ML061290185
| ML061290185 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/01/2005 |
| From: | Operations Branch IV |
| To: | Southern California Edison Co |
| References | |
| 50-361/05-301, 50-362/05-301 | |
| Download: ML061290185 (23) | |
Text
1 ES-401 PWR Examination Outline Form ES-401-2 Date of Exam: April 2005 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Total A2 G*
Total
- 1.
Emergency &
Abnormal Plant Evolutions 1
3 4
1 N/A 2
4 N/A 4
18 2
4 6
2 2
2 1
N/A 0
2 N/A 2
9 3
1 4
Tier Totals 5
6 2
N/A 2
6 N/A 6
27 5
5 10
- 2.
Plant Systems 1
3 1
2 3
3 2
2 3
3 3
3 28 3
2 5
2 1
1 1
1 1
1 1
1 1
1 0
10 2
1 3
Tier Totals 4
2 3
4 4
3 3
4 4
4 3
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 3
2 2
10 1
2 2
2 7
Ensure that at least two topics from every applicable K/A 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 K/A category shall not be less than two).
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.
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 ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
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.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall
2 be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
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.
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. Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, importance ratings, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
3 ES-401PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G
K/A Statements KA/IR 000007 (BW/E02&E10; CE/E02)
Reactor Trip - Stabilization - Recovery
/ 1 S
Knowledge of the process for determining the internal and external effects on core reactivity.
2.2.34 2.9 000008 Pressurizer Vapor Space Accident / 3 R
Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: ECCS termination or throttling criteria AK3.05 4.0 000009 Small Break LOCA / 3 R
Ability to operate and monitor the following as they apply to a small break LOCA:
Secondary pressure control EA1.14 3.4 000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 R
Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Effects of unbalanced RCS flow on in-core average temperature, core imbalance, and quadrantpower tilt AK1.05 2.7 000022 Loss of Rx Coolant Makeup /
2 R
S Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Pump Makeup: Whether charging line leak exists Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.
AA2.01 3.2 2.4.23 4.0 000025 Loss of RHR System / 4 R
Knowledge of the parameters and logic used to assess the 2.4.21
4 S
status of safety functions including Core cooling and heat removal.
Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Increasing reactor building sump level 3.7 AA2.03 3.8 000026 Loss of Component Cooling Water / 8 R
S Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water:
The CCWS surge tank, including level control and level alarms, and radiation alarm Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water:
The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition AA1.05 3.1 AA2.03 2.9 000027 Pressurizer Pressure Control System Malfunction / 3 R
Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions: Definition of saturation temperature AK1.01 3.1 000029 ATWS / 1 R
Ability to determine or interpret the following as they apply to a ATWS:
Reactor trip breaker indicating lights EA2.07 4.2
5 000038 Steam Gen. Tube Rupture / 3 R
Knowledge of the reasons for the following responses as they apply to SGTR: Criteria for securing RCP EK3.08 4.1 000040 (BW/E05; CE/E05; W/E12)
Steam Line Rupture - Excessive Heat Transfer / 4 R
Knowledge of the facility ALARA program.
2.3.2 2.5 000054 (CE/E06) Loss of Main Feedwater / 4 R
AK2 not used due to no KA
> 2.4 Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater: Reactor and/or turbine trip, manual and automatic.
Deleted AK3.01 4.1 000055 Station Blackout / 6 R
AK2 Not used due to no KA
> 2.5 Actions necessary to restore power.
Deleted EA2.03 3.9 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 R
S Ability to operate and/or monitor the following as they apply to the loss of vital AC bus: Manual inverter swapping Knowledge of the process for managing troubleshooting activities.
AA1.01 3.7 2.2.20 3.3 000058 Loss of DC Power / 6 R
Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Use of dc control power by D/Gs AK3.01 3.4 000062 Loss of Nuclear Svc Water / 4 R
Knowledge of system purpose and or function.
2.1.27 2.8 000065 Loss of Instrument Air / 8 R
Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Failure modes of air-operated AA2.08 2.9
6 equipment W/E04 LOCA Outside Containment /
3 R
Knowledge of the operational implications of the following concepts as they apply to the (LOCA Outside Containment) Components, capacity, and function of emergency systems.
EK1.1 3.5 W/E11 Loss of Emergency Coolant Recirc. / 4 S
Knowledge of the process for determining if the proposed change, test, or experiment involves an unreviewed safety question.
2.2.8 3.3 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 R
Knowledge of the interrelations between the (Inadequate Heat Transfer) and the following: Facility heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these s.
EK2.2 4.2 SRO K/A Category Totals:
N A
N A
N A
N A
2 4
SRO Group Point Total:
6 RO K/A Category Totals:
3 2
3 3
4 3
RO Group Point Total:
18
7 ES-401PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G
K/A Statement(s)
IR 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod /
1 000024 Emergency Boration / 1 R
Knowledge of EOP layout, symbols, and icons.
2.4.19 2.7 000028 Pressurizer Level Malfunction /
2 R
Ability to track limiting conditions for operations.
2.2.23 2.6 000032 Loss of Source Range NI / 7 S
Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation:
Maximum allowable channel disagreement AA2.07 3.4 000033 Loss of Intermediate Range NI /
7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 R
Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM)
System Alarms: ARM panel displays AA2.01 3.7
8 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac.
/ 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity /
9 W/EO1 & E02 Rediagnosis & SI Termination / 3 R
Knowledge of the interrelations between the (Reactor Trip or Safety Injection/Rediagnosis) and the following:
Facility heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper EK2.2 3.8 W/E13 Steam Generator Over-pressure /
4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 R
Knowledge of the operational implications of the following concepts as they apply to the (Plant Runback):
Components, capacity, and function of emergency systems.
AK1.1 3.0 BW/A02&A03 Loss of NNI-X/Y / 7 R
Knowledge of the inter-relations between the (Loss of NNI-X) and the following: Facility s heat removal systems, AK2.2
9 S
including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to Knowledge of conditions and limitations in the facility license.
3.8 2.1.10 3.9 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation /
6 BW/A07 Flooding / 8 R
Ability to determine and interpret the following as they apply to the (Flooding):
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
AA2.1 3.6 BW/E03 Inadequate Subcooling Margin
/ 4 R
S Knowledge of the operational implications of the following concepts as they apply to the (Inadequate Subcooling Margin): Annunciators and conditions indicating signals, and remedial actions associated with the (Inadequate Subcooling Margin).
Ability to determine and interpret the following as they apply EK1.3 4.0 EA2.2
10 to the (Inadequate Subcooling Margin)
Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
4.0 BW/E08; W/E03 LOCA Cooldown -
Depress. / 4 R
Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown)
Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown).
EK3.2 3.6 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 S
Ability to determine and interpret the following as they apply to the (Natural Circulation Cooldown):
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
EA2.1 4.2 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling -
PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery SRO K/A Category Point Totals:
3 1
SRO Group Point Total:
4 RO K/A Category Point Totals:
2 2
1 0
2 2
RO Group Point Total:
9
11 ES-401PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Statement(s)
KA/IR 003 Reactor Coolant Pump R
R Knowledge of bus power supply to the following:
RCPs.
Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effects of fluctuation of K2.01 A2.04 2.8 004 Chemical and Volume Control R
R Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: Interface between HPI flow path and excess letdown flow path Ability to monitor automatic operation of the CVCS,including:
PZR level and pressure K1.25 3.2 A3.10 3.9 005 Residual Heat Removal R
Ability to explain and apply all system limits and precautions.
2.1.32 3.4 006 Emergency Core Cooling R
Knowledge of the operational implications K5.02
12 of the following concepts as they apply to ECCS:
Relationship between accumulator volume and pressure 2.9 007 Pressurizer Relief/Quench Tank R
Ability to manually operate and/or monitor in the control room:
Relationships between PZR level and changing levels of the PRT and bleed holdup tank A4.09 2.7 008 Component Cooling Water R
Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:
Operation of the surge tank, including the associated valves and controls K4.02 2.7 010 Pressurizer Pressure Control R
R S
Knowledge of the operational implications of the following concepts as the apply to the PZR PCS: Constant enthalpy expansion through a valve Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS:
Controllers and positioners Ability to (a) predict the impacts of the following malfunctions or K5.02 3.0 K6.07 2.5 A2.02
13 operations on the PZR PCS; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures.
3.5 012 Reactor Protection R
R Knowledge of RPS design feature(s) and/or interlock(s) which provide for the following:
Separation of control and protection circuits Ability to manually operate and/or monitor in the control room: Bistable, trips, reset and test switches.
K4.09 3.1 A4.04 3.3 013 Engineered Safety Features Actuation R
Ability to predict and/or monitor changes in parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including:
Containment radiation A1.07 3.9 022 Containment Cooling R
R Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including:
Containment pressure Ability to monitor automatic operation of the CCS, including Initiation of safeguards mode of operation A1.02 3.8 A3.01 4.3
14 025 Ice Condenser Ability to manually operate and/or monitor in the control room: Ice condenser isolation valves Delete d
026 Containment Spray R
Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: Cooling water K1.02 4.1 039 Main and Reheat Steam R
S Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: S/G Knowledge of procedures relating to emergency response to sabotage.
K1.01 3.2 2.4.28 3.3 059 Main Feedwater R
Knowledge of the operational implications of the following concepts as the apply to the MFW:Increased MFW pump discharge with increased turbine speed K5.12 2.5 061 Auxiliary/Emergency Feedwater R
S Knowledge of AFW design feature(s) and/or interlock(s) which provide for the following:Crossties between multi-unit stations Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; K4.09 3.3 A2.04
15 and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: pump failure or improper operation.
3.8 062 AC Electrical Distribution R
(multi-unit) Knowledge of the design, procedural, and operational differences between units.
2.2.3 3.1 063 DC Electrical Distribution R
S Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: ED/G Ability to apply technical specifications for a system.
K3.01 4.1 2.2.12 064 Emergency Diesel Generator R
R Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system:
Air receivers Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: ED/G lube oil temperature and pressure K6.07 2.9 A1.01 3.1 073 Process Radiation Monitoring R
Knowledge of the process for performing a containment purge.
2.3.9 2.5 076 Service Water R
Knowledge of the effect that a loss or malfunction of the SWS K3.08
16 will have on the following:
Radioactive liquid waste discharges 2.9 078 Instrument Air S
R Ability to monitor automatic operation of the IAS, including:
Air pressure Ability to (a) predict the impacts of the following mal-functions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunction A3.01 3.2 A2.01 2.9 103 Containment R
R Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operation Containment evac Ability to manually operate and/or monitor in the control room:
Operation of the Containment personnel airlock door A2.04 3.6 A4.06 2.9
17 SRO K/A Category Point Totals:
N A
N A
N A
N A
N A
N A
N A
3 N
A N
A 2
SRO Group Point Total:
5 K/A Category Point Totals:
3 1
2 3
3 2
2 3
3 3
3 RO Group Point Total:
28
18 ES-401PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation R
Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including: Quadrant power tilt ratio A1.04 3.5 016 Non-nuclear Instrumentation No KA statement importances
>2.5 (A1)
Delete d
017 In-core Temperature Monitor S
Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
Thermo-couple open and A2.01 3.5 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control R
S Knowledge of the effect that a loss or malfunction of the HRPS will have on the following:
Hydrogen concentration in containment Malfunctions or operations on the HRPS; and (b) those predictions, use procedures to correct, control K3.01 4.0 A2.03
19 or mitigate the consequences of those malfunctions or operations:
The hydrogen air concentration in excess of limit flame propagation or detonation with 4.0 029 Containment Purge R
Knowledge of bus power supplies to the following:
Purge exhaust radiation monitors K2.03 2.7 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator R
Ability to (a) predict the impacts of the following mal-functions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Small break LOCA A2.06 4.6 041 Steam Dump/Turbine Bypass Control R
Knowledge of the operational implications of the following concepts as the apply to the SDS:
Relationship of no-load T-ave. to saturation pressure relief setting on valves K5.01 3.2 045 Main Turbine Generator R
Knowledge of MT/G system design feature(s) and/or inter-lock(s) which provide for the following:
Overspeed protection K4.13 2.8
20 055 Condenser Air Removal R
Ability to monitor automatic operation of the CARS, including:
Automatic diversion of CARS exhaust A3.03 2.7 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal R
Ability to manually operate and/or monitor in the control room: Water drainage from the WGOS decay tanks A4.30 2.6 072 Area Radiation Monitoring R
Knowledge of the effect of a loss or malfunction of the following will have on the ARM system:
Sensors and detectors K6.01 2.6 075 Circulating Water 079 Station Air R
Knowledge of the physical connections and/or cause-effect relationships between the SAS and the following systems:
IAS K1.01 3.1 086 Fire Protection S
Knowledge of the process to track inoperable alarms.
2.4.33 2.8
21 SRO K/A Category Point Totals:
N A
N A
N A
N A
N A
N A
N A
2 N
A N
A 1
SRO Group Point Total:
3 RO K/A Category Point Totals:
1 1
1 1
1 1
1 1
1 1
RO Group Point Total:
10
22 ES-401Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: SONGS Date of Exam: April 2005 Category K/A # Topic RO SRO-Only IR IR
- 1. Conduct of Operations 2.1.1 Knowledge of the Conduct of Operations 3.7 2.1.22 Ability to determine Mode of Operation 2.8 2.1.31 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
4.2 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
4.4 2.1.
2.1.
Subtotal 3
1
- 2. Equipment Control 2.2.11 Knowledge of the process for controlling temporary changes.
2.5 2.2.13 Knowledge of tagging and clearance procedures.
3.6 2.2.22 Knowledge of limiting conditions for operations and safety limits.
3.4 2.2.26 Knowledge of refueling administrative requirements.
3.7 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.
3.8 2.2.
Subtotal 3
2
23
- 3. Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
2.5 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
2.9 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.
3.0 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.
3.2 2.3.
2.3.
Subtotal 2
2 Emergency Procedures /
Plan 2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes.
3.3 2.4.24 Knowledge of loss of cooling water procedures.
3.3 2.4.37 Knowledge of the lines of authority during an emergency.
3.5 2.4.41 Knowledge of the emergency action level thresholds and classifications.
4.1 2.4.
2.4.
Subtotal 2
2 Tier 3 Point Total 10 7
7