ML092920115
| ML092920115 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/17/2009 |
| From: | NRC/RGN-II |
| To: | Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-280/09-301, 50-281/09-301 | |
| Download: ML092920115 (13) | |
See also: IR 05000280/2009301
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ES-401 PWR Examination Outline Form ES-401-2
Facility: Surry Date of July 2009
Exam:
Tier Group RO KIA Categon. Points SRO - Only Points
K K K K K K A A A A G* Total A2 G* Total
1 2 3 4 5 6 1 2 3 4
1. 1 3 1 2 5 5 2 18 3 3 6
Emergenc
y& 2 1 2 1 N/A 1 2 N/A 2 9 2 2 4
Abnormal
Plant Tier 4 3 3 6 7 4 27 5 5 10
Evolutions Totals
1 3 1 4 5 2 1 3 1 2 3 3 28 3 2 5
2.
Plant 2 0 1 0 1 2 1 1 1 1 1 1 10 0\1 2 3
Systems
Tier 3 2 4 6 4 2 4 2 3 4 4 38 4 4 8
Totals
3. Generic Knowledge and 1 2 3 4 112 314
Abilities Categories 3 2 2 3 10 1 j 2 21 2 7
Note: I. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the
RO and SRO-only outlines (Le., 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 +/-1 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-
401 for guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 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.1.b of ES-401 for the
applicable KlAs.
8. On the following pages, enter the KIA numbers, a brief deSCription of each topic, the topics' importance
ratings (IRs) 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; if fuel 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 10 CFR
55.43.
I ES-401 PWR Examination Outline Form
Surry 2009-30 I Emergency and Abnormal Plant Evolutions - Tier I/Group I (RO-R 1 SRO-S)
E/APE # 1 Name 1 Safety Function K K K A A G KIA Topic(s) IR #
I 2 3 I 2
000007 (BW/E02&EI0; CEJE(2) Reactor
Trip - Stabilization - Recovery I I Not Selected
000008 Pressurizer Vapor Space R R AKI.02 Knowledge of the operational 3.1
Accident! 3 implications of the following concepts as they
apply to a Pressurizer Vapor Space Accident:
Change in leak rate with change in pressure
000009 Small Break LOCA I 3 R R EK2.03 Knowledge of the interrelations 3.0
between the small break LOCA and the
following: S/Gs
0000 II Large Break LOCA 1 3 R R EK3 .12 Knowledge of the reasons for the 4.4
following responses as the apply to the Large
Break LOCk Actions contained in EOP for
emergency LOCA (large break)
0000 15117 RCP Malfunctions 1 4 R S R AA2.09 Ability to determine and interpret 3.4
the following as they apply to the Reactor
Coolant Pump Malfunctions (Loss of RC
Flow): Wben to secure RCPs on high stator
temperatures
S 2.2.22 Knowledge of limiting conditions for 4.7
operations and safety limits.
000022 Loss of Rx Coolant Makeup 1 2 R R G 2.4. II Knowledge of abnormal condition 4.0
procedures. (related to Loss of Rx Coolant
Makeup)
000025 Loss of RHR System I 4 R S R AK1.01 Knowledge of the operational 3.9
implications of the following concepts as they
apply to Loss of Residual Heat Removal
System: Loss of RHRS during all modes of
operation.
S AA2.05 Ability to determine and interpret 3.5
the following as they apply to the Loss of
Residual Heat Removal System:
Limitations on LPI flow and temperature
rates of change.
000026 Loss of Component Cooling S S 2.1.7 Ability to evaluate plant performance 4.7
Water 18 and make operational judgments based on
operating characteristics, reactor behavior,
and instrument interpretation
000027 Pressurizer Pressure Control R S R AK3.03 Knowledge of the reasons for the 3.7
System Malfunction 1 3 following responses as they apply to the
Pressurizer Pressure Control Malfunctions:
Actions contained in EOP for PZR PCS
malfunction.
S AA2.15 Ability to determine and interpret 4.0
the following as they apply to the Pressurizer
Pressure Control Malfunctions: Actions to
be taken if PZR pressure instrument fails
high
000029 ATWS I I R R EA 1.02 Ability to operate and monitor the 3.6
following as they apply to a ATWS: Charging
pump suction valves from RWST operating
switch.
000038 Steam Gen. Tube Rupture 13 R R EA 1.21 Ability to operate and monitor the 3.4
following as they apply to a SGTR: Charging
pump ammeter and running indicator
ES-401 PWR Examination Outline Form ES-401-2
Surry 2009-301 Emergency and Abnormal Plant Evolutions - Tier I/Group I (RO-R 1 SRO-S)
EI APE # 1 Name 1 Safety Function K K K A A G KI A Topic(s) IR #
I 2 3 I 2
000040 (BW/E05; CElE05; W/EI2) R R AA2.05 Ability to determine and interpret 4.1
Steam Line Rupture - Excessive Heat the following as they apply to the Steam Line
Transfer I 4 Rupture: When ESFAS systems may be
secured
000054 (CE/E06) Loss of Main S S 2.4.47 Ability to diagnose and recognize 4.2
Feed water 1 4 trends in an accurate and timely manner
utilizing the appropriate control room
reference material
000055 Station Blackout 1 6 R R EKl.02 Knowledge of the operational 4.1
implications of the following concepts as they
apply to the Station Blackout: Natural
circulation cooling
000056 Loss of Off-site Power 1 6 R R AA 1.29 Ability to operate and 1 or monitor 2.7
the following as they apply to the Loss of
Offsite Power: CCW heat exchanger
temperature control valves
000057 Loss of Vital AC Inst. Bus I 6 R R AA2.20 Ability to determine and interpret 3.6
the following as they apply to the Loss of Vital
AC Instrument Bus:
Interlocks in effect on loss of ac vital electrical
instrument bus that must be bypassed to restore
normal equipment operation
000058 Loss of DC Power 16 R G 2.1.23 Ability to perform specific system 4.3
and integrated plant procedures during all
modes of plant operation. (as related to Loss of
DC Power)
000062 Loss of Nuclear Svc Water 14 S S AA2.03 Ability to determine and interpret 2.9
the following as they apply to the Loss of
Nuclear Service Water: The valve lineups
necessary to restart the SWS while
bypassing the portion of the system causing
the abnormal condition
000065 Loss of Instrument Air 1 8 R R AA 1.03 Ability to operate and 1 or monitor 2.9
the following as they apply to the Loss of
Instrument Air: Restoration of systems served
by instrument air when pressure is regained
W/E04 LOCA Outside Containment 13 R R EA2.1 Ability to determine and interpret the 3.4
following as they apply to the (LOCA Outside
Containment): Facility conditions and selection
of appropriate procedures during abnormal and
emergency operations.
WIE II Loss of Emergency Coolant Not Selected
Recire./4
BW/E04; W/E05 Inadequate Heat Trans- R R EAI.I Ability to operate and I or monitor 4.1
fer - Loss of Secondary Heat Sink 14 the following as they apply to the (Loss of
Secondary Heat Sink) : Components, and
functions of control and safety systems,
including instrumentation, signals, interlocks,
failure modes, and automatic and manual
features.
000077 Generator Voltage and Electric R R AA2.07 Ability to determine and interpret 3.6
Grid Disturbances I 6 the following as they apply to Generator
Voltage and Electric Grid Disturbances:
Operational status of engineered safety
features.
K K K A A G
I 2 3 I 2
KI A Category Totals: 3 1 2 5 5 2 Group Point Total: 18/6
3 3
ES-401 PWR Examination Outline Form ES-401-2
SUIT) i009-30 1 Emergency and Abnormal Plant Evolutions - Tier I/Group 2 (RO-R / SRO-S)
E/ APE # / Name / Safety Function K K K A A G KI A Topic(s) IR #
I 2 3 I 2
00000 I Continuous Rod Withdrawal / I
000003 Dropped Control Rod / I S S G2.4.31 Knowledge of annunciator 4.1
alarms, indications, or response
procedures.
000005 Inoperable/Stuck Control Rod / I R R AA2.01 Ability to determine and interpret 33
the following as they apply to the Inoperable /
Stuck Control Rod: Stuck or inoperable rod
from in-core and ex-core NIS,
in-core or lo~ temgerature measurements
000024 Emergency Boration / I
000028 Pressurizer Level Malfunction / 2
000032 Loss of Source Range NI I 7
000033 Loss of Intermediate Range NI 17
000036 (BW/A08) Fuel Handling Accident 18 S S AA2.03 Ability to determine and 4.2
interpret the following as they apply to the
Fuel Handling Incidents: Magnitude of
potential radioactive release.
R R AA2.01 Ability to determine and interpret 3.2
the following as they apply to the Fuel
Handling Incidents: ARM system indications
000037 Steam Generator Tube Leak I 3 R R G2.4.4 Ability to recognize abnormal 4.5
indications for system operating parameters
that are entry-level conditions for emergency
and abnormal operating procedures.
000051 Loss of Condenser Vacuum I 4 S S G2.4.11 Knowledge of abnormal 4.2
condition procedures.
000059 Accidental Liquid RadWaste ReI. 19
000060 Accidental Gaseous Radwaste ReI. 19 R R AK3 .02 Knowledge of the reasons for the 33
following responses as they apply to the
Accidental Gaseous Radwaste: Isolation of
the auxiliary building ventilation
000061 ARM System Alarms I 7
000067 Plant Fire On-site I 8
000068 (BW/A06) Control Room Evac./8 R R G 2.4.21 Knowledge of the parameters and 4.0
logic used to assess the status of safety
functions, such as reactivity control, core
cooling and heat removal, reactor coolant
system integrity, containment conditions.
radioactivity release control, etc.
000069 (W/EI4) Loss ofCTMT Integrity /5
000074 (W/E06&E07) Inad. Core Cooling 14 R R EK2.1 Knowledge of the interrelations 3.6
between the (Degraded Core Cooling) and the
following: Components, and functions of
control and safety systems. including
instrumentation, signals, interlocks, failure
modes, and automatic and manual features
000076 High Reactor Coolant Activity I 9 S S AA2.02 Ability to determine and 3.4
interpret the following as they apply to the
High Reactor Coolant Activity: Corrective
actions required for high fission product
activity in RCS
WlEO I & E02 Rediagnosis & SI Termination / 3
, ~S-401 PWR Examination Outline
UJry 2009-301 Emergency and Abnormal Plant Evolutions - Tier IIGroup 2 (RO-R I SRO-S)
EI APE # I Name I Safety Function K K K A A G KIA Topic(s) II'. H
I 2 3 I 2
WIE 13 Steam Generator Over-pressure I 4 R R EK2.2 Knowledge of the interrelations 3.0
between the (Steam Generator Overpressure)
and the following: Facility's heat removal
systems, including primary coolant,
emergency coolant, the decay heat removal
systems, and relations between the proper
operation of these systems to the operation of
the facility.
W!EI5 Containment Flooding I 5
WIE 16 High Containment Radiation I 9 R EA 1.1 Ability to operate and I or monitor the 3.1
following as they apply to the (High
Containment Radiation): Components, and
functions of control and safety systems,
including instrumentation, signals, interlocks,
failure modes, and automatic and manual
features.
BW/AOI Plant Runbackl I
BW/A02&A03 Loss of NN I-XIY I 7
BW/A04 Turbine Trip I 4
BWI A05 Emergency Diesel Actuation I 6
BWI A07 Flooding 18
BW/E03 Inadequate Subcooling Margin I 4
BW/E08; WIE03 LOCA Cool down - Depress. 14
BW/E09; CElAI3; W/E09&EIO Natural Cire. 14
BWIEI3&EI4 EOP Rules and Enclosures
CEI A II; W/E08 RCS Overcooling - PTS 14 R R EK1.3 Knowledge of the operational 3.5
implications of the following concepts as they
apply to the (Pressurized Thermal Shock):
Annunciators and conditions indicating
signals, and remedial actions associated with
the (Pressurized Thermal Shock).
CEI A 16 Excess RCS Leakage I 2
CElE09 Functional Recovery
K K K A A G
I 2 3 I 2
K! A Category Point Totals: I 2 I I 2
2
2
2
Group Point Total: I 9/4
SAOI PWR Examination Outline Fo
rry 2009-301 Plant Systems - Tier 2/Group I (RO-R / SRO-S)
System # / Name K K K K K K A A A A G KIA Topic(s) IR #
I 2 3 4 5 6 I 2 3 4
003 Reactor Coolant R R R A3.04 Ability to monitor automatic 3.6
Pump operation of the RCPS, including: RCS
flow
R A4.08 Ability to manually operate 3.2
and/or monitor in the control room: RCP
cooling water supplies
004 Chemical and R R A4.08 Ability to manually operate 3.8
Volume Control and/or monitor in the control room:
Charging
005 Residual Heat R R G 2.4.9 Knowledge oflow 3.8
Removal power/shutdown implications in accident
(e.g., loss of coolant accident or loss of
residual heat removal) mitigation
strategies.
006 Emergency Core R S R KI.05 Knowledge of the physical 2.8
Cooling connections and/or cause-effect
relationships between the ECCS and the
following systems: RCP seal injection and
return
S A2.12 Ability to (a) predict the impacts 4.8
of the following malfunctions or
operations on the ECCS; and (b) based
on those predictions, use procedures to
correct, control, or mitigate the
consequences of those malfunctions or
operations: Conditions requiring
actuation of ECCS
007 Pressurizer R R AI.03 Ability to predict and/or monitor 2.6
Relief/Quench Tank changes in parameters (to prevent exceeding
design limits) associated with operating the
PRTS controls including: Monitoring quench
tank temperature
008 Component R R R A2.04 Ability to (a) predict the impacts 3.3
Cooling Water of the following malfunctions or operations
on the CCWS, and (b) based on those
predictions. use procedures to correct,
control, or mitigate the consequences of
those malfunctions or operations: PRMS
alarm
R G 2.1.31 Ability to locate control room 4.6
switches, controls, and indications, and to
determine that they correctly reflect the
desired plant lineup. (as related to the
Component Cooling Water system)
010 Pressurizer R S R A3.02 Ability to monitor automatic 3.6
Pressure Control operation of the PZR PCS, including: PZR
pressure
S 2.4.20 Knowledge of the operational 4.3
implications of EOP warnings, cautions,
and notes.
ES-401 PWR Examination Outline FOTIn ES-40 1-2
Surry 2009-301 Plant Systems - Tier 2/Group I (RO-R / SRO-S)
System # / Name K K K K K K A A A A G KIA Topic(s) IR #
I 2 3 4 5 6 I 2 3 4
012 Reactor Protection R R R K 1.0 I Knowledge of the physical 3.4
connections and/or cause-effect
relationships between the RPS and the
following systems: 120V vital/instrument
power system.
R A4.07 Ability to manually operate 3.9
and/or monitor in the control room: MIG
set breakers
013 Engineered Safety R R G 2.4.49 Ability to perfoTIn without 4.6
Features Actuation reference to procedures those actions that
require immediate operation of system
components and controls.
022 Containment R R K 1.04 Knowledge of the physical 2.9
Cooling connections and/or cause-effect
relationships between the CCS and the
following systems: Chilled water
025 Ice Condenser Not Applicable to the Surry Containment.
026 Containment Spray R R K3.02 Knowledge of the effect that a loss 4.2
or malfunction of the CSS will have on the
following: Recirculation spray system
039 Main and Reheat R R S R K4.04 Knowledge ofMRSS design 2.9
Steam feature(s) and/or interlock(s) which provide
for the following:
Utilization of steam pressure program
control when steam dumping through
atmospheric relief/dump valves, including
T-ave. limits
R A 1.05 Ability to predict and/or monitor 3.2
changes in parameters (to prevent
exceeding design limits) associated with
operating the MRSS controls including:
RCS T-ave
S A2.03 Ability to (a) predict the impacts 3.7
of the following malfunctions or
operations on the MRSS; and (b) based
on predictions, use procedures to
correct, control, or mitigate the
consequences of those malfunctions or
operations: Indications and alarms for
main steam and area radiation
monitors (during SGTR)
059 Main Feedwater R S R K4.16 Knowledge of MFW design 3.1
feature(s) and/or interlock(s) which provide
for the following:
Automatic trips for MFW pumps
S 2.4.35 Knowledge of local auxiliary 4.0
operator tasks during an emergency and
the resultant operational effects.
061 R R R K5.02 Knowledge of the operational 3.2
Auxiliary/Emergency implications of the following concepts as
Feedwater the apply to the AFW:
Decay heat sources and magnitude
R K6.01 Knowledge of the effect ofa loss 2.5
or malfunction of the following will have
on the AFW components: Controllers and
positioners
01 PWR Examination Outline Fonn ES-40 1-2
-301 Plant Systems - Tier 2/Group I (RO-R 1 SRO-S)
arne K K K K K K A A A A G KIA Topic(s) IR #
I 2 3 4 5 6 I 2 3 4
062 AC Electrical R R R K2.01 Knowledge of bus power 33
Distribution supplies to the following: Major system
loads
R K3.03 Knowledge of the effect that a loss 3.7
malfunction of the ac distribution system
will have on the following: DC system
063 DC Electrical R R K3.02 Knowledge of the effect that a 3.5
Distribution loss or malfunction of the DC electrical
system will have on the following:
Components using DC control power.
064 Emergency Diesel R R K4.04 Knowledge of ED/G system 3.1
Generator design feature(s) and/or interlock(s) which
provide for the following: Overload ratings
073 Process Radiation R S R K5.02 Knowledge of the operational 2.5
Monitoring implications as they apply to concepts as
they apply to the PRM system: Radiation
intensity changes with source distance
S A2.02Ability to (a) predict the impacts 3.2
of the following malfunctions or
operations on the PRM system; and (b)
based on those predictions, use
procedures to correct, control, or
mitigate the consequences of those
malfunctions or operations: Detector
failure
076 Service Water R R K4.02 Knowledge of SWS design 2.9
feature(s) and/or interlock(s) which provide
for the following: Automatic start features
associated with SWS pump controls
078 Instrument Air R R K3.03 Knowledge of the effect that a 3.0
loss or malfunction of the lAS will have on
the following: Cross-tied units
103 Containment R R R K4.04 Knowledge of containment 2.5
system design feature(s) and/or interlock(s)
which provide for the following: Personnel
access hatch and emergency access hatch.
R A 1.0 I Ability to predict and/or monitor 3.7
changes in parameters (to prevent
exceeding design limits) associated with
operating the containment system controls
including: Containment pressure,
temperature, and humidity.
K K K K K K A A A A G
I 2 3 4 5 6 I 2 3 4
KI A Category Point 3 I 4 5 2 I 3 I 2 3 3 Group Point Total: 28/5
Totals:
3 2
ESAOI PWR Examination Outline Fonn ES-40 1-2
Surry 2009-30 I Plant Systems - Tier 2/Group 2 (RO-R I SRO-S)
System # I Name K K K K K K A A A A G KIA Topic(s) IR #
I 2 3 4 S 6 I 2 3 4
00 I Control Rod Drive R R K2,OS Knowledge of bus power supplies to the 3, I
following: MIG sets
002 Reactor Coolant
oII Pressurizer Level R R K6,06 Knowledge of the effect of a loss or 2.5
Control malfunction on the following will have on the
PZR LCS: Correlation of demand signal
indication on charging pump flow valve
controller to the valve position
014 Rod Position R R A4,01 Ability to manually operate and/or 33
Indication monitor in the control room: Rod selection
control
° IS Nuclear
Instrumentation
R R KS, IO Knowledge of the operational
implications of the following concepts as they
2,8
apply to the NlS: Ex-core detector operation
° 16 Non-nuclear
Instrumentation
017 In-core R R KS02 Knowledge of the operational 3,7
Temperature Monitor implications of the following concepts as they
apply to the ITM system: Saturation and
subcooling of water
027 Containment S S 2.2.22 Knowledge of limiting conditions for 4.7
Iodine Removal operations and safety limits.
028 Hydrogen
Recombiner and Purge
Control
029 Containment
Purge
033 Spent Fuel Pool
Cooling
034 Fuel Handling
Equipment
035 Steam Generator S S A2.01 Ability to (a) predict the impacts of 4.6
the following malfunctions or operations on
the S/GS; and (b) based on those predictions,
use procedures to correct, control, or mitigate
the consequences of those malfunctions or
operations: Faulted or Ruptured S/Gs
R A2,02 Ability to (a) predict the impacts of the 4,2
R following malfunctions or operations on the
S/GS; and (b) based on those predictions, use
procedures to correct, control, or mitigate the
consequences ofthose malfunctions or
operations: Reactor trip/turbine trip
041 Steam R R A3,03 Ability to monitor automatic operation 2,7
DumplTurbine Bypass of the SDS, including: Steam flow
Control
045 Main Turbine
Generator
OSS Condenser Air S S 2.2.25 Knowledge of the bases in Technical 4.2
Removal Specifications for limiting conditions for
operations and safety limits.
R R G2,4,4S Ability to prioritize and interpret the 4,1
significance of each annunciator or alann,
056 Condensate
06S Liquid Radwaste
ES-401 PWR Examination Outline Fonn ES-40 1-2
Surry 2009-301 Plant Systems - Tier 2/Group 2 (RO-R 1 SRO-S)
1 Name K K K K K K A A A A G KIA Topic(s) IR #
I 2 3 4 5 6 I 2 3 4
071 Waste Gas
Disposal
072 Area Radiation R R K4.0 I Knowledge of ARM system design 3.3
Monitoring feature(s) and/or interlock(s) which provide for
the following: Containment ventilation isolation
075 Circulating Water
079 Station Air
086 Fire Protection R R A 1.03 Ability to predict and/or monitor 2.7
changes in parameters (to prevent exceeding
design limits) associated with Fire Protection
System operating the controls including: Fire
doors
K! A Category Point 0 I 0 I 2 I I I I I I Group Point Total: 10/3
Totals: I 2
ES-40 1 Generic Knowledge and Abilities Outline (Tier 3) Fonn ES-40 1-3
Facility: Surry Date of Exam: June 2009
Category KJA# Topic RO SRO-Only
IR # lR #
Conduct of S GZ.1.4S Ability 10 ideDlify Ind inlerprel diverse 4.3 I
Operations iudications to "aJidale the respouse of anotller
ludiealjon.
R 02. 1.29 Knowledge: of how 10 conduct syslem lineups, such 4 .1 1
D.S YlI I\If:=l, breakers, SWilChe!l, elc.
R 02. 1.40 Knowledge of refueling administrative 2.8 I
n;qu ircml:nLs.
R G2. 1.44 Knowledge of RO dutic ' in the conlrol room 3.9 I
during fuel handlIng, uth a responding LO alarms
from the fuel handling area, eommunic.uulln wilh
the ruel stonlge facility, sy tems opcr,lIl:d rrom the
control room in 'uppo" of fueling oper.uions. and
supporting instlUmenlation.
Subtulal I:' .'j:{,Cj:l- '.:.. 3 ~"2:' ~':"" I
Equipmcnt S G2.Z.14 Knowledge of the prot s for conl.roUing 4.3 I
equipment cOnfiltUrlilio u or sta tus.
C nrrol
S G2.2.22 Knowlcdgt' of limiting condltlom (or opl.'rDllons 4.7 )
and safety IinlllS.
R 02.2.40 Abi.lity 10 apply TL'Chnical Specificalions for II 3.4 I
~)'S1c m .
R G2.2.42 Ability to recognize system pnrnmClers thilt are 3.9 1
cnlly- Ievel conditiQns for Tocbnicol SpeciliClltions.
Subtotal >"'J.;,i;;\i',-," 2 '. 2
Radialion S Gl.3.4 Knowledge of radialion t' po ure limil undt'r 3.7 I
normal or eml.'r~enc)' condl[ion,.
ContTOI
S G2.3.6 Ablll!)' to approve release permits. 3.8 I
R OU.S Ability to use radiation monitoring systcms. such 2.9 1
as fixed radiJltion monitors nd alanns, ponabk
survey ilJ..~tru.men t.s. personnel monitoring
equipment , ClC.
R Gl.3.7 Abi lity to comply wiLh rdd iation work pennit 3.5 I
rc!qulremenl.S during normal or abnonnlll
condit.ions.
SublUW l 2 I.~ "c ~ 2
Emergc ncy S G2.4.9 Knowlwge of low power{ hUldo n impllcalions 4.2 I
In acdd~n t (e.g. 10 or cool.anl laeddent or 10 S
Procedure ' I
of residual heat remova l) mitlgalion stralegics.
Plan S G2.4.30 Knowlcdg~ of event reilit d to sySlem 4. 1 I
oper 110 lalult'hal must be: reported to
internal organizaUons or e terna! agendes, uch
lIS Ihe tate, thl.' NRC or the Iran mis ion
system operator.
R02.4.14 Knowledge of g(.'11cruJ guidelines for EOP usage. 3.8 1
R02.4.18 Know ledge of the specific bases for EOPs. 3.3 I
R 0 2,4,49 Ability to perform without Tcfcrcncc to procedures 4.6 1
..
those clions that requin: immediate operation of
system components an.d controls .
Subtotal 3 r:~T....~- 2
Tier 3 P o int Total 10 ~';",',; 7
ES*301 Administrative Topics Outline Form ES*301*1
DR~1
Facility: Surry Power Station Date of Examination: 7/20109
Examination Level: RO 0 SRO ~ Operating Test Number: 2009-301
Administrative Topic Type Describe activity to be performed
(see Note) Code*
Verify Blender settings for desired Cb.
Conduct of Operations RIN
Description: Calculate boric acid flow for a given RCS boron
G2.1.25 (3.9/4.2) calculation and detennine controller settings.
Review O-OSP-ZZ-004 to determine if conditions allow for
fuel movement.
Conduct of Operations SIN
G2.IAO (2.8/3.9) Description: Review procedure and board indication to
determine if fuel movement can commence.
Respond to a main control room chiller failure in accordance
with O-OP-VS-006, Control Room and Relay Room
Equipment Control RIN Ventilation System.
G2.2.37 (3.6/4.6) Description: Determine ifMCR chiller alignment is adequate
and complies with technical specifications.
Determine the applicability of a RWP for a specific job and
determine which personnel may be assigned the task based on
Radiation Control RID personal qualifications and dose limitations.
G2.3.7 (3.5/3.6) Description: Calculate dose received verse limitations given.
Classify an Event and Recommend PAR.
Emergency ProcedureslPlan RIN
Description: Given an event, detennine the EAL
G2.4.41 (2.9/4.6) classification and protective action recommendation, if
applicable.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking
only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom
(D)irect from bank (::;3 for ROs; ::sA for SROs & RO retakes)
(N)ew or (M)odified from bank ( ;:::1)
(P)revious 2 exams (:::;1; randomly selected)
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2
Df.?-:n-F1
Facility: Sur!}: Power Station Date of Examination: 07/20/2009
Exam Level: RO D SRO-I D SRO-U [3J Operating Test No.: 2009-301
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety
Function
a. Load the #3 EDG on the 1J bus iaw AP-17.0S. EPEOSSEA 1 .06 D/E/LIS 6- Electrical
(4.1/4.S)
b. Establish Redundant HHSI Flowpaths 006A4.07 (4.4/4.4) S/LID 2- RCS Inventory
Control
c. Configure spray systems in accordance with ECA-1.1 (Loss of A/N/EN/LIS 5- Containment
Emergency Recirculation). 026A2.03 (4.1/4.4) Integrity
d.
e.
f.
g.
h.
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Increase RCS boron SOO ppm in accordance with AP-40.00 step AlE/LINIR 1- Reactivity
17. 004A2.11 (3.6/4.2) Control
j. Isolate Service Water to #3 MER During Flooding. 076A2.01 AlDIE 4- Heat Removal
(3.S/3.7) from Core
k.
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety
functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may
overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U
(A)ltemate path 4-6 / 4-6 / 2-3
(C)ontrol room
(O)irect from bank :::;,9/ :::;,8/:::;,4
(E)mergency or abnormal in-plant ::::1 / ::::1 / ::::1
(EN)gineered safety feature - / - / ~ (control room system)
(L)ow-Power / Shutdown ::::1 / ::::1 / ::::1
(N)ew or (M)odified from bank including 1(A) ::::2 / ::::2 / ::::1
(P)revious 2 exams :::;,3/ :::;,3/ :::;,2 (randomly selected)
(R)CA ::::1 / ::::1 / ::::1
(S)imulator