ML092881117
| ML092881117 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/15/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-327/09-302, 50-328/09-302 | |
| Download: ML092881117 (14) | |
Text
DRAFT ES-401 1 Rev. 9 ES-401. PWR Examination Outline Form ES-401-2
, Sequoy~
Facility: Sequoyat.. Date of Exam: 2009 Retake Exam RO KIA 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 & 1 2 2 1 1 9 2 2 4 2 2 Abnormal Plant N/A N/A Evolutions Tier Totals 4 5 5 5 4 4 27 5 5 10 1 2 2 4 3 2 2 2 3 2 3 3 28 3 2 5 2.
2 0 1 1 1 1 1 1 1 1 1 1 10 2 1 3 Plant Systems Tier Totals 2 3 5 4 3 3 3 4 3 4 4 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2
- 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 pointspOints and the SRO-only exam must total 25 pOints.
- 3. Systems/evolutions within each group are identified on the associated outline; outiine; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.
- 4. Select topics fro.:n fro';' 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 KIAs 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) KIAs in TIers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics "The must be relevanHo relevant to the applicable evolution or system.
- 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; iffuel handling equipment is sampled in other than Category A2 or G" 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 KIAs that are linked to 10 CFR 55.43.
Ii DRAFT
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR KS KS K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3~5 3.S 3.6 3.S 0 ~ 0 0 0 0 0 0 0 0 0 Reactor trip status panel 11 009EK1.02 Small Break LOCA LOCA/3 I3 3.S 3.5 4.2 ~ 0 0 0 0 0 0 DOD 0 0 0 0 Use of steam tables 011EK2.02 Large Break LOCA 13 I3 2.6 2.7 0 ~
~ 0 0 0 0 0 0 0 0 0 Pumps 015AK2.10 01SAK2.10 RCP Malfunctions I 4 2.8 2.8 2.8 2.8 0 ~
~ 0 0D 0DOD 0 0 0D 0D 0D 0 RCP indicators and controls 022AG2.1.31 Loss of Rx Coolant Makeup I 2 4.6 4.6 4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~
~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
026AA2.02 Loss of Component Cooling Water I18 8 2.9 3.6 0 0DOD 0 0 DOD 0 0 0 ~ 0 0 0 The cause of possible CCW loss 029EG2.2.22 ATWS 11 4.0 4.7 0 0DOD0 0 0 0 0DOD 0 0 0D ~ Knowledge of limiting conditions for operations and safety limits.
038EA1.13 Steam Gen. Tube Rupture 13 3.7 3.6 0 DODD D 0 0 0 0 0 ~ 0 DOD 0 0 0 Steam flow indicators 040AA1.09 040AA 1.09 Steam Line Rupture - Excessive Heat 3.4 3.4 0DDDDDD~DDDD 0 0 0 0 0 ~ 0 0 0 0 Setpoints of main steam safety and PORVs Transfer 14 OS4AK1.02 054AK1.02 Loss of Main Feedwater 14 I4 3.6 3.6 4.2 4.2 ~ 0 0 0 0 0 0 0 0 0 0
~DDDDDDDDDD Effects of feedwater introduction on dry S/G OSSEK3.02 055EK3.02 I6 Station Blackout 16 4.3 4.6 0DD~DDDDDDDD 0 ~ 0 0 0 0 0 0 0 0 Actions contained in EOP for loss of offsite and onsite power of 2 Page 1 of2 2111/2009 12:16 PM
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A A11 A2 A3 A4 G TOPIC:
RO AO SRO SAO 056AA1.11 Oft-site Power /6 Loss of Off-site /6 3.7 3.7 D D D D D D ~ D D D D HPI system 057AK3.01 Loss of Vital AC Inst. Bus 1
/6 4.1 4.4 D D ~ D D D D D D D D Actions contained in EOP for loss of vital ac electrical instrument bus 058AK1.01 05SAK1.01 Loss of DC Power //66 2.8 2.S 3.1 ~ D D D D D D D D D D BatterY charger equipment and instrumentation 062AK3.01 Loss of Nuclear Svc Water /414 3.2 3.5 D D ~ D D D D D D D D The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers 065AA2.05 Loss of Instrument Air 1 8
/S 3.4 4.1 D D D D D D D ~ D D D When to commence plant shutdown if instrument air pressure is decreasing 077AG2.2.39 Generator Voltage and Electric Grid 3.9 4.5 D D D D D D D D D D ~ Knowledge of less than one hour technical specification Disturbances / 6 for systems.
action statements tor WE11 EA2.1 Loss of Emergency Coolant Recirc.
Aecirc. / 4 3.4 4.2 D D D D D D D ~ D D D Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
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ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 KS Kl K5 K6 Al A1 A2 A3 A4 G TOPIC:
RO SRO 003AK3.06 Dropped Control Rod 1111 2.7 3 D 0 D0 ~ D 0 D0 D 0 DOD0 0 0 D 0 0 Reset of demand position counter to zero 032AK1.01 NI 1 7 Loss of Source Range NI/7 2.5 2.S 3.1 ~ D 0 D0 D0 D0 D 0 D 0 D0 DOD 0 0 0 Effects of voltage changes on performance 059AK2.02 Accidental Liquid RadWaste Rei. I9 ReI. 1 2.7 2.7 D 0 ~ D 0 D0 D0 D 0 D 0 D0 D0 D0 D0 Radioactive-gas monitors 068AG2.1.27 Control Room Evac. I188 3.9 4 DDDDDDDDDD~ Knowledge of system purpose and or function.
076AA1.04 076AA 1.04 I9 High Reactor Coolant Activity 19 3.2 3.4 0 0 0 0 0 0 ~ 0 0 0 0 DDDDDD~DDDD Failed fuel-monitoring equipment WE03EK3.4 LOCA Cooldown - Depress. 1 4 14 3.5 3.9 0 0 ~ 0 0 0 0 0 0 0 0 DD~DDDDDDDD RO 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.
WE07EA2.1 Saturated Core Cooling Core Cooling 3.2 4.0 0 0 0 0 DOD ~ 0 0 0 DDDDDDD~DDD Facility conditions and selection of appropriate 14 procedures during abnormal and emergency operations.
WE10EK2.1 Natural Circ. With Seam Void! 4 3.3 3.5 0 ~ 0 0 0 0 0 0 0 0 0 D~DDDDDDDDD Components and functions of control and safety systems, signals, interlocks, failure including instrumentation, Signals, modes and automatic and manual features.
WE16EA1.3 WE16EA 1.3 High Containment Radiation 1 9 2.9 3.3 DOD 0 0 0 ~ 0 0 0 0 DDDDDD~DDDD Desired operating results during abnormal and emergency situations.
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ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 003A3.03 Reactor Coolant Pump 3.2 3.1 D 0D 0D 0D 0D 0D 0D 0D 0 ~ D 0D 0 Seal DIP 004A 1.12 0D4A1.12 Chemical and Volume Control 2.8 2.B 3.2 3.2 0 0 0 0 0 0 ~ 0 0 0 0 DDDDDD~DDDD Rate of boron concentration reduction in RCS as a function of letdown flow while deborating demineralizer is in service 004A2.25 Chemical and Volume Control 3.8 3.B 4.3 4.3 0 0 0 0 0 0 0 ~ 0 0 0 DDDDDDD~DDD Uncontrolled boration or dilution
--_._- ----~-
005K1.13 Residual Heat Removal 3.3 3.3 3.5 3.5 li'lDDDDDDDDDD
~ 0 0 0 0 0 0 0 0 0 0 SIS 006K5.06 Emergency Core Cooling 3.5 3.5 3.9 3.9 0 0 0 0 ~ 0 0 0 0 0 0 DDDD~DDDDDD Relationship between ECCS flow and RCS pressure 007A2.01 Pressurizer Relief/Quench Tank 3.9 3.9 4.2 4.2 0 0 0 0 0 0 0 ~ 0 0 0 DDDDDDD~DDD Stuck-open PORV or code safety 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.5 2.7 2.7 0 0 0 0 0 DOD 0 ~ 0 DDDDDDDDD~D Relationships between PZR level and changing levels of the PRT and bleed holdup tank OOBK3.01 008K3.01 Component Cooling Water 3.4 3.4 3.5 3.5 0 0 ~ 0 0 0 0 0 0 0 0 DD~DDDDDDDD Loads cooled by CCWS 010G2.4.30 Pressurizer Pressure Control 2.7 2.7 4.1 4.1 0 0 DO 0 DOD 0 0 ~
DDDDDDDDDD~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
012K6.09 Reactor Protection 3.6 3.6 3.7 3.7 0 0 0 0 0 ~ 0 0 0 0 0 DDDDD~DDDDD CEAC 013K5.02 Engineered Safety Features Actuation 2.9 3.3 0 0 0 0 ~ 0 0 0 0 0 0 DDDD~DDDDDD Safety system logic and reliability Page 1 of3 of 3 2/11/2009 2111/2009 12:16 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR IR K1 K2 K3 K4 K5 K6 A A11 A2 A3 A4 G TOPIC:
RO SRO 022K3.02 Containment Cooling 3.0 3.0 3.3 3.3 D D ~ D D D D D D D D DD~DDDDDDDD Containment instrumentation readings 025A4.02 Ice Condenser 2.7 2.7 2.5 2.5 D D D D D D D D D ~ D DDDDDDDDD~D Containment vent fans 025G2.2.42 Ice Condenser 3.9 3.9 4.6 4.6 D D D D D D D D D D ~
DDDDDDDDDD~ Ability to recognize system parameters that are entry-level conditions for Technical Specifications 026K2.01 Containment Spray 3.4 3.4 3.6 3.6 D ~ D D D D D D D D D D~DDDDDDDDD Containment spray pumps 026K3.01 Containment Spray 3.9 3.9 4.1 4.1 D D ~ D D D D D D D D DD~DDDDDDDD CCS 039A1.03 Main and Reheat Steam 2.6 2.6 2.7 2.7 D D D D D D ~ D D D D DDDDDD~DDDD Primary system temperature indications and required values, during main steam system warm-up 059K4.02 Main Feedwater 3.3 3.3 3.5 3.5 D D D ~ D D D D D D D DDD~DDDDDDD Automatic turbine/reactor trip runback run back 061A3.03 Auxiliary/Emergency Feedwater 3.9 3.9 3.9 3.9 D D D D D D D D ~ D D DDDDDDDD~DD AFW S/G level control on automatic start 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.6 2.7 2.7 D D D D D ~ D D D D D DDDDD~DDDDD Pumps 062K2.01 AC Electrical Distribution 3.3 3.3 3.4 3.4 D ~ D D D D D D D D D D~DDDDDDDDD Major system loads 063A4.02 DC Electrical Distribution 2.8 2.8 2.9 2.9 D D D D D D D D D ~ D DDDDDDDDD~D Battery voltage indicator Page 2 of3 of 3 2111/2009 12:16 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR fR Kl K1 K2 K3 K4 K5 K6 Al A1 A2 A3 A4 G TOPIC:
RO SRO 064K4.03 Emergency Diesel Generator 2.5 3.0 0 0 0 ~ 0 0 0 0 0 0 0 Governor Govemor valve operation 073A2.0l 073A2.01 Process Radiation Monitoring 2.5 2.9 0 0 0 0 0 0 0 ~ 0 0 0 Erratic or failed power supply 076K3.02 Service Water 2.5 2.8 0 0 ~ 0 0 0 0 0 0 0 0 Secondary closed cooling water 076K4.Q3 076K4.03 Service Water 2.9 3.4 0 0 0 ~ 0 0 0 0 0 0 0 Automatic opening features associated with SWS isolation valves to CCW heat exchanges
~~---------- ---_._....._----------
.. - _._- ------~.----
~~~~~~~~~~~~~~~~~~~--
078G2.2.38 Instrument Air 3.6 4.5 0 [J DOD 0 0 0 0 0 0 0 0 0 ~ Knowledge of conditions and limitations in the facility license.
103Kl.03 103K1.03 Containment 3.1 3.5 ~ 0 0 0 0 0 0 0 0 0 0 Shield building vent system Page 3 of 3 2111/2009 12:16 PM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 011A1.03 Pressurizer Level Control 2.8 3.2 DDDDDD~DDDD VCT level 015K2.01 Nuclear Instrumentation 3.3 3.7 D~DDDDDDDDD NIS channels, components and interconnections 028K3.01 Hydrogen Recombiner and Purge 3.3 4.0 DD~DDDDDDDD Hydrogen concentration in containment Control 029G2.1.31 Containment Purge 4.6 4.3 DDDDDDDDDD~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
033K4.01 Spent Fuel Pool Cooling 2.9 3.2 DDD~DDDDDDD Maintenance of spent fuel level 034K6.02 Fuel Handling Equipment 2.6 3.3 DDDDD~DDDDD Radiation monitoring systems 041K5.05 Steam DumpiTurbine DumpfTurbine Bypass Control 2.6 3.2 DDDD~DDDDDD Basis for RCS design pressure limits 071A2.02 Waste Gas Disposal 3.3 3.6 DDDDDDD~DDD Use of waste gas release monitors, radiation, gas flow rate and totalizer 079A4.01 Station Air 2.7 2.7 DDDDDDDDD~D Cross-tie valves with lAS 086A3.03 Fire Protection 2.9 3.3 DDDDDDDD~DD Actuation of fire detectors Page 1 of 1 2111/2009 12:16 PM 2I11/200912:16PM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO G2.1.41 Conduct of operations 2.8 2.8 3.7 3.7 0 0 0 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Knowledge of the refueling processes G2.1.42 Conduct of operations 2.5 2.5 3.4 3.4 0 0 0 0 0 0 DOD 0 ~
DDDDDDDDDD~ Knowledge of new and spent fuel movement procedures G2.2.23 Equipment Control 3.1 3.1 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Ability to track Technical Specification limiting conditions for operations.
operations .
G2.2.44 Equipment Control 4.2 4.2 4.4 4.4 0 0 0 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions G2.3.11 Radiation Control 3.8 3.8 4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Ability to control radiation releases.
G2.3.5 Radiation Control 2.9 2.9 2.9 2.9 DOD 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Ability to use radiation monitoring systems G2.3.7 Radiation Control 3.5 3.5 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.11 Emergency Procedures/Plans 4.0 4.0 4.2 4.2 0 0 0 DOD 0 D D 0 ~
DDDDDDDDDD~ Knowledge of abnormal condition procedures.
G2.4.16 Emergency Procedures/Plans 3.5 3.5 4.4 4.4 0 0 0 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
G2.4.37 Emergency Procedures/Plans 3.0 3.0 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~
DDDDDDDDDD~ Knowledge of the lines of authority during implamentation of an emergency plan.
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ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 009EA2.11 Small Break LOCA I1 3 3.8 4.1 0D 0D 0D 0D 0D 0D 0D ~ 0D 0D 0D Containment temperature, pressure, and humidity 015AA2.11 RCP Malfunctions / 4 3.4 3.8 0D 0D 0D 0D 0D 0D 0D ~ 0D 0D 0D When to jog RCPs during ICC 038EG2.4.20 Steam Gen. Tube Rupture 1 3 3.8 4.3 0D 0D 0D 0D 0D 0D 0DOD 0 0 0D ~ Knowledge of operational implications of EOP warnings, cautions and notes.
040AA2.02 Steam Line Rupture - Excessive Heat 4.6 4.7 0D 0D 0D 0D 0D 0D 0D ~ 0D 0D 0D Conditions requiring a reactor trip
/4 Transfer 14 057AG2.2.44 057 AG2.2.44 Inst. Bus 16 Loss of Vital AC Ins!. /6 4.2 4.4 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~
~ Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 062AG2.1.7 Loss of Nuclear Svc Water I/44 4.4 4.7 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~
~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
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ES-401, REV 9 SRO T1 G2 PWR EXAMINATION OUTLINE T1G2 FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 060AA2.05 /9 Accidental Gaseous Radwaste ReI. /9 3.7 4.2 0D 0D 0D D0 D0 0D 0D ~ 0 D D 0 0D That the automatic safety actions have occurred as a result of a high ARM system signal
.------------------,-~---:-:---,------:----------
~------------------------------------
061AG2.4.46 ARM System Alarms /7
/7 4.2 4.2 0 D DOD D D D D D D D D D ~ Ability to verify that the alarms are consistent with the plant conditions.
WE13EA2.1 Steam Generator Over-pressure / 4 2.9 3.4 D D DODD D D D D ~ 0 D D D 0 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
we15EG2.4.30 we15EG2A.30 Containment Flooding /5
/5 2.7 4.1 D D D D D D D D D D ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
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ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A 1 A2 A3 A4 G TOPIC:
RO SRO 004G2.2.44 Chemical and Volume Control 4.2 4.4 D 0 D0 D0 D0 D0 D 0 D 0 D 0 D0 0D ~ Ability to interpret control room indications to verify the system. and understand how status and operation of a system, operator actions and directives affect plant and system conditions 00SA2.04 Residual Heat Removal 2.9 2.9 D 0 0D 0D D0 D0 D 0 D 0 ~ D D 0 0 D0 RHR valve malfunction 012A2.0S Reactor Protection 3.1 3.2 D D 0 0 D0 0D 0D D 0 0 D ~ 0 D D DOD Faulty or erratic operation of detectors and function generators OS9A2.06 Main Feedwater 2.7 2.9 D 0 0D D0 0D D0 0 [J D 0 ~ D 0 0 D 0D Loss of steam flow to MFW system 064G2.4.8 Emergency Diesel Generator 3.8 4.S D 0 D0 D0 D0 D0 D 0 0 D D0 D 0 0D ~ Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
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ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 028G2.1.23 Hydrogen Recombiner and Purge 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to perform specific system and integrated plant Control procedures during all modes of plant operation.
068A2.04 Liquid Radwaste 3.3 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Failure of automatic isolation 071A2.03 Waste Gas Disposal 2.7 3.3 0 0 0 0 0 0 0 ~ DOD 0 0 0 Rupture disk failures Page 1 of 1 2111/2009 12:16 PM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A 1 A2 A3 A4 G TOPIC:
RO SRO G2.1.9 Conduct of operations 2.9 4.5 0 0 0 0 0 0 0 0 0 0 Ii'J ~ Ability to direct personnel activities inside the control room.
G2.2.12 Equipment Control 3.7 4.1 0 0 0 0 0 0 0 0 0 0 ~ Ii'J Knowledge of surveillance procedures.
G2.2.17 Equipm ent Control Equipment 2.6 3.8 0 0 0 0 0 0 0 0 0 0 Ii'J ~ Knowledge of the process for managing maintenance activities during power operations.
G2.3.11 Radiation Control 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ii'J Ability to control radiation releases G2.3.14 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Ii'J Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.16 Emergency Procedures/Plans 3.5 4.4 0 0 0 0 0 0 0 0 0 0 Ii'J ~ Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines guidelines..
G2.4.38
. -~--~~------~~~~~-=~=-~~-=~=-~~-=~=---~~~~--~--~~~~~~~--------
Emergency Procedures/Plans 2.4 2.4 4.4 4.4 0 0 0 0 0 0 0 0 0 0 Ii'J ~ Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.
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