ML032340717

Outline Submittal for the Dresden Initial Exam - June 2002

ML032340717
Person / Time
Site:	Dresden
Issue date:	06/03/2002
From:	Otten M Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
50-237/02-301, 50-249/02-301, ES-401-2
Download: ML032340717 (12)

Text

ES-401 BWR RO Examination Outline Printed: 01/04/2002 Facility: Dresden Form ES-401-2 Exam Date: 05/27/2002 Exam Level: RO K/A Category Points Tier Group KI K2 K3 K4 K5 K6 AI A2 A3 A4 G Point Total

-4 3 3 2 1 0 13 Emergency 2 4 4 3 4 3 I 19

& _ _ _ _ _ _ _ _ _ _ ' . . _._ _,.:0:-<

a Abnormal Plant 3 0 0 1 2 01 4 Evolutions _ _ __ __ ___:__

Totals 8 7 7 8 4 2 36

__________ T ier .

1 2 3 3 3 2 2 2 3 3 3 2 28

2. 2 1 2 2 2 3 2 2 2 2 1 0 19 Plant I _ _ _ _ _ _ _ _

Systems 3 0 0 0 0 0 0 0 2 1 0 1 4 Tier Totals 3 5 5 5 5 4 4 7 6 4 3 51 Cat I Cat2 Cat3 Cat4

3. Generic Knowledge And Abilities 3 3 4 3 13 Note:

1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.

2. Actual point totals must match those specified in the table.

3. Select topics from many systems; avoid selecting more than two or three K/A 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 category tier.

ARC COPy

) Facility: .den BWR RI lamination Outline Printed: 01/

o ES - 401

< _ Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 I I I I: 1I -- - -- - Form ES-401-2 E/APE # E/APE Name / Safety F K1 l K2 I K3 IA2 I( JKA Topic Ki 11(211(3 AljA :Imp.lPo:ints 295005 Main Turbine Generator Tri x AA 1.04 - Main generator controls

_2.7 295005 Main Turbine Generator Trip / 3 X AKI1.02'- tCore thermal limit considerations I I 3.2 295014 Inadvertent Reactivity Addition / 1 I

x AK2.01 - RPS 295014 Inadvertent Reactivity AdditionR P x AK3.02 - Control rod blocks 3.7 295015 Incomplete SCRAM / I x AKI.04 - Reactor pressure: Plant-Specific 3.8 295024 High lDrywell Pressure /5 EK 1.01I - Drywell integrity: Plant-Specific I_

4.1 295025 High Reactor Pressure /3 x EK3.04 - Isolation condenser initiation: Plant-Specific 4.5*

295031 Reactor Low Water Level /2 I .I x EK2.16 - Reactor water level control 295031 Reactor Low Water Level /2 x EA2.01 - Reactor water level 4.6*

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 x EK1.02 - Reactor water level effects on reactor power 4.1

• 295037 SCRAM Condition Present and Reactor Power I Above APRM Downscale or Unknown / 1 x 1A.04 - SBLC 4.5* 11 500000 High Containment Hydrogen Concentration /5 x EK2.09 - Drywell nitrogen purge system 3.0 11 500000 High Containment Hydrogen Concentration / 5 EK3.01 - Initiation of containment atmosphere control x system 2.9 1 K/A Category Totals: 4 3 3 2 1 0 Group Point TIotal:tI 13 I

Facility: aden BWR Rr tamination Outline Printed: 01/,

ES - 401 Emergency and Abnormal Plant Evolutions

- Tier 1 / Group 2 Form ES-401->

E/APE # E/APE Name / Safety Function KI K2 1(3 Al A2 G KA Topic 2 Imp. Points 295002 Loss of Main Condenser Vacuum / 3 X AK2.04 - Reactor/turbine pressure regulating system 3.2 1 295003 Partial or Complete Loss of A.C. Power / 6 X AK2.03 - A.C. electrical distribution system 7

3.7 1 295003 Partial or Complete Loss of A.C. Power / 6 X AA 1.03 - Systems necessary to assure safe plant 4.4* 1 shutdown 295004 Partial or Complete Loss of D.C. Power / 6 X AK3.02 - Ground isolation/fault determination 2.9 295008 Hig-h Reactor Water Level / 2 XAK3.04 - Reactor feed pump trip: Plant-Specific3.

I 2950 13 High Suppression Pool Temperature /5 X AA2.01 - Suppression pool temperature3.

I 295016 Control Room Abandonment / 7AA 1.04 - A.C. electrical distribution 295017 Hi-gh Off-Site Release Rate / 9 X AK2.04 - Plant ventilation systems 3.1 1 295017 IHigh Off-Site Release Rate / 9 X AK3.03 - tImplementation of site emergency plan 3.3 295018 Partial or Complete Loss of Component Cooling Water / 8 X 2.1.14 - Knowledge of system status criteria which 2.5 require the notification of plant personnel.

I]

295019 Partial or Complete Loss of Instrument Air / 8 X AK2.17 - High pressure coolant injection:

IH 2.7 Plant-Specific 295020 .advertent Containment Isolation /5 X AA2.01 - Drywell/containment pressure 295028 ligh Drywell Temperature /5 X1.02 - Equipment environmental qualfication1 295029 H'igh Suppression Pool Water Level / 5 X A.02 - Reactor pressure35 1

() Facility: ,den BWR RC zamination Outline Printed: 01/( 12 Q ES-401 0

-0 1< .- _ .

K/A Category Totals: 4 4 3 4 3 1 Group Point Total: 19 2

Cn Facility: ,den BWRR' Namination Outline Printed: 01/ 12 (0 ES - 401 Emergency and Abnormal Plant Evolutions 1< w . - Tier 1 / Gi Ki IK2IK3IA1 IA2 IGiKATonjC I

K/A Category Totals: 0 0 1 2 0 1 Group Point Total: 4 1

L BWR RO 1Th -nination Outline Printed: 0 '002 o Facility: resden 0

ES 401 -

__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ D 1u n D F + ^

I

BWR RO F -mination Outline Printed: 0 002 L

° Facility: esden 0

-0 ES -401 Plant Systems - Tier 2 / Groun 1 Warm VQ AM -1_

y1c Sys/Ev # System / Evolution Name KL K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 215004 Source Range Monitor (SRM) System X A4.04 - SRM drive control switches 3.2 1

/7 215005 Average Power Range Monitor/Local X A3.07 - RPS status 3.8 I Power Range Monitor System / 7 215005 Average Power Range Monitor/Local X K5.06 - Assignment of LPRM's to specific 2.5* 1 Power Range Monitor System / 7 APRM channels 216000 Nuclear Boiler Instrumentation / 7 X K6.01 - A.C. electrical distribution 3.1 1 216000 Nuclear Boiler Instrumentation / 7 X K4.01 - Reading of nuclear boiler parameters 3.6 1 outside the control room 218000 Automatic Depressurization System / X K3.01 - Restoration of reactor water level after 4.4*

3 a break that does not depressurize the reactor when required 218000 Automatic Depressurization System / X K4.01 - Prevent inadvertent initiatior of ADS 3.7 3 logic 223001 Primary Containment System and X A3.02 - Vacuum breaker/relief valve operation 3.4 1 Auxiliaries / 5 223002 Primary Containment Isolation X KI.19 - Component cooling water systems 2.7 1 System/Nuclear Steam Supply Shut-Off / 5 2

BWR RO1v -mination Outline Printed: C '002 Zu Facility: r esden 0

~) ES -401 Plant Systems - Tier 2 / Group 1 Form E 1<

Sys/Ev # System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 241000 Reactor/Turbine Pressure Regulating X 2.4.4 - Ability to recognize abnormal 4.0 1 System / 3 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

259001 Reactor Feedwater System / 2 X 2.1.2 - Knowledge of operator responsibilities 3.0 1 during all modes of plant operation.

259002 Reactor Water Level Control System / X A2.01 - Loss of any number of main steam flo 3.3 I 2 inputs 259002 Reactor Water Level Control System / X A4.06 - DP/Single/three element control 3.1 1 selector switch: Plant-Specific 261000 Standby Gas Treatment System / 9 X A2.04 - High train moisture content 2.5 I 261000 Standby Gas Treatment System / 9 X A2.13 - High secondary containment 3.4 1 ventilation exhaust radiation 264000 Emergency Generators (Diesel/Jet) /6 X Al .09 - Maintaining minimum load on 3.0 1

_________________ __emergency generator (to prevent reverse power) 264000 Emergency Generators (Diesel/Jet) / 6 X A3.06 - Cooling water system operation 3.1 1 K/A Category Totals: 2 3 3 3 2 2 2 3 3 3 2 Group Point Total: 28 3

BWR RO F mination Outline Printed: 0 '002

°Facility: esden

° ES - 401 -

Plant Systems - Tier 2 / Groun 2 hV- Vm WRAM '

I- I - t fli I2,O 'ui . .l k K-Sys/Ev # System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 201006 Rod Worth Minimizer System X A3.05 - Latched group indication: 3.0 l (RWM) (Plant Specific) / 7 P-Spec(Not-BWR6) 2 0200 1 Recirculation System / I X K6.02 - Component cooling water systems 3.1 205000 Shutdown Cooling System (RHR X K4.03 - Low reactor water level: Plant-Specific 3.8 Shutdown Cooling Mode) /4 205000 Shutdown Cooling System (RHR X A4.11 - Heat exchanger cooling flow 3.2 Shutdown Cooling Mode) / 4 215002 Rod Block Monitor System / 7 X K .01I- APRM: BWR-3, 4, 5 2.9 219000 RHiRILPCI: Torus/Suppression Pool X Al.02 - System flow 3.5 Cooling Mode / 5 219000 RHRPLPCI: Torus/Suppression Pool X A2.05 - A.C. electrical failures 3.3 Cooling Mode / 5 226001 RHR/LPCI: Containment Spray X K2.02 - Pumps 2.9*

System Mode / 5 22600 1 RHR/LPCI: Containment Spray X K5.02 - Water hammer 2.6 I System Mode / 5 230000 RHIRLPCI: Torus/Suppression Pool X K6.05 - Suppression pool 3.3 l Spray Mode / 5 23:9001 Main and Reheat Steam System / 3 X K5.06 - Air operated MSIV's 2.8 I

BWR RO v' mination Outline Printed: 0 902 n Facility: uresden 0

1< ES -401 K/A Category Totals: 1 2 2 2 3 2 2 2 2 1 0 Group Point Total: 19 2

z BWR RO mination Outline Printed: 0 002

° Facility: Dresden E0 1< ES -401 Plv#nf qvcfo-. - 'r;- I / 'I Ph -t -. - Trn'j 1 I %ff P I rm ES-401-2 Sys/Ev # System / Evolution Name K1 I K2 K3 l K4 K5 K6 A1 lA2 IA3 IA4 G KA Tan~i I 1 .

I r -

F--T l __

I Al I

A2 1

A lA4 1

A 1

A .-

Tr P., Points 215001 Traversing In-Core Probe / 7 Points X A3.03 - Valve operation: Not-BWRI 2.5*

_ I I I I I 234000 Fuel Handling Equipment / 8 X A2.03 - tl.nqz r)f Piprtri-i -- _

-_ A2I.0I *l

- _ -- -r t -

11p -- 1 2.8 1 288000 Plant Ventilation Systems / 9 X A ? n I - TJ,',k I-q-11 - -

l_ -.- -x11 W.y-an pressure: Plant- -Specific 3.3 288000 Plant Ventilation Systems / 9 x 2.1.33 - Ability to recognize indications for 3.4 I system operating parameters which are entry-level conditions for technical specifications.

K/A Category Totals: 0 0 0 0 0 0 0 2 1. 0 1 Group Point Total: 4 I

z Generic Knowledge and Abilities Outline (Tier 3)

Printed: 01/04/21 0 BWR RO Examination Outline Facilitv: Dresden Form ES-401-5 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.22 Ability to determine Mode of Operation.

2.8 _

2.1.8 Ability to coordinate personnel activities outside the control room.

3.8 I 2.1.32 Ability to explain and apply system limits and precautions.

3.4 _

Category Total: 3 Equipment Control 2.2.26 Knowledge of refueling administrative requirements.

2.5 2.2.2 Ability to manipulate the console controls as required to operate the facility between 4.0 shutdown and designated power levels.

2.2.34 Knowledge of the process for determining the internal and external effects on core 2.8 I

_ _ _ __ _ reactivity.

Category Total: 3 Radiation Control 1l 2 IWnowepraep nff -;1t- AT AT)-A tms ..l -lix<Lap i o ra m y Ad 2 .5 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible 2.5 I levels in excess of those authorized.

2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.

2.6 I 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 2.9 I personnel exposure.

I _______________________

Category Total: 4 Pmeratrnev Plan r 9z A 17

- Knowledge of event based EOP mitigation strategies.

3.1 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including 3.3 I system geography and system implications.

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

3.3 1 I ______ I Category Total: 3 Generic Total: 13 I