ML111540481
| ML111540481 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/02/2011 |
| From: | Division Reactor Projects II |
| To: | Duke Energy Corp |
| References | |
| 50-413/10-301, 50-414/10-301, ES-301-1 50-413/10-301, 50-414/10-301 | |
| Download: ML111540481 (19) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility:
Catawba Nuclear Station Date of Examination: Dec. 2010 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note)
Code*
Conduct of Operations R,D Perform a shutdown margin calculation with Xenon credit in Mode 3.
Conduct of Operations R,N Determine active/inactive license for RO.
Equipment Control R,D Perform a manual NC leakage detection calculation per PT111N46001009.
Radiation Control Emergency Procedures/Plan S,D Perform emergency plan requirements for a site fire emergency.
NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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, Page 22 of 27
ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility:
Catawba Nuclear Station Date of Examination: Dec. 2010 Examination Level: RO U SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed See Note)
Code*
Conduct of Operations R,D Perform a shutdown margin calculation with Xenon credit in Mode 3.
Conduct of Operations R,N Determine active/inactive license for SRO.
Equipment Control R,D Perform a manual NC leakage detection calculation per PT/i IA46001009.
Radiation Control R,D Calculate Low Pressure Service Water discharge flow for Liquid Radioactive Release.
Emergency Procedures/Plan R,D Determine guidance for protective action recommendations.
NOTE:
All items (5 total) are required for SROs. RD applicants require only 4 items unless they are retaking only the administrative topics, when 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 (< i; randomly selected)
ES 301, Page 22 of 27
ES-301 Control Roorn!lfl-Plflt Systems Outline Form ES-301-2 NRC EXAM Facility:
Catawba Nuclear Station Date of Examination: Dec. 2010 Exam Level: RO SRO-I El SRO-U El Operating Test Number: I Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-J, including 1 ESF)
System I JPM Title Type Code*
Sy
- a. NV pump IA controlled restart per APIIIAI5500IO21 (Loss of N,S 1
Component Cooling Water) End. 6
- b. TransferEocstoCold Leg Recirc A,D,EN,S__]
2
- c. Depressurize the NC system during natural circulation D,L,S 3
- d. Establish NC system Feed and Bleed A,M,L,S 4P
- e. Restore power to 1 ETA from offsite power A,M,L,S 6
- f. Ensure proper feedwater isolation on a reactor trip A,D,L,S 45
- g. Place KC in parallel operation perOPIlIN6400IOO5 1
N:S 8
- h. Increase level in the PRT using OPI1IA/6150/004 End. 4.2 1
N,S f
In-Plant Systems (3 for RO); <3 for SRO-l); <3 or 2 for SRO-U) i.
Start MG set 1A J
D,L
[
1 j.
Place lB Hydrogen recombinerin service D,R 5
- k. 28 D/G start using AP121A155001007 A,D,E
{
6 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.
- TypeJodes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3
<C)ontrol room (D)irectfrom bank
<91
<8 I <4 (E)mergency or abnormal in-plant
> 1 I
> 1 I
> I (EN)gineered safety feature I
I 1
(L)ow-Power/Shutdown
> 1 I
> 1 I
> I (N)ew or (M)odified from bank including 1(A)
> 2 I 2
I 1
(P)revious 2 exams
< 3
< 3 I
< 2 randomly selected)
(R)CA
>1/
>1 1>1 (S)imulator ES-301, Page 23 of 27
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility:
Catawba Nuclear Station Date of Examination: Dec. 2010 Exam Level: RO El SRO-l SRO-U El Operating Test Number: I Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. NV pump 1A controlled restart per AP/1/A15500/021 (Loss of N,S 1
Component Cooling Water) End. 6
- b. Transfer ECCS to Cold Leg Recirc A,D,EN,S 2
- c. Depressurize the NC system during natural circulation D,L,S 3
- d. Establish NC system Feed and Bleed A,M,L,S 4P
- e. Restore power to 1 ETA from offsite power A,M,L,S 6
f.
Ensure proper feedwater isolation on a reactor trip A,D,L,S 4S
- g. N/A N/A N/A
- h. Increase level in the PRT using OP/1/A161501004Encl. 4.2 N,S 5
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
StartMGsetlA D,L 1
j.
Place lB Hydrogen recombiner in service D,R 5
- k. 2B D/G start using AP/21A15500/007 A,D,E
[
6 All RD 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 / SRO-I / SRO-U (A)lternate path 4-6 I 4-6
/ 2-3 (C)ontrol room (D)irectfrom bank
<9/
<8 I <4 (E)mergency or abnormal in-plant
> 1 /
> I
/
> 1 (EN)gineered safety feature
/
/
1 (L)ow-Power / Shutdown
> 1 I
> I
/
> 1 (N)ew or (M)odified from bank including 1 (A) 2 I 2
/
I (P)revious 2 exams
< 3
< 3 /
< 2 (randomly selected)
(R)CA
>1/
>1 1>1 (S)imu lator ES-301, Page 23 of 27
ES-301 Control Room!ln-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Dec. 2010 Exam Level: RO LI SRO-l LI SRO-U Operating Test Number: I Control Room Systems (8 for RO); (7 forSRO-l); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
I Fn a.
- b. Transfer ECCS to Cold Leg Recirc A,D,EN,S 2
c.
- d. Establish NC system Feed and Bleed A,M,L,S 4P e.
f.
g.
h.
In-Plant Systems(3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
Start MG set 1A D,L 1
j.
Place I B hydrogen iecombiner in service D,R 5
- k. 2B DIG start using AP121N55001007 A,D,E 6
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 I SRO-l / SRO-U (A)lternate path 4-6 I 4-6
/ 2-3 (C)ontrol room (D)irect from bank
< 9 I
< 8 I
< 4 (E)mergency or abnormal in-plant
> I I
> 1 I
> 1 (EN)gineeredsafetyfeature
/
/ >1 (L)ow-Power / Shutdown
> 1 /
> 1
/
> I (N)ew or (M)odified from bank including 1(A) 2 I 2
I 1
(P)revious -2 exams
< 3
< 3 I
< 2 (randomly selected)
(R)CA
>1/
>1
/>1 (S)imulator ES-3D 1, Page 23 of 27
ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Catawba Dateof Exam: 2010 RO K/A Category Points SRO-OnIy Points Tier Group K
K K
KK KAAAAG 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 E
2 1
2 9
2 2
4 Abnormal Plant
N/A N/A
Evolutions Tier Totals 27 5
5 10 1
32332323232 28 3
2 5
2.
2 1
1 1
11 1
011 1
1 10 2
1 3
Plant Systems Tier Totals 4
3 4
4 3
4 2
4 3
4 3
38 3
8
- 3. GenericKnowledgeandAbilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
2 2
2 1
1 Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RD and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier 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 RD 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 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 (lR) of 2.5 or higher shall be selected.
Use the RD and SRD ratings for the RD and SRD-only portions, respectively.
6.
Select SRD 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 KAs.
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 SRD-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 RD and SRD-on{y 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 SRD selections to K/As that are linked to 10 CFR 55.43..
ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 007EK2.02 Reactor Trip
- Stabilization
- Recovery 2.6 2.8 Breakers, relays and disconnects OO8AK1.01 Pressurizer Vapor Space Accident/ 3 3.2 3.7 Thermodynamics and flow characteristics of open or leak-ing valves 009EK2.03 Small Break LOCA /3 3
3.3 S/Gs OIIEG2.l.7 LargeBreakLOCA/3 4.4 4.7 fl Abilitytoevaluateplantperformanceandmake operational judgments based on operating characteristics, reactor behavior and instwment interpretation.
015AA2.08 RCP Malfunctions / 4 3.4 3.5 When to secure RCPs on high bearing temperature 022AG2.4.34 Loss of Rx Coolant Makeup / 2 4.2 4.1 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 025AK3.03 Loss of RHR System / 4 3.9 4.1 Immediate actions contained in EOP for Loss of RHRS 029EA2.06 ATWS / 1 3.8 3.9 LI LI LI LI LI LI LI LI LI Main turbine trip switch position indication 038EA1.15 Steam Gen. Tube Rupture / 3 3.9 3.9 LI LI LI LI LI LI LI LI LI LI AFW source level and capacity (chart) 040AK2.0l Steam Line Rupture
- Excessive Heat 2.6 2.5 LI LI LI LI LI LI LI LI LI LI Valves Transfer I 4 054AK1.02 Loss of Main Feedwater / 4 3.6 4.2 LI LI LI LI LI LI LI LI LI LI Effects of feedwater introduction on dry S/G Page 1 of2 03/17/2010 6:40AM
ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 056AA2.83 Loss of Off-site Power /6 2.7 3
[] []
[] []
[]
Instrument air pressure gauge 062AG2.4.6 Loss of Nuclear Svc Water/4 3.7 4.7
]
El El El El Knowledge symptom based EOP mitigation strategies.
065AK3.03 Loss of Instrument Air! 8 2.9 3.4 El El El El El El El El El El Knowing effects on plant operation of isolating certain equipment from instrument air 077AA1.03 Generator Voltage and Electric Grid 3.8 3.7 Voltatge regulator controls Disturbances / 6 WE04EK1.1 LOCA Outside Containment! 3 3.5 3.9 El Components, capacity, and function of emergency systems.
WEO5EA1.l Inadequate HeatTransfer-Loss of 4.1 4.0 El El El El El El El El El El Components and functions of control and safety systems, Secondary Heat Sink / 4 including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE1 1 EK3.4 Loss of Emergency Coolant Recirc. /4 3.6 3.8 El El I] El El El El El El El El 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.
Page 2 of 03/17/2010 6:40AM
ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO OO1AA1.05 Continuous Rod Withdrawal / 1 4.3 4.2 LI Reactor trip switches 028AA2.12 Pressurizer Level Malfunction / 2 3.1 3.5 Cause for PZR level deviation alarm: controller mal function or other instrumentation malfunction 036AK3.Ol Fuel Handling Accident / 8 3.1 3.7 Different inputs that will cause a reactor building evacuation 060AK3.03 Accidental Gaseous Radwaste Rel. /9 3.8 4.2 Actions contained in EOP for accidental gaseous-waste release 067AK1.Ol Plant Fire On-site / 98 2.9 3.9 Fire classifications by type 068AG2.4.45 Control Room Evac. /8 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.
076AK2.O1 High Reactor Coolant Activity / 9 2.6 3
LI LI LI LI LI LI LI LI LI LI Process radiation monitors WEO8EK1.2 RCS Overcooling
- PTS / 4 3.4 4.0 LI LI LI LI LI LI LI LI LI LI Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).
WEO9EA2.1 Natural Circ. / 4 3.1 3.8 LI LI LI LI LI LI LI LI LI LI Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Page 1 of 1 03/17/2010 6:41 AM
ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
RO SRO 003K 1.13 Reactor Coolant Pump 2.5 2.5
[]
[]
RCP Bearing Lift Oil Pump 003K3.0l Reactor Coolant Pump 3.7 4.0 RCS 004K3.08 Chemical and Volume Control 3.6 3.8 RCP seal injection 005K1.l0 Residual Heat Removal 3.2 3.4
[] [] []
[]
[]
[]
CSS 005K4.05 Residual Heat Removal 2.5 2.9 Relation between RHR flowpath and refueling cavity 006K2.02 Emergency Core Cooling 2.5 2.9 Valve operators for accumulators 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4
[]
Method of farming a steam bubble in the PZR 010K6.02 Pressurizer Pressure Control 3.2 3.5 PZR 012K5.01 Reactor Protection 3.3 3.8 DNB 012K6.04 Reactor Protection 3.3 3.6
[] []
[]
Bypass-block circuits 013K2.01 Engineered Safety Features Actuation 3.6 3.8 j
j ESFAS/safeguards equipment control Page 1 of 3 03/17/2010 6:41 AM
Fan motor over-current Knowledge of limiting conditions for operations and safety limits.
Ability to verify that the alarms are consistent with the plant conditions.
Failure of automatic recirculation transfer Pump starts and correct MOV positioning Air ejector PRM Indications and alarms for main steam and area radiation monitors (during SGTR)
Feed Pump speed, including normal control speed for ICS AFW automatic start upon loss of MFW pump, S/G level, blackout or safety injection Safety-related indicators and controls ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 013K5.02 Engineered Safety Features Actuation 2.9 3.3
[]
]
Safety system logic and reliability LI 022A2.Ol Containment Cooling 2.5 2.7 LI LI LI LI LI LI LI 025G2.2.22 Ice Condenser 4.0 4.7 LI LI LI LI LI LI LI 025G2.4.46 Ice Condenser 4.2 4.2 LI LI LI LI LI LI LI 026A2.02 Containment Spray 4.2 4.4 LI LI LI LI LI LI LI 026A3.01 Containment Spray 4.3 4.5 LI LI LI LI LI LI LI 039A1.10 Main and Reheat Steam 2.9 3.0 LI LI LI LI LI LI 039A2.03 Main and Reheat Steam 3.4 3.7 LI LI LI LI LI LI LI 059A1.07 Main Feedwater 2.5 2.6 LI LI LI LI LI LI 061K4.02 Auxiliary/EmergencyFeedwater 4.5 4.6 LI LI LI LI LI LI 062A3.05 AC Electrical Distribution 3.5 3.6 LI LI LI LI LI LI LI LI LI LI LI LI LI LI LILILI LILI LILI LILILI LILI LILILI LILILI LILILI LILILI LILI Page 2 of 3 03/17/2010 6:41 AM
ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RD SRO 063K3.02 DC Electrical Distribution 3.5 3.7 Components using DC control power 063K4.02 DC Electrical Distribution 2.9 3.2 Breaker interlocks, permissives, bypasses and cross-ties.
064K1.02 Emergency Diesel Generator 3.1 3.6 D/G cooling water system 073G2.2.40 Process Radiation Monitoring 3.4 4.7 Ability to apply technical specifications for a system.
076A4.02 Service Water 2.6 2.6
[] []
[]
[] []
[]
SWS valves 1 03A4.04 Containment 3.5 3.5 Phase A and phase B resets Page 3 of 3 03/17/2010 6:41 AM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 001G2.2.44 Control Rod Drive 4.2 4.4 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 011K3.02 Pressurizer Level Control 3.5 3.7 RCS 015A1.05 Nuclear Instrumentation 3.7 3.9 Imbalance (axial shape) 017A2.02 In-core Temperature Monitor 3.6 4.1 Core damage 027K2.O1 Containment Iodine Removal 3.1 3.4 Fans 029A3.01 Containment Purge 3.8 4.0 CPS isolation 035K5.01 Steam Generator 3.4 3.9 Effect of secondary parameters, pressure and temperature on reactivity 045A4.02 Main Turbine Generator 2.7 2.6 LI LI LI T/G controls, including breakers 068K1.07 Liquid Raclwaste 2.7 2.9 LI LI LI LI LI LI LI LI LI LI Sources of liquid wastes for LRS 079K4.01 Station Air 2.9 3.2 LI LI LI LI LI LI LI LI LI LI Cross-connect with AS Page lofI 03/17/2010 6:41AM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401 -2 KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
Knowledge of RO duties in the control room during fuel handling.
Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
Knowledge of the process for managing troubleshooting activities.
Knowledge of the process for making changes to procedures Knowledge of radiation monitoring systems Knowledge of radiation exposure limits under normal and emergency conditions Ability to comply with radiation work permit requirements during normal or abnormal conditions Ability to identify post-accident instrumentation.
Knowledge of annunciators alarms, indications or response procedures Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
RO SRO G2.1.44 Conduct of operations 3.9 3.8 El El El G2.1.5 Conduct of operations 2.9 3.9 El G2.2.20 Equipment Control 2.6 3.8 G2.2.6 Equipment Control 3.0 3.6 G2.3.15 RadiationControl 2.9 3.1 LID Ii G2.3.4 Radiation Control 3.2 3.7 El El El El El El El El [1 El G2.3.7 Radiation Control 3.5 3.6 El El El El El El El El El El I 02.4.3 Emergency Procedures/Plans 3.7 3.9 El El El El El El El El El El 02.4.31 Emergency Procedures/Plans 4.2 4.1 El El El El El El El El El El 02.4.47 Emergency ProcedureslPlans 4.2 42 El El El El El El El El El El Il Page 1 of 1 03/17/2010 6:42AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
O11EG2.2.37 Large Break LOCA/ 3 025AG2.1.7 Loss of RHR System / 4 026AA2.05 Loss of Component Cooling Water /8 056AA2.46 Loss of Off-site Power / 6 077AG2. 1.28 Generator Vdtage and Electric Grid Disturbances I 6 WEO5EA2.2 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 SRO TIGI PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.6 4.6 4.4 4.7 2.4 2.5 4.2 4.4 4.1 4.1 3.7 4.3 FORM ES-401-2 TOPIC:
Ability to determine operability and/or availability of safety related equipment Ability to evuate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
The normal vaues for CCW-header flow rate and the flow rates to the components cooled by the CCWS That the ED/Gs have started automatically and that the bus tie breakers are closed Knowledge of the purpose and function of major system components and controls.
Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
Page 1 of 1 03/17/2010 6:45AM
ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G
RO SRO 032AA2.09 Loss of Source Range NI / 7 2.5 2.9 LI LI LI LI LI LI LI LI LI LI 060AA2.04 Accidental Gaseous Radwaste Rel. / 9 2.6 3.4 LI LI LI LI LI LI LI LI LI LI LILILILILILILILILI LILILILILILILILILI 061AG2.4.46 ARM System Alarms 17 4.2 4.2 LI wel3EG2.l.27 Steam Generator Over-pressure/ 4 3.9 4
Effect of improper HV setting The effects on the power plant of isolating a given radioactive-gas leak Ability to verify that the alarms are consistent with the plant conditions.
Knowledge of system purpose and or function.
Page 1 of I 03/17/2010 6:46AM
ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 004A2.21 Chemical and Volume Control 2.7 2.7 Excessive letdown flow, pressure and temperatures on ion exchange resins (also causes) 013G2.2.38 EngineeredSafetyFeaturesActuation 3.6 4.5 Knowledge of conditions and limitations in the facility license.
022G2.4.l Containment Cooling 4.6 4.8 Knowledge of EOP entry conditions and immediate action steps.
064G2.4.1 Emergency Diesel Generator 4.6 4.8 Knowledge of EOP entry conditions and immediate action steps.
073A2.Ol Process Radiation Monitoring 2.5 2.9 LI LI fl LI LI Erratic or failed power supply Page 1 of 1 03/17/2010 6:46 AM
ES-401, REV9 KA NAME I SAFETY FUNCTION:
028G2.2.25 Hydrogen Recombiner and Purge Control 068A2.04 Liquid Radwaste 071G2.4.4 Waste Gas Disposal SRO T2G2 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
RO SRO 3.2 4.2 4.5 4.7 FORM ES-401 -2 TOPIC:
Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Failure of automatic isolation Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Page 1 of 1 03/17/2010 6:46AM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR 1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
RO SRO G2.l.17 Conduct of operations 3.9 4.0 Ability to make accurate, clear and concise verbal reports.
G2.l.7 Conduct of operations 4.4 4.7
[]
[] []
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
G2.2.20 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.
G2.3.12 Radiation Control 3.2 3.7 El Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.29 EmergencyProcedures/Plans 3.1 4.4 El El El El El El El El El El Knowledgeoftheemergencyplan.
G2.4.44 Emergency Procedures/Plans 2.4 4.4 El El El El El El El El El El Knowledge of emergency plan protective action recommendations.
Page 1 of 1 03/17/2010 6:47AM