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