREG-1021, Rev 9 Page 1 of 6 Susquehanna Facsimile

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (SRO)

WA Topic@)

AA2. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :

AA2.02 Reactor power / pressure / and level AA2. Ability to determine and/or interpret the following as they apply to SCRAM :

AA2.06 Cause of reactor SCRAM 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

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

AA2.05 ?Entry conditions of emergency plan EA2. Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE :

EA2.04 Drywell pressure.

2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

2.4.11 Knowledge of abnormal condition procedures.

Group Point Total:

IR -

4.3' 3.8 4.0 4.6' 4.2 3.8 3.6 7

NUREG-1021, Rev 9 Page 2 of 6 Susquehanna Facsimile

ES-401 BW R Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (SRO) 11 WACategory Point Totals: I I I I I 2 WA Topic(s)

AA2. Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM :

AA2.01 Condenser vacuumlabsolute pressure 2.4.6 Knowledge symptom based EOP mitigation strategies.

EA2. Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL EA2.02 ?Off-site release rate: Plant-Specific Group Point Total:

IR -

3.1 4.0 -

4.1 3

NUREG-1021, Rev 9 Page 3 of 6 Susquehanna Facsimile

ES-401 BW R Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 1 (SRO)

WA Topic(s)

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

A2.02 SRM inop condition 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:

A2.13 High secondary containment ventilation exhaust radiation A2. Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.CJD.C.)

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

A2.02 Over voltage 2.4.5 Knowledge of the organization of the operating procedures network for normal /

abnormal / and emergency evolutions.

2.1.32 Ability to explain and apply system limits and precautions.

Group Point Total:

IR -

3.7 3.7 2.7 3.6 3.8 -

5 NUREG-1021, Rev 9 Page 4 of 6 Susquehanna Facsimile

ES-401 BWR Examination Outline F

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~

ES-401-1 Plant Systems - Tier 2 / Group 2 (SRO) 215002 Rod Block Monitor System WA Topic(s)

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

A2.03 Loss of associated reference APRM channel:

BWR-3,4,5 2.4.27 Knowledge of fire in the plant procedure.

A3. Ability to monitor automatic operations of the FUEL HANDLING EQUIPMENT including:

A3.01 ?Cranehefuel bridge movement: Plant-Specific.

Group Point Total:

3.3 3.5 3.6 3

NUREG-1021, Rev 9 Page 5 of 6 Susquehanna Facsimile

ES 401 Generic Knowledge and Abilities Outline Tier 3 Form ES-401-3 Conduct of Operations I

Equipment Control Radiation Control Emergency Procedures /

Plan Tier 3 Point Category I Facility: Susquehanna Steam Electric Station Date of Exam: 12 to 22 December 2005 OdY 2.1.7 2.1.12 1

1 2

1 1

2 1

1 2

1 1

7 NUREG-1021. Rev 9 Page 6 of 6 Susquehanna Facsimile

is-401 BWR Examination Outline Form ES-401

-I Group 1

2 Tier Totals 1

2 Tier Totals Facility: Susq K1 K2 4

3 1

2 5

5 3

2 1

1 4

3 uehanna Steam Electric Station I

Tier

1. Emergency &

Abnormal Plant Evolutions

2. Plant Systems I

RO WA Category Points

3. Generic Knowledge and Abilities Categories Date of Exam:

K3 K4 K5 K6 A1 A2 A3 A4 G*

Note:

1.

2.

3.

4.

5.

6.

7.

8.

Ensure that at least two topics from every WA 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 *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.

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 categoryhier.

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 auidance reaardina the elimination of inaDDroDriate WA statements.

NUREG-1021, Rev 9 Page 1 of 15 Susquehanna Facsimile

ES-401 BWR Examinatic Outline Form ES-401-1 HAPE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation 295003 Partial or Complete Loss of A.C. Power 295004 Partial or Complete Loss of D.C. Power 295004 Partial or Complete Loss of D.C. Power 295005 Main Turbine Trip 295006 SCRAM 295016 Control Room Abandonment

'lant Evolutions - Tier 1 I Group 1 (RO)

WA Topic@)

AK2. Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the following:

AK2.07 Core flow indication AK3. Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :

AK3.06 Containment isolation AK1. Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C.

POWER:

AK1.05 Loss of breaker protection 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms I from fuel handling area / communication with fuel storage facility / systems operated from the control room in support of fueling operations / and supporting instrumentation.

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

AK2.04 Main generator protection AA2. Ability to determine and/or interpret the following as they apply to SCRAM :

AA2.04 Reactor pressure AK3. Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT :

AK3.03 Disabling control room controls IR -

3.4 3.7 3.3 3.5 3.3 4.1 3.5 NUREG-1021. Rev 9 Page 2 of 15 Susquehanna Facsimile

P ES-401 Form ES-401-1 WAPE # I Name I Safety Function 2950 18 Partial or Complete Loss of Component 295019 Partial or Complete Loss of Instrument Air 11 295021 Loss of Shutdown Cooling 295023 Refueling Accidents 295024 High Drywell Pressure I 295025 High Reactor Pressure 295026 Suppression Pool High Water Temperature 295028 High Drywell Temperature lant Evolutions - Tier 1 I Group 1 (RO)

WA Topic(s)

AK1. Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :

AKl.01 Effects on componentlsystem operations AA1. Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :

AAl.03 Instrument air compressor power supplies AA2. Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING:

AA2.07 Reactor recirculation flow AK1. Knowledge of the operational implications of the following concepts as they apply to REF'UELING ACCIDENTS :

AK1.O1 Radiation exposure hazards 2.3.2 Knowledge of facility ALARA program.

EA2. Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:

EA2.02 Reactor power EK1. Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

EK1.O1 Pump NPSH EK3. Knowledge of the reasons for the Following responses as they apply to HIGH DRYWELL TEMPERATURE:

EK3.02 RPV flooding 9ee3 IR -

3.5 3.0 2.9 3.6 2.5 4.2 3.0 3.5 NUREG-1021, Rev 9 Page 3 of 15 Susquehanna Facsimile

) ES-401 BWR Examination Outline Form ES-401-1 II Ern(

I WAPE # / Name / Safety Function 295030 Low Suppression Pool Water Level 29503 1 Reactor Low Water Level 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown 295038 High Off-Site Release Rate 600000 Plant Fire On Site 11 WA Category Totals:

iencv and Abnormal Plant Evolutions - Tier 1 / GrouD 1 IRO)

==+

EA1. Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:

EA1.06 Condensate storage and transfer (make-up to the suppression pool):

Plant-Specific EK2. Knowledge of the interrelations between REACTOR LOW WATER LEVEL and the following:

EK2.13 ARI/RFT/ATWS: Plant-Specific 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

X EA1. Ability to operate and/or monitor the following as they apply to EAl.07 Control room ventilation: Plant-Specific HIGH OFF-SITE RELEASE RATE:

AA1 Ability to operate and / or monitor the following as they apply to PLANT FIRE ON SITE:

AA 1.06 Fire alarm Group Point Total:

IR 3.6 4.1 4.0 3.6 3.0 -

20 NUREG-1021, Rev9 page4 of 15 Susquehanna Facsimile

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

EIAPE # I Name I Safety Function

~~

295008 HighReactorWaterLevel I I I I 295009 Low Reactor Water Level X

295009 Low Reactor Water Level X

X 295013 High Suppression Pool Temperature 2950 15 Incomplete SCRAM X

X 295013 High Suppression Pool Temperature 2950 15 Incomplete SCRAM X

WA Category Point Totals: I 1 I 21 1 I 1 FO~TTI ES-401-1 WA Topic@)

2.2.20 Knowledge of the process for managing troubleshooting activities.

AK1. Knowledge of the operational implications of the following concepts as they apply to LOW REACTOR WATER LEVEL :

AK1.02 Recirculation pump net positive suction head: Plant-Specific AK2. Knowledge of the interrelations between HIGH SUPPRESSION POOL TEMPERATURE and the following:

AK2.01 Suppression pool cooling AK2. Knowledge of the interrelations between INCOMPLETE SCRAM and the following:

AK2.06 RSCS: Plant-Specific EK3. Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION EK3.03 Personnel evacuation EA1. Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT HIGH SUMPIAREA WATER LEVEL :

EAl.01 Secondary containment equipment and floor drain systems EA2 Ability to determine and / or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:

EA2.04 Combustible limits for wetwell Group Point Total:

IR 4.3 3.O 3.6 2.6 4.0*

3.2 3.3 7

NUREG-1021. Rev9 Page 5 of 15 Susquehanna Facsimile

BWR Examination Outline F

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ES-401-1 ES-401 (stems - Tier 2 / Grc Plant v

WA Topic(s)

System #

IR -

4.2 K3. Knowledge of the effect that a loss or malfunction of the HIGH PRESSURE COOLANT INJECTION SYSTEM will have on following:

K3.03 Suppression pool level control: BWR-2,3,4 203000 Residual Heat Removal /Low Pressure Coolant Injection: Injection Mode (Plant Specific)

K2. Knowledge of electrical power supplies to the following:

K2.02 System pumps: BWR-2,394 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode) 3.4-42 2.5 Al. Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:

A1.O1 Reactor water level:

BWR-2,3,4 206000 High Pressure Coolant Injection System 4.3 3.0 2.2.12 Knowledge of surveillance procedures.

206000 High Pressure Coolant Injection System K4. Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.08 Automatic system initiation 209001 Low Pressure Core Spray System 3.8 3.8 K4. Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.04 Indication of fault in explosive valve firing circuits 21 1000 Standby Liquid Control System Page 6 of 15 NUREG-1021, Rev 9 Susquehanna Facsimile

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

'RO)

Plant (stems - Tier 2 / Group IR WA Topic(s)

System #

21 lo00 Standby Liquid Control System 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

K4. Knowledge of AVERAGE POWER RANGE MONITORLOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.09 Control rod insertion following RPS system electrical failure.

3.0 -

3.8 212000 Reactor Protection System A3. Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including:

A3.01 Reactor Power K2. Knowledge of electrical power supplies to the following:

K2.01 IRM channels/detectors K5. Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM)

SYSTEM :

K5.03 Changing detector position 2 12000 Reactor Protection System 4.4 2.5 2.8 21 5003 Intermediate Range Monitor System 215004 Source Range Monitor (SRM) System NUREG-1021, Rev 9 Page 7 of 15 Susquehanna Facsimile

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

2 15005 Average Power Range Monitorbcal Power Range Monitor 217000 Reactor Core Isolation Cooling System 2 18000 Automatic Depressurization System 223002 Primary Containment Isolation System / Nuclear Steam Supply Shut-Off NUREG-1021, Rev9 Plant stems - Tier 2 / Grc Page 8 of 15 WA Topic@)

Al. Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITORLOCAL POWER RANGE MONITOR SYSTEM controls including:

A1.02 RPS status K1. Knowledge of the physical connections and/or cause effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following:

K1.02 Nuclear boiler system A3. Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:

A3.01 ADS valve operation K6. Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF:

K6.02 D.C. electrical distribution IR -

3.9 3.5 4.2 3.0 Susquehanna Facsimile

ES-401 System #

239002 Safety Relief Valves 259002 Reactor Water Level Control System 259002 Reactor Water Level Control System 261000 Standby Gas Treatment System BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 1 (RO)

WA Topic(s)

K5. Knowledge of the operational implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM :

K5.02 Safety function of SRV operation K3. Knowledge of the effect that a loss or malfunction of the HIGH PRESSURE COOLANT INJECTION SYSTEM will have on following:

K3.03 Suppression pool level control: BWR-2,3,4 A4. Ability to manually operate and/or monitor in the control room:

A4.09 Suppression pool level:

BWR-2,3,4 K1. Knowledge of the physical connections and/or cause effect relationships between MSIV LEAKAGE CONTROL SYSTEM and the following:

K1.O1 Main steam system:

BWR-4,5,6(P-Spec)

IR 3.7 2.7 3.4 3.4 NUREG-1021. Rev 9 Page 9 of 15 Susquehanna Facsimile

BWR Examination Outline Plant Systems - Tier 2 / Group FOITII ES-401-1 WA Topic(s)

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

A2.08 Opening a disconnect under load K6. Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.CJD.C.) :

K6.01 A.C. electrical power K1. Knowledge of the physical connections and/or cause effect relationships between D.C.

ELECTRICAL DISTRIBUTION and the following:

K1.02 Battery charger and battery Al. Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEL/JET) controls including:

A 1.09 Maintaining minimum load on emergency generator (to prevent reverse power)

IR 3.3 2.7 3.2 3.O NUREG-1021, Rev 9 Page 10 of 15 Susquehanna Facsimile

BWR Examination Outline Form ES-401-1 ES-401 rstems - Tier 2 / Group 1 (RO)

Plant IR System #

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:

A2.01 Air dryer and filter malfunctions 300000 Instrument Air System 2.9 2.6 2.8 A4. Ability to manually operate and / or monitor in the control room:

A4.01 Pressure gauges 300000 Instrument Air System A2. Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

A2.02 HigMow surge tank level 400000 Component Cooling Water System Group Point Total:

WA Category Point Totals:

26 NUREG-1021. Rev 9 Page 11 of 15 Susquehanna Facsimile

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

- Tier 2 / Group 2 (RO)

IR WA Topic(s)

System #

A3. Ability to monitor automatic operations of the CONTROL ROD DRIVE HYDRAULIC SYSTEM including:

A3.11 SDV level 201001 Control Rod Drive Hydraulic System 3.5 K1. Knowledge of the physical connections and/or cause effect relationships between REACTOR MANUAL CONTROL SYSTEM and the following:

K1.04 Rod block monitor:

Plant-Specific 201002 Reactor Manual Control System 3.5 A3. Ability to monitor automatic operations of the ROD SEQUENCE CONTROL SYSTEM (PLANT SPECIFIC) including:

A3.05 ?Verification of proper function/ operability: BWR-201004 Rod Sequence Control System (Plant Specific) 3.7-33 3.5 2.5 2.2.26 Knowledge of refueling administrative rea uiremen ts.

201006 Rod Worth Minimizer System (RWM)

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

A4.02 System valves 202001 Recirculation System 3.5 3.5 K3. Knowledge of the effect that a loss or malfunction of the CONTROL ROD DRIVE HYDRAULIC SYSTEM will have on following:

K3.01 Recirculation pumps:

Plant-Specific 202002 Recirculation flow Control System K6. Knowledge of the effect that a loss or malfunction of 204000 Reactor Water Cleanup System 3.1 NUREG-1021, Rev 9 Page 12 of 15 Susquehanna Facsimile

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

- Tier 2 I Group 2 (RO)

WA Topic(s)

System #

the following will have on the REACTOR WATER CLEANUP SYSTEM :

K6.01 Component cooling water sys tems K4. Knowledge of ROD POSITION INFORMATION SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.02 Thermocouple 2.5 214000 Rod Position Information System K2. Knowledge of electrical power supplies to the following:

K2.02 Pumps 2 19000 RHR/LPCI:

Torus/Suppression Pool Cooling Mode 3.1 A2. Ability to (a) predict the impacts of the following on the RHRLPCI:

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:

A2.03 Valve closures Al. Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including:

A1.O1 Main steam pressure.

226001 RHR/LPCI:

Containment Spray System 3.1 239001 Main and Reheat Steam System 3.6 3.1 K5. Knowledge of the operational implications of the following concepts as they apply to PLANT VENTILATION 288000 Plant Ventilation Systems Page 13 of 15 Susquehanna Facsimile NUREG-1021. Rev 9

BWR Examination Outline F

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ES-401-1 K5.0 1 Airborne contamination control NUREG-1021. Rev 9 Page 14 of 15 Susquehanna Facsimile

I ES 401 Generic Knowledge and Abilities Outline Tier 3 Form ES -40 1 -3 2.4.22 12 to 22 December 2005 Knowledge of the bases for prioritizing safety functions during abnormaVemergency operations.

Facility: Susquehanna Steam Electric Station Date of Exam:

WA# 1 R

Topic Category IR Ability to obtain and verify controlled Drocedure CODY.

2.1.21 I 3.1

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Procedures/

Plan 3.4 Ability to explain and apply system limits and precautions.

2.1.32 Subtotal 2.2.11 Knowledge of the process for controlling temporary changes.

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

Knowledge of the refueling process.

2.5 2.5 2.2.25 2.2.27 2.6 Subtotal Knowledge of 10 CFR: 20 and related facility radiation control requirements.

2.3.1 2.6 2.3.2 I Knowledge of facility ALMA program.

2.5 Subtotal Knowledge symptom based EOP mitigation strategies.

2.4.6 3.1 2.4.17 I Knowledge of EOP terms and definitions.

3.1 3.0 Page 15 of 15 NUREG-1021, Rev 9 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-401-4 Randomly Selected WA NIA 295004.2.2.1 295004.2.2.5 295004.2.2.6 295004.2.2.1 1 295037.2.2.24 295037.2.2.8 295008.2.1.1 7 2.1.16 Reason for Rejection As per letter PIA005439 PIA1 4-1 3 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.

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Generic K/A to perform plant pre-startup or startup activities that could affect reactivity during a partial or full loss of DC power. This is not a reasonably foreseeable situation. Randomly selected and 295004.2.2.5.

Generic WA to demonstrate knowledge of making changes to the facility as described in the FSAR during a partial or full loss of DC power. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 294004.2.2.6.

Generic WA to demonstrate knowledge of making changes to the procedures as described in the FSAR during a partial or full loss of DC power. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 294004.2.2.1 1.

Generic WA to demonstrate knowledge of controlling temporary changes during a partial or full loss of DC power. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 294004.2.2.30.

Generic WA to demonstrate knowledge or ability during an ATWS while analyzing the affect of maintenance activities on LCO status. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 295037.2.2.8.

Generic WA to demonstrate knowledge or ability during an ATWS while determining if a proposed change, test, or experiment involves an un-reviewed safety question. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 295037.2.2.2.

Generic WA to make accurate, clear and concise verbal reports. A written examination is not the optimum forum for testing this ability. Randomly selected 295008.2.2.20.

Generic WA to operate the plant phone, paging system and two-way radio. A written examination is not the optimum forum for testing this ability. Randomly selected 2.1.21.

NUREG-1021 Rev 9 Page lof 2 Susquehanna Facsimile

Record of Rejected WAS Form ES-401-4 295030.2.2.32 EPE WA concerning Low Suppression Pool Water Level and Generic WA concerning effects of alteration on core configuration. These are unrelated topics such that writing an exam item that matches the WA is probably not useful. Randomly selected 295030.2.2.33.

295030.2.2.33 295030 A2.4 EPE WA concerning Low Suppression Pool Water Level and Generic WA concerning knowledge of control rod programming. These are unrelated topics such that writing an exam item that matches the WA is probably not useful.

Randomly selected 295030.2.2.4.

EPE WA concerning Low Suppression Pool Water Level and Generic WA concerning differences between units. According to Susquehanna Training Department, there are insignificant differences between the units. Therefore, it probably not possible to develop a meaningful exam item. Randomly selected 295030.2.2.25.

The WAS above were rejected during written exam outline development. New WAS were selected using a random number generator available at http://www.random.org. WAS were selected from the same tier, group and WAPE #/Name/Safety Function to maintain outline fidelity to the maximum extent possible.

NUREG-1021 Rev 9 Page 20f 2 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-40 1 -4 Tier I Group Randomly Selected WA N/A 295004.2.2.1 295004.2.2.5 295004.2.2.6 295004.2.2.1 1 295037.2.2.24 295037.2.2.8 Question 21 RO Tier 1 / Group 2 295008.2.1.1 7 Question 66 RO Tier 3 2.1.16 Reason for Rejection As per letter PLA005439 PLAl4-13 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.

Generic WA to perform plant pre-startup or startup activities that could affect reactivity during a partial or full loss of DC power. This is not a reasonably foreseeable situation. Randomly selected 295004.2.2.5.

Generic WA to demonstrate knowledge of making changes to the facility as described in the FSAR during a partial or full loss of DC power. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 294004.2.2.6.

Generic WA to demonstrate knowledge of making changes to the procedures as described in the FSAR during a partial or full loss of DC power. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 294004.2.2.1 1.

Generic WA to demonstrate knowledge of controlling temporary changes during a partial or full loss of DC power. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 294004.2.2.30.

Generic WA to demonstrate knowledge or ability during an ATWS while analyzing the affect of maintenance activities on LCO status. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 295037.2.2.8.

Generic WA to demonstrate knowledge or ability during an ATWS while determining if a proposed change, test, or experiment involves an un-reviewed safety question. These are unrelated such that writing an exam item that matches the WA is probably not useful. Randomly selected 295037.2.2.2.

Generic WA to make accurate, clear and concise verbal reports. A written examination is not the optimum forum for testing this ability. Randomly selected 295008.2.2.20.

Generic WA to operate the plant phone, paging system and two-way radio. A written examination is not the optimum forum for testing this ability. Randomly selected 2.1.21.

NUREG-1021 Rev 9 Page lof 6 Susquehanna Facsimile

ES-40 1 Record of Rejected WAS Form ES-401-4 Changed HIGH PRESSURE COOLANT INJECTION SYSTEM to REACTOR WATER LEVEL CONTROL SYSTEM. Changed Suppression pool level control to Rod worth minimizer. This corrects typographical errors in the original outline that were incorrectly copied from the original random 295030.2.2.32 295030.2.2.33 295030.2.2.4 EPE WA concerning Low Suppression Pool Water Level and Generic WA concerning effects of alteration on core configuration. These are unrelated topics such that writing an exam item that matches the WA is probably not useful. Randomly selected 295030.2.2.33.

EPE WA concerning Low Suppression Pool Water Level and Generic WA concerning knowledge of control rod programming. These are unrelated topics such that writing an exam item that matches the WA is probably not useful. Randomly selected 295030.2.2.4.

EPE WA concerning Low Suppression Pool Water Level and Generic WA concerning differences between units. According to Susquehanna Training Department, there are insignificant differences between the units. Therefore, it probably not possible to develop a meaningful exam item. Randomly selected 295030.2.2.25.

The WAS above were rejected during written exam outline development. New WAS were selected using a random number generator available at http://www.random.org. WAS were selected from the same tier, group and WAPE #/Name/Safety Function to maintain outline fidelity to the maximum extent possible.

Per telephone conversation with Susquehanna Steam Electric Station staff on Tuesday, 2 August 2005, the following corrections were made to the exam outline:

RO Tier l/Group 1, 295037.2.2.24 - as noted above, this WA was replaced during sample selection.

However, the original, deselected WA was not replaced in the exam outline. Question 18.

RO Tier 2/Group 1, 205000.K2.02 - deleted 3.4-42 because this was a page number carried over from the original cut-n-paste from the WA catalog. Corrected the WA to read Motor operated valves.

Question 29.

RO Tier 2/Group 2, 201 004.A3.05 - deleted 3.7-33 because this was a page number carried over from the original cut-n-paste from the WA catalog. Question 56.

SRO Tier l/Group 1, 295037.2.4.1 1 - deleted 4.1-24 because this was a page number carried over from the original cut-n-paste from the WA catalog. Question 82.

SRO Tier l/Group 2, 295035.EA2.02 - deleted 4.1 -22 because this was a page number carried over from the original cut-n-paste from the WA catalog. Question 85.

This form, 295008.2.2.1 7 - corrected the table above to correctly indicate that this WA was sampled and rejected under RO Tier l/Group 2 vice RO Tier l/Group 1 as originally shown. Question 21.

Also found and corrected two WAS that were incorrectly copied from the original random sample generator to the examination outline:

m RO Tier 2/Group 1, 203000.K3.03 - Corrected the WA to refer to RHR/LPCI. Question 28.

m RO Tier 2/Group 1, 205000.K2.02 - Corrected the WA to read Motor operated valves. Question 29.

Question 44 RO Tier 2 / Group 1 NUREG-1021 Rev 9 I

Page 20f 6 Susquehanna Facsimile

ES-40 1

~

Record of Rejected WAS Form ES-401-4 259002. K3.03 Question 45 259002.A4.09 Question 46 261 000.K1.01 Question 47 262001.A2.08 Question 59 202002. K3.0 1 Question 64 239001.Al.Ol Question 64 NUREG-1021 Rev 9

_ _ ~

sample generator to the examination outline.

15 SeDtember 2005 Changed Suppression pool level to TDRFP lockout reset: TDRFP. This corrects a typographical error in the original outline that was incorrectly copied from the original random sample generator to the examination outline.

16 September 2005 Changed MSIV LEAKAGE CONTROL SYSTEM to STANDY GAS TREATMENT SYSTEM. Changed Main steam system: BW R-4,5,6( P-Spec) to Reactor building ventilation system. This corrects typographical errors in the original outline that were incorrectly copied from the original random sample generator to the examination outline.

16 September 2005 Rejected W A as too simplistic (GFE level knowledge). Unable to develop a discriminatory examination question. Used http://www.random.orq to select another WA from the 262001.A2 series. Selected 262001 A2.03.

19 September 2005 Changed K3. Knowledge of the effect that a loss or malfunction of the CONTROL ROD DRIVE HYDRAULIC SYSTEM will have on following:

K3.01 Recirculation pumps: Plant-Specific to K3. Knowledge of the effect that a loss or malfunction of the RECIRCULATION FLOW CONTROL SYSTEM will have on following: K3.01 Core flow. This corrects a typographical error in the original outline that was incorrectly copied from the original random sample generator to the examination outline.

21 September 2005 This WA was rejected from the August 2004 ILO exam with the following statement: This K/A is not directly applicable to Susquehanna and parallels system 241 000 WAS. Susquehanna has no direct reheater controls, and reactor pressure is controlled by EHC (system 241 OOO).

Therefore, this WA is rejected from this ILO exam as well.

Used htttx//www.random.org to select another WA from the 239001.A1 series.

Selected 239001.Al.O6.

22 September 2005 Rejected 239001.Al.O6 because Susquehanna Steam Electric Station (SSES) does NOT have air ejector radiation monitors. Air Ejector effluent is directed to the Offgas processing system. Offgas effluent is monitored for radiation.

However, this is too far removed from the Air Ejector system to justify a WA Page 30f 6 Susquehanna Facsimile

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ES-401 Record of Rejected WAS Form ES-40 1 -4 I

239001.Al.O6 1 Question 34 RO Tier 2 / Group 1 21 1000.2.1.2 3 October 2005 Question 47 RO Tier 2 / Group 1 1 262001.A2.03 Question 88 SRO Tier 2 / Group 1 262002.M.02 Question 92 SRO Tier 2 / Group 1 21 6000.2.4.27 Week of 14 October 2005 Question 13 RO Tier 1 / Group 1 295025. EA2.02 I match.

Used http://www.random.orq to select another WA from the 239001.A1 series.

Selected 239001.A1.lo.

22 September 2005

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Rejected 21 1000.2.1.2 during Chief Examiner review because unable to develop question with LOD greater than 1.O.

Used http://www.random.orq to select another WA from the 21 1000.2.1 series.

Selected 21 1000.2.1.33.

30 September 2005 Submitted questions 1 through 50, except 25 and 47 to SSES Rejected 262001.A2.03 during Branch Chief review because unable to develop RO level question that meets this WA. The requirement to I... use procedures to correct, control, or mitigate... is an SRO level task.

Used http://www.random.orq to select another WA from the262001.A2 series.

Selected 262001.A2.05.

3 October 2005 Rejected 262002.A2.02 because Uninterruptible Power Supplies were sampled and tested at the RO level (Question 48).

Substituted the question originally developed for 262001.A2.03 in place for 262002.A2.02. This substitutes one A2 WA for another A2 WA; thereby preserving the breadth and diversity of the original sample plan.

5 October 2005.

Rejected 21 6000.2.4.27 because I was unable to develop a plausible and discriminatory question after over eight hours of effort.

Used http://www.random.org to select another WA from the 21 6000.2. series (two random draws: first for the 4, second for the 22). Selected 21 6000.2.2.22.

12 October 2005 NRC received comments from SSES on the first submission. Discussed comments with SSES by telephone.

Rejected 295025.EA2.02 because during review it was determined to be similar to 295006.AA2.04 and because development of a suitable question proved difficult.

Used http://www.random.orq to select another WA from the 295025.EA2 series. Selected 295025.EA2.03 17 October 2005 NUREG-1021 Rev 9 Page 4of 6 Susquehanna Facsimile

ES-40 1 Record of Rejected WAS Form ES-40 1 -4 Question 14 RO Tier 1 / Group 1 295026.EK1.01 Question 21 RO Tier 1 / Group 1 295008.2.2.20 Question 51 RO Tier 2 / Group 1 300000.A2.O 1 Question 53 RO Tier 2 / Group 1 400000.A2.02 Question 57 RO Tier 2 / Group 2 Rejected 295026.EK1.01 because during review it was determined high Suppression Pool water temperature and Pump NPSH was not a limiting concern at SSES. Therefore, SSES advised that recommendations on this WA would have little relevance.

Selected 295026.EK1.02 directly because there are only two WAS under the 295026.EKl series.

17 October 2005 Rejected because this was incorrectly copied from original sample. See, 295008.2.1.1 7 above. This should have been 295008.2.1.20.

17 October 2005 Unable to adequately test both ability to predict and use procedures of this two part WA. Per authority of NUREG 1021, ES401, Section D.2.a., second paragraph [When selecting or writing questions for WAS that test coupled knowledge or abilities (e.g., the A.2 WA statements in Tiers 1 and 2 and a number of generic WA statements, such as 2.4. I, in Tier 3), try to test both aspects of the WA statement. If that is not possible without expending an inordinate amount of resources, limit the scope of the question to that aspect of the WA statement requiring the highest cognitive level (e.g., the (b) portion of the A.2 WA statements) or substitute another randomly selected WA.], the test question tests the ability to predict the impact of an air dryer malfunction.

18 October 2005.

Unable to adequately test both ability to predict and use procedures of this two part WA. Per authority of NUREG 1021, ES401, Section D.2.a., second paragraph [When selecting or writing questions for WAS that test coupled knowledge or abilities (e.g., the A.2 WA statements in Tiers 1 and 2 and a number of generic WA statements, such as 2.4.1, in Tier 3), try to test both aspects of the WA statement. If that is not possible without expending an inordinate amount of resources, limit the scope of the question to that aspect of the WA statement requiring the highest cognitive level (e.g., the (b) portion of the A.2 WA statements) or substitute another randomly selected WA.], the test question tests the ability to predict the impact of an air dryer malfunction.

18 October 2005.

This WA requires a nexus between the RWM and refueling administrative requirements. The ROD TEST function is the only nexus I can find.

Specifically, the RWM Bypass Keylock switch is ADMINISTRATIVELY prohibited under the conditions of the question. Therefore, this question is submitted as an adequate WA match pursuant to the authority of of NUREG 1021, ES401, Section D.2.a., second paragraph [When selecting or writing questions for WAS that test coupled knowledge or abilities (e.g., the A.2 WA statements in Tiers 1 and 2 and a number of generic WA statements, such as 2.4.1, in Tier 3), try to test both aspects of the WA statement. If that is not NUREG-1021 Rev 9 Page 50f 6 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-401-4 201 006.2.2.26 Question 63 RO Tier 2 / Group 2 226001.A2.03 20 October 2005 Question 100 SRO Tier 3 Generic 2.4.1 0 2 November 2005 4 November 2005 possible without expending an inordinate amount of resources, limit the scope of the question to that aspect of the WA statement requiring the highest cognitive level (e.g., the (b) portion of the A.2 WA statements) or substitute another randomly selected WA.].

18 October 2005 Unable to adequately test both ability to predict and use procedures of this two part WA. Per authority of NUREG 1021, ES401, Section D.2.a., second paragraph [When selecting or writing questions for WAS that test coupled knowledge or abilities (e.g., the A.2 WA statements in Tiers 1 and 2 and a number of generic WA statements, such as 2.4.1, in Tier 3), try to test both aspects of the WA statement. If that is not possible without expending an inordinate amount of resources, limit the scope of the question to that aspect of the WA statement requiring the highest cognitive level (e.g., the (b) portion of the A.2 WA statements) or substitute another randomly selected WA.], the test question tests the ability to predict the impact of an air dryer malfunction.

18 October 2005.

Submitted Questions 1 through 75 to SSES.

Rejected Gen.2.4.10 because I was unable to develop an SRO level question with Level of Difficulty greater than 1 and less than 5 based on knowledge of annunciator response procedures.

Used http://www.random.orq to select another WA from the Gen2.4.10 series.

Selected Gen.2.4.11.

31 October 2005 Submitted Questions 76 to 100 to SSES.

Discussed questions 2,13,18,20,21,22,31,64,68,73,74, and 75 with SSES. Specific comments are documented in the comments section of each question. SSES will not submit formal written comments to the submittal of 20 October 2005.

NUREG-1021 Rev 9 Page 60f 6 Susquehanna Facsimile

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

SSES Examination Level Administrative Topic (See Note)

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~

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan RO Date of Examination:

Operating Test Number:

12/12/05 (Rev. 1)

Type Code*

Describe activity to be performed 2.1.18 2.9 78.AD.001.101 Document a failed LPRM and determine the appropriate compensatory actions.

2.1.25 2.8 45.ON.007.001 Determine the Cause for reactor Water level anomaly.

2.2.24 2.6 00.AD.269.101 Determine the Inputs to Zone 3 Is0 Signal Lockout relay prior to maintenance.

NIA 2.4.43 2.8 00.EP.004.002 Perform Control room communicator Emergency Notification.

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)irnulator, or Class(R)oom (D)irect from bank (r 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

I1 (Plrevious 2 exams (< 1; randomlv selected)

NUREG-1021, Revision 9 Susquehanna Facsimile

Form ES-301-1 Facility:

SSES Examination Level Date of Examination:

l a 1 2/05 (Rev. 1)

SRO Operating Test Number:

Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Describe activity to be performed 2.1.12 4.0 00.AD.273.001 Determine TRO applicability and complete the LCO/TRO log sheet.

2.1.25 3.1 45.0N.007.001 Determine the Cause for reactor Water level anomaly, and determine Tech Spec required actions.

2.2.24 3.8 00.AD.269.102 Determine the Inputs to Zone 3 Is0 Signal Lockout relay prior to maintenance, and determine appropriate Tech Spec actions.

2.3.6 3.1 69.0P.044.051 Review and Approve LW Discharge 2.4.41 4.0 OO.EP.001.304, 305,504,505, 602 Perform Emergency Plan C/assification and Complete the ENR form.

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 (5 3 for ROs; (N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (I 1; randomly selected) 4 for SROs & RO retakes)

NUREG-1021, Revision 9 Susquehanna Facsimile

Facility: SSES Date of Examination:l2/12/05 (Rev. 1)

Exam Level:

RO Operating Test No.:

System / JPM Title Type Code*

-I Safety Function All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all ewe different safety functions; in-plant systems and functions may overlap those 59/58/54 2 1 1 2 1 121 2 1 121 121 2 2 / 2 2 / 2 1 5 31 5 3 / 5 2 (randomly selected) 2 1 1 2 1 121 (E)mergency or abnormal in-plant (L)ow-power / Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams

a. 223001 Al.10 3.4/3.6 79.0P.006.102 Startup the A Containment Radiation Monitor System After Maintenance (post scram)

NUREG-1021, Revision 9 N, s, L 5

Susquehanna Facsimile

b. 29501 6 AA1.07 4.0/4.0 00.ON.015.104 Establish And Maintain Reactor Pressure With SRVs From The RSDP IAW ON-100-009 98.G0.001.101 Synchronize Main Generator (17% power) 52.0P.009.151 Override An Inadvertent Start Of The HPCl System In Accordance With OP-152-001 58.0P.008.101 Transferring Power Supply From RPS M-G Set To Alternate 55.ON.007.152 Respond To A Stuck Control Rod IAW ON-155-001 45.0P.004.151 Commence Feeding with an additional RFP/Shutdown RFP due to high vibrations.

73.0P.001.101 Vent The Drywell IAW OP-173-003

c. 262001 A4.04 3.W3.7

d. 206000 A4.14 4.24.1

e. 21 2000 K4.03 3.0D.1

f. 201003 A2.01 3.43.6

g. 259001 A3.10 3.4j3.4

, h. 288000 A2.01 3.3/3.4 M, s, L 3

N, A, s 6

D, A. S 4

D.

S 7

N, A. S 1

N, A, s 2

N, s 9

i. 264000 A2.09 3.7/4.1 24.0P.001.007 Transfer of DG E for DG C

j. 29501 6 AA1.06 4.014.1 50.0P.004.152 Establish and Maintain Reactor Vessel Level (RCIC Not Injecting) from the RSDP Using the Trip and Throttle Valve D, E 6

D,A,E, 4

R,L

ES-301 Control RooMn-Plant Systems Outline Form ES-301-2 Facility: SSES Date of Examination:l2/12/05 (Rev. 11 Exam Level:

SROl Operating Test No.:

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. 223001 Al.10 3.413.6 79.0P.006.102 Startup the AI Containment Radiation Monitor System After Maintenance (post scram)

b.

c. 262001 A4.04 3.6/3.7 N, A, S 6

d. 206000 A4.14 4.2/4.1 D, A. S 4

98.G0.001.lo1 Synchronize Main Generator (1 7% power) 52.0P.009.151 Override An Inadvertent Start Of The HPCl System In Accordance With OP-152-001

e. 21 5000 K4.03 3.0j3.1 D, S 7

f. 203003 A2.01 3.413.6 N, A, S 1

g. 259001 A3.10 3.413.4 N, A, S 2

h. 288000 A2.01 3.313.4 N, s 9

58.0P.008.101 Transferring Power Supply From RPS M-G Set To Alternate 55.0N.007.152 Resmnd To A Stuck Control Rod IAW ON-1 55-001 45.0P.004.151 Commence Feeding with an additional RFP/Shutdown RFP due to high vibrations.

73.0P.001.101 Vent The Drywell IAW OP-173-003 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. 264000 A2.09 3.7/4.1 24.0P.001.007 Transfer of DG E for DG C

j. 29501 6 AA1.06 4.0/4.1 50.0P.004.152 Establish and Maintain Reactor Vessel Level (RCIC Not Injecting) from the RSDP Using the Trip and Throttle Valve 55.0P.007.001 Shift The CRD Flow Stations From A To B In Accordance With

k. 201 001 A2.07 3.U3.1 OP-255-001 Q

All RO and SRO 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.

irect from bank I 91s a / I 4 (E)mergency or abnormal in-plant (L)ow-power f Shutdown (N)ew or (M)odified from bank including 1 (A) 2 1 f 2 1 f 2 1 2 1 121 I 2 1 2 2 / 2 2 / 2 1 I 3/ 5 3 f 5 2 (randomly selected) 2 1 1 2 1 / 2 1 revious 2 exams NUREG-1021, Revision 9 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-0-1 Facility: SSES Scenario No.: ILO-304 (Rev. 1)

Op-Test No.:

Examiners:

Operators:

Initial Conditions:

The scenario begins with both Units at 100% power. Fuel handling is in progress in Unit 1 Spent Fuel Pool.

Turnover :

Maintain current plant status.

Event Malf.

No. 1 No.

I 3

1 Type*

Event I Event Description C

I DRW Cooler Fan 1V416B Trip ( TS)

N/R I Min Gen Emergency Reduce Pwr 100 MWE (From 100% To - 92 %)

RRP 'A' MG-Set Hyd Fluid Temp Ctlr Failure In Auto - Manual Is Avai I a b le C/R 1 Loss Of Extraction Steam To 46 Feedwater Heater (TS)

C 1 3 Rods Drift I I RPS Failure/ARI is Successful C

M Loss Of Aux Buses 11A and 11 B lnstr Line Break Inside DW C

1 HPCl Auto Start Failure (Requires Manual Start Comp/Cornp)

M RHWSuppression Pool Leak

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Scenario No.: ILO-305 (Rev. 1)

Op-Test No.:

1 2

Examiners:

Operators:

N/R C

Increase Power with control Rod withdrawal Blown Fuse on common power Supply to IRMs B&F, and SRM B (RPS Div 2 half Scram)

Initial Conditions:

3 4

The scenario begins with Unit at 5% power with a startup in progress. Unit 2 at 100% power.

C C

D EDG Inadvertent Start (TS)

ESW pump trip (TS)

Turnover :

GO-1 00-002 has been completed through step 5.51.5. Continue plant startup at step 5.51.6 of GO-1 00-002.

I I

I Event No.

Event Description 5

1 I

Ch# I RWCUpumpRoomleak 161-C I RWCU Isolation valves Fail to isolate (Maintains leak to Sec Cont.)

I C

I 7StuckRods II I

I C

I Failed Fuel ll I

9 1

Rapid Depressurization (2 Reactor Building Areas reaching I

M l

radiation levels greater than Max Safe values)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Scenario No.: ILO-504 (Rev. 1)

Op-Test No.:

Examiners:

Operators:

Initial Conditions:

The scenario begins with both Units at 100% power. All systems are operable.

Turnover:

Maintain current plant status.

Event Malf.

Event 1

No.

No.

I Type*

1 I/R 5

1 I C/M I

CIM 9

1 Event Description RRP A Controller malfunction High Flow Causes High RX Power HPCl Steam Supply Line Leak (TS)

HPCl Valves Auto Isolation Logic Failure C RFP Control Signal failure Inadvertent Opening of D SRV Reactor vessel Leak to DRW RClC failure to Stamrip on overspeed ADS Auto Logic failure Condensate Pumps Lockout on Overcurrent RPV Rapid Depressurization (Due to RPV level < -1 61 inches)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 (1 Facility: SSES Scenario No.: ILO-505 (Rev. 1)

Op-Test No.:

Examiners:

Operators:

Initial Conditions:

The scenario begins with both Units at 100% power. All systems are operable.

Turnover:

Maintain current plant status. Perform scheduled surveillance.

Event Malf.

No.

1 NO.

2 3

1 Type*

Event I Event Description N

I Perform SO-184-001 Quarterly MSlV Closure RPS Instrumentation C72A-K3F Relay Failure during SO-1 84-001 ; Surveillance Fails I U S )

I EHC oscillations C/R Inadvertent HPCI Initiation with HPCI low Flow alarm failed OFF. (Unexplained reactivity addition) (TS)

Recirc Loop B suction line break ADS Auto Logic failure (Preload)

M I

C M

M RHR injection valve 15B Auto logic failure RPV Rapid Depressurization (lead in to RPV Flooding)

RPV Flooding (RPV level indication indeterminate due to violation of the SAT curve).

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Scenario No.: ILO-602 (Rev. 1)

Op-Test No.:

Examiners:

Operators:

Initial Conditions:

The scenario begins with both Units at 100% power. HPCl is 00s.

Turnover:

Swap in-service CRD pumps to allow maintenance to take vibration data on the CRD pump, maintenance crew is standing by.

Event Description Event Type*

Event Malf.

No.

No.

N Swap in service CRD pumps LEFM failure/forced power reduction (TS)

C MSL Flow Transmitter failure to 1.5 MPPH Recirc flow Unit D fails downscale I/R 2

1 3

1 C

Loss of CRD/inoperable accumulator (TS)

C/M Failure to ScradARI Failure/ Electrical ATWS C

SLC System failure C

Main Turbine trip without bypass valve operationAoss of Aux busses 1 1 N 1 1 B I

RClC speed controller failure

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Rapid Depressurization M

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Susquehanna Facsimile