ML081370266

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)

See also: IR 05000259/2008301

Text

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*

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

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

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).

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)

6. Bank use meets limits (no more than 75 percent Bank Modified New

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

new or modified); enter the actual RO / SRO-only 49 8 18

question distribution(s) at right.

7. Between 50 and 60 percent of the questions on the RO Memo CIA

exam are written at the comprehension /analysis level;

the SRO exam may exceed 60 percent if the randomly 28 47

selected KAs support the higher cognitive levels; enter 37.40/0 62.6%

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

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 apprcoriate for the Tier to which they are assigned;

deviations are justified

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

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

the total is correct and agrees with value on cover sheet

Date

a. Author 1/8/2008

b. Facility Reviewer (*) 1/8/2008

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor

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

1. 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*

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

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

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).

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)

6. Bank use meets limits (no more than 75 percent Bank Modified New

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

new or modified); enter the actual RO / SRO-only 12 2 11

question distribution(s) at right.

7. Between 50 and 60 percent of the questions on the RO Memo CIA

exam are written at the comprehension /analysis level;

the SRO exam may exceed 60 percent if the randomly 3 22

selected KAs support the higher cognitive levels; enter 120/0 88°~

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

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

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

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

the total is correct and agrees with value on cover sheet

Date

a. Author 1/8/2008

b. Facility Reviewer (*) E. Robert Scillian 1/8/2008

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor

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

1. 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 of Exam: 02/25/2008

RO KIA Category Points SRO-Only Points

Tier Group K K K K K K A A A A G

Total A2 G* Total

1 2 3 4 5 6 1 2 3 4 *

1. 1 3 3 3 3 4 4 20 4 3 7

Emergency

& 2 1 1 1 1 2 1 7 1 2 3

Plant

Tier

Evolutions 4 4 4 4 6 5 27 5 5 10

Totals

1 2 3 2 2 2 2 2 3 3 3 2 26 3 2 5

2.

Plant 2 1 1 1 1 1 2 1 1 1 1 1 12 0 2 1 3

Systems

Tier

3 4 3 3 3 4 3 4 4 4 3 38 5 3 8

Totals

3. Generic Knowledge & Abilities

1 2 3 4 1 2 3 4

10 7

Categories

3 2 2 3 1 2 2 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

L

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

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

7.* The generic (G) KI As 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 of ES-40 1 for the applicable KIA's

8. On the following pages, enter the KIA numbers, a brief description of each 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 of Column 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 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

I EAPE # I Name Safety Function K1 K2 K3 I A1 I A2 I G KJA Topic(s) Imp. I Q# I

AA2.01 - Ability to determineand/or interpret

295006 SCRAM 11 X the followingas they apply to SCRAM: 4.6 76

Reactor power

AA2.07 - Ability to determineand/or interpret

the followingas they applyto LOSS OF

295021 Loss of ShutdownCooling I 4 X 3.1 77

SHUTDOWN COOLING: Reactor

recirculation flow

2.1.28 - Conductof OperationsKnowledge of

295024 High Drywell Pressure I 5 X the purpose and functionof major system 3.3 78

components and controls.

EA2.01 - Abilityto determineand/or interpret

295026 SuppressionPool High Water the followingas they apply to SUPPRESSION

X 4.2 79

Temp. 15 POOL HIGH WATERTEMPERATURE:

Suppression pool water temperature

EA2.05 - Ability to determineand/or interpret

295037 SCRAM Condition Present the followingas they apply to SCRAM

and Power Above APRM Downscale X CONDITION PRESENTAND REACTOR 4.3 80

or Unknown11 POWER ABOVEAPRM DOWNSCALE OR

UNKNOWN: Control rod position

2.2.22 - EquipmentControlKnowledge of

295038High Off-site Release Rate 19 X limiting conditionsfor operationsand safety 4.1 81

limits.

2.2.24 - EquipmentControlAbility to analyze

600000Plant Fire On-site I 8 X the affect of maintenance activitieson LCO 3.8 82

status.

c 295001Partial or CompleteLoss of

Forced Core Flow Circulation II & 4 X

2.1.14 - Conduct of OperationsKnowledgeof

system status criteria whichrequirethe

notificationof plant personnel.

AK3.01 - Knowledgeof the reasons for the

followingresponsesas they applyto PARTIAL

2.5 39

29500I Partial or CompleteLoss of

Forced Core Flow Circulation II & 4

X OR COMPLETELOSS OF FORCEDCORE 3.4 40

FLOW CIRCULATION : Reactorwater level

response

AA2.01 - Ability to determineand/or interpret

295003Partial or Complete Loss of the followingas they apply to PARTIALOR

AC/6

X 3.4 41

COMPLETELOSS OF AC. POWER : Cause

of partial or completeloss of AC. power

AKI.03 - Knowledgeof the operational

295004Partial or Total Loss of DC implicationsof the followingconceptsas they

X applyto PARTIALOR COMPLETE LOSS OF 2.9 42

Pwr/6

D.C. POWER: Electricalbus divisional

separation

AA1.04 - Abilityto operate and/or monitor

295005Main Turbine GeneratorTrip I the following as they apply to MAIN

3

X 2.7 43

TURBINE GENERATOR TRIP : Main

generator controls

AK3.05 - Knowledge of the reasons for the

following responses as they apply to

295006SCRAM I 1 X 3.8 44

SCRAM : Direct turbine generator trip:

Plant-5pecific

AA2.04 - Abilityto determine and/or

295016 Control Room AbandonmentI interpret the following as they apply to

7

X 3.9 45

CONTROL ROOM ABANDONMENT :

Suppression pool temoerature

AK2.01 - Knowledge of the interrelations

295018Partial or Total Loss ofCCW I between PARTIALOR COMPLETE LOSS

X 3.3 46

8 OF COMPONENT COOLING WATER and

the following: System loads

( 295019Partial or Total Loss ofInst.

X

AA2.02 - Ability to determine and/or

3.6 47

Air I 8 interpret the following as they apply to

ES-401 2 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 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

Ability to verify system alarm setpoints and

295021Loss of ShutdownCooling I 4 X operate controls identified in the alarm 3.3 48

I'" response manual.

AK1.02 - Knowledge of the operational

295023Refueling Ace Cooling Mode I implications of the following concepts as

X they apply to REFUELING ACCIDENTS :

3.2 49

8

Shutdown margin

2.1.33 - Conduct of Operations Ability to

recognize indications for system operating

295024High DrywelI Pressure I 5 X parameters which are entry-level 3.4 50

conditions for technical specifications.

'" EK2.08 - Knowledge of the interrelations

between HIGH REACTOR PRESSURE

295025High ReactorPressure 13 X 3.7 51

and the following: Reactor/turbine pressure

regulating system: Plant-Specific

EA2.01 - Ability to determine and/or

interpret the following as they apply to

295026Suppression Pool High Water

X SUPPRESSION POOL HIGH WATER 4.1 52

Temp. 15

TEMPERATURE: Suppression pool water

temperature

~

EK3.04 - Knowledge of the reasons for the

following responses as they apply to HIGH

295028High DrywelI Temperature I 5 X 3.6 53

DRYWELL TEMPERATURE: Increased

drywell cooling

EA1.06 - Ability to operate and/or monitor

the following as they apply to LOW

295030Low Suppression Pool Water "

Levell 5

X SUPPRESSION POOL WATER LEVEL : 3.4 54

Condensate storage and transfer (make-up

'" to the suppression pool): Plant-Specific

~

2.4.6 - Emergency Procedures I Plan

295031 ReactorLow Water Level/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

andPower Above 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 Rate 19 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

the follOWing as they apply to PLANT FIRE

600000Plant Fire On-site I 8 X 2.6 58

ON SITE : Fire fighting equipment used on

each class of fire

KIA CategoryTotals: 3 3 3 3 8 7 Group Point Total:

I 20/7

(

ES-401 3 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 2

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 of Main 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 of annunciators alarms and 3.4 84

indications, and use of the response instructions.

EA2.02 - Ability to determine and I or interpret

the following as they apply to HIGH

500000 High CTMT Hydrogen Cone, I

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 of the operational

implications of the following concepts as they

295015 Incomplete SCRAM /1 X 3.9 61

apply to INCOMPLETE SCRAM: (CPR 41.8 to

41.10) Cooldown effects on reactor DOwer

AKJ.08 - Knowledge of the reasons for the

following responses as they apply to

295020 Inadvertent Cont. Isolation I 5 &

X INADVERTENT CONTAINMENT 3.3 62

7

ISOLATION: Suppression chamber pressure

response

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

295032 High Secondary Containment following as they apply to HIGH SECONDARY

X 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 the following as they apply to HIGH

X 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

X CONTAINMENT HIGH DIFFERENTIAL 2.8 65

Differential Pressure I 5

PRESSURE: Off-site release rate: Plant-

Specific

KIA Category Totals : 1 1 1 1 3 3 Group Point Total:

I 7/3

(

ES-401 4 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

( Plant Systems - Tier 2 Group 1

K K K K K K A A A A Q#

System # / Name G Imp.

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 and (b) basedon thosepredictions, use

X 4.5 86

Mode procedures to correct, control, or mitigate

the consequences of those abnormal

conditions or operations: Loss of coolant

accident

2.1.14- Conductof Operations Knowledge

215003lRM X of systemstatus criteriawhichrequire the 3.3 87

notification of plantpersonnel.

2.l.23 - Conductof Operations Abilityto

259002ReactorWaterLevel performspecificsystemand integrated

X 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 COOLING MODE); and (b) basedon

X 3.5 89

Control those predictions, use procedures to correct,

control, or mitigatethe consequences of

those abnormal conditions SOCIRHR

pumptrips

A2.12 - Abilityto (a) predictthe impacts

( of the following on the REACTOR

PROTECTION SYSTEM; and (b) based

259002ReactorWaterLevel on thosepredictions, use procedures to

Control

X 4.1 90

correct, control, or mitigatethe

consequences of those abnormal conditions

or operations: Mainturbinestop control

valveclosure

Al.OI - Abilityto predictand/ormonitor

203000RHRILPCI: Injection changes in parameters associated with

X operating the RHRILPCI: INJECTION 4.2 I

Mode

MODE(pLANTSPECIFIC) controls

including: Reactorwater level

K4.02 - KnOWledge of SHUTDOWN

COOLING SYSTEM (RHR

205000Shutdown Cooling SHUTDOWNCOOLINGMODE)

X 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 have on the HIGHPRESSURE

X 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 K2.01 - Knowledge of electrical power

X 2.9 5

supplies to the following: SBLC pumps

(

ES-401 4 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

( Plant Systems - Tier 2 Group 1

K K K K K K A A A A Q#

System # / Name G Imp.

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

and/or monitor in the control room: IRM

215003 IRM X 3.1 7

back panel switches , meters , and

indicating lights

A3 .03 - Ability to monitor automatic

operations of the SOURCE RANGE

215004 Source Range Monitor X 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

relationships between AUTOMATIC

218000 ADS X 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

SYSTEM/NUCLEAR STEAM SUPPLY

223002 PCISlNuclear Steam

X SHUT-oFF; and (b) based on those 3.0 13

Supply Shutoff

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 CONTAINMENT ISOLATION

Supply Shutoff

X 3.4 14

SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF including : System

indicatinQ IiQhtsand alarms

A3 .03 - Ability to monitor automatic

operat ions of the RELIEF/SAFETY

239002SRVs X VALVES including : Tail pipe

3.6 15

temoeratures

A4.08 - Ability to manually operate

and/or monitor in the control room:

239002SRVs X Plant air system pressure: Plant-

3.2 16

Specific

(

ES-401 4 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

( Plant Systems - Tier 2 Group 1

K K K K K K A A A A

System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4

A4.03 - Ability to manually operate

and/or monitor in the control room: All

259002 Reactor Water Level

X individual component controllers when 3.8 17

Control

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.

ELECTRICAL DISTRIBUTION design

262001 AC Electrical

X feature(s) and/or interlocks which 2.8 19

Distribution

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

connections and/or cause- effect

263000 DC Electrical

X relationships between D.C. 3.2 21

Distribution

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 Knowledge of annunciators alarms and

X 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)

based on those predictions, use

400000 Component Cooling

X procedures to correct, control , or 2.8 26

Water

mitigate the consequences of those

abnormal operation: High/low surge

tank level

KJA Category Totals : 2 3 2 2 2 2 2 6 3 3 4 Group Point Total:

I 26/5

(

ES-401 5 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

( Plant Systems - Tier 2 Group 2

K K K K K K A A A A Imp. Q#

System # I Name G

1 2 3 4 5 6 1 2 3 4

A2.01 - Abilityto (a) predictthe impacts

of the following on the RADWASTE ; and

(b) basedon thosepredictions, use

268000Radwaste X 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

of the following on the PLANT

VENTILATION SYSTEMS; and (b)

basedon thosepredictions, use procedures

288000PlantVentilation X to correct, control, or mitigate the 3.7 93

consequences of thoseabnormal conditions

or operations: Lossof coolantaccident:

Plant-Specific

10.03 - Knowledge of the effectthat a

201003 Control Rod and Drive lossor malfunction of the CONTROL

X 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 for the following:

System initialization: P-Soec(Not-BWR6)

K6.09 - Knowledge of the effectthat a

lossor malfunction of the following will

20200I Recirculation X 3.4 29

haveon the RECIRCULATION SYSTEM

Reactorwater level

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. relationships between NUCLEAR

X 3.2 31

BOILERINSTRUMENTATION and the

following: Recirculation flowcontrol

svstem

219000RHRILPCI: TorusIPool K2.02 - Knowledge of electrical power

CoolingMode X 3.1 32

supplies to the followina: Pumps

226001 RHRILPCI: CTMTSpray A4.12 - Ability to manually operate

X and/or monitor in the control room: 3.8 33

Mode

Containmentldrywell pressure

2.4.50 - Emergency Procedures I Plan

234000FuelHandling Equipment Ability to verify system alarm setpoints

X 3.3 34

and operate controls identified in 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 Form ES-401-1

0610 NRC Exam Outline

Written Examination Outline

Plant Systems - Tier 2 Group 2

(

K K K K K K A A A A Q#

System # I Name G Imp.

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

268000 Radwaste 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

as they apply to RADIATION

272000 RadiationMonitoring X 3.2 37

MONITORING SYSTEM : Hydrogen

injection operation's effect on process

radiation indications: Plant-5oecific

A3.01 - Ability to monitor automatic

operations of the CONTROL ROOM

290003 Control Room HVAC X 3.3 38

HVAC inclUding:

Initiationlreconfiguration

KIA CategoryTotals: 1 1 1 1 1 2 1 3 1 1 2 Group Point Total:

I 1213

(

(

ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3

( Facility: 0610 NRC Exam Outline Date:

RO SRO-Only

Category K/A# Topic

IR Q# IR Q#

2.1.12 Ability to apply technical specifications for a system . 4.0 94

Ability to recognize indications for system operating

1. 2.1.33 parameters which are entry-level conditions for 3.4 66

Conduct technical specifications.

of Operations Ability to operate plant phone, paging system, and

2.1.16

two-way radio.

2.9 67

Ability to make accurate, clear and concise logs,

2.1.18

records , status boards, and reports.

2.9 68

~

Subtotal 3 1

Knowledge of limiting conditions for operations and

2.2.22

safety limits.

4.1 95

Ability to analyze the affect of maintenance activities

2.2.24

on LCO status.

3.8 96

2.

Equipment

Control 2.2.13 Knowledge oftagging and clearance procedures. 3.6 69

2.2.33 Knowledge of control rod programming. 2.5 70

Subtotal 2 2

Knowledge of SRO responsibilities for auxiliary

2.3.3 systems that are outside the control room (e.g., waste 2.9 97

disposal and handling systems).

Knowledge ofthe process for performing a

2.3.9 3.4 98

containment purge.

3.

Radiation Ability to perform procedures to reduce excessive

Control 2.3.10 levels of radiation and guard against personnel 2.9 71

exposure.

Knowledge of the process for performing a

2.3.9 2.5 72

containment purge.

Subtotal 2 2

Knowledge of the parameters and logic used to

4.

assess the status of safety functions including: I

Emergency

2.4.21 Reactivity control 2. Core cooling and heat removal 3. 4.3 99

Procedures/

Reactor coolant system integrity 4. Containment

Plan

( conditions 5. Radioactivity release control.

ES-401 Generic Knowledge andAbilities Outline (Tier3) Form ES-401-3

Knowledge of which events related to system

( 2.4.30 operations/status should be reported to outside

agencies.

3.6 100

Ability to diagnose and recognize trends in an

2.4.47 accurate and timely manner utilizing the appropriate 3.4 73

control room reference material.

Knowledge of communications procedures

2.4.15 3.0 74

associated with EOP implementation

Knowledge of how the event-based

2.4.8 emergency/abnormal operating procedures are used in 3.0 75

conjunction with the symptom-based EOPs .

Subtotal 3 2

Tier 3 Point Total 10 7

(

ES-401 Record of Rejected KIA's Form ES-401-4

( Tier! Group

Randomly Selected

Reason for Rejection

KIA

1/1 295016/ AA2.07 Replaced by NRC Chief Examiner

2/1 218000/2.1.14 Replaced by NRC Chief Examiner

2/1 600000 /2.2.25 Replaced by NRC Chief Examiner

2/1 212000/ A2.17 Replaced by NRC Chief Examiner

2/1 205000 / A2.04 Replaced by NRC Chief Examiner

2/1 400000 / 2.4.30 Replaced by NRC Chief Examiner

Admin Replaced due to conflict with independently developed Audit

AJPM501

JPM examination.

('-. ..