ML040160085

Revised Examination Outline - ES-401-1 and ES-401-2 for the Monticello Initial Examination - September 2003

ML040160085
Person / Time
Site:	Monticello
Issue date:	09/23/2003
From:	Allex G Nuclear Management Co
To:	NRC/RGN-III
References
50-263/03-301, ES-401-1, ES-401-2 50-263/03-301
Download: ML040160085 (26)

Text

REVISED EXAMINATION OUTLINE - ES-401-1 AND ES-401-2 FOR THE MONTICELLO INITIAL EXAMINATION - SEP 2003

ES-401 BWR RO Examination Outline Form ES-401-2 Facility: hort.f;rc//o Date of Exam: q/Zub,E w

Tier I

Group 1 7

K K

K K

I 1

1 1

1

1.

Emergency &

Abnormal Plant Evolutions Totals Tier 3 L j 3 7

3. Generic Knowledge and Abilities

am Level:

Point 1. 2 4 3 3

4 28 2 0 2 3 2 2 2 19 3

3 7

6 5

7 3

51 Note: 1.

Ensure that at least two topics from every WA category are sampled within each tier (i.e., 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 +I from that specified in the table based on NRC revisions. The final exam must total 100 points.

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.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the category/tier.

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.

On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings for the SRO license level, and the point totals for each system and category. WAS below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

2.

3.

4.

5.

6.*

7.

19 of 46 NUREG-1021, Revision 8, Supplement 1

Monucello Nuclear Generating Z

BWR RO I(

nination Outline Printed:

0910212(

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

KATopic AK3.06 - Recirculation pump speed reduction:

Plant-Specific AA2.06 - Cause of reactor SCRAM Facility:

ES - 401 K

Form ES-401-2 AA2.02 - Reactor power AK2.03 - Recirculation system AK2.02 - DrywelYsuppression chamber differential pressure: Mark-I&II AA1.05 - DrywelYsuppression vent and purge EK1.O1 - Drywell integrity: Plant-Specific 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Emergenc I

EIAPE #

EIAPE Name I Safety Function K1 SCRAM I 1 295006 3-2 I +

295006 SCRAM1 1 295007 I AK2.03 - RHR/LPCI: Plant-Specific I

High Reactor Pressure / 3 High Reactor Pressure 13 4.1 295007 Low Reactor Water Level 12 High Drywell Pressure / 5 295009 295010 2950 10 295024 High Drywell Pressure / 5 High Reactor Pressure / 3 295025 29503 1 29503 1 I EK3.01 - Automatic depressurization system actuation I

Reactor Low Water Level / 2 I

3.6 I

1 Reactor Low Water Level 12 I

EA1.10 - Control rod drive 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 EA2.06 - Reactor pressure 3.3 I

1 High Containment Hydrogen Concentration I 5 Ix KIA Category Totals:

2 I EK1.O 1 - Containment integrity 500000 1

Group Point Total:

13 1

(

Facility:

Monricello Nuclear Generating E/AF'E Name / Safety Function Partial or Complete Loss of Forced Core Flow Circulation I 1 Loss of Main Condenser Vacuum 13 High Reactor Water Level / 2 High Drywell Temperature 15 ES - 401 I K1 X

E/AF'E #

t-295001 Imp.

3.3 3.2 3.1 3 -3 3.6 3.8 4.0*

3.5 3.4 2950 12 295013 2950 13 Points 1

1 1

1 1

1 1

1 1

2950 16 t-2950 16 295017 2950 18 2950 18 295019 295026 I295028

~

High Suppression Pool Temperature / 5 High Suppression Pool Temperature / 5 Control Room Abandonment I 7 Control Room Abandonment I 7 High Off-Site Release Rate 19 Partial or Complete Loss of Component Cooling Water / 8 Partial or Complete Loss of Component Cooling Water I 8 Partial or Complete Loss of Instrument Air / 8 Suppression Pool High Water Temperature / 5 High Drywell Temperature / 5 BWR RO 6 nination Outline Printed:

09/0~.(

and Abnormal Plant Evolutions - Tier 1 / Group 2 KA Topic AK2.04 - Reactodturbine pressure regulating system:

Plant-Specific AA2.02 - Reactor power: Plant-Specific AK2.11 - Main steam AK1.O 1 - Pressure/temperature relationship AK3.O 1 - Sumression D O O ~ cooling oDeration AA2.0 1 - Suppression pool temperature AK2.02 - Local control stations: Plant-Specific AK3.03 - Disabling control room controls AK2.12 - Standby gas treatment/FRVS

~

~~

AK3.05 - Placing standby heat exchanger in service 2.1.20 - Ability to execute procedure steps.

~~

~~

AA1.03 - Instrument air compressor power supplies EK3.04 - TSBLC injection EA1.05 - ADS Form ES-401-2 3.7 I

1 1

Facility:

Monticello Nuclear Generating E/APE Name / Safety Function Low Suppression Pool Water Level I 5 Low Suppression Pool Water Level 15 High Secondary Containment Area Radiation Levels I 9

Secondary Containment Ventilation High Radiation I 9

High Off-Site Release Rate / 9 ES - 401 K1 X

E/APE #

295030 42 295030 G KATopic Imp.

EA1.05 - HPCI 3.5 295033 EK2.08 - SRV discharge submergence EK1.02 - Personnel protection 295034 3.5 3.9 295038 EA1.07 - Control room ventilation: Plant-SDecific Emergenc:

3.6 BWR RO 6 nination Outline tnd Abnormal Plant Evolutions - Tier 1 / Grow 2 Printed:

091021<

Form ES-401-2 5

4 EK3.02 - Starting SBGTRRVS: Plant-Specific I I 1 4.1 2

1 Group Point Total:

Points 1

1 1

1 1

19 2

(

Facility:

Monticello Nuclear Generating A2 BWR RO r( nination Outline G KATopic Imp.

Points E/APE #

E/APE Name / Safety Function K1 K2 K3 295032 High Secondary Containment Area Temperature I 5 X

295035 295036 Secondary Containment High Differential Pressure 1 5 Secondary Containment High SumplArea Water Level I 5 295036 Secondary Containment High SumplArea Water X

Level I 5 X

WACategory Totals:

0 1

1 1

EK2.05 - Temperature sensitive instrumentation 3.2 1

EAl.02 - SBGTIFRVS 3.8 1

EA2.03 - Cause of the high water level 3.4 1

Printed:

0910214 Form ES-401-2 I

1 I

I I

I I I

I 2.6 I I

EK3.O 1 - Emergency depressurization l l 1

0 Group Point Total:

4 1

BWR RO E$

nation Outline 13 X

X Printed:

09102(

3 A4 X

X X

Facility:

Monticello Nuclear Generating I1 X

Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2 X

ES - 401 K5 K6 G KA Topic A2.17 - Keep fill system failure 3.3 1

Imp. !Points 1 2.7 I 1

A3.03 - System pressure 20 1002 202002 Reactor Manual Control System / 1 Recirculation Flow Control System I 1 203000 RHRLPCI: Injection Mode (Plant Specific) 12 AI.04 - Overall reactor power K4.06 - Recirculation pump adequate NPSH:

Plant-SDecific 2.7* I 1

K2.03 - Initiation logic RHRLPCI: Injection Mode (Plant SDecific) 12 I

High Pressure Coolant Injection 1206000 I System 12 I

I A4.10 - System pumps: BWR-2, 3,4 I 3.7 I 1

K4.05 - Pump minimum flow 1

2.6 I209001 I Low Pressure Core Spray System I 2 I 1

12 12000 I Reactor Protection System / 7 I

3.9*

1 A3.04 - System status lights and alarms A4.05 - Trip bypasses K3.01 - RPS A4.04 - SRM drive control switches K1.04 - LPRM channels I

/2i5003 1 Intermediate Range Monitor (IRM)

System I 7 3.4 1

12 15004 I Source Range Monitor (SRM) System I 1

3.4 3.2 3.6 2 15004 Source Range Monitor (SRM) System 17 215005 Average Power Range MonitorlLocal X

Power Range Monitor System I 7 1

(

Facility:

Monticello Nuclear Generating ES - 401 91 X

X X

BWR RO EX( nation Outline A2 A3 X

X Printed:

09/04 3

K5 Plant Systems K6 X

her 2 /Group 1 I

Sys/Ev #

Form ES-401-2 System / Evolution Name KA Topic

~

Imp.

Points A4 X

G

~

K1.03 - Containment/drywell atmosphere A2.03 - Safetyhelief valve leaking or stuck open A3.03 - SPDS/ERIS/CRIDS/GDS:

Plant-Specific control

~

3.2 I

4.0 1

2.5*

1 K4.05 - Single failures will not impair the function ability of the system 2.9 K6.03 - A.C. power: Plant-Specific A4.06 - Reactor water level 2.7*

1 3.9 1

AI.05 - Lights and alarms 1 3 - 3 1 1 I 215005 I Average Power Range MonitorLocal Power Range Monitor System / 7 2 16000 t 2 16000 Nuclear Boiler Instrumentation / 7 Nuclear Boiler Instrumentation / 7 K3.14 - High pressure coolant injection:

Plant-Specific A 1.O 1 - Recorders and meters

~

K4.04 - Prevents turbine damage: Plant-Specific 2 17000 Reactor Core Isolation Cooling System (RCIC) / 2 Primary Containment System and Auxiliaries / 5 Primary Containment System and Auxiliaries / 5 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off / 5 223001 22300 1 223002 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off / 5

~

239002 Relieusafety Valves / 3 239002 Relief/Safety Valves / 3 ReactodTurbine Pressure Regulating System / 3 24 1000 AI.07 - Bypass valve position I 3-8 I I

2

BWR RO EXS nation Outline Sys/Ev #

System I Evolution Name K1 K2 K3 K4 24 1000 ReactodTurbine Pressure Regulating System / 3

,259001 Reactor Feedwater System / 2 X

Printed:

09/04 3

25900 1 259002 26 IO00 Facility:

Monticello Nuclear Generating Reactor Feedwater System / 2 Reactor Water Level Control System /

2 Standby Gas Treatment System / 9 ES - 401 I

1 I

I I

Plant Svstems - Tiel

roup 1 KA Topic K5.04 - Turbine inlet pressure vs. reactor pressure K2.0 1 - Reactor feedwater pump(s):

Motor-Driven-Only A2.05 - Loss of applicable plant air systems 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

K6.03 - Emergency diesel generator system Form ES-401-2 WACategory Totals:

2 2

2 4

1 2

4 3

3 4

1 Group Point Total:

28 3

BWR RO EX( nation Outline Al.03 - Latched group indication:

P-Specmot-BWR6)

Printed:

09/02(

3 2.9 1

Facility:

Monticello Nuclear Generating A2.01 - Withdrawal of control rod in high K2.03 - APRM channels: BWR-3,4, 5 A3.01 - Valve operation A2.02 - Pumps trips A4.14 - Suppression pool temperature power region of core: BWR-3,4, 5

roup 2 Form ES-401-2 I

I 3.3 1

2.8 1

3.3 1

3.3 1

3.3 1

KA Topic I Imp. I Points I

I K2.0 1 - Off-site sources of power 3.3 1

K5.02 - Valve operation 1 2.8 1 I

Al.05 - Reactor water level K1.05 - A.C. electrical 1

3.2 I 1

I I

I I 2.6 I A4.10 - Hydrogen gas pressure 1

Facility:

ES - 401 A4

~~

G KATopic X 2.4.10 - Knowledge of annunciator response Drocedures.

BWR RO EX(

nation Outline Sys/Ev #

26200 1 r

262002 263000 27 1000 271000 290001 29000 1 400000 ZI Printed:

09/04 3

K5.0 1 - Hydrogen generation during battery charging K3.02 - ?Off-site radioactive release rate Monticello Nuclear Generating 2.6 3.3 Form ES-401-2 Plant Svstems - Tier 2 / Grow 2 A3.02 - Normal building differential pressure:

I x I I I Plant-Specific System / Evolution Name A.C. Electrical Distribution / 6 3.5 Unintermptable Power Supply (A.C./D.C.) 1 6 D.C. Electrical Distribution / 6

~

X Offgas System / 9 2.2.2 - Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

4.0 Offgas System 19 Secondary Containment I 5 Secondary Containment I 5 Component Cooling Water System (CCWS) I 8 K/A Category Totals:

1 2

1 2

2 0

X 1 1 I lA2.01 -Under voltage 1 2.6 I

I I

I I

1 I

I 1

1 1 I ( ~ 4. 0 5

-Redundancy I 2.6 I I l l K4.03 - Fluid leakage collection I 2.8 Points 1

1 I

1 1

1 1

1 3

2 2

2 Group Point Total:

19 2

(

Facility:

Monticello Nuclear Generating ES - 401 SysIEv #

System 1 Evolution Name K1 K2 K3 K4 2 1500 1 Traversing In-Core Probe / 7 Fuel Handling Equipment / 8 234000 268000 Radwaste I 9 290002 Reactor Vessel Internals / 5 X

BWR RO EX( nation Outline K5 K6 A1 A2 X

X Printed:

09/04 3

KA Topic A1.03 - Valve status: Mark-I&II(Not-BWRI)

K6.04 - ?Refueling platform air system:

Plant-Specific A4.0 1 - Sump integrators K4.04 - Moisture removal fi-om generated steam Plant Systems - Tier 2 / Group 3 Form ES-401-2 Imp.

2.6*

2.9 3.4 2.8 WA Category Totals:

0 0

0 1

0 1

1 0

A3 A4 G v 0

1 0

Points 1

1 1

1 4

1

Facility:

Monticello Nuclear Generating Equipment Control Generic Category 2.2.30 Conduct of Operations Knowledge of RO duties in the control room during fuel handling such as alarms from Knowledge of tagging and clearance procedures.

fuel handling area / communication with fuel storage facility / systems operated from the control room in support of fueling operations / and supporting instrumentation.

KA 2.1.1 1 2.1.32 2.1.18 2.1.22 3.5 1

3.6 1

Ability to control radiation releases.

Knowledge of facility ALARA program.

I 2-2-13 2.7 1

2.5 1

1 2.3.11 Emergency Plan I 2.3.9 2.4.24 I 2.3.4 Knowledge of loss of cooling water procedures.

3.3 1

Generic Knowledge an?

bilities Outline (Tier 3)

(~

BWR RO Examination Outline Printed: 09/02/2003 \\

Form ES-401-5 KA Topic Imp.

Points Knowledge of less than one hour technical specification action statements for systems.

Ability to explain and apply system limits and precautions.

Ability to make accurate, clear and concise logs, records, status boards, and reports.

Ability to determine Mode of Operation.

3.O 3.4 2.9 2.8 1

1 1

1 Knowledge of the process for performing a containment purge.

I 2.5 I Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

Knowledge of EOP terms and definitions.

2.9 3.1 Category Total:

3 Generic Total:

13 1

ES-401 BWR SRO Examination Outline Form ES-401-1 Cat I 5-Facility: H~.);LP-//U Date of Exam: i / z t / L ! ! Exam Level: S L O I

Cat 2 Cat 3 Cat 4 17 5

3 7

WA Category Points I

Tier Group Emergency &

Abnormal Plant Evolutions Tier Totals

2.

Plant k-Systems Tier Totals

3. Generic Knowledge and Abilities Point K

K K

A A

A A

G Total 4

5 6

1 2

3 4

I O

O i

~

O

/

O 4

5 2 3 6 Y 3 3 40 Note: 1.

Ensure that at least two topics from every WA category are sampled within each tier (i.e., the Tier Totals in each WA category shall not be less than 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 k1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

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.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryker.

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.

On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings for the SRO license level, and the point totals for each system and category. WAS below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

two).

2.

3.

4.

5.

6.*

7.

13 of 46 NUREG-1021, Revision 8, Supplement 1

Facility:

Monucello Nuclear Generating E/APE Name / Safety Function Partial or Complete Loss of A.C. Power I 6 BWR SRO(

imination Outline Printed:

091021%

K1 K2 K3 AI A2 G X

ES - 401 KA Topic 2.4.27 - Knowledge of fire in the plant procedure.

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

~~

Imp.

Points 3.5 1

High Reactor Pressure I 3 High Reactor Pressure / 3 X

X E/APE #

295003 Low Reactor Water Level I 2 High Drywell Pressure 15 High Suppression Pool Temperature I 5 I I l x I I I X

X X

1 3.3 1 1

AK2.03 - Recirculation system AAl.05 - DrywelVsuppression vent and purge AK3.O 1 - Suppression pool cooling operation AA2.01 - Suppression pool temperature 295006 3.2 1

3.4 1

3.8 1

4.0 1

SCRAM / 1 AA 1.02 - RPS AK3.06 - Recirculation pump speed reduction:

Plant-Specific 4.2*

1 AK2.03 - RHNLPCI: Plant-SDecific I 3.2 I 1

AK3.03 - Disabling control room controls AK2.06 - +Site emergency plan AK2.12 - Standby gas treatment/FRVS EKl.01 - Drywell integrity: Plant-Specific 3.7*

1 4.6*

1 3.7 1

4.2*

1 295007 295007 AA2.02 - Reactor power 1411*/

1 295009 295010 295013 2950 13 High Suppression Pool Temperature I 5 I

I I I

1x1 i 2950 15 Incomplete SCRAM / 1 AK2.02 - Local control stations: Plant-Specific I 4.1* I 1

I 1

2950 16 Control Room Abandonment I 7 2950 16 Control Room Abandonment 17 High Off-Site Release Rate I 9 High Off-Site Release Rate 19 High Drywell Pressure / 5 2950 17 2950 17 295024 1

Facility:

Monricello Nuclear Generating A 2 G X

X X

BWR SRO(

rmination Outline Printed:

09/02/$

X Emergent:

High Containment Hydrogen Concentration 1 5 and Abnormal Plant Evolutions - Tier 1 /Group 1 X

Form ES-401-1 ES - 401

~~

E/APE Name / Safety Function High Reactor Pressure 13 K1 -

Imp.

4.4 Points 1

E/APE #

295025 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

X 295025 High Reactor Pressure 13 EK1.05 - ?Exceeding safety limits 4.7*

1 EA2.02 - Suppression pool level 295026 3.9 1

Suppression Pool High Water Temperature / 5 295026 1

EK3.04 - tSBLC injection Suppression Pool High Water Temperature I 5 Low Suppression Pool Water Level / 5 Low Suppression Pool Water Level I 5 Reactor Low Water Level I 2 Reactor Low Water Level / 2 4.1*

3.5 3.8 4.2*

3.7 295030 1

EAl.05 - HPCI EK2.08 - SRV discharge submergence 295030

~~

~

~~~

EK3.O 1 - Automatic depressurization system actuation EA1. 10 - Control rod drive 29503 1 29503 1

~

1 EA2.02 - Reactor water level 4.2*

1 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 295037 295037 EA2.06 - Reactor pressure 4.1 1

~~

High Off-Site Release Rate 19 295038 EA1.07 - Control room ventilation: Plant-Specific 1

3.8 3.9 EKl.01 - Containment integrity 500000 1

5 2

Group Point Total:

26 6

5 5

2

Facility:

Monricello Nuclear Generating BWR SRO imination Outline and Abnormal Plant Evolutions - Tier 1 / Group 2 Printed:

09/02/4 Form ES-401-1 ES - 401 Emei E/APE Name / Safety Function Partial or Complete Loss of Forced Core Flow Circulation I 1 E/APE #

mp.

3.3 KA Topic AK2.04 - Reactorlturbine pressure regulating system:

Plant-Specific Points 29500 1 1

295002 Loss of Main Condenser Vacuum 13 3.3 1

AA2.02 - Reactor power: Plant-Specific AA 1.02 - Systems necessary to assure safe plant shutdown Partial or Complete Loss of D.C. Power / 6 295004 4.1 1

Main Turbine Generator Trip / 3 295005 AA1.02 - RPS AK2.11 - Main steam 3.6 3.3 4.3 295008 High Reactor Water Level I 2 2.4.2 1 - Knowledge of the parameters and logic used to assess the status of safety functions including:

1.Reactivity control 2.Core cooling and heat removal 3.Reactor coolant system integrity 4.Containment conditions 5.Radioactivity release control.

295012 High Drywell Temperature / 5 2950 12 3.5 1

High Drywell Temperature / 5 Partial or Complete Loss of Component Cooling Water I 8 Partial or Complete Loss of Instrument Air / 8 High Drywell Temperature / 5 High D w e l l TemDerature / 5 AKl.O 1 - Pressure/temperature relationship AK3.05 - Placing standby heat exchanger in service 2950 18 2950 19 295028 3 -3 3.0 4.0 3.7 AA1.03 - Instrument air compressor power supplies 2.4.16 - Knowledge of EOP implementation hierarchy and coordination with other support procedures.

EA1.05 -ADS 295028 1

1

Facility:

Monticello Nuclear Generating

<Z - K3 ES - 401 Emergenc:

I A1 A2 G KATopic Imp.

X EA2.03 - Drywell/containment water level 3.5 E/APE #

X E/APE Name / Safety Function I K1 EK3.03 - Reactor SCRAM 3.5 295029 I High Suppression Pool Water Level I 5 I

X 295029 X

EA1.02 - SBGTIFRVS 3.8 2.8 EK3.0 1 - Emergency depressurization 295033 295034 295035 295036 High Suppression Pool Water Level / 5 High Secondary Containment Area Radiation Levels I 9

Secondary Containment Ventilation High Radiation I 9

Secondary Containment High Differential Pressure / 5

~~~

Secondary Containment High SumpIArea Water Level I 5 KJA Category Totals: u 2

BWR SRO(

tmination Outline Printed:

09/02/i I

I I I EKl.02 - Personnel protection 1 4.2*

EK3.02 - Starting SBGTIFRVS: Plant-Specific 1 I I 1 4.1 4

5 2

2 Group Point Total:

Points 1

1 1

1 1

1 17 2

(

Facility:

Monticello Nuclear Generating ES - 401 K5 BWR SRO E{

ination Outline K6 Printed:

09/04 3

A2 X

X X

Plant Svstems - Tier 2 I Grow 1 A3 X

Form ES-401-1 3.8 3.4 3.6 4.2*

3.3 3.3 4.2*

i-1 1

1 1

1 1

1

~

SysIEv #

203000 203000 System I Evolution Name K1 RHWLPCI: Injection Mode (Plant Specific) 12 RHWLPCI: Injection Mode (Plant SDecific) 12 KA ToDic K2.03 - Initiation logic A2.17 - Keep fill system failure I

3.5 I 209001 I Low Pressure Core Spray System / 2 I K4.05 - Pump minimum flow A2.05 - Core spray line break 3.6 I 1

Low Pressure Core Spray System I 2 Reactor Protection System I 7 Source Range Monitor (SRM) System

/ 7 Average Power Range MonitorLocal X

Power Range Monitor System / 7 Nuclear Boiler Instrumentation I 7 20900 1 2 12000 I

A3.04 - System status lights and alarms K3.01 - RPS K 1.04 - LPRM channels K3.14 - High pressure coolant injection:

Plant-SDecific 2 15004 2 15005 2 16000 A 1.O 1 - Recorders and meters K1.03 - Containment/drywell atmosphere control A2.03 - Safetykelief valve leaking or stuck open A3.03 - SPDSERIS/CRIDS/GDS:

Plant-Specific Auxiliaries I 5 223001 Primary Containment System and Auxiliaries I 5 SystemNuclear Steam Supply Shut-Off 1 5 1

BWR SRO E(

ination Outline 41 X

X Printed:

09/04 3

A2 A3 X

Facility:

Monticello Nuclear Generating

<1 K2 X

Plant Systems - Tier 2 / Group 1 Form ES-401-1 K3 ES - 401 s y s m #

223002 (4

X X

K5 X

G KATopic Imp.

Points 1

Svstem / Evolution Name I 3-1 K4.05 - Single failures will not impair the function ability of the system Primary Containment Isolation System/Nuclear Steam Supply Shut-Off I 5 RHRnPCl: Containment Spray System Mode 1 5 RelieVSafety Valves 13 1 3.6 1

22600 1 A4.14 - Suppression pool temperature 1

239002 K6.03 - A.C. power: Plant-Specific 2.9*

24 1000 I AI.07 - Bypass valve position I 3-7 1

ReactodTurbine Pressure Regulating System I 3 ReactodTurbine Pressure Regulating System / 3 Reactor Water Level Control System /

2 Standby Gas Treatment System 19 A.C. Electrical Distribution / 6 1

I K5.04 - Turbine inlet pressure vs. reactor 1

3.3 pressure 1

24 1000 1

259002 Al.05 - FWRVIstartup level control position:

Plant-Specific 2.9 1

K6.03 - Emergency diesel generator system K2.0 1 - Off-site sources of power X 2.4.38 - Ability to take actions called for in the facility emergency plan, including (if required)supporting or acting as emergency coordinator.

3.1 3.6 4.0 26 1000 26200 1 264000 1

1 Emergency Generators (DieseVJet) / 6 1

29000 1 Secondary Containment I 5 K4.03 - Fluid leakage collection A3.02 - Normal building differential pressure:

~

Secondary Containment I 5 29000 I 1

2

sr!

75 -.

m 0

.m Y

U W

0 a:

m s

f9 a

a e

W U a E30 s

W 3

m

K5 K6 X

X A1 X

X 12 X

A3 A4 X

X BWR SRO E{

ination Outline Printed:

09/04 3

Facility:

ES - 401 Monticello Nuclear Generating Plan1 I

I s y s m #

20 1002 System / Evolution Name Reactor Manual Control System I 1 KA Topic Imp.

Points AI.04 - Overall reactor power 3.5 1

I 2*9 I i

205000 Shutdown Cooling System (RHR Shutdown Cooling Mode) I 4 K5.02 - Valve operation 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode) I 4 1 3. 4 1 1 I

Al.05 - Reactor water level 2 15002 Rod Block Monitor System I 7 A2.01 - Withdrawal of control rod in high power region of core: BWR-3,4, 5 K2.03 - APRM channels: BWR-3,4, 5 Rod Block Monitor System 17 2 15002 2 19000 RHWLPCI: TorusISuppression Pool Cooling Mode I 5 1 3. 3 1 1 I A3.01 - Valve operation A4.09 - Indicating lights and alarms I 3.3 I I

230000 230000 234000 RHRLPCI: TorusISuppression Pool Spray Mode I 5 RHWLPCI: Torus/Suppression Pool Spray Mode I 5 Fuel Handling Equipment I 8 I 3.3 I I

Kl.05 - A.C. electrical K6.04 - ?Reheling platform air system:

3.7 1

2.1.33 - Ability to recognize indications for 4.0 1

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

Fuel Handling Equipment I 8 234000 27 1000 I 3.9 I I

K3.02 - ?Off-site radioactive release rate Offgas System / 9 1

(

BWR SRO E(

iination Outline Printed:

09/04 j3 Sys/Ev #

271000 Facility:

Monticello Nuclear Generating ES - 401 System I Evolution Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp.

Points Offgas System / 9 X

K4.05 - Redundancy 2.6 1

Plant Systems - Tier 2 /Group 2 Form ES-401-1 WACategory Totals:

1 1

1 1

1 1

2 1

1 1

2

?.l Group Point Total:

13 2

BWR SRO E(

iination Outline Printed:

09/04

)3 Facility:

Monticello Nuclear Generating ES - 401 290002 290002 Reactor Vessel Internals / 5 Reactor Vessel Internals / 5 K2 Plant Systems - Tiel 2 1 G -

Group 3 KAT0 ic A1.03 - Valve status: Mark-I&II(Not-BWRI)

A4.01 - Sump integrators I 3.6 1 K4.04 - Moisture removal from generated steam K3.01 - Reactor water level WACategory Totals:

0 0

1 1

0 0

1 0

0 1

0 Group Point Total:

4 1

(

Facilitv:

Monticello Nuclear Generating 2.1.7 2.1.1 1 2.1.32

2. I. I8 2.1.22 Generic Knowledge a

• Qbilities Outline (Tier 3) r BWR SRO Examination Outline Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Knowledge of less than one hour technical specification action statements for systems.

Ability to explain and apply system limits and precautions.

Ability to make accurate, clear and concise logs, records, status boards, and reports.

Ability to determine Mode of Operation.

Printed: 09/02/2003 \\

Form ES-401-5 2.2.8 2.2.13 2.2.26 2.2.24 2.2.32 Generic Category Knowledge of the process for determining if the proposed change, test, or experiment involves an unreviewed safety question.

Knowledge of tagging and clearance procedures.

Knowledge of refueling administrative requirements.

Ability to analyze the affect of maintenance activities on LCO status.

Knowledge of the effects of alterations on core configuration.

Conduct of Operations 2.3.1 I 2.3.2 2.3.4 Ability to control radiation releases.

Knowledge of facility ALARA program.

Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Equipment Control 3.2 1

2.9 1

3.1 1

Radiation Control KA KATopic Imp.

Points 4.4 3.8 3.8 3.O 3.3 1

1 1

1 1

Category Total:

5 3.3 3.8 3.7 3.8 3.3 Category Total:

5 1

Generic Knowledge an

• Qbiiities Outline (Tier 3)

(

BWR SRO Examination Outline Facility:

Monticello Nuclear Generating Generic Category Emergency Plan KA 2.4.24 2.4.5 2.4.30 2.4.6 c

Printed: 09/02/2003 Form ES-401-5 KA Topic Knowledge of loss of cooling water procedures.

Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

Knowledge of which events related to system operationshtatus should be reported to outside agencies.

Knowledge symptom based EOP mitigation strategies.

Imp.

Points Category Total:

4 Generic Total:

17 2