ML060870178
| ML060870178 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/13/2005 |
| From: | Gody A T Operations Branch IV |
| To: | Blevins M TXU Electric |
| References | |
| 50-445/05-302, 50-446/05-302, CPSES-09-2005, ES-401-2, NUREG-1021, Rev 9 50-445/05-302, 50-446/05-302 | |
| Download: ML060870178 (6) | |
Text
ES-401Facility:Date of Exam:TierGroup K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G*TotalKA A 2 G*Total 1133333318Emergency &21221219 Abnormal Plant Evolutions Tier Totals45545427 212232332323328Plant20111111111110 Systems Tier Totals2343443434438 1234 Notes: 1 2 3 4 5 6*7 8 9 NUREG-1021, Revision 9 For Tier 3, enter the K/A numbers, descriptions, importance ratings, and points totals on Form ES
-401-3.Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
Form ES-401-2 PWR Examination Outline Select topics from many systems; avoid selecting more than two K/A topics from a given system or evolution unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category/tier.
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. The SRO K/As must also be
linked to 10CFR55.43 or an SRO-level learnin g ob j ective.3 Generic Knowledge and Abilities Categories Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section
D.1.c for additional guidance regarding SRO sampling.
1 2 On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) 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; summarize all the
SRO-only knowledge and non-A2 ability categories in the column labeled "K" and "A". Use
du p licate p a g es for RO and SRO-onl y exams.332 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.
4 COMANCHE PEAK SRO-Only Points RO K/A Category Points 3 2 10 09/13/2005 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s)
IR#000007 Reactor Trip - Stabilization -
Recover y / 1 03 Interrelation with Reactor trip status panel 3.5 1 000008 Pressurizer Vapor Space
Accident / 3 12 Determine / interpret PZR level indicators 3.4 2 000009 Small Break LOCA / 3 406 EOP miti g ation strate g ies 3.1 3 000011 Large Break LOCA / 3 (PRA/IPE)02 Interrelation with Pumps 2.6*4 000015/17 RCP Malfunctions / 4 000022 Loss of Reactor Coolant
Makeu p / 2 08 Operate / monitor VCT level 3.4 5 000025 Loss of RHR System / 4 (IPE)01 Operational implications of Loss of RHRS
durin g all modes of o p eration 3.9 6 000026 Loss of Component Cooling
Water / 8 222 LCO and safety limits 3.4 7 000027 Pressurizer Pressure Control
S y stem Malfunction / 3 15 Determine / interpret the Actions to be taken if
PZR p ressure fails hi gh 3.7 8 000029 ATWS / 1 (PRA/IPE)000038 Steam Gen. Tube Rupture / 3 (PRA/IPE)03 Operational implication of Natural circulation 3.9 9 000040 (W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 (PRA)03 000040 - Interrelations with Valves 2.6*10 02 W/E12 - Reasons for procedures associated with Uncontrolled Depressurization of all SGs 3.3 11 000054 Loss of Main Feedwater / 4 (PRA/IPE)04 Reasons for Actions contained in EOPs for loss
of MFW 4.4 12 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 (PRA/IPE)01 Reasons for Order / time for the load sequencer 3.5 13 000057 Loss of Vital AC Inst. Bus / 6 (IPE)03 Operate / monitor Feedwater pump speed to
control S/G 3.6*14 000058 Loss of DC Power / 6 03 Determine / interpret DC loads lost; impact on
abilit y to o p erate / monitor 3.5 15 000062 Loss of Nuclear Svc Water /
4 449 Actions requiring immediate operation of
com p onents / controls 4.0 16 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment /
3 02 Operational implication of procedures
associated with LOCA Outside Containmen t 3.5 17 W/E11 Loss of Emergency Coolant
Recirc. / 4 01 Operate / monitor Components, and functions o f control / safet y s y stem s 3.9 18 W/E05 Inadequate Heat Transfer -
Loss of Secondary Heat Sink / 4 K/A Category Totals:
3 3 3 3 3 3 Group Point Total:
18 NUREG-1021, Revision 9 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s)
IR#000001 Continuous Rod Withdrawal
/ 1 000003 Dro pp ed Control Rod / 1 000005 Inoperable/Stuck Control
Rod / 1 000024 Emer g enc y Boration / 1 04 Determine / inter p ret Availabilit y of BWST 3.4 19 000028 Pressurizer Level
Malfunction / 2 01 Operational implication of PZR reference leak
abnormalities 2.8*20 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range N I / 7 000036 Fuel Handling Accident / 8 000037 Steam Generator Tube Leak /
3 000051 Loss of Condenser Vacuum /
4 000059 Accidental Liquid RadWaste
Rel. / 9 01 Operate / monitor Radioactive-liquid monitor 3.5 21 000060 Accidental Gaseous
Radwaste Rel. / 9 02 Interrelation with Auxiliary building ventilation
s y ste m 2.7 22 000061 ARM S y stem Alarms / 7 000067 Plant Fire On-site / 8 000068 Control Room Evac. / 8 000069 (W/E14) Loss of CTMT
Inte g rit y / 5 01 Reasons for Facility operating characteristics
durin g transient conditions 3.2 23 000074 (W/E06&E07) Inad. Core Coolin g / 4 (PRA)01 Determine / interpret Facility conditions /
selection of p rocedures 3.4 24 000076 High Reactor Coolant
Activit y / 9 W/E01 & E02 Rediagnosis & SI
Termination / 3 02 Interrelation with Facility's heat removal
s y stems / o p eratio n 3.5 25 W/E13 Steam Generator Over-p ressure / 4 W/E15 Containment Floodin g / 5 W/E16 High Containment Radiation /
9 406 EOP mitigation strategies 3.1 26 W/E03 LOCA Cooldown/Depress. /
4 W/E09&E10 Natural Circ. / 4 W/E08 RCS Overcooling - PTS / 4 03 Reasons for Manipulation of controls 3.7 27 K/A Category Totals:
1 2 2 1 2 1 Group Point Total:
9 NUREG-1021, Revision 9 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)
IR#003 Reactor Coolant Pump 02 Effect of loss / malfunction of S/G 3.5 28 004 Chemical and Volume Control (IPE)36 Operational implication of Solubility of b oron in water; tem p erature effec t 2.5 29 19 Operate / monitor CVCS letdown orifice isolation valve 3.1 30 005 Residual Heat Removal 03 Power supplies to pressure boundary
MOVs 2.7*31 006 Emergency Core
Coolin g 05 Effect of loss / malfunction of HPI/LPI
coolin g wate r 3.0 32 007 Pressurizer
Relief/Q uench Tan k 02 Operational implication of Method of
formin g a steam bubble in the PZ R 3.1 33 008 Component Cooling Water (IPE)02 Predict / monitor changes in CCW tem p erature 2.9 34 132 Explain / apply system limits and p recautions 3.4 35 010 Pressurizer Pressure
Control 01 Effect of loss / malfunction of Pressure
detection s y stems 2.7 36 012 Reactor Protection 01 O p erational im p lication of DNB 3.3*37 05 Operate / monitor Channel defeat
controls 3.6 38 013 Engineered Safety Features Actuation (IPE)01 Effect of loss / malfunction of Sensors and detectors 2.7*39 022 Containment Cooling 05 Predict impact of Major leak in CCS / use p rocedures to miti g ate 3.1 40 01 O p erate / monitor CCS fans 3.6 41 026 Containment S p ra y 02 Cause / effect with Coolin g wate r 4.1 42 039 Main and Reheat Steam 05 Design feature / interlock for Automatic
isolation of steam line 3.7 43 056 Condensate 04 Predict impact of Loss of condensate p um p s / use p rocedures to miti g ate 2.6 44 059 Main Feedwater 02 Effect of loss / malfunction on AFW
syste m 3.6 45 061 Auxiliary/Emergency Feedwater (PRA/IPE)02 Knowledge of bus power supplies to the following: AFW electric drive pumps 3.7*46 102 Operator responsibilities during operation 3.0 47 062 AC Electrical
Distribution 02 Effect of loss / malfunction on ED/G 4.1 48 063 DC Electrical
Distribution 01 Monitor Meters, annunciators, dials, recorders, li g hts 2.7 49 222 LCO and safet y limit s 3.4 50 064 Emergency Diesel 10 Design feature / interlock for Automatic 3.5 51 073 Process Radiation
Monitorin g 01 Cause / effect with those systems served by PRMs 3.6 52 076 Service Water (PRA/IPE)01 Predict impact of Loss of SWS / use p rocedures to miti g ate 3.5*53 078 Instrument Ai r 01 Monitor Air p ressure 3.1 54 103 Containment 01 Predict / monitor changes in pressure, temperature, humidit y 3.7 55 K/A Category Totals:
2 2 3 2 3 3 2 3 2 3 3 Group Point Total:
28 NUREG-1021, Revision 9 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)
IR#001 Control Rod Drive 002 Reactor Coolant 431 Annunciators alarms / indications / use of instructions 3.3 56 011 Pressurizer Level
Control 06 Design feature / interlock for Letdown
isolation 3.3 57 014 Rod Position Indication 03 Predict impact of Dropped rod / use p rocedures to miti g ate 3.6 58 015 Nuclear Instrumentation 02 Operational implication of compensation
o p eration 2.7 59 016 Non-nuclear
Instrumentatio n 017 In-core Temperature
Monitor 027 Containment Iodine
Removal 01 Power supplies to Fans 3.1*60 028 Hydrogen Recombiner
and Purge Control 029 Containment Pur g e 01 Monitor CPS isolation 3.8 61 033 Spent Fuel Pool
Coolin g 034 Fuel Handling
E q ui p men t 02 Effect of loss / malfunction of Radiation
monitorin g s y stem s 2.6 62 035 Steam Generator 01 Effect of loss / malfunction on RCS 4.4 63 041 Steam Dump/Turbine
B yp ass Control 045 Main Turbine
Generator 06 Predict / monitor changes in secondary
plant parameters following T/G trip 3.3 64 055 Condenser Air Removal 068 Li q uid Radwaste 071 Waste Gas Dis p osal 072 Area Radiation
Monitorin g 075 Circulatin g Water 079 Station Air 086 Fire Protection 02 Operate / monitor Fire detection panels 3.5 65 K/A Category Totals:
0 1 1 1 1 1 1 1 1 1 1 Group Point Total:
10 NUREG-1021, Revision 9 ES-401 Form ES-401-3 Facility: CategoryK/A #TopicIR#IR#2.1.30Locate / o p erate com p onents, includin g local3.966 12.1.01Conduct of o p erations re quirements3.767 Conduct of Operations 22.2.12Surveillance procedures3.068 22.2.13Ta gg in g / clearance procedures3.669 Equipment2.2.03Design, procedural, operational differences between units3.170 Control 32.3.02Facilit y ALARA p ro gram2.571 32.3.11Control radiation releases2.772 Radiation2.3.10Perform procedures to reduce radiation / personnel ex p osure2.973 Control 32.4.39Res p onsibilities in emer g enc y p lan im p lementatio n3.374 42.4.01EOP entr y conditions / immediate action ste ps4.375 Emergency Procedures/
Plan 2107 NUREG-1021, Revision 9 Generic Knowledge and Abilities Outline (Tier 3)ROSRO-Only Subtotal COMANCHE PEAK Tier 3 Point TotalDate of Exam:9/13/2005 Subtotal Subtotal Subtotal