Text

Feb-Mar 05000259/2008301 Exam Draft Written Exam Outlines
	ML081370266
Person / Time
Site:	Browns Ferry
Issue date:	04/08/2008
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-259/08-301 50-259/08-301
	Download: ML081370266 (15)
	v • d • e

Draft Submittal

(Pink Paper)

ti;

DRAFT Written Exam Quality Checklist (ES-401-6)

vi &Written Exam Sample Plan

ES-401

Written Examination Quality Checklist

Form ES-401-6

Facility: Browns Ferry

Date of Exam: 2/25/2008

Exam Level: RO ~ SRO 0

Initial

Item Description

a

b*

4.

The sampling process was random and systematic (If more than 4 RO or 2 SRO questions

were repeated from the last 2 NRC licensing exam, consult the NRR OL program office).

3.

SRO questions are appropriate in accordance with Section D.2.d of ES-401

Date

1/8/2008

18

New

CIA

47

62.6%

8

Modified

28

37.40/0

Memo

49

Bank

Bank use meets limits (no more than 75 percent

from the bank, at least 10 percent new, and the rest

new or modified); enter the actual RO / SRO-only

question distribution(s) at right.

Between 50 and 60 percent of the questions on the RO

exam are written at the comprehension /analysis level;

the SRO exam may exceed 60 percent if the randomly

selected KAs support the higher cognitive levels; enter

the actual RO / SRO question distribution(s) at right.

2.

a. NRC KlAs are referenced for all questions.

b. Facility learning objectives are referenced as available.

1.

Questions and answers are technically accurate and applicable to the facility.

5.

Question duplication from the license screening/audit exam was controlled

as indicated below (check the item that applies) and appears appropriate:

~ the audit exam was systematically and randomly developed; or

_ the audit exam was completed before the license exam was started; or

~ the examinations were developed independently; or

~ the licensee certifies that there is no duplication; or

_other (explain)

11.

The exam contains the required number of one-point, multiple choice items;

the total is correct and agrees with value on cover sheet

10.

Question psychometric quality and format meet the guidelines in ES Appendix B.

7.

6.

9.

Question content conforms with specific KIA statements in the previously approved

examination outline and is apprcoriate for the Tier to which they are assigned;

deviations are justified

8.

References/handouts provided do not give away answers

or aid in the elimination of distractors.

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor

Note:

The facility reviewer's initials/signature are not applicable for NRGdeveloped examinations.

Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.

ES-401, Page 29 of 33

ES-401

Written Examination Quality Checklist

Form ES-401-6

Facility: Browns Ferry

Date of Exam: 2/25/2008

Exam Level: RO D SRO C8J

Initial

Item Description

a

b*

4.

The sampling process was random and systematic (If more than 4 RO or 2 SRO questions

were repeated from the last 2 NRC licensing exam, consult the NRR OL program office).

1.

Questions and answers are technically accurate and applicable to the facility.

Date

1/8/2008

11

New

CIA

22

88°~

2

Modified

3

120/0

Memo

12

Bank

E. Robert Scillian

Between 50 and 60 percent of the questions on the RO

exam are written at the comprehension /analysis level;

the SRO exam may exceed 60 percent if the randomly

selected KAs support the higher cognitive levels; enter

the actual RO / SRO question distribution(s) at right.

Bank use meets limits (no more than 75 percent

from the bank, at least 10 percent new, and the rest

new or modified); enter the actual RO / SRO-only

question distribution(s) at right.

11.

The exam contains the required number of one-point, multiple choice items;

the total is correct and agrees with value on cover sheet

10.

Question psychometric quality and format meet the guidelines in ES Appendix B.

6.

8.

References/handouts provided do not give away answers

or aid in the elimination of distractors.

9.

Question content conforms with specific KIA statements in the previously approved

examination outline and is appropriae for the Tier to which they are assigned;

deviations are justified

2.

a. NRC KlAs are referenced for all questions.

b. Facility learning objectives are referenced as available.

3.

SRO questions are appropriate in accordance with Section D.2.d of ES-401

5.

Question duplication from the license screening/audit exam was controlled

as indicated below (check the item that applies) and appears appropriate:

~ the audit exam was systematically and randomly developed; or

_ the audit exam was completed before the license exam was started; or

~ the examinations were developed independently; or

~ the licensee certifies that there is no duplication; or

_other (explain)

7.

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor

Note:

The facility reviewer's initials/signature are not applicable for NRGdeveloped examinations.

Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.

ES-401, Page 29 of 33

ES-401

Written Examination Outline

Form ES-401-1

.(

Facility:

0610 NRC Exam Outline

Date ofExam: 02/25/2008

RO KIA Category Points

SRO-Only Points

Tier

Group

K

A

G

Total

A2

G*

Total

1

2

3

4

5

6

1

2

3

4

1.

1

3

4

20

4

3

7

Emergency

2

1

2

1

7

1

2

3

&

Plant

Tier

Evolutions

Totals

4

6

5

27

5

10

1

2

3

2

3

2

26

3

2

5

2.

Plant

2

1

2

1

12

0

2

1

3

Systems

Tier

Totals

3

4

3

4

3

4

3

38

5

3

8

3. Generic Knowledge & Abilities

1

2

3

4

1

2

3

4

10

7

Categories

3

2

3

1

2

Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and

SRO-only outlines (i.e., except for one category in Tier 3 ofthe SRO-only outline, the "Tier Totals" in each KIA

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 +/-l from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not

apply at the facility should be deleted and justified; operationally important, site-specific systems that are not

included on the outline should be added. Refer to section D.l.b ofES-401, for guidance regarding elimination of

inappropriate KIA statements.

4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group

before selecting a second topic for any system or evolution.

5.

Absent a plant specific priority, only those KAs having an importance rating (IR) of2.5 or higher shall be

selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

L

6.

Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.

7.*

The generic (G) KIAs in Tiers I and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be

relevant to the applicable evolution or system. Refer to Section D.I .b ofES-401 for the applicable KIA's

8.

On the following pages, enter the KIA numbers, a briefdescription ofeach topic, the topics' importance ratings

(IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and

tier totals for each category in the table above. Iffuel handling equipment is sampled in other than Category A2 or

G* on the SRO-only exam, enter it on the left side ofColumn A2 for Tier 2, Group 2 (Note #1 does not apply).

Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 ofthe KIA Catalog, and enter the KIA numbers, descriptions, IRs, and

point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to IOCFR55.43

ES-401

2

0610 NRC Exam Outline

Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

Form ES-401-1

I EAPE # I Name Safety Function

K1

K2

K3 I A1 I A2 I G

KJA Topic(s)

Imp. I Q# I

c

(

AA2.01 - Abilityto determineand/orinterpret

295006SCRAM11

X

the followingas they applyto SCRAM:

4.6

76

Reactorpower

AA2.07 - Abilityto determineand/orinterpret

295021LossofShutdownCoolingI 4

X

the followingas they applyto LOSSOF

3.1

77

SHUTDOWN COOLING: Reactor

recirculation flow

2.1.28- Conductof OperationsKnowledge of

295024HighDrywellPressureI 5

X

the purposeand functionof majorsystem

3.3

78

componentsand controls.

EA2.01 - Abilityto determineand/orinterpret

295026SuppressionPool High Water

X

the followingas they applyto SUPPRESSION

4.2

79

Temp. 15

POOLHIGH WATERTEMPERATURE:

Suppressionpool watertemperature

EA2.05 - Abilityto determineand/orinterpret

295037SCRAMConditionPresent

the followingas they applyto SCRAM

and PowerAbove APRM Downscale

X

CONDITION PRESENTANDREACTOR

4.3

80

or Unknown11

POWERABOVEAPRMDOWNSCALE OR

UNKNOWN: Controlrod position

2.2.22 - EquipmentControlKnowledge of

295038High Off-siteReleaseRate19

X

limitingconditionsfor operationsand safety

4.1

81

limits.

2.2.24 - EquipmentControlAbilityto analyze

600000Plant Fire On-siteI 8

X

the affect of maintenance activitieson LCO 3.8

82

status.

295001Partial or CompleteLoss of

2.1.14 - Conductof OperationsKnowledgeof

ForcedCore FlowCirculationII & 4

X

systemstatus criteriawhichrequirethe

2.5

39

notificationof plantpersonnel.

AK3.01 - Knowledgeof the reasonsforthe

29500I Partial or CompleteLoss of

followingresponsesas they applyto PARTIAL

ForcedCoreFlow CirculationII & 4

X

OR COMPLETELOSS OF FORCEDCORE

3.4

40

FLOWCIRCULATION : Reactorwaterlevel

response

AA2.01 - Abilityto determineand/orinterpret

295003Partial or CompleteLossof

X

the followingas they applyto PARTIALOR

3.4

41

AC/6

COMPLETELOSS OF AC. POWER: Cause

of partial or completeloss of AC. power

AKI.03 - Knowledgeof the operational

295004Partial or TotalLoss of DC

implicationsof the followingconceptsasthey

Pwr/6

X

applyto PARTIALOR COMPLETE LOSSOF

2.9

42

D.C. POWER: Electricalbus divisional

separation

AA1.04 - Abilityto operate and/or monitor

295005Main TurbineGeneratorTrip I

X

the following as they apply to MAIN

2.7

43

3

TURBINE GENERATOR TRIP : Main

generator controls

AK3.05 - Knowledge of the reasons for the

295006SCRAMI 1

X

following responses as they apply to

3.8

44

SCRAM : Direct turbine generator trip:

Plant-5pecific

AA2.04 - Abilityto determine and/or

295016ControlRoom AbandonmentI

X

interpret the following as they apply to

3.9

45

7

CONTROL ROOM ABANDONMENT :

Suppression pool temoerature

AK2.01 - Knowledge of the interrelations

295018Partial or TotalLoss ofCCW I

X

between PARTIALOR COMPLETE LOSS

3.3

46

8

OF COMPONENT COOLINGWATER and

the following: System loads

295019Partial or TotalLoss ofInst.

X

AA2.02 - Ability to determine and/or

3.6

47

Air I 8

interpret the followingas they apply to

ES-401

2

0610 NRC Exam Outline

Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

Form ES-401-1

I EAPE # I Name Safety Function

I K1 I K2 I K3 I A1 I A2 I G I

KIA Topic(s)

Imp. I Q# I

(

PARTIAL OR COMPLETE LOSS OF

INSTRUMENT AIR: Status of safety-

related instrument air system loads (see

""

AK2.1 - AK2.19)

2.4.50 - Emergency Procedures I Plan

295021LossofShutdownCooling I 4

X

Ability to verify system alarm setpoints and

3.3

48

operate controls identified in the alarm

I'"

response manual.

AK1.02 - Knowledge of the operational

295023Refueling Ace Cooling Mode I

X

implications of the following concepts as

3.2

49

8

they apply to REFUELING ACCIDENTS :

Shutdown margin

2.1.33 - Conduct of Operations Ability to

295024High DrywelI Pressure I 5

X

recognize indications for system operating

3.4

50

parameters which are entry-level

'"

conditions for technical specifications.

EK2.08 - Knowledge of the interrelations

295025High ReactorPressure 13

X

between HIGH REACTOR PRESSURE

3.7

51

and the following: Reactor/turbine pressure

regulating system: Plant-Specific

EA2.01 - Ability to determine and/or

295026Suppression Pool High Water

interpret the following as they apply to

X

SUPPRESSION POOL HIGH WATER

4.1

52

Temp.15

TEMPERATURE: Suppression pool water

temperature

~

EK3.04 - Knowledge of the reasons for the

295028High DrywelI Temperature I 5

X

following responses as they apply to HIGH

3.6

53

DRYWELL TEMPERATURE: Increased

drywell cooling

EA1.06 - Ability to operate and/or monitor

295030Low Suppression Pool Water

"

the following as they apply to LOW

X

SUPPRESSION POOL WATER LEVEL:

3.4

54

Levell 5

'"

Condensate storage and transfer (make-up

to the suppression pool): Plant-Specific

~

2.4.6 - Emergency Procedures I Plan

295031 ReactorLow WaterLevel/2

X

Knowledge symptom based EOP

3.1

55

'"

mitigation strateg ies.

EK2.11 - Knowledge of the interrelations

295037SCRAM Condition Present

between SCRAM CONDITION PRESENT

andPowerAbove APRM Downscale

X

WI

AND REACTOR POWER ABOVE APRM

3.8

56

or Unknown 11

~

DOWNSCALE OR UNKNOWN and the

following : RMCS: Plant-Specific

EK1.01 - Knowledge of the operational

~,

implications of the following concepts as

295038High Off-site Release Rate19

X

they apply to HIGH OFF-SITE RELEASE

2.5

57

RATE : Biological effects of radioisotope

inaestion

"

AA 1.08 - Ability to operate and I or monitor

600000PlantFire On-siteI 8

X

the follOWing as they apply to PLANT FIRE

2.6

58

ON SITE: Fire fighting equipment used on

each class of fire

KIA CategoryTotals:

3

8

7

Group Point Total:

I

20/7

ES-401

3

0610 NRC Exam Outline

Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 2

Form ES-401-1

I EAPE # / Name Safety Function

K1

K2

K3

A1

A2

G

KIA Topic(s)

Imp. I Q# I

(

2.4.6 - Emergency Procedures I Plan

295002 Loss ofMain Condenser Vac 13

X

Knowledge symptom based EOP mitigation

4.0

83

strategies.

2.4.31 - Emergency Procedures I Plan

295009 Low Reactor Water Level 12

X

Knowledge ofannunciators alarms and

3.4

84

indications, and use of the response instructions.

EA2.02 - Ability to determine and I or interpret

500000 High CTMT Hydrogen Cone,I

the following as they apply to HIGH

X

PRIMARY CONTAINMENT HYDROGEN

3.5

85

5

CONCENTRATIONS: Oxygen monitoring

system availabilitv

AK2.01 - Knowledge ofthe interrelations

295009 Low Reactor Water Level 12

X

between LOW REACTOR WATER LEVEL

3.9

59

and the following: Reactor water level indication

2.2.22 - Equipment Control Knowledge of

295012 High Drywell Temperature 15

X

limiting conditions for operations and safety

3.4

60

limits.

AK1.02 - Knowledge ofthe operational

295015 Incomplete SCRAM /1

X

implications ofthe following concepts as they

3.9

61

apply to INCOMPLETE SCRAM: (CPR 41.8 to

41.10) Cooldown effects on reactor DOwer

AKJ.08 - Knowledge ofthe reasons for the

295020 Inadvertent Cont. Isolation I 5 &

following responses as they apply to

7

X

INADVERTENT CONTAINMENT

3.3

62

ISOLATION: Suppression chamber pressure

response

EA1.01 - Ability to operate and/or monitor the

295032 High Secondary Containment

X

following as they apply to HIGH SECONDARY

3.6

63

Area Temperature 15

CONTAINMENT AREA TEMPERATURE :

Area temperature monitorinz svstem

EA2.01 - Ability to determine and/or interpret

295033 High Secondary Containment

X

the following as they apply to HIGH

3.8

64

Area Radiation Levels 19

SECONDARY CONTAINMENT AREA

RADIATION LEVELS: Area radiation levels

EA2.02 - Ability to determine and/or interpret

295035 Secondary Containment High

the following as they apply to SECONDARY

Differential Pressure I 5

X

CONTAINMENT HIGH DIFFERENTIAL

2.8

65

PRESSURE: Off-site release rate: Plant-

Specific

KIA Category Totals:

1

3

Group Point Total:

I

7/3

(

ES-401

4

0610 NRC Exam Outline

Written Examination Outline

Plant Systems - Tier 2 Group 1

Form ES-401-1

(

System # / Name

K

A

G

Imp.

Q#

1

2

3

4

5

6

1

2

3

4

A2.16 - Abilityto (a) predictthe impacts

of the following on the RHRILPCI:

INJECTION MODE(pLANTSPECIFIC) ;

203000RHRILPCI: Injection

X

and (b) basedon thosepredictions, use

4.5

86

Mode

procedures to correct, control, or mitigate

the consequences of thoseabnormal

conditions or operations: Lossof coolant

accident

2.1.14- Conductof Operations Knowledge

215003lRM

X

of systemstatuscriteriawhichrequire the

3.3

87

notification of plantpersonnel.

2.l.23 - Conductof Operations Abilityto

259002ReactorWaterLevel

X

performspecificsystemand integrated

4.0

88

Control

plantprocedures duringall modesof plant

operation.

A2.06- Abilityto (a) predictthe impacts

of the following on the SHUTDOWN

COOLING SYSTEM(RHR SHUTDOWN

259002ReactorWaterLevel

X

COOLING MODE); and (b) basedon

3.5

89

Control

thosepredictions, useprocedures to correct,

control, or mitigatethe consequences of

thoseabnormal conditions SOCIRHR

pumptrips

A2.12 - Abilityto (a) predictthe impacts

of thefollowing on the REACTOR

PROTECTION SYSTEM; and(b) based

259002ReactorWaterLevel

X

on thosepredictions, useprocedures to

4.1

90

Control

correct, control, or mitigatethe

consequences of thoseabnormal conditions

or operations: Mainturbinestopcontrol

valveclosure

Al.OI - Abilityto predictand/ormonitor

203000RHRILPCI: Injection

changes in parameters associated with

Mode

X

operating theRHRILPCI: INJECTION

4.2

I

MODE(pLANTSPECIFIC) controls

including: Reactorwaterlevel

K4.02 - KnOWledge of SHUTDOWN

COOLING SYSTEM (RHR

205000Shutdown Cooling

X

SHUTDOWNCOOLINGMODE)

3.7

2

design feature(s) and/or interlocks

which provide for the following: High

pressure isolation: Plant-Specific

K6.09 - Knowledge of the effect that a

loss or malfunction of the follOWing will

206000HPCI

X

have on the HIGHPRESSURE

3.5

3

COOLANTINJECTIONSYSTEM :

Condensate storage and transfer

system: BWR-2,3,4

K5.04 - Knowledge of the operational

implications of the following concepts

209001 LPCS

X

as they apply to LOWPRESSURE

2.8

4

CORE SPRAY SYSTEM : Heat

removal (transfer) mechanisms

211000SLC

X

K2.01 - Knowledge of electrical power

2.9

5

supplies to the following: SBLC pumps

(

ES-401

4

0610 NRC Exam Outline

Written Examination Outline

Plant Systems - Tier 2 Group 1

Form ES-401-1

(

System # / Name

K

A

G

Imp.

Q#

1

2

3

4

5

6

1

2

3

4

K6.03 - Knowledge of the effect that a

loss or malfunction of the following will

212000RPS

X

have on the REACTOR PROTECTION

3.5

6

SYSTEM: Nuclear boiler

instrumentation

A4.04 - Ability to manually operate

215003 IRM

X

and/or monitor in the control room: IRM

3.1

7

back panel switches , meters, and

indicating lights

A3.03 - Ability to monitor automatic

215004 Source Range Monitor

X

operations of the SOURCE RANGE

3.6

8

MONITOR (SRM) SYSTEM including:

RPS status

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

of the following on the AVERAGE

POWER RANGE MONITOR/LOCAL

POWER RANGE MONITOR SYSTEM ;

215005 APRM / LPRM

X

and (b) based on those predictions, use

3.6

9

procedures to correct, control, or

mitigate the consequences of those

abnormal conditions Inoperative trip (all

causes)

K2.03 - Knowledge of electrical power

217000 RCIC

X

supplies to the following: RCIC flow

2.7

10

controller

K1.05 - Knowledge of the physical

connections and/or cause- effect

218000 ADS

X

relationships between AUTOMATIC

3.9

11

DEPRESSURIZATION SYSTEM and

the following: Remote shutdown

system : Plant-5pecific

2.1.24 - Conduct of Operations Ability

218000 ADS

X

to obtain and interpret station electrical

2.8

12

and mechanical drawings.

A2.06 - Ability to (a) predict the impacts

of the following on the PRIMARY

CONTAINMENT ISOLATION

223002 PCISlNuclear Steam

SYSTEM/NUCLEAR STEAM SUPPLY

Supply Shutoff

X

SHUT-oFF; and (b) based on those

3.0

13

predictions, use procedures to correct,

control , or mitigate the consequences

of those abn cond or ops. Containment

instrumentation failures

A3.01 - Ability to monitor automatic

operations of the PRIMARY

223002 PCISlNuciear Steam

X

CONTAINMENT ISOLATION

3.4

14

Supply Shutoff

SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF including: System

indicatinQ IiQhtsand alarms

A3.03 - Ability to monitor automatic

239002SRVs

X

operations of the RELIEF/SAFETY

3.6

15

VALVES including: Tail pipe

temoeratures

A4.08 - Ability to manually operate

239002SRVs

X

and/or monitor in the control room:

3.2

16

Plant air system pressure: Plant-

Specific

(

ES-401

4

0610 NRC Exam Outline

Written Examination Outline

Plant Systems - Tier 2 Group 1

Form ES-401-1

(

System # / Name

K

A

G

Imp.

Q#

1

2

3

4

5

6

1

2

3

4

A4.03 - Ability to manually operate

259002 Reactor Water Level

and/or monitor in the control room: All

Control

X

individual component controllers when

3.8

17

transferring from manual to automatic

modes

K3.06 - Knowledge of the effect that a

loss or malfunction ofthe STANDBY

261000 SGTS

X

GAS TREATMENT SYSTEM will have

3.0

18

on following: Primary containment

oxygen content: Mark-I&II

K4.04 - Knowledge of A.C.

262001 AC Electrical

ELECTRICAL DISTRIBUTION design

Distribution

X

feature(s) and/or interlocks which

2.8

19

provide for the following: Protective

relavina

A1.02 - Ability to predict and/or monitor

changes in parameters associated with

262002 UPS (ACIDC)

X

operating the UNINTERRUPTABLE

2.5

20

POWER SUPPLY (A.C.ID.C.) controls

including: Motor generator outputs

K1.02 - Knowledge of the physical

263000 DC Electrical

connections and/or cause- effect

Distribution

X

relationships between D.C.

3.2

21

ELECTRICAL DISTRIBUTION and the

following: Battery charger and battery

K5.06 - Knowledge of the operational

implications of the following concepts

264oooEOOs

X

as they apply to EMERGENCY

3.4

22

GENERATORS (DIESEUJET): Load

secuencina

K2.02 - Knowledge of electrical power

300000 Instrument Air

X

supplies to the following: Emergency

3.0

23

air compressor

K3.01 - Knowledge of the effect that a

loss or malfunction of the

300000 Instrument Air

X

(INSTRUMENT AIR SYSTEM) will

2.7

24

have on the following: Containment air

svstem

2.4.31 - Emergency Procedures / Plan

400000 Component Cooling

X

Knowledge of annunciators alarms and

3.3

25

Water

indications, and use of the response

instructions.

A2.02 - Ability to (a) predict the impacts

of the following on the CCWS and (b)

400000 Component Cooling

based on those predictions, use

Water

X

procedures to correct, control, or

2.8

26

mitigate the consequences of those

abnormal operation: High/low surge

tank level

KJA Category Totals :

2

3

2

6

3

4

Group Point Total:

I 26/5

(

ES-401

5

0610 NRC Exam Outline

Written Examination Outline

Plant Systems - Tier 2 Group 2

Form ES-401-1

(

System # I Name

K

A

G

Imp.

Q#

1

2

3

4

5

6

1

2

3

4

A2.01- Abilityto (a)predictthe impacts

ofthe following on the RADWASTE ; and

268000Radwaste

X

(b)basedon thosepredictions, use

3.5

91

procedures to correct, control, or mitigate

the consequences of thoseabnormal

conditions or operations: System rupture

2.4.36- Emergency Procedures I Plan

271000Off-gas

X

Knowledge of chemistry I healthphysics

2.8

92

tasksduringemergency operations.

A2.03 - Abilityto (a)predictthe impacts

ofthefollowing on the PLANT

VENTILATION SYSTEMS;and(b)

288000PlantVentilation

X

basedon thosepredictions, useprocedures

3.7

93

to correct, control, or mitigate the

consequences of thoseabnormal conditions

or operations: Lossof coolantaccident:

Plant-Specific

10.03 - Knowledge of the effectthata

201003 Control RodandDrive

X

lossormalfunction ofthe CONTROL

3.2

27

Mechanism

RODANDDRIVEMECHANISM will

haveon following: Shutdown margin

K4.09- Knowledge of RODWORTH

MINIMIZER SYSTEM (RWM) (pLANT

20loo6RWM

X

SPECIFIC) designfeature(s) and/or

3.2

28

interlocks whichprovide forthefollowing:

System initialization: P-Soec(Not-BWR6)

K6.09 - Knowledge ofthe effectthata

20200I Recirculation

X

lossor malfunction ofthefollowing will

3.4

29

haveonthe RECIRCULATION SYSTEM

Reactorwaterlevel

A1.01 - Ability to predict and/or monitor

changes in parameters associated with

215001 Traversing In-coreProbe

X

operating the TRAVERSING IN-CORE

2.8

30

PROBE controls including:Radiation

levels: (Not-BWR1)

K1.10 - Knowledge of the physical

connections and/or cause- effect

216000NuclearBoilerInst.

X

relationships between NUCLEAR

3.2

31

BOILERINSTRUMENTATION and the

following: Recirculation flowcontrol

svstem

219000RHRILPCI: TorusIPool

X

K2.02 - Knowledge of electrical power

3.1

32

CoolingMode

supplies to the followina: Pumps

226001 RHRILPCI: CTMTSpray

A4.12 - Ability to manually operate

X

and/or monitor inthe control room:

3.8

33

Mode

Containmentldrywell pressure

2.4.50 - Emergency Procedures I Plan

234000FuelHandling Equipment

X

Ability to verifysystem alarm setpoints

3.3

34

and operate controls identifiedin the

alarm response manual.

K6.04- Knowledge of the effect that a

loss or malfunction of the following will

245000MainTurbineGen.I Aux.

X

have on the MAIN TURBINE

2.6

35

GENERATORANDAUXILIARY

SYSTEMS : Hydrogen cooling

(

ES-401

5

0610 NRC Exam Outline

Written Examination Outline

Plant Systems - Tier 2 Group 2

Form ES-401-1

(

System # I Name

K

A

G

Imp.

Q#

1

2

3

4

5

6

1

2

3

4

A2.01 - Ability to (a) predict the

impacts of the following on the

RADWASTE ; and (b) based on those

268000Radwaste

X

predictions, use procedures to correct,

2.9

36

control , or mitigate the consequences

of those abnormal conditions or

ooerations: SYStemruoture

K5.01 - Knowledge of the operational

implications of the following concepts

272000RadiationMonitoring

X

as they apply to RADIATION

3.2

37

MONITORING SYSTEM : Hydrogen

injection operation's effect on process

radiation indications: Plant-5oecific

A3.01 - Ability to monitor automatic

290003ControlRoomHVAC

X

operations of the CONTROL ROOM

3.3

38

HVAC inclUding:

Initiationlreconfiguration

KIA CategoryTotals:

1

2

1

3

1

2

GroupPointTotal:

I

1213

ES-401

Generic Knowledge and Abilities Outline (Tier3)

Form ES-401-3

(

Facility:

0610 NRC Exam Outline

Date:

K/A#

Topic

RO

SRO-Only

ML081370266

Text

Navigation menu

Search