ML032650858

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Draft - Outlines
ML032650858
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/13/2003
From: Reid J
Public Service Enterprise Group
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-354/03-302, ES-401, ES-401-1 50-354/03-302, NUREG-1021, Rev 8
Download: ML032650858 (30)
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Text

ES-401 BWR SRO Examination Outline FORM ES-401-1 I Cat1 I cat2 I cat3 I cat4 I

3. Generic Knowledge and Abilities I 4 I 4 I 3 1 6 I 17 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (Le., the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate b y 3 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three WA topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the categoryhier.
6. *The generic WAS in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified based on plant-specific priorities. Enter the tier totals for each category in the table above.

Page 13 of 46 NUREG-I 021, Revision 8, Supplement 1

ES-401 BWR SRO Exam,,A i o n Outline ES-401-1 Emergency and Abnormal Evolutions - Tier l/Group 1 System# Name K1 K2 K3 A I A2 G KATopic(s) Imp. Pts. I I

1 1

295003 Partial or Complete Loss of A.C. Power X AKI .05 Failsafe component design 2.7 1

~ 295003 Partial or Complete Loss of A.C. Power X AK2.04 A.C. electrical loads 3.5 1 1 295006 SCRAM X AK2.05 CRD mechanism 3.3 1 I 295007 High Reactor Pressure X AK3.05 Low pressure system isolation 3.2 1 1 295007 I

High Reactor Pressure X AK2.02 Reactor power 3.8 1 I 295009 Low Reactor Water Level X

~~ ~

AA2.01 Reactor water level 4.2 1 295010 High Drywell Pressure 295013 High Suppression Pool Temperature 295014 'Inadvertent Reactivity Addition

-~

295015 Incomplete SCRAM 295016 Control Room Abandonment X AK2.03 Control room HVAC 3.1 1 i

~ ~-

295016 Control Room Abandonment X AK3.01 Reactor SCRAM 4.2 1 I 1

~ ~ ~~ ~~

295017 High Off-Site Release Rate X !2.1.32 Ability to explain and apply system l i m k and precautions. 3.8 1

~ ~~

295023 Refueling Accidents X 2.4.49 Ability to perform without reference to procedures those actions that require 4.0 1 immediate operation of system components and controls.

~ -~

295023 Refueling Accidents X AKI .03 Inadvertent criticality 4.0 1 295024 High Drywell Pressure X EA2.04 Suppressionchamber pressure: Plant-Specific 3.9 1 295024 High Drywell Pressure X EA2.01 Drywell pressure 4.4 I

~ ~~ ~

295025 High Reactor Pressure X EA1.03 Safetykelief valves: Plant-Specific 4.4 I 295026 Suppression Pool High Water Temperature X ,EK3.04 SBLC injection 4.1 1 Saturday, May 10, 2003 12:59:37 PM Page 1

ES-401 i BWR SRO Exa ill ,ation Outline Emergency and Abnormal Evolutions - Tier l/Group 1

( ES-401-1

'System# 'Name K1 K2 K3 A I A2 G KA Topic(s) Imp. Pts. 1 295026 Suppression Pool High Water Temperature X EKI .02 Steam condensation 3.8 1 295027 IHigh Containment Temperature (Mark Ill Containment Only) 295030 Low Suppression Pool Water Level X EA1.06 Condensate storage and transfer (make-up to the suppression pool) Plant-Specific 3.4 1 295030 Low Suppression Pool Water Level X 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations 3.7 1 and safety limits.

295031 Reactor Low Water Level X EA2.02 Reactor power 4.2 1 295031 Reactor Low Water Level X EA1.01 Low pressure coolant injection (RHR): Plant-Specific 4.4 1

~~

295037 C R A M Condition Present and Reactor X 2.4.6 Knowledge symptom based EOP mitigation strategies. 4.0 1

'Power Above APRM Downscale or Unknown

~~~ ~ ~

295037 SCRAM Condition Present andReactor X EA2.03 SBLCtank level 4.4 1

'Power Above APRM Downscale or Unknown

_ _ ~~ ~

- ~ - ~

295038 High Off-Site Release Rate X EK3.01 Implementationof site emergency plan 4.5 1 1

~~ I I ~~ -~

295038 High Off-Site Release Rate X EA1.02 Meteorological instrumentation 3.8 1 500000 High Containment Hydrogen Concentration X EKI .01 Containment integrity 3.9 1 I

Saturday, May I O , 2003 12:59:38 PM Page 2

ES-401

( (

BWR SRO Exam,,,ation Outline ( ES-401-1 Emergency and Abnormal Evolutions - Tier l/Group 2 System# Name K1 K2 K3 A I A2 G KATopic(s) Imp. Pts. 1 295001 Partial or Complete Loss of Forced Core Flow X AK2.06 Reactor power 3.8 1 Circulation 295002 Loss of Main Condenser Vacuum X f i 2 . 0 2 Reactor power: Plant-Specific 3.3 1 295004 Partial or Complete Loss of D.C. Power 295005 Main Turbine Generator Trip X AA1.03 Reactor manual controllrod control and information system 2.8 1 295005 Main Turbine Generator Trip X 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations 3.7 1 and safety limits.

295008 High Reactor Water Level X AKI .03 Feed flowkteam flow mismatch 3.2 1

~~ --

295011 High Containment Temperature (Mark I l l Containment Only) 295012 High Drywell Temperature X 2.4.6 Fnowledge symptom based EOP mitigation strategies. 4.0 1 ,

~ - -_____~

295012 High Drywell Temperature X AKI .02 Reactor power level control 3.2 1

- -- - --- - -~ --

295018 Partial or Complete Loss-of Component Cooling Water

~~~ ~~ ~

295019 Partial or Complete Lossoflnstrument Air X AK2.07 Condensate system 3.2 I

~ - - ~~~

295019 Partial or Complete Loss of Instrument Air X AA2.01 Instrument air system pressure 3.6 1

~ ~~ ~~ ~-

295020 Inadvertent Containment Isolation X AK2.03 Drywelkontainment ventilationkooling: Plant- Specific 3.3 1

~

295020 Inadvertent Containment Lolation X AKI .02 Powerheactivitycontrol 3.8 1

~ - - - ~ ~-~

295021 Loss of Shutdown Cooling X AK3.02 Feeding and bleeding reactor vessel 3.4 1 295022 Loss of CRD Pumps X AK3.02 CRDM high temperature 3.1 1 295028 High Drywell Temperature 295029 High Suppression Pool Water Level X EA203 DryweWcontainment water level 3.5 1 295032 High Secondary Containment Area Temperature Saturday, May 10, 2003 12:59:38 PM Page 3

( ES-401-1 ES-401 Emergency and Abnormal Evolutions - Tier 1IGroup 2 K1 K2 K3 A I A2 G KATopic(s) Imp. Pts.

1 Svstem# Name ~

295033 High Secondary Containment Area Radiation X EA1.02 Process radiation monitoring system 3.8 1 Levels 295034 Secondary Containment Ventilation High Radiation ~

295035 Secondary Containment High Differential X 2.1.32 Ability to explain and apply system limits and precautions. 3.8 1 Pressure 295036 Secondary Containment High Sump/Area X EK3.03 Isolating affected systems 3.6 1 Water Level 600000 Plant Fire On Site Saturday, May 10, 2003 12:59:39 PM Page 4

ES-401 ( BWR SRO E x a d ,on Outline ES-401-1 Plant Svstems - Tier 2IGroup 1 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s) imp. Pts.)

?01005 Rod Control and Information System (RCIS) 202002 Recirculation Flow Control System 203000 RHR/LPCI: kjection Mode (Plant Specific) X KI .IO ECCS room coolers 3.2 1 206000 High Pressure Coolant Injection System X A4.02 Flow controller: BWR-2, 3, 4 3.8 1 207000 Isolation (Emergency) Condenser 209001 Low Pressure Core Spray System X A2.06 Inadequate system flow 3.2 1

~~ ~

209002 High Pressure Core Spray System (HPCS)

I 21 1000 Standby Liquid Control System K2.02 Explosive valves 3.2 1

_ _ _ _ _ ~ ~ ~ ~ ~~ _

212000 Reactor Protection System X A4.04 Bypass SCRAM instrument volume high level SCRAM signal 3.9 1

~~

-~

215004 !Source Range Monitor (SRM) System I

~~ ~~~

I

~~~

215005 ,Average Power Range Monitor/Local A I .02 RPS status 4.0 1 Power Range Monitor System

~ ~ ~ ~ ~ _ _ _ _ _ _ _ _ ~

215005 Average Power Range Monitor/Local K6.04 Trip units 3.2 1 Power Range Monitor System ~-

216000 Nuclear Boiler Instrumentation X 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 I

. , , ~~~- -

216000 Nuclear Boiler Instrumentation X A I .04 System venting 2.8 1 217000 Reactor Core Isolation Cooling System K3.01 Reactorwater level 3.7 1 (RCIC)

~~ . . .

217000 Reactor Core Isolation Cooling System X K5.02 Flow indication 3.1 1 (RCIC)

~

276600 Automatic Depressurization System X K4.02 Allows manual initiation of ADS logic 4.0 1 223001 Primary Containment System and Auxiliaries 223002 Primary Containment Isolation X K4.08 Manual defeating of selected isolations during specified emergency 3.7 1 SystemlNuclear Steam Supply Shut-Off conditions 226001 RHR/LPCI: containment Spiay System X ' K1.08 Nuclear boiler instrumentation 3.4 1

  1. Mode Saturday, May 10, 2003 1 2 5 9 5 0 P M Page 1

ES-401 ( BWR SRO E x a d ,onOutline ES-401-1 Plant Systems - Tier 2/Group 1 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 GIKATopic(s)

.. . -~ - ---- - -. --.___ ____ __ .

Imp Pts. 1 239002 Relief/Safety Valves X 1A2.04ADS actuation 4.2 1 1 -~

241000 Reactornurbine Pressure Regulating X 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 1 System T- -

241000 Reactornurbine Pressure Regulating X lK5.04 Turbine inlet pressure vs. reactor pressure 3.3 1 System 259002 Reactor Water Level Control System X K3.07 Reactor water level indication 3.4 1

~~~ ~

259002 Reactor Water Level Control System X 2.1.33 Ability to recognize indications for system operating parameters which 4.0 1 are entry-level conditions for technical specifications.

261000 Standby Gas Treatment System 262001 A.C. Electrical Distribution 264000 Emergency Generators (Dieselfiet) X A3.04 Operation of the governor control system on frequency and voltage 3.1 1 pontrol

~ ~ ~

264000 Emergency Generators (DieseVJet) X ~K6.01Starting air 3.9 1 I

~- I I - ____~-~

290001 Secondary Containment X A3.01 Secondary containment isolation 4.0 1

___ 1-290001 Secondary Containment X K1.07 Turbine building ventilation (steam tunnel): Plant- Specific 3.1 1 Saturday, May 10, 2003 125950 PM Page 2

ES-401 ( BWR SRO ~ x a d .on Outline { ES-401-1 Plant Systems - Tier 2/Group 2 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s)

Imp. Pts.

j

__.-- ~

~

201001 Control Rod Drive Hydraulic System X K6.05 A.C. power 3.3 I 201001 Control Rod Drive Hydraulic System X K3.03 Control rod drive mechanisms 3.2 1 201002 Reactor Manual Control System X AI .OS Local reactor power 201004 Rod Sequence Control System (Plant Specific)

~ _ - ~ ~~~

201006 Rod Worth Minimizer System (RWM) X 2.1.32 Ability to explain and apply system limits and precautions.

(Plant Specific) 202001 Recirculation System X A2.03 Single recirculation pump trip

~204000Reactor Water Cleanup System X K1.03 Reactor feedwater system 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

~~ ~

214000 Rod Position Information System 215002 Rod Block Monitor System

_ _ ~~~ ~ ' .

215003 Intermediate Range Monitor (IRM) System 219000 RHRILPCI: Torus/SuppressionPool X K2.01 Valves Cooling Mode 230000 RHRILPCI.ToruslSuppression Pool Spray Mode

~

234000 Fuel Handling Equipment X 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. 3.6 1 I

239003 MSlV Leakage Control System 245000 Main Turbine Generator and Auxiliary Systems

~~~~~~ ~

259001 Reactor Feedwater System 262002 UninterruptablePower Supply (A.C./D.C.) X K I r O l Feedwater level control: Plant-Specific 3.0 1 1263000 D.C.Electrical Distribution X A I .01 Battery charging/dischargingrate 2.8 1 I Saturday, May 10, 2003 12:59:51 PM Page 3 i

/

ES-401 \ BWR SRO Exam,

(,,

,on Outline ( ES-401-1 Plant Systems - Tier 2IGroup 2 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s)

__ - - ._ ~ _ -_ .

Imp. Pts.

L 1

i 272000 Radiation Monitoring System I

~ 286000 Fire Protection System I

I

' 290003 Control Room HVAC X A3.01 Initiation/reconfiguration 3.5 I 300000 Instrument Air System (IAS) X K5.01 Air compressors 2.5 1

~ ~ ~~~ ~~ ~~~~ ~ ~

400000 Component Cooling Water System X K4.01 Automatic start of standby pump 3.9 1 (CCWS)

Saturday, May 10, 2003 12:59:51 PM Page 4

/  ;'

ES-401 (' BWR SRO Exam, .ion Outline \ ES-401-1 Plant Systems - Tier 2IGroup 3 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s) Imp. Pts. ~

201003 Control Rod and Drive Mechanism 215001 Traversing In-Core Probe

~~

233000 Fuel Pool Cooling and Clean-up X 1Al . O l Surge tank level 2.9 233000 Fuel Pool Cooling and Clean-up X ' K I.09 Component cooling water systems 2.6

~~ ~ ~

239001 Main and Reheat Steam System 256000 Reactor Condensate System X K4.06 Control of extraction steam 2.8

~ ~~

268000 Radwaste X 2.4.4 Ability to recognize abnormal indications for system operating parameters 4.3 which are entry-level conditions for emergency and abnormal operating procedures. ~ ~~ ~

288000 Plant Ventilation Systems 2 9 6 0 2 Reactor Vessel lnternak Saturday, May I O , 2003 12:59:52 PM Page 5

ES-401 BWR RO Examination Outline FORM ES-401-2 Abnormal Plant 1 2 2 3 3 2 3 3 3 3 3 1 28 2.

Plant 2 4 2 2 2 2 0 1 2 2 2 0 19 Systems 3 1 0 1 0 0 0 1 0 0 0 1 4 Tier 7 4 6 l 5 4 l 3 5 l 5 5 l 5 2 51 Totals Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge and Abilities 3 4 2 4 13 Note: 1, Ensure that at least two topics from every WA category are sampled within each tier (i.e.,the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate b y 3 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three WA topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the categoryhier.
6. *The generic 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.
7. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified based on plant-specific priorities. Enter the tier totals for each category in the table above.

Page 26 of 46 NUREG-I 021, Revision 8, Supplement 1

i ES-40 1 BWR RO Examination Outline ES-401-2 Emergency and Abnormal Evolutions - Tier l/Group 1 System # Name K1 K2 K3 A l l A 2 GlKATopic(s) Imp. Pts.1 295005 Main Turbine Generator Trip X AA1.03 Reactor manual controllrod control and information system 2.7 1 295006 SCRAM X AK2.05 CRD mechanism 3.1 1 295007 High Reactor Pressure X AK3.05 Low pressure system isolation 3.0 1

~~

295007 High Reactor Pressure X AK2.02 Reactor power 3.8 I 295009 Low Reactor Water Level X AK3.01 Recirculation pump run back: Plant-Specific 3.2 1 295010 High Drywell Pressure

~~ ~ _ _ ~ ~ _______ ~~

295014 Inadvertent Reactivity Addition X AK2.01 RPS 3.9 1

~~ ~~~

295015 Incomplete SCRAM X 'AKl.01 Shutdown margin 3.6 1 I

-~ -~~ ~ ~ ~ ~~~~

295024 High Drywell Pressure X '2.1.27 Knowledge of system purpose and or function. 2.8 1

~~

295024 High Drywell Pressure X EA2.01 Drywell pressure 4.2 1

~~~

295025 High Reactor Pressure X EA1.03 Safetylrelief valves: Plant-Specific 4.4 1

-~

295031 Reactor Low Water Level X EAI .OI LOW pressure-coolant injection (RHR): Plant-Specific 4.4 1

-~

295037 SCRAM Condition Present and Reactor Power X 'EA2.03 SBLC tank level 4.3 1 Above APRM Downscale or Unknown

~ ~~

500000 High Containment Hydrogen Concentration X EKI . O l Containment integrity 3.3 1 Saturday, May 10, 2003 12:51:29 PM Page 1

ES-401 BWR RO Examination Outline ES-401-2 Emergency and Abnormal Evolutions - Tier IlGroup 2 System # Name K1 K2 K3 A I A2 G KA Topic(s) Imp. Pts. 1 I

295001 Partial or Complete Loss of Forced Core Flow X AK2.06 Reactor power 3.8 1 Circulation 295002 Loss of Main Condenser Vacuum 295003 Partial or Complete Loss of A.C. Power X AK2.04 A.C. electrical loads 3.4 1 295003 Partial or Complete Loss of A.C. Power ' X AKI .05 Failsafe component design 2.6 1

~ ~~ ~~

295004 Partial or Complete Loss of D.C. Power

~ ~ ~~

295008 High Reactor Water Level X AKI .03 Feed flowlsteam flow mismatch 3.2 1 295011 High Containment Temperature (Mark Ill Containment Only)

~~~_______

295012 High Drywell Temperature X AKI .02 Reactor power level control 3.1 1

~

~ ~~~

295013 High Suppression Pool Temperature X AA1.02 Systems that add heat to the suppression pool 3.9 1

~~ ~~~~ ~~~~~ ~~ -~ ~ ~~~ ~ ~ ~~~~

295016 Control Room Abandonment X AK3.01 Reactor SCRAM 4.1 1

~ ~~~ ~ ~~~~~

295016 Control Room Abandonment X AK2.03 Control room HVAC 2.9 1 295017 High Off-Site Release Rate X 2.1.32 Ability to explain and apply system limits and precautions. 3.4 295018 Partial or Complete Loss of Component Cooling Water Partial or Complete Loss 2 Instrument Air

~~~~ ~ ~~~ ~~~

%%%9I X AK2.07 Condensate system 3.2 295020 Inadvertent Containment Isolation X AK2.03 Drywelllcontainment ventilationlcooling: Plant- Specific 3.1

~~~ ~ ~ ~~

295020 Inadvertent Containment Isolation X AKI .O2 Power/reactivity control 3.5

~ ~~~

295022 Loss of CRD Pumps X AK3.02 CRDM high temperature 2.9 295026 Suppression Pool High Water Temperature X EKI .02 Steam condensation 3.5 295026 Suppression Pool High Water Temperature X ' EK3.04 SBLC injection 3.7 Saturday, May I O , 2003 12:51:30 P M Page 2

i ES-401 BWR RO Examination Outline ES-401-2 Emergency and Abnormal Evolutions - Tier l/Group 2 System # IName K1 K2 K31A1 A2 G IKA Topic(s) Imp. Pts. j 295027 High Containment Temperature (Mark Ill Containment Only) 295028 High Drywell Temperature 295029 High Suppression Pool Water Level 295030 Low Suppression Pool Water Level X EA1.06 Condensate storage and transfer (make-up to the suppression pool): Plant- 3.4 1 Specific

~ ~~-~

295033 High Secondary Containment Area Radiation X EA1.02 Process radiation monitoring system 3.7 I Levels

. ~- ~

295034 Secondary Containment Ventilation High IRadiation

-___- - ~-

295038 High Off-Site Release Rate X EA1.02 Meteorological instrumentation

,, I

~ ~ _ _

295038 High Off-Site Release Rate X I IEK3.01 Implementation of site emergency plan i '

-~_-

600000 IPlant Fire On Site ' I Saturday, May 10, 2003 12:51:30 PM Page 3

(

ES-401 BWR RO Examination Outline ES-401-2 Emergency and Abnormal Evolutions - Tier l/Group 3 1

~

System # Name K1 K2 K3 A I A2 GIKATopic(s) Imp. Pts.

295021 Loss of Shutdown Cooling X AK3.02 Feeding and bleeding reactor vessel 3.3 1 295023 Refueling Accidents X AKI .03 Inadvertent criticality 3.7 1

~~

295032 High Secondary Containment Area X EAI .OI Area temperature monitoring system 3.6 1 Temperature 295035 Secondary Containment High Differential Pressure

~~~ ~~

~~ ~~~ ~

Secondary Containment High Sump/Area X EK3.03 Isolating affected systems 3.5 1 Water Level

~

Saturday, May 10, 2003 12:51:31 PM Page 4

ES-401 BWR RO Exatnil Jn Outline ES-401-2 Plant Systems - Tier 2/Group 1 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s) Imp. Pts. I

___ - _____ - __ - -. -- I 201001 Control Rod Drive Hydraulic System X K3.03 Control rod drive mechanisms 3.1 1 201001 'Control Rod Drive Hydraulic System X K6.05 A.C. power 3.3 1 201002 IReactor Manual Control System A I .05 Local reactor power 3.4 1 201005 Rod Control and Information System (RCIS) 202002 'Recirculation Flow Control System I

203000 RHR/LPCI: Injection Mode (Plant Specific) X K1.I 0 ECCS room coolers 3.2 1

~ - ~~~

206000 High Pressure Coolant Injection System X 2.1.23 Ability to perform specific system and integrated plant procedures during 3.9 1 different modes of plant operation.

~ ~ ~~~~~

I 207000 Isolation (Emergency) Condenser-I I

~~ ~

I ~~~~

i 209001 ILow Pressure Core Spray System X 1K2.01Pump power 3.0 1 I

_________ I I I '

209001 'LOW Pressure Core Spray System X A2.06 Inadequate systemflow 3.2 1

___________~-

~

~ - ~ - ~ ~ _ _ _ _ _ - ~

209002 High Pressure Core Spray System (HPCS) I

~- ~~

21 1000 ,Standby Liquid Control System X K2.02 Explosive valves 3.1 1 I

21 1000 Standby Liquid Control System X K4.02 Component and system testing 3.0 1 I

- ~ ~~ ~ ~~ ~~

212000 IReactor Protection System X A3.07 SCRAM air header pressure 3.6 1 212000 Reactor Protection System X A4.04 Bypass SCRAM instrument volume high level SCRAM signal 3.9 1

~~~~~

21 5003 hermediate Range Monitor (IRM) System X A4.03 IRM range switches 3.6 1

~-

21 5003 Intermediate Range Monitor (1RM)System X K1.02 Reactor manual control 3.6 1 215004 Source Range Monitor (SRM) System 215005 Average Power Range Monitor/Local X K6.04 Trip units 3.1 1 Power Range Monitor System 21 5005 lAverage Power Range Monitor/Local X A I .02 RPS status 3.9 1 Power Range Monitor System Iturday, May IO, 2003 12:51:40 PM Page 1

ES-401 ( BWR RO Exam( ,n Outline ( ES-401-2 Plant Systems - Tier 2IGroup 1 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s) Imp. Pts.1

. - - - _ _ _ . ~ ~. ~- .._ _ -~ - - .

216000 Nuclear Boiler Instrumentation X A I .04 System venting 2.6 1 217000 Reactor Core Isolation Cooling System X K5.02 Flow indication 3.1 I (RCIC)

~-

217000 Reactor Core Isolation Cooling System X K3.01 Reactor water level 3.7 1 (RCIC) 218000 Automatic Depressurization System X A4.02 ADS logic initiation 4.2 1 218000 .Automatic Depressurization System X K4.02 Allows manual initiation of ADS logic 3.8 1 223001 Primary Containment System and Auxiliaries 223002 Primary Containment Isolation X K4.08 Manual defeating of selected isolations during specified emergency 3.3 1 System/Nuclear Steam Supply Shut-Off conditions

- - ~~ - ~~ ________

239002 RelieWSafety Valves X A2.01 Stuck open vacuum breakers 3.0 1 I

1 1 239002 RelieWSafety Valves I x I ' A2.04 ADS actuation

- 4.1 1 I

241000 Reactornurbine Pressure Regulating X K5.04 Turbine inlet pressure vs. reactor pressure 3.3 1 ISystem I

~ ~~~ - 1 .

259001 Reactor Feedwater System 'X A3.07 FWRV position 3.2 1

_ _ ~ _ ~ _ ____~

259002 Reactor Water Level Control System X K3.07 Reactor water level indication 3.4 1 261000 Standby Gas Treatment System

. ~~ ~~

264000 Emergency Generators(Diesel/Jet) X A3.04 Operation of the governor control system on frequency and voltage 3.1 1 control

~~ ~~ -

264000 Emergency Generators (DieseVJet) X K6.01 Starting air 3.8 1

~~ ~ ~ ~-

Saturday, May 10, 2003 12:51:40 PM Page 2

i ES-401 BWR RO Examik. Jn Outline ( ES-401-2 Plant Systems - Tier 2/Group 2 I'

System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s) Imp. Pts.

201003 Control Rod a n d E v e Mechanism 201004 Rod Sequence Control System (Plant Specific) 201006 Rod Worth Minimizer System (RWM)

(Plant Specific) 202001 Recirculation System X A2.03 Single recirculation pump trip 3.6 1

~-~ ~

204000 Reactor Water Cleanup System X K1.03 Reactor feedwater system 3.1 1 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

~

214000 Rod Position Information System 215002 Rod Block Monitor System K2.03 APRM channels: BWR-3, 4, 5 2.8 1

~- I 219000 RHRILPCI: Torus/Suppression Pool ' X lK2.01 Valves 2.5 1 Cooling Mode

~~

219000 RHRILPCI: Torus/Suppression Pool X ~A4.04Minimum flow valves 3.0 1 Cooling Mode I I - ~~~~

226001 RHR/LPCI: Containment Spray System ~

X iA4.04 Keep fill system 2.8 1 Mode 226001RHRILPCI:

~

Containment Spray System x K1.08 Nuclear boiler instrumentation 3.2 1 Mode 230000 RHRILPCI: Torus/Suppression Pool Spray Mode

~~~~~-

1 239001 Main and Reheat Steam System

~ ~-

245000 Main Turbine Generator and Auxiliary X K5.03 Hydraulically operated valve operation 2.6 1 Systems

~-

256000 Reactor Condensate System X K4.06 Control of extraction steam 2.8 1

~ ~- - ~ - - - ~

256000 Reactor Condensate System X lA2.06 Low hotwell level 3.2 1 262001 A.C. Electrical Distribution 262002 Uninterruptable Power Supply (A.C./D.C.) X K1.O Feedwater level control: Plant-Specific 2.8 1 263000 D.C. Eiectrical Distribution X A I .O Battery charging/discharging rate 2.5 1 Saturday, May IO,2003 12:51:41 PM Page 3

i ES-40 1 BWR RO Examih Jn Outline i ES-401-2 Plant Systems - Tier 2IGroup 2 1

/271000----

System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s)

__ - ~ ...

Imp. Pts.

272000 Radiation Monitoring System x K3.01 Station liquid effluent release monitoring 3.2 1 286000 Fire Protection System 290001 Secondary Containment A3.01 Secondary containment isolation 3.9 1 290001 Secondary Containment K1.07 Turbine building ventilation (steam tunnel): Plant- Specific 290003 Control Room HVAC A3.01 Initiation/reconfiguration 3.3 1 300000 Instrument Air System (IAS) K5.01 Air compressors 2.5 1 400000 Component Cooling Water System K4.01 Automatic start of standby pump 3.4 1 (CCWS)

~ , ~ ~ ~ _ _

400000 Component Cooling Water System K3.01 Loads cooled by CCWS

'(CCWS)

_ ~ _ _ ~ ~ _ _ ~

Saturday, May 10, 2003 12:51:41 PM Page 4

ES-401 ( BWR RO Examir,. Jn Outline i ES-401-2 Plant Systems - Tier 2IGroup 3 System Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KATopic(s) Imp. P t d 215001 Traversing In-Core Probe 233000 Fuel Pool Cooling and Clean-up X rA1.O1 Surge tank level 2.6 1 233000 Fuel Pool Cooling and Clean-up X IK1.09 Component cooling water systems 2.6 1 234000 Fuel Handling Equipment 239003 MSlV Leakage Control System 268000 Radwaste 288000 Plant Ventilation Systems X ,2.4.50 Ability to verify system alarm setpoints and operate controls identified in 3.3 1 the alarm response manual. ~~ ~

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290002 Reactor Vessel lnternals X K3.03 Reactor power 3.3 1

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Saturday, May I O , 2003 12:51:42 PM Page 5

ES-401 Generic Knowledge and Abilities Outline (Tier 3) ES-401-5 Facility: Hope Creek Date of Exam 06/17/2003 Exam Level: RO Category ~~ ~

K A #-- ._

Topic Imp. ___oints Conduct of Operations 2.1.28 Knowledge of the purpose and function of major system components 3.2 1 and controls.

2.1. I 1 Knowledge of less than one hour technical specification action 1 3.0 1 statements for systems.

2.1.8 Ability to coordinate personnel activities outside the control room. 3.8 1 Total 3 Equipment Control 2.2.35 Knowledge of control rod programming. 2.5 . 1

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2.2.27 Knowledge of the refueling process. 2.6 1 2.2.26 iKnowledge of refueling administrative requirements. 2.5 1 2.2.22 Knowledge of limiting conditions for operations and safety limits. 3.4i I I

'Total 4

- - - _ - - -~

Radiological Controls 2.3.1 1 IAbility to control radiation releases. 2.7 I 2.3.4 iKnowledge of radiation exposure limits and contamination control, 2.51 1 iincluding permissible levels in excess of those authorized.

Total 2l Emergency Procedures and 2.4.48 iAbility to interpret control room indications to verify the status and 3.51 1 Plan loperation how r action s and 2.4.47 Ability to nds in an accurate and timely 3.4 1 manner utilizing the appropriate control room reference material.

2.4.1 7 Knowledge of EOP terms and definitions. 3.1 1 2.4.4 Ability to recognize abnormal indications for system operating 4.0 1 parameters which are entry-level conditions for emergency and Total 4 Tier 3 Target Point Total (RO/SRO) 13

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L' Saturday, May I O , 2003 12:52:11 PM

ES-40I Generic Knowledge and Abilities Outline (Tier 3) ES-401-5 Facility: Hope Creek Date o f E G m 06/17/2003 Exam Level: SRO Category KA# Topic . -

Imp. oints Conduct of Operations 2.1 .I 1 Knowledge of less than one hour technical specification action 38 1 L-, statements for systems.

2.1 .I 2 Ability to apply technical specifications for a system. 4.0 1 2.1.34 Ability to maintain primary and secondary plant chemistry within 2.9 1 allowable limits.

218 Ability to coordinate personnel activities outside the control room. 3.6 1 Total 4 Equipment Control 2.2.27 IKnowledge of the refueling process. 3.5 1 2.2.7 Knowledge of the process for conducting tests or experiments not 3.2 1

'described in the safety analysis report.

12.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 1 Radiological Controls k3.10 Ability to perform procedures to reduce excessive levels of radiation and 3.3 1 guard against personnel exposure.

2 3 . 11 Ability to control radiation releases. 3.2 1 2.3.4 Knowledge of radiation exposure limits and contamination control, 3.1 1 including permissible levels in excess of those authorized. __ -

Total '3 Emergency Procedures and 2.4.48 Ability to interpret control room indications to verify the status and 3.8 1 Plan operation of system, and understand how operator action s and

\-- 2.4.4 Ability to recognize abnormal indications for system operating 4.3 1 parameters which are entry-level conditions for emergency and 2.4.1 7 Knowledge of EOP terms and definitions. 3.8 1 2.4.30 Knowledge of which events related to system operations/status should 3.6 1 be reported to outside agencies.

2.4.44 Knowledge of emergency plan protective action recommendations. 4.0 1 2.4.47 Ability to diagnose and recognize trends in an accurate and timely 3.7 1 manner utilizing the appropriate control room reference material.

Total 6 Tier 3 Target Point Total (ROISRO) 17

- Saturday, May I O , 2003 12:59:57 PM

NC.TQ-WB.ZZ-O027(2)

ES-301 Administrative Toeics 0utIine FORM ES-301-1 Facility: Hope Creek Generating Station Date of Examination: 6/16/03 Examination Level: [XI RO 0 SRO Operating Test Number:

~

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions ..

A. 1 Conduct of 2.1.12 Ability to apply technical specifications to a system. (2.9)

Operations JPM- Gather information and determines if conditions are Plant Parameter satisfactory for a Recirculation Pump restart. (New)

Verification (Simulator Perform) 2.1.31 Ability to locate control room switches/controIs and indications and to determine that they are correctly reflecting the desired plant lineup. (4.2)

System Lineup JPM - RHR System Piping and Flow Path Verification (Simulator Perform) (07/02 NRC Exam)

A.2 Equipment Control 2.2.12 Knowledge of surveillance procedures. (3.0)

Su rveiIlance JPM- Perform alternate determination of Drywell Air Procedures Temperature. (Simulator Perform) (03/02 NRC)

A.3 Radiation Control 2.3.9 Knowledge of the process for performing a containment purge. (2.5)

JPM - Complete containment purge paperwork. (Bank)

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A.4 Emergency Plan 2.4.39 Knowledge of the ROs responsibilities in emergency plan Emergency implementation. (3.3)

Communications JPM- Complete the Operational Status Board-Hope Creek (Simulator Perform) (03/02 NRC Modified)

Page 29 of 104 Rev. 2

NC.TQ-WS.ZZ-O027(2)

ES-301 Administrative ToPics Outline FORM ES-301-1 Facility: Hope Creek Generating Station Date of Examination: 6/16/03 Examination Level: 0 RO SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject I.ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. 1 Conduct of 2.1.25 Ability to obtain and interpret station reference materials Operations such as graphs/monographs/and tables which contain data.

(2.8)

Plant Parameter Question-Given plant conditions, what is the highest recommended Verification OOKlO7 discharge pressure that gives reasonable assurance of avoiding surge. (New) 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data.

(2.8)

Question- Given plant conditions, determine the Reactor Temperature at which a HPCl high RPV Level 8 Trip occurs during a Reactor cooldown. (New) 2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities. (3.4)

Shift Manning JPM- Determine if minimum shift manning requirements are met.

(3103 LSRO)

A.2 Equipment Control 2.2.1 2 Knowledge of surveillance procedures. (3.4)

Surveillance JPM- Perform a review of a completed surveillance. (Modified)

Procedures A.3 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. (3.0)

Question- Given an emergency condition, determine allowable stay times. (Bank) 2.3.1 Knowledge of 10CFR20 and related facility radiation control requirements. (3.0)

Question- Apply the NBU radiation exposure limits for a Declared Pregnant Worker with existing exposure. (Bank)

A.4 Emergency Plan 2.4.38 Ability to take actions called for in the facility emergency Emergency Action plan/including (if required) supporting or acting as Levels and emergency coordinator. (4.0)

Classifications JPM - Given a set of conditions, classify an event. (Bank)

Page 29 of 104 Rev. 2

NC.TQ-WB.Z2-0027(Z)

ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2 Facility: Hope Creek Generating Station Date of Examination: 6/16/03 Examinations Developed by: [XI Facility 0 NRC Examination Level: [XI RO [XI SRO(I) c]SRO(U) Operating Test Number:

B.l Control Room Systems I I System / JPM Title Type Code* Safety Function

a. Conduct Reactor Recirculation Two Loop Operation /

(D)l (A), (SI .I Respond to a Positive Reactivity Addition (Abnormal)

b. Perform The Weekly RPS Manual SCRAM Test /

(N), (A), (SI 7 Multiple Control Rods Scram During Testing (Abnormal)

c. Place the First RFPT In-Service l 2
d. Equalize SACS Expansion Tank Levels
e. Shutdown the HPCl System
f. Perform Non Emergency Operation of the Diesel Generators I (N), (S), (E) I 6
g. Respond To A Low Turbine Hydraulic Pressure (03/02 NRC) I ~~

(D), (A), (S) 1 '3 B.2 Facility Walk-Through

a. Place the Emergency Instrument Air Compressor In Service from the Local Control Panel
b. Bypass A Control Rod in the Reactor Manual Control System I (D>l(PI I 1
c. Defeat ARI Interlocks (Emergency)
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA, (E)SF Page 30 of 104 Rev. 2

NC.TQ-WB.ZZ-0027(2)

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Generating Station Scenario Number: -1 Operating Test Number: -

Examinees: Evaluators:

Initial 81% Power. A Reactor startup is in progress. (Bank)

Conditions:

Turnover: Continue with Reactor startup.

Event Malf. Event Event Description Number Number TY Pe" 1 Alternate Reactor Auxiliary Cooling Pumps 2 Reactor building isolation ED021 3 Loss of station power transformer T-4 and 1OAI 10 ED03 RR26/

4 C(ALL) Recirculation pump high vibrations and subsequent trip RR13 RR31/

5 M(ALL) LOCA with Loss of Feedwater FWOI 6 HPOI HPCl auto start failure

  • (N)ormal, (R)eactivity, ( nstrument , (C)omponent, (M)ajor Page 32 of 104 Rev. 2

NC.TQ-WB.ZZ-O027(Z)

Appendix D Scenario Outline Form ES-D-I L-Facility: Hope Creek Generating Station Scenario Number: - 2 Operating Test Number: -

Examinees: Evaluators:

Initial Reactor startup in progress at approximately 17% power. (New)

Conditions:

Turnover: Withdraw Control Rods. lnerting the Containment. Continue startup.

Event Malf. Event Event Description Number Number Type*

1 Raise Reactor Power with Control Rods

,._J 2 CD03 Stuck Control Rod lnerting the Containment (Similar to audit. Audit-pressure 3

control.)

4 ED09A2 Loss of 1AD482 inverter 5 MS04 C(ALL) Steam leak in the steam tunnel RR31/

M(ALL) Small break LOCNRHR pump room flooding(Fai1ure to isolate)

RH07

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ADO1 Emergency Depressurization/SRV Failure to open

  • (N)ormal, (R)eac vity, (I)nstrument, (C)omponent, (M)ajor Page 32 of 104 Rev. 2

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Generating Station Scenario Number: - 3 Operating Test Number: -

Examinees: EvaIuato rs:

Initial 95% Reactor power. Shutdown in progress. (Bank)

Conditions:

Turnover: Continue with Reactor shutdown.

Event Malf. Event Event Description Number Number Type 1 Lower Reactor Power with Recirculation Flow 2 FW04 Secondary Condensate Pump Trip/Failure of Recirculation Pump to Runback 3 CUOl RWCU Pump Trip ED0116/ Loss of Station Power Transformer, and then a loss of offsite 4 M(ALL)

EG12 power DG02/

5 Failure of B EDG, and failure of A EDG breaker to auto close DG08 HP09/

6 HPCl steam leak with failure to automatically isolate HPIO 7 RCO1 RClC turbine overspeed

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  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor G

Page 32 of 104 Rev. 2

NC.TQ-WBmZZ-0027(Z)

Appendix D Scenario Outline Form ES-D-1 c

Facility: Hope Creek Generating Station Scenario Number: - 4 Operating Test Number:. -

Examinees:

4- I Evaluators:

I I Initial Plant startup is in progress. Reactor power is approximately 45%. (Bank Modified)

Conditions:

Turnover: Continue with startup.

Event Malf. Event Event Description Number Number Type*

1 Raise power with Control Rods

'L NM21/

2 APRM failure upscale with single rod scram CD06 EGO41 Failure of Main Turbine to runback following loss of Stator Water 3

TC06 Cooling RP061 4 M(ALL) Full-core ATWS (Modified from Half-Core ATWS)

RP07 TCOI -

5 C(ALL) Turbine Bypass Valve failure 10 SLOII 6 SLC Failure to Automatically Initiate I SLC Pump A trip SL04

  • (N)ormal, (R)eactivity, I nstrument, (C)omponent, (M)ajor Page 32 of 104 Rev. 2

NC.TQ-WB.ZZ-O027(Z)

Appendix D Scenario Outline Form ES-D-1 c

ixaminees: EvaIuators:

nitial 100% power.

Zonditions:

urnover
Transfer B RPS to the Alternate Power Supply in preparation for RPS MG outage.

Event Malf. Event Event Description

\lumber Number Type*

1 N(ALL) Transfer B RPS to the Alternate Power Supply b

2 MC13 Condenser Level Transmitter failure CU03/

3 RWCU leak, failure to automatically isolate CUI 1 4 AD02 SRV stuck open, and then closes (Similar to Audit, but modified)

PC07/

5 Seismic Event, Loss of Chilled Water to the Drywell cwia RR31A21 6 M(ALL) Large Break LOCAIDowncomer Failure PC04

  • (N)ormal, (R)ea tivity, (I)nstrument, (C)omponent, (M)ajor Page 32 of 104 Rev. 2
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