ML102780359
| ML102780359 | |
| Person / Time | |
|---|---|
| Site: | Surry  (DPR-032, DPR-037) |
| Issue date: | 09/14/2010 |
| From: | Division of Reactor Safety II |
| To: | Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-280/10-301, 50-281/10-301 | |
| Download: ML102780359 (23) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: SURRY Power Station Date of Exam: JULY 2010 RO KJA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
A2 G*
Total 1
2 3
4 5
6 1
2 3
4. Total
- 1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
2 2
I I
2 I
2 9
2 2
4 Abnormal N/A N/A Plant Tier Totals 5
4 4
5 4
5 27 5
5 10 Evolutions 1
2 2
3 3
3 2
2 3
3 2
3 28 3
2 5
- 2.
Plant 2
I I
I I
I I
I I
0 I
I 10 0
2 I
3 Systems Tier Totals 3
3 4
4 4
3 3
4 3
3 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
3 2
3 2
2 I
2 Note:
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (I.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
2 The pOint total for each group and tier in the proposed outline must match that specified in the table.
The final pOint total for each group and tier may deviate by +/-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 5543.
ES-401 3
Form ES-401-2
. ES-401 PWR Examination Outline Form ES-401-2 EmerQency and Abnormal Plant Evolutions* Tier 1/Group 2 (RO 1 SRo)
E/APE # 1 Name 1 Safety Function K K K A A
G KIA Topic(s)
IR 1
2 3
1 2
000001 Continuous Rod Withdrawal 1 1 000003 Dropped Control Rod 11 R
R 003AA 1.02 Ability to operate and /
3.6 19 (j) or monitor the following as they apply to the Dropped Control Rod: Controls and components necessary to recover rod.
(CFR 41.7 / 4S.S /4S.6) 8J 000005 Inoperable/Stuck Control Rod / 1 R R 00SAG2.4.46 Ability to verify that 4.2 20 the alarms are consistent with the plant conditions.
(CFR: 41.10/ 43.S / 4S.3 /4S.12) tv 000024 Emergency Boration / 1 S S 024AG2.4.20 Knowledge of the 4.3 82 operational implications of EOP warnings, cautions, and notes.
(CFR: 41.10/43.5/45.13) 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 R
R 032AK3.02 Knowledge of the 3.7 21 reasons for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Guidance contained in EOP for loss of source-range nuclear instrumentation.
(CFR4I.S,41.10/4S.6/4S.13) tv 000033 Loss of Intermediate Range NI / 7 S S 033AG2.4.30 Knowledge of events 4.1 83 related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
(CFR: 41.10 143.5/45.11) 000036 (BW/A08) Fuel Handling Accident / 8
@)
000037 Steam Generator Tube Leak / 3 S
S 037 AA2.11 Ability to determine 3.8 84 and interpret the foJ/owing as they apply to the Steam Generator Tube Leak: When to isolate one or more S/Gs.
(CFR: 43.5 I 45.13)
000051 Loss of Condenser Vacuum I 4 R R 051 AG2.4.35 Knowledge of local 38 22 (t) auxiliary operator tasks during an emergency and the resultant operational effects.
(CFR: 41.10/43.5/45.13) 000059 Accidental liquid RadWaste ReI. 19 R
R 059AAI.02 Ability to operate and /
3.3 23 8) or monitor the following as they apply to the Accidental Liquid Radwaste Release: ARM system (CFR 41.7 / 45.5/45.6) 000060 Accidental Gaseous Radwaste ReI. 19 000061 ARM System Alarms I 7
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000067 Plant Fire On-site I 8 R
R 067 AA2.17 Ability to determine and 35 24 interpret the following as they apply to the Plant Fire on Site: Systems that may be affected by the fire.
(CFR: 43.5 /45.13)
~
000068 (BWIA06) Control Room Evac. 18 R
R 068AK2.07 Knowledge of the 3.1 25 interrelations between the Control Room Evacuation and the following: EO/G (CFR 41.7 / 45.7) 000069 (W/E14) Loss of CTMT Integrity 1 5 000074 (WIE06&E07) Inad. Core Cooling 14 000076 High Reactor Coolant Activity 1 9 W/E01 & E02 Rediagnosis & SI Termination I 3 WIE13 Steam Generator Over-pressure I 4 W/E15 Containment Flooding 15 W/E16 High Containment Radiation 19 BWIA01 Plant Runback I 1 BWIA02&A03 Loss of NNI-x/Y 17 BWIA04 Turbine Trip I 4 BWIA05 Emergency Diesel Actuation 1 6 BW/A07 Flooding 1 8 BW/E03 Inadequate Subcooling Margin I 4 BW/E08; W/E03 LOCA Cooldown - Depress. 14 S
S WfE03EA2.2 Ability to determine 4.1 8S and interpret the following as they apply to the (LOCA Cooldown and Depressurization): Adherence to
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appropriate procedures and operation within the limitations in the facility's license and amendments.
(CFR: 43.5/45.13)
BWIE09; CEIA13; WIE09&E10 Natural Circ.14 R
R W /E I OEK 1.2 Knowledge of the 34 26 @
operational implications of the following concepts as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLJS):
Normal, abnormal and emergency operating procedures associated with (Natural Circulation with Steam Void in Vessel with/without RVLJS).
(CFR: 41.8 /41.10/45.3)
BWIE13&E14 EOP Rules and Enclosures I~
CEIA 11; WIE08 RCS Overcooling - PTS I 4 R
R W/E08EK 1.1 Knowledge of the 3.5 27 operational implications of the following concepts as they apply to the (Pressurized Thermal Shock):
~l Components, capacity, and function of emergency systems.
(CFR: 41.8 /41.10, 45.3)
CEI A 16 Excess RCS Leakage I 2 CEIE09 Functional Recovery KIA Category Point Totals:
2 1
I 2
1 2 Group Point Total:
9 2 2 4
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Emeraencv and Abnormal Plant Evolutions - Tier 1/GrouD 1 IRO 1 SRO)
Form ES-401-2 E/APE # 1 Name 1 Safety Function K K K A A
G KIA Topic(s)
IR 1
2 3
1 2
000007 (BW/E02&E10; CE/E02) Reactor R
R 007EK3.01 Knowledge of the reasons for 4.0 J
(I)
Trip - Stabilization - Recovery 1 1 the following as the apply to a reactor trip:
Actions contained in EOP for reactor trip.
(CFR 41.5 /41.10/45.6/45.13) 000008 Pressurizer Vapor Space R
R 008AK2.02 Knowledge of the 2.7 2 8)
Accident 13 interrelations between the Pressurizer Vapor Space Accident and the following: Sensors and detectors.
(CFR 41.7 / 45.7) 000009 Small Break LOCA I 3 R
R 009EK 1.0 I Knowledge of the operational 4.2 3 ~
implications of the following concepts as they apply to the small break LOCA: Natural circulation and cooling, including reflux boiling.
(CFR 41.8 /41.10/45.3) 000011 Large Break LOCA I 3 R
ROIl EG2.4.6 Large Break LOCA:
3.7 4
Knowledge of EOP mitigation strategies.
(CFR: 41.10/43.5/45.13) 000015/17 RCP Malfunctions 1 4 S
S 015AG2.4.41 RCP Malfunctions:
4.6 76
~
Knowledge of the emergency action level thresholds and classifications.
(CFR: 41.10/43.5/45.11) 000022 Loss of Rx Coolant Makeup I 2 R
S R 022AA 1.07 Ability to operate and / or 2.8 5 @
monitor the following as they apply to the Loss of Reactor Coolant Makeup: Excess letdown containment isolation valve switches and indicators.
(CFR 41.7 / 45.5 /45.6)
S 022AG2.2.25 Loss ofRx Coolant
~
Makeup: Knowledge of the bases In 4.2 77 Technical Specifications for limiting conditions for operations and safety limits.
(CFR: 41.5/41.7/43.2) 000025 Loss of RHR System 1 4 R
R 025AA 1.12 Ability to operate and / or 3.6 6 @
monitor the following as they apply to the Loss of Residual Heat Removal System:
RCS temperature indicators.
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(CFR 41.7/45.5 /45.6)
000026 Loss of Component Cooling R
R 026AA2.03 Ability to detennine and 2.6 7 tv Water 18 interpret the following as they apply to the Loss of Component Cooling Water: The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition.
(CFR: 43.5/45.13) 000027 Pressurizer Pressure Control R
S R 027AK2.03 Knowledge of the 2.6 8
- 0)
System Malfunction 13 interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners.
(CFR 41.7 /45.7)
S 027 AG2.4.8 Pressurizer Pressure 4.5 78 tv Control Malfunction: Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
(CFR: 41.10 /43.5 / 45.13) tv 000029 A TWS I 1 R
R 029EA2.08 Ability to detennine or 3.4 9
interpret the following as they apply to a ATWS: Rod bank step counters and RPI.
(CFR 43.5 /45.13) 000038 Steam Gen. Tube Rupture I 3 R
R 038EKI.02 Knowledge of the operational 3,2 10 tv implications of the following concepts as they apply to the SGTR: Leak rate vs. pressure drop.
(CFR 41.8 / 41,10/45.3) 000040 (BW/E05; CE/E05; W/E12)
R W /E 12EA2.2 Ability to detennine and 3.4 II (tv Steam Line Rupture - Excessive Heat interpret the following as they apply to the Transfer 14 (Uncontrolled Depressurization of all Steam Generators): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
(CFR: 43.5 /45.13)
S 040AA2.04 Ability to determine and 4.7 79 ~
S interpret the following as they apply to the Steam Line Rupture: Conditions requiring ESFAS initiation.
(CFR: 43.5/45.13)
~
000054 (CE/E06) Loss of Main R
R 054AKI.02 Knowledge of the operational 3.6 12 Feedwater 14 implications of the following concepts as they apply to Loss of Main Feedwater (MFW):
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Effects offeedwater introduction on dry S/G.
(CFR 41.8 /41.10/45.3)
000055 Station Blackout I 6 S
S OssEA2.03 Ability to determine or interpret the following as they apply to a 4.7 80 I
Station Blackout: Actions necessary to restore power (CFR 43.5 / 45.13) 000056 Loss of Off-site Power I 6 NOT SELECTED 000057 Loss of Vital AC Inst Bus I 6 R
R 057AG2.2.37 Loss of Vital AC Instrument 3.6 13 G)
Bus: Ability to detennine operability and/or availability of safety related equipment.
(CFR: 41.7/43.5 145.12) t?)
000058 Loss of DC Power I 6 R
R 058AG2.2.36 Ability to analyze the effect 3.1 14 of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
(CFR: 41.10/43.2/45.13) 000062 Loss of Nuclear Svc Water I 4 R
R 062AK3.04 Knowledge of the reasons for 3.5 15 I@
the following responses as they apply to the Loss of Nuclear Service Water: Effect on the nuclear service water discharge flow header of a loss of CCW (CFR 41.4, 41.8 145.7) 000065 Loss of Instrument Air 18 NOT SELECTED W/E04 LOCA Outside Containment I 3 R
R W/E04EA 1.3 Ability to operate and lor 3.8 16 UJ monitor the following as they apply to the (LOCA Outside Containment): Desired operating results during abnonnal and emergency situations.
(CFR: 41.7 I 45.5/45.6)
W/E11 Loss of Emergency Coolant S
S W/EOllEA2.1 Ability to determine and 4.2 81 ~
Recirc. 14 interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(CFR: 43.5 I 45.13)
BW/E04; W/E05 Inadequate Heat R
R WIE05EK2.2 Knowledge of the 3.9 17 ~
Transfer - Loss of Secondary Heat Sink I 4 interrelations between the (Loss of Secondary Heat Sink) 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.
(CFR: 41.7 /45.7)
000077 Generator Voltage and Electric R
R 077AK3.02 Knowledge of the reasons for 36 18 8)
Grid Disturbances 16 the following responses as they apply to Generator Voltage and Electric Grid Disturbances: Actions contained in abnormal operating procedure for voltage and grid disturbances.
(CFR: 41.4,41.5,41.7,41.1 0/45.8)
KIA Category Totals:
3 3 3 3 3 3
Group Point Total:
18 3
3 6
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group 1(RO I SRO)
System # I Name K K K K K K A A
A A
G KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 U) 003 Reactor Coolant Pump R
R 003K4.07 Knowledge of RCPS 3.2 28 design feature(s) and/or interlock(s) which provide for the following:
Minimizing RCS leakage (mechanical seals).
(CFR: 41.7)
W 004 Chemical and Volume R
R S
R 004K6.36 Knowledge of the 2.9 29 Control effect of a loss or malfunction on the following CVCS components:
Letdown pressure control to prevent RCS coolant from flashing to steam in letdown piping.
(CFR: 41.7 /45.7)
R 004A2.25 Ability to (a) predict 3.8 30 tv the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Uncontrolled boration or dilution.
(CFR: 41.5/43.5/45.3/45.5)
S 004G2.I.23 CVCS: Ability to tv perform specific system and 4.4 86 Integrated plant procedures during all modes of plant operation.
(CFR: 4I.IO / 43.5 / 45.2 / 45.6) 005 Residual Heat Removal R
R 005A4.01 Ability to manually 3.6 31 W operate and/or monitor in the control room: Controls and indication for RHR pumps.
(CFR: 41.7 /45.5 to 45.S)
006 Emergency Core Cooling R
S R 006K 1.07 Knowledge of the 2.9 32 ~
physical connections and/or cause-effect relationships between the ECCS and the following systems: MFW System (CFR: 41.2 to 41.9 / 4S.7 to 4S.8)
S 006A2.J3 Ability to (a) predict tv the impacts of the following 4.2 87 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:
Inadvertent SIS actuation.
(CFR: 41.5/45.5)
~
007 Pressurizer Relief/Quench R
R 007A2.0S Ability to (a) predict 3.2 33 Tank the impacts of the following malfunctions or operations
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on the PRTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Exceeding PRT high-pressure limits.
(CFR: 41.5 / 43.S / 4S.3 /4S.13)
G) 008 Component Cooling Water R
R R 008K4.09 Knowledge ofCCWS 2.7 34 design feature(s) and/or interlock(s) which provide for the following:
The "standby" feature for the CCW pumps.
(CFR: 41.7)
R 008A3.0S Ability to monitor 3.0 35 0 automatic operation of the CCWS, including: Control of the electrically operated, automatic isolation valves in the CCWS.
(CFR: 41.7 /4S.S)
- 0) 010 Pressurizer Pressure Control R
R OJOKS.02 Knowledge of the 2.6 36 operational implications of the following concepts as they apply to the PZR PCS: Constant enthalpy expansion through a valve (CFR: 41.S /4S.7)
012 Reactor Protection R
R R 012K2.01 Knowledge of bus 3.3 I
power supplies to the following:
37 CD RPS channels, components, and interconnections.
(CFR: 41.7)
R 012K3.04 Knowledge of the (j) effect that a loss or malfunction of 3.8 38 the RPS will have on the following:
(CFR: 41.7/ 4S.6) 013 Engineered Safety Features R
S R OI3KS.02 Knowledge of the 29 39 ~
Actuation operational implications of the following concepts as they apply to the ESFAS: Safety system logic and reliability.
(CFR: 41.S / 4S. 7)
S 013A2.03 Ability to (a) predict ltv the impacts of the following 4.7 88 malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Rapid depressurization.
(CFR: 41.5 /43.5 / 45.3 /45.13) 022 Containment Cooling R
R 022G2.l,7 Containment Cooling 4.4 40 V System: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(CFR:41.5/43.S/4S.l2/4S.l3) 025 Ice Condenser SYSTEM NOT APPLICABLE TO SURRY.
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026 Containment Spray R
R 026K2.0l Knowledge of bus 3.4 41 power supplies to the following:
Containment spray pumps.
(CFR: 41.7)
039 Main and Reheat Steam R
R 039 A 1.03 Ability to predict 2.6 42 tV and/or monitor changes in parameters (to prevent exceeding design limits) associated with A),
operating the MRSS controls including: Primary system temperature indications, and required values, during main steam system warm-up.
(CFR: 41.5 145.5)
(J) 059 Main Feedwater R
R R 059A2.11 Ability to (a) predict 3.0 43 the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those mal functions or operations: Failure of feedwater control system.
(CFR: 41.5/43.5 /45.3/45.13)
R 059A4.03 Ability to manually 29 44 (})
operate and monitor in the control room: Feedwater control during power increase and decrease.
(CFR: 41.7/45.5 to 45.S) 061 Auxiliary/Emergency R
R R 06IK5.03 Knowledge of the 2.6 45 Feedwater operational implications of the following concepts as they apply to the AFW: Pump head effects when control valve is shut.
(CFR: 41.5/45.7)
R 061A3.04 Ability to monitor tv automatic operation of the AFW, 4.1 46 including: Automatic AFW isolation.
(CFR: 41.7/45.5)
062 AC Electrical Distribution R
R R 062K3.01 Knowledge of the 3.5 47 ~
effect that a loss or malfunction of the ac distribution system will have on the following: Major system loads.
(CFR: 41.7/45.6)
~
R 062A 1.01 Ability to predict 3.4 48 and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Significance of DIO load limits (CFR: 41.5/45.5)
(i) 063 DC Electrical Distribution R
R R 063Kl.02 Knowledge of the 2.7 49 physical connections andlor cause-effect relationships between the DC electrical system and the following systems: AC electrical system.
(CFR: 41.2 to 41.9/45.7 to 45.S)
R 06302.2.44 DC Electrical tv Distribution: Ability to interpret 4.2 50 control room indications to verify 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)
~
064 Emergency Diesel Generator R
S R 064K6.0S Knowledge of the 3.2 51 effect of a loss or malfunction of the following will have on the EDIO system: Fuel oil storage tanks.
(CFR: 41.7/45.7)
- 2)
S 064G2.I.20 Emergency Diesel 4.6 89 Generator: Ability to interpret and execute procedure steps.
(CFR: 41.10/43.5/45.12) 073 Process Radiation R
R 07302.2.22 Process Radiation 4.0 52 Monitoring Monitoring System: Knowledge of limiting conditions for operations and safety limits.
t (CFR: 41.5 143.2 I 45.2)
076 Service Water R
R 076A3.02 Ability to monitor 3.7 53 @
automatic operation of the SWS, including: Emergency heat loads.
(CFR: 41.7 / 45.5)
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078 Instrument Air R
S R 078K4.02 Knowledge of lAS 3.2 54 design feature(s) and/or interlock(s) which provide for the following:
\\~t.
Cross-over to other air systems.
(CFR: 41.7)
S 078A2.01 Ability to (a) predict 2.9 90
~.
the impacts of the following malfunctions or operations on the lAS; and (b) based on those
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predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions (CFR: 41.5/43.5/45.3/45.13) 103 Containment R
R I03K3.03 Knowledge of the 37 55 effect that a loss or malfunction of the containment system will have on the following: Loss of
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containment integrity under refueling operations (CFR: 41.7 / 45.6)
KJA Category Point Totals:
2 2
3 3
3 2
2 3
3 2
3 Group Point Total:
28 3
2 5
ES-401 5
Form ES-401-2 10"'" tV PWR Examination Outline Form ES-401-2 Plant S stems - Tier 21Group 2 IRO I SRO)
System # I Name K K K K K K A A A A G KJA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4
(])
001 Control Rod Drive S
S 001 A2.l9 Ability to (a) predict 4.0 91 the impacts of the following malfunction or operations on the CRDS-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Axial flux distribution (CFR: 41.5/43.5/45.3/45.13) tv 002 Reactor Coolant R
R 002K 1.0 I Knowledge of the 3.7 56 physical connections and/or cause*
effect relationships between the RCS and the following systems: RWST (CFR: 41.2 to 41.9/45.7 to 45.8)
V 011 Pressurizer Level Control R
ROIl A4.04 Ability to manually 3.2 57 operate andlor monitor in the control room: Transfer of PZR LCS from automatic to manual control.
(CFR: 41.7 145.5 to 45.8)
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014 Rod Position Indication R
R 0 14K5.02 Knowledge of the 28 58 operational implications of the following concepts as they apply to the RPIS: RPIS independent of demand position.
(CFR: 41.5 145.7) 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation
- 2) 017 In*core Temperature Monitor S S 017G2.4.18 In-Core Temperature 4.0 92 Monitor: Knowledge of the specific bases for EOPs.
(CFR: 41.10/43.1/45.13) 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control
029 Containment Purge R
R 029K3.01 Knowledge of the effect 2.9 59 (j) that a loss or malfunction of the Containment Purge System will have on the following: Containment parameters (CFR: 41.7/45.6) 033 Spent Fuel Pool Cooling
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034 Fuel Handling EqUipment R
R 034A2.01 Ability to (a) predict the 3.6 60 impacts of the following malfunctions or operations on the Fuel Handling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Dropped fuel element (CFR: 41.5 /43.5/45.3 145.13) 035 Steam Generator 041 Steam DumplTurbine
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Byj)ass Control 045 Main Turbine Generator R
R 045A 1.05 Ability to predict and/or 3.8 61 monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G
\\L; system controls including: Expected response of primary plant parameters (temperature and pressure) following TIG trip.
(CFR: 41.5 /45.5) 055 Condenser Air Removal W,
056 Condensate S
S 056A2.05 Ability to (a) predict the 2.5 93 impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Condenser tube leakage (CFR: 41.5 /43.5 ! 45.3 ! 45.13) lV 068 Liquid Radwaste R
R 068K6.1 0 Knowledge of the effect 2.5 62 of a loss or mal function on the following will have on the Liquid Radwaste System: Radiation monitors (CFR: 41.7 / 45.7)
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R 071 K4.0 I Knowledge of design 2.6 63 071 Waste Gas Disposal R
feature(s) and/or interIock(s) which provide for the following:
Pressure capability of the waste gas decay tank.
(CFR: 41.7)
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R R 07202.2.40 Area Radiation 3.4 64 072 Area Radiation Monitoring Monitoring: Ability to apply Technical Specifications for a system.
(CFR:41.10/43.2/43.S14S.3) lD R 07SK2.03 Knowledge of bus 2.6 65 075 Circulating Water R
power supplies to the following:
Emergency/essential SWS pumps (CFR: 41.7) 079 Station Air 086 Fire Protection KIA Category Point Totals:
I J
I I
I I
I I
0 I
I Group Point Total 10 2
1 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Date of Exam:
Category KiA #
Topic RO SRO-Only IR IR 2.1.1 S G2.1.1 Knowledge of conduct of operations 4.2 94 fJ requirements.
- 1.
(CFR: 41.10/45.13)
Conduct tp of Operations 2.1.25 R 02.1.25 Ability to interpret reference materials, such 3.9 66 as graphs, curves, tables, etc.
(CFR: 41.10/43.5/45.12)
(i) 2.1.37 R 02.1.37 Knowledge of procedures, guidelines, or 4.3 67 limitations associated with reactivity management.
(CFR: 41.1 /43.6/45.6)
~
2.1.42 S G2.I.42 Knowledge of new and spent fuel 3.4 95 movement procedures.
(CFR: 41.10 143.7 1 45.1 3) 2.1.
2.1.
Subtotal 2
2 (j) 2.2.7 S G2.2.7 Knowledge of the process for conducting 3.6 96 special or infrequent tests.
(CFR: 41.10/43.3/45.13)
- 2.
tD Equipment 2.2.13 R 02.2.13 Knowledge of tagging and clearance 4.1 68 Control procedures.
(CFR: 41.10/45.13) 2.2.18 S G2.2.IB Knowledge of the process for managing 3.9 97 tv maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.
(CFR: 41.10/43.5/45.13)
~
2.2.35 R 02.2.35 Ability to determine Technical Specification 3.6 69 Mode of Operation.
(CFR: 41.7/41.10/43.2 / 45.13) 2.2.39 R 02.2.39 Knowledge of less than or equal to one hour 3.9 70 (w
Technical Specification action statements for systems.
(CFR: 41.7 / 4110 / 43.2! 45.13) 2.2.
Subtotal 3
2
2.3.7 R 02.3.7 Ability to comply with radiation work permit 3.5 71
- 0) requirements during normal or abnormal conditions.
(CFR: 41.12 /45.10)
- 3.
Radiation R 02.3.12 Knowledge of radiological safety principles 32 72 Control 2.3.12 pertaining to licensed operator duties, such as
~
containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(CFR: 41.12/45.9/4510)
~
2.3.14 S G2.3.14 Knowledge of radiation or contamination 3.8 98 hazards that may arise during normal, abnormal, or emergency conditions or activities.
(CFR: 41.12 /43.4/45.10) 2.3.
2.3.
2.3.
Subtotal 2
I @
2.4.5 S G2.4.5 Knowledge of the organization of the 4.3 99 operating procedures network for normal, abnormal,
- 4.
and emergency evolutions.
Emergency (CFR: 41.10/43.5/45.13)
Procedures /
I})
Plan R 02.4.19 Knowledge of EOP layout, symbols, and 2.4.19 3.4 73 icons.
(CFR: 41.10/45.13) 2.4.29 S G2.4.29 Knowledge of the emergency plan.
(CFR: 41.10/43.5/45.11) 4.4 100 CD 2.4.42 R 02.4.42 Knowledge of emergency response facilities.
2.6 74 tI2 (CFR: 41.10/45.11) 2.4.45 R 02.4.45 Ability to prioritize and interpret the 4.1 75
- 3) significance of each annunciator or alarm.
(CFR: 41.10/43.5 /45.3 /45.12) 2.4.
Subtotal 3
2 Tier 3 Point Total 10 7
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Surry Power Station______________________
Date of Examination: __07/26/10 Examination Level: RO SRO Operating Test Number: ___
301____
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations GEN 2.1.20 (4.6/4.6)
R/D
Title:
Determine containment partial pressure following a loss of containment cooling (SRO only).
==
Description:==
Calculate containment partial pressure detectors during a loss of containment cooling and verify associated Technical Specifications are met.
Conduct of Operations GEN2.1.23 (4.3/4.4)
R/N
Title:
Complete 1-OPT-10.0 (Reactor Coolant Leakage
- Computer Calculated).
==
Description:==
Given plant leak rate data, complete 1-OPT-RC-10.0 and determine if the PT is SAT or UNSAT. Determine if a Technical Specification violation exists.
Equipment Control GEN2.2.37 (3.6/4.6)
R / N
Title:
Review a performance test to determine system operability (SRO - only).
==
Description:==
Given a completed performance test, review the test for possible errors and identify any system operability concerns.
Radiation Control GEN2.3.4 (3.2/3.7)
R / M
Title:
Determine Stay Time.
==
Description:==
Given current dose and dose rates in an area, determine stay times.
Emergency Procedures/Plan GEN2.4.41 (2.9/4.6)
R / M
Title:
Classify an event in accordance with EPIP-1.01 (SRO only).
==
Description:==
Modified facility JPM that will result in a Site Area Emergency due to loss of power or control room evacuation.
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; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1
Facility: __Surry Power Station______________________
Date of Examination: __07/26/10 Examination Level: RO SRO Operating Test Number: ___
301____
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations GEN 2.1.37 (4.3/4.6)
R/D Perform 1-OP-RX-010 (Documentation of Reactivity Parameters during Power Operations)
==
Description:==
Calculate the reactivity parameters for a given time in core life and boric acid concentration.
Conduct of Operations GEN2.1.23 (4.3/4.4)
R/N Complete 1-OPT-10.0 (Reactor Coolant Leakage -
Computer Calculated)
==
Description:==
Given plant leak rate data, complete 1-OPT-RC-10.0 and determine if the PT is SAT or UNSAT.
Equipment Control GEN2.2.13 (4.1/4.3)
R / M Generate a no rotation tagout to ensure a safe working boundary.
==
Description:==
Generate a tagout utilizing controlled prints to ensure a safe working boundary exists.
Radiation Control GEN2.3.4 (3.2/3.7)
R / M Determine Stay Time.
==
Description:==
Given current dose and dose rates in an area, determine stay times.
Emergency Procedures/Plan 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; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
Facility: _Surry Power Station ________
Date of Examination: ___07/26/10 Exam Level: RO SRO-I SRO-U Operating Test No.: ____
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. Recover a dropped rod. APE003.AA1.02 (3.6/3.4)
D / S I
- b. Pressurizer level channel fails low. 011.A2.11 (3.4/3.6)
M/S II
005.A4.01 (3.6/3.4)
D/S/L IV - P
- d. Establish feed flow from the condensate system IAW FR-H.1.
EPEE05.EA1.1 (4.1/4.0)
M/S/A/L IV - S
- e. Respond to a spurious CS Actuation. 026.A4.01 (4.5/4.3)
D/S/A/EN V
064A2.05 (3.1/3.2)
M/S/A/L VI
- g. Isolate a WGDT release. 071.A3.03 (3.6/3.8)
N/S/A IX
- h.
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Isolate Charging Crosstie IAW ECA-0.2. APE022.AA1.01 (3.4/3.3)
M/P/E/R II
- j. Trip Unit 1 Reactor Locally (must use MG Breakers).
EPE029EA1.12 (4.1/4.0)
M/P/E/A 1
- k. Fill the CC Head Tank using 1-BC-P-2. 008.A2.02 (3.2/3.5)
N/P VIII 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)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
Facility: _Surry Power Station ________
Date of Examination: ___07/26/10 Exam Level: RO SRO-I SRO-U Operating Test No.: ____
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. Recover a dropped rod. APE003.AA1.02 (3.6/3.4)
D / S I
- b. Pressurizer level channel fails low. 011.A2.11 (3.4/3.6)
M/S II
005.A4.01 (3.6/3.4)
D/S/L IV - P
- d. Establish feed flow from the condensate system IAW FR-H.1.
EPEE05.EA1.1 (4.1/4.0)
M/S/A/L IV - S
- e. Respond to a spurious CS Actuation. 026.A4.01 (4.5/4.3)
D/S/A/EN V
064A2.05 (3.1/3.2)
M/S/A/L VI
- g. Isolate a WGDT release. 071.A3.03 (3.6/3.8)
N/S/A IX
010.A4.01 (3.7/3.5)
N/S III In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Isolate Charging Crosstie IAW ECA-0.2. APE022.AA1.01 (3.4/3.3)
M/P/E/R II
- j. Trip Unit 1 Reactor Locally (must use MG Breakers).
EPE029EA1.12 (4.1/4.0)
M/P/E/A 1
- k. Fill the CC Head Tank using 1-BC-P-2. 008.A2.02 (3.2/3.5)
N/P VIII 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)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1