ML20078M160
| ML20078M160 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/27/2020 |
| From: | Gregory Roach NRC/RGN-III/DRS/OLB |
| To: | FirstEnergy Nuclear Operating Co |
| Roach G | |
| Shared Package | |
| ML19121A160 | List: |
| References | |
| Download: ML20078M160 (9) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: DAVIS-BESSE NUCLEAR POWER STATION Date of Exam: 02/03/2020 to 02/17/2020 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 and Abnormal Plant Evolutions 1
3 2
4 N/A 3
3 N/A 3
18 3
3 6
2 2
2 1
2 1
1 9
2 2
4 Tier Totals 5
4 5
5 4
4 27 5
5 10
- 2.
Plant Systems 1
3 2
2 2
2 2
3 3
3 3
3 28 2
3 5
2 1
1 1
1 1
1 1
1 1
1 0
10 0
2 1
3 Tier Totals 4
3 3
3 3
3 4
4 4
4 3
38 4
4 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 2
3 2
2 2
1 2
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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
- 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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 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. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). 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.
G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 03 (BW E02) EK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (Vital System Status Verification): Annunciators and conditions indicating signals, and remedial actions associated with the (Vital System Status Verification) 3.8 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 0
000009 (EPE 9) Small Break LOCA / 3 0
000011 (EPE 11) Large Break LOCA / 3 02 EK2.02 - Knowledge of the interrelations between the large break LOCA and the following: Pumps 2.6 1
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunction (Loss of RC Flow): Potential damage from high winding and/or bearing temperatures 2.5 1
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 01 AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Makeup: CVCS letdown and charging 3.4 1
000025 (APE 25) Loss of Residual Heat Removal System / 4 07 AA2.07 - Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System:
Pump cavitation 3.4 1
000026 (APE 26) Loss of Component Cooling Water / 8 04.
47 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material 4.2 1
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 01 AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions: Definition of saturation temperature KA change to 027 AK1.02, see ES-401-4.
3.1 1
000029 (EPE 29) Anticipated Transient Without Scram / 1 0
000038 (EPE 38) Steam Generator Tube Rupture / 3 01 EK3.01 - Knowledge of the reasons for the following responses as they apply to the SGTR: Equalizing pressure on primary and secondary sides of ruptured S/G 4.1 1
000040(APE 40; BW E05; CE E05; W E12)
Steam Line Rupture: Excessive Heat Transfer/4 02 AK2.02 - Knowledge of the interrelations between the Steam Line Rupture and the following: Sensors and detectors 2.6 1
000054 (APE 54; CE E06) Loss of Main Feedwater /4 02 AA1.02 - Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater: Manual startup of electric and steam-driven AFW pumps 4.4 1
000055 (EPE 55) Station Blackout / 6 06 EA2.06 - Ability to determine and interpret the following as they apply to a Station Blackout: Faults and lockouts that must be cleared prior to re-energizing buses 3.7 1
000056 (APE 56) Loss of Offsite Power / 6 04.
46 2.4.46 - Ability to verify that the alarms are consistent with the plant conditions 4.2 1
000057 (APE 57) Loss of Vital AC Instrument Bus / 6 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus 4.1 1
000058 (APE 58) Loss of DC Power / 6 01 AK3.01 - 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 3.4 1
000062 (APE 62) Loss of Nuclear Service Water / 4 04 AA1.04 - Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water (SWS):
CRDM high-temperature alarm system 2.7 1
000065 (APE 65) Loss of Instrument Air / 8 03 AA2.03 - Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Location and isolation of leaks 2.6 1
000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 02.
38 2.2.38 - Knowledge of conditions and limitations in the facility license 3.6 1
(W E04) LOCA Outside Containment / 3 NOT APPLICABLE 0
(W E11) Loss of Emergency Coolant Recirculation / 4 NOT APPLICABLE 0
(BW E04; W E05) Inadequate Heat Transfer Loss of Secondary Heat Sink / 4 02 (BW E04) EK1.2 - Knowledge of the operational implications of the following concepts as they apply to (Inadequate Heat Transfer): Normal, abnormal and emergency procedures associated with (Inadequate Heat Transfer) 4.0 1
ES-401 3
Form ES-401-2 K/A Category Totals:
3 2
4 3
3 3
Group Point Total:
18 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 0
000003 (APE 3) Dropped Control Rod / 1 0
000005 (APE 5) Inoperable/Stuck Control Rod/1 03 AK2.03 - Knowledge of the interrelations between the Inoperable /
Stuck Control Rod and the following: Metroscope KA change to 005 AK2.01, see ES-401-4.
3.1 1 000024 (APE 24) Emergency Boration/ 1 0
000028 (APE 28) Pressurizer (PZR) Level Control Malf./ 2 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions:
Relationships between PZR pressure increase and reactor makeup/letdown imbalance KA change to AK1.01, see ES-401-4.
2.9 1
000032 (APE 32) Loss of Source Range Nuclear Inst./ 7 01 AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of Source Range Nuclear Instrumentation:
Manual restoration of power 3.1 1
000033 (APE 33) Loss of Intermediate Range Nuclear Inst./ 7 0
000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 0
000037 (APE 37) Steam Generator Tube Leak/ 3 06 AA2.06 - Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: S/G tube failure 4.3 1
000051 (APE 51) Loss of Condenser Vacuum / 4 0
000059 (APE 59) Accidental Liquid Radwaste Release / 9 0
000060 (APE 60)Accidental Gaseous Radwaste Release/ 9 0
000061 (APE 61) Area Radiation Monitoring System Alarms / 7 0
000067 (APE 67) Plant Fire On Site / 8 0
000068 (APE 68; BW A06) Control Room Evacuation / 8 0
000069 (APE 69; W E14) Loss of Containment Integrity / 5 01.
20 2.1.20 - Ability to interpret and execute procedure steps 4.6 1 000074(EPE 74; W E06 & E07)Inadequate Core Cooling/ 4 0
000076 (APE 76) High Reactor Coolant Activity / 9 01 AK2.01 - Knowledge of the interrelations between the High Reactor Coolant Activity and the following: Process radiation monitors 2.6 1 000078 (APE 78*) RCS Leak / 3 0
(W E01 & E02) Rediagnosis & SI Termination / 3 NOT APPLICABLE 0
(W E13) Steam Generator Overpressure / 4 NOT APPLICABLE 0
(W E15) Containment Flooding / 5 NOT APPLICABLE 0
(W E16) High Containment Radiation /9 NOT APPLICABLE 0
(BW A01) Plant Runback / 1 03 (BW A01) AK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (Plant Runback):
Annunciators and conditions indicating signals, and remedial actions associated with the (Plant Runback) 3.7 1
(BW A02 & A03) Loss of NNI-X/Y/7 01 (BW A02) AK3.1 - Knowledge of the reasons for the following responses as they apply to the (Loss of NNI-X): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics 3.7 1 (BW A04) Turbine Trip / 4 0
(BW A05) Emergency Diesel Actuation / 6 0
(BW A07) Flooding / 8 03 (BW A07) AA1.3 - Ability to operate / monitor the following as they apply to (Flooding): Desired operating results during abnormal and emergency situations 3.3 1 (BW E03) Inadequate Subcooling Margin / 4 0
(BW E08; W E03) LOCA CooldownDepressurization / 4 0
(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 0
(BW E13 & E14) EOP Rules and Enclosures 0
(CE A11**; W E08) RCS OvercoolingPTS/ 4 NOT APPLICABLE 0
(CE A16) Excess RCS Leakage / 2 NOT APPLICABLE 0
ES-401 4
Form ES-401-2 (CE E09) Functional Recovery NOT APPLICABLE 0
(CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 NOT APPLICABLE 0
K/A Category Point Totals:
1 2
2 2
1 1
Group Point Total:
9 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 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 Topic(s)
IR #
003 (SF4P RCP) Reactor Coolant Pump 0
5 0
1 A1.05 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:
RCS flow A2.01 - 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: Problems with RCP seals, especially rates of seal leak-off 3.4 3.5 2
004 (SF1; SF2 CVCS) Chemical and Volume Control 0
8 A3.08 - Ability to monitor automatic operation of the CVCS, including: reactor power 3.9 1 005 (SF4P RHRS) Residual Heat Removal System 0
4 0
2 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction A4.02 - Ability to manually operate and/or monitor in the control room: Heat exchanger bypass flow control 2.9 3.4 2
006 (SF2; SF3 ECCS) Emergency Core Cooling
- 02.
36 2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations 3.1 1 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 0
3 0
1 K1.03 - Knowledge of the physical connections and/or cause-effect relationships between the PRTS and the following systems: RCS A3.01 - Ability to monitor automatic operation of the PRTS, including: Components which discharge to the PRT 3.0 2.7 2
008 (SF8 CCW) Component Cooling Water 0
2 K2.02 - Knowledge of bus power supplies to the following: CCW pump, including emergency backup 3.0 1 010 (SF3 PZR PCS) Pressurizer Pressure Control 0
2 K3.02 - Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: RPS 4.0 1 012 (SF7 RPS) Reactor Protection 0
1 K5.01 - Knowledge of the operational implications of the following concepts as they apply to the RPS: DNB 3.3 1 013 (SF2 ESFAS) Eng. Safety Features Actuation 0
1 K5.01 - Knowledge of the operational implications of the following concepts as they apply to the ESFAS: Definitions of safety train and ESF channel 2.8 1 022 (SF5 CCS) Containment Cooling 0
3 A4.03 - Ability to manually operate and/or monitor in the control room: Dampers in the CCS KA change to 022 A4.01, see ES-401-4.
3.2 1 025 (SF5 ICE) Ice Condenser NOT APPLICABLE 0
026 (SF5 CSS) Containment Spray System 0
2 0
1 A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:
Containment temperature A4.01 - Ability to manually operate and/or monitor in the control room: CSS controls 3.6 4.5 2
039 (SF4S MRSS) Main and Reheat Steam System 0
4 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Malfunctioning steam dump 3.4 1 059 (SF4S MFW) Main Feedwater 0
2 A3.02 - Ability to monitor automatic operation of the MFW, including: Programmed levels of the S/G 2.9 1 061 (SF4S AFW) Auxiliary/Emergency Feedwater 0
2 K6.02 - Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps 2.6 1 062 (SF6 ED AC) AC Electrical Distribution 0
2
- 02.
44 K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the AC distribution system and the following systems: EDG 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 4.1 4.2 2
063 (SF6 ED DC) DC Electrical Distribution 0
2 K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the DC distribution system and the following systems: AC electrical system 2.7 1 064 (SF6 EDG) Emergency Diesel Generator 0
7 K6.07 - Knowledge of the effect of a loss or malfunction of the following will have on the EDG system: Air receivers 2.7 1 073 (SF7 PRM) Process Radiation Monitoring 0
1
- 04.
49 K3.01 - Knowledge of the effect that a loss or malfunction of the PRM system will have on the following: Radioactive effluent releases 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls KA change to 064 G2.4.49, see ES-401-4.
3.6 4.6 2
076 (SF4S SWS) Service Water System 0
8 0
1 K2.08 - Knowledge of bus power supplies to the following: ESF-actuated MOVs K4.01 - Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return valves KA change to 076 K4.06, see ES-401-4.
3.1 2.5 2
078 (SF8 IAS) Instrument Air 0
1 K4.01 - Knowledge of IAS design feature(s) and/or interlock(s) which provide for the following: Manual/automatic transfers of control 2.7 1
ES-401 5
Form ES-401-2 103 (SF5 CNT) Containment 0
1 A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Containment system controls including: Containment pressure, temperature, and humidity 3.7 1 053 (SF1; SF4P ICS*) Integrated Control System NOT APPLICABLE 0
K/A Category Point Totals:
3 2 2 2 2 2 3 3 3 3 3 Group Point Total:
28 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 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 (SF1 CRDS) Control Rod Drive 0
3 K1.03 - Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the following systems: CRDM 3.4 1
002 (SF2; SF4P RCS) Reactor Coolant 0
011 (SF2 PZR LCS) Pressurizer Level Control 0
014 (SF1 RPI) Rod Position Indication 0
015 (SF7 NIS) Nuclear Instrumentation System 0
1 K2.01 - Knowledge of bus power supplies to the following: NIS channels, components, and interconnections 3.3 1
016 (SF7 NNI) Nonnuclear Instrumentation 0
017 (SF7 ITM) In-Core Temperature Monitor 0
1 K3.01 - Knowledge of the effect that a loss or malfunction of the ITM system will have on the following: Natural circulation indications 3.5 1
027 (SF5 CIRS) Containment Iodine Removal NOT APPLICABLE 0
028 (SF5 HRPS) Hydrogen Recombiner and Purge Control NOT APPLICABLE 0
029 (SF8 CPS) Containment Purge 0
2 K4.02 - Knowledge of the design feature(s) and/or interlock(s) which provide for the following: Negative pressure in containment 2.9 1
033 (SF8 SFPCS) Spent Fuel Pool Cooling 0
1 A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling system operating the controls including: Spent fuel pool water level 2.7 1
034 (SF8 FHS) Fuel-Handling Equipment 0
035 (SF 4P SGS) Steam Generator System 0
1 K6.01 - Knowledge of the effect of a loss or malfunction of the following will have on the S/G system: MSIVs 3.2 1
041 (SF4S SDS) Steam Dump/Turbine Bypass Control 0
7 K5.07 - Knowledge of operational implications of the following concepts as they apply to the SDS: Reactivity feedback effects 3.1 1
045 (SF 4S MTG) Main Turbine Generator 1
7 A2.17 - Ability to (a) predict the impacts of the following malfunctions or operation on the MTG system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Malfunction of electrohydraulic control 2.7 1
055 (SF4S CARS) Condenser Air Removal 0
056 (SF4S CDS) Condensate 0
068 (SF9 LRS) Liquid Radwaste 0
071 (SF9 WGS) Waste Gas Disposal 0
072 (SF7 ARM) Area Radiation Monitoring 0
075 (SF8 CW) Circulating Water 1
079 (SF8 SAS**) Station Air 0
1 A4.01 - Ability to manually operate and/or monitor in the control room: Cross-tie with Instrument Air system 2.7 1
086 Fire Protection 0
2 A3.02 - Ability to monitor automatic operation of the Fire Protection system, including: Actuation of the FPS 2.9 0
050 (SF 9 CRV*) Control Room Ventilation NOT APPLICABLE 0
K/A Category Point Totals:
1 1 1 1 1 1 1 1 1 1 0 Group Point Total:
10
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 0
000008 (APE 8) Pressurizer Vapor Space Accident / 3 03 A2.03 - Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:
PORV position indicators and acoustic monitors 3.9 1 000009 (EPE 9) Small Break LOCA / 3
- 04.
06 2.4.06 - Knowledge of the EOP mitigation strategies 4.7 1 000011 (EPE 11) Large Break LOCA / 3 0
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 0
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 0
000025 (APE 25) Loss of Residual Heat Removal System / 4 0
000026 (APE 26) Loss of Component Cooling Water / 8 0
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 0
000029 (EPE 29) Anticipated Transient Without Scram / 1 09 EA2.09 - Ability to determine and interpret the following as they apply to a ATWS: Occurrence of a main turbine/reactor trip 4.5 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 0
000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 0
000054 (APE 54; CE E06) Loss of Main Feedwater /4 01.
23 2.1.23 - Ability to perform specific system and integrated plant procedures in all modes of plant operation 4.4 1 000055 (EPE 55) Station Blackout / 6 0
000056 (APE 56) Loss of Offsite Power / 6 33 AA2.33 - Ability to determine and interpret the following as they apply to the Loss of Offsite Power: ESF channels, A and B breaker-trip alarms, indicators, and bus voltage indicators 3.7 1 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 0
000058 (APE 58) Loss of DC Power / 6 0
000062 (APE 62) Loss of Nuclear Service Water / 4 0
000065 (APE 65) Loss of Instrument Air / 8 0
000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 0
(W E04) LOCA Outside Containment / 3 NOT APPLICABLE 0
(W E11) Loss of Emergency Coolant Recirculation / 4 NOT APPLICABLE 0
(BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 04.
35 2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects 4.0 1 K/A Category Totals:
0 0
0 0
3 3
Group Point Total:
6
ES-401 7
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 0
000003 (APE 3) Dropped Control Rod / 1
- 02.
40 2.2.40 - Ability to apply Technical Specifications for a system 4.7 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 0
000024 (APE 24) Emergency Boration / 1 0
000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 0
000032 (APE 32) Loss of Source Range Nuclear Instrumentation
/ 7 0
000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 0
000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 0
000037 (APE 37) Steam Generator Tube Leak / 3 0
000051 (APE 51) Loss of Condenser Vacuum / 4 0
000059 (APE 59) Accidental Liquid Radwaste Release / 9 0
000060 (APE 60) Accidental Gaseous Radwaste Release / 9 06 AA2.06 - Ability to determine and interpret the following as they apply to Accidental Gaseous Radwaste Release: Valve lineup for release of radioactive gases 3.8 1 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 0
000067 (APE 67) Plant Fire On Site / 8 0
000068 (APE 68; BW A06) Control Room Evacuation / 8 04.
03 2.4.03 - Ability to identify post-accident instrumentation 3.9 1 000069 (APE 69; W E14) Loss of Containment Integrity / 5 0
000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / 4 0
000076 (APE 76) High Reactor Coolant Activity / 9 0
000078 (APE 78*) RCS Leak / 3 0
(W E01 & E02) Rediagnosis & SI Termination / 3 NOT APPLICABLE 0
(W E13) Steam Generator Overpressure / 4 NOT APPLICABLE 0
(W E15) Containment Flooding / 5 NOT APPLICABLE 0
(W E16) High Containment Radiation /9 NOT APPLICABLE 0
(BW A01) Plant Runback / 1 0
(BW A02 & A03) Loss of NNI-X/Y/7 0
(BW A04) Turbine Trip / 4 0
(BW A05) Emergency Diesel Actuation / 6 0
(BW A07) Flooding / 8 0
(BW E03) Inadequate Subcooling Margin / 4 0
(BW E08; W E03) LOCA CooldownDepressurization / 4 0
(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 0
(BW E13 & E14) EOP Rules and Enclosures 02 (BW E13) EA2.2 - Ability to determine and interpret the following as they apply to the (EOP Rules): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments 4.0 1 (CE A11**; W E08) RCS OvercoolingPTS/ 4 NOT APPLICABLE 0
(CE A16) Excess RCS Leakage / 2 NOT APPLICABLE 0
(CE E09) Functional Recovery NOT APPLICABLE 0
(CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 NOT APPLICABLE 0
K/A Category Point Totals:
0 0
0 0
2 2
Group Point Total:
4
ES-401 8
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR #
003 (SF4P RCP) Reactor Coolant Pump 0
004 (SF1; SF2 CVCS) Chemical and Volume Control 04.
45 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm 4.3 1 005 (SF4P RHR) Residual Heat Removal 0
006 (SF2; SF3 ECCS) Emergency Core Cooling 03 A2.03 - 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: System leakage 3.7 1 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 0
008 (SF8 CCW) Component Cooling Water 02.
25 2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits 4.2 1 010 (SF3 PZR PCS) Pressurizer Pressure Control 0
012 (SF7 RPS) Reactor Protection 0
013 (SF2 ESFAS) Engineered Safety Features Actuation 0
022 (SF5 CCS) Containment Cooling 06 A2.06 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCS pump KA change to 013 A2.06, see ES-401-4.
3.2 1 025 (SF5 ICE) Ice Condenser NOT APPLICABLE 0
026 (SF5 CSS) Containment Spray 0
039 (SF4S MSS) Main and Reheat Steam 0
059 (SF4S MFW) Main Feedwater 0
061 (SF4S AFW) Auxiliary/Emergency Feedwater
- 02.
37 2.2.37 - Ability to determine operability and/or availability of safety related equipment 4.6 1 062 (SF6 ED AC) AC Electrical Distribution 0
063 (SF6 ED DC) DC Electrical Distribution 0
064 (SF6 EDG) Emergency Diesel Generator 0
073 (SF7 PRM) Process Radiation Monitoring 0
076 (SF4S SW) Service Water 0
078 (SF8 IAS) Instrument Air 0
103 (SF5 CNT) Containment 0
053 (SF1; SF4P ICS*) Integrated Control NOT APPLICABLE 0
K/A Category Point Totals:
0 0
0 0
0 0
0 2
0 0
3 Group Point Total:
5
ES-401 9
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 001 (SF1 CRDS) Control Rod Drive 0
002 (SF2; SF4P RCS) Reactor Coolant 0
011 (SF2 PZR LCS) Pressurizer Level Control 12 A2.12 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Operation of auxiliary spray KA change to 011 A2.06, see ES-401-4.
3.3 1
014 (SF1 RPI) Rod Position Indication 01.
07 2.1.07 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation 4.7 1
015 (SF7 NI) Nuclear Instrumentation 0
016 (SF7 NNI) Nonnuclear Instrumentation 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of power supply 3.2 1
017 (SF7 ITM) In-Core Temperature Monitor 0
027 (SF5 CIRS) Containment Iodine Removal NOT APPLICABLE 0
028 (SF5 HRPS) Hydrogen Recombiner and Purge Control NOT APPLICABLE 0
029 (SF8 CPS) Containment Purge 0
033 (SF8 SFPCS) Spent Fuel Pool Cooling 0
034 (SF8 FHS) Fuel-Handling Equipment 0
035 (SF 4P SG) Steam Generator 0
041 (SF4S SDS) Steam Dump/Turbine Bypass Control 0
045 (SF 4S MTG) Main Turbine Generator 0
055 (SF4S CARS) Condenser Air Removal 0
056 (SF4S CDS) Condensate 0
068 (SF9 LRS) Liquid Radwaste 0
071 (SF9 WGS) Waste Gas Disposal 0
072 (SF7 ARM) Area Radiation Monitoring 0
075 (SF8 CW) Circulating Water 0
079 (SF8 SAS**) Station Air 0
086 Fire Protection 0
050 (SF 9 CRV*) Control Room Ventilation NOT APPLICABLE 0
K/A Category Point Totals:
0 0
0 0
0 0
0 2
0 0
1 Group Point Total:
3