ML093640747
| ML093640747 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 12/08/2009 |
| From: | Division of Nuclear Materials Safety II |
| To: | Duke Energy Carolinas |
| References | |
| 50-369/09-302, 50-370/09-302 | |
| Download: ML093640747 (12) | |
Text
FACILITY NAME: McGuire Section 1 REPORT NUM BER: 05000369,370/2009302 NUMBER:
DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:
lEI' Draft Written Exam sample plan 1!1' (ES-401-1/2)
~D Draft Administrative Topics Outline (ES-301-1)
...~D
~~D Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)
Location of Electronic Files:
Draft RO/SRO Written Outline:
Draft RO Written Exam Outline ES-401-2.pdf (Attached)
Admin Topics RO:
NA Admin Topics SRO:
NA Control Room Systems Outline RO/SROi:
NA Control Room Systems Outline SROU:
NA Submitted By: ~o'c~ VerifiedBY~~
~. verifiedBY~£)~
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2009 RO NRC R.~ .ke Examination ike ES 401, Rev 9 /) fJ f) *.Jql--r . f 1L{ql!-r II fl N IJ L Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System*
System Tier/Group Importance RO/SRO KIA Description SYS003 A1.02 Reactor Coolant Pump System (RCPS) T/G 2 11 I1 RO 2.9 SRO 2.9 1
1801 Ability to predict and/or monitor changes in parameters RCP pump and motor bearing temperatures ......................... .
(to prevent exceeding design limits) associated with operating the RCPS controls including: (CFR: 41.5/45.5)
SYS003 A3.01 Reactor Coolant Pump System (RCPS) T/G 2 1I 1 RO 3.3 SRO 3.2 2
1802 Ability to monitor automatic operation of the RCPS, Seal injection flow.
flow .............................................. .
including: (CFR: 41.7/45.5) 41.7 145.5)
SYS004 K5.49 KS.49 Chemical and Volume Control System T/G 2 11 I 1 RO 2.7 SRO 3.3 3
1803 Knowledge of the operational implications of the following Purpose and method of hydrogen removal from RCS before opening system:
concepts as they apply to the CVCS: (CFR: 41.5/45.7) explosion hazard, nitrogen purge .................... .
SYSOOS SYS005 2.4.S0 2.4.50 Residual Heat Removal System (RHRS) T/G 2 11 I 1 RO 4.2 SRO 4.0 4
1804 SYS005 GENERIC Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10/43.5/45.3)
SYS006 K2.01 Emergency Core Cooling System (ECCS) 2I 1 T/G 2/1* RO 3.6 3.6. SRO 3.9 5
1805 Knowledge of bus power supplies to the following: (CFR: ECCS pumps 41.7)
SYS006 K2.04 Emergency Core Cooling System (ECCS) T/G 2 11 I1 RO 3.6 SRO 3.8 6
1806 Knowledge of bus power supplies to the following: (CFR: ESFAS-operated valves 41.7)
SYS007 A1.01 Pressurizer Relief Tank/Quench Tank System (PRTS) T/G 2112I1 RO 2.9 SRO 3.1 7
1807 Ability to predict and/or monitor changes in parameters Maintaining quench tank water level within limits design limits) associated with (to prevent exceeding deSign operating the PRTS controls including: (CFR: 41.5/45.5)
Page 1 of 11
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2009 RO NRC ~ f\ lke "ke Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS008 A2.03 Component Cooling Water System (CCWS) T/G 211 RO 3.0 SRO 3.2 8
1808 Ability to (a) predict the impacts of the following High/low CCW temperature malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunc- tions or operations: (CFR: 41.5/43.5/45.3/45.13) 41.5 /43.5 /45.3 /45.13)
SYS010 K6.04 KG.04 Pressurizer Pressure Control System (PZR PCS) 2I 1 RO 2.9 SRO 3.2 9 T/G 211 1809 Knowledge of the effect of a loss or malfunction of the PRT .....
following will have on the PZR PCS: (CFR: 41.7 //45.7) 45.7)
SYS012 K6.03 KG.03 Reactor Protection System (RPS) T/G 2112 11 RO 3.1 SRO 3.5 10 1810 Knowledge of the effect of a loss or malfunction of the Trip logic circuits ............................................... .
following will have on the RPS: (CFR: 41.7 /45/7)/ 45/7)
SYS013 A4.03 Engineered Safety Features Actuation System (ESFAS) T/G 2112I 1 RO 4.5 SRO 4.7 11 1811 Ability to manually operate and/or monitor in the control ESFAS initiation ................................................ .
room: (CFR: 41.7/45.5 to 45.8)
SYS013 K1.01 Engineered Safety Features Actuation System (ESFAS) T/G 2 11 I 1 RO 4.2 SRO 4.4 12 1812 Knowledge of the physical connections and/or cause Initiation signals for ESF circuit logic .............................. .
effect relationships between the ESFAS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)
SYS022 A2.03 Containment Cooling System (CCS) T/G 2112I 1 RO 2.6 2.G SRO 3.0 13 1813 Ability to (a) predict the impacts of the following Fan motor thermal overload/high-speed operation .................... .
malfunctions or operations on the CCS; 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) 41.5 /43.5 /45.3/45.13)
Page 2 of 11
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2009 RO NRC R. R ike .ke Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS025 K502 Ice Condenser System RO 2.6* SRO 2.S*
2.8*
14 T/G 211 2I 1 1814 Knowledge of operational implications of the following Heat transfer ............
concepts as they apply to the ice condenser system:
(CFR: 41.5/45.7)
SYS026 A2.08 A2.0S Containment Spray System (CSS) T/G 211 2I1 RO 3.2 SRO 3.7 15 1815 Ability to (a) predict the impacts of the following Safe securing of containment spray when it can be done) ... .............. .
malfunctions or operations on the CSS; 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)
SYS026 2.2.12 Containment Spray System (CSS) T/G 211 2I1 RO 3.7 SRO 4.1 16 1816 SYS026 GENERIC Knowledge of surveillance procedures. (CFR: 41.10/45.13)
SYS039 K3.04 Main and Reheat Steam System (MRSS) T/G 211 2I 1 RO 2.5* SRO 2.6*
17 1817 MFW pumps Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: (CFR: 41.7 41.7/45.6) 145.6)
SYS059 K3.02 Main Feedwater (MFW) System T/G 2 11 I 1 RO 3.6 SRO 3.7 18 1818 AFWsystem AFW system Knowledge of the effect that a loss or malfunction of the MFW M FW will have on the following: (CFR: 41.7 1/45.6) 45.6)
SYS059 K3.03 Main Feedwater (MFW) System T/G 2 11 I 1 RO 3.5 SRO 3.7.
19 1819 Knowledge of the effect that a loss or malfunction of the S/GS .......................................................... .
M FW will have on the following: (CFR: 41.7 145.6)
MFW /45.6)
SYS061 K1.01 Auxiliary I Emergency Feedwater (AFW) System T/G 2 11 I 1 RO 4.1 SRO 4.1 20 1820 Knowledge of the physical connections and/or cause- S/G system ... .................................................... .
effect relationships between the AFW and the following 41.9 /45.7 to 45.8) systems: (CFR: 41.2 to 41.9/45.7 Page 3 of 11
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2009 RO NRC R f\ ike "ke Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description SYS062 K4.10 AC Electrical Distribution System T/G 2 2/111 RO 3.1 SRO 3.5 21 1821 Knowledge of ac distribution system design feature(s) Uninterruptable ac power sources and/or interlock(s) which provide for the following: (CFR:
41.7)
SYS063 K2.01 DC Electrical Distribution System T/G 2/1 RO 2.9* SRO 3.1*
22 1822 Knowledge of bus power supplies to the following: (CFR: Major DC loads 41.7)
SYS064 A3.01 Emergency Diesel Generator (ED/G) System T/G 2 2/111 RO 4.1 SRO 4.0 23 1823 Ability to monitor automatic operation of the ED/G Automatic start of compressor and ED/G ........................... .
41.7/45.5) system, including: (CFR: 41.7 /45.5)
SYS064 K6.08 Emergency Diesel Generator (ED/G) System T/G 2 2/111 RO 3.2 SRO 3.3 24 1824 Knowledge of the effect of a loss or malfunction of the Fuel oil storage tanks ... ............................................ .
following will have on the ED/G system: (CFR: 41.7/
45.7)
SYS073 A4.03 Process Radiation Monitoring (PRM) System T/G 2 11 /1 RO 3.1 SRO 3.2 25 1825 Ability to manually operate and/or monitor in the control Check source for operability demonstration ......................... .
room: (CFR: 41.7 /45.5 to 45.8)
SYS076 K4.06 Service Water System (SWS) 2/ 1 T/G 211 RO 2.8 SRO 3.2 26 1826 Knowledge of SWS design feature(s) and/or interlock(s) Service water train separation ..................................... .
which provide for the following: (CFR: 41/7)
SYS078 A3.01 Instrument Air System (lAS) T/G 2 2/111 RO 3.1 SRO 3.2 27 1827 Ability to monitor automatic operation of the lAS, Air pressure .................................................... .
including: (CFR: 41.7/45.5)
Page 4 of 11
2009 RO NRC f\ ~ .ke Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA KiA Number KIA System KiA Tier/Group Importance RO/SRO KIA KiA Description SYS103 A4.03 Containment System RO 2.7* SRO 2.7*
28 T/G 2/1 211 1828 Ability to manually operate and/or monitor in the control ESF slave relays room: (CFR: 41.7/45.5 to 45.8)
SYS002 K3.03 Reactor Coolant System (RCS) T/G 2/2 212 RO 4.2 SRO 4.6 4.S 29 1829 Knowledge of the effect that a loss or malfunction of the Containment RCS will have on the following: (CFR: 41.7)
SYS014 A1.02 Rod Position Indication System (RPIS) T/G 2/2 212 RO 3.2 SRO 3.6 3.S 30 1830 Ability to predict and/or monitor changes in parameters Control rod position indication on control room panels ............... .
(to prevent exceeding design limits) associated with operating the RPIS controls, including: (CFR: 41.541.5/45.5)
/45.5)
SYS017 K6.01 KS.01 In-Core Temperature Monitor (ITM) System T/G 2 2/2/2 RO 2.7 SRO 3.0 31 1831 Sensors and detectors Knowledge of the effect of a loss or malfunction of the following ITM system components: (CFR: 41.7 //45.7) 45.7)
SYS029 A2.03 Containment Purge System (CPS) T/G 2 2/2/2 RO 2.7 SRO 3.1 32 1832 Startup operations and the associated required valve lineups ............ .
Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge 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)
SYS034 A3.03 Fuel Handling Equipment System (FHES) T/G 2/2 212 RO 2.9 SRO 3.3 33 1833 High flux at shutdown ............................................ .
Ability to monitor automatic operation of the Fuel Handling System, including: (CFR: 41.7/45.5)
SYS045 K4.13 Main Turbine Generator (MT/G) (MTlG) System T/G 2/2 212 RO 2.6*
2.S* SRO 2.8*
34 1834 Knowledge of MT/G system design feature(s) and/or Overs peed protection ............................................ .
Overspeed interlock(s) which provide for the following: (CFR: 41.7)
Page 5 of 11 Page50f
2009 RO NRC f\. R~e ,ke Examination
- ES401, ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Que!?tion Question KIA Number KJA KIA System KJA Tier/Group Importance RO/SRO KIA Description KJA SYS055 K1.06 Condenser Air Removal System (CARS) T/G 2/22 12 RO 2.6 SRO 2.6 35 1835 Knowledge of the physical connections and/or cause- PRM system effect relationships between the CARS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8)
SYS068 SYS06S 2.4.50 Liquid Radwaste System (LRS) T/G 2/2 RO 4.2 SRO 4.0 36 212 1836 SYS068 GENERIC Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10/43.5/45.3)
SYS071 A4.14 Waste Gas Disposal System (WGDS) T/G 2/22 12 RO 2.S 2.8 SRO 3.0 37 1837 Ability to manually operate and/or monitor in the control WDGS status alarms room: (CFR: 41.7 /45.5 to 45.8) 41.7/45.5 SYS075 K2.03 Circulating Water System T/G 2/2 RO 2.6* SRO 2.7*
38 1838 Knowledge of bus power supplies to the following: (CFR: Emergency/essential SWS pumps .................................. .
41.7)
EPE007 2.4.2 Reactor Trip T/G 1 1 / 1 RO 4.5 SRO 4.6 39 1839 EPE007 GENERIC Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.'7 41.7 /45.7
/ 45.7 /45.8)
/ 45.8)
APE008 APEOOS AK1.01 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck 0 T/G 1 T/G 1 11
/ 1 RO 3.2 SRO 3.7 40 1840 Thermodynamics and flow characteristics of open or leaking valves Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: (CFR 41.8/41.10/45.3) 41.8 /41.10/45.3)
APE015/017 AK2.08 AK2.0S Reactor Coolant Pump (RCP) Malfunctions T/G 1 1/1 11 RO 2.6 SRO 2.6 41 1841 Knowledge of the interrelations between the Reactor ........................................................
CCWS .................... . .
Coolant Pump Malfunctions (Loss of RC Flow) and the following: (CFR 41.7 / 45.7)
Page 6 of 11
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2009 RO NRC R. f... -iike "ke Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA KiA Number KiA System KIA Tier/Group TierlGroup Importance RO/SRO KIA KiA Description APE022 AK1.02 Loss of Reactor Coolant Makeup 1/ 1 T/G 1/1 RO 2.7 SRO 3.1 42 1842 Knowledge of the operational implications of the following Relationship of charging flow to pressure differential between charging and concepts*
concepts as they apply to Loss of Reactor Coolant RCS ................................ .
Makeup: (CFR 41.8/41.10/45.3) 41.8 1 41.10/45.3)
APE026 AA2.04 Loss of Component Cooling Water (CCW) T/G 1 /1 I 1 RO 2.5 SRO 2.9*
43 1843 Ability to determine and interpret the following as they The normal values and upper limits for the temperatures of the components apply to the Loss of Component Cooling Water: (CFR: cooled by CCW ... ................................ .
43.5/45.13) 43.5 145.13)
APE027 AK3.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 I/11 RO 2.8 SRO 3.3 44 1844 Knowledge of the reasons for the following responses as Why, if PZR level is lost and then restored, that pressure recovers much more they apply to the Pressurizer Pressure Control ...............................
slowly ........... . .
Malfunctions: (CFR 41.5,41.10/45.6/45.13)
EPE029 2.4.2 Anticipated Transient Without Scram (ATWS) T/G 1 11
/1 RO 4.5 SRO 4.6 45 1845 EPE029 GENERIC Knowledge of system set pOints, points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7 41.7/45.7/45.8) 145.7 1 45.8)
EPE038 EA1.10 Steam Generator Tube Rupture (SGTR) T/G 1/1 1 11 RO 3.7* SRO 3.7 46 1846 Ability to operate and monitor the following as they apply Control room radiation monitoring indicators and alarms .............. .
to a SGTR: (CFR 41.741.7/45.5/45.6) 145.5/45.6)
APE040 AK1.01 Steam Line Rupture T/G 1 I/ 1 RO 4.1 SRO 4.4 47 1847 Knowledge of the operational implications of the following Consequences of PTS concepts as they apply to Steam Line Rupture: (CFR 41.8/41.10/45.3)
APE054 AA2.08 Loss of Main Feedwater (MFW) T/G 1 /I 1 RO 2.9 SRO 3.3*
48 1848 Ability to determine and interpret the following as they Steam flow-feed trend recorder ................................... .
apply to the Loss of Main Feedwater (MFW): (CFR: 43.51 45.13)
Page 7 of 11
2009 RO NRC nke f... ~ke Examination
- ES401, ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description EPE055 EK3.02 Loss of Offsite and Onsite Power (Station Blackout) T/G 1 11 RO 4.3 SRO 4.6 49 1849 Knowledge of the reasons for the following responses as Actions contained in EOP for loss of offsite and onsite on site power
/41.10 1/
the apply to the Station Blackout: (CFR 41.5 141.10 45.6/45.13) 50 APE056 AA2.37 Loss of Offsite Power T/G 1/1 111 RO 3.7* SRO 3.8 1850 Ability to determine and interpret the following as they ED/G indicators for the following: voltage, frequency, load, load-status, and apply to the Loss of Offsite Power: (CFR: 43.543.5/45.13) 1 45.13) closure of bus tie breakers ..................... .
APE057 AA1.06 Loss of Vital AC Electrical Instrument Bus T/G 1 11 RO 3.5 SRO 35 51 1851 Ability to operate and 1/ or monitor the following as they Manual control of components for which automatic control is lost ...... .
apply to the Loss of Vital AC Instrument Bus: (CFR 41.7 1 /
45.5/45.6)
APE058 AK3.02 Loss of DC Power T/G 1 11 RO 4.0 SRO 4.2 52 1852 Knowledge of the reasons for the following responses as Actions contained in EOP for loss of dc power ...................... .
41.5,41.10/1 they apply to the Loss of DC Power: (CFR 41.5,41.10 45.6/45.1)
APE062 AA1.05 Loss of Nuclear Service Water I 1 T/G 1 11 RO 3.1 SRO 3.1 53 1853 Ability to operate and 1/ or monitor the following as they The CCWS surge tank, including level control and level alarms, and radiation apply to the Loss of Nuclear Service Water (SWS): (CFR alarm .............................................. .
41.7/45.5/45.6)
WE04 EK2.2 LOCA Outside Containment T/G 1 11 RO 3.8 SRO 4.0 54 1854 Knowledge of the interrelations between the (LOCA Facility*s heat removal systems, including primary coolant, emergency coolant, Outside the decay heat removal systems, and relations between the proper operation Containment) and the following: of these systems to the operation of the facility.
(CFR: 41.7/45.7)
(CFR:41.7/45.7)
Page 8 of 11
2009 RO NRC f ike Examination
-ike ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KJA Number KIA KIA KJA System Tier/Group Importance RO/SRO KIA KJA Description WEOS WE05 EK2.1 Loss of Secondary Heat Sink 1I 1 T/G 1/1 RO 3.7 SRO 3.9 55 1855 Knowledge of the interrelations between the (Loss of Components, and functions of control and safety systems, including Secondary Heat Sink) and the following: instrumentation, signals, interlocks, failure modes, and automatic and manual
/45.7)
(CFR: 41.7 145.7) features.
WE11 2.4.8 Loss of Emergency Coolant Recirculation I 1 T/G 1 11 RO 3.8 56 SRO 4.S 4.5 1856 WE11 GENERIC Knowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR: 41.10/43.5/45.13)
APE003 AK1.07 Dropped Control Rod RO 3.1 57 T/G 1 12 SRO 3.9 1857 Knowledge of the operational implications of the following Effect of dropped rod on insertion limits and SDM concepts as they apply to Dropped Control Rod: (CFR 41.8/41.10/45.3)
APEOOS APE005 AK2.02 Inoperable/Stuck Control Rod T/G 1 12 RO 2.S 2.5 SRO 2.6 58 1858 Knowledge of the interrelations between the Inoperable 1 / Breakers, relays, disconnects, and control room switches Stuck Control Rod and the following: (CFR 41.7 145.7)
/ 45.7)
APE024 AK1.04 Emergency Boration T/G 1 12 RO 2.8 SRO 3.6 59 1859 Knowledge of the operational implications of the following Low temperature limits for born concentration ................... .
concepts as they apply to Emergency Boration: (CFR 41.8/41.10/45.3)
APE061 AA2.04 Area Radiation Monitoring (ARM) System Alarms T/G 1 12 RO 3.1 SRO 3.S 3.5 60 1860 Ability to determine and interpret the following as they Whether an alarm channel is functioning properly .................... .
apply to the Area Radiation Monitoring (ARM) System Alarms: (CFR: 43.5/45.13)
APE067 AK3.02 Plant Fire On Site T/G 1 12 RO 2.S 2.5 SRO 3.3 61 1861 Knowledge of the reasons for the following responses as Steps called out in the site fire protection plan, FPS manual, and fire zone they apply to the Plant Fire on Site: (CFR 41.5,41.101 41.5,41.10 / manual ...................................... .
45.6/45.13) 45.6 /45.13)
Page 9 of 11
2009 RO NRC h. ~ .ke Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KJA Number KIA KJA System KIA Tier/Group Importance RO/SRO KJA Description KIA APE068 2.1.28 Control Room Evacuation T/G 1 12 1/2 RO 4.1 SRO 4.1 62 1862 APE068 GENERIC Knowledge of the purpose and function of major system components and controls. (CFR: 41.7)
WE03 EK3.2 Cool down and Depressurization LOCA Cooldown T/G 1 12 RO 3.4 SRO 3.S 63 1863 Knowledge of the reasons for the following responses as Normal, abnormal and emergency operating procedures associated with they apply to the (LOCA Cooldown and Depressurization) (LOCA Cooldown and Depressurization).
(CFR: 41.5 41.5/41.10,45.6/45.13)
/41.10, 45.6 /45.13)
WEOS EA1.1 Natural Circulation Operations T/G 1 12 RO 3.5 SRO 3.5 64 1864 Ability to operate and / or monitor the following as they Components, and functions of control and safety systems, including apply to the (Natural Circulation Operations) instrumentation, signals, interlocks, failure modes, and automatic and manual (CFR: 41.7 //45.5/45.6) 45.5 /45.6) features.
WE13 2.2.37 Steam Generator Overpressure T/G 1 12 RO 3.6 SRO 4.6 65 1865 Ability to determine operability and/or availability of safety related equipment.
WE13 GENERIC (CFR: 41.7/43.5/45.12)
GEN2.1 2.1.28 GENERIC - Conduct of Operations T/G 3 I 0 RO 4.1 SRO 4.1 66 1866 Knowledge of the purpose and function of major system components and Conduct of Operations controls. (CFR: 41.7)
GEN2.1 2.1.30 GENERIC - Conduct of Operations T/G 3 10 I 0 RO 4.4 SRO 4.0 67 1867 Ability to locate and operate components, including local controls. (CFR: 41.7 /
Conduct of Operations 45.7)
GEN2.1 2.1.31 GENERIC - Conduct of Operations T/G 3/0 3 I0 RO 4.6 SRO 4.3 68 1868 Conduct of Operations Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. (CFR: 41.10/
41.10 /
45.12)
Page 10 of 11
2009 RO NRC K f\ Jke Examination
",ke ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question KIA Number KIA System Tier/Group Importance RO/SRO KIA Description GEN2.2 2.2.21 GENERIC - Equipment Control T/G 3/0 RO 2.9 SRO 4.1 69 1869 Equipment Control Knowledge of pre- and post-maintenance operability requirements. (CFR:
41.10 / 43.2) 41.10/43.2)
GEN2.2 2.2.35 GENERIC - Equipment Control T/G 3/0 RO 3.6 SRO 4.5 70 1870 Equipment Control Ability to determine Technical Specification Mode of Operation. (CFR: 41.71 41.7/
41.10/43.2/45.13)
GEN2.3 2.3.12 GENERIC - Radiation Control T/G 3/0 RO 3.2 SRO 3.7 71 1871 Radiation Control Knowledge of radiological safety principles 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/
41.12 145.91 45.10)
GEN2.3 2.3.14 GENERIC - Radiation Control T/G 3/0 RO 3.4 SRO 3.8 72 1872 Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12/43.4 41.12 143.4 1/ 45.10)
GEN2.3 2.3.7 GENERIC - Radiation Control T/G 3/0 RO 3.5 SRO 3.6 73 1873 Radiation Control Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10) 41.12 145.10)
GEN2.4 2.4.16 GENERIC - Emergency Procedures I Plan T/G 3/0 RO 3.5 SRO 4.4 74 1874 Emergency Procedures 1/ Plan Knowledge of EOP implementation hierarchy and 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)
GEN2.4 2.4.46 GENERIC - Emergency Procedures I Plan T/G 3/0 RO 4.2 SRO 4.2 75 1875 Emergency Procedures 1/ Plan Ability to verify that the alarms are consistent with the plant conditions. (CFR:
41.10/43.5/45.3/45.12) 41.10/43.5 145.3/45.12)
Page 11 of 11