ML032650556

Final - Outlines (Change Summaries - Optional)

ML032650556
Person / Time
Site:	Susquehanna
Issue date:	08/01/2003
From:	Kroush K Susquehanna
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-387/03-301, 50-388/03-301
Download: ML032650556 (18)

Text

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

SUSQUEHANNA Date of Exam 8/11-8/15 2003 1

1. P-Emergency 8z Abnormal Plant Tier Evolutions Totals 1

2.

Plant Systems 2

Tier Totals RO O I 1 w

AC :ategory Poi K

K K

K A

3 I 4 1 5 16 I 1

3. Generic Knowledge and Abilities Categories Note:

1.

2.

3.

4.

5.

5.

7.

3.

9.

Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the Tier Totals in each WA category shall not be less than two). Refer to Section D.1.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 KIA 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 n0n-M 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 KIA statements.

NUREG-1021, Draft Rev 9 2003 NRC Exam Rev. 2 RO 1 of 10 Susquehanna Facsimile

BWR Examination Outline Form ES-401-1 I1 ES-401 Emergency and Abnormal Plant Evolutions -Tier 1lGroup I(R0)

EIAPE # / Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 Q.

2 295004 Partial or Total Loss of DC Pwr 16 Q.

3 11 295005 Main Turbine Generator Trip /

295005 Main Turbine Generator Trip /

Q.4 295006 SCRAM / 1 Q.

5 It Q-5

" 295016 Control Room Abandonment / 7

-4.6

~

295018 Partial or Total Loss of CCW I 8

~~

295019 Partial or Total Loss of Inst. Air 18 Q. 8 295021 Loss of Shutdown Cooling / 4 Q. 9 295023 Refueling Accidents Cooling Mode

/ 8 Q.

I O 295024 High Drywell Pressure I 5 Q.11

~

295025 High Reactor Pressure I 3 Q. 12 NUREG-1021, DraH Rev 9 2003 NRC Exam Rev. 2 R 0 2 of 10 WA Topic(s)

I IR I

AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

3.3 AA1.05 Recirculation flow control system I

AK2 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF A.C. POWER and the following:

AK2.02 Emergency generators AKI Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

4.1 2.9 AKI.03 Electrical bus divisional separation I

AA2 Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP :

3.1 AA2.03 Turbine valve position AA1 Ability to operate and/or monitor the following as they apply to SCRAM :

AA1.04 Recirculation system AK3 Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT :

AK3.03 Disabling control room controls 2.4.1 1 Knowledge of abnormal condition procedures 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

3.1 3.5 3.4 3.5 AK3 Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING :

3.6 AK3.05 Establishing alternate heat removal flow paths AA1. Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS :

AA1.07 Standby gas treatmenVFRVS 3.6 EA2. Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE:

3.9 EA2.04 Suppression chamber pressure: Plant-2.4.18 Knowledge of the specific bases for EOPs.

Susauehanna Facsimile

ll ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier I/Group l(R0)

I r-E/APE # I Name / Safety Function 295026 Suppression Pool High Water Temp. / 5 Q. 13 295028 High Drywell Temperature I5 Q. 14 295030 Low Suppression Pool Water Level I 5 Q. 15 295031 Reactor Low Water Level / 2 Q. 16 295031 Reactor Low Water Level / 2 Q.17 295037 SCRAM Condition Present and Power Above APRM Downscale or

'Jnknown I I Q. 18 295038 High Off-site Release Rate I 9 I

ll Q-19 600000 Plant Fire On Site I 8 I Q.20 K/A Categoly Totals:

NUREG-1021. Draft Rev 9 2003 NRC Exam Rev. 2 I IR I #

WA Topic(s)

EA2 Ability to determine and/or interpret the EA1 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE :

LOW WATER LEVEL :

POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following:

EK3. Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE:

EK3.02 S stem isolations 2.1.31 Ability to locate control room switches I,

controls and indications and to determine that they are correct1 reflectin the desired lant lineu.

Group Point Total:

20 RO 3 of 10 Susquehanna Facsimile

ES-401 Em 3.2 4.0 3.9 3.8 EIAPE # I Name I Safety Function 295008 High Reactor Water Level I 2 1

1 1

1 I

11 295009 Low Reactor Water Level I 2 Q-27 11 Q.22 295015 Incomplete SCRAM I I I

11 Q.24 11 295020 Inadvertent Cont. Isolation / 5 & 7 Q. 26 71 11 295022 Loss of CRD Pumps I 1 11 Q.27 WA Category Point Totals:

NUREG-1 021, Drafl Rev 9 2003 NRC Exam Rev. 2 R O 4 o f l O BWR Examination Outline Form ES-401-1 rencv and Abnormal Plant Evolutions - Tier 11Group 2(RO)

I I

A G

WA Topic(s) 2 AKI Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR WATER LEVEL :

AKI.03 Feed flow/steam flow mismatch AA1 Ability to operate andlor monitor the following as they apply to LOW REACTOR WATER LEVEL :

AA1.02 Reactor water level control AA1 Ability to operate andlor monitor the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE :

AA1.01 Suppression pool cooling AA1. Ability to operate andlor monitor the following as they apply to INCOMPLETE SCRAM :

AA1.01 CRD hydraulics AKI Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE :

AKI.02 Protection of the general public AK3 Knowledge of the reasons for the following responses as they apply to INADVERTENT CONTAINMENT ISOLATION:

AK3.06 Suppression pool water level response AA2 Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS :

x I AA2.03 CRD mechanism temperatures I

1 2 I 0 I Grow Point Total:

~

17 Susquehanna Facsimile

ll ES-401 BWR Examination Outline F O I ~

ES-401-1 I

System #

203000 RHWLPCI:

Injection Mode Q. 28 203000 RHWLPCI:

Injection Mode 205000 Shutdown Cooling 206000 HPCl Q.31 209001 LPCS Q. 32

~~

209001 LPCS 3.33 21 1000 SLC Q. 34 21 1000 SLC Q. 35 212000 RPS Q. 36 212000 RPS Q.37 21 5003 IRM Q.38 21 5004 Source Range Monitor Q. 39

- Tier 2/Grour, 1 IRO)

I IR WA Topic(s)

K4. Knowledge of RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) design feature@) and/or interlocks which provide for the following:

K4.06 Adequate pump net positive suction head (interlock suction valve open): Plant-Specific 2.2.22 Knowledge of limiting conditions for operations and safety limits.

A3. Ability to monitor automatic operations of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including:

A3.02 Pump trips 2.4.10 Knowledge of annunciator response procedures.

3.2 3.0 K2. Knowledge of electrical power supplies to the following:

K2.03 Initiation logic K3. Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:

K3.02 ADS logic A4. Ability to manually operate and/or monitor in the control room:

2.9 3.8 4.2 A4.08 System initiation: Plant-Specific I

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation.

KI. Knowledge of the physical connections and/or cause/effect relationships between REACTOR PROTECTION SYSTEM and the following:

KI.I4 Main steam system K2. Knowledge of electrical power supplies to the following:

K2.01 RPS motor-generator sets A3. Ability to monitor automatic operations of the including:

3.7 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM A3.03 RPS status K5. Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM) SYSTEM :

K5.01 Detector operation 3.7 3.6 3.2 2.6 NUREG-1021, Draft Rev9 2003 NRC Exam Rev. 2 RO 5 of 10 Susauehanna Facsimile

ES-401 I System #

"I 259002 Reactor Water Level Control Q.45 261000 SGTS Q.46 262001 AC Electrical Distribution Q.47 262002 UPS (AC/DC)

Q.48 263000 DC Electrical Distribution 1.49 NUREG-1021. Draft Rev 9 2003 NRC Exam Rev. 2 BWR Examination Outline Form ES-401-1 R 0 6 of 10

- Tier 2/Group I (RO)

WA Topic(s)

K6. Knowledge of the effect that a loss or malfunction of the following will have on the AVERAGE POWER RANGE MONITOIWLOCAL POWER RANGE MONITOR SYSTEM :

K6.07 Flow convertedcomparator network: Plant-Specific K2. Knowledge of electrical power supplies to the following:

K2.02 RClC initiation signals (logic)

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

K6.03 Nuclear boiler instrument system (level indication)

K4. Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design feature@) and/or interlocks which provide for the following:

K4.03 Manual initiation capability: Plant-Specific AI. Ability to predict andlor monitor changes in parameters associated with operating the RELIEFEAFETY VALVES controls including:

AI.06 Reactor power A2. Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 Loss of reactor water level input K1. Knowledge of the physical connections and/or cause/effect relationships between STANDBY GAS TREATMENT SYSTEM and the following:

KI.I 1 Primary containment pressure K3. Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following:

K3.05 Off-site power system K4. Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature@) and/or interlocks which provide for the following:

K4.01 Transfer from preferred power to alternate power supplies K3. Knowledge of the effect that a loss or malfunction of the D.C. ELECTRICAL DISTRIBUTION will have on following:

K3.03 Systems with D.C. components (Le. valves, motors, solenoids, etc.)

Susquehanna Facsimile 2.8 -

3.8 3.5 3.7 3.6 3.2 3.2 3.1 3.4

ES-401 I System #

300000 Instrument Air Q. 52 400000 Component WA Category Point Totals:

X BWR Examination Outline Form ES-401-1 P

A 1

nt A

2

- - ;ystems p X

X

- Tier 2IGroup 1 (RO)

WA Topic(s)

A3. Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including:

A3.01 Meters, dials, recorders, alarms, and indicating lights AI. Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEUJET) controls including:

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

K3. Knowledge of the effect that a loss or malfunction of the (INSTRUMENT AIR SYSTEM) will have on the following:

K3.01 Containment air system A4. Ability to manually operate and / or monitor in the control room:

A4.01 CCW indications and control Group Point Total:

3.0 2.7 -

3.1 NUREG-1021, Orafl Rev 9 2003 NRC Exam Rev. 2 R 0 7 of 10 Susquehanna Facsimile

BWR Examination Outline Form ES-401-1 I1 ES-401 er 2/Group 2 (RO)

WA Topic(s)

System #

K6. Knowledge of the effect that a loss or malfunction of the following will have on the CONTROL ROD DRIVE HYDRAULIC System :

K6.05 A.C. power AI. Ability to predict and/or monitor changes in parameters associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including:

A I -03 CRD drive water flow K5. Knowledge of the operational implications of the following concepts as they apply to ROD SEQUENCE:

K5.01 Prevention of clad damage if a control rod drop accident (CRDA) occurs: BWR-4,5 AI. Ability to predict and/or monitor changes in parameters associated with operating the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) controls including:

A I.01 Rod position: P-Spec(Not-BWRG)

K2. Knowledge of electrical power supplies to the following:

K2.03 Recirculation system valves A3. Ability to monitor automatic operations of the ROD BLOCK MONITOR SYSTEM including:

A3.03 Alarm and indicating lights: BWR-3,4,5 K4. Knowledge of NUCLEAR BOILER INSTRUMENTATION design feature(s) and/or interlocks which provide for the following:

K4.09 Protection against filling the main steam lines from the feed system AI. Ability to predict and/or monitor changes in parameters associated with operating the RHWLPCI: TORUS/SUPPRESSION POOL COOLING MODE controls including:

A I.02 System flow A2. Ability to (a) predict the impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.12 Loss of equipment component cooling water systems A3. Ability to monitor automatic operations of the RADIATION MONITORING SYSTEM including:

A3.06 Ventilation system isolation indications 201001 CRD Hydraulic Q. 54 201 003 Control Rod and Drive Mechanism Q. 55 2.9 201 004 RSCS Q. 56 3.6 3.2

~

~~

201 006 RWM Q.57 202001 Recirculation Q. 58 2.7 -

3.1 21 5002 RBM Q. 59 21 6000 Nuclear Boiler Instrumentation Q. 60 3.3 3.5 219000 RHWLPCI:

ToruslPool Cooling Mode Q.61 256000 Reactor Condensate Q. 62 3.1 272000 Radiation Monitoring Q. 63 ri 3.4 RO 8 of 10 Susquehanna Facsimile NUREG-1021, DraH Rev 9 2003 NRC Exam Rev. 2

II ES-401 4

'I System #

A G

WA Topic(s)

IR K3. Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION SYSTEMS will have on following:

2.9 1

290001 Secondary CTMT K/A Category Point Totals:

X K3.02 Reactor building temperature: Plant-Specific A4. Ability to manually operate and/or monitor in the control room:

3.4 1

NUREG-1021. Draft Rev9 2003 NRC Exam Rev. 2 1

K 1

0 Group Point Total:

12 K

2 BWR Examination Outline Form ES-401-1 tems

- Tier 2/Group 2 (RO)

I I

I I

Plant S!

qqi li RO 9 of 10 I

1 I

I A4.11 System reset: Plant-Specific Susquehanna Facsimile

ES 401 Generic Knowledge and Abilities Outline Tier 3 Form ES-40 1-3 Date of Exam 8/11-8/15 2003

' Gacility SUSOUEHANNA Category K/A#

Topic IR Knowledge of operator responsibilities during all modes of plant operation.

3.0

1.

2.1.2 Q. 66 2.1.23 Conduct of Operations Ability to perform specific system and integrated plant procedures during different modes of plant operation.

3.9 Q.67 2.1.7 Q. 68 Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation.

3.7 Subtotal

2.

2.2.22 Q. 69 Knowledge of limiting conditions for operations and safety limits.

3.4 Equipment Control 2.2.1 1 Q. 70 Knowledge of the process for controlling temporary changes.

2.5 2.2.26 Q. 71 Knowledge of refueling administrative requirements.

2.5 Subtotal

3.

Radiation Control 2.6 2.3.1 Q. 72 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

2.3.9 Q. 73 Knowledge of the process for performing a containment purge.

2.5 Subtotal

4.

I 2.4.18 2.4.18 Knowledge of the specific bases for EOPs.

2.7 Q.74 I

I Emergency Procedures/

Plan 3.3 2.4.9 Q. 75 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation stratea ies.

Subtotal rier 3 Point Total RO 10 of 10 NUREG-1021. Draft Rev 9 2003 NRC Exam Rev. 2 Susquehanna Facsimile

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

SUSQUEHANNA Date of Exam 8/1 1-8/15 2003 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.1.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 KIA 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, Draft Rev 9 2003 NRC Exam Rev. 2 SRO 1 of 6 Susquehanna Facsimile

BWR Examination Outline Form ES-401-1 ES-401 I EIAPE # I Name / Safety Function Plant Evolutions - Tier I/Group I(SR0)

K/A Topic@)

295001 Partial or ComDlete Loss of Forced Core Flow Circulation / I & 4 Q. 76 AA2. Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

AA2.02 Neutron monitoring (IOCFR 55.43)

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

AA2.02 Status of safety-related instrument air system loads (1 OCFR 55.43)

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

AA2.05 +Entry conditions of emergency plan (1 OCFR 55.43)

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

EA2.02 Drywell temperature (IOCFR 55.43) 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation.

• SRO LEVEL OBJECTIVE 2.4.1 1 Knowledge of abnormal condition procedures.

(1 OCFR 55.43)

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

EA2.03 Reactor water level (1 OCFR 55.43) 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormallemergency operations.

(1 OCFR 55.43)

Group Point Total:

295019 Partial or Total Loss of Inst. Air / 8 Q. 77 3.7 4.6 295023 Refueling Accidents Cooling Mode 18 Q. 78 295024 High Drywell Pressure I 5 Q. 79 4.0 295025 High Reactor Pressure I 3 Q. 80 4.0 71 295026 Suppression Pool High Water Temp. I 5 3.6 3.9 4.0 T

11 WA Category Totals:

SRO 2 of 6 NUREG-1021, Draft Rev 9 2003 NRC Exam Rev. 2 Susquehanna Facsimile

II ES-401 II BWR Examination Outline Forp ES-401-1 Em1 K

1 EIAPE # I Name I Safety Function 295002 Loss of Main Condenser Vacuum /

295014 Inadvertent Reactivity Addition I 1 Q. 85 295015 Incomplete SCRAM / 1 Q. 86 295022 Loss of CRD Pumps I 1 Q. 87 WA Category Point Totals:

0 I

I

!I v and Abnormal Plant Evolutions - Tier 11Group 2(SRO)

I IR I II WA Topic(s)

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

AA2.02 Reactor power: Plant-Specific (IOCFR 55.43)

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

AA2.01 Reactor power (1 OCFR 55.43) 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation.

(IOCFR 55.43)

AA2. Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS :

AA2.01 Accumulator pressure (1 OCFR 55.43)

Group Point Total:

4 4.4 3.6 NUREG-1021, Drafl Rev 9 2003 NRC Exam Rev. 2 SRO 3 of 6 Susquehanna Facsimile

II ES-401 II System #

203000 RHWLPCI:

Injection Mode Q. 88 205000 Shutdown Cooling Q. 89 203000 RHWLPCI:

Injection Mode Q. 88 205000 Shutdown Cooling Q. 89 209001 LPCS Q. 90 264000 EDGs Q. 91 209001 LPCS Q. 90 264000 EDGs Q. 91 WA Category Point 11 Totals:

NUREG-1021. Draft Rev 9 2003 NRC Exam Rev. 2 BWR Examination Outline Form ES-401-1 SRO 4 of 6 stems

- Tier 2IGroup l(SR0)

WA Topic(s)

~

A2. Ability to (a) predict the impacts of the following on the RHWLPCI: INJECTION MODE (PLANT SPECIFIC) : and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.06 Emergency generator failure (IOCFR 55.43)

A3. Ability to monitor automatic operations of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including:

A3.02 Pump trips

• SRO LEVEL OBJECTIVE A2. Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.05 Core spray line break (1 OCFR 55.43)

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

A2.09 Loss of A.C. power (1 OCFR 55.43)

Group Point Total:

Susquehanna Facsimile 3.9 3.2 3.6 4.1

System #

219000 RHWLPCI:

ToruslPool Cooling Mode Q. 92 234000 Fuel Handling Equipment Q. 93 WA Category Point Totals:

NUREG-1021, Draft Rev 9 2003 NRC Exam Rev. 2 0

BWR Examination Outline Form ES-401-1 Plant Svstems

- Tier 2IGroup 2(SRO)

SRO 5 of 6 WA Topic(s) 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

(IOCFR 55.43)

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

A3.02 tlnterlock operation Group Point Total:

l 2 Susquehanna Facsimile

ES 401 Generic Knowledge and Abilities Outline Tier 3 Form ES-401-3 Facility SUSQUEHANNA Date of Exam 8/11 -8/15 2003 Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Proced u res/P I a n Tier 3 Point Total WA#

2.1.20 Q. 94 2.1.I 1

Q. 95 Subtotal 2.4.30 Q. 99 2.4.49 Q. 700 NUREG-1021, Drafl Rev9 2003 NRC Exam Rev. 2 SRO 6 of 6 Susquehanna Facsimile

ES-401 Record of Rejected WAS Form ES-40 1 -4 Randomly Selected WA Reason for Rejection Tier I Group N/A N/A As per letter PLA005439 PLA14-13 from Jeff Helsel (PPL) to Alan Blamey (NRC) dated Feb. 4'h 2002 all WAS that are not applicable to SSES design were suppressed. Use of these previously approved suppressions was discussed with John Caruso (NRC) prior to development of the outline. A copy of the letter and the specific WAS involved is available upon request.

No longer applicable-Only applies to initial fuel loading I

/ I 2/1 295023 AK3.04 209001 K3.05 RO WA value is less than 2.5 2/1 259002 K2.01 RO WA value is less than 2.5 Cannot write a discriminatory question on this WA. The only available control room indication is a single common trouble alarm.

Low discriminatory value 2/1 262002 A4.01 3

2.1.29 3

2. I

.22 Low discriminatory value RO WA value is less than 2.5 RO WA value is less than 2.5 3

2.1.34 3

2.1.26 3

2.1.13 RO WA value is less than 2.5 3

2.2.29 RO WA value is less than 2.5 3

2.2.16 RO K/A value is less than 2.5 RO WA value is less than 2.5 3

3 2.2.6 2.3.3 RO WA value is less than 2.5 RO WA value is less than 2.5 2.3.7 3

3 2.4.28 RO WA value is less than 2.5 RO K/A value is less than 2.5 RO WA value is less than 2.5 3

2.4.36 3

2.4.33 I

/ I SRO No design differences 295026 2.2.3 295002 AA2.03 1 /2 SRO WA value is less than 2.5 1 / I 1 / I 295023 AA1.02 295024 EKI. O l SRO tie to 10CFR 55.43 does not exist SRO tie to 10CFR 55.43 does not exist 1 / I 1 /2 295028 EKI.01 29501 5 AK2.07 SRO tie to IOCFR 55.43 does not exist SRO tie to 10CFR 55.43 does not exist 2/ 1 264000 K6.09 SRO tie to 10CFR 55.43 does not exist NUREG-1021. Draft Rev 9 2003 NRC Exam Rev. 2 Susquehanna Facsimile 1 of2

ES-40 1 295006 AA1.06 1 / I 29501 8 2.4.4 NUREG-1021, Draft Rev9 2003 NRC Exam Rev. 2 Record of Rejected WAS Form ES-401-4

~

RO Q.5 WA replaced - Validation finding too many CRD questions 11 RO Q.7 K/A replaced-necessary to raise question to HCL status 11 RO Q.17 WA replaced - Validation finding too many CRD questions RO (2.36 WA replaced - Validation finding too many CRD questions RO Q.45 K/A replaced -too similar to Q 21 WA RO Q.74 K/A replaced-difficulty constructing discriminatory question for this WA RO Q.5 K/A replaced - low discriminatory value RO (2.24 WA replaced - low discriminatory value RO Q.49 WA replaced - low discriminatory value 2of2 Susquehanna Facsimile