ML060310520

Final Outlines (Folder 3)

ML060310520
Person / Time
Site:	Susquehanna
Issue date:	12/11/2005
From:	Balian H Operations Branch I
To:	Todd Fish Operations Branch I
Conte R
References
Download: ML060310520 (35)

Text

ES-401 BWR Examination Outline Form ES-401-1 11 Facilitv: Susauehanna Steam Electric Station Date of Exam: 12 to 22 December 2005 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 i1 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.

Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

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.

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.

2.

3.

4.

9.

is-401 BW R Examination Outline Form ES-401-1 Facility: Susqi iehanna Steam Electric Station Tier Group Totals

1. Emergency &

Abnormal Plant Evolutions l 2

2. Plant Systems Tier Totals Date RO WA Category Points K1 K2 K3 K4 K5 K6 A I 1 1 L

3. Generic Knowledge and Abilities Categories 2

3 Note:

of E -

X I

.an -

n: -

A2 1 A3 I A4 I G*

41 4 1 31 3

1.

2.

3.

4.

5.

6.

7.

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 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.

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

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

ES-401 BWR Examination Outline Form ES-401-1 Emerge1 K

K 1

2 EIAPE # I Name I Safety Function Question 1 Forced Core Flow Circulation 295001 Partial or Complete Loss of X

I t

I I

Question 2 295003 Partial or Complete Loss of A.C. Power Question 3 295004 Partial or Complete Loss of D.C. Power Question 4 295004 Partial or Complete Loss of D.C. Power lr Question 5 295005 Main Turbine Trip Ouestion 6 295006 SCRAM Question 7 3,95016 Control Room Abandonment Jlant Evolutions - Tier 1 / Group 1 (RO)

WA Topic(s)

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:

AKl.05 Loss of breaker protection 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area /

communication with fuel storage facility

/ systems operated from the control room in support of fueling operations / and sumorti n E 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

BWR Examination Outline Form ES-401-1 ES-401 EIAPE # I Name I Safety Function Ouestion 8 295018 Partial or Complete Loss of Component Question 9 2950 19 Partial or Complete Loss of Instrument Air Question 10 295021 Loss of Shutdown Cooling Ouestion 11 295023 Refueling Accidents Question 12 295024 High Drywell Pressure Question 13 295025 High Reactor Pressure Question 14 295026 Suppression Pool High Water Temperature Question 15 295028 High Drywell Temperature 1 Abnorma 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 :

AK1.01 Effects on componentlsystem operations AA1. Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :

AA1.03 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 REFUELING ACCIDENTS :

AKl.01 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:

EA2.03 Suppression Pool Temperature EK1. Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

EK 1.02 Steam Condensation EK3. Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE:

EK3.02 RPV flooding IR -

3.5 3.O 2.9 3.6 2.5 -

3.9 3.5 3.5 NUREG-1021, Rev 9 Page3 of 15 Susquehanna Facsimile

ES-401 BWR Examination Outline Form ES-401-1 d Abnc nal Plant Evolutions - Tier 1 / Group 1 (RO)

IR -

3.6 4.1 -

4.0 3.6 3.O -

WAPE # I Name I Safety Function WA Topic(s)

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

EA 1.06 Condensate storage and transfer (make-up to the suppression pool):

Plant-Specific Question 16 29.5030 Low Suppression Pool Water Level EK2. Knowledge of the interrelations between REACTOR LOW WATER LEVEL and the following:

EK2.13 ARVRPT/ATWS: Plant-Specific Question 17 29503 1 Reactor Low Water Level 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Question 18 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1. Ability to operate and/or monitor the following as they apply to EA1.07 Control room ventilation: Plant-Specific HIGH OFF-SITE RELEASE RATE:

Question 19 295038 High Off-Site Release Rate AA1 Ability to operate and / or monitor the following as they apply to PLANT FIRE ON SITE:

AAl.06 Fire alarm Question 20 600000 Plant Fire On Site WA Category Totals:

Group Point Total:

20 page 4 of 1.5 NUREG-1021. Rev 9 Susquehanna Facsimile

ES-401 Eme UAPE i# I Name I Safety Function Question 21 295008 High Reactor Water Level Question 22 295009 Low Reactor Water Level Question 23 2950 13 High Suppression Pool Temperature Question 24 2950 15 Incomplete SCRAM Question 25 295034 Secondary Containment Ventilation High Question 26 295036 Secondary Containment High Sump Question 27 SO0000 High Containment Hydrogen Concentration WA Category Point Totals:

BWR Examination Outline Form ES-401-1 ency and Abnormal Plant Evolutions - Tier 1 I Group 2 (RO)

WA Topic(s) 2.1.20 Ability to execute procedure steps.

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 SUMP/AREA WATER LEVEL :

EA 1.O 1 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. Rev 9 page 5 of 15 Susquehanna Facsimile

11 ES-401 (1 System #

Question 28 203000 Residual Heat Removal /Low Pressure Coolant Injection: Injection Mode (Plant Specific)

Question 29 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

Question 30 206000 High Pressure Coolant Question 31 206000 High Pressure Coolant Injection System Question 32 209001 Low Pressure Core Spray System Question 33 21 1000 Standby Liquid Control System NUREG-1021, R e v 9 BWR Examination Outline Plant Systems - Tier 2 / Group 1 (RO)

Form ES-401-1 page 6 of 15 Susquehanna Facsimile

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

Form ES-401-1 System #

WA Topic(s) 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

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.

Question 34 21 1000 Standby Liquid Control System 3.4 Question 35 2 12000 Reactor Protection System 3.8 A3. Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including:

A3.01 Reactor Power Question 36 2 I2000 Reactor Protection System 4.4 K2. Knowledge of electrical power supplies to the following:

K2.0 1 IRM channels/detectors Question 37 2 15003 Intermediate Range Monitor System 2.5 K5. Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM)

SYSTEM :

K5.03 Changing detector position Question 38 2 15004 Source Range Monitor (SRM) System 2.8 page 7 of 15 NUREG-1021, Rev 9 Susquehanna Facsimile

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

IR System #

WA Topic(s)

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 Question 39 2 15005 Average Power Range MonitorLocal Power Range Monitor 3.9 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 Question 40 217000 Reactor Core Isolation Cooling System 3.5

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A3. Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:

A3.01 ADS valve operation Question 41 2 18000 Automatic Depressurization System 4.2 K6. Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEMAYUCLEAR OFF :

K6.02 D.C. electrical distribution STEAM SUPPLY SHUT-Ouestion 42 223002 Primary Containment Isolation System / Nuclear Steam Supply Shut-Off 3.0 NUREG-1021, Rev 9 page 8 of 15 Susquehanna Facsimile

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

Form ES-401 IR System #

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 Question 43 239002 Safety Relief Valves 3.7 K3. Knowledge of the effect that a loss or malfunction of the HIGH PRESSURE COOLANT INJECTION SYSTEM will have on following:

K3.03 Rod worth minimizer:

BWR-2,3,4 Question 44 259002 Reactor Water Level Control System 2.7 A4. Ability to manually operate and/or monitor in the control room:

A4.09TDRFP lockout reset:

K1. Knowledge of the physical connections and/or cause effect relationships between STANDBY GAS TREATMENT SYSTEM and the following:

K1.O1 Reactor building ven ti 1 ati on s ys tern.

TDRFP. BWR-2,3,4 Question 45 259002 Reactor Water Level Control System 3.4 Question 46 261000 Standby Gas Treatment S ys tern 3.4 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:

A2.05 Bus grounds.

Question 47 262001 A.C. Electrical Distribution 3.8 NUREG-1021, Rev 9 page9 of 15 Susquehanna Facsimile

I/ ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2 / Group 1 (RO)

Question 48 262002 Uninterruptable Power Supply 263000 D.C. Electrical Distribution 11 264000 Emergency Generators (Diesel/Jet)

Question 51 300000 Instrument Air System WA Topic(s)

K6. Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.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:

Al.09 Maintaining minimum load on emergency generator (to prevent reverse power)

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 IR -

2.7 3.2 3.O 2.9 NUREG-1021. Rev 9 Page 10 of 15 Susquehanna Facsimile

11 ES-401 I System #

Question 52 300000 Instrument Air System Question 53

1) WA Category Point Totals:

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

A A

2 3

X WA Topic(s)

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

A4.01 Pressure gauges 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 HighJlow surge tank level Group Point Total:

IR 2.6 2.8 26 NUREG-1021, Rev 9 Page I I of 15 Susquehanna Facsimile

ES-401 I Y I !

System #

Ouestion 54 20 100 I Control Rod Drive Hydraulic System Ouestion 55 201002 Reactor Manual Control System X I Ouestion 56 201004 Rod Sequence Control System (Plant Specific)

Ouestion 57 201006 Rod Worth Minimizer System (RWM)

Question 58 202001 Recirculation System I Ouestion 59 202002 Recirculation flow Control System BW R Examination Outline Form ES-401-1 Plant Systems

- Tier 2 /Group 2 (RO)

WA Topic@)

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

A3.11 SDV level 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 A3. Ability to monitor automatic operations of the ROD SEQUENCE CONTROL SYSTEM (PLANT SPECIFIC) including:

A3.05 ?Verification of proper function/ operability: BWR-4,s 2.2.26 Knowledge of refueling administrative requirements.

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

A4.02 System valves K3. Knowledge of the effect that a loss or malfunction of the RECIRCULATION FLOW CONTROL SYSTEM will have on following:

K3.01 Core flow 3.5 3.5 3.5 2.5 3.5 3.5 NUREG-1021, Rev 9 Page 12 of 15 Susquehanna Facsimile

ES-401 System #

Question 60 204000 Reactor Water Cleanup System Question 61 214000 Rod Position Information System Question 62 2 19000 RHRLPCI:

Torus/Suppression Pool Cooling Mode Question 63 22600 1 RWLPCI:

Containment Spray System Ouestion 64 239001 Main and Reheat Steam System BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2 / Group 2 (RO)

WA Topic(s)

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

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

K4.02 Thermocouple K2. Knowledge of electrical power supplies to the following:

K2.02 Pumps 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:

A 1.10 Reactor power.

IR 3.1 2.5 3.1 3.1 3.6 NUREG-1021, Rev 9 Page 13 of 15 Susquehanna Facsimile

ll li System #

Question 65 I 28 8000 Plant Ven ti 1 ation Systems WA Category Point Totals:

BW R Examination Outline Plant Systems Form ES-401-1

- Tier 2 / Group 2 (RO)

K K

K K

K 1

2 3

4 5

x WA Topic@)

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

K5.0 1 Airborne contamination control Group Point Total:

IR 3.1 12 NUREG-1021. Rev 9 Page 14 of 15 Susquehanna Facsimile

S-40 1 BW R Examination Outline Form ES-401-1

1.

2.

3.

4.

5.

6.

7.

8.

9.

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 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 statements.

NUREG-1021, Rev 9 Page 1 of 6 S u s q u e h a n n a Facsimile

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

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

/I ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (SRO) 11 WA Category Point Totals:

I I I I I 21 1 WA Topic(s)

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

AA2.01 Condenser vacuudabsolute pressure 3.1 2.4.6 Knowledge symptom based EOP mi tigation strategies.

4.O EA2. Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL EA2.02 tOff-site release rate: Plant-Specific 4.1 Group Point Total:

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)

System ##

Question 86 2 15004 Source Range Monitor System Question 87 261000 Standby Gas Treatment System Question 88 262001 A.C. Electrical Distribution Question 89 263000 D.C. Electrical Distribution Question 90 264000 Emergency ( ;enerators (DieseVJet)

WA Category Point Totals:

~

~

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 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:

A2.03 Loss of off-site power.

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 4.3 3.6 3.8 -

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

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

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 2.2.22 Knowledge uf limiting conditions for operations and safety limits.

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

A3.01 tCrane/refuel bridge movement: Plant-Specific.

~~~

Group Point Total:

3.3 3.4 -

3.6 3

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

ES 401 Generic Knowledge and Abilities Outline Tier 3 Form ES-40 1-3 Facility: Susquehanna Steam Electric Station Date of Exam:

12 to 22 December 2005 Topic Question KIA#

Category 66 -

2.1.21 3.1 Ability to obtain and verify controlled procedure I.

Zonduct 3f 3perations copy.

Ability to explain and apply system limits and 3.4 67 -

2.1.32 Subtotal 2.5 Knowledge of the process for controlling temporary changes.

Knowedge of bases in technical specifications 68 2.2.11

2.

Equipment Control conditions for 2.5 the refueling process.

2.6 safety limits.

Subtotal 1 2.6 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

71 1 2.3.1 I

3.

Radiation Control 72 2.3.2 Knowledge of facility ALARA program.

2.5 Subtotal 3.1 Knowledge symptom based EOP mitigation strategies.

Knowledge of EOP terms and definitions.

3.1 Knowledge of the bases for prioritizing safety functions during 3.O 73 2.4.6

4.

Emergency Procedures/

Plan 2.4.17 74 75 2.4.22 Tier 3 Point Total

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Subtotal Page 15 of 15 Susquehanna Facsimile NUREG-1021. Rev 9

ES 401 Generic Knowledge and Abilities Outline Tier 3 Form ES-40 1-3 Facility: Susquehanna Steam Electric Station Category Conduct of Operations Equipment Control Radiation Control Emergency Procedures /

Plan Tier 3 Point Ouestion WA#

94 2.1.7 95 12.1.12 Subtotal 96 1 2.2.7 2.2.19 97 I

Subtotal Date of Exam:

12 to 22 December 2005 NUREG-1021, Rev 9 Page 6 of 6 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Group Randomly Selected WA 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 I Group 2

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295008.2.1.17 Question 66 RO Tier 3 2.1.16 Reason for Rejection 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-401 Record of Rejected WAS Form ES-40 1 -4 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 E/APE #/Name/Safety Function to maintain outline fidelity to the maximum extent possible.

. 3.-

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:

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

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

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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 NUREG-1021 Rev 9 Page 2of 6 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-401-4 I 259002.K3.03 Question 45 259002.A4.09

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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 September 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

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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 WA 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 262001A2.03.

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 WA 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 httD://www.random.orq 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

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Page 3of 6 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-401-4 Question 47 RO Tier 2 / Group 1 262001.A2.03 239001.Al.O6 Rejected 262001.A2.03 during Branch Chief review because unable to develop RO level question that meets this WA. The requirement to... 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

/

I match.

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

Selected 239001.A1.lo.

I 22 SeDtember 2005 Question 92 Tier Group 21 6000.2.4.27 Question 34 RO Tier 2 / Group 1 21 1000.2.1.2 30 September 2005 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.

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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.orq 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 1 Question 88 SRO Tier 2 / Group 1 262002.A2.02 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.

Question 13 Rejected 295025.EA2.02 because during review it was determined to be similar to 295006.AA2.04 and because development of a suitable question moved difficult.

Used http://www.random.orq to select another WA from the 295025.EA2 series. Selected 295025.EA2.03 RO Tier 1 / Group 1 1 295025.EA2.02 1 17 October 2005 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.

directly because there are only two WAS under the

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Question 14 RO Tier 1 / Group 1 NUREG-1021 Rev 9 Page 4of 6 Susquehanna Facsimile

ES-40 1 Record of Rejected WAS Form ES-401-4 295026.EK1.01 Question 21 Question 51 I RO Tier 2 / Group 1 300000.A2.0 1 1 Question 53 400000.A2.02 Question 57 I RO Tier 2 / Group 2

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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 W A statements in Tiers 1 and 2 and a number of generic W A 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 W A statement requiring the highest cognitive level (e.g., the (b) portion of the A.2 W A 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.

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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 W A statements, such as 2.4. I, in Tier 3), try to test both aspects of the W A statement. If that is not possible without expending an inordinate amount of resources, limit the scope of the question to that aspect of the W A statement requiring the highest cognitive level (e.g., the (b) portion of the A.2 W A 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.

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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 W A statements, such as 2.4.1, in Tier 3), try to test both aspects of the tVA 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 K/A statements) or substitute another randomly selected WA.].

18 October 2005 NUREG-1021 Rev 9 Page Sof 6 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-401-4 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 W A statements in Tiers 7 and 2 and a number of generic WA statements, such as 2.4.7, 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 KZA 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.

Question 63 RO Tier 2 / Group 2 226001.A2.03 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 remonse Drocedures.

Question 100 SRO Tier 3 Generic 2.4.1 0 Used http://www.random.org to select another WA from the Gen2.4.10 series.

Selected Gen.2.4.11.

31 October 2005 NUREG-1021 Rev 9 Page 60f 6 Susquehanna Facsimile

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

SSES Examination Level RO Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code*

Date of Examination:

Operating Test Number:

I Describe activity to be performed 12/12/05 (Rev. 2) 2.1.18 2.9 78.AD.001.101 Document a failed LPRM and determine the appropriate compensatory actions.

2.1.25 2.8 45.0N.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 reauired.

Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (1.3 for ROs; 5 4 for SROs & RO retakes)

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

(P)revious 2 exams (5 1; randomly selected)

NUREG-1021, Revision 9 Susquehanna Facsimile

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Administrative ToDics Outline Form ES-301-1 Facility:

SSES Examination Level SRO Date of Examination:

Operating Test Number:

12/12/05 (Rev. 2)

Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code*

M, S Describe activity to be performed 2.1.12 4.0

00. AD.273.OO 1 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.

69.0P.044.051 Review and Approve LW Discharge 2.4.41 4.0 00.EP.001.304, 305, 504, 505, 602 Perform Emergency Plan Classification 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 (r 3 for ROs; 1.4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2.1)

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

NUREG-1021, Revision 9 Susquehanna Facsimile

ES-301 Control Roomhn-Plant Systems Outline Form ES-301-2 Facility: SSES Date of Examination:12/12/05 (Rev. 2)

Exam Level:

RO Operating Test No.:

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

System / JPM Title Type Safety Code*

Function

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

N, s, L 5

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

~ c. 262001 A4.04 3.6/3.7 N, s 6

d. 206000 A4.14 424.1 D. A, S 4

e. 21 2000 K4.03 3.0i3.1 D,

S 7

f. 20003 A2.01 3.4/3.6 N, A. S 1

98.G0.001.101 Synchronize Main Generator (1 7% power) 52.0P.009.151 Terminate HPCl injection (with several malfunctions inserted) 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

g. 259001 A3.10 3.413.4 2

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

h. 288000 A2.01 3.3/3.4 N, s 9

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

i. 264000 A2.09 3.7/4.1 D, E 6

24.0P.001.007 Transfer of DG E for DG C

j. 295016 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.H3.1 OP-255-001 4

1 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.

(D)irect from bank 5 9 / 5 8 / 5 4 (E)mergency or abnormal in-plant 2 1 121 121 (L)ow-power / Shutdown 2 1 / 2 1 121 (N)ew or (M)odified from bank including 1 (A) 2 2 / 2 2 / 2 1 (P)revious 2 exams 5 3/ 5 3 I s 2 (randomly selected)

(R)CA 2 1 121 1 2 1 (S)imulator NUREG-1021, Revision 9 Susquehanna Facsimile

ES-301

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

Exam Level:

SROl Operating Test No.:

I 1

System I JPM Title Type Safety Code*

Function

a. 223001 Al.10 3.4/3.6 5

79.0P.006.102 Startup the A Containment Radiation Monitor System After Maintenance (post scram)

b.

c. 262001 A4.04 3.613.7 N, s 6

d. 206000 A4.14 4.2/4.1 D, A. S 3

e. 212000 K4.03 3.0/3.1 D,

S 7

98.G0.001.lo1 Synchronize Main Generator (17% power) 52.0P.009.151 Terminate HPCI injection (with several malfunctions inserted) 58.0P.008.101 Transferring Power Supply From RPS M-G Set To Alternate

f. 201003 A2.01 3.413.6 N. A, S 1

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

55.0N.007.152 Respond To A Stuck Control Rod IAW ON-1 55-001 45.0P.004.151 Commence Feeding with an additional RFPIShutdown RFP due to high vibrations.

h. 288000 A2.01 3.313.4 N, s 9

73.0P.001.lo1 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 D, E 6

24.0P.001.007 Transfer of DG E for DG C 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

j. 29501 6 AAl.06 4.014.1 D, A E, 4

k. 201 001 A2.07 3.U3.1 D, R 1

R, L OP-255-001 8

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.

(D)irect from bank (E)mergency or abnormal in-plant 2 1 12 1 / 2 1 (L)ow-power I Shutdown 2 112 112 1 (N)ew or (M)odified from bank including 1 (A) 2 2 1 2 2 1 2 1 (P)revious 2 exams S 31 S 3 / 5 2 (randomly selected)

(WCA 2 1 I 2 1/22 1 (S)imulator 5 91 5 a I 5 4 NUREG-1021, Revision 9 Susquehanna Facsimile

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Scenario No.: ILO-602 (Rev. 2)

Op-Test No.:

I 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 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 Loss of CRD/inoperable accumulator (TS)

Failure to Scram/ARI Failure/ Electrical ATWS SLC System failure Main Turbine trip without bypass valve operation/loss of Aux busses 1 1 N11 B

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RClC speed controller failure Rapid Depressurization

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

Appendix D Scenario Outline Form ES-D-1 Event Malf.

Event No.

No.

Type*

Facility: SSES Scenario No.: ILO-505 (Rev. 2)

Op-Test No.:

I Examiners:

Operators: ~

Event Description 4

5 I1 I

M I

Recirc Loop B suction line break ADS Auto Logic failure (Preload) 1 N

1 Perform SO-1 84-001 Quarterly MSlV Closure RPS Instrumentation 7

8 II I

M M

RPV Rapid Depressurization (lead in to RPV Flooding)

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

C C72A-K3F Relay Failure during SO-1 84-001 ; Surveillance Fails I

IFS)

I/

I Inadvertent HPCl Initiation with HPCl low Flow alarm failed OFF.

I CR I (Unexplained reactivity addition) (TS) 1 C

1 RHR injection valve 15B Auto logic failure (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. 2)

Op-Test No.:

1 Examiners:

Operators:

Initial Conditions:

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

power.

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.

Event Malf.

Event No.

1 No. 1 Type*

1 N/R 2

C 3

1 I

C 4

1 I

C 5

1 I

CIM I

C 7

1 I

C I

C 8

C 9

M Event Description

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

D EDG Inadvertent Start (TS)

ESW pump trip (TS)

RWCU pump Room leak RWCU Isolation valves Fail to isolate (Maintains leak to Sec Cont.)

7 Stuck Rods Failed Fuel Rapid Depressurization (2 Reactor Building Areas reaching radiation levels greater than Max Safe values)

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