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'
Written Examination Outline
n NA-t..
Form ES-401-1
Facility:
0610 NRC Exam Outline
Date ofExam: 02/25/2008
RO KJA Category Points
SRO-Only Points
Tier
Group
K
K
K
K
K
K
A
A
A
A
G
Total
1
2
3
4
5
6
1
2
3
4
A2
G*
Total
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
Totals
4
4
4
4
6
5
27
5
5
10
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
Totals
3
4
3
3
3
4
3
4
4
4
3
38
5
3
8
3. Generic Knowledge & Abilities
1
2
3
4
1
2
3
4
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 ofthe RO and
SRO-only outlines (i.e., except for one category in Tier 3 ofthe SRO-only outline, the "Tier Totals" in each KIA
category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final
point total for each group and tier may deviate by +/-l from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not
apply at the facility should be deleted and justified; operationally important, site-specific systems that are not
included on the outline should be added. Refer to section D.l.b ofES-401, for guidance regarding elimination of
inappropriate KIA statements.
4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group
before selecting a second topic for any system or evolution.
5.
Absent a plant specific priority, only those KAs having an importance rating (IR) of2.5 or higher shall be
selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
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 ofthe 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 briefdescription ofeach topic, the topics' importance ratings
(IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and
tier totals for each category in the table above. Iffuel handling equipment is sampled in other than Category A2 or
G* on the SRO-only exam, enter it on the left side ofColumn A2 for Tier 2, Group 2 (Note #1 does not apply).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 ofthe KIA Catalog, and enter the KIA numbers, descriptions, IRs, and
point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to IOCFR55.43
2
0610 NRC Exam Outline
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
Form ES-401-1
~ 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
29502 I Loss ofShutdown Cooling I 4
X
the following as they apply to LOSS OF
3.1
77
SHUTDOWN COOLING : Reactor
recirculation flow
2.I.28 - Conduct ofOperations Knowledge of
295024 High DrywelI Pressure I 5
X
the purpose and function ofmajor system
3.3
78
components and controls.
EA2.01 - Ability to determine and/or interpret
295026 Suppression Pool High Water
X
the following as they apply to SUPPRESSION
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
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.
29500 I Partial or Complete Loss of
2.I.14 - Conduct ofOperations Knowledge of
X
system status criteria which require the
2.5
39
Forced Core Flow Circulation I I & 4
notification ofplant personnel.
AIG .OI - Knowledge ofthe reasons for the
295001 Partial or Complete Loss of
following responses as they apply to PARTIAL
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
X
the following as they apply to PARTIAL OR
3.4
41
AC/6
COMPLETE LOSS OF <<c.POWER: Cause
of partial or complete loss ofA.C. power
AKl.03 - Knowledge ofthe operational
295004 Partial or Total Loss of DC
implications ofthe following concepts as they
Pwr/6
X
apply to PARTIAL OR COMPLETE LOSS OF
2.9
42
D.C. POWER: Electrical bus divisional
separation
AA1.04 - Ability to operate and/or monitor
295005 Main Turbine Generator Trip I
X
the following as they apply to MAIN
2.7
43
3
TURBINE GENERATOR TRIP: Main
aenerator controls
AK3.05 - Knowledge of the reasons for the
295006 SCRAM II
X
following responses as they apply to
3.8
44
SCRAM: Direct turbine generator trip:
Plant-Specific
AA2.04 - Ability to determine and/or
295016 Control Room Abandonment!
X
interpret the following as they apply to
3.9
45
7
CONTROL ROOM ABANDONMENT:
Suppression pool temperature
AK2.01 - Knowledge of the interrelations
295018 Partial or Total Loss ofCCW I
X
between PARTIAL OR COMPLETE LOSS
3.3
46
8
OF COMPONENT COOLING WATER and
the following: System loads
295019 Partial or Total Loss of inst.
X
AA2.02 - Ability to determine and/or
3.6
47
Air/8
interpret the following as they apply to
2
0610 NRC Exam Outline
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
Form ES-401-1
~ EAPE # / Name Safety Function
K1
K2
K3 I A1 I A2 I G
KIA Topic(s)
Imp. I Q#
~
PARTIALOR COMPLETELOSS OF
INSTRUMENTAIR : Status of safety-
related instrument air system loads (see
AK2.1 - AK2.19)
2.4.50 - Emergency Procedures/ Plan
295021 Loss ofShutdown Cooling/ 4
X
Ability to verify system alarm setpoints and
3.3
48
operate controls identified in the alarm
response manual.
AK1.02 - Knowledge of the operational
295023 Refueling AceCoolingMode/
X
implications of the following concepts as
3.2
49
8
they apply to REFUELINGACCIDENTS :
2.1.33 - Conduct of OperationsAbility to
295024 HighDrywell Pressure / 5
X
recognize indications for system operating
3.4
50
parameterswhich are entry-level
conditionsfor technical specifications.
EK2.08 - Knowledgeof the interrelations
295025 HighReactor Pressure I 3
X
between HIGH REACTORPRESSURE
3.7
51
and the following: Reactor/turbinepressure
regulating system: Plant-Specific
EA2.01 - Ability to determineand/or
295026 Suppression PoolHigh Water
interpret the following as they apply to
X
SUPPRESSIONPOOL HIGHWATER
4.1
52
Temp. 15
TEMPERATURE: Suppressionpool water
temperature
EK3.04 - Knowledgeof the reasonsfor the
295028 High Drywell TemperatureI 5
X
following responses as they applyto HIGH
3.6
53
DRYWELLTEMPERATURE: Increased
drywell cooling
EA1.06 - Ability to operate and/or monitor
295030 Low Suppression PoolWater
the following as they apply to LOW
X
SUPPRESSION POOLWATER LEVEL:
3.4
54
Level/5
Condensatestorage and transfer (make-up
to the suppression pool): Plant-Specific
2.4.6 - Emergency Procedures/ Plan
29503I 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 CONDITIONPRESENT
and Power AboveAPRM Downscale
X
AND REACTORPOWER ABOVE APRM
3.8
56
or Unknown I I
DOWNSCALEOR UNKNOWN and the
following: RMCS: Plant-Specific
EK1.01 - Knowledgeof the operational
implications of the following concepts as
295038 HighOff-siteRelease 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
600000 Plant FireOn-site 18
X
the following as they apply to PLANT FIRE
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
3
0610 NRC Exam Outline
Written Examination Outline
Emergency andAbnormal Plant Evolutions - Tier 1 Group 2
Form ES-401-1
II EAPE # / Name Safety Function
K1
K2
K3
A1
A2
G
KIA Topic(s)
Imp. I Q#
~
2.4.6 - Emergency Procedures/ Plan
295002 LossofMainCondenserVac/3
X
Knowledge symptombasedEOP mitigation
4.0
83
strategies.
2.4.31 - Emergency Procedures/ Plan
295009 LowReactorWater Level/2
X
Knowledge of annunciators alarmsand
3.4
84
indications, and useof the response instructions.
EA2.02- Abilityto determineand/ or interpret
500000 HighCTMT HydrogenCone. /
the following as they applyto HIGH
X
3.5
85
5
CONCENTRATIONS: Oxygenmonitoring
systemavailability
AK2.01 - Knowledge of the interrelations
295009 LowReactorWaterLevel/2
X
betweenLOWREACTOR WATERLEVEL
3.9
59
andthe following: Reactorwaterlevel indication
2.2.22 - EquipmentControlKnowledgeof
295012 High DrywellTemperature/5
X
limitingconditionsfor operationsand safety
3.4
60
limits.
AKI.02 - Knowledge of the operational
295015 IncompleteSCRAM/1
X
implications of the followingconceptsas they
3.9
61
apply to INCOMPLETE SCRAM: (CFR41.8 to
41.10)Cooldowneffectson reactorpower
AK3.08- Knowledge of the reasonsfor the
295020 InadvertentCont. Isolation/ 5 &
following responsesas they applyto
7
X
INADVERTENT CONTAINMENT
3.3
62
ISOLATION: Suppressionchamberpressure
response
EAI.OI- Abilityto operateand/ormonitorthe
295032 High SecondaryContainment
X
following as they applyto HIGHSECONDARY
3.6
63
AreaTemperature/ 5
CONTAINMENT AREATEMPERATURE :
Areatemperature monitoringsystem
EA2.01 - Abilityto determineand/or interpret
295033 High SecondaryContainment
X
the following as they applyto HIGH
3.8
64
Area RadiationLevels/ 9
RADIATION LEVELS : Area radiationlevels
EA2.02 - Abilityto determineand/or interpret
295035 SecondaryContainmentHigh
the following as they applyto SECONDARY
X
CONTAINMENT HIGHDIFFERENTIAL
2.8
65
DifferentialPressure/ 5
PRESSURE: Off-sitereleaserate: Plant-
Specific
KIA CategoryTotals:
1
1
1
1
3
3
GroupPointTotal:
I
713
4
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 1
Form ES-401-1
System # / Name
K
K
K
K
K
K
A
A
A
A
G
Imp.
Q#
1
2
3
4
5
6
1
2
3
4
A2.16 - Abilityto (a) predictthe impacts
of the followingon the RHRlLPCI:
INJECTION MODE(PLANTSPECIFIC);
203000RHRILPCI: Injection
X
and (b) basedon thosepredictions, use
4.5
86
Mode
proceduresto correct,control,or mitigate
the consequences of thoseabnormal
conditionsor operations: Lossof coolant
accident
2.1.14 - Conductof OperationsKnowledge
2150031RM
X
of systemstatus criteriawhichrequirethe
3.3
87
notificationof plant personnel.
2.1.23 - Conductof OperationsAbilityto
259002 ReactorWater Level
X
performspecificsystemand integrated
4.0
88
Control
plantproceduresduringall modesof plant
operation.
A2.06 - Abilityto (a) predictthe impacts
of the followingon the SHUTDOWN
COOLINGSYSTEM(RHRSHUTDOWN
259002ReactorWater Level
X
COOLINGMODE); and (b) basedon
3.5
89
Control
those predictions, use proceduresto correct,
control, or mitigatethe consequences of
those abnormalconditionsSDCIRHR
pumptrips
A2.12- Abilityto (a) predictthe impacts
of the followingon the REACTOR
PROTECTION SYSTEM; and (b) based
259002ReactorWater Level
X
on those predictions, use proceduresto
4.1
90
Control
correct,control, or mitigatethe
consequences of thoseabnormalconditions
or operations: Mainturbinestop control
valveclosure
AI.OI - Abilityto predict and/ormonitor
203000 RHRlLPCI: Injection
changes in parametersassociatedwith
X
operatingthe RHRlLPCI: INJECTION
4.2
I
Mode
MODE(PLANTSPECIFIC)controls
including: Reactorwater level
K4.02 - Knowledge of SHUTDOWN
COOLING SYSTEM (RHR
205000ShutdownCooling
X
SHUTDOWN COOLING MODE)
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
206000 HPCI
X
have on the HIGH PRESSURE
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
211000SLC
X
K2.01 - Knowledge of electrical power
2.9
5
supplies to the following: SBLC pumps
4
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 1
Form ES-401-1
System # / Name
K
K
K
K
K
K
A
A
A
A
G
Imp.
Q#
1
2
3
4
5
6
1
2
3
4
K6.03 - Knowledge of the effect that a
loss or malfunction of the following will
212000RPS
X
have on the REACTOR PROTECTION
3.5
6
SYSTEM: Nuclear boiler
instrumentation
A4.04 - Ability to manually operate
2150031RM
X
and/or monitor in the control room: IRM
3.1
7
back panel switches, meters, and
indicatina Iiahts
A3.03 - Ability to monitor automatic
215004 Source Range Monitor
X
operations of the SOURCE RANGE
3.6
8
MONITOR (SRM) SYSTEM including:
RPS status
A2.03 - Ability to (a) predict the impacts
of the following on the AVERAGE
POWER RANGE MONITOR/LOCAL
POWER RANGE MONITOR SYSTEM;
215005APRM / 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
217000RCIC
X
supplies to the following : RCIC flow
2.7
10
controller
K1.05 - Knowledge ofthe physical
connections and/or cause- effect
218000ADS
X
relationships between AUTOMATIC
3.9
II
DEPRESSURIZATION SYSTEM and
the following: Remote shutdown
system: Plant-Specific
2.1.24 - Conduct of Operations Ability
218000ADS
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
223002PCISlNuclearStearn
SYSTEM/NUCLEAR STEAM SUPPLY
X
SHUT-OFF; and (b) based on those
3.0
I3
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
223002PCISlNuclearStearn
X
CONTAINMENT ISOLATION
3.4
14
Supply Shutoff
SYSTEM/NUCLEAR STEAM SUPPLY
SHUT-OFF including : System
indicatina Iiahts and alarms
A3.03 - Ability to monitor automatic
239002SRVs
X
operations ofthe RELIEF/SAFETY
3.6
15
VALVES including : Tail pipe
temperatures
A4.08 - Ability to manually operate
239002SRVs
X
and/or monitor in the control room:
3.2
16
Plant air system pressure : Plant-
Soecific
4
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 1
Form ES-401-1
System # / Name
K
K
K
K
K
K
A
A
A
A
G
Imp.
Q#
1
2
3
4
5
6
1
2
3
4
A4.03 - Ability to manually operate
259002ReactorWater Level
and/or monitor in the control room: All
Control
X
individual component controllers when
3.8
17
transferring from manual to automatic
modes
K3.06 - Knowledge of the effect that a
loss or malfunction 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.
26200I AC Electrical
ELECTRICAL DISTRIBUTION design
Distribution
X
feature(s) and/or interlocks which
2.8
19
provide for the following : Protective
relaying
A1.02 - Ability to predict and/or monitor
changes in parameters associated with
262002UPS(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
263000DC Electrical
connections and/or cause- effect
Distribution
X
relationships between D.C.
3.2
21
ELECTRICAL DISTRIBUTION and the
following : Battery charger and battery
K5.06 - Knowledge of the operational
implications of the following concepts
264000EDGs
X
as they apply to EMERGENCY
3.4
22
GENERATORS (DIESEUJET) : Load
sequencing
K2.02 - Knowledge of electrical power
300000InstrumentAir
X
supplies to the following : Emergency
3.0
23
air comcressor
K3.01 - Knowledge of the effect that a
loss or malfunction of the
300000InstrumentAir
X
(INSTRUMENT AIR SYSTEM) will
2.7
24
have on the following : Containment air
system
2.4.31 - Emergency Procedures / Plan
400000Component Cooling
X
Knowledge of annunciators alarms and
3.3
25
Water
indications, and use of the response
instructions.
A2.02 - Ability to (a) predict the impacts
of the following on the CCWS and (b)
400000ComponentCooling
based on those predictions, use
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
5
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 2
Form ES-401-1
System # / Name
K
K
K
K
K
K
A
A
A
A
G
Imp.
Q#
1
2
3
4
5
6
1
2
3
4
A2.01 - Ability to (a) predict the impacts
ofthe following on the RADWASTE ; and
268000 Radwaste
X
(b) basedon thosepredictions, use
3.5
91
proceduresto correct, control, or mitigate
the consequences ofthoseabnormal
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
ofthe following on the PLANT
VENTILATION SYSTEMS; and (b)
288000 Plant Ventilation
X
basedon thosepredictions, useprocedures
3.7
93
to correct, control, or mitigate the
consequences ofthoseabnormal conditions
or operations: Loss of coolant accident:
Plant-Specific
K3.03 - Knowledge ofthe effect that a
201003 Control Rod and Drive
X
lossor malfunction ofthe CONTROL
3.2
27
Mechanism
ROD AND DRIVE MECHANISM will
haveon following: Shutdown margin
K4.09 - Knowledge ofROD 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 ofthe effect that a
202001 Recirculation
X
lossor malfunction ofthe following will
3.4
29
haveon the RECIRCULATION SYSTEM
- Reactor water level
A1.01 - 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
216000 Nuclear Boiler Inst.
X
relationships between NUCLEAR
3.2
31
BOILER INSTRUMENTATION and the
following: Recirculation flow control
system
219000 RHRILPCI: ToruslPool
X
K2.02 - Knowledge of electrical power
3.1
32
Cooling Mode
supplies to the following: Pumps
226001 RHRILPCI: CTMT Spray
A4.12 - Ability to manually operate
X
and/or monitor in the control room :
3.8
33
Mode
ContainmenVdrvwell pressure
2.4.50 - Emergency Procedures / Plan
234000 Fuel Handling Equipment
X
Ability to verify system alarm setpoints
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
5
0610 NRC Exam Outline
Written Examination Outline
PlantSystems - Tier 2 Group 2
Form ES-401-1
System # I Name
K
K
K
K
K
K
A
A
A
A
G
Imp.
Q#
1
2
3
4
5
6
1
2
3
4
A2.01 - Ability to (a) predict the
impacts of the following on the
RADWASTE; and (b) based on those
268000Radwaste
X
predictions, use procedures to correct,
2.9
36
control, or mitigate the consequences
of those abnormal conditions or
ooerations: SYstem ruoture
K5.01 - Knowledge of the operational
implications of the following concepts
272000RadiationMonitoring
X
as they apply to RADIATION
3.2
37
MONITORING SYSTEM : Hydrogen
injection operation's effect on process
radiation indications: Plant-Soecific
A3.01 - Ability to monitor automatic
290003Control Room HVAC
X
operations of the CONTROL ROOM
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
Generic Knowledge and Abilities Outline (Tier3)
Form ES-401-3
Facility:
0610 NRC Exam Outline
Date:
KJA#
Topic
SRO-Only
Category
IR
Q#
IR
Q#
2.1.12
Ability to apply technical specifications for a system.
4.0
94
1.
Ability to recognize indications for system operating
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
67
2.1.16
two-way radio.
2.9
2.1.18
Ability to make accurate, clear and concise logs,
2.9
68
records, status boards, and reports.
Subtotal
3
1
2.2.22
Knowledge of limiting conditions for operations and
4.1
95
safety limits.
2.2.24
Ability to analyze the affect ofmaintenance activities
3.8
96
on LCO status.
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 ofSRO responsibilities for auxiliary
2.3.3
systems that are outside the control room (e.g., waste
2.9
97
disposal and handling systems).
2.3.9
Knowledge ofthe process for performing a
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.
2.3.9
Knowledge ofthe process for performing a
2.5
72
containment purge.
Subtotal
2
2
4.
Knowledge ofthe parameters and logic used to
Emergency
assess the status ofsafety functions including: I
Procedures /
2.4.21
Reactivity control 2. Core cooling and heat removal 3.
4.3
99
Plan
Reactor coolant system integrity 4. Containment
conditions 5. Radioactivity release control.
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.
2.4.15
Knowledge of communications procedures
3.0
74
associated with EOP implementation
Knowledge ofhow 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
Record of Rejected KIA's
Form ES-401-4
Tier/ Group
Randomly Selected
Reason forRejection
KIA
1/1
295016 / AA2.07
Replaced by NRC ChiefExaminer
2/1
218000/2.1.14
Replaced by NRC ChiefExaminer
2/1
600000 / 2.2.25
Replaced by NRC ChiefExaminer
2/1
212000/ A2.17
Replaced by NRC Chief Examiner
2/1
205000 / A2.04
Replaced by NRC ChiefExaminer
2/1
400000 / 2.4.30
Replaced by NRC ChiefExaminer
Admin
A1PM 501
Replaced due to conflict with independently developed Audit
lPM
examination.
In-plant
P1PM 63
Removed from exam by direction of ChiefExaminer.
lPM
In-plant
P1PM 66
Removed from exam by direction ofChiefExaminer.
lPM
In-plant
PJPM 311
Removed from exam by direction of ChiefExaminer.
lPM
In-plant
PJPM 76F
Removed from exam by direction of ChiefExaminer.
lPM
In-plant
P1PM 1-8
Developed for Unit-l by direction of ChiefExaminer.
lPM
In-plant
PJPM 1-108
Developed for Unit-l by direction of ChiefExaminer.
lPM
Simulator
HLTS 3-3
Revised to remove Event 4 at direction of ChiefExaminer.
Scenario
Simulator
HLTS 3-4
Revised to add Event 3 at direction ofChiefExaminer.
Scenario
Admin
A1PM 511
Replaced due to unsat evaluation by ChiefExaminer.
lPM
Appendix D
Scenario Outline
FINAL
Form ES-D-l
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
ofthe 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
mrfanOIb reset
N-ATC
The crew will alternate Stator Cooling Water Pumps using 3-
N-BOP
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
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 ofservice. 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
imfrd0718-35
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 ofturbine 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 ofturbine
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 of3A CRD pump.
C-SRO
4
imfsw02a 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 zdihs691
All
before any area reaches max safe value.
null
- (N)onnal,
(Rjeactivity,
(I)nstrument,
(C)omponent,
(Mjajor
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 HLT0610
Administrative Topic
Type
Describe Activity to be performed
(see Note)
Code*
A. Conduct ofOperations
M
Perform 2-SR-3.4.9.3&4 Reactor Recirculation Pwnp
0610 AJPM 542
StartEimitations (RO/SRO)
.
B.
Conduct of Operations
M
Determination'OfActive/Inactive License Status
0610 AJPM 504
~O/SRO)
r:
I,
C. Equipment Control
,
.. P
c Perform 2-SR-3.4.2.1Jet Pump Mismatch and
0610 AJPM 12G
Operability (OPERAnON) (RO/SRO)
"
"-
I
- \\" .'.
,
-
"
...
~
D. Radiation Control
M
Calculate StayTimeforEmergencyExposure
0610 AJPM 518
.
(RO/SRO)
}.J
- ,
."'
.
~ .
~;
~'
~
J'"
-,
,
'i"
.
.-
N/S
Classifythe Eventperthe REP (Torusexceeds
0610 AJPM 487TCF
PSP Curve)(SROOnly)
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
Control Roomlln Plant Systems Outline
f7-v'4r..-
Form ES-301-2
Facility: BFN
Date ofExamination: 2/25/08
Exam Level (circle one): [RO] / ISRO-~ / 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-61OF)
B.
Perform Control Room Transfer of4KV 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 eRDHCU from Service (0610 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 including I(A)
~
I
~2
I
~ 1
(P)revious 2 exams
53
I
- 3
I
- 2
(R)CA
~ l
I
~ l
I
~ l
(Slimulator