ML21293A227
| ML21293A227 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/21/2021 |
| From: | Thomas Setzer Operations Branch I |
| To: | Dominion Nuclear Connecticut |
| Setzer T | |
| Shared Package | |
| ML20275A100 | List: |
| References | |
| EPID L-2021-OLL-0005 | |
| Download: ML21293A227 (25) | |
Text
Type text here 9/6/21 9/6/21 N/A N/A N/A N/A N/A N/A N/A N/A
Facility: Millstone 3. Scenario No.: 2K21 NRC-03 (Rev 0). Op-Test No.: 2K21.
Examiners:
Operators:.
Initial Conditions: IC-94, 4% Power, Beginning of life Turnover: The plant is at 4% power at the beginning of life. The SBO Diesel is out of service for electrical maintenance on the synch circuit. 3GMC-P1B, B Stator Cooling Pump, is tagged out to repair a suction flange leak.
Critical Tasks: 1. Manually close an open PORV during Station Blackout (CT-22)
Event No.
Malf.
No Event Type*
Event Description 1
US N RO R BOP N Power ascension from 4% to 8% power using OP 3203, Plant Startup.
2 US TS 3RSS*P1B RECIRC SPRAY PUMP B reported to have motor oil leak.
3 CH06B US C BOP C The B CRDM fan trips. The crew responds using ARP actions.
4 CV05 US I RO I Letdown pressure transmitter 3CHS-PT131 fails low.
(Annunciator response).
5 RX12I US I, TS BOP I C steam generator level transmitter 3FWS-LT539 fails high (AOP 3571).
6 EG06A EG07B EDO1 ALL M Loss of offsite power with failure of station diesels (ECA-0.0).
7 RC07A US C RO C A PORV fails open shortly after manual reactor trip.
8 ED11D ED11E US C RO C A Train Service Water Pumps do not auto start when A EDG is restored - manual start necessary.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Page 1 of 13 Facility:
Millstone 3 Rev.
0 Date of Exam:
09/13/2021 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
2 0
3 4
6 3
18 3
3 6
2 2
2 2
1 1
1 9
2 2
4 Tier Totals 4
2 5
5 7
4 27 5
5 10
- 2.
Plant Systems 1
4 2
4 3
2 0
2 2
3 3
3 28 3
2 5
2 2
0 0
1 0
2 0
2 1
1 1
10 0
2 1
3 Tier Totals 6
2 4
4 2
2 2
4 4
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
2 2
3 3
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.
Page 2 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
1 000007 (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery / 1 X
(000007EK3.01) Knowledge of the reasons for the following responses as they apply to (EPE 7) REACTOR TRIP, STABILIZATION, RECOVERY / 1 (CFR: 41.5 / 41.10 / 45.6 /
45.13): Actions contained in EOP for reactor trip 4
4 2
000008 (APE 8)
Pressurizer Vapor Space Accident /
3 X
(000008AA1.06) Ability to operate and / or monitor the following as they apply to the (APE 8) PRESSURIZER VAPOR SPACE ACCIDENT / 3 (CFR 41.7 / 45.5 / 45.6):
Control of PZR level 3.6 12 3
000009 (EPE 9)
Small Break LOCA / 3 X
(000009EA2.06) Ability to determine and interpret the following as they apply to (EPE 9) SMALL BREAK LOCA / 3 (CFR: 43.5 / 45.13): Whether PZR water inventory loss is imminent 3.8 69 4
000011 (EPE 11)
Large Break LOCA / 3 X
(000011EK1.01) Knowledge of the operational implications of the following concepts as they apply to (EPE 11) LARGE BREAK LOCA / 3 (CFR: 41.8 / 41.10 / 45.3): Natural circulation and cooling, including reflux boiling.
4.1 14 5
000015 (APE 15)
Reactor Coolant Pump Malfunctions / 4 X
(000015G2.1.23) (APE 15) Reactor Coolant Pump Malfunctions / 4: (G2.1.23) Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.4 96 6
000022 (APE 22)
Loss of Reactor Coolant Makeup /
2 X
(000022AA1.02) Ability to operate and / or monitor the following as they apply to the (APE 22) LOSS OF REACTOR COOLANT MAKEUP / 2 (CFR 41.7 / 45.5 / 45.6): CVCS charging low flow alarm, sensor, and indicator 3
25 7
000025 (APE 25)
Loss of Residual Heat Removal System / 4 X
(000025G2.4.31) (APE 25) Loss of Residual Heat Removal System / 4: (G2.4.31) Knowledge of annunciator alarms, indications, or response procedures. (CFR: 41.10 / 45.3) 4.1 86 8
000026 (APE 26)
Loss of Component Cooling Water / 8 X
(000026G2.2.25) (APE 26) Loss of Component Cooling Water / 8: (G2.2.25) Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2) 4.2 83 9
000027 (APE 27)
Pressurizer Pressure Control System Malfunction / 3 X
(000027AK3.01) Knowledge of the reasons for the following responses as they apply to the (APE 27) PRESSURIZER PRESSURE CONTROL SYSTEM MALFUNCTION / 3 (CFR 41.5,41.10 / 45.6 / 45.13): Isolation of PZR spray following loss of PZR heaters 3.5 24 10 000029 (EPE 29)
Anticipated Transient Without Scram / 1 X
(000029EA1.09) Ability to operate and / or monitor the following as they apply to (EPE 29) ANTICIPATED TRANSIENT WITHOUT SCRAM / 1 (CFR: 41.7 / 45.5 / 45.6):
Manual rod control 4.0 64 11 000038 (EPE 38)
Steam Generator Tube Rupture / 3 X
(000038EA2.02) Ability to determine and interpret the following as they apply to (EPE 38) STEAM GENERATOR TUBE RUPTURE / 3 (CFR: 43.5 / 45.13): Existence of an S/G tube rupture and its potential consequences 4.8 97 12 000040 (APE 40; BW E05; CE E05; W E12) Steam Line Rupture Excessive Heat Transfer / 4 X
(000040G2.4.20) (APE 40; BW E05; CE E05; W E12) Steam Line RuptureExcessive Heat Transfer / 4: (G2.4.20)
Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13) 3.8 56 13 000054 (APE 54; CE E06) Loss of Main Feedwater
/4 X
(000054G2.4.4) (APE 54; CE E06) Loss of Main Feedwater
/4: (G2.4.4) Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures. (CFR:
41.10 / 43.2 / 45.6) 4.5 54 14 000055 (EPE 55)
Station Blackout /
6 X
(000055EA1.06) Ability to operate and / or monitor the following as they apply to (EPE 55) STATION BLACKOUT / 6 (CFR: 41.7 / 45.5 / 45.6): Restoration of power with one ED/G 4.1 8
15 000055 (EPE 55)
Station Blackout
/ 6 X
(000055EA2.06) Ability to determine and interpret the following as they apply to (EPE 55) STATION BLACKOUT
/ 6 (CFR: 43.5 / 45.13): Faults and lockouts that must be cleared prior to re-energizing buses 4.1 100 16 000056 (APE 56)
Loss of Offsite Power / 6 X
(000056AA2.19) Ability to determine and interpret the following as they apply to the (APE 56) LOSS OF OFFSITE POWER / 6 (CFR: 43.5 / 45.13): T-cold and T-hot indicators (wide range) 4 22
Page 3 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
17 000057 (APE 57)
Loss of Vital AC Instrument Bus / 6 X
(000057AK3.01) Knowledge of the reasons for the following responses as they apply to the (APE 57) LOSS OF VITAL AC INSTRUMENT BUS / 6 (CFR 41.5,41.10 / 45.6 / 45.13):
Actions contained in EOP for loss of vital ac electrical instrument bus 4.1 38 18 000058 (APE 58)
Loss of DC Power
/ 6 X
(000058AA2.01) Ability to determine and interpret the following as they apply to the (APE 58) LOSS OF DC POWER / 6 (CFR: 43.5 / 45.13): That a loss of dc power has occurred; verification that substitute power sources have come on line 3.7 51 19 000062 (APE 62)
Loss of Nuclear Service Water / 4 X
(000062AA2.04) Ability to determine and interpret the following as they apply to the (APE 62) LOSS OF NUCLEAR SERVICE WATER / 4 (CFR: 43.5 / 45.13): The normal values and upper limits for the temperatures of the components cooled by SWS 2.9 76 20 000065 (APE 65)
Loss of Instrument Air / 8 X
(000065AA2.01) Ability to determine and interpret the following as they apply to the (APE 65) LOSS OF INSTRUMENT AIR / 8 (CFR: 43.5 / 45.13): Cause and effect of low-pressure instrument air alarm 2.9 37 21 000077 (APE 77)
Generator Voltage and Electric Grid Disturbances / 6 X
(000077G2.4.31) (APE 77) Generator Voltage and Electric Grid Disturbances / 6: (G2.4.31) Knowledge of annunciator alarms, indications, or response procedures.
(CFR: 41.10 / 45.3) 4.2 28 22 (W E04) LOCA Outside Containment / 3 X
(WE04EA2.2) Ability to determine and interpret the following as they apply to (W E04) LOCA OUTSIDE CONTAINMENT /
3 (CFR: 43.5 / 45.13): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
3.6 57 23 (W E11) Loss of Emergency Coolant Recirculation / 4 X
(WE11EK1.1) Knowledge of the operational implications of the following concepts as they apply to (W E11) LOSS OF EMERGENCY COOLANT RECIRCULATION / 4 (CFR: 41.8 /
41.10 / 45.3): Components, capacity, and function of emergency systems.
3.7 67 24 (BW E04; W E05)
Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X
(WE05EA2.1) Ability to determine and interpret the following as they apply to (W E05) LOSS OF SECONDARY HEAT SINK / 4 (CFR: 43.5 / 45.13): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
3.4 17 K/A Category Totals:
2 0
3 4
9 6
Group Point Total:
24
Page 4 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
25 000003 (APE 3)
Dropped Control Rod / 1 X
(000003G2.1.19) (APE 3) Dropped Control Rod / 1:
(G2.1.19) Ability to use plant computers to evaluate system or component status. (CFR: 41.10 / 45.12) 3.8 90 26 000005 (APE 5)
Inoperable/Stuck Control Rod / 1 X
(000005AA1.04) Ability to operate and / or monitor the following as they apply to the (APE 5) INOPERABLE/STUCK CONTROL ROD / 1 (CFR 41.7 / 45.5 / 45.6): Reactor and turbine power 3.9 18 27 000028 (APE 28)
Pressurizer (PZR)
Level Control Malfunction / 2 X
(000028AK3.03) Knowledge of the reasons for the following responses as they apply to the (APE 28) PRESSURIZER (PZR) LEVEL CONTROL MALFUNCTION / 2 (CFR 41.5,41.10 / 45.6 / 45.13): False indication of PZR level when PORV or spray valve is open and RCS saturated 3.5 2
28 000032 (APE 32)
Loss of Source Range Nuclear Instrumentation / 7 X
(000032AK2.01) Knowledge of the interrelations between the (APE 32) LOSS OF SOURCE RANGE NUCLEAR INSTRUMENTATION / 7 and the following (CFR 41.7 / 45.7):
Power supplies, including proper switch positions 2.7 27 29 000036 (APE 36; BW/A08) Fuel-Handling Incidents
/ 8 X
(000036AK1.03) Knowledge of the operational implications of the following concepts as they apply to (APE 36) FUEL HANDLING INCIDENTS / 8 (CFR 41.8 / 41.10 / 45.3):
Indications of approaching criticality 4.3 66 30 000037 (APE 37)
Steam Generator Tube Leak / 3 X
(000037AK1.02) Knowledge of the operational implications of the following concepts as they apply to (APE 37) STEAM GENERATOR TUBE LEAK / 3 (CFR 41.8 / 41.10 / 45.3):
Leak rate vs. pressure drop 3.5 39 31 000059 (APE 59)
Accidental Liquid Radwaste Release / 9 X
(000059AA2.02) Ability to determine and interpret the following as they apply to the (APE 59) ACCIDENTAL LIQUID RADWASTE RELEASE / 9 (CFR: 43.5 / 45.13): The permit for liquid radioactive-waste release 2.9 89 32 000067 (APE 67)
Plant Fire On Site / 8 X
(000067AA2.10) Ability to determine and interpret the following as they apply to the (APE 67) PLANT FIRE ON SITE / 8 (CFR: 43.5 / 45.13): Time limit of long-term-breathing air system for control room 2.9 88 33 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X
(000069G2.2.3) (APE 69; W E14) Loss of Containment Integrity / 5: (G2.2.3) (multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5 / 41.6 / 41.7 / 41.10 / 45.12) 3.8 36 34 000074 (EPE 74; W E06 & E07)
Inadequate Core Cooling / 4 X
(WE06EK3.3) Knowledge of the reasons for the following responses as they apply to (W E06) DEGRADED CORE COOLING / 4 (CFR: 41.5 / 41.10 / 45.6 / 45.13): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
4 13 35 000076 (APE 76)
High Reactor Coolant Activity / 9 X
(000076AA2.04) Ability to determine and interpret the following as they apply to the (APE 76) HIGH REACTOR COOLANT ACTIVITY / 9 (CFR: 43.5 / 45.13): Process effluent radiation chart recorder 2.6 60 36 (W E01 & E02)
Rediagnosis & SI Termination / 3 X
((W E01 & E02)G2.1.32) Rediagnosis & SI Termination / 3:
(G2.1.32) Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 4.0 93 37 (CE A11**; W E08) RCS Overcooling Pressurized Thermal Shock / 4 X
(WE08EK2.1) Knowledge of the interrelations between (W E08) PRESSURIZED THERMAL SHOCK / 4 and the following (CFR: 41.7 / 45.7): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and automatic and manual features.
3.4 32 000001 (APE 1)
Continuous Rod Withdrawal / 1 000024 (APE 24)
Emergency Boration / 1 000033 (APE 33)
Loss of Intermediate Range Nuclear Instrumentation / 7 000051 (APE 51)
Page 5 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
000060 (APE 60)
Accidental Gaseous Radwaste Release / 9 000061 (APE 61)
Area Radiation Monitoring System Alarms / 7 000068 (APE 68; BW A06) Control Room Evacuation
/ 8 000078 (APE 78*)
RCS Leak / 3 (W E13) Steam Generator Overpressure / 4 (W E15)
Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW E08; W E03)
LOCA Cooldown Depressurization /
4 (BW E09; CE A13**; W E09 &
E10) Natural Circulation/4 K/A Category Totals:
2 2
2 1
3 3
Group Point Total:
13
Page 6 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
38 003 (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM X
(003A1.09) Ability to predict and/or monitor changes in parameters associated with operating the (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM controls including (CFR: 41.5 / 45.5): Seal flow and D/P 2.8 7
39 003 (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM X
(003K1.12) Knowledge of the physical connections and/or cause-effect relationships between (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): CCWS 3.3 73 40 004 (SF1; SF2 CVCS)
CHEMICAL AND VOLUME CONTROL SYSTEM X
(004A4.05) (SF1; SF2 CVCS)
CHEMICAL AND VOLUME CONTROL SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8):
Letdown pressure and temperature control valves.
3.6 21 41 005 (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM X
(005G2.4.8) (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM: (G2.4.8) Knowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR:
41.10 / 43.5 / 45.13) 4.5 29 42 006 (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM X
(006A1.01) Ability to predict and/or monitor changes in parameters associated with operating the (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM controls including (CFR: 41.5 / 45.5):
Avoidance of thermal and pressure stresses due to pump startup 3.4 5
43 006 (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM X
(006G2.1.30) (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM: (G2.1.30)
Ability to locate and operate components, including local controls.(CFR: 41.7 / 45.7) 4.4 61 44 007 (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM X
(007A2.05) Ability to (a) predict the impacts of the following on the (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/ 45.3/45.13):
Exceeding PRT high-pressure limits 3.2 1
45 008 (SF8 CCW)
COMPONENT COOLING WATER SYSTEM X
(008A3.02) Ability to monitor automatic operations of the (SF8 CCW) COMPONENT COOLING WATER SYSTEM including (CFR: 41.7 / 45.5):
Operation of the CCW pumps, including interlocks and the CCW booster pump 3.2 15
Page 7 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
46 010 (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM X
(010K2.02) (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM Knowledge of electrical power supplies to the following (CFR:
41.7): Controller for PZR spray valve 2.5 75 47 012 (SF7 RPS)
(012A2.06) Ability to (a) predict the impacts of the following on the (SF7 RPS)
REACTOR PROTECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 /43.5/ 45.3/45.13): Failure of RPS signal to trip the reactor 4.7 85 48 012 (SF7 RPS)
(012K2.01) (SF7 RPS)
REACTOR PROTECTION SYSTEM Knowledge of electrical power supplies to the following (CFR: 41.7): RPS channels, components, and interconnections 3.3 74 49 013 (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013A2.01) Ability to (a) predict the impacts of the following on the (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 /43.5/ 45.3/45.13): LOCA 4.8 79 50 013 (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013K1.11) Knowledge of the physical connections and/or cause-effect relationships between (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): CVCS 3.8 46 51 022 (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022G2.4.6) (SF5 CCS)
CONTAINMENT COOLING SYSTEM: (G2.4.6) Knowledge of EOP mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 4.7 91 52 022 (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022K3.02) Knowledge of the effect that a loss or malfunction of the (SF5 CCS)
CONTAINMENT COOLING SYSTEM will have on the following (CFR: 41.7 / 45.6):
Containment instrumentation readings 3.3 59
Page 8 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
53 061 (SF4S AFW)
AUXILIARY /
(061A2.05) Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5 / 43.5 / 45.3 /
45.13): Automatic control malfunction 3.1 6
54 073 (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM X
(073K5.03) Knowledge of the operational implications as they apply to concepts as they apply to the PRM system:
(CFR: 41.5 / 45.7): Relationship between radiation intensity and exposure limits 2.9 34 55 026 (SF5 CSS)
CONTAINMENT SPRAY SYSTEM X
(026K3.01) Knowledge of the effect that a loss or malfunction of the (SF5 CSS)
CONTAINMENT SPRAY SYSTEM will have on the following (CFR: 41.7 / 45.6):
Containment Cooling System 3.9 10 56 078 (SF8 IAS)
INSTRUMENT AIR SYSTEM X
(039G2.2.25) (SF8 IAS)
INSTRUMENT AIR SYSTEM:
(G2.2.3) Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7
/ 43.2) 4.2 92 57 039 (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM X
(039G2.4.46) (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM: (G2.4.46) Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 / 43.5 /
45.3 / 45.12) 4.2 41 58 059 (SF4S MFW)
MAIN FEEDWATER SYSTEM X
(059K3.03) Knowledge of the effect that a loss or malfunction of the (SF4S MFW) MAIN FEEDWATER SYSTEM will have on the following (CFR:
41.7 / 45.6): S/Gs 3.5 47 59 061 (SF4S AFW)
AUXILIARY /
(061K5.01) Knowledge of the operational implications of the following concepts as they apply to the (SF4S AFW)
AUXILIARY / EMERGENCY FEEDWATER SYSTEM (CFR:
41.5 / 45.7): Relationship between AFW flow and RCS heat transfer 3.9 55 60 062 (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062K3.02) Knowledge of the effect that a loss or malfunction of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM will have on the following (CFR: 41.7 / 45.6):
ED/G 4.1 63 61 062 (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062K4.07) Knowledge of (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): One-line diagram of 4kV to 480V distribution, including sources of normal and alternative power 2.7 40
Page 9 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
DC ELECTRICAL DISTRIBUTION SYSTEM X
(063K4.04) Knowledge of (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): Trips 2.6 43 63 064 (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X
(064A3.12) Ability to monitor automatic operations of the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM including (CFR: 41.7 /
45.5): Purpose of automatic load sequencer 3.3 68 64 064 (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X
(064A4.02) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8):
Adjustment of exciter voltage (using voltage control switch) 3.4 72 65 073 (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM X
(073A4.01) (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8):
Effluent release 3.9 35 66 076 (SF4S SW)
SERVICE WATER SYSTEM X
(076A2.01) Ability to (a) predict the impacts of the following on the (SF4S SW)
SERVICE WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/ 45.3/45.13):
Loss of SWS 3.7 94 67 076 (SF4S SW)
SERVICE WATER SYSTEM X
(076K1.05) Knowledge of the physical connections and/or cause-effect relationships between (SF4S SW) SERVICE WATER SYSTEM and the following (CFR: 41.2 to 41.9 /
45.7 to 45.8): D/G 3.8 30 68 078 (SF8 IAS)
INSTRUMENT AIR SYSTEM X
(078A3.01) Ability to monitor automatic operations of the (SF8 IAS) INSTRUMENT AIR SYSTEM including (CFR: 41.7 /
45.5): Air pressure 3.2 23 69 103 (SF5 CNT)
CONTAINMENT SYSTEM X
(103K1.01) Knowledge of the physical connections and/or cause-effect relationships between (SF5 CNT)
CONTAINMENT SYSTEM and the following (CFR: 41.2 to 41.9
/ 45.7 to 45.8): CCS 3.9 45 70 103 (SF5 CNT)
CONTAINMENT SYSTEM X
(103K4.01) Knowledge of (SF5 CNT) CONTAINMENT SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7):
Vacuum breaker protection 3.7 11 K/A Category Totals:
4 2
4 3
2 0
2 5
3 3
5 Group Point Total:
33
Page 10 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 2/Group 2 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
71 001 (SF1 CRDS)
CONTROL ROD DRIVE SYSTEM X
(001K1.03) Knowledge of the physical connections and/or cause-effect relationships between (SF1 CRDS)
CONTROL ROD DRIVE SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): CRDM 3.4 44 72 011 (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM X
(011A4.01) (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8):
Charging pump and flow controls 3.2 33 73 015 (SF7 NI)
NUCLEAR INSTRUMENTATION SYSTEM X
(015G2.2.40) (SF7 NI)
NUCLEAR INSTRUMENTATION SYSTEM: (G2.2.40) Ability to apply Technical Specifications for a system.
(CFR: 41.10 / 43.2 / 43.5 /
45.3) 4.7 80 74 017 (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM X
(017K6.01) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM (CFR:
41.7 / 45.7): Sensors and detectors 3
16 75 027 (SF5 CIRS)
CONTAINMENT IODINE REMOVAL SYSTEM X
(027A2.01) Ability to (a) predict the impacts of the following on the (SF5 CIRS)
CONTAINMENT IODINE REMOVAL SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 /43.5/ 45.3/45.13): High temperature in the filter system 3.3 81 76 028 (SF5 HRPS)
HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM X
(028K6.01) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF5 HRPS)
HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM (CFR: 41.7 / 45.7):
Hydrogen recombiners 3.1 20 77 033 (SF8 SFPCS)
SPENT FUEL POOL COOLING SYSTEM X
(033A2.02) Ability to (a) predict the impacts of the following on the (SF8 SFPCS)
SPENT FUEL POOL COOLING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 /43.5/ 45.3/45.13): Loss of SFPCS 3
49 78 041 (SF4S SDS)
STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM X
(041A3.03) Ability to monitor automatic operations of the (SF4S SDS) STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM including (CFR: 41.7 / 45.5): Steam flow 2.8 9
Page 11 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 2/Group 2 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
79 045 (SF4S MTG)
MAIN TURBINE GENERATOR SYSTEM X
(045A2.17) Ability to (a) predict the impacts of the following on the (SF4S MTG)
MAIN TURBINE GENERATOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 /43.5/ 45.3/45.13):
Malfunction of electrohydraulic control 2.7 50 80 055 (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM X
(055G2.1.20) (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM: (G2.1.20) Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5 / 45.12) 4.6 42 81 068 (SF9 LRS)
LIQUID RADWASTE SYSTEM X
(068A2.02) Ability to (a) predict the impacts of the following on the (SF9 LRS)
LIQUID RADWASTE SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 /43.5/ 45.3/45.13): Lack of tank recirculation prior to release 2.8 82 82 075 (SF8 CW)
(075K1.02) Knowledge of the physical connections and/or cause-effect relationships between (SF8 CW)
CIRCULATING WATER SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): Liquid radwaste discharge 2.9 3
83 079 (SF8 SAS**)
STATION AIR SYSTEM X
(079K4.01) Knowledge of (SF8 SAS**) STATION AIR SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR:
41.7): Cross-connect with IAS 3.2 62 002 (SF2; SF4P RCS) REACTOR COOLANT SYSTEM 014 (SF1 RPI) ROD POSITION INDICATION SYSTEM 016 (SF7 NNI)
NONNUCLEAR INSTRUMENTATION SYSTEM 029 (SF8 CPS)
CONTAINMENT PURGE SYSTEM 034 (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM 035 (SF4P SG)
STEAM GENERATOR SYSTEM 056 (SF4S CDS)
CONDENSATE SYSTEM
Page 12 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 2/Group 2 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
071 (SF9 WGS)
WASTE GAS DISPOSAL SYSTEM 072 (SF7 ARM)
AREA RADIATION MONITORING SYSTEM 086 (SF8 FPS) FIRE PROTECTION SYSTEM 086 (SF8 FPS) FIRE PROTECTION SYSTEM K/A Category Totals:
2 0
0 1
0 2
0 4
1 1
2 Group Point Total:
13
Page 13 of 13 ES-401 PWR Examination Outline (Millstone 3)
Form ES-401-3 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
Facility:
Millstone 3 Date of Exam:
09/13/2021 Category K/A #
Topic RO SRO-Only Item #
IR Q#
IR Q#
- 1. Conduct of Operations G2.1.13 (G2.1.13) Knowledge of facility requirements for controlling vital/controlled access. (CFR: 41.10 / 43.5 / 45.9 / 45.10) 84 2.5 65 G2.1.42 (G2.1.42) Knowledge of new and spent fuel movement procedures. (CFR:
41.10 / 43.7 / 45.13) 85 2.5 19 G2.1.36 (G2.1.36) Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10 / 43.6 / 45.7) 86 4.1 78 G2.1.43 (G2.1.43) Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 /
45.6) 87 4.3 99 Subtotal 2
2
- 2. Equipment Control G2.2.43 (G2.2.43) Knowledge of the process used to track inoperable alarms. (CFR:
41.10 / 43.5 / 45.13) 88 3
48 G2.2.7 (G2.2.7) Knowledge of the process for conducting special or infrequent tests. (CFR: 41.10 / 43.3 / 45.13) 89 2.9 26 G2.2.23 (G2.2.23) Ability to track Technical Specification limiting conditions for operations. (CFR: 41.10 / 43.2 / 45.13) 90 4.6 95 G2.2.6 (G2.2.6) Knowledge of the process for making changes to procedures.
(CFR: 41.10 / 43.3 / 45.13) 91 3.6 98 Subtotal 2
2
- 3. Radiation Control G2.3.11 (G2.3.11) Ability to control radiation releases. (CFR: 41.11 / 43.4 / 45.10) 92 3.8 58 G2.3.6 (G2.3.6) Ability to approve release permits. (CFR: 41.13 / 43.4 / 45.10) 93 3.8 84 G2.3.4 (G2.3.4) Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 94 3.2 53 G2.3.5 (G2.3.5) Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11 / 41.12 / 43.4 / 45.9) 95 2.9 31 Subtotal 3
1
- 4. Emergency Procedures/Plan G2.4.12 (G2.4.12) Knowledge of general operating crew responsibilities during emergency operations. (CFR: 41.10 / 45.12) 96 4.3 77 G2.4.25 (G2.4.25) Knowledge of fire protection procedures. (CFR: 41.10 / 43.5 /
45.13) 97 3.3 70 G2.4.40 (G2.4.40) Knowledge of SRO responsibilities in emergency plan implementation. (CFR: 41.10 / 43.5 / 45.11) 98 2.7 52 G2.4.26 (G2.4.26) Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage. (CFR: 41.10 / 43.5 /
45.12) 99 3.6 87 G2.4.27 (G2.4.27) Knowledge of fire in the plant procedures. (CFR: 41.10 / 43.5 /
45.13) 100 3.4 71 Subtotal 3
2
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/2 Rejected Emergency and Abnormal Plant Evolutions associated with Babcock and Wilcox (BW) and Combustion Engineering (CE) reactors - Millstone Unit 3 is a Westinghouse design.
2/1 Rejected 025 (SF5 ICE) Ice Condenser - Millstone Unit 3 does not have an ice condenser installed.
2/1 Rejected 053 (SF1; SF4P ICS*) Integrated Control - Millstone Unit 3 does not have ICS. This topic has no operational significance but similar topics are covered in MSRs.
1/2 The licensee requested to add 7 items to the Tier 1, Group 2 list of E/APEs to be available for random selection in accordance with ES-401 Attachment 1:
- AOP 3550, Turbine / Generator Trip
- AOP 3569, Severe Weather Conditions
- AOP 3571, Instrument Failure Response
- AOP 3577, Loss of a 4kv bus
- AOP 3579, Response to Turbine Runback 2/2 The licensee requested to add 2 items to the Tier 2, Group 2 list of Plant Systems to be available for random selection in accordance with ES-401 Attachment 1:
- SBO (Station Blackout) Diesel ALL Rejected generics 2.2.3 and 2.2.4 as Millstone 3 is a single unit site 1/1 011K1.01 RO Question 14 Natural circulation will not develop in a large break LOCA at MS3 due to the energy that is relieved out the break.
Randomly reselected 011K312 1/1 055A1.06 RO Question 8 This K/A will overlap with the Operating exam. Randomly reselected 055A1.07 1/1 065A2.01 RO Question 37 This K/A overlaps with other written questions. Randomly reselected 065A2.08
ES-401 Record of Rejected K/As Form ES-401-4 1/2 059A2.02 SRO Question 89 Liquid Radwaste is oversampled. Randomly reselected new E/APE. AOP 3555, RCS Leak, was selected, A2.02 1/2 067A2.10 SRO Question 88 There is no long term breathing system in the control room, only SCBAs. Randomly reselected 067A2.07 1/2 069G2.2.3 RO Question 36 MS3 is not a multi-unit site. Randomly reselected 069G2.4.21 1/2 076A2.04 RO Question 60 MS3 does not have a process effluent radiation chart recorder in the CR. E/APE is also of low importance.
Randomly reselected 033A2.11 2/1 073K5.03 RO Question 34 K/A is too simplistic, GFES level. Randomly reselected 004K5.19 2/1 078G2.2.25 SRO Question 92 No TS bases for instrument air that would lead to a discriminating question. Randomly reselected G2.4.11 2/1 073A4.01 RO Question 35 Process radiation monitoring K/A is oversampled. Randomly reselected 073K4.01 2/1 078A3.01 RO Question 23 Instrument air system air pressure topic is oversampled.
Randomly reselected 078K2.01 2/1 103K4.01 RO Question 11 MS3 does not have containment vacuum breakers.
Randomly reselected 103K4.06 2/2 028K6.01 RO Question 20 No H2 recombiners at MS3. Randomly reselected 034K6.02 2/2 068A2.02 SRO Question 82 Cannot write a discriminating question at SRO level.
Randomly reselected 002A2.03 2/2 075K1.02 RO Question 3 Liquid radwaste is oversampled. Randomly reselected 016K1.03 3
G2.2.23 SRO Question 95 Cant write a discriminating question at SRO level. Randomly reselected G2.2.18 1/1 026G2.2.25 SRO Question 83 Cant write a discriminating question for bases of TSs in Component Cooling water. Randomly reselected 026G2.2.22 3
G2.4.40 RO Question 52 This generic K/A tests SRO level knowledge. Randomly reselected G2.4.14
ES-401 Record of Rejected K/As Form ES-401-4 1/1 APE 8 A1.06 RO Question 12 APE 8 Pressurizer Vapor Space Accident topic is already being tested in Question 2 (overlap). Randomly selected WE11 Loss of Emergency Coolant Recirculation, A1.03 1/1 062AA2.04 SRO Question 76 Double jeopardy with question #94. Randomly selected G2.4.41 3
G2.1.42 RO Question 19 K/A deals with fuel handling, which is mostly SRO. Cannot write a discriminating question. Randomly selected G2.1.37 2/2 034K6.02 RO Question 20 K/A deals with fuel handling/refueling, which is mostly SRO.
Cannot write a discriminating question. Randomly selected AMSAC K6.01 (licensees site priority list of systems added into the random draw per ES 401 Attachment 1))
3 G2.4.27 RO Question 71 Fire is oversampled on other exam questions (#70, #87).
Randomly selected G2.4.47 2/1 010K2.02 RO Question 75 This K/A topic is minutia, cannot write a discriminating question. Randomly selected 010K2.01 2/2 027A2.01 SRO Question 81 This K/A topic is minutia, cannot write a discriminating question. Randomly selected 014A2.04