ML060870144
| ML060870144 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/13/2005 |
| From: | Gody A Operations Branch IV |
| To: | Blevins M TXU Power |
| References | |
| 50-445/05-302, 50-446/05-302, ES-401-2, NUREG-1021, Rev 9 50-445/05-302, 50-446/05-302 | |
| Download: ML060870144 (8) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: COMANCHE PEAK Date of Exam: 09/13/2005 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A G Total K A Total 1 2 3 4 5 6 1 2 3 4
- 2
- 1 1 3 3 3 3 3 3 18 Emergency & 2 1 2 2 1 2 1 9 Abnormal Plant Tier Evolutions 4 5 5 4 5 4 27 Totals 2 1 2 2 3 2 3 3 2 3 2 3 3 28 Plant 2 0 1 1 1 1 1 1 1 1 1 1 10 Systems Tier 2 3 4 3 4 4 3 4 3 4 4 38 Totals 3 Generic Knowledge and 1 2 3 4 1 2 3 4 10 Abilities Categories 2 3 3 2 Notes:
1 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.
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 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.
4 Systems/evolutions within each group are identified on the associated outline.
5 The shaded areas are not applicable to the category/tier.
6* 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 learning objective.
7 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 duplicate pages for RO and SRO-only exams.
8 For Tier 3, enter the K/A numbers, descriptions, importance ratings, and points totals on Form ES-401-3.
9 Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
NUREG-1021, Revision 9
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 - Interrelation with Reactor trip status panel 3.5 1 03 Recovery / 1 000008 Pressurizer Vapor Space Determine / interpret PZR level indicators 3.4 2 12 Accident / 3 000009 Small Break LOCA / 3 406 EOP mitigation strategies 3.1 3 000011 Large Break LOCA / 3 Interrelation with Pumps 2.6* 4 02 (PRA/IPE) 000015/17 RCP Malfunctions / 4 000022 Loss of Reactor Coolant Operate / monitor VCT level 3.4 5 08 Makeup / 2 000025 Loss of RHR System / 4 Operational implications of Loss of RHRS 3.9 6 01 (IPE) during all modes of operation 000026 Loss of Component Cooling LCO and safety limits 3.4 7 222 Water / 8 000027 Pressurizer Pressure Control Determine / interpret the Actions to be taken if 3.7 8 15 System Malfunction / 3 PZR pressure fails high 000029 ATWS / 1 (PRA/IPE) 000038 Steam Gen. Tube Rupture / 3 Operational implication of Natural circulation 3.9 9 03 (PRA/IPE) 000040 (W/E12) Steam Line Rupture 000040 - Interrelations with Valves 2.6* 10 03
- Excessive Heat Transfer / 4 (PRA)
W/E12 - Reasons for procedures associated 3.3 11 02 with Uncontrolled Depressurization of all SGs 000054 Loss of Main Feedwater / 4 Reasons for Actions contained in EOPs for loss 4.4 12 04 (PRA/IPE) of MFW 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 Reasons for Order / time for the load sequencer 3.5 13 01 (PRA/IPE) 000057 Loss of Vital AC Inst. Bus / 6 Operate / monitor Feedwater pump speed to 3.6* 14 03 (IPE) control S/G 000058 Loss of DC Power / 6 Determine / interpret DC loads lost; impact on 3.5 15 03 ability to operate / monitor 000062 Loss of Nuclear Svc Water / Actions requiring immediate operation of 4.0 16 449 4 components / controls 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / Operational implication of procedures 3.5 17 02 3 associated with LOCA Outside Containment W/E11 Loss of Emergency Coolant Operate / monitor Components, and functions of 3.9 18 01 Recirc. / 4 control / safety systems 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 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 04 Determine / interpret Availability of BWST 3.4 19 000028 Pressurizer Level Operational implication of PZR reference leak 2.8* 20 01 Malfunction / 2 abnormalities 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 Fuel Handling Accident / 8 000037 Steam Generator Tube Leak /
3 000051 Loss of Condenser Vacuum /
4 000059 Accidental Liquid RadWaste Operate / monitor Radioactive-liquid monitor 3.5 21 01 Rel. / 9 000060 Accidental Gaseous Interrelation with Auxiliary building ventilation 2.7 22 02 Radwaste Rel. / 9 system 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Reasons for Facility operating characteristics 3.2 23 01 Integrity / 5 during transient conditions 000074 (W/E06&E07) Inad. Core Determine / interpret Facility conditions / 3.4 24 01 Cooling / 4 (PRA) selection of procedures 000076 High Reactor Coolant Activity / 9 W/E01 & E02 Rediagnosis & SI Interrelation with Facility's heat removal 3.5 25 02 Termination / 3 systems / operation W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / EOP mitigation strategies 3.1 26 406 9
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 Operational implication of Solubility of 2.5 29 36 Control (IPE) boron in water; temperature effect Operate / monitor CVCS letdown orifice 3.1 30 19 isolation valve 005 Residual Heat Removal Power supplies to pressure boundary 2.7* 31 03 MOVs 006 Emergency Core Effect of loss / malfunction of HPI/LPI 3.0 32 05 Cooling cooling water 007 Pressurizer Operational implication of Method of 3.1 33 02 Relief/Quench Tank forming a steam bubble in the PZR 008 Component Cooling Predict / monitor changes in CCW 2.9 34 02 Water (IPE) temperature Explain / apply system limits and 3.4 35 132 precautions 010 Pressurizer Pressure Effect of loss / malfunction of Pressure 2.7 36 01 Control detection systems 012 Reactor Protection 01 Operational implication of DNB 3.3* 37 Operate / monitor Channel defeat 3.6 38 05 controls 013 Engineered Safety Effect of loss / malfunction of Sensors 2.7* 39 01 Features Actuation (IPE) and detectors 022 Containment Cooling Predict impact of Major leak in CCS / use 3.1 40 05 procedures to mitigate 01 Operate / monitor CCS fans 3.6 41 026 Containment Spray 02 Cause / effect with Cooling water 4.1 42 039 Main and Reheat Steam Design feature / interlock for Automatic 3.7 43 05 isolation of steam line 056 Condensate Predict impact of Loss of condensate 2.6 44 04 pumps / use procedures to mitigate 059 Main Feedwater Effect of loss / malfunction on AFW 3.6 45 02 system 061 Auxiliary/Emergency Knowledge of bus power supplies to the 3.7* 46 Feedwater (PRA/IPE) 02 following: AFW electric drive pumps Operator responsibilities during operation 3.0 47 102 062 AC Electrical Effect of loss / malfunction on ED/G 4.1 48 02 Distribution 063 DC Electrical Monitor Meters, annunciators, dials, 2.7 49 01 Distribution recorders, lights 222 LCO and safety limits 3.4 50 064 Emergency Diesel 10 Design feature / interlock for Automatic 3.5 51 073 Process Radiation Cause / effect with those systems served 3.6 52 01 Monitoring by PRMs 076 Service Water Predict impact of Loss of SWS / use 3.5* 53 01 (PRA/IPE) procedures to mitigate 078 Instrument Air 01 Monitor Air pressure 3.1 54 103 Containment Predict / monitor changes in pressure, 3.7 55 01 temperature, humidity 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 Annunciators alarms / indications / use of 3.3 56 431 instructions 011 Pressurizer Level Design feature / interlock for Letdown 3.3 57 06 Control isolation 014 Rod Position Indication Predict impact of Dropped rod / use 3.6 58 03 procedures to mitigate 015 Nuclear Instrumentation Operational implication of compensation 2.7 59 02 operation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Power supplies to Fans 3.1* 60 01 Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 01 Monitor CPS isolation 3.8 61 033 Spent Fuel Pool Cooling 034 Fuel Handling Effect of loss / malfunction of Radiation 2.6 62 02 Equipment monitoring systems 035 Steam Generator 01 Effect of loss / malfunction on RCS 4.4 63 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Predict / monitor changes in secondary 3.3 64 Generator 06 plant parameters following T/G trip 055 Condenser Air Removal 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating 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 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: COMANCHE PEAK Date of Exam: 9/13/2005 Category K/A # Topic RO SRO-Only IR # IR #
2.1.30 Locate / operate components, including local 3.9 66 1 2.1.01 Conduct of operations requirements 3.7 67 Conduct of Operations Subtotal 2 2.2.12 Surveillance procedures 3.0 68 2 2.2.13 Tagging / clearance procedures 3.6 69 2.2.03 Design, procedural, operational differences between units 3.1 70 Equipment Control Subtotal 3 2.3.02 Facility ALARA program 2.5 71 3 2.3.11 Control radiation releases 2.7 72 2.3.10 Perform procedures to reduce radiation / personnel 2.9 73 Radiation exposure Control Subtotal 3 2.4.39 Responsibilities in emergency plan implementation 3.3 74 4 2.4.01 EOP entry conditions / immediate action steps 4.3 75 Emergency Procedures/
Plan Subtotal 2 Tier 3 Point Total 10 7 NUREG-1021, Revision 9
I. GENERAL DESIGN The WOG KA Catalog Database provides a means of accessing both Rev 0 and Rev 2 versions of the NUREG-1122, Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (PWRs), with exception of the non-Westinghouse vendor-specific EPEs and APEs. Exam outlines can be generated manually or automatically. Facility-specific importance values may be given to specific KAs and KAs not relevant to the specific facility may be suppressed from view.
The KA Catalog Database may be accessed in a user or supervisor mode. The user mode ensures that the user does not make any changes to the database. They simply view the contents of the KA database. The user will be able to create and change outlines. The supervisor mode is required to suppress KAs, edit supervisor logins, and assign facility-specific values. The program starts in the user mode.
Exam outlines may be saved to any location and they may be printed in the ES-401 format. Saved exam outlines may have passwords assigned. Comments may be added to exam outlines. An Ad Hoc list of KAs may be developed, saved, and printed, if desired.
The entire Rev 2 version of the KA catalog may be printed.
The KA database location is defined by the user. This will allow facilities to create multiple versions of the KA database, if desired.
XVIII. Random Selection Methodology Random Selection: RO Exam Create two identical lists of systems for Tier, ROGroup, Category Generate Random Number Between 1 and number of systems in the list.
Begin Loop
- 1) Look for available system number in first system list in the same row as the random number. If system number is found, use it and blank out entry in first list. If a blank is found at that row number, then try to find system number in second list at same row number. If found, then use it and blank out entry in second list. If not found in second list, then generate another random number and go back to first list and look for new system.
- 2) Select the system in the same row as the random number.
- 3) Create list of KAs for Tier, ROGroup, and randomly selected system number.
- 6) Check to see if KA is in master list of KAs already selected. If it is in master list, then select another random number and select KA at that row number. If not selected, then add to master KA list.
Loop Back (until number of required KAs have been selected for specific tier, group, and category)
Go back to top of list until all tiers, groups, and categories have been cycled through.