ML20297A306
| ML20297A306 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-070, DPR-075) |
| Issue date: | 10/23/2020 |
| From: | Public Service Enterprise Group |
| To: | Operations Branch I |
| Shared Package | |
| ML19105A168 | List: |
| References | |
| CAC 000500 | |
| Download: ML20297A306 (39) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: SALEM Date of Exam: JULY 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 3
3 N/A 3
4 N/A 2
18 6
2 1
2 2
1 1
2 9
4 Tier Totals 4
5 5
4 5
4 27 10
- 2.
Plant Systems 1
4 2
2 4
2 2
2 2
3 2
3 28 5
2 1
1 2
2 0
1 1
1 1
0 0
10 3
Tier Totals 5
3 4
6 2
3 3
3 4
2 3
38 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 3
2 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/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 X
EK 2.03 - Knowledge of the interrelations between a reactor trip and the following: Reactor trip status panel 3.5 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 X
AK 2.02 - Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Sensors and detectors 2.7 2
000009 (EPE 9) Small Break LOCA / 3 X
EK 1.02 - Knowledge of the operational implications of the following concepts as they apply to the small break LOCA: Use of steam tables 3.5 3
000011 (EPE 11) Large Break LOCA / 3 N/A - Not randomly selected 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X
AK 3.01 - Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) :
Potential damage from high winding and/or bearing temperatures 2.5 4
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X
AA 1.07 - Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Makeup: Excess letdown containment isolation valve switches and indicators 2.8 5
000025 (APE 25) Loss of Residual Heat Removal System / 4 X
AA 2.04 - Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Location and isolability of leaks 3.3 6
000026 (APE 26) Loss of Component Cooling Water / 8 N/A - Not randomly selected 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X
AK 3.03 - Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction 3.7 7
000029 (EPE 29) Anticipated Transient Without Scram / 1 X
AK 3.12-Knowledge of the reasons for the following responses as the apply to the ATWS: Actions contained in EOP for ATWS 4.4 8
000038 (EPE 38) Steam Generator Tube Rupture / 3 N/A - Not randomly selected 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 X G 2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.
4.2 9
000054 (APE 54; CE E06) Loss of Main Feedwater /4 X
AK 1.02 - Effects of feedwater introduction on dry S/G 3.6 10 000055 (EPE 55) Station Blackout / 6 N/A - Not randomly selected 000056 (APE 56) Loss of Offsite Power / 6 X
AA 1.03 - Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power:
Adjustment of ED/G load by selectively energizing PZR backup heaters 3.2 11 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X
AA 2.13 - Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: VCT level and pressure indicators and recorders 3.0 12 000058 (APE 58) Loss of DC Power / 6 X
Ability to determine and interpret the following as they apply to the Loss of DC Power: DC Loads lost, impact on ability to operate and monitor plant systems 3.5 13 000062 (APE 62) Loss of Nuclear Service Water / 4 X G 2.2.40 - Ability to apply Technical Specifications for a system 3.4 14 000065 (APE 65) Loss of Instrument Air / 8 X
AA 1.03 - Ability to operate and / or monitor the following as they apply to the Loss of Instrument Air: Emergency air compressor 3.5 15
ES-401 3
Form ES-401-2 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 N/A - Not randomly selected (W E04) LOCA Outside Containment / 3 X
EK 2.1 - Knowledge of the interrelations between the (LOCA Outside Containment) and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
3.5 16 (W E11) Loss of Emergency Coolant Recirculation / 4 X
EK 1.2 - Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation) 3.6 17 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X
EA 2.1 - Ability to determine and interpret the following as they apply to the (Loss of Secondary Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations 3.4 18 K/A Category Totals:
3 3
3 3
4 2
Group Point Total:
18/6
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 N/A - Not randomly selected 000003 (APE 3) Dropped Control Rod / 1 X
Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod:
Actions contained in EOP for dropped control rod.
3.8 19 000005 (APE 5) Inoperable/Stuck Control Rod / 1 X
AA 1.04 - Ability to operate and /
or monitor the following as they apply to the Inoperable / Stuck Control Rod: Reactor and turbine power 3.9 20 000024 (APE 24) Emergency Boration / 1 X
AK 2.01 - Knowledge of the interrelations between Emergency Boration and the following: Valves 2.7 21 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 N/A - Not randomly selected 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 N/A - Not randomly selected 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 X
AA 2.09 - Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation:
Conditions which allow bypass of an intermediate-range level trip switch.
3.4 22 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 N/A - Not randomly selected 000037 (APE 37) Steam Generator Tube Leak / 3 N/A - Not randomly selected 000051 (APE 51) Loss of Condenser Vacuum / 4 N/A - Not randomly selected 000059 (APE 59) Accidental Liquid Radwaste Release / 9 N/A - Not randomly selected 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 N/A - Not randomly selected 000061 (APE 61) Area Radiation Monitoring System Alarms
/ 7 X
AK 3.02 - Knowledge of the reasons for the following responses as they apply to the Area Radiation Monitoring (ARM) System Alarms: Guidance contained in alarm response for ARM system 3.4 23 000067 (APE 67) Plant Fire On Site / 8 N/A - Not randomly selected 000068 (APE 68; BW A06) Control Room Evacuation / 8 N/A - Not randomly selected 000069 (APE 69; W E14) Loss of Containment Integrity / 5 N/A - Not randomly selected 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /
4 X G 2.1.19 - Ability to use plant computers to evaluate system or component status 3.9 24 000076 (APE 76) High Reactor Coolant Activity / 9 N/A - Not randomly selected 000078 (APE 78*) RCS Leak / 3 N/A - Not randomly selected (W E01 & E02) Rediagnosis & SI Termination / 3 X G 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm 4.1 25 (W E13) Steam Generator Overpressure / 4 N/A - Not randomly selected (W E15) Containment Flooding / 5 N/A - Not randomly selected (W E16) High Containment Radiation /9 X
EK 2.1 - Knowledge of the interrelations between the (High Containment Radiation) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.0 26
ES-401 5
Form ES-401-2 (BW A01) Plant Runback / 1 N/A - Not randomly selected (BW A02 & A03) Loss of NNI-X/Y/7 N/A - Not randomly selected (BW A04) Turbine Trip / 4 N/A - Not randomly selected (BW A05) Emergency Diesel Actuation / 6 N/A - Not randomly selected (BW A07) Flooding / 8 N/A - Not randomly selected (BW E03) Inadequate Subcooling Margin / 4 N/A - Not randomly selected (BW E08; W E03) LOCA CooldownDepressurization / 4 X
EK 1.3 - Knowledge of the operational implications of the following concepts as they apply to the (LOCA Cooldown and Depressurization): Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Cooldown and Depressurization) 3.5 27 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 N/A - Not randomly selected (BW E13 & E14) EOP Rules and Enclosures N/A - Not randomly selected (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 N/A - Not randomly selected (CE A16) Excess RCS Leakage / 2 N/A - Not randomly selected (CE E09) Functional Recovery N/A - Not randomly selected (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 N/A - Not randomly selected K/A Category Point Totals:
1 2
2 1
1 2
Group Point Total:
9/4
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/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 X
A 1.04 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including: RCP standpipe levels 2.5 28 004 (SF1; SF2 CVCS) Chemical and Volume Control X
K 2.03 - Knowledge of bus power supplies to the following: Charging Pumps 3.3 29 004 (SF1; SF2 CVCS) Chemical and Volume Control X
G 2.1.28 - Knowledge of the purpose and function of major system components and controls 4.1 30 005 (SF4P RHR) Residual Heat Removal X
K 6.03 - Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: RHR heat exchanger 2.5 31 006 (SF2; SF3 ECCS) Emergency Core Cooling X
K 5.04 - Knowledge of the operational implications of the following concepts as they apply to ECCS: Brittle fracture, including causes and preventative actions.
2.9 32 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X
K 3.01 - Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: Containment 3.3 33 008 (SF8 CCW) Component Cooling Water X
K 1.04 - Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems:
RCS, in order to determine source(s) of RCS leakage into the CCWS 3.3 34 008 (SF8 CCW) Component Cooling Water X
K 4.09 - Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: The "standby" feature for the CCW pumps 2.7 35 010 (SF3 PZR PCS) Pressurizer Pressure Control X
A 3.02 - Ability to monitor automatic operation of the PZR PCS, including PZR pressure.
3.6 36 012 (SF7 RPS) Reactor Protection X
K 5.01 - Knowledge of the operational implications of the following concepts as the apply to the RPS: DNB 3.3 37 012 (SF7 RPS) Reactor Protection X G 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures 4.2 38 013 (SF2 ESFAS) Engineered Safety Features Actuation X
K 4.12 - Knowledge of ESFAS design feature(s) and/or interlocks which provide the following: Safety injection block 3.7 39 022 (SF5 CCS) Containment Cooling X
A 1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Containment temperature 3.6 40 025 (SF5 ICE) Ice Condenser N/A - Not randomly selected, not applicable to Salem 026 (SF5 CSS) Containment Spray X
K 4.08 - Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following: Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm).
4.1 41 026 (SF5 CSS) Containment Spray X
G 2.1.25 - Containment Spray: Ability to interpret reference materials, such as graphs, curves, tables, etc.
3.9 42 039 (SF4S MSS) Main and Reheat Steam X
K 1.02 - Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems:
Atmospheric relief dump valves 3.3 43
ES-401 7
Form ES-401-2 059 (SF4S MFW) Main Feedwater X
K 1.02 - Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems:
AFW system 3.4 44 059 (SF4S MFW) Main Feedwater X
A 2.12 - Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of feedwater regulating valves 3.1 45 061 (SF4S AFW)
Auxiliary/Emergency Feedwater X
A 3.03 - Ability to monitor automatic operation of the AFW, including: AFW S/G level control on automatic start 3.9 46 062 (SF6 ED AC) AC Electrical Distribution X
K 1.02 - Knowledge of the physical connections and/or cause-effect relationships between the ac distribution system and the following systems: ED/G 4.1 47 062 (SF6 ED AC) AC Electrical Distribution X
A 4.07 - Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different ac supplies 3.1 48 063 (SF6 ED DC) DC Electrical Distribution X
A 4.03 - Ability to manually operate and/or monitor in the control room: Battery discharge rate 3.0 49 064 (SF6 EDG) Emergency Diesel Generator X
K 6.07 - Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system. Air Receivers 2.7 50 073 (SF7 PRM) Process Radiation Monitoring X
K 4.01 - Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint 4.0 51 076 (SF4S SW) Service Water X
K 3.07 - Knowledge of the effect that a loss or malfunction of the SWS will have on the following: ESF loads 3.7 52 076 (SF4S SW) Service Water X
A 2.01 - 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 (SF8 IAS) Instrument Air X
K 2.02 - Knowledge of bus power supplies to the following: Emergency air compressor 3.3 54 103 (SF5 CNT) Containment X
A 3.01 - Ability to monitor automatic operation of the containment system, including:
Containment isolation 3.9 55 053 (SF1; SF4P ICS*) Integrated Control N/A for NUREG-1122, Rev. 2 K/A Category Point Totals:
4 2
2 4
2 2
2 2
3 2
3 Group Point Total:
28/5
ES-401 8
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/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 X
K 2.05 - Knowledge of bus power supplies to the following: M/G sets 3.1 56 002 (SF2; SF4P RCS) Reactor Coolant N/A - Not randomly selected 011 (SF2 PZR LCS) Pressurizer Level Control N/A - Not randomly selected 014 (SF1 RPI) Rod Position Indication N/A - Not randomly selected 015 (SF7 NI) Nuclear Instrumentation N/A - Not randomly selected 016 (SF7 NNI) Nonnuclear Instrumentation X
K3.02 - Knowledge of the effect that a loss or malfunction of the NNIS will have on the following: PZR LCS 3.4 57 017 (SF7 ITM) In-Core Temperature Monitor X
K 4.01 - Knowledge of ITM system design feature(s) and/or interlock(s) which provide for the following: Input to subcooling monitors 3.4 58 027 (SF5 CIRS) Containment Iodine Removal N/A - Not randomly selected 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control N/A - Not randomly selected 029 (SF8 CPS) Containment Purge X
K 1.03 - Knowledge of the physical connections and/or cause-effect relationships between the Containment Purge System and the following systems: Engineered safeguards 3.6 59 033 (SF8 SFPCS) Spent Fuel Pool Cooling X
K 4.03 - Spent Fuel Cooling: Knowledge of design feature(s) and/or interlock(s) which provide for the following: Anti-siphon devices 2.6 62 034 (SF8 FHS) Fuel-Handling Equipment N/A - Not randomly selected 035 (SF 4P SG) Steam Generator X
K 6.03 - Knowledge of the effect of a loss or malfunction on the following will have on the S/GS: S/G level detector 2.6 60 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X
A 3.05 - Ability to monitor automatic operation of the SDS, including: Main steam pressure 2.9 61 045 (SF 4S MTG) Main Turbine Generator N/A - Not randomly selected 055 (SF4S CARS) Condenser Air Removal X
K 3.01 - Knowledge of the effect that a loss or malfunction of the CARS will have on the following: Main condenser 2.5 63 056 (SF4S CDS) Condensate N/A - Not randomly selected 068 (SF9 LRS) Liquid Radwaste N/A - Not randomly selected 071 (SF9 WGS) Waste Gas Disposal N/A - Not randomly selected 072 (SF7 ARM) Area Radiation Monitoring N/A - Not randomly selected 075 (SF8 CW) Circulating Water X
A 2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps 2.5 64 079 (SF8 SAS**) Station Air N/A - Not randomly selected 086 Fire Protection X
A 1.05 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: FPS lineups 2.9 65
ES-401 9
Form ES-401-2 050 (SF 9 CRV*) Control Room Ventilation N/A for NUREG-1122, Rev. 2 K/A Category Point Totals:
1 1
2 2
0 1
1 1
1 0
0 Group Point Total:
10/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: SALEM Date of Exam: JULY 2020 Category K/A #
Topic RO SRO-only IR IR
- 1. Conduct of Operations 2.1.
G 2.1.1 - Knowledge of conduct of operations requirements.
3.8 66 2.1.
G 2.1.3 - Knowledge of shift or short-term relief turnover practices.
3.7 67 2.1.
G 2.1.37 - Knowledge of procedures, guidelines, or limitations associated with reactivity management.
4.3 68 2.1.
2.1.
2.1.
Subtotal
- 2. Equipment Control 2.2.
G 2.2.14 - Knowledge of the process for controlling equipment configuration or status.
3.9 69 2.2.
G 2.2.13 - Knowledge of tagging and clearance procedures.
4.1 70 2.2.
G 2.2.12 - Knowledge of surveillance procedures.
3.7 71 2.2.
2.2.
2.2.
Subtotal
- 3. Radiation Control 2.3.
G 2.3.14 - Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3.4 72 2.3.
G 2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 73 2.3.
2.3.
2.3.
2.3.
Subtotal
- 4. Emergency Procedures/Plan 2.4.
G 2.4.17 - Knowledge of EOP terms and definitions.
3.9 74 2.4.
G 2.4.25 - Knowledge of fire protection procedures.
3.3 75 2.4.
2.4.
2.4.
2.4.
Subtotal Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 000058G2.1.25 Unable to write a discriminating question utilizing graphs, curves, tables, etc. Replaced with K/A 000058G2.4.6.
1/1 000058G2.4.6.
Unable to write a fair and discriminating RO level question.
Replaced with K/A 000058AA2.03 1/1 000065AA1.03 Unable to write a discriminating question with plausible distractors. Replaced with K/A 000065AA1.04.
1/2 000003AK1.22 Unable to write a discriminating question with plausible distractors. Replaced with K/A 000003AK3.04.
1/2 000033AA2.02 Unable to write a fair and discriminating RO level question.
Replaced with K/A 000033AA2.09.
1/2 WE01G2.4.45 Unable to write a discriminating question with plausible distractors. Replaced with K/A WE02G2.4.45.
2/1 003A1.04 Potential overlap with Question #4. Replaced with K/A 003A1.10.
2/1 004K2.06 Potential overlap with Question #12. Replaced with K/A 004K2.03.
2/1 006K5.09 Potential overlap with LOCA-2 questions (2,3,25,27).
Replaced with K/A 006K5.04.
2/1 010A3.01 Potential overlap with Question # 33. Replaced with K/A 010A3.02.
2/1 013A2.03 Unable to write a fair and discriminating RO level question.
Replaced with K/A 013K4.12.
2/1 026K2.01 Potential overlap with Question #40. Replaced with K/A 026K4.08.
2/1 026G2.4.8 Unable to write a discriminating question with plausible distractors. Replaced with K/A 026G2.1.25.
2/1 064A2.16 Unable to write a fair and discriminating RO level question.
Replaced with K/A 064K6.07.
2/2 035K6.02 Potential overlap with Question # 43. Replaced with K/A 035K6.03.
2/2 045K5.17 Unable to write a fair and discriminating RO level question.
Replaced with K/A 033K4.03.
3/1 G2.1.15 Unable to write a fair and discriminating RO level question.
Replaced with K/A G2.1.1.
3/1 G2.1.30 Unable to write discriminating question that maintained its focus on being a plantwide generic question. Replaced with K/A G2.1.3.
ES-401 Record of Rejected K/As Form ES-401-4 3/4 G2.4.39 Unable to write discriminating question that maintained its focus on being a plantwide generic question. Replaced with K/A G2.4.17.
ES-401 PWR Examination Outline Form ES-401-2 Facility: SALEM Date of Exam: JULY 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
N/A N/A 18 4
2 6
2 9
3 1
4 Tier Totals 27 7
3 10
- 2.
Plant Systems 1
28 3
2 5
2 10 2
1 3
Tier Totals 38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
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/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 N/A - Not randomly selected 000008 (APE 8) Pressurizer Vapor Space Accident / 3 N/A - Not randomly selected 000009 (EPE 9) Small Break LOCA / 3 N/A - Not randomly selected 000011 (EPE 11) Large Break LOCA / 3 X
EA 2.07 - Ability to determine or interpret the following as they apply to a Large Break LOCA:
That equipment necessary for functioning of critical pump water seals is operable 3.4 1/76 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 N/A - Not randomly selected 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X G 2.2.22 - Knowledge of limiting conditions for operations and safety limits 4.7 2/77 000025 (APE 25) Loss of Residual Heat Removal System / 4 N/A - Not randomly selected 000026 (APE 26) Loss of Component Cooling Water / 8 X
A 2.06 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The length of time after the loss of CCW flow to a component before that component may be damaged 3.1 3/78 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 N/A - Not randomly selected 000029 (EPE 29) Anticipated Transient Without Scram / 1 N/A - Not randomly selected 000038 (EPE 38) Steam Generator Tube Rupture / 3 X
EA 2.07 - Ability to determine or interpret the following as they apply to a SGTR: Plant conditions, from survey of control room indications 4.8 4/79 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 N/A - Not randomly selected 000054 (APE 54; CE E06) Loss of Main Feedwater /4 N/A - Not randomly selected 000055 (EPE 55) Station Blackout / 6 X
EA 2.05 - Ability to determine or interpret the following as they apply to a Station Blackout: When battery is approaching fully discharged 3.7 5/80 000056 (APE 56) Loss of Offsite Power / 6 N/A - Not randomly selected 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 N/A - Not randomly selected 000058 (APE 58) Loss of DC Power / 6 N/A - Not randomly selected 000062 (APE 62) Loss of Nuclear Service Water / 4 N/A - Not randomly selected 000065 (APE 65) Loss of Instrument Air / 8 N/A - Not randomly selected 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X
G 2.1.7 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation 4.7 6/81 (W E04) LOCA Outside Containment / 3 N/A - Not randomly selected (W E11) Loss of Emergency Coolant Recirculation / 4 N/A - Not randomly selected
ES-401 3
Form ES-401-2 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 N/A - Not randomly selected K/A Category Totals:
4 2
Group Point Total:
18/6
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 N/A - Not randomly selected 000003 (APE 3) Dropped Control Rod / 1 N/A - Not randomly selected 000005 (APE 5) Inoperable/Stuck Control Rod / 1 N/A - Not randomly selected 000024 (APE 24) Emergency Boration / 1 N/A - Not randomly selected 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 N/A - Not randomly selected 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 N/A - Not randomly selected 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 N/A - Not randomly selected 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X G 2.1.32 - Ability to apply system limits and precautions 4.0 7/82 000037 (APE 37) Steam Generator Tube Leak / 3 N/A - Not randomly selected 000051 (APE 51) Loss of Condenser Vacuum / 4 N/A - Not randomly selected 000059 (APE 59) Accidental Liquid Radwaste Release / 9 N/A - Not randomly selected 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 N/A - Not randomly selected 000061 (APE 61) Area Radiation Monitoring System Alarms
/ 7 N/A - Not randomly selected 000067 (APE 67) Plant Fire On Site / 8 X
AA 2.04 - Ability to determine and interpret the following as they apply to the Plant Fire on Site:
The fire's extent of potential operational damage to plant equipment 4.3 8/83 000068 (APE 68; BW A06) Control Room Evacuation / 8 N/A - Not randomly selected 000069 (APE 69; W E14) Loss of Containment Integrity / 5 N/A - Not randomly selected 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /
4 N/A - Not randomly selected 000076 (APE 76) High Reactor Coolant Activity / 9 N/A - Not randomly selected 000078 (APE 78*) RCS Leak / 3 N/A - Not randomly selected (W E01 & E02) Rediagnosis & SI Termination / 3 N/A - Not randomly selected (W E13) Steam Generator Overpressure / 4 N/A - Not randomly selected (W E15) Containment Flooding / 5 N/A - Not randomly selected (W E16) High Containment Radiation /9 N/A - Not randomly selected (BW A01) Plant Runback / 1 N/A - Not randomly selected (BW A02 & A03) Loss of NNI-X/Y/7 N/A - Not randomly selected (BW A04) Turbine Trip / 4 N/A - Not randomly selected (BW A05) Emergency Diesel Actuation / 6 N/A - Not randomly selected (BW A07) Flooding / 8 N/A - Not randomly selected (BW E03) Inadequate Subcooling Margin / 4 N/A - Not randomly selected (BW E08; W E03) LOCA CooldownDepressurization / 4 N/A - Not randomly selected (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 X
EA 2.2 - Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments 3.9 9/84 (BW E13 & E14) EOP Rules and Enclosures N/A - Not randomly selected
ES-401 5
Form ES-401-2 (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 X
EA 2.2 - Ability to determine and interpret the following as they apply to the (Pressurized Thermal Shock): Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments 4.1 10/
85 (CE A16) Excess RCS Leakage / 2 N/A - Not randomly selected (CE E09) Functional Recovery N/A - Not randomly selected (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 N/A - Not randomly selected K/A Category Point Totals:
3 1
Group Point Total:
9/4
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/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 X
G 2.4.34 - Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 4.1 11/
86 004 (SF1; SF2 CVCS) Chemical and Volume Control N/A - Not randomly selected 005 (SF4P RHR) Residual Heat Removal N/A - Not randomly selected 006 (SF2; SF3 ECCS) Emergency Core Cooling X
G 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material 4.2 12/
87 007 (SF5 PRTS) Pressurizer Relief/Quench Tank N/A - Not randomly selected 008 (SF8 CCW) Component Cooling Water N/A - Not randomly selected 010 (SF3 PZR PCS) Pressurizer Pressure Control N/A - Not randomly selected 012 (SF7 RPS) Reactor Protection N/A - Not randomly selected 013 (SF2 ESFAS) Engineered Safety Features Actuation X
A 2.04 - 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 4.2 13/
88 022 (SF5 CCS) Containment Cooling X
A 2.04 - 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 service water 3.2 14/
89 025 (SF5 ICE) Ice Condenser N/A - Not randomly selected, not applicable to Salem 026 (SF5 CSS) Containment Spray N/A - Not randomly selected 039 (SF4S MSS) Main and Reheat Steam N/A - Not randomly selected 059 (SF4S MFW) Main Feedwater N/A - Not randomly selected 061 (SF4S AFW)
Auxiliary/Emergency Feedwater N/A - Not randomly selected 062 (SF6 ED AC) AC Electrical Distribution N/A - Not randomly selected 063 (SF6 ED DC) DC Electrical Distribution N/A - Not randomly selected 064 (SF6 EDG) Emergency Diesel Generator N/A - Not randomly selected 073 (SF7 PRM) Process Radiation Monitoring X
A 2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure 3.2 15/
90
ES-401 7
Form ES-401-2 076 (SF4S SW) Service Water N/A - Not randomly selected 078 (SF8 IAS) Instrument Air N/A - Not randomly selected 103 (SF5 CNT) Containment N/A - Not randomly selected 053 (SF1; SF4P ICS*) Integrated Control N/A for NUREG 1122, Rev. 2 K/A Category Point Totals:
3 2 Group Point Total:
28/5
ES-401 8
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/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 N/A - Not randomly selected 002 (SF2; SF4P RCS) Reactor Coolant N/A - Not randomly selected 011 (SF2 PZR LCS) Pressurizer Level Control X
A 2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of one, two or three charging pumps 3.7 16/
91 014 (SF1 RPI) Rod Position Indication N/A - Not randomly selected 015 (SF7 NI) Nuclear Instrumentation N/A - Not randomly selected 016 (SF7 NNI) Nonnuclear Instrumentation N/A - Not randomly selected 017 (SF7 ITM) In-Core Temperature Monitor N/A - Not randomly selected 027 (SF5 CIRS) Containment Iodine Removal N/A - Not randomly selected 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control X G 2.1.20 - Ability to interpret and execute procedure steps 4.6 17/
92 029 (SF8 CPS) Containment Purge N/A - Not randomly selected 033 (SF8 SFPCS) Spent Fuel Pool Cooling N/A - Not randomly selected 034 (SF8 FHS) Fuel-Handling Equipment N/A - Not randomly selected 035 (SF 4P SG) Steam Generator N/A - Not randomly selected 041 (SF4S SDS) Steam Dump/Turbine Bypass Control N/A - Not randomly selected 045 (SF 4S MTG) Main Turbine Generator N/A - Not randomly selected 055 (SF4S CARS) Condenser Air Removal N/A - Not randomly selected 056 (SF4S CDS) Condensate X
A 2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps 2.8 18/
93 068 (SF9 LRS) Liquid Radwaste N/A - Not randomly selected 071 (SF9 WGS) Waste Gas Disposal N/A - Not randomly selected 072 (SF7 ARM) Area Radiation Monitoring N/A - Not randomly selected 075 (SF8 CW) Circulating Water N/A - Not randomly selected 079 (SF8 SAS**) Station Air N/A - Not randomly selected 086 Fire Protection N/A - Not randomly selected 050 (SF 9 CRV*) Control Room Ventilation N/A for NUREG 1122, Rev. 2 K/A Category Point Totals:
2 1 Group Point Total:
10/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:SALEM SRO Date of Exam:JULY 2020 Category K/A #
Topic RO SRO-only IR IR
- 1. Conduct of Operations 2.1.
G 2.1.40 - Knowledge of refueling administrative requirements 3.9 19/94 2.1.
G 2.1.34 - Knowledge of primary and secondary plant chemistry limits 3.5 20/95 2.1.
2.1.
2.1.
2.1.
Subtotal 2
- 2. Equipment Control 2.2.
G 2.2.7 - Knowledge of the process for conducting special or infrequent tests 3.6 21/96 2.2.
G 2.2.21 - Knowledge of pre-and post-maintenance operability requirements 4.1 22/97 2.2.
2.2.
2.2.
2.2.
Subtotal 2
- 3. Radiation Control 2.3.
G 2.3.11 - Ability to control radiation releases 4.3 23/98 2.3.
2.3.
2.3.
2.3.
2.3.
Subtotal 1
- 4. Emergency Procedures/Plan 2.4.
G 2.4.37 - Knowledge of the lines of authority during implementation of the emergency plan.
4.1 24/99 2.4.
G 2.4.14 - Knowledge of general guidelines for EOP usage 4.5 25/
100 2.4.
2.4.
2.4.
2.4.
Subtotal 2
Tier 3 Point Total 10 7
7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 000022G2.4.18 Unable to write an SRO level question related the specific bases for EOPs. Replaced with K/A 000022G2.2.22.
1/1 000038EA2.04 Unable to write a discriminating SRO level question about interpreting MREM/HR relative to SGTR. Replaced with K/A 000038EA2.07.
1/1 000077G2.2.25 Unable to write a discriminating SRO level question about Tech Spec bases specifically. Replaced with K/A 000077G2.1.7.
1/2 000001G2.2.44 Unable to write question on continuous rod withdrawal as a recent DCP has removed all Auto Rod Withdrawal capability.
Resampled, replaced with 000036G2.1.32.
3/RC G2.3.15 Unable to write discriminating SRO level question about fixed radiation monitors, alarms, etc. Replaced with K/A G2.3.11.
ES-401 Record of Rejected K/As Form ES-401-4
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
SALEM Date of Examination:
JULY 2020 Examination Level: RO SRO Operating Test Number:
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations D, R Calculate Shutdown Margin IAW SC.RE-ST.ZZ-0002(Q)
(2.1.43, RO-4.1, Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.)
Conduct of Operations N, R Verification of Active License Status (2.1.4, RO-3.3, Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.)
Equipment Control M, R Identify Components to Isolate a Service Water System Leak Using Station Drawings (2.2.41, RO-3.5, Ability to obtain and interpret station electrical and mechanical drawings.)
Radiation Control N/A N/A Emergency Plan D, S, P Activate ERDS during an ALERT.
(2.4.43, RO-3.2, Knowledge of emergency communications systems and techniques.)
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
SALEM Date of Examination:
JULY 2020 Examination Level: RO SRO Operating Test Number:
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations N, R Review Completed Shutdown Margin IAW SC.RE-ST.ZZ-0002 (2.1.43 SRO-4.3; Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.)
Conduct of Operations N, R Evaluate a shift staffing situation and take corrective actions IAW administrative procedures.
(2.1.5, SRO-3.9; Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.)
Equipment Control M, R Determine Component Operability and Technical Specification Action Statement(s)
(2.2.37, SRO-4.6; Ability to determine operability and/or availability of safety related equipment.)
Radiation Control D, R Select Release Path for Radioactive Liquid Waste Release IAW S1.OP-SO.WL-0002.
(2.3.6, SRO-3.8; Ability to approve release permits.)
Emergency Plan R, D, P Classify the Event and Complete / Approve the ICMF IAW EP-SA-325-101 (Time Critical)
(2.4.41, SRO-4.6: Knowledge of the emergency action level thresholds and classifications.)
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
SALEM Date of Examination:
JULY 2020 Exam Level: RO SRO-I SRO-U Operating Test Number:
Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*
Safety Function
- a. Respond to Failed Open Pressurizer Spray Valve IAW S2.OP-AB.PZR-0001.
A, D, E 3
- b. Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented.
A, E, L, N 4P
- c. Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001.
A, D 1
- d. Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002.
D 2
- e. Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 During a LOCA.
A, E, EN, N 5
- f. Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001.
(RO Only)
N 7
- g. Perform RCS Cooldown using atmospherics IAW EOP-SGTR-1.
E, N 4S
A, D, P 6
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. Locally Control Charging Flow IAW S2.OP-AB.CR-0001.
R, D, E 2
D, E 8
R, N 9
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SRO-I/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3 9/ 8/ 4 1/ 1/ 1 1/ 1/ 1 (control room system) 1/ 1/ 1 2/ 2/ 1 3/ 3/ 2 (randomly selected) 1/ 1/ 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
SALEM Date of Examination:
JULY 2020 Exam Level: RO SRO-I SRO-U Operating Test Number:
Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*
Safety Function
- a. Respond to Failed Open Pressurizer Spray Valve IAW S2.OP-AB.PZR-0001.
A, D, E 3
- b. Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented.
A, E, L, N 4P
- c. Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001.
A, D 1
- d. Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002.
D 2
- e. Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 During a LOCA.
A, E, EN, N 5
- f. N/A - RO Only N/A N/A
- g. Perform RCS Cooldown using atmospherics IAW EOP-SGTR-1.
E, N 4S
A, D, P 6
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. Locally Control Charging Flow IAW S2.OP-AB.CR-0001.
R, D, E 2
D, E 8
R, N 9
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SRO-I/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3 9/ 8/ 4 1/ 1/ 1 1/ 1/ 1 (control room system) 1/ 1/ 1 2/ 2/ 1 3/ 3/ 2 (randomly selected) 1/ 1/ 1
Appendix D Scenario Outline Form ES-D-1 Facility: _____Salem______
Scenario No.:
____1_____
Op-Test No.: __19-01 NRC__
Examiners:
Operators:
Initial Conditions: IC-201: 90% power, MOL; 23 Charging Pump is in service. The following equipment is out of service: 2C EDG C/T for governor oil replacement and fuel rack lube.
Turnover: The crew is directed to continue power ascension to 100% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using dilution, control rods and turbine load control.
Critical Tasks:
Event No.
Malf. No.
Event Type*
Event Description 1
N/A ALL (R)
Power ascension to 100% at 10% per hour IAW IOP-4 2
RC0022A CRS (TS)
RCS Wide Range Pressure Channel 2PT-405 fails low 3
PR0017A ATC (I)
CRS (I,TS)
PZR Level Channel 1 fails Low 4
EL0048 ATC (C)
BOP (C)
CRS (C, TS)
Loss of #4 SPT and 23 CW Bus 5
EL0134 ALL (M)
EL0144 EL0162 ALL (C)
Loss of 2A 4KV Vital Bus 2B EDG Trips on Overspeed (time delayed)
ABs AR.ZZ-4 AB.CVC-1 AB.CW AB.LOAD-1 AB.LOOP-3 EOPs TRIP-1 LOPA-1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Scenario No.: 1 Target Quantitative Attributes per Scenario (See Section D.5.d)
Actual Attributes Event No.
- 1. Total malfunctions (5-8) 4 3-6
- 2. Malfunctions after EOP entry (1-2) 1 6
- 3. Abnormal events (2-4) 2 3,4
- 4. Major transients (1-2) 1 5
- 5. EOPs entered/requiring substantive actions (1-2) 1 LOPA-1
- 6. Entry into a contingency EOP with substantive actions ( 1 per scenario set) 0 N/A
- 7. Preidentified critical tasks (2) 2 CT-24, CT-25
- 8. Tech Specs exercised ( 2) 3 2,3,4
Appendix D Scenario Outline Form ES-D-1 Facility: _____Salem______
Scenario No.:
____2_____
Op-Test No.: __19-01 NRC__
Examiners:
Operators:
Initial Conditions: IC-211: 100% power, EOL; 21 Charging Pump I/S. The following equipment is out of service:
23 Charging Pump and 21 RHR Pump are C/T for maintenance.
Turnover: The crew is directed to reduce power to 89% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using boration, control rods and turbine load control in preparation for Main Turbine valve testing.
Critical Tasks:
Event No.
Malf. No.
Event Type*
Event Description 1
N/A ALL (R)
Load reduction to 89% at 10% per hour IAW IOP-4 2
SG0100C CRS (TS) 23 SG Pressure Channel 3 fails low 3
VC0087C BOP (C)
CRS (C) 24 vacuum pump trips 4
RC0015D ATC (I)
CRS (I, TS) 24 Loop Cold Leg RTD fails high 5
RC0002 RP0108 ALL (M)
-RCS Leak (18000 gpm, ramped)
-Auto Safety Injection fails to actuate 6
RC0001A ALL (C)
Large Break LOCA 7
RP318A2 BOP (I)
CRS (I) 22 RHR Pump fails to start on SEC signal 8
RH0026B ATC (C)
CRS (C) 22 RHR Pump trips ABs IOP-4 AR.ZZ-2 AB.COND-1 AB.ROD-3 AB.RC-1 EOPs TRIP-1 LOCA-1 LOCA-5 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Scenario No.: 2 Target Quantitative Attributes per Scenario (See Section D.5.d)
Actual Attributes Event No.
- 1. Total malfunctions (5-8) 7 2-8
- 2. Malfunctions after EOP entry (1-2) 3 6,7,8
- 3. Abnormal events (2-4) 3 2,3,4
- 4. Major transients (1-2) 1 5
- 5. EOPs entered/requiring substantive actions (1-2) 1 LOCA-1
- 6. Entry into a contingency EOP with substantive actions ( 1 per scenario set) 1 LOCA-5
- 7. Preidentified critical tasks (2) 3 CT-2, CT-5, CT-29
- 8. Tech Specs exercised ( 2) 2 2,4
Appendix D Scenario Outline Form ES-D-1 Facility: _____Salem______
Scenario No.:
____3_____
Op-Test No.: __19-01 NRC__
Examiners:
Operators:
Initial Conditions: IC-203: 100% power, MOL; 21 SW Pump is C/T.
Turnover: Maintain current power level.
Critical Tasks:
- 1. Manually trip the reactor before transition to EOP-FRSM-1 is required (see WOG CT-1)
Event No.
Malf. No.
Event Type*
Event Description 1
CV0036 RO (I)
CRS (I)
VCT Level Channel 2LT-114 fails high 2
ANN0025 BOP (C)
CRS (TS) 21 SW Accumulator Tank low pressure 3
SW0215C SW0339F RO (C)
CRS (C,TS) 23 SW Pump trips and 26 SW Pump fails to start in Auto 4
CN0117C ALL (C) 23 Condensate Pump trips 5
BF0111A ALL (M) 21 SG Feed Line Break inside containment 6
RP0058 RP0059A RP0059B RP0060A RP0060B RO (I)
CRS (I)
ATWS 7
VL0446 VL0023 ALL (C) 21 BF19 and 21BF13 fails to close ABs AB.CVC-1 AR.ZZ-2 AB.SW-1 AB.CN-1 AB.LOAD-1 EOPs TRIP-1 LOSC-1 TRIP-3 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Scenario No.: 3 Target Quantitative Attributes per Scenario (See Section D.5.d)
Actual Attributes Event No.
- 1. Total malfunctions (5-8) 7 1-7
- 2. Malfunctions after EOP entry (1-2) 2 6,7
- 3. Abnormal events (2-4) 4 1,2,3,4
- 4. Major transients (1-2) 1 5
- 5. EOPs entered/requiring substantive actions (1-2) 3 TRIP-1 LOSC-1 TRIP-3
- 6. Entry into a contingency EOP with substantive actions ( 1 per scenario set) 0 NA
- 7. Preidentified critical tasks (2) 2 5,6
- 8. Tech Specs exercised ( 2) 2 2,3
Appendix D Scenario Outline Form ES-D-1 Facility: _____Salem______
Scenario No.:
____4_____
Op-Test No.: __19-01 NRC__
Examiners:
Operators:
Initial Conditions: IC-204: 2% power, BOL; 21 SGFP I/S. 25 CFCU is in low speed to monitor bearing temperatures following maintenance.
Turnover: The crew is directed to continue power ascension to 10% reactor power IAW S2.OP-IO.ZZ-0003 using control rods, steam dumps, and turbine load control.
Critical Tasks:
Event No.
Malf. No.
Event Type*
Event Description 1
N/A ALL (R)
Continue power ascension to 10% IAW IOP-3 2
RM0207A CRS (TS) 2R1B Control Room Radiation monitor fails high 3
TU0056 RO (C)
CRS (TS) 25 CFCU trips in low speed 4
BF0105A ALL (C) 21 SGFP trips 5
RC42CX RC42CY RC43CX RC43CY ALL (M) 23 RCP high shaft vibrations 6
SG0078A ALL (C) 21 SGTR (650 gpm ramped over 5 minutes) 7 SJ0184A BOP (I)
CRS (I) 21 SI Pump fails to start on SEC signal 8
VL0297 VL0298 ALL (C)
PZR PORV fails to close during RCS depressurization ABs IOP-3 AB.CN-1 AB.RCP-1 AB.SG-1 EOPs TRIP-1 TRIP-2 TRIP-1 SGTR-1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Scenario No.: 4 Target Quantitative Attributes per Scenario (See Section D.5.d)
Actual Attributes Event No.
- 1. Total malfunctions (5-8) 7 2-8
- 2. Malfunctions after EOP entry (1-2) 3 6,7,8
- 3. Abnormal events (2-4) 3 2,3,4
- 4. Major transients (1-2) 1 5
- 5. EOPs entered/requiring substantive actions (1-2) 1 TRIP-1
- 6. Entry into a contingency EOP with substantive actions ( 1 per scenario set) 0 NA
- 7. Preidentified critical tasks (2) 3 CT-18,CT-19, CT-10
- 8. Tech Specs exercised ( 2) 2 2,3
Appendix D Scenario Outline Form ES-D-1 Facility: _____Salem______
Scenario No.:
____5_____
Op-Test No.: __19-01 NRC__
Examiners:
Operators:
Initial Conditions: IC-210: 85% power, EOL; 21 Charging Pump I/S. The following equipment is out of service:
23 Charging Pump C/T for maintenance.
Turnover: 23 Condensate Pump just placed in service following maintenance and commence power ascension to 100% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using dilution, control rods and turbine load control.
Critical Tasks:
- 1. Manually trip the turbine (see WOG CT-13)
Event No.
Malf. No.
Event Type*
Event Description 1
N/A ALL (R)
Commence power ascension to 100% at 10% per hour IAW IOP-4 2
TU0055 ALL (C, TS) 2PT-505 turbine inlet pressure channel fails low.
3 ANCGA072 BOP (C)
CRS (C,TS) 22 ABV Exhaust Fan discharge damper fails close (low air flow) 4 VL0448 ALL (M) 23BF19 fails closed 5
RP0073 RP0279A RP0279B ATC (I)
CRS (I)
Main Turbine fails to Auto trip Auto MSLI fails to actuate 6
EL0145 ATC (I)
CRS (I) 2B 4KV Vital Bus de-energizes on bus differential protection (loss of 22 MDAFW Pump) 7 AF0181A BOP (C)
CRS (C) 21 AFW Pump trips following Rx Trip 8
AF0183 ALL (C) 23 AFW Pump trips on overspeed (loss of all AFW flow) during EOP-TRIP-1 ABs IOP-4 AB.ROD-3 AR.ZZ-11 EOPs TRIP-1 FRHS-1 w/condensate recovery (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Scenario No.: 5 Target Quantitative Attributes per Scenario (See Section D.5.d)
Actual Attributes Event No.
- 1. Total malfunctions (5-8) 7 2-8
- 2. Malfunctions after EOP entry (1-2) 4 5,6,7,8
- 3. Abnormal events (2-4) 2 2,3
- 4. Major transients (1-2) 1 4
- 5. EOPs entered/requiring substantive actions (1-2) 1 TRIP-1
- 6. Entry into a contingency EOP with substantive actions ( 1 per scenario set) 1 FRHS-1
- 7. Preidentified critical tasks (2) 2 CT-13, CT-43
- 8. Tech Specs exercised ( 2) 2 2,3