ML12304A008
| ML12304A008 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/26/2012 |
| From: | NRC/RGN-II |
| To: | Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-280/12-301, 50-281/12-301 | |
| Download: ML12304A008 (21) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Surry Date of Exam: August 2012
SRO-Qnly_Points Tier Group I
KKKKKKAIAAAG A2 G*
Total 1
2 3
4 5
6 11.2 3
4 Total
= = = = =
= =
1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
Abnormal 2
I N/A 1
2 N/A 1
9 2
2 4
Evolutions Tier Totals 4
5 5
4 5
4 27 5
5 10 1
2223 3333322 28 3
2 5
2.
Plant 2
1 110111 111 1
10 1
1 1
3 Systems Tier Totals 3
3 3
3 4
4 4
4 4
3 3
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 3
2 2
3 2
2 1
2 Note:
1 Ensure that at least two topics from every applicable K/A 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 9ler Totals in each K/A 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 K/A 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 K/As 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 K/A categories, 7.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1.b of ES-401 for the applicable K/As.
8.
On the following pages, enter the K/A 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401.3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
/
/1
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 -2 EmerqencandAbnornwPlarEvutions - Tier 1/Group 1 (RO / SRO)
E/APE # / Name / Safety Function K
K K
A A
G K/A Topic(s)
IR iig__
EK2 Knowledge of the interrelations between a 000007 (BW/E02&E10; CEJEO2) Reactor R
reactor trip and the following:
2.6 1
Trip
- Stabilization - Recovery / 1 (CFR 41.7 / 45.7)
EK2.02 Breakers, relays and disconnects
AK1. Knowledge of the operational implications of 000008 Pressurizer Vapor Space R
the following concepts as they apply to a 3.2 2
Accident /3 Pressurizer Vapor Space Accident:
(CFR41.8/41.10/45.3)
AK1.01 Thermodynamics and flow characteristics of open or leaking valves
2.1.19 Abilityto use plant computers to 000009 Small Break LOCA /3 S
evaluate system or component status.
3.8 76 (CFR: 41.10145.12)
EA1 Ability to operate and monitor the following as 000011 Large Break LOCA /3 R
they apply to a Large Break LOCA:
4.3 3
(CFR 41.7 / 45.5/ 45.6)
EA1.09 Core flood tank initiation
AA2. Ability to determine and interpret the 000015/17 RCP Malfunctions / 4 S
following as they apply to the Reactor Coolant 3.5 77 Pump Malfunctions (Loss of RC Flow):
(CFR: 43.5 /45.13)
AA2.08 When to secure RCPs on high bearing temperature
AA2. Abihty to determine and interpret the following 000022 Loss of Rx Coolant Makeup /2 R
as they apply to the Loss of Reactor Coolant 3.2 4
Makeup:
(CFR 43.5/ 45.13)
AA2.02 Charging pump problems
2.4.31 Knowledge of annunciator alarms, 000025 Loss of RHR System /4 R
indications, or response procedures.
4.2 5
(CFR: 41.10/45.3)
AA2. Ability to determine and interpret the following
000026 Loss of Component Cooling R
as they apply to the Loss of Component Cooling 2.8 6
Water / 8 Water (CFR: 43.5/45.13)
AA2.06 The length of time after the loss of CCW flow to a component before that component may be damaged
AK2. Knowledge of the interrelations between the 000027 Pressurizer Pressure Control R
Pressurizer Pressure Control 2.6 7
System Malfunction /
Malfunctions and the following:
(CFR 41.7 / 45.7)
AK2.03 Controllers and positioners S
2.1.23 Ability to perform specific system and 4.4 78 integrated plant procedures during all modes of plant operation.
r
EA1 Ability to operate and monitor the following as
000029 ATjNS / 1 R
they apply to a ATWS:
3.4 8
(CFR 41.7 / 45.5 / 45.6)
EA1.07 Operating switch for charging pump recirculation valve
EKS Knowledge of the reasons for the following 000038 Steam Gen. Tube Rupture /3 R
responses as the apply to the SGTR:
4.1 9
(CFR 41.5 / 41.10 / 45.6/45.13)
EK3.01 Equalizing pressure on primary and secondary sides of ruptured S/G
WE1 2 EK2. Knowledge of the interrelations between 000040 (8W/E05; CE/E05; W!E1 2)
R the (Uncontrolled Depressurization of all Steam 3.4 10 Steam Line Rupture-Excessive Heat Generators) and the following:
Transfer! 4 (CFR: 41.7 / 45.7)
WE1 2 EK2. 1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
s WE12 EA2. Ability to determine and Interpret the following as they apply to the (Uncontrolled Depressurization of all Steam Generators)
(CFR: 4.3.5 145.13)
WE12 EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.
000054 (CE/E06) Loss of Main Feedwater /4
EK1 Knowledge of the operational implications of 000055 Station Blackout / 6 A
the following concepts as they apply to the Station 4.1 11 Blackout:
(CFR 41.8 / 41.10 / 45.3)
EK1.02 Natural ci,culation cooling 2.4.9 Knowledge of low power/shutdown 4
S implications in accident (e.g., loss of coolant
.2 accident or loss of residual heat removal) mitigation strategies.
(CFR: 41.10143.5145.13)
000056 Loss of Off-site Power / 6
AK3. Knowledge of the reasons for the following 000057 Loss of Vital AC Inst. Bus! 6 R
responses as they apply to the Loss of Vital AC 4.1 12 Instrument Bus:
(CFR 41.5,41.10/45.6/45.13)
AK3.01 Actions contained in EOP for loss of vital ac
electrical instrument bus
AA1. Ability to operate and / or monitor the following 000058 Loss of DC Power! 6 R
as they apply to the Loss of DC Power:
3.4 13 (CFR 41.7 / 45.5 / 45.6)
AA1.01 Cross-tie of the affected dc bus with the
alternate supply
AA2. Ability to determine and interpret the following 000062 Loss of Nuclear Svc Water / 4 R
as they apply to the Loss of Nuclear Service Water:
2.9 14 (CFR: 43.5/45.13)
AA2.01 Location of a leak in the SWS
2.1.31 Ability to locate control room switches, 000065 Loss of Instrument Air / 8 R
controls, and indications, and to determine that they 4.6 15 correctly reflect the desired plant lineup.
(CFR:41.10/45.12)
2.4.45 Ability to prioritize and interpret the W/E04 LOCA Outside Containment! 3 R
significance of each annunciator or alarm.
41 16 (CFR:41,10/43.5/45.3/45.12)
EK1. Knowledge of the operational implications of W/E1 1 Loss of Emergency Coolant R
the following concepts as they apply to the (Loss of 3.6 17 Recirc. /4 Emergency Coolant Recirculation)
(CFR: 41.8! 41.10 / 45.3)
EK1.2 Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).
WEO5 EK3. Knowledge of the reasons for the BW!E04; W/E05 Inadequate Heat R
following responses as they apply to the (Loss of 3.7 18 Transfer - Loss of Secondary Heat Sink /
Secondary Heat Sink)
(CFR: 41.5141.10, 45.6, 45.13)
WEO5 EK3.2 Normal, abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).
AA2. AbilIty to determIne and Interpret the 000077 Generator Voltage and Electric S
following as they apply to Generator Voltage and 3.5 81 Grid Disturbances / 6 Electric Grid Disturbances: (CFR: 41.5 and 43.51 45.5, 45.7, and 45.8)
AA2.06 Generator frequency limitatIons
=
=
=
=
K/A Category Totals:
3 3
3 3
3 3
Group Point Total:
18
- ii
ES-401 3
Form ES-401 -2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Pnt Evoluhons - Tier 1/Group 2 (RO I SRO)
E/APE # / Name / Safety Function K
K K
A A
G K/A Topic(s)
IR i__i__
000001 Continuous Rod Withdrawal / 1
AK3. Knowledge of the reasons for the 38 19 000003 Dropped Control Rod / 1 R
following responses as they apply to the Dropped Control Rod:
(CFR 41.5,41.10 / 45.6 / 45.13)
AK3.07 Tech*Spec limits for T-ave
000005 Inoperable/Stuck Control Rod / 1
AK2. Knowledge of the interrelations 2.6 20 000024 Emergency Boration / 1 R
between Emergency Boration and the following:
(CFR 41.7 / 45.7)
AK2.03 Controllers and positioners AK2. Knowledge of the interrelations 2.6 21 000028 Pressurizer Level Malfunction /2 R
between the Pressurizer Level Control Malfunctions and the following:
(CFR 41.7 / 45.7)
AK2.02 Sensors and detectors
000032 Loss of Source Range NI / 7
AK1. Knowledge of the operational 2.7 22 000033 Loss of Intermediate Range NI /7 R
implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation:
(CFR41.8/41.10145.3)
AK1.01 Effects of voltage changes on performance
000036 (BW/A08) Fuel Handling Accident / 8
000037 Steam Generator Tube Leak / 3
000051 Loss of Condenser Vacuum / 4
000059 Accidental Liquid RadWaste Rel. / 9
AA2. Ability to determine and interpret 3.7 82 000060 Accidental Gaseous Radwaste Rel. / 9 S
the following as they apply to the Accidental Gaseous Radwaste:
(CFR: 43.5/45.13)
AA2.O1 A radiation-level alarm, as to whether the cause was due to a gradual (in time) signal increase or due to a sudden increase (a spike), including the use of strip-chart recorders, meter
and alarm observations
000061 ARM System Alarms / 7 2.4.11 Knowledge of abnormal condition 4.2 000067 Plant Fire On-site / 8 S
procedures.
(
)
000068 (BW/A06) Control Room Evac. /8
=
=
=
=
000069 (W/E14) Loss of CTMT Integrity / 5
H
=
=
WE14 EK3. Knowledge of the reasons for
the following responses as they apply to 3.3 23 the (High Containment Pressure)
(CFR: 41.5? 41.10. 45.6, 45.13)
WE14 EK3.4 HO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not
violated.
000074 (W/E06&E07) mad. Core Cooling /4
000076 High Reactor Coolant Activity! 9
W/EO1 & E02 Rediagnosis & SI Termination / 3
W/E13 Steam Generator Over-pressure /4 R
EA1. Ability to operate and! or monitor the following as they apply to 3.1 24 the (Steam Generator Overpressure)
(CFR: 41.7 / 45.5 / 45.6)
EA1.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
W/E15 Containment Flooding / 5 s
2.4.6 Knowledge of EOP mitigation
strategIes.
(CFR: 41.10/43.5/45.13)
W/E16 High Containment Radiation / 9 R
EA2. Ability to determine and interpret the
following as they apply to 3.0 25 the (High Containment Radiation)
(CFR: 43.5 /45.13)
EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.
8W/Aol Plant Runback /1 BW!A02&A03 Loss of NNI-X/Y / 7
BW/A04 Turbine Trip? 4
8W/A05 Emergency Diesel Actuation /6
BW/A07 Flooding / 8
BW!E03 Inadequate Subcooling Margin / 4
BW/E08; W/E03 LOCA Cooldown
- Depress. /4 H
2.1.20 Ability to interpret and execute
procedure steps.
4.6 26 (CFR:41.l0?43.5/45.12)
BW/E09; CE/Al 3; W?E09&E10 Natural Circ. / 4 S
WE1O EA2. Ability to determine and
interpret the following as they apply to 85 the (Natural Circulation with Steam Void in Vessel with/without RVLIS)
(CFR: 43.5 / 45.13)
WE1O EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
BW/E1 3&E14 EOP Rules and Enclosures
=
=
-=
-
WEO8 EA2. Ability to determine arid interpret 35 27 CE/Al 1; W/E08 RCS Overcooling - PTS /4 R
the following as they apply to the (Pressurized Thermal Shock)
(CFR: 43.5/ 45.13)
WEO8 EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.
CEIAl6ExcessRCSLeakage/2
CEJEO9 Functional Recovery
=
=
.-
=
1 2
2 1 I 2 1
Group Point Total:
9 K/A Category Point Totals:
J 2
2 4
=
=
=
=
ES-401 4
Form ES-401 -2 ES-401 PWR Examination Outline Form ES-401 -2 Plant Systems
- Tier 2JGroujJRO / SRO)
System # / Name K
K K
K K
K A
A A
A G
K/A Topic(s)
IR 1*
1234561234 K6 Knowledge of the effect of a loss or 003 Reactor Coolant Pump R
malfunction on the following will have on 2.7 28 the RCPS:
(CFR: 41.7 / 45/5)
K6.02 RCP seals and seal water supply R
A3 Ability to monitor automatic operation 3.2 29 of the RCPS, including:
(CFR: 41.7 / 45.5)A3.03 A3.03 Seal 0/P A2 Ability to (a) predict the impacts of 004 Chemical and Volume S
the following malfunctions or 4.2 86 Control operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5! 43/5 14513! 45/5)
A2.O1 RCS pressure allowed to exceed limits A2 Ability to (a) predict the impacts of the following malfunctions or operations 3.6 30 on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5/ 43/5/45/3/45/5)
A2.13 Low RWST 2.4.2 Knowledge of system set points, R
interlocks and automatic actions associated with EOP entry conditions.
(CFR: 41.7 / 45.7 /45.8)
K5 Knowledge of the operational 005 Residual Heat Removal R
implications of the following concepts as 3.4 32 they apply the RHRS:
(CFR: 41.5/ 45.7)
K5.02 Need for adequate subcooling j
2.2.42 Ability to recognize system 3.9 33 parameters that are entry-level conditions for Technical Specifications.
=
(CFR:41.7/41.10/43.2/43.3/45.3)
=
A2 Ability to (a) predict the impacts of 006 Emergency Core Cooling S
the following malfunctions or 35 87 operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5 / 45.5)
A2.05 improper amperage to the pump motor A
A4 Ability to manually operate and/or 3 8 34 monitor in the control room; (CFR: 41.7 / 45.5 to 45.8)
A4.10 Safety Parameter display svsteni K4 Knowledge of PRTS design 007 Pressurizer Relief/Quench A
feature(s) and/or interlock(s) 2.6 35 Tank which provide for the following:
(CFR: 41.7)
K4.01 Quench tank cooling R
A3 Ability to monitor automatic operation 2 7 36 of the PRTS, including:
(CFR: 41.7 / 45.5)
A3.01 Components which discharge to the PRT
A2 Ability to (a) predict the impacts of 008 Component Cooling Water R
the following malfunctions or operations 3.3 37 on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5/43.5/45.3/45.13)
A2.04 PRMS alann
K2 Knowledge of bus power supplies to 010 Pressurizer Pressure Control R
the following:
2.5 38 (CFR; 41.7)
K2.02 Controller for PZR spray valve Al Ability to predict and/or monitor R
changes in parameters (to prevent 3.6 39 exceeding design limits) associated with operating the PZR PCS controls including:
(CFR: 41.5 / 45.5)
Al.04 Effects of temperature change during solid operation
K6 Knowledge of the effect of a loss or 012 Reactor Protection R
malfunction of the following will have on 3.1 40 the RPS:
(CFR: 41.7/45/7)
K6.03 Trip logic circuits S
2.2.38 Knowledge of conditions and 45 88 limitations in the facility license, jcFR: 41.7/41.10143.1 I45.13)
=
S = = = = = = =
=
-=
=
=
=
=
=
=
=
1<1 Knowledge of the physical 013 Engineered Safety Features R
connections and/or cause effect 4.1 41 Actuation relationships between the ESFAS and the following systems:
(CFR: 41.2 to 41.9/ 45.7 to 45.8)
K1.12 ED/G K5 Knowledge of the operational R
implications of the following concepts 2.9 42 as they apply to the ESFAS:
(CFR: 41.5/ 45.7)
K5.02 Safety system logic and reliability
K4 Knowledge of CCS design feature(s) 022 Containment Cooling and/or interlock(s) which provide for the 2.6 43 following:
(CFR: 41.7) 1<4.05 Containment cooling after LOCA
destroys ventilation ducts 025 Ice Condenser
Not applicable to Surry
K3 Knowledge of the effect that a loss or 026 Containment Spray R
malfunction of the CSS will have on 4.2 44 the following:
(CFR: 41.7/ 45.6)
1<3.02 Recirculation spray system
A4 Ability to manually operate and/or 039 Main and Reheat Steam R
monitor in the control room:
3.8 45 (CFR: 41.7 / 45.5 to 45.8)
A4.04 Emergency feedwater pump turbines
Ki Knowledge of the physical 059 Main Feedwater R
connections and/or cause-effect 3.4 46 relationships between the MFW and the following systems:
(CFR: 41.2 to 41.9/45.7 to 45.8)
K1.O2AFWsystem
1<2 Knowledge of bus power supplies to 061 Auxiliary/Emergency R
the following:
3.2 47 Feedwater (CFR: 41.7) 1<2.01 AFW system MOVs 1<5 Knowledge of the operational R
implications of the following concepts 3.2 48 as the apply to the AFW:
(CFR: 41.5! 45.7)
K5.02 Decay heat sources and
magnitude
KS Knowledge of the effect that a loss or 062 AC Electrical Distribution R
malfunction of the ac distribution 3.7 49 system will have on the following:
(CFR: 41.7 / 45.6)
=
=
=
=
=
=
K3.03 DC system
063 DC Electrical Distribution K4 Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following:
(CFR: 41.7>
K4.02 Breaker interlocks, permissives, bypasses and cross-ties.
Al Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including:
(CFR: 41.5 / 45.5)
Al.01 Battery capacity as it is affected by discharge rate R
R 2.9 50 2.5 51 K6 Knowledge of the effect of a loss or 064 Emergency Diesel Generator R
malfunction of the following will have on 2.7 52 the EDIG system:
(CFR: 41.7/ 45.7)
K6.07 Air receivers A2 Ability to (a) predict the impacts of 073 Process Radiation R
the following malfunctions or operations 2.5 53 Monitoring on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5/43.5/45.3/45.13)
A2.01 Erratic or failed power supply A2 Ability to (a) predict the impacts of the following malfunctions or S
operations on the PRM system; and 2.9 89 (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5143.5! 45.3145.13)
A203 Calibration drift Al Ability to predict and/or monitor 076 Service Water R
changes in parameters (to prevent 2.6 54 exceeding design limits) associated with operating the SWS controls including:
(CFR: 41.5 / 45.5)
Al.02 Reactor and turbine building
closed cooling water temperatures.
2.1.7 Ability to evaluate plant 078 Instrument Air S
performance and make operatIonal 4.7 90 judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(CFR: 41.5143.5! 45.12 I 45.13)
A3 Ability to monitor automatic operation 103 Containment R
of the containment system, including:
3*9 55 (CFR: 41.7 / 45.5)
A3.01 Containment isolation K!A Category Point Totals:
2 2
2 3
3 3
3 3
3 2
2 Group Point Total:
28 3
2 5
= =
= = = =
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2
=
Plant SVstems
System #IName K
K K
K K
K A
A A
A G
KJA Topic(s)
IR 1234561234
K2 Knowledge of bus power supplies to the 001 Control Rod Drive R
following; 2.7 56 (CFR: 41.7)
K2.03 One-line diagram of power supplies
tologiccircuits
002 Reactor Coolant
K3 Knowledge of the effect that a loss or 011 Pressurizer Level Control R
malfunction of the PZR LOS 3.2 57 will have on the following:
(CFR: 41.7/ 45.6)
K3.01 CVCS 014 Rod Position Indication
015 Nuclear Instrumentation
016 Non-nuclear Instrumentation K6 Knowledge of the effect of a loss or 017 In-core Temperature Monitor R
malfunction of the following ITM system 2.7 58 components; (CFR: 41.7 / 45.7)
K6.01 Sensors and detectors KI Knowledge of the physical connections 027 Containment Iodine Removal R
and/or cause-effect relationships between 3.4 59 the CIRS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.01 CSS 2.1.28 Knowledge of the purpose and 028 Hydrogen Recombiner R
function of major system components and j 4.1 60 and Purge Control controls.
(CFR:41.7)
A4 Ability to manually operate and/or 029 Containment Purge R
monitor in the control room:
3.5 61 (CFR: 41.7 / 45.5 to 45.8)
A4.04 Containment evacuation signal
033 Spent Fuel Pool Cooling
K4 Knowledge of design feature(s) 034 Fuel Handling Equipment S
and/or Interlock(s) which provide for the 3.3 91 following:
(CFR: 41.7)
K4.03 Overload protection
A3 Ability to monitor automatic operation of 035 Steam Generator R
the S/G including:
4.0 62 (CFR: 41.7 / 45.5)
A3.01 S/G water level control 041 Steam Dump)Turbine BypassControl
2.1.27 Knowledge of system purpose 045 Main Turbine Generator S
and/or function.
4.0 92
=
= =
(CFR: 41.7)
= = = = = = = = =
055 Condenser Air Removal
A2 Ability to (a) predict the impacts of the 056 Condensate R
following malfunctions or operations on the 2.6 63 Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5/ 43.5 I 45.3 / 45.13)
A2.04 Loss of condensate pumps
A2 Ability to (a) predict the impacts of 068 Uquid Radwaste S
the following malfunctions or 3.3 93 operations on the Liquid Radwaste System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5/43.5145.3145.13)
A2.04 Failure of automatic isolatIon Al Ability to predict and/or monitor 071 Waste Gas Disposal R
changes in parameters(to prevent 2.5 64 exceeding design limits) associated with Waste Gas Disposal System operating the controls including:
(CFR: 41.5 / 45.5)
Al.06 Ventilation system
K5 Knowledge of the operational 072 Area Radiation Monitoring R
implications of the following 2.7 65 concepts as they apply to the ARM system:
(CFR: 41.5 / 45.7)
K5.01 Radiation theoty, including sources, types, units, and effects
075 Circulating Water
O79StationAir
086 Fire Protection
=
=
=
=
=
=
=
=
=
=
=
K/A Category Point Totals:
1 1
1 0
1 1
1 1
1 1
1 Group Point Total:
10
==
1 Ii 11 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Date of Exam:
Category K/A #
Topic SRO-Only IR IR 2.1.1 2.1.1 Knowledge of conduct of operations requirements.
3.8 66 (CFR: 41.10/45.13) 2.1.8 2.1.8 Ability to coordinate personnel activities outside the 3.4 67 C
d t
control room.
of° ations (CFR: 41.10/ 45.5 / 45.12 / 45.13) p 2.1.26 2.1.26 Knowledge of industrial safety procedures (such 3.4 68 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
(CFR: 41.10/45.12) 2.1.34 2.1.34 Knowledge of primary and secondary plant 3.5 94 chemistry limits.
(CFR: 41.10/43.5/45.12) 2.1.13 2.1.13 Knowledge of facility requirements for controlling 3.2 95 vital/controlled access.
(CFR:_41.10143.5/45.9/45.10)
Subtotal 3
2 2.2.4 2.2.4 (multi-unit license) Ability to explain the variations in 3.6 69 control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.
(CFR: 41.6/41.7/41.10/45.1 /45.13)
Equipnent 2.2.44 2.2.44 Ability to interpret control room indications to verify 4.2 70 the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
(CFR:_41.5/ 43.5 / 45.12) 2.2.11 2.2.11 Knowledge of the process for controlling temporary 3.3 96 design changes.
(CFR: 41.10/43.3/45.13) 2.2.12 2.2.12 Knowledge of surveillance procedures.
4.1 97 (CFR: 41.10/45.13)
Subtotal 2
2 2.3.7 2.3.7 Ability to comply with radiation work permit 3.5 71 requirements during normal or abnormal conditions.
(CFR: 41.12/45.10) 3 2.3.12 2.3.12 Knowledge of radiological safety principles 3.2 72 Radiation pertaining to licensed operator duties, such as Control containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(CFR: 41.12/45.9/45.10) 2.3.13 2.3.13 Knowledge of radiological safety procedures 3.8 98 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(CFR: 41.12 / 43.4 / 45.9145.10)
2.4.5 Subtotal 2
1 4.
Emergency Procedures /
Plan 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
(CFR: 41.10/43.5145.13 3.7 73 2.4.20 2,4.20 Knowledge of the operational implications of EOP 3.8 74 warnings, cautions, and notes.
(CFR: 41.10/43.5/45.13) 2.4.37 2.4.37 Knowledge of the lines of authority during 3.0 75 implementation of the emergency plan.
(CFR: 41.10/45.13) 2.4.16 2.4.16 Knowledge of EOP implementation hierarchy and 4.4 99 coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.
(CFR: 41.10 / 43.5/45.13) 2.4.30 2.4.30 Knowledge of events related to system 4.1 100 operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
(CFR: 41.10/43.5/45.11)
Subtotal 3
2 Tier3PointTotal 10 7
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Pi ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
Date of Examination; Initials Item Task Description
1.
a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
Jf R
b.
Assess whether the outline was systematically and randomly prepared in accordance with I
Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
cth T
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
L Jf d.
Assess whether the justifications for deselected or rejected K/A statements are appropriate.
IIJA 2.
a.
Using Form ES-301 -5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S
and major transients.
M b.
Assess whether there are enough scenario sets (and spares) to test the projected number u
and mix of applicants in accordance with the expected crew composition and rotation schedule L
without compromising exam integrity, and ensure that each applicant can be tested using A
at least one new or significantly modified scenario, that no scenarios are duplicated T
from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative and_quantitative_criteria specified on Form ES-301 -4 and described_in_Appendix D.
3.
a.
Verify that the systems walk-through outline meets the criteria specified on Form ES-301 -2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks W
distributed among the safety functions as specified on the form I
(2) task repetition from the last two NRC examinations is within the limits specified on the form T
(3) no tasks are duplicated from the applicants audit test(s)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
b.
Verify that the administrative outline meets the criteria specified on Form ES-301 -1; (1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations
c.
Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4.
a.
Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
4
R d.
Check for duplication and overlap among exam sections.
th L
e.
Check the entire exam for balance of coverage.
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
a Author dNamenatQ
/o?Iz,
- b. Facility Reviewer ()
C4 IC1
- c. NRC Chief Examiner (If)
- d. NRC Supervisor Note:
If Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
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Control Room!ln-Plant Systems Outline Facility: Surry Power Station Date of Examination: 08/2012 Exam Level: RO SRO-l SRO-U Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function a.
Swap to Th Recirc A/S/NIL/EN 2
b.
Perform 1-FR-H.3 for SG High Level A/S/NIL 4
c.
Place the Containment H2 Analyzer in Service SIDIL 5
d.
Perform AP-3.00 to Emergency Borate the RCS AS/N 1
e.
Place the AAC Diesel on the 1J Emergency Bus SIDIL 6
f.
Adjust the PRNIs in accordance with 1-OPT-RX-001 A/SIN 7
g.
Isolate a Leaking Recirc Spray Heat Exchanger SIMIL 9
h.
Respond to a Spurious SI <350°F SIDIL 3
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
Isolate Flooding in #5 MER A/D/E 4
j.
Align Turbine Building IA to Containment D/R 8
k.
Locally Isolate the Secondary System (E-3, Attachment 1)
E/D 3
All RO and SRO-l 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 RO Actual Criteria Met?
(A)lternate path 4-6 5
Yes (D)irect from bank 9
6 Yes (E)mergency or abnormal in-plant 1
2 Yes (EN)gineered safety feature (L)ow-Power/ Shutdown 1
6 Yes (N)ew or (M)odified from bank including 1 (A) 2 5
Yes (P)revious 2 exams (randomly selected) 3 0
Yes (R)CA 1
1 Yes (S)imulator / (C)ontrol room ES-301 Form ES-301-2
ES-301 Control Roomiln-Plant Systems Outline Form ES-301 -2 Facility: Surry Power Station Date of Examination: 08/2012 Exam Level: RO SRO-l
- X SRO-U Operating Test No.:
1 Control Room Systems© (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)
System I JPM Title Type Code*
Safety Function a.
Swap to Th Recirc A/S/N/LIEN 2
b.
Perform 1-FR-H.3 for SG High Level A/S/NIL 4
c.
Place the Containment H2 Analyzer in Service S/D/L 5
d.
Perform AP-3.00 to Emergency Borate the RCS A/S/N 1
e.
Adjust the PRNIs in accordance with 1-OPT-RX-001 A/S/N 7
f.
Isolate a Leaking Recirc Spray Heat Exchanger SIMIL 9
g.
Respond to a Spurious SI <350°F S/D/L 3
In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
Isolate Flooding in #5 MER A/DIE 4
j.
Align Turbine Building tAto Containment D/R 8
k.
Locally Isolate the Secondary System (E-3, Attachment 1)
EID 3
All RO and SRO-l 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 SRO-I SRO-l Actual Criteria Met?
(A)lternate path 4-6 5
Yes (D)irect from bank 8
5 Yes (E)mergency or abnormal in-plant 1
2 Yes (EN)gineered safety feature (L)ow-Power I Shutdown 1
5 Yes (N)ew or (M)odified from bank including 1 (A) 2 5
Yes (P)revious 2 exams (randomly selected) 3 0
Yes (R)CA 1
1 Yes (S)imulator I (C)ontrol room
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Surry Power Station Date of Examination: 08/2012 Exam Level: RO SRO-I SRO-U-Operating Test No.:
1 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.
Swap to Th Recirc A/S/NIL/EN 2
b.
Isolate a Leaking Recirc Spray Heat Exchanger S/M/L 9
c.
Respond to a Spurious SI <350°F S/D/L 3
d.
e.
f.
g.
h.
In-Plant Systems© (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i.
Isolate Flooding in #5 MER A/DIE 4
j.
Align Turbine Building IA to Containment D/R 8
k.
All RO and SRO-l 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 SRO-U SRO-U Actual Criteria Met?
(A)lternate path 2-3 2
Yes (D)irect from bank 4
3 Yes (E)mergency or abnormal in-plant 1
1 Yes (EN)gineered safety feature
> 1 1
Yes (L)ow-Power I Shutdown 1
3 Yes (N)ew or (M)odified from bank including 1 (A) 1 2
Yes (P)revious 2 exams (randomly selected) 2 0
Yes (R)CA I
I Yes (S)imulator I (C)ontrol room