ML081370143
| 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
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
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 :
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
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
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
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
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
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
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