Text

October 2002 Exam 50-321/2002-301 Draft Written Outlines
	ML023400182
Person / Time
Site:	Hatch
Issue date:	01/09/2003
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Sumner H; Southern Nuclear Operating Co
References
	50-321/02-301, 50-366/02-301, ES-401, ES-401-1 50-321/02-301, 50-366/02-301
	Download: ML023400182 (33)
	v • d • e

Draft Submittal

E. I. HATCH NUCLEAR PLANT

EXAM 2002-301

50-321 & 50-366

OCTOBER16

OCTOBER

18, 21 -25, &

30, 2002,

1.

Written Exam Sample outlines

ES-401

BWR SRO Examination Outline

Form ES-401-1 (R8, Si)

Facility: gAf'-

Date of Exam: 0Cd ClExam Level: SRO

K/A Category Points

Tier

Group

Point

K

K KK

I

K

A

IG

Total

1

2

3

4

5

1

2

3

4

_

1.

1

3

5

4

5

4

26

Emergency &

-

Abnormal

2

.3

33

17

Plant

Evolutions

Tier

5

8

88

43

T o ta ls

.

...........

..

2.

Plant

2

1

2

1

2

1

13

Systems

3

1

Tier

3

4

5

440

Totals

I

3. Generic Knowledge and Abilities

Cat 1

Cat 2

Cat 3

Cat 4

17

4

1

4

1

4

1

5

1

Note:

1.

Ensure that at least two topics from every K/A 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 by +/-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 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.

6.*

The generic K/As 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 SRO license level, and the point

totals for each system and category. K/As below 2.5 should be justified on

the basis of plant-specific priorities. Enter the tier totals for each category in

the table above.

(

ES401

BWR SRO Examination Outline

Form ES-401-1 (R8, Si)

ES-401

_Emergency

and Abnormal Plant Evolutions - Tier 1/Group 1

E/APE # / Name / Safety Function

K1

K2

K3

Al

A2

G

K/A Topic(s)

Imp.

Point

s

295003 Partial or Complete Loss of AC Pwr /6

X

AK2.01 Knowledge of the interrelations between PARTIAL OR

3.2/3.3

1

COMPLETE LOSS OF A.C. POWER and the following: station batteries.

295006 SCRAM / 1

X

AK3.01 Knowledge of the reasons for the following responses as they

3.8/3.9

2

apply to SCRAM: Reactor water level response.

2.2.22 Knowledge of limiting conditions for operations and safety limits.

3.4/4.1

295007 High Reactor Pressure / 3

X

AA1.04 Ability to operate and/or monitor the following as they apply to

3.9/4.1

1

HIGH REACTOR PRESSURE: Safety/relief valve operation.

295009 Low Reactor Water Level /2

X

AK1.05 Knowledge of the operational implications of the following

2

concepts as they apply to LOW REACTOR WATER LEVEL: Natural

3.3/3.4

circulation.

2.4.1 Knowledge of EOP entry conditions and immediate action steps.

4.3/4.6

___

295010 High Drywell Pressure/ 5

X

AA2.06 Ability to determine and/or intemret the following as they apply

3.6/3.6

1

to HIGH DRYWELL PRESSURE: Drywell temperature.

295013 High Suppression Pool Temp. /5

X

AKI.03 Knowledge of the operational implications of the following

3.0/3.3

2

concepts as they apply to HIGH SUPPRESSION POOL

TEMPERATURE: Localized heating.

AK3.01 Knowledge of the reasons for the following responses as they

3.6/3.8

apply to HIGH SUPPRESSION POOL TEMPERATURE: Suppression

pool cooling operation.

295014 Inadvertent Reactivity Addition / 1

X

AK2.03 Knowledge of the interrelations between INADVERTENT

3.3/3.4

1

REACTIVITY ADDITION and the following: Fuel temperature.

295015 Incomplete SCRAM / 1

X

AA2.01 Ability to determine and/or interpret the following as they apply to

4.1/4.3

1

INCOMPLETE SCRAM: Reactor power.

295016 Control Room Abandonment / 7

X

AK3.01 Knowledge of the reasons for the following responses as they

4.1/4.2

1

apply to CONTROL ROOM ABANDONMENT: Reactor SCRAM.

295017 High Off-site Release Rate / 9

X

2.3.4 Knowledge of radiation exposure limits and contamination

2.5/3.1

1

control/including permissible levels in excess of those authorized.

295023 Refueling Accidents Cooling Mode / 8

X

AK1.03 Knowledge of the operational implications of the following

3.7/4.0

1

concepts as they apply to REFUELING ACCIDENTS: Inadvertent

criticality,

295024 High Drywell Pressure / 5

X

EAI.O4Abili

to operate and/or monitor the following as they apply to

4.1/3.9

1

HIGH DRY

LL PRESSURE: RHRILPCI.

295025 High Reactor Pressure / 3

X

EA.07 Abili

to oerate and/or monitor the following as they apply to

4.1/4.1

2

HIGH REAC OR RESSURE: ARI/RPT/ATWS.

EA2.04 Ability to determine and/or interpret the following as they apply

3.9/3.9

to HIGH REACTOR PRESSURE: Suppression pool level.

295026 Suppression Pool High Water Temp. / 5

X

EK2.04 Knowledge of the interrelations between SUPPRESSION POOL

2.5/2.8

1

HIGH WATER TEMPERATURE and the following:

7

SPDS/ERIS/CRIDS/GDS.

295030 Low Suppression Pool Water Level / 5

x

EK3.03 Knowledge of the reasons for the following responses as they

apply to LOW SUPRESSION POOL WATER LEVEL: RCIC operation.

EA2.01 Ability to determine and/or interpret the following as they apply

to LOW SUPPRESSION POOL WATER LEVEL: Suppression pool level.

(

3.6/3.7

4.1/4.2

2

295031 Reactor Low Water Level / 2

X

2.4.4 Ability to recognize abnormal indications for system operating

4.0/4.3

1

parameters which are entry-level conditions for emergency and abnormal

operating procedures.

295037 SCRAM Condition Present and Power

X

EK2.05 Knowledge of the interrelations between SCRAM CONDITION

4.0/4.1

2

Above APRM Downscale or Unknown /1

PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR

UNKNOWN and the following: CRD hydraulic system.

EK3.02 Knowledge of the reasons for the following responses as they

4.3/4.5

apily to SCRAM CONDITION PRESENT AND REACTOR POWER

ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC injection.

295038 High Off-site Release Rate / 9

XX

EK2.03 Knowlege of the interrelations between HIGH OFF-SITE

3.6/3.8

2

RELEASE RAT and the following: Plant ventilation systems.

EA2.03 Ability to determine and/or interret the following as they apply to

3.5/4.3

HIGH OFF-SITE RELEASE RATE: Radiation levels.

500000 High Containment Hydrogen Conc. /5

X

EAI.01 Abily to ocrate and monitor the following as they apply to HIGH

3.4/3.3

1

CONTAINM NT H DROGEN CONTROL: Primary containment

hydrogen instrumentation.

K/A Category Totals:

J3

5

1 5 _F4

IS5

I 4

Group Point Total:

26

NUREG-1021

I

Revision 8

3 of 45

C

ES-401

BWR SRO Examination Outline

Form ES-401-1 (R8, SI)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2

E/APE # / Name / Safety Function

K1

K2

K3

Al

A2

G

K/A Topic(s)

Imp.

Point

s

295001 Partial or Complete Loss of Forced Core

X

AK2.07 Knowledge of the interrelations between PARTIAL OR

3.4/3.4

1

Flow Circulation / I & 4

COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the

following: Core flow indication.

295002 Loss of Main Condenser Vacuum / 3

X

AA2.02 Ability to determine and/or inter pret the following as they apply

3.2/3.3

1

to LOSS OF MAIN CONDENSER VACUUM: Reactor power.

295004 Partial or Total Loss of DC Pwr / 6

X

AK3.03 Knowledge of the reasons for the following responses as they

3.1/3.5

1

applyVto PARTIAL OR COMPLETE LOSS OF D.C. POWER: Reactor

295005 Main Turbine Generator Trip / 3

X

AAI.05 Ability to operate and/or monitor the following as they apply to

3.6/3.6

1

MAIN TURBINE GENERATOR TRIP: Reactor/turbine pressure

regulating system.

295008 High Reactor Water Level / 2

X

AK3.01 Knowledge of the reasons for the following responses as they

3.4/3.5

1

apply to HIGH REACTOR WATER LEVEL: Main turbine trip.

295011 High Containment Temperature / 5

Does not apply to Hatch. For Mark III containment only.

295012 High Drywell Temperature / 5X

AAI.02 Ability too perate and/or monitor the following as they apply to

3.8/3.8

1

HIGH DRYWELL TEMPERATURE: Drywell cooling system.

295018 Partial or Total Loss of CCW / 8

X

AK2.02 Knowledge of the interrelations between PARTIAL OR

3.4/3.6

1

COMPLETE LOSS OF COMPONENT COOLING WATER and the

following: Plant operations.

295019 Partial or Total Loss of Inst. Air / 8

Not selected.

295020 Inadvertent Cont. Isolation / 5 & 7

Not selected.

295021 Loss of Shutdown Cooling / 4

X

AK2.05 Knowledge of the interrelations between LOSS OF

2.7/2.8

1

SHUTDOWN COOLING and the following: Fuel pool cooling and

cleanup system.

295022 Loss of CRD Pumps / 1

X

2.1.30 Ability to locate and operate components ( including local

3.9/3.4

1

controls.

295028 High Drywell Temperature / 5

X

EKI.02 Knowledge of the operational implications of the following

2.9/3.1

1

concepts as they apply to HIGH DRYWELL TEMPERATURE:

Equipment environmental qualification.

295029 High Suppression Pool Water Level /5

X

EKI.01 Knowledge of the operational implications of the following

3.4/3.7

1

concepts as they apply to HIGH SUPPRESSION POOL WATER

LEVEJ: Containment integrity.

1

295032 High Secondary Containment Area

X

EK3.03 Knowledge of the reasons for the following responses as they

3.5/3.8

1

Temperature / 5

apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:

Emergency/normal depressurization.

295033 High Secondary Containment Area

X

2.3.10 Ability to perform procedures to reduce excessive levels of

2.9/3.3

1

Radiation Levels / 9

radiation and guard against personnel exposure.

C

$

295034 Secondary Containment Ventilation High

X

EA2.02 Ability to determine and/or inter pret the following as they apply

3.7/4.2

1

Radiation /9

to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION

I

I 9Cause of high radiation levels.

295035 Secondary Containment High Differential

X

2.1.7 Ability to evaluate plant performance and make operational

3.7/4.4

1

Pressure / 5

judgments based on operating characteristics / reactor behavior / and

I instrument interpretation.

295036 Secondary Containment High Sump/Area

X

EA1.02 Ability to operate and/or monitor the following as they apply to

3.5/3.6

1

Water Level/ 15SECONDARY

CONTAINMENT HIGH SUMP/AREA WATER LEVEL:

It

Ie 5Affected systems so as to isolate damaged portions..

600000 Plant Fire On Site / 8

X

AA2.06 Ability to determine and interpret the following as they apply to

2.5/2.8

1

PLANT FIRE ON SITE: Need for pressurizing control room

(recirculation mode).

I AcategoryPointTotals:

1213

3

1 3 J3

Group Point Total:

[17

Revision 8

NUREG-1021

5 of 45

(

&

ES-401

BWR SRO Examination Outline

Form ES-401-1 (R8, S)

Plant Systems - Tier 2/Group 1

System # / Name

K1

K2

K3

K4

K5

K6

Al

A2

A3

A4

G

KIA Topic(s)

Imp.

Point

s

201005 RCIS

System does not apply to Hatch.

202002 Recirculation Flow Control

X

K3.05 Knowledge of the effect that a loss or

3.2/3.3

1

malfunction of the RECIRCULATION FLOW

CONTROL SYSTEM will have on the

following: Recirculation pump speed.

203000 RHRILPCI: Injection Mode

X

A1.01 Ability to predict and/or monitor

4.2/4.3

1

changes in parameters associated with

operating the RHR/LPCI: INJECTION MODE

controls including: Reactor water level.

206000 HPCI

X

K5.08 Knowledge of the operational

3.0/3.2

2

implications of the following concepts as they

apply to HIGH PRESSURE COOLANT

INJECTION SYSTEM: Vacuum breaker

o6eration.

6.08 Knowledge of the effect that a loss or

3.8/3.8

malfunction of the following will have on the

HIGH PRESSURE COO LANT INJECTION

SYSTEM: Reactor pressure.

207000 Isolation (Emergency) Condenser

System does not apply to Hatch.

209001 LPCS

X

2.2.21 Knowledge of pre and post

2.3/3.5

1

maintenance operability requirements.

209002 HPCS

System does not apply to Hatch.

211000 SLC

X

A3.04 Ability to monitor automatic operations

4.3/4.4

2

of the STANDBY LIQUID CONTROL

SYSTEM including: Reactor power.

A4.01 Ability to manually operate and/or

3.9/3.9

monitor in the control room: Tank level.

212000 RPS

X

K4.06 Knowledge of REACTOR

3.0/3.0

1

PROTECTION SYSTEM design feature(s)

and/or interlocks which provide for the

following: Select rod insertion.

215004 Source Range Monitor

X

K5.03 Knowledge of the operational

2.8/2.8

1

implications of the following concepts as they

apply to SOURCE RANGE MONITOR

(SRM) SYSTEM: Changing detector position.

215005 APRM / LPRM

X

A2.03 Ability to (a) predict the impacts of the

3.6/3.8

1

following on the AVERAGE POWER RANGE

MONITOR/LOCAL POWER RANGE

MONITOR SYSTEM; and (b) based on those

predictions, use procedures to correct,

control, or mitigate the consequences of

those abnormal conditions or operations:

Inoperative trip (all causes).

216000 Nuclear Boiler Instrumentation

X

K2.01 Knowledge of electrical power

2.8/2.8

1

supplies to the following: Analog trip system.

I

(

217000 RCIC

X

K1.01 Knowledge of the physical

3.5/3.5

1

connections and/or cause-effect

relationships between REACTOR CORE

ISOLATION COOLING SYSTEM (RCIC) and

the following: Condensate storage and

transfer system.

218000 ADS

X

2.2.22 Knowledge of limiting conditions for

3.4/4.1

1

operations and safety limits.

223001 Primary CTMT and Auxiliaries

X

A2.12 Ability to (a) predict the impacts of the

3.7/3.8

1

following on thePRIMARY CONTAINMENT

SYSTEM AND AUXILIARIES; and (b) based

on those predictions, use procedures to

correct, control, or mitigate the

consequences of those abnormal conditions

or operations: Abnormal suppression pool

temperature.

223002 PCIS/Nuclear Steam Supply Shutoff

X

K1.07 Knowled e of the physical

3.4/3.6

1

connections and/or cause-effect

relationships between PRIMARY

CONTAINMENT ISOLATION

SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF and the following: Reactor core

isolation cooling.

226001 RHR/LPCI: CTMT Spray Mode

X

K2.02 Knowledge of electrical power

2.9/2.9

1

supplies to the following: Pumps.

239002 SRVs

X

A1.01 Ability to predict and/or monitor

3.3/3.4

1

changes in parameters associated with

operating the RELIEF/SAFETY VALVES

controls including: Tail pipe temperature.

241000 Reactor/Turbine Pressure Regulator

X

K6.05 Knowledge of the effect that a loss or

3.4/3.4

malfunction of the following will have on the

REACTOR/TURBINE PRESSURE

REGULATING SYSTEM: Condenser

vacuum.

259002 Reactor Water Level Control

X

K3.02 Knowledge of the effect that a loss or

3.7/3.7

1

malfunction of he REACTOR WATER

LEVEL CONTROL SYSTEM will have on the

following: Reactor feedwater system.

261000 SGTS

K4.01 Knowledge of STANDBY GAS

3.7/3.8

1

TREATMENT STEM design feature(s)

and/or interlocks which provide for the

following: Automatic system initiation.

262001 AC Electrical Distribution

X

A4.02 Ability to manually operate and/or

3.4/3.4

1

monitor in the control room: Synchroscope,

including understanding of running and

incoming voltages.

264000 EDGs

X

K5.06 Knowledge of the operational

3.4/3.5

1

implications of the followin concepts as they

apply to EMERGENCY GENERA ORS

(DIESEL/JET): Load sequencing.

290001 Secondary CTMT

X

A3.01 Ability to monitor automatic operations

3.9/4.0

1

of the SECONDARY CONTAINMENT

inr#llriinn

,frnnltrr, rnntJinmnt ikntinn

I

Revision 8

7 of 45

NUREG-1021

ci

(

KIA Category Point Totals:

2

12

13 12

12

1Group Point Total

23

NUREG-1021

Revision 8

8 of 45

7

C

I

ES401

BWR SRO Examination Outline

Form ES-401-1 (R8, Sl)

Plant Systems - Tier 2/Group 2

System # Name

KI

K2

K3

K4

K5

K6

Al

A2

A3

A4

G

K/A Topic(s)

Imp.

Point

s

201001 CRD Hydraulic

I Not selected.

201002 RMCS

X

A3.03 Ability to monitor automatic operations

3.2/3.2

of the REACTOR MANUAL CONTROL

SYSTEM including: rod drift alarm.

201004 RSCS

Does not apply to Hatch.

201006 RWM

Not selected.

202001 Recirculation

X

A1.07 Ability to predict and/or monitor

2.7/2.8

changes in parameters associated with

operating the RECIRCULATION SYSTEM

controls including: Recirculation pump

speed.

204000 RWCU

X

K5.08 Knowledge of the operational

2.6/2.6

implications of the following concepts as they

applyto REACTOR WATER CLEANUP

SYSTEM: Temperature measurement.

205000 Shutdown Cooling

X

2.1.22 Ability to determine Mode of

2.8/3.3

Operation.

214000 RPIS

X

K4.01 Knowledge of ROD POSITION

3.013.1

INFORMATION-SYSTEM design feature(s)

and/or interlocks which provide for the

following]: Reed switch locations.

215002 RBM

Not selected.

215003 IRM

Not selected.

219000 RHRILPCI: Torus/Pool Cooling Mode

X

A2.08 Ability to (a) predict the impacts of the

2.8/3.1

followin on theFRH/LPCh

TORUSTSUPPRESSION POOL COOLING

MODE; and (b) based on those predictions,

use procedures to correct, control, or

mitigate the consequences of those

abnormal conditions or operations: Pump

seal failure.

230000 RHR/LPCI: Torus/Pool Spray Mode

Changed to 272000K2.05 due to KA

selecfed was the same as 226001 K2.02.

234000 Fuel Handling Equipment

X

K6.02 Knowledge of the effect that a loss or

2.8/3.5

malfunction of the following will have on the

FUEL HANDLING EQUIPMENT: Reactor

manual control system.

239003 MSIV Leakage Control

Does not apply to Hatch.

245000 Main Turbine Gen. and Auxiliaries

X

K1.09 Knowledge of the physical

2.7/2.7

connections and/or cause-effect

relationships between MAIN TURBINE

GENERATOR AND AUXILIARY SYSTEMS

and the following: D.C. electrical distribution.

K

245000 Main Turbine Gen. and Auxiliaries

X

I

K1.09 Knowledge of the physical

connections and/or cause-effect

relationships between MAIN TURBINE

GENERATOR AND AUXILIARY SYSTEMS

and the following: D.C. electrical distribution.

2.7/2.7

1

259001 Reactor Feedwater

Not selected.

262002 UPS (AC/DC)

Not selected.

263000 DC Electrical Distribution

X

K3.01 Knowledge of the effect that a loss or

3.4/3.8

1

malfunction of the D.C. ELECTRICAL

DISTRIBUTION will have on the following:

Emergency generators.

271000 Offgas

Not selected.

272000 Radiation Monitoring

X

K2.05 Knowledge of electrical power

2.6/2.9

1*

supplies to the following: Reactor building

ventilation monitors.

286000 Fire Protection

x

A1.01 Ability to predict and/or monitor

2.9/2.9

1

changes in parameters associated with

operating the FIRE PROTECTION SYSTEM

controls including: System pressure.

290003 Control Room HVAC

X

K5.02 Knowledge of the operational

2.8/2.8

1

implications of the following concepts as they

apply to CONTROL ROOM HVAC:

Differential pressure control.

300000 Instrument Air

Not selected.

400000 Component Cooling Water

X

A4.01 Ability to manually operate and/or

3.1/3.0

1

monitor in the control room: CCW indications

and control.

K/A Category Point Totals:

111111

1

2Ir 12

1

1 1 1 1 1

Group PointTotal:

-13

Revision 8

NUREG-1021

10 of 45

(

ES-401

BWR SRO Examination Outline

Form ES-401-1 (R8, Si)

Plant Systems - Tier 2/Group 3

System # / Name

K1

K2

K3

K4

K5

K6

Al

A2

A3

A4

G

K/A Topic(s)

Imp.

Point

e

201003 Control Rod and Drive Mechanism

Not selected.

215001 Traversing In-core Probe

Not selected.

233000 Fuel Pool Cooling and Cleanup

Not selected.

239001 Main and Reheat Steam

X

K4.04 Knowledge of MAIN AND

3.4/3.5

1

REHEAT STEAM SYSTEM design

feature(s) and/or interlocks which

provide for the following: limits steam

flow during a steam line rupture to 200%

256000 Reactor Condensate

Not selected.

268000 Radwaste

X

AI.01 Ability to predict and/or monitor

2.7/3.1

1

changes in parameters associated with

operating the RADWASTE controls

including: Radiation level.

288000 Plant Ventilation

X

A2.05 Ability to (a) predict the impacts

2.6/2.7

1

of the following on the PLANT

VENTILATION SYSTEMS; and (b)

based on those predictions, use

procedures to correct, control, or

mitigate the consequences of those

abnormal conditions or operations:

Extreme outside weather conditions.

290002 Reactor Vessel Internals

X

2.1.28 Knowledge of the purpose and

3.213.3

1

function of major system components

and controls.

K/A Category Point Totals:

1

i

Group Point Total:

4

Plant-Specific Priorities

System / Topic

Recommended Replacement for..

Reason

Point

s

/

(K

( K

Plant-Specific Pdority Total (limit 10):

I

NUREG-1021, Revision 8, Supplement 1

18 of 46

NUREG-1021

34 of 45

Revision 8

ES-401

Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-5 (R8, Si)

Facility:

IAA,*l

t

Date of Exam:

0 c-..r(&

&

2 -a6-t-

Exam Level: SRO

Category

K/A #

Topic

Imp.

Points

2.1.4*

Knowledge of shift staffing requirements.

2.3/3.4

1

2.1.22*

Ability to determine Mode of Operation.

2.8/3.3

1

Conduct of

2.1.29

Knowledge of how to conduct and verify valve lineups.

3.4/3.3

1

Operations

2.1.32

Ability to explain and apply system limits and precautions.

3.4/3.8

1

Total

4

2.2.1

Ability to perform pre-startup procedures for the facility /3.7/3.6

1

including operating those controls associated with plant

eqnuipment that could affect reactivity.

2.2.6*

Knowledge of the process for making changes in procedures as

2.3/3.3

1

described in the safety analyses report.

Equipment

2.2.27*

Knowledge of the refueling process.

2.6/3.5

1

2.2.32-

Knowledge of the effects of alterations on core configuration.

2.3/3.3

1

Total

4

2.3.1

Knowledge of 10 CFR:20 and related facility radiation control

2.6/3.0

1

requirements.

2.3.2

Knowledge of facility ALARA program.

2.5/2.9

1

2.3.3"

Knowledge of SRO responsibilities for auxiliary systems that are

1.8/2.9

1

outside the control room (e.g. waste disposal and handling

Radiation

systems).

Control

2.3.4*

Knowledge of radiation exposure limits and contamination

2.5/3.1

1

control I including permissible levels in excess of those

authorized.

Total

4

2.4.12

Knowledge of crew roles and responsibilities during EOP

3.4/3.9

1

flowchart use.

2.4.16

Knowledge of EOP implementation hierarchy and coordination

3.0/4.0

1

with other support procedures.

Emergency

2.4.43

Knowledge of emergency communication systems and

2.8/3.5

1

Procedures/

techniques

Plan

2.4.47

Ability to diagnose and recognize trends in an accurate and

3.4/3.7

1

timely manner utilizing the appropriate control room reference

material.

2.4.48-

Ability to interpret control room indications to verify the status

3.5/3.8

1

and operation of system / and understand how operator actions

and directives affect plant and system operation.

Total

5

Tier 3 Point Total (RO/SRO)

13/17

ES-401

Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-b (XU, 1)

Form ES-401-5 (R8, S51)

"*.*

ES-401

Generic Knowledge and Abilities Outline (Tier 3)

12116/99, MEE

WRITTEN EXAMINATION

SAMPLE PLAN DIFFERENCES

PWR

BWR

K/A

K/A TOPIC

RO

SRO

K/A

K/A TOPIC

RO

SRO

Tier

001A

ROD WDR

1/2

1/1

295003

LOSS AC

1/2

1/1

003A

DROP ROD

1/2

1/1

295005

MT TRIP

1/1

1/2

011E

LB LOCA

1/2

1/1

295013

HI SP TEMP

1/2

1/1

W/E04

LOCA

1/2

1/1

295016

CR ABAND

1/2

1/1

W/EO1

SI TERM

1/2

1/1

295017

OS REAL

1/2

1/1

027A

PPC MALF

1/1

1/2

295021

LOSS SDC

1/3

1/2

029E

ATWAS

1/2

1/1

295023

REFUEL AC

1/3

1/1

059A

LIQ RELS

1/2

1/1

295026

SP WTR TEM

1/2

1/1

065A

LOSS IA

1/3

1/2

295027

HI CONT TP.

1/2

1/1

295030

LO SP LVL

1/2

1/1

014

RPI

2/2

2/1

295032

HI SC TMP

1/3

1/2

026

CNT SPRAY

2/2

2/1

295035

SC DP

1/3

1/2

027

IODINE RVL

2/3

2/2

295036

SC HI SMP

1/3

1/2

028

H2 RECOMB

2/3

2/2

295038

OS REAL

1/2

1/1

034

FUEL HAND

2/3

2/2

201001

CRD HYDR

2/1

2/2

063

DC ELEC

2/2

2/1

201002

RMCS

2/1

2/2

103

CONT

2/3

2/2

215003

IRM

2/1

2/2

226001

C SPRAY

2/2

2/1

259001

FEEDWATER

2/1

2/2

262001

AC ELEC

2/2

2/1

290001

SEC CTMT

2/2

2/1

201003

CRD

2/2

2/3

234000

FUEL HAND

2/3

2/2

239001

MAIN STM

2/2

2/3

239003

MSIV LEAKG

2/3

2/2

256000

COND

2/2

2/3

ES-41

BWR RO Examination Outline.

Facility:

Date of Exam:

Exam Level: RO

K/A Category Points

Tier Group III

Point

K

A

G

Total

1

345

61

2

34

1.1

1

2

5

2

1

13

Emergency &

Abnormal

Plant

3

1

114

Evolutions

Tier

5

8

7

4

36

Totals

1

3

2

1

3

2

28

2.

2

3

2

1

2

1

2

1

19

Plant

Systems

3

1

4

Tier

5

3

5

6

5

4

51

__ Totals

-

I

3. Generic Knowledge and Abilities

Cat 1

Cat 2

Cat 3

Cat 4

4

/

3

2

4

13

Note:

1.

Ensure that at least two topics from every K/A 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 by +/-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 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.

6V

The generic K/As in Tiers I 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 SRO license level, and the point

totals for each system and category. K/As below 2.5 should be justified on

the basis of plant-specific priorities. Enter the tier totals for each category in

the table above.

Form ES-401-2 (R8, $1)

I::R-4(31

C

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, $1)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 1

E/APE # / Name / Safety Function

K1

K2

K3

Al

A2

G

K/A Topic(s)

Imp.

Point

s

295005 Main Turbine Generator Trip / 3

X

AAI.05 Abilit to operate and/or monitor the following as they apply to

3.6/3.6

1*

MAIN TURBINE GENERATOR TRIP: Reactor/turbine pressure regulating

system.

295006 SCRAM / 1

X

AK3.01 Knowledge of the reasons for the following responses as they

3.8/3.9

1 *

apply to SCRAM: Reactor water level response.

295007 High Reactor Pressure / 3

X

AAI.04 Ability to operate and/or monitor the following as they apply to

3.9/4.1

1 *

HIGH REACTOR PRESSURE: Safety/relief valve operation.

295009 Low Reactor Water Level / 2

X

AK1.05 Knowledge of the operational implications of the following

2*

concepts as they apply to LOW REACTOR WATER LEVEL: Natural

3.3/3.4

circulation.

2.4.1 knowledge of EOP entry conditions and immediate action steps.

295010 High Drywell Pressure/ 5X

AA2.02 Ability to determine and/or interpret the following as they apply to

3.8/3.9

1

HIGH DRYVE LL PRESSURE: Drywell pressure.

295014 Inadvertent Reactivity Addition / 1

X

AK2.03 Knowledge of the interrelations between INADVERTENT

3.3/3.4

1*

REACTIVITY ADDITION and the following: Fuel temperature.

295015 Incomplete SCRAM / 1

X

AA2.01 Abilityto determine and/or interpret the following as they apply to

4.1/4.3

1"

INCOMPLETE SCRAM: Reactor power.

295024 High Drywell Pressure / 5

X

EAI.04 Abilitto operate and/or monitor the following as they apply to

4.1/3.9

1"

HIGH DRYWELL PRESSURE: RHRILPCI.

295025 High Reactor Pressure / 3

X

EAI.07 Abili

to oprate and/or monitor the following as they apply to

4.1/4.1

1V

HIGH REAC OR

RESSURE: ARI/RPT/ATWS.

295031 Reactor Low Water Level / 2

Not selected.

295037 SCRAM Condition Present and Power

X

EK2.05 Knowledge of the interrelations between SCRAM CONDITION

4.0/4.1

2*

Above APRM Downscale or Unknown / 1

PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR

UNKNOWN and the following: CRD hydraulic system.

EK3.02 Knowledge of the reasons for the following responses as they

4.3/4.5

apply to SCRAM CONDITION PRESENT AND REACTOR POWER

ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC injection.

500000 High Containment Hydrogen Conc. / 5

X

EA1.01 Abili

to oerate and monitor the following as they apply to HIGH

3.4/3.3

1*

CONTAINM NT H DROGEN CONTROL: Primary containment

hydrogen instrumentation.

C

KJA Category Totals:

111 2 12

15 J 2 111 GroupPoint Total:

1 13

(

K

\\\\

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, SI)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2

E/APE #1 Name / Safety Function

K1

K2

K3

Al

A2

G

K/A Topic(s)

Imp.

Point

s

295001 Partial or Complete Loss of Forced Core

X

AK2.07 Knowledge of the interrelations between PARTIAL OR

3.4/3.4

1*

Flow Circulation / 1 & 4

COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the

following: Core flow indication.

295002 Loss of Main Condenser Vacuum / 3

X

2.1.2 Knowledge of operator responsibilities during all modes of plant

3.0/4.0

1

operation.

295003 Partial or Complete Loss of AC Pwr / 6

X

AK2.01 Knowledge of the interrelations between PARTIAL OR

3.2/3.3

1

COMPLETE LOSS OF A.C. POWER and the following: station

batteries.

295004 Partial or Complete Loss of DC Pwr /6

X

AK3.03 Knowledge of the reasons for the following responses as they

3.1/3.5

1

2pItI PARTIAL OR COMPLETE LOSS OF D.C. POWER: Reactor

295008 High Reactor Water Level / 2

X

AK3.01 Knowledge of the reasons for the following responses as they

3.4/3.5

1

apply to HIGH REACTOR WATER LEVEL: Main turbine trip.

295011 High CTMT Temperature / 5

Does not apply to Hatch. For Mark III containment only.

295012 High Drywell Temperature / 5

X

AAI.02 Ability to operate and/or monitor the following as they apply to

3.8/3.8

1*

HIGH DRYWELL TEMPERATURE: Drywell cooling system.

295013 High Suppression Pool Temp. /5

X

AKI.03 Knowledge of the operational implications of the following

3.0/3.3

2*

concepts as they apply to HIGH SUPPRESSION POOL

TEMPERATURE: Localized heating.

AK3.01 Knowledge of the reasons for the following responses as they

3.6/3.8

apply to HIGH SUPPRESSION POOL TEMPERATURE: Suppression

pool cooling operation.

295016 Control Room Abandonment / 7

X

AK3.01 Knowledge of the reasons for the following responses as they

4.1/4.2

1*

apply to CONTROL ROOM ABANDONMENT: Reactor SCRAM.

295017 High Off-site Release Rate / 9

Not selected.

295018 Partial or Complete Loss of CCW / 8

X

AK2.02 Knowledge of the interrelations between PARTIAL OR

3.4/3.6

1*

COMPLETE LOSS OF COMPONENT COOLING WATER and the

following: Plant operations.

295019 Part. or Comp. Loss of Inst. Air / 8

Not selected.

295020 Inadvertent Cont. Isolation / 5 & 7

X

2.1.31 Ability to locate control room switches / controls and indications

4.2/3.9

1

and to determine that they are correctly reflecting the desired plant

lineup.

295022 Loss of CRD Pumps / 1

X

2.1.30 Ability to locate and operate components / including local

3.9/3.4

1*

controls.

295026 High Suppression Pool Water Temp. / 5

X

EK2.04 Knowledge of the interrelations between SUPPRESSION

2.5/2.8

1*

POOL HIGH WATER TEMPERATURE and the following:

SPDS/ERIS/CRIDS/GDS.

295027 High Containment Temperature / 5

Does not apply to Hatch. Mark III containment only.

295028 High Drywell Temperature / 5

X

EK1.02 Knowledge of the operational implications of the following

2.9/3.1

1*

concepts as they apply to HIGH DRYWELL TEMPERATURE:

Equipment environmental qualification.

295029 High Suppression Pool Water Level/ 5

X

EK1.01 Knowledge of the operational implications of the following

3.4/3.7

1*

concepts as they apply to HIGH SUPPRESSION POOL WATER

LEVEL: Containment integrity.

295030 Low Suppression Pool Water Level/ 5

X

EK3.03 Knowledge of the reasons for the following responses as they

3.6/3.7

1*

apply to LOW SUPPRESSION POOL WATER LEVEL: RCIC operation.

295033 High Sec. Cont. Area Rad. Levels / 9

Not selected.

295034 Sec. Cont. Ventilation High Rad. / 9

Not selected.

295038 High Off-site Release Rate / 9

X

EK2.03 Knowledge of the interrelations between HIGH OFF-SITE

3.6/3.8

2*

RELEASE RATE and the following: Plant ventilation systems.

EA2.03 Ability to determine and/or interpret the following as they apply

to HIGH OF F-SITE RELEASE RATE: Radiation levels.

3.5/4.3

600000 Plant Fire On Site / 8

X

AA2.06 Ability to determine and interpret the following as they apply to

2.5/2.8

1"

PLANT FIRE ON SITE: Need for pressurizing control room

(recirculation mode).

K/A Category Point Totals:

J3 I

J5 I5 12

13 I Group Point Total:

9

K

C

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, $1)

Emergency and Abnormal Plant Evolutions -Tier I/Group 3

E/APE # / Name / Safety Function

K1

K2

K3

Al

A2

G

K/A Topic(s)

Imp.

Point

s

295021 Loss of Shutdown Cooling / 4

X

AK2.05 Knowledge of the interrelations between LOSS OF SHUTDOWN

2.7/2.8

1*

COOLING and the following: Fuel pool cooling and cleanup system.

295023 Refueling Accidents / 8

X

AK1.03 Knowledge of the operational implications of the following

3.7/4.0

1

concepts as they apply to REFUELING ACCIDENTS: Inadvertent

criticality.

295032 High Secondary Containment Area

X

EK3.03 Knowledge of the reasons for the followin responses as they

3.5/3.8

1*

Temperature / 5

apply to HIGH SECONDARY CONTAINMENT AR{A TEMPERATURE:

_mergency/normal depressurization.

295035 Secondary Containment High Differential

Not selected.

Pressure / 5

295036 Secondary Containment High Sump/Area

X

EA1.04 Ability to operate and/or monitor the following as they apply to

3.1/3.4

1"

Water Level / 5

SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL:

Radiation monitoring.

$

C

1K/A Category Point Totals:

I

1 1

1

Group Point Total:

7

4]

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, S1)1

Plant Systems - Tier 2/Group I 1

System #/ Name

K1

K2

K3

K4

K5

K

Al

A2

A3

A4

G

K/A Topic(s)

Imp.

Point

6

s

201001 CRD Hydraulic

X

K2.02 Knowledge of electrical power

3.6/3.7

2

supplies to the following: Scram vralve

so enoids.

2.1.28 Knowledge of the purpose and

3.2/3.3

function of major system components and

controls.

201002 RMCS

X

A3.03 Ability to monitor automatic operations

3.2/3.2

1*

of the REACTOR MANUAL CONTROL

SYSTEM including: rod drift alarm.

201005 RCIS

System does not apply to Hatch.

202002 Recirculation Flow Control

K3.05 Knowledge of the effect that a loss or

3.213.3

1

malfunction of the RECIRCULATION FLOW

CONTROL SYSTEM will have on the

following: Recirculation pump speed.

203000 RHRILPCI: Injection Mode

X

A1.01 Ability to predict and/or monitor

4.214.3

1*

changes in parameters associated with

operating the RHRILPCI: INJECTION MODE

controls including: Reactor water level.

206000 HPCI

X

K6.08 Knowledge of the effect that a loss or

3.8/3.8

1

malfunction of the following will have on the

HIGH PRESSURE COOLNT INJECTION

SYSTEM: Reactor pressure.

A2.16 Ability to (a)predict the impacts of the

4.0/4.1

1

followin on the HIGH PRESSURE

COOLANT INJECTION SYSTEM; and (b)

based on those predictions, use procedures

to correct, control, or mitigate the

consequences of those abnormal conditions

or operations: High drywell pressure.

207000 Isolation (Emerg.) Condenser

System does not apply to Hatch.

209001 LPCS

X

K5.01 Knowledge of the operational

2.6/2.7

2

implications of the following concepts as they

apply to LOW PRESSURECORE SPRAY

SYSTEM: Indications of pump cavitation.

2.4.31 Knowledge of annunciators alarms

3.3/3.4

and indications Iand use of the response

instructions.

209002 HPCS

System does not apply to Hatch.

211000 SLC

X

A3.04 Ability to monitor automatic operations

4.3/4.4

2*

of the STANDBY LIQUID CONTROL

SYSTEM including: Reactor power.

A4.01 Ability to manually operate and/or

3.9/3.9

monitor in the control room: Tank level.

212000 RPS

X

K4.06 Knowledge of REACTOR

3.0/3.0

1*

PROTECTION SYSTEM design feature(s)

and/or interlocks which provide for the

following: Select rod insertion.

A3.05 A i12 to monitor automatic operations

3.9/3.9

1

of the REACTOR PROTECTION SYSTEM

including; SCRAM instrument volume level.

(

$

215003 IRM

X

A4.05 Ability to manually operate and/or

3.413.4

monitor in the control room: Trip bypasses.

215004 SRM

X

K2.01 Knowledge of electrical power

2.6/2.8

supplies to the following: SRM

channels/detectors.

215005 APRM / LPRM

X

A2.03 Ability to (a) predict the impacts of the

3.6/3.8

1

followin on the AVERGE POWER RANGE

MONIT 8 R/LOCAL POWER RANGE

MONITOR SYSTEM; and (b) based on those

predictions, use procedures to correct,

control, or miti ate the consequences of

those abnormal conditions or operations:

Inoperative trip (all causes).

216000 Nuclear Boiler Instrumentation

X

K2.01 Knowledge of electrical power

2.8/2.8

1

supplies to the following: Analog trip system.

217000 RCIC

X

K1.01 Knowledge of the physical

3.5/3.5

1*

connections an oor cause-effect

relationships between REACTOR CORE

ISOLATION COOLING SYSTEM (RCOC) and

the following: Condensate storage and

transfer system.

218000 ADS

Not selected.

223001 Primary CTMT and Auxiliaries

X

A2.12 Ability to a predict the impacts of the

3.7/3.8

1*

following on the PRIMARY CONTAINMENT

SYSTEM AND AUXILIARIES; and (b) based

on those predictions, use procedures to

correct, control, or mitigate the

consequences of those abnormal conditions

or operations: Abnormal suppression pool

temperature.

223002 PCIS/Nuclear Steam Supply Shutoff

X

KI.07 Knowledge of the physical

3.4/3.6

1*

connections and/or cause-effect

relationships between PRIMARY

CONTAINMENT ISOLATION

SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF and the following: Reactor core

isolation cooling.

239002 SRVs

X

A1.01 Ability to predict and/or monitor

3.3/3.4

1*

changes in parameters associated with

opera Ing the RELIEF/SAFETY VALVES

controls including: Tail pipe temperature.

K6.05 Knowledge of the effect that a loss or

2.7/3.0

malfunction of the following will have on the

RELIEF/SAFETY VALVES: Vacuum breaker

operation.

241000 Reactor/Turbine Pressure Regulator

X

K6.05 Knowledge of the effect that a loss or

3.4/3.4

1

malfunction of the following will have on the

REACTOR/TURBINE PRESSURE

REGULATING SYSTEM: Condenser

vacuum.

259001 Reactor Feedwater

X

K1.05 Knowledge of the physical

3.2/3.2

connections and/or cause-effect

relationships between REACTOR

FEED WATER SYSTEM and the following:

Condensate system.

(,

(

C

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, S$)

I

Plant Systems - Tier 2/Group 2

System # / Name

K1

K2

K3

K4

K5

K6

Al

A2

A3

A4

G

K/A Topic(s)

Imp.

Point

s

201003 Control Rod and Drive Mechanism

Not selected.

201004 RSCS

Not selected.

201006 RWM

Not selected.

259002 Reactor Water Level Control

X

K3.02 Knowledge of the effect that a loss or

3.713.7

1*

malfunction of the REACTOR WATER

LEVEL CONTROL SYSTEM will have on the

following: Reactor feedwater system.

261000 SGTS

X

K4.01 Knowledge of STANDBY GAS

3.713.8

1*

TREATMENT SYSTEM design feature(s)

and/or interlocks which provide for the

following: Automatic system initiation.

264000 EDGs

X

K3.01 Knowledge of the effect that a loss or

4.2/4.4

2

malfunction of the EMERGENCY

GENERATORS will have on the following:

Emergency core cooling systems.

A1.01-Ability to predict and/or monitor

3.0/3.0

changes in parameters associated with

operating the EMERGENCY GENERATORS

controls including: Lube oil temperature.

K/A Category Point Totals:

13 13 13 12_Ii 13 13 13 13 12 12

Group Point Total:

28

K

(

C

202001 Recirculation

X

A1.07 Ability to predict and/or monitor

2.7/2.8

1*

changes in parameters associated with

operating the RECIRCULATION SYSTEM

controls including: Recirculation pump

speed.

204000 RWCU

X

K5.04 Knowledge of the operational

2.7/2.7

1

implications of the following concepts as they

a I to REACTOR WATER CLEANUP

SYSEM: Heat exchanger operation.

205000 Shutdown Cooling

X

K3.04 Knowledge of the effect that a loss or

3.7/3.7

1

malfunction of the SHUTDOWN COOLING

SYSTEM (RHR SHUTDOWN COOLING

MODE) will have on the following:

Recirculation loop temperatures.

214000 RPIS

X

K4.01 Knowledge of ROD POSITION

3.0/3.1

1"

INFORMATIOI4SYSTEM design feature(s)

and/or interlocks which provide for the

following: Reed switch locations.

215002 RBM

X

2.1.23 Ability to perform specific system and

3.9/4.0

1

integrated plant procedures during different

modes of plant operation.

219000 RHRJLPCI: Torus/Pool Cooling Mode

X

A2.08 Ability to a predict the impacts of the

2.8/3.1

1*

following on the RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING

MODE; and (b) based on those predictions,

use procedures to correct, control, or

mitigate the consequences of those

abnormal conditions or operations: Pump

seal failure.

226001 RHR/LPCI: CTMT Spray Mode

X

K2.02 Knowledge of electrical power

2.9/2.9

1*

supplies to the following: Pumps.

230000 RHR/LPCI: Torus/Pool Spray Mode

Changed to 272000K2.05 due to KA

selected was the same as 226001K2.02.

239001 Main and Reheat Steam

X

K4.04 Knowledge of MAIN AND REHEAT

3.4/3.5

1"

STEAM SYSTEM design feature(s) and/or

interlocks which provide for the following:

limits steam flow during a steam line rupture

to 200%.

245000 Main Turbine Gen. and Auxiliaries

X

K1.09 Knowledge of the physical

2.7/2.7

1

connections and/or cause-effect

relationships between MAIN TURBINE

GENERATOR AND AUXILIARY SYSTEMS

and the following: D.C. electrical distribution.

256000 Reactor Condensate

X

K1.05 Knowledge of the physical

3.1/3.1

connections and/or cause-effect

relationships between REACTOR

CONDENSATE SYSTEM and the following:

CRD hydraulic system.

262001 AC Electrical Distribution

X

A4.02 Ability to manually operate and/or

3.4/3.4

1*

monitor in the control room: Synchroscope,

including understanding of running and

incoming voltages.

I

(

(K

262002 UPS (AC/DC)

Not selected.

263000 DC Electrical Distribution

X

K3.01 Knowledge of the effect that a loss or

3.4/3.8

1*

malfunction of the D.C. ELECTRICAL

DISTRIBUTION will have on the following:

Emergency generators.

271000 Offgas

X

K4.08 Knowledge of OFFGAS SYSTEM

3.1/3.3

1

design feature(s) and/or interlocks which

provide for the following: Automatic system

isolation.

272000 Radiation Monitoring

X

K2.05 Knowledge of electrical power

2.6/2.9

1*

supplies to the following: Reactor building

ventilation monitors.

286000 Fire Protection

X

A1.01 Ability to predict and/or monitor

2.9/2.9

1*

changes in parameters associated with

operating the FIRE PROTECTION SYSTEM

controls including: System pressure.

290001 Secondary CTMT

X

A3.01 Ability to monitor automatic operations

3.9/4.0

1"

of the SECONDARY CONTAINMENT

including: Secondary containment isolation.

290003 Control Room HVAC

X

K5.02 Knowledge of the operational

2.8/2.8

1"

implications of the following concepts as they

apply to CONTROL ROOM HVAC:

Differential pressure control.

300000 Instrument Air

X

K6.12 Knowledge of the effect that a loss or

2.9/2.9

1

malfunction of the following will have on the

INSTRUMENT AIR SYSTEM: Breakers,

relays and disconnects.

400000 Component Cooling Water

X

A4.01 Ability to manually operate and/or

3.1/3.0

1*

monitor in the control room: CCW indications

and control.

EKA Category Point Totals:

2

2 I2 13 l

2

I

1 1 L

.2 I

1.1 2 lI

Group PointTotal:

119

C

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, Si)

Plant Systems -Tier 2/Group 3

System # / Name

KI

K2

K3

K4

K5

K6

Al

A2

A3

A4

G

K/A Topic(s)

Imp.

Point

S

215001 Traversing In-core Probe

Not selected.

233000 Fuel Pool Cooling and Cleanup

Not selected.

234000 Fuel Handling Equipment

X

K6.02 Knowledge of the effect that a loss or

2.8/3.5

1

malfunction of the following will have on the

FUEL HANDLING EQUIPMENT: Reactor

manual control system.

239003 MSIV Leakage Control

Does not apply to Hatch.

268000 Radwaste

X

A1.01 Ability to predict and/or monitor

2.7/3.1

1*

changes in parameters associated with

operating the RADWASTE controls

including: Radiation level.

288000 Plant Ventilation

X

A2.05 Ability to (a) predict the impact of the

2.6/2.7

1*

following on the PLNT VENTILATION

SYSTEMS; and (b) based on those

predictions, use procedures to correct,

control, or mitigate the consequences of

those abnormal conditions or operations:

Extreme outside weather conditions.

290002 Reactor Vessel Internals

X

2.1.28 Knowledge of the purpose and

3.2/3.3

1*

function of major system components and

controls.

K/A Category Point Totals:

1 I 1 i+/-1 IIL i

Group Point Total:

Plant-Specific Priorities

System / Topic

Recommended Replacement for...

Reason

Point

S

(/

K

Plant-Specific Priority Total: (limit 10)

I

Facility:

j4

____

Date of Exam: OcM6(.'- .- Zo

t-7-

Exam Level: RO

ML023400182

Text

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