ML13093A187
| ML13093A187 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/26/2013 |
| From: | NRC/RGN-III/DRS/OLB |
| To: | Entergy Nuclear Operations |
| References | |
| ES-401-2, ES-401-3 | |
| Download: ML13093A187 (7) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Palisades Nuclear Plant Date of Exam: 02/26/2013 Tier Group RO K/A Category Points SRO-Only Points K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total
- 1.
Emergency
& Abnormal Plant Evolutions 1
2 3
3 N/A 3
4 N/A 3
18 n/a n/a 6
2 2
2 1
1 1
2 9
n/a n/a 4
Tier Totals 4
5 4
4 5
5 27 n/a n/a 10
- 2.
Plant Systems 1
2 2
2 3
2 3
3 3
3 3
2 28 n/a n/a 5
2 1
0 1
1 1
1 1
1 1
1 1
10 n/a n/a 3
Tier Totals 3
2 3
4 3
4 4
4 4
4 3
38 n/a n/a 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 3
2 2
n
/
a n/
a n/
a n/
a Note:
- 1.
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 ATier 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 RO 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 ES-401, Attachment 2, 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 (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO 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.
- 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. Use duplicate pages for RO and SRO-only 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 SRO selections to K/As that are linked to 10 CFR 55.43.
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 K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 000007 (CE/E02) Reactor Trip -
Stabilization - Recovery / 1 0
3 K3.3-Knowledge of the reasons for the following responses as they apply to the (Reactor Trip Recovery): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
3.7 1
000008 Pressurizer Vapor Space Accident
/ 3 0
6 A2.06-Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: PORV logic control under low-pressure conditions 3.3 5
000009 Small Break LOCA / 3 0
1 A1.01-Ability to operate and monitor the following as they apply to a small break LOCA: RCS pressure and temperature 4.4 2
000011 Large Break LOCA / 3 0
5 A2.05-Ability to determine or interpret the following as they apply to a Large Break LOCA: Significance of charging pump operation 3.3 3
000015/17 RCP Malfunctions / 4 x
2.1.31-Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
4.6 4
000025 Loss of RHR System / 4 0
3 K2.03-Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following: Service water or closed cooling water pumps 2.7 6
000026 Loss of Component Cooling Water
/ 8 0
1 K3.01-Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCW/nuclear service water coolers 3.2 7
000027 Pressurizer Pressure Control System Malfunction / 3 0
4 A1.04-Ability to operate and / or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions:
Pressure recovery, using emergency-only heaters 3.9 8
000029 ATWS / 1 0
2 A2.02-Ability to determine or interpret the following as they apply to a ATWS: Reactor trip alarm 4.2 9
000038 Steam Gen. Tube Rupture / 3 x
2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.6 10 000040 (CE/E05) Steam Line Rupture -
Excessive Heat Transfer / 4 0
1 EK2.1-Knowledge of the interrelations between the (Excess Steam Demand) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
3.3 11 000055 Station Blackout / 6 0
2 K1.02-Knowledge of the operational implications of the following concepts as they apply to the Station Blackout:
Natural circulation cooling 4.1 12 000056 Loss of Off-site Power / 6 0
2 K3.02-Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power 4.4 13 000057 Loss of Vital AC Inst. Bus / 6 0
6 A1.06-Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual control of components for which automatic control is lost 3.5 14 000058 Loss of DC Power / 6 0
1 K1.01-Knowledge of the operational implications of the following concepts as they apply to Loss of DC Power: Battery charger equipment and instrumentation 2.8 15 000062 Loss of Nuclear Svc Water / 4 x
2.1.30-Ability to locate and operate components, including local controls.
4.4 16 000065 Loss of Instrument Air / 8 0
3 A2.03-Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Location and isolation of leaks 2.6 17 000077 Generator Voltage and Electric Grid Disturbances / 6 0
3 K2.03-Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following:
Sensors, detectors, indicators 3.0 18 K/A Category Totals:
2 3
3 3
4 3
Group Point Total:
18
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 K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 000003 Dropped Control Rod / 1 x
2.4.21-Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
4.0 19 000005 Inoperable/Stuck Control Rod / 1 0
5 K1.05-Knowledge of the operational implications of the following concepts as they apply to Inoperable / Stuck Control Rod: Calculation of minimum shutdown margin 3.3 20 000024 Emergency Boration / 1 0
3 K2.03-Knowledge of the interrelations between Emergency Boration and the following: Controllers and positioners 2.6 21 000032 Loss of Source Range NI / 7 0
2 K3.02-Knowledge of the reasons for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Guidance contained in EOP for loss of source-range nuclear instrumentation 3.7 22 000051 Loss of Condenser Vacuum / 4 0
4 A1.04-Ability to operate and / or monitor the following as they apply to the Loss of Condenser Vacuum: Rod position 2.5 23 000060 Accidental Gaseous Radwaste Rel. / 9 0
3 A2.03-Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste:
The steps necessary to isolate a given radioactive-gas leak, using P&Ids 3.2 24 000068 (BW/A06) Control Room Evac. / 8 x
2.1.32-Ability to explain and apply system limits and precautions.
3.6 25 000069 (W/E14) Loss of CTMT Integrity / 5 0
1 K1.01-Knowledge of the operational implications of the following concepts as they apply to Loss of Containment Integrity: Effect of pressure on leak rate 2.6 26 CE/A11; W/E08 RCS Overcooling - PTS / 4 0
2 AK2.2-Knowledge of the interrelations between the (RCS Overcooling) and the following: Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
3.2 27 K/A Category Point Totals:
2 2
1 1
1 2
Group Point Total:
9
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)
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 003 Reactor Coolant Pump 0
1 K5.01-Knowledge of the operational implications of the following concepts as they apply to the RCPS: The relationship between the RCPS flow rate and the nuclear reactor core operating parameters (quadrant power tilt, imbalance, DNB rate, local power density, difference in loop T-hot pressure) 3.3 28 004 Chemical and Volume Control 0
7 K6.07-Knowledge of the effect of a loss or malfunction on the following CVCS components:
Heat exchangers and condensers 2.7 29 005 Residual Heat Removal 0
3 A1.03-Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including: Closed cooling water flow rate and temperature 2.5 30 006 Emergency Core Cooling 1
1 0
3 A2.11-Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture of ECCS header A3.03-Ability to monitor automatic operation of the ECCS, including: ESFAS-operated valves 4.0 4.1 31 32 007 Pressurizer Relief/Quench Tank 1
0 x
A4.10-Ability to manually operate and/or monitor in the control room: Recognition of leaking PORV/code safety 2.2.39-Knowledge of less than or equal to one hour Technical Specification action statements for systems.
3.6 3.9 33 34 008 Component Cooling Water 0
3 0
2 K1.03-Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems: PRMS K2.02-Knowledge of bus power supplies to the following: CCW pump, including emergency backup 2.8 3.0 35 36 010 Pressurizer Pressure Control 0
2 0
1 K3.02-Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: RPS K4.01-Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for the following:
Spray valve warm-up 4.0 2.7 37 38 012 Reactor Protection 0
2 0
7 K5.02-Knowledge of the operational implications of the following concepts as the apply to the RPS:
Power density K6.07-Knowledge of the effect of a loss or malfunction of the following will have on the RPS:
Core protection calculator 3.1 2.9 39 40 013 Engineered Safety Features Actuation 0
6 0
4 A1.06-Ability to predict and/or monitor changes in parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: RWST level A2.04-Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Loss of instrument bus 3.6 3.6 41 42 022 Containment Cooling 0
1 A3.01-Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation 4.1 43 026 Containment Spray 0
1 A4.01-Ability to manually operate and/or monitor in the control room: CSS controls 4.5 44 039 Main and Reheat Steam x
2.4.6-Knowledge of EOP mitigation strategies.
3.7 45 059 Main Feedwater 0
3 K1.03-Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems S/Gs 3.1 46 061 Auxiliary/Emergency Feedwater 0
2 K2.02-Knowledge of bus power supplies to the following: AFW electric driven pumps 3.7 47 062 AC Electrical Distribution 0
3 K3.03-Knowledge of the effect that a loss or malfunction of the ac distribution system will have 3.7 48
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO) on the following: DC system 063 DC Electrical Distribution 0
1 0
1 K4.01-Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Manual/automatic transfers of control A1.01-Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate 2.7 2.5 49 50 064 Emergency Diesel Generator 0
8 K6.08-Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Fuel oil storage tanks 3.2 51 073 Process Radiation Monitoring 0
1 K4.01-Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint 4.0 52 076 Service Water 0
1 A2.01-Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS 3.5 53 078 Instrument Air 0
1 A3.01-Ability to monitor automatic operation of the IAS, including: Air pressure 3.1 54 103 Containment 0
4 A4.04-Ability to manually operate and/or monitor in the control room: Phase A and phase B resets 3.5 55 K/A Category Point Totals:
2 2 2 3 2 3 3 3 3 3 2
Group Point Total:
28
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)
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 0
3 K4.03-Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following: Rod control logic 3.
5 56 002 Reactor Coolant 1
0 K5.10-Knowledge of the operational implications of the following concepts as they apply to the RCS: Relationship between reactor power and RCS differential temperature 3.
6 57 014 Rod Position Indication 0
2 A1.02-Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including:
Control rod position indication on control room panels 3.
2 58 015 Nuclear Instrumentation 0
1 K6.01-Knowledge of the effect of a loss or malfunction on the following will have on the NIS: Sensors, detectors, and indicators 2.
9 59 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 0
1 A2.01-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:
Thermocouple open and short circuits 3.
1 60 033 Spent Fuel Pool Cooling 0
2 A3.02-Ability to monitor automatic operation of the Spent Fuel Pool Cooling System including: Spent fuel leak or rupture 2.
9 61 035 Steam Generator 0
6 A4.06-Ability to manually operate and/or monitor in the control room: S/G isolation on steam leak or tube rupture/leak 4.
5 62 056 Condensate x
2.2.44-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.
4.
2 63 079 Station Air 0
1 K1.01-Knowledge of the physical connections and/or cause-effect relationships between the SAS and the following systems: IAS 3.
0 64 086 Fire Protection 0
1 K3.01-Knowledge of the effect that a loss or malfunction of the Fire Protection System will have on the following: Shutdown capability with redundant equipment 2.
7 65 K/A Category Point Totals:
1 0
1 1
1 1
1 1
1 1
1 Group Point Total:
10
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Palisades Nuclear Plant Date of Exam: 02/ 26/2013 Category K/A #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.01 2.1.1-Knowledge of conduct of operations requirements.
3.8 66 2.1.28 2.1.28-Knowledge of the purpose and function of major system components and controls.
4.1 67 2.1.43 2.1.43-Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
4.1 68 Subtotal 3
- 2.
Equipment Control 2.2.07 2.2.7-Knowledge of the process for conducting special or infrequent tests.
2.9 69 2.2.42 2.2.42-Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
3.9 70 2.2.44 2.2.44-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.
4.2 71 Subtotal 3
- 3.
Radiation Control 2.3.07 2.3.7-Ability to comply with radiation work permit requirements during normal or abnormal conditions.
3.5 72 2.3.14 2.3.14-Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3.4 73 Subtotal 2
- 4.
Emergency Procedures /
Plan 2.4.02 2.4.2-Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
4.5 74 2.4.46 2.4.46-Ability to verify that the alarms are consistent with the plant conditions.
4.2 75 Subtotal 2
Tier 3 Point Total 10