ML081370143

Feb-Mar 05000259/2008301 Exam Final Written Exam Outlines

ML081370143
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: ML081370143 (18)

See also: IR 05000259/2008301

Text

Final Submittal

(Blue Paper)

FINAL OUTLINES'

ES-401 Written Examination Outline Form ES-401-1

n NA-t..

Facility: 0610 NRC Exam Outline Date of Exam: 02/25/2008

RO KJA 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 *

l. I 3 3 3 3 4 4 20 4 3 7

Emergency

& 2 1 I 1 1 2 1 7 I 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 I 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

1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities

10 7

Categories

3 2 2 3 I 2 2 2

Note: l. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and

SRO-only outlines (i.e., except for one category in Tier 3 of the 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.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be

relevant to the applicable evolution or system. Refer to Section D.l.b ofES-401 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 of the 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

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

AA2.01 - Ability to determine and/or interpret

295006 SCRAM I I X the following as they apply to SCRAM : 4.6 76

Reactor power

AA2.07 - Ability to determine and/or interpret

the following as they apply to LOSS OF

29502 I Loss of Shutdown Cooling I 4 X 3.1 77

SHUTDOWN COOLING : Reactor

recirculation flow

2.I .28 - Conduct of Operations Knowledge of

295024 High DrywelI Pressure I 5 X the purpose and function of major system 3.3 78

components and controls.

EA2.01 - Ability to determine and/or interpret

295026 Suppression Pool High Water the following as they apply to SUPPRESSION

X 4.2 79

Temp . 15 POOL HIGH WATER TEMPERATURE:

Suppression pool water temperature

EA2.05 - Ability to determine and/or interpret

295037 SCRAM Condition Present the following as they apply to SCRAM

and Power Above APRM Downscale X CONDITION PRESENT AND REACTOR 4.3 80

or Unknown I I POWER ABOVE APRM DOWNSCALE OR

UNKNOWN: Control rod position

2.2.22 - Equipment Control Knowledge of

295038 High Off-site Release Rate 19 X limiting conditions for operations and safety 4.1 81

limits.

2.2.24 - Equipment Control Ability to analyze

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

status.

2.I.14 - Conduct of Operations Knowledge of

29500 I Partial or Complete Loss of

X system status criteria which require the 2.5 39

Forced Core Flow Circulation I I & 4

notification of plant personnel.

AIG .OI - Knowledge of the reasons for the

following responses as they apply to PARTIAL

295001 Partial or Complete Loss of

X OR COMPLETE LOSS OF FORCED CORE 3.4 40

Forced Core Flow Circulation I I & 4

FLOW CIRCULATION: Reactor water level

response

AA2.01 - Ability to determine and/or interpret

295003 Partial or Complete Loss of the following as they apply to PARTIAL OR

X 3.4 41

AC/6 COMPLETE LOSS OF <<c. POWER: Cause

of partial or complete loss of A.C. power

AKl.03 - Knowledge of the operational

implications of the following concepts as they

295004 Partial or Total Loss of DC

X apply to PARTIAL OR COMPLETE LOSS OF 2.9 42

Pwr/6

D.C. POWER: Electrical bus divisional

separation

AA1.04 - Ability to operate and/or monitor

295005 Main Turbine Generator Trip I the following as they apply to MAIN

X 2.7 43

3 TURBINE GENERATOR TRIP: Main

aenerator controls

AK3.05 - Knowledge of the reasons for the

following responses as they apply to

295006 SCRAM II X 3.8 44

SCRAM: Direct turbine generator trip:

Plant-Specific

AA2.04 - Ability to determine and/or

295016 Control Room Abandonment! interpret the following as they apply to

X 3.9 45

7 CONTROL ROOM ABANDONMENT:

Suppression pool temperature

AK2.01 - Knowledge of the interrelations

295018 Partial or Total Loss ofCCW I between PARTIAL OR COMPLETE LOSS

X 3.3 46

8 OF COMPONENT COOLING WATER and

the following: System loads

295019 Partial or Total Loss of inst. AA2.02 - Ability to determine and/or

X 3.6 47

Air/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

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

PARTIAL OR COMPLETE LOSS OF

INSTRUMENTAIR : Status of safety-

related instrument air system loads (see

AK2.1 - AK2.19)

2.4.50 - Emergency Procedures/ Plan

Ability to verify system alarm setpoints and

295021 Loss of Shutdown Cooling/ 4 X 3.3 48

operate controls identified in the alarm

response manual.

AK1.02 - Knowledge of the operational

295023 Refueling Ace CoolingMode/ implications of the following concepts as

X 3.2 49

8 they apply to REFUELINGACCIDENTS :

Shutdown margin

2.1.33 - Conduct of OperationsAbility to

recognize indications for system operating

295024 High Drywell Pressure / 5 X 3.4 50

parameters which are entry-level

conditions for technical specifications.

EK2.08 - Knowledge of the interrelations

between HIGH REACTOR PRESSURE

295025 High Reactor Pressure I 3 X 3.7 51

and the following: Reactor/turbinepressure

regulating system: Plant-Specific

EA2.01 - Ability to determine and/or

interpret the following as they apply to

295026 Suppression PoolHigh Water

X SUPPRESSION POOL HIGHWATER 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

295028 High Drywell 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

295030 Low Suppression PoolWater

X SUPPRESSION POOL WATER LEVEL: 3.4 54

Level/5

Condensate storage and transfer (make-up

to the suppression pool): Plant-Specific

2.4.6 - Emergency Procedures/ Plan

29503 I Reactor Low Water Level/2 X Knowledge symptom based EOP 3.1 55

mitigation strategies.

EK2.11 - KnOWledge of the interrelations

295037 SCRAMCondition Present between SCRAM CONDITION PRESENT

and Power AboveAPRM Downscale X AND REACTOR POWER ABOVE APRM 3.8 56

or Unknown I I DOWNSCALE OR UNKNOWN and the

following: RMCS: Plant-Specific

EK1.01 - Knowledge of the operational

implications of the following concepts as

295038 High Off-site Release Rate 19 X they apply to HIGH OFF-SITE RELEASE 2.5 57

RATE : Biological effects of radioisotope

ingestion

AA1.08 - Ability to operate and / or monitor

the following as they apply to PLANT FIRE

600000 Plant Fire On-site 18 X 2.6 58

ON SITE: Fire fighting equipment used on

each class of fire

KiA Category Totals: 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

II EAPE # / Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. I Q# ~

2.4.6 - Emergency Procedures/ Plan

295002 Loss of Main Condenser Vac /3 X Knowledge symptombased EOP mitigation 4.0 83

strategies.

2.4.31 - Emergency Procedures/ Plan

295009 Low Reactor Water Level/2 X Knowledge of annunciators alarms and 3.4 84

indications, and use of the response instructions.

EA2.02- Abilityto determineand / or interpret

the following as they apply to HIGH

500000 High CTMT HydrogenCone. /

X PRIMARY CONTAINMENT HYDROGEN 3.5 85

5 CONCENTRATIONS: Oxygen monitoring

systemavailability

AK2.01 - Knowledge of the interrelations

295009 Low Reactor Water Level/2 X betweenLOWREACTOR WATERLEVEL 3.9 59

and the following: Reactorwater level indication

2.2.22 - EquipmentControlKnowledgeof

295012 High DrywellTemperature/5 X limitingconditionsfor operationsand safety 3.4 60

limits.

AKI.02 - Knowledge of the operational

implications of the followingconceptsas they

295015 IncompleteSCRAM/1 X 3.9 61

apply to INCOMPLETE SCRAM: (CFR41.8 to

41.10) Cooldowneffects on reactor power

AK3.08- Knowledge of the reasons for the

following responsesas they apply to

295020 InadvertentCont. Isolation/ 5 &

X INADVERTENT CONTAINMENT 3.3 62

7

ISOLATION: Suppressionchamber pressure

response

EAI.OI - Abilityto operate and/or monitorthe

295032 High SecondaryContainment following as they apply to HIGH SECONDARY

X 3.6 63

Area Temperature/ 5 CONTAINMENT AREATEMPERATURE :

Area temperature monitoringsystem

EA2.01 - Abilityto determineand/or interpret

295033 High SecondaryContainment the following as they apply to HIGH

X 3.8 64

Area Radiation Levels/ 9 SECONDARY CONTAINMENT AREA

RADIATION LEVELS : Area radiation levels

EA2.02 - Abilityto determineand/or interpret

the following as they apply to SECONDARY

295035 SecondaryContainmentHigh

X CONTAINMENT HIGH DIFFERENTIAL 2.8 65

Differential Pressure/ 5

PRESSURE: Off-site releaserate: Plant-

Specific

KIA Category Totals: 1 1 1 1 3 3 Group PointTotal:

I 713

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

A2.16 - Ability to (a) predictthe impacts

of the followingon the RHRlLPCI:

INJECTION MODE (PLANTSPECIFIC);

203000 RHRILPCI: Injection and (b) based on those predictions, use

X 4.5 86

Mode proceduresto correct,control,or mitigate

the consequences of those abnormal

conditionsor operations: Loss of coolant

accident

2.1.14 - Conductof OperationsKnowledge

2150031RM X of system status criteriawhich requirethe 3.3 87

notificationof plant personnel.

2.1.23 - Conductof OperationsAbilityto

259002 ReactorWater Level performspecific system and integrated

X 4.0 88

Control plant proceduresduring all modesof plant

operation.

A2.06 - Abilityto (a) predict the impacts

of the followingon the SHUTDOWN

COOLINGSYSTEM(RHR SHUTDOWN

259002 ReactorWater Level COOLINGMODE) ; and (b) based on

X 3.5 89

Control those predictions, use proceduresto correct,

control, or mitigatethe consequences of

those abnormalconditionsSDCIRHR

pump trips

A2.12 - Abilityto (a) predictthe impacts

of the followingon the REACTOR

PROTECTION SYSTEM; and (b) based

259002 ReactorWater Level on those predictions, use proceduresto

X 4.1 90

Control correct, control, or mitigatethe

consequences of those abnormalconditions

or operations: Main turbinestop control

valve closure

AI.OI - Abilityto predict and/or monitor

changes in parametersassociated with

203000 RHRlLPCI: Injection

X operatingthe RHRlLPCI: INJECTION 4.2 I

Mode MODE (PLANTSPECIFIC)controls

including: Reactorwater level

K4.02 - Knowledge of SHUTDOWN

COOLING SYSTEM (RHR

SHUTDOWN COOLING MODE)

205000 ShutdownCooling 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

have on the HIGH PRESSURE

206000 HPCI X 3.5 3

COOLANT INJECTION SYSTEM:

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 LOW PRESSURE 2.8 4

CORE SPRAY SYSTEM : Heat

removal (transfer) mechanisms

K2.01 - Knowledge of electrical power

211000 SLC 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

System # / Name 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

2150031RM and/or monitor in the control room: IRM

X 3.1 7

back panel switches, meters, and

indicatina Iiahts

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 ofthe physical

connections and/or cause- effect

218000 ADS X relationsh ips between AUTOMATIC

3.9 II

DEPRESSURIZATION SYSTEM and

the following: Remote shutdown

system : Plant-Specific

2.1.24 - Conduct of Operations Ability

218000 ADS X to obtain and interpret station electrical 2.8 12

and mechanical drawinas.

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

of the following on the PRIMARY

CONTAINMENT ISOLATION

223002PCISlNuclear Stearn SYSTEM/NUCLEAR STEAM SUPPLY

Supply Shutoff X SHUT-OFF; and (b) based on those 3.0 I3

predictions, use procedures to correct,

control, or mitigate the consequences

of those abn cond or ops . Conta inment

instrumentation failures

A3.01 - Ability to monitor automatic

operations of the PRIMARY

223002PCISlNuclear Stearn CONTAINMENT ISOLATION

Supply Shutoff

X 3.4 14

SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF including : System

indicatina Iiahts and alarms

A3.03 - Ability to monitor automatic

239002SRVs operations ofthe RELIEF/SAFETY

X 3.6 15

VALVES including : Tail pipe

temperatures

A4 .08 - Ability to manually operate

239002 SRVs and/or monitor in the control room:

X 3.2 16

Plant air system pressure : Plant-

Soecific

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

259002ReactorWater 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 of the STANDBY

261000SGTS X GAS TREATMENT SYSTEM will have 3.0 18

on following : Primary containment

oxvcen content: Mark-I&II

K4.04 - Knowledge of A.C .

ELECTRICAL DISTRIBUTION design

26200I AC Electrical

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

Distribution

provide for the following : Protective

relaying

A 1.02 - 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.lD.C.) controls

includinCl: Motor cenerator cutouts

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 operat ional

implications of the follow ing concepts

264000EDGs X as they apply to EMERGENCY 3.4 22

GENERATORS (DIESEUJET) : Load

sequencing

K2.02 - Knowledge of electrical power

300000 InstrumentAir X supplies to the following : Emergency 3.0 23

air comcressor

K3.01 - Knowledge of the effect that a

loss or malfunction of the

300000 InstrumentAir X (INSTRUMENT AIR SYSTEM) will 2.7 24

have on the following : Containment air

system

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

400000ComponentCooling

X procedures to correct , control, or 2.8 26

Water mitigate the consequences of those

abnormal operation : Highllow surge

tank level

KiA CategoryTotals: 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

System # / Name 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) basedon those predictions, use

268000 Radwaste X 3.5 91

proceduresto correct, control, or mitigate

the consequences of those abnormal

conditions or operations: Svstem ruoture

2.4.36 - EmergencyProcedures / Plan

271000 Off-gas X Knowledge of chemistry / health physics 2.8 92

tasksduring emergencv operations.

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

of the following on the PLANT

VENTILATION SYSTEMS; and (b)

basedon those predictions, use procedures

288000 Plant Ventilation X 3.7 93

to correct, control, or mitigate the

consequences of those abnormal conditions

or operations: Loss of coolant accident:

Plant-Specific

K3 .03 - Knowledge of the effect that a

201003 Control Rod and Drive loss or malfunction of the CONTROL

X 3.2 27

Mechanism ROD AND DRIVE MECHANISM will

have on following: Shutdown margin

K4.09 - Knowledge of ROD WORTH

MINIMIZER SYSTEM (RWM) (pLANT

201006RWM X SPECIFIC) design feature(s)and/or 3.2 28

interlocks which provide for the following:

Systeminitialization: P-Spec(Not-BWR6)

K6 .09 - Knowledge of the effect that a

loss or malfunction of the following will

202001 Recirculation X 3.4 29

have on the RECIRCULATION SYSTEM

Reactor water level

A 1.01 - Ability to predict and/or monitor

changes in parameters associated with

21500I Traversing In-core Probe X operating the TRAVERSING IN-CORE 2.8 30

PROBE controls including: Radiation

levels: (Not-BWR1)

K1 .10 - Knowledge ofthe physical

connections and/or cause- effect

relationships between NUCLEAR

216000 Nuclear Boiler Inst. X 3.2 31

BOILER INSTRUMENTATION and the

following : Recirculation flow control

system

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

X 3.1 32

Cooling Mode supplies to the following : Pumps

A4 .12 - Ability to manually operate

226001 RHRILPCI: CTMT Spray

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

Mode

ContainmenVdrvwell pressure

2.4.50 - Emergency Procedures / Plan

Ability to verify system alarm setpoints

234000 Fuel Handling Equipment 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

245000 Main Turbine Gen. / Aux . X have on the MAIN TURBINE 2.6 35

GENERATOR AND AUXILIARY

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

System # I Name 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: SYstem ruoture

K5.01 - Knowledge of the operational

implications of the following concepts

as they apply to RADIATION

272000 Radiation Monitoring X 3.2 37

MONITORING SYSTEM : Hydrogen

injection operation's effect on process

radiation indications: Plant-Soecific

A3.01 - Ability to monitor automatic

operations of the CONTROL ROOM

290003Control Room HV AC X 3.3 38

HVAC including :

Initiation/reconfiguration

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

I 12/3

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

Facility: 0610 NRC Exam Outline Date:

RO SRO-Only

Category KJA# 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 of tagging and clearance procedures. 3.6 69

2.2.33 Knowledge of control rod programming. 2.5 70

Subtotal 2 2

Knowledge ofSRO responsibilities for auxiliary

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

disposal and handling systems).

Knowledge of the 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.

Knowle dge 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 and Abilities Outline (Tier3) Form ES-401-3

Knowledge of which events related to system

2.4.30 operations/status should be reported to outside 3.6 100

agencies.

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

assoc iated 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

KIA

Reason for Rejection

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

A1PM 501

lPM examination.

In-plant

P1PM 63 Removed from exam by direction of Chief Examiner.

lPM

In-plant

P1PM 66 Removed from exam by direction of Chief Examiner.

lPM

In-plant

PJPM 311 Removed from exam by direction of Chief Examiner.

lPM

In-plant

PJPM 76F Removed from exam by direction of Chief Examiner.

lPM

In-plant

P1PM 1-8 Developed for Unit-l by direction of Chief Examiner.

lPM

In-plant

PJPM 1-108 Developed for Unit-l by direction of Chief Examiner.

lPM

Simulator

HLTS 3-3 Revised to remove Event 4 at direction of Chief Examiner.

Scenario

Simulator

HLTS 3-4 Revised to add Event 3 at direction of Chief Examiner.

Scenario

Admin

A1PM 511 Replaced due to unsat evaluation by Chief Examiner.

lPM

Appendix D Scenario Outline Form ES-D-l

FINAL

Facility: BFN Scenario Number: HLTS-3-1 Op-Test Number: HLT0610

Examiners: Operators:

Initial Conditions:

Unit 3 has been operating for 192 days. Unit 2 has been operating for 56 days. Unit 1 has been

operating for 274 days . 3ED Diesel Generator is tagged for water jacket leakage repair. Day 2

of the LCO. Expected to be returned to service this shift . Fuelleakers on U3 are currently at

RFI 60,000. Thunderstorms are passing through the region, but no watches are in effect for the

immediate area. The 3C RFP was oscillating approximating 30 RPM during last shift, but is

now working properly and being monitored. The 3C RFP Pump is operating in automatic

in order to collect data for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A trouble shooting plan is being developed.

Turnover:

Support scheduled maintenance and testing activities. Alternate Stator Cooling Water Pumps per 3-01-

35A, Sect 6.4 per scheduled OPA.

Event Malfunction Event Event

Number Number Type* Description

la mrf anOIb reset N-ATC The crew will alternate Stator Cooling Water Pumps using 3-

N-BOP 0I-35A.

N-SRO

lb N/A TS-SRO The US will respond to a HPCI Rupture Diaphragm pressure

switch PS-73-20B failure.

2 imf fw05b 100 R-ATC The crew will respond to a 3B HP FW heater isolation using

8:00 C-BOP 3-AOI-6-1.

R-SRO The crew will reduce power to -91 % using a recirc flow

reduction.

The crew will isolate feedwater to the 3B FW heater string.

The crew will further reduce power to <79% using a recirc

flow reduction.

3 imfswlOa C-ATC The crew will respond to a trip of the 3A Fuel Pool Cooling

C-SRO pump using 3-AOI-78-1.

TS-SRO

4 imffw13b C-ATC The crew will respond to a trip of the 3B Reactor Feedwater

C-BOP Pump (RFP) using 3-AOI-3-1 and 3-01-3.

C-SRO

5 bat rfpactrip M The crew will respond to a total loss of feedwater and reactor

All scram.

6 bat M The crew will respond to a RCIC steam leak into secondary

HLTS3-1 All containment and a HPCI 120V AC power failure .

The crew will anticipate Emergency Depressurization or

perform Emergency Depressurization due to secondary

containment high radiation.

• (N)ormal, (R)eactivity, (Imstrument, (C)omponent, (M)ajor

AppendixD Scenario Outline Form ES-D-l

Facility: BFN Scenario Number: HLTS-3-3 Op-Test Number: HLT0610

Examiners: Operators:

Initial Conditions:

The HPCI system is tagged out for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> to repair the Auxiliary Oil Pump. It is expected back in 3

hours. Flow indicator 3-78B is out of service. Instrument Mechanics are looking for a new transmitter.

The Main Generator voltage regulator has been placed in Manual for PMs on the Automatic voltage

regulator. The spare RBCCW pump in service to Unit 2.

Turnover:

Reduce power to 95% using recirculation flow due to low system load requirements. PMs on the

voltage regulator are complete. Return the Main Generator voltage regulator to Automatic operation.

Event Malfunction Event Event

Number Number Type* Description

1 .\oJ N/A R-ATC The ATC operator will reduce reactor power to 95% using

R-SRO recirc flow using 3-01-68.

1 b N/A N-BOP The BOP operator will return the Main Generator voltage

N-SRO regulator to Automatic using 3-01-47.

2 ior zdihs7542a C-BOP The crew will recognize and respond to an inadvertent start of

start C-SRO the 3D Core Spray pump.

TS-SRO The SRO will address Tech Specs.

3 imf rd0718-35 C-ATC The crew will recognize and respond to a control rod drifting

C-SRO into the core using 3-AOI-85-5.

TS-SRO The SRO will address Tech Specs.

4 bat NRC/ C-ATC The crew will recognize and respond to a recirc pump trip,

HLTSIO-l C-SRO power oscillations, scram and ATWS .

C-BOP

5 . Timed out from M The crew will recognize and respond to a fuel failure during

batch file All the ATWS recovery actions.

• (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

AppendixD Scenario Outline Form ES-D-l

Facility: BFN Scenario Number: HLTS-3-4 Op-Test Number: HLT0610

Examiners: Operators:

Initial Conditions:

The unit is starting up following a refuel outage. Reactor power is at - 1%. "C" RFP is uncoupled for

performance of turbine overspeed testing . Currently at step 5.76.8 oO-GOI-IOO-IA.

Turnover:

The 3C RFP is uncoupled and the suction and discharge valves are tagged for performance of turbine

overspeed. Currently at step 5.76.8 oO-GOI-lOO-IA and at step 5.6.13 00-01-3 for warming 3B RFP.

Event Malfunction Event Event

Number Number Type* Description

1 none R-ATC Crew will continue to pull rods to increase power and start

N-BOP warming up 2B RFP

R-SRO

2 imfrd14a I-ATC Crew will respond to a RWM failure.

I-SRO SRO references Tech Specs.

TS-SRO

3 imfrdOla C-ATC Crew will respond to a trip of 3A CRD pump.

C-SRO

4 imf sw02a trip C-BOP Crew will respond to a RBCCW pump trip

7048FTC C-SRO Crew manually closes 70-48 after fails to auto close

5 ior zdihs468a C-BOP Crew will respond to feedwater controller malfunction which

imfth235 C-SRO results in cold water injection

6 imfth235 M Crew responds to fuel failure after cold water injection

All

7 imf cu0425 M Crew responds to a RWCU line break and scrams reactor

ior zdihs69 1 All before any area reaches max safe value.

null

• (N)onnal, (Rjeactivity, (I)nstrument, (C)omponent, (Mjajor

ES-301 Administrative Topics Outline Form ES-301-1

Facility: Browns Ferry Date of Examination: 2/25/08

Examination Level (circle one): RO/SRO Operating Test Number HLT061 0

Administrative Topic Type

Describe Activity to be performed

(see Note) Code*

A. Conduct of Operations M Perform 2-SR-3.4.9.3&4 Reactor Recirculation Pwnp

Start Eimitations (RO/SRO)

0610 AJPM 542

.

B. Conduct of Operations M Determination' OfActive/Inactive License Status

0610 AJPM 504 ~O/SRO)

r: I,

. Perform 2-SR-3.4.2.1 Jet Pump Mismatch and

C. Equipment Control

,

c

. P

Operability (OPERAnON) (RO/SRO)

0610 AJPM 12G

. " "-

'.

I  ;\"

,

- ... ~

"

D. Radiation Control M Calculate Stay Time for EmergencyExposure

0610 AJPM 518 . (RO/SRO)

}.J ~' ~

, J'"

. "'

-, ,

'i"

. .- . ~ . ~;

E. Emergency Plan N/S Classifythe Event per the REP (Torus exceeds

0610 AJPM 487TCF PSP Curve)(SRO Only)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless

they areretakina only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room

(D)irect from bank (::S 3 for ROs; ::s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (::s 1; randomly selected)

(S)imulator

ES-301, Page 22 of27

ES-301 Control Roomlln Plant Systems Outline Form ES-301-2

f7-v'4r..-

Facility: BFN Date of Examination: 2/25/08

Exam Level (circle one): [RO] / IS RO-~ / SRO-U Operating Test Number: HLT0610

Control Room Systems (8 for RO; 7for SRO-I; 2 or 3 for SRO-U)

System / lPM Title Type Safety

Code* Function

A. Respond to a Dual Recirc Pump Trip (OPRM'S Operable)

ADES 1

(0610 SJPM-61 OF)

B. Perform Control Room Transfer of 4KV Unit Board 2B Power

NS 6

Supplies (0610 SJPM-222)

C. Restoration to Normal following RPS Bus Power Loss (0610

DES 7

SJPM-132)

D. Respond to Offaas Post Treat HI HI HI (0610 SJPM-190) DSP 9

E. Respond to Stuck Open SRV (0610 SJPM-3136F) AMELS 3

F. Placing Standby Steam Jet Air Ejector in Operation (0610

AMES 4

SJPM-3116F)

G. Respond to Drywell Pressure and/or Temperature High or

Excessive Leakage into the Drywell - FAULTED - SBGT C ADEMS 5

Failed (0610 SJPM-3126F)

H. Injection system Iineup-CS SYS I (0610 SJPM-322F)

ADELS 2

(ROOnly)

In-Plant Systems (3 for RO; 3 for SRO-I ; 3 or 2 for SRO-U)

I. Place a 250V Battery Charger in Service (0610 PJPM-86) DL 6

J. Vent and Re-pressurize the Scram Pilot Air Header (0610

DEPR 1

PJPM-I -8)

K. Remove a eRD HCU from Service (06 10 PJPM- I08 ) NR 1

• Type Codes Criteria for RO I SRO-I I SRO-U

(A)ltemate Path 4-6 I 4-6 I 2-3

(C)ontrol Room

(D)irect from bank ~ I :::8 I :s4

(E)mergency or abnormal in-plant ~1 I ~l I ~1

(L)ow-Power ~1 I ~1 I ~1

(N)ew or (M)odified from bank includi ng I(A) ~ I ~2 I ~1

(P)revious 2 exams 53 I :::3 I  :::2

(R)CA ~l I ~l I ~l

(Sli mulator