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 Facility:

Dresden BWR RO Examination Outline Printed: 01/04/2002 Form ES-401-2 Exam Level: RO Exam Date: 05/27/2002 K/A Category Points Tier Group K I K2 K3 K4 K5 K6 A I 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 1 3 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 o ES - 401 E/APE #

E/APE Name / Safety F 295005 Main Turbine Generator Tri BWR RI lamination Outline Printed:

01/

Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 I

I I

I:

1 I K1 l K2 I K3 IA2 I(

Ki 11(211(3 AljA x

295005 295014 Main Turbine Generator Trip / 3 Inadvertent Reactivity Addition / 1 X

I I

I x

295014 295015 295024 295025 295031 295031 295037 295037 Inadvertent Reactivity Addition R P

Incomplete SCRAM / I High lDrywell Pressure /5 High Reactor Pressure /3 Reactor Low Water Level /2 Reactor Low Water Level /2 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 x

x x

x JKA Topic AA 1.04 - Main generator controls AKI1.02'- tCore thermal limit considerations AK2.01 - RPS AK3.02 - Control rod blocks AKI.04 - Reactor pressure: Plant-Specific EK 1.01I - Drywell integrity: Plant-Specific EK3.04 - Isolation condenser initiation: Plant-Specific EK2.16 - Reactor water level control EA2.01 - Reactor water level EK1.02 - Reactor water level effects on reactor power 1A.04 - SBLC EK2.09 - Drywell nitrogen purge system EK3.01 - Initiation of containment atmosphere control system

_2.7 3.2 3.7 3.8 4.1 4.5*

4.6*

4.1

• I_

I

. I Form ES-401-2

Imp.lPo:ints x

x I

x 500000 500000 High Containment Hydrogen Concentration /5 High Containment Hydrogen Concentration / 5 x

x 4.5*

11 3.0 11 2.9 1

TIotal:

13 K/A Category Totals:

4 3

3 2

1 0

Group Point tI I

Facility:

ES - 401 E/APE #

295002 295003 295003 295004 295008 2950 13 295016 295017 295017 295018 7

aden BWR Rr tamination Outline Printed:

01/,

I I]

IH H

Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401->

E/APE Name / Safety Function KI K2 1(3 Al A2 G KA Topic Imp.

Points Loss of Main Condenser Vacuum / 3 X

AK2.04 - Reactor/turbine pressure regulating system 3.2 1

Partial or Complete Loss of A.C. Power / 6 X

AK2.03 - A.C. electrical distribution system 3.7 1

Partial or Complete Loss of A.C. Power / 6 X

AA 1.03 - Systems necessary to assure safe plant 4.4*

1 shutdown Partial or Complete Loss of D.C. Power / 6 X

AK3.02 - Ground isolation/fault determination 2.9 Hig-h Reactor Water Level / 2 XAK3.04

- Reactor feed pump trip: Plant-Specific3.

I High Suppression Pool Temperature /5 X

AA2.01 - Suppression pool temperature3.

I Control Room Abandonment / 7AA 1.04 - A.C. electrical distribution Hi-gh Off-Site Release Rate / 9 X

AK2.04 - Plant ventilation systems 3.1 1

High Off-Site Release Rate / 9 X

AK3.03 - tImplementation of site emergency plan 3.3 Partial or Complete Loss of Component Cooling X 2.1.14 - Knowledge of system status criteria which 2.5 Water / 8 require the notification of plant personnel.

Partial or Complete Loss of Instrument Air / 8 X

AK2.17 - High pressure coolant injection:

2.7 Plant-Specific

.advertent Containment Isolation /5 X

AA2.01 - Drywell/containment pressure ligh Drywell Temperature /5 X1.02

- Equipment environmental qualfication1

'igh Suppression Pool Water Level / 5 X

A.02 - Reactor pressure35 1

2 295019 295020 295028 295029

() 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 1< w Emergency and Abnormal Plant Evolutions - 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 L

° Facility:

0-0 ES -401 Printed:

0 002 esden 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 Zu Facility:

0~) ES -401 Printed:

C

'002 r esden 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:

° ES -401 esden Plant Systems - Tier 2 / Groun 2 hV-Vm WRAM K-I-

I -

t fli I2,O 'ui..l 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

° Facility:

Dresden E0 1< ES -401 BWR RO mination Outline Printed:

0 002 Plv#nf qvcfo-. - 'r;- I /

'I Ph

-t -.

- Trn'j 1 I %ff I

P Sys/Ev #

System / Evolution Name K1 I K2 K3 l K4 K5 K6 A1 lA2 I A3 I A4 G rm ES-401-2 1.

KA Tan~i l

Al A2 A

lA4 A A

Tr.-

P.,

I I

r F--T I

I 1

1 1

Points 215001 Traversing In-Core Probe / 7 X

I I

I I

I A3.03 - Valve operation: Not-BWRI 2.5*

Points 234000 Fuel Handling Equipment / 8 X

A2.03 - tl.nqz r)f Piprtri-i --

A2I.0I - *l

_ -- -r 11p -

t 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 system operating parameters which are entry-level conditions for technical specifications.

3.4 I

K/A Category Totals:

0 0

0 0

0 0

0 2

1.

0 1

Group Point Total:

4 I

z 0

Generic Knowledge and Abilities Outline (Tier 3)

Printed:

01/04/21 BWR RO Examination Outline Form ES-401-5 Facilitv:

Dresden 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 2.3.4 2.3.1 2.3.10 I _______________________

Pmeratrnev Plan r

9 A 17 z

tms y Ad..l -l ix <La p i o r a m 2.5 Knowledge of radiation exposure limits and contamination control, including permissible 2.5 I

levels in excess of those authorized.

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

2.6 I

Ability to perform procedures to reduce excessive levels of radiation and guard against 2.9 I

personnel exposure.

Category Total:

4 Knowledge of event based EOP mitigation strategies.

3.1 Knowledge of local auxiliary operator tasks during emergency operations including 3.3 I

system geography and system implications.

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

3.3 1

Category Total:

3 Generic Total:

13 2.4.35 2.4.45 I ______

I I