ML20274A136
| ML20274A136 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/07/2020 |
| From: | Division of Reactor Safety I |
| To: | |
| Shared Package | |
| ML19105A101 | List: |
| References | |
| CAC 000500, ES-301-1, ES-301-2, ES-401-2, ES-401-3, ES-401-4, ES-D-1 | |
| Download: ML20274A136 (22) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Exam Level: RO Date of Examination: 1/27/2020 Operating Test #: 2020 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, D Estimate Time to Boil G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (RO-3.9)
Conduct of Operations R, D Determine Shutdown Margin G2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (RO-4.3)
Equipment Control R, N Print Reading G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (RO-3.5)
Emergency Plan R, N Respond to a Plant Fire G2.4.27 Knowledge of fire in the plant procedures (RO-3.4)
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) [2]
(N)ew or (M)odified from bank ( 1) [2]
(P)revious 2 exams ( 1; randomly selected) [0]
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Exam Level: RO Date of Examination: 1/27/2020 Operating Test #: 2020 Control Room Systems:
Safety Function
- a.
SIM-1 Respond to a CEDS failure 001 Control Rod Drive System A4.03 CRDS mode control (RO-4.0)
A, N 1
- b. SIM-2 Verify Validity of CIS Actuation 013 Engineered Safety Features Actuation System A3.01 Input channels and logic (RO-3.7)
D, EN 2
- c.
SIM-3 Verify HPSI/LPSI Flow 006 Emergency Core Cooling System A4.07 ECCS pumps and valves (RO-4.4)
A, EN, N, L 3
- d. SIM-4 Attempt to Correct the Abnormal SDC Condition 005 Residual Heat Removal System A4.01 Controls and indications for RHR pumps (RO-3.6)
A, D, L 4P
- e.
SIM-5 Align Saltwater Emergency Overboard 076 Service Water System A4.04 Emergency heat loads (RO-3.5)
N 4S
- f.
SIM-6 Pressurizer Vent Valve Testing 007 Pressurizer Relief Tank/Quench Tank System A4.04 PZR Vent Valve (RO-2.6)
N, L 5
- g. SIM-7 Rapid Shutdown of the Diesel 064 Emergency Diesel Generator System A4.06 Manual Start, loading, and stopping of the EDG (RO-3.9)
N 6
- h. SIM-8 Respond to RCS leakage into Component Cooling System 008 Component Cooling Water System A4.01 CCW indications and controls (RO-3.3)
A, N 8
In-Plant Systems
- 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
- i.
PLT-1 Align AFW flow control to 1C43 061 Auxiliary/Emergency Feedwater System 2.1.30 Ability to locate and operate components (RO-4.4)
D, E 4S
- j.
PLT-2 Operate MCC Load Breakers 068 Control Room Evacuation AA1.10 Power Distribution: ac and dc (RO-3.7)
N, E, R 6
- k. PLT-3 Respond to a Loss of Instrument Air 065 Loss of Instrument Air AA1.04 Emergency air compressor (RO-3.5)
D, E 8
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (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 [4]
9 / 8 / 4 [4]
1 / 1 / 1 [3]
1 / 1 / 1 (control room system) [2]
1 / 1 / 1 [3]
2 / 2 / 1 [7 including 3(A)]
3 / 3 / 2 (randomly selected) [0]
1 / 1 / 1 [1]
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Exam Level: SRO-I Date of Examination: 1/27/2020 Operating Test #: 2020 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, N Evaluate Overtime Work Request G2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (SRO-3.9)
Conduct of Operations R, D Supervisory Review of Shutdown Margin G2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (SRO-4.6)
Equipment Control R, N Print Reading and Application of Tech Specs G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (SRO-3.9)
Radiation Control R, N Administrative Requirements for RMS Inoperability G2.3.15 - Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (SRO-3.1)
Emergency Plan R, D Perform Shift Emergency Director Functions G2.4.41 Knowledge of emergency action level thresholds and classifications. (SRO-4.6)
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) [2]
(N)ew or (M)odified from bank ( 1) [3]
(P)revious 2 exams ( 1; randomly selected) [0]
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Exam Level: SRO-I Date of Examination: 1/27/2020 Operating Test #: 2020 Control Room Systems:
Safety Function
- a.
SIM-1 Shutdown CEA Free Movement Test 001 Control Rod Drive System A4.03 CRDS mode control (SRO-3.7)
A, N 1
- b. SIM-2 Verify Validity of CIS Actuation 013 Engineered Safety Features Actuation System A3.01 Input channels and logic (SRO-3.9)
D, EN 2
- c.
SIM-3 Verify HPSI/LPSI Flow 006 Emergency Core Cooling System A4.07 ECCS pumps and valves (SRO-4.4)
A, EN, N, L 3
- d. SIM-4 Attempt to Correct the Abnormal SDC Condition 005 Residual Heat Removal System A4.01 Controls and indications for RHR pumps (SRO-3.4)
A, D, L 4P
- e.
SIM-5 Align Saltwater Emergency Overboard 076 Service Water System A4.04 Emergency heat loads (SRO-3.5)
N 4S
- f.
SIM-7 Rapid Shutdown of the Diesel 064 Emergency Diesel Generator System A4.06 Manual Start, loading, and stopping of the EDG (SRO-3.9)
N 6
- g. SIM-8 Respond to RCS leakage into Component Cooling System 008 Component Cooling Water System A4.01 CCW indications and controls (SRO-3.1)
A, N 8
In-Plant Systems
- 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
- h. PLT-1 Align AFW flow control to 1C43 061 Auxiliary/Emergency Feedwater System 2.1.30 Ability to locate and operate components (SRO-4.4)
D, E 4S
- i.
PLT-2 Operate MCC Load Breakers 068 Control Room Evacuation AA1.10 Power Distribution: ac and dc (SRO-3.9)
N, E, R 6
- j.
PLT-3 Respond to a Loss of Instrument Air 065 Loss of Instrument Air AA1.04 Emergency air compressor (SRO-3.4)
D, E 8
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (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 [4]
9 / 8 / 4 [4]
1 / 1 / 1 [3]
1 / 1 / 1 (control room system) [2]
1 / 1 / 1 [2]
2 / 2 / 1 [6 including 3(A)]
3 / 3 / 2 (randomly selected) [0]
1 / 1 / 1 [1]
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Exam Level: SRO-U Date of Examination: 1/27/2020 Operating Test #: 2020 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, N Evaluate Overtime Work Request G2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (SRO-3.9)
Conduct of Operations R, D Supervisory Review of Shutdown Margin G2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (SRO-4.6)
Equipment Control R, N Print Reading and Application of Tech Specs G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (SRO-3.9)
Radiation Control R, N Administrative Requirements for RMS Inoperability G2.3.15 - Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (SRO-3.1)
Emergency Plan R, D Perform Shift Emergency Director Functions G2.4.41 Knowledge of emergency action level thresholds and classifications. (SRO-4.6)
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) [2]
(N)ew or (M)odified from bank ( 1) [3]
(P)revious 2 exams ( 1; randomly selected) [0]
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Exam Level: SRO-U Date of Examination: 1/27/2020 Operating Test #: 2020 Control Room Systems:
Safety Function
- a.
SIM-2 Verify Validity of CIS Actuation 013 Engineered Safety Features Actuation System A3.01 Input channels and logic (SRO-3.9)
D, EN 2
- b. SIM-3 Verify HPSI/LPSI Flow 006 Emergency Core Cooling System A4.07 ECCS pumps and valves (SRO-4.4)
A, EN, N, L 3
- c.
SIM-8 Respond to RCS leakage into Component Cooling System 008 Component Cooling Water System A4.01 CCW indications and controls (SRO-3.1)
A, N 8
In-Plant Systems
- 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
- d. PLT-1 Align AFW flow control to 1C43 061 Auxiliary/Emergency Feedwater System 2.1.30 Ability to locate and operate components (SRO-4.4)
D, E 4S
- e.
PLT-2 Operate MCC Load Breakers 068 Control Room Evacuation AA1.10 Power Distribution: ac and dc (SRO-3.9)
N, E, R 6
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (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 [2]
9 / 8 / 4 [2]
1 / 1 / 1 [2]
1 / 1 / 1 (control room system) [2]
1 / 1 / 1 [1]
2 / 2 / 1 [3 including 2(A)]
3 / 3 / 2 (randomly selected) [0]
1 / 1 / 1 [1]
ES-401 PWR Examination Outline Form ES-401-2 Facility: Calvert Cliffs Date of Exam: January 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
3 N/A 3
18 3
3 6
2 2
2 2
1 1
1 9
2 2
4 Tier Totals 5
5 5
4 4
4 27 5
5 10
- 2.
Plant Systems 1
3 2
3 2
2 2
3 3
2 3
3 28 3
2 5
2 1
0 1
1 1
1 1
1 1
1 1
10 0
2 1
3 Tier Totals 4
2 4
3 3
3 4
4 3
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 2
3 2
1 2
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 6
Relationship of emergency feedwater flow to S/G and decay heat removal following reactor trip 3.7 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 6
Control of PZR level 3.6 2
000009 (EPE 9) Small Break LOCA / 3 24 ECCS throttling or termination criteria 4.1 3
000011 (EPE 11) Large Break LOCA / 3 2
Pumps 2.6 4
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 1
Natural circulation in a nuclear reactor power plant 4.4 5
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 2
Relationship of charging flow to pressure differential between charging and RCS 2.7 6
000025 (APE 25) Loss of Residual Heat Removal System / 4 4
Location and isolability of leaks 3.3 7
000026 (APE 26) Loss of Component Cooling Water / 8 1
Location of a leak in the CCWS 2.9 8
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 2
SCR-controlled heaters in manual mode 3.1 9
000029 (EPE 29) Anticipated Transient Without Scram / 1 2.4.6 Knowledge symptom based EOP mitigation strategies.
3.7 10 000038 (EPE 38) Steam Generator Tube Rupture / 3 6
Actions contained in EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures 4.2 11 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 2
Sensors and detectors 2.6 12 000055 (EPE 55) Station Blackout / 6 2
RCS core cooling through natural circulation cooling to S/G cooling 4.4 13 000056 (APE 56) Loss of Offsite Power / 6 2.4.31 Knowledge of annunciators alarms, indications or response procedures 4.2 14 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 3
Feedwater pump speed to control pressure and level in S/G 3.6 15 000058 (APE 58) Loss of DC Power / 6 2.4.3 Ability to identify post-accident instrumentation.
3.7 16 Loss of Salt Water 2
The automatic actions (alignments) within the salt water system resulting from the actuation of the ESFAS.
3.6 17 000054 (CE E06) Loss of Main Feedwater
/4 2
Facility s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
3.5 18 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.
4.2 76 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 1
Whether charging line leak exists 3.8 77 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 2.2.22 Knowledge of limiting conditions for operations and safety limits.
4.7 78 000058 (APE 58) Loss of DC Power / 6 2
125V dc bus voltage, low/critical low, alarm 3.6 79
ES-401 3
Form ES-401-2 000062 (APE 62) Loss of Nuclear Service Water / 4 2.1.30 Ability to locate and operate components, including local controls.
4.0 80 000065 (APE 65) Loss of Instrument Air / 8 5
When to commence plant shutdown if instrument air pressure is decreasing 4.1 81 K/A Category Totals:
3 3
3 3
3/3 3/3 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 21 Integral rod worth 2.9 19 000003 (APE 3) Dropped Control Rod / 1 17 Fuel temperature coefficient 2.9 20 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 1
Power supplies, including proper switch positions 2.7 21 000051 (APE 51) Loss of Condenser Vacuum / 4 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 4.2 22 000061 (APE 61) Area Radiation Monitoring System Alarms
/ 7 1
Automatic actuation 3.6 23 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /
4 7
The difference between a LOCA and inadequate core cooling from trends and indicators 4.1 24 (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 1
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
3.2 25 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 1
Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
3.4 26 (CE E09) Functional Recovery 3
Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
3.7 27 000005 (APE 5) Inoperable/Stuck Control Rod / 1 2.2.40 Ability to apply Technical Specifications for a system.
4.7 82 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 14 The effect on indicated PZR levels, given a change in ambient pressure and temperature of reflux boiling 2.8 83 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
4.1 84 (CE A16) Excess RCS Leakage / 2 1
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
3.5 85 K/A Category Point Totals:
2 2
2 1
1/2 1/2 Group Point Total:
9/4
ES-401 5
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 3
RCP seal system 3.3 28 003 (SF4P RCP) Reactor Coolant Pump 4
Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow and feed flow 3.2 29 004 (SF1; SF2 CVCS) Chemical and Volume Control 1
Importance of oxygen control in RCS 2.7 30 005 (SF4P RHR) Residual Heat Removal 3
RHR heat exchanger 2.5 31 006 (SF2; SF3 ECCS) Emergency Core Cooling 6
Water hammer 3.3 32 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 3
RCS 3.0 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 1
Containment 3.3 34 008 (SF8 CCW) Component Cooling Water 1
Loads cooled by CCWS 3.4 35 010 (SF3 PZR PCS) Pressurizer Pressure Control 3
Over pressure control 3.8 36 012 (SF7 RPS) Reactor Protection 7
M/G set breakers 3.9 37 013 (SF2 ESFAS) Engineered Safety Features Actuation 2.4.20 Knowledge of operational implications of EOP warnings, cautions and notes.
3.8 38 022 (SF5 CCS) Containment Cooling 1
Containment equipment subject to damage by high or low temperature, humidity and pressure 2.9 39 022 (SF5 CCS) Containment Cooling 5
Containment cooling after LOCA destroys ventilation ducts 2.6 40 026 (SF5 CSS) Containment Spray 4
Failure of spray pump 3.9 41 039 (SF4S MSS) Main and Reheat Steam 4
Malfunctioning steam dump 3.4 42 039 (SF4S MSS) Main and Reheat Steam 2.1.32 Ability to explain and apply all system limits and precautions.
3.8 43 059 (SF4S MFW) Main Feedwater 3
Power level restrictions for operation of MFW pumps and valves.
2.7 44 061 (SF4S AFW)
Auxiliary/Emergency Feedwater 3
Interactions when multi-unit systems are cross tied 3.1 45 061 (SF4S AFW)
Auxiliary/Emergency Feedwater 2
AFW electric drive pumps 3.7 46 062 (SF6 ED AC) AC Electrical Distribution 4
Operation of inverter (e.g. precharging synchronizing light,static transfer) 2.7 47 063 (SF6 ED DC) DC Electrical Distribution 1
Meters, annunciators, dials, recorders and indicating lights 2.7 48 064 (SF6 EDG) Emergency Diesel Generator 1
Local and remote operation of the ED/G 4.0 49 064 (SF6 EDG) Emergency Diesel Generator 8
Fuel oil storage tanks 3.2 50
ES-401 6
Form ES-401-2 073 (SF7 PRM) Process Radiation Monitoring 1
Radiation levels 3.2 51 076 (SF4S SW) Service Water 17 PRMS 3.6 52 078 (SF8 IAS) Instrument Air 1
Instrument air compressor 2.7 53 103 (SF5 CNT) Containment 4
Phase A and phase B resets 3.5 54 103 (SF5 CNT) Containment 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
4.3 55 004 (SF1; SF2 CVCS) Chemical and Volume Control 13 Low RWST 3.9 86 008 (SF8 CCW) Component Cooling Water 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications 4.6 87 010 (SF3 PZR PCS) Pressurizer Pressure Control 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.
4.2 88 013 (SF2 ESFAS) Engineered Safety Features Actuation 4
Loss of instrument bus 4.2 89 012 (SF7 RPS) Reactor Protection 3
Incorrect channel bypassing 3.7 90 K/A Category Point Totals:
3 2
3 2
2 2
3 3/3 2 3
3/2 Group Point Total:
28/5
ES-401 7
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 011 (SF2 PZR LCS) Pressurizer Level Control 4
Operation of PZR level controllers 3.1 56 014 (SF1 RPI) Rod Position Indication 1
Rod selection control 3.3 57 016 (SF7 NNI) Nonnuclear Instrumentation 1
Separation of control and protection circuits 2.7 58 029 (SF8 CPS) Containment Purge 2
Containment entry 2.9 59 033 (SF8 SFPCS) Spent Fuel Pool Cooling 2
RHRS 2.5 60 035 (SF 4P SG) Steam Generator 1
S/ G water level control 4.0 61 045 (SF 4S MTG) Main Turbine Generator 5
Expected response of primary plant parameters (temperature and pressure) following T/G trip 3.8 62 068 (SF9 LRS) Liquid Radwaste 4
Failure of automatic isolation 3.3 63 017 (SF7 ITM) In-Core Temperature Monitor 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions 4.0 64 086 Fire Protection 2
Maintenance of fire header pressure 3.0 65 016 (SF7 NNI) Nonnuclear Instrumentation 2
Loss of power supply 3.2 91 045 (SF 4S MTG) Main Turbine Generator 2.1.20 Ability to execute procedure steps.
4.6 92 075 (SF8 CW) Circulating Water 2
Loss of circulating water pumps 2.7 93 K/A Category Point Totals:
1 0
1 1
1 1
1 1/2 1 1
1/1 Group Point Total:
10/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Calvert Cliffs Date of Exam: January 2020 Category K/A #
Topic RO SRO-only IR IR
- 1. Conduct of Operations 2.1.42 Knowledge of new and spent fuel movement procedures 2.5 66 2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication 4.3 67 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
3.9 68 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
3.6 94 Subtotal 3
1
- 2. Equipment Control 2.2.13 Knowledge of tagging and clearance procedures.
4.1 69 2.2.4 (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
3.6 70 2.2.11 Knowledge of the process for controlling temporary design changes.
3.3 95 2.2.3 (multi-unit license) Knowledge of the design, procedural and operational differences between units.
3.9 96 Subtotal 2
2
- 3. Radiation Control 2.3.11 Ability to control radiation releases.
3.8 71 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 3.4 72 2.3.5 Ability to use radiation monitoring systems 2.9 73 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.7 97 2.3.6 Ability to aprove release permits 3.8 98 Subtotal 3
2
- 4. Emergency Procedures/Plan 2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
3.1 74 2.4.27 Knowledge of "fire in the plant" procedures.
3.4 75 2.4.14 Knowledge of general guidelines for EOP usage.
4.5 99 2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
4.5 100 Subtotal 2
2 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 Rejected Emergency and Abnormal Plant Evolutions associated with Babcock and Wilcox (BW) reactors - Calvert Cliffs is a CE design.
Rejected 025 (SF5 ICE) Ice Condenser - Calvert Cliffs does not have an ice condenser installed.
Rejected 033 Loss of Intermediate Range Nuclear Instrumentation. Calvert Cliffs does not have Intermediate Range NIs 1/1 RO Question #17: Added Loss of Salt Water to the Tier 1, Group 1 list of E/APEs to be available for random selection in accordance with ES-401 Attachment 1. Loss of Salt Water was randomly selected for Question 17.
1/1 000065 (APE 65)
Loss of Instrument Air A2.02 SRO Question
- 81 Cannot write an operationally valid question regarding flow readings in the instrument air system Randomly reselected 065 Loss of Instrument Air, A2.05 2/2 011 (SF2 PZR LCS) Pressurizer Level Control K6.06 RO Question #56 Cannot write an operationally valid question regarding demand signal indication on charging pump flow valve controller to the valve position.
Randomly reselected 011 Pressurizer Level Control, K6.04 2/2 068 (SF9 LRS)
Liquid Radwaste A2.03 RO Question #63 Cannot write an operationally valid question regarding insufficient sampling frequency of the boric acid in the evaporator bottoms.
Randomly reselected 068 Liquid Radwaste, A2.04
ES-401 Record of Rejected K/As Form ES-401-4
Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Examiners:
Operators:
Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.
Instructions to the crew: Maintain 100% power.
Critical Tasks
- 1. Trip the reactor within 1 minute of the PROT CH TRIP alarm.
- 2. Commences an RCS Cooldown not to exceed 100°F in any one hour.
- 3. Commences OTCC when both S/G levels are below (-)350 inches and prior to CET temperatures reaching 560°F after Heat Removal capability has been lost.
Event #
Malfunction #
Event Type*
Event Description 1
ceds012_01 C-ALL T-SRO Dropped CEA / AOP-1B 2
hdv001_02 C-BOP/SRO 12 Heater Drain Tank Pump trips / AOP-3G 3
srw003_02 C-BOP/SRO T-SRO 12 SRW Pump Trip / AOP-7B 4
480v003_04 Downpower C-BOP/SRO R-ATC Loss of MCC-116 / AOP-7I 5
rps005 rcs006_02 C-ATC/SRO 11B RCP Trip / ATWS / EOP-0 6
rcs002 C-ALL LOCA 7
swyd002 C-ALL Loss of Offsite Power 8
afw001_01 M-ALL 11 AFW Pump Trip (Loss of All Feed) / EOP-8 (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec
Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Examiners:
Operators:
Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.
Instructions to the crew: None.
Critical Tasks
- 2. Trips all RCPs within 15 minutes after receiving CIS actuation.
- 3. Identifies 12 Steam Generator as faulted and isolates 12 S/G.
- 4. Establishes at least one train of Containment Spray flow to Containment.
Event #
Malfunction #
Event Type*
Event Description 1
rcs004_03 I-BOP/SRO T-SRO 11A Loop TCOLD 1-TT-112CC Fails High 2
480v001_08 C-ALL T-SRO Loss of 14B 480V Bus / AOP-7I 3
Rapid Downpower N-BOP/SRO R-ATC Call from TSO to reduce load to <825 MWE in
<15 minutes 4
ccw002_01 C-BOP/SRO T-SRO 11 CCW Pump Breaker Failure / AOP-7C 5
4kv001_02 C-ATC/SRO 12 4KV Bus / AOP-7I EOP-0 6
tg005_01 esfa012 C-BOP/SRO MTSV-1/MTCV-1 fail as-is / SGIS Failure 7
ms010_02 M-ALL Steam Line Rupture in Containment / EOP-4 8
esfa004_01/02 esfa005_01/02 I-ATC/SRO CSAS Auto and Manual Failure (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec
Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Examiners:
Operators:
Initial Conditions: Unit-1 is at 3% power, MOC. Unit-2 is at 100% power.
Turnover: 13 CBP is OOS. 11 HPSI Pump is OOS.
Instructions to the crew: Raise reactor power and stabilize at 8% per OP-2.
Critical Tasks
- 1. Commences an RCS Cooldown not to exceed 100°F in any one hour.
- 2. Trip 11A & 12B RCPs or 11B & 12A RCPs when RCS pressure decreases to <1725 PSIA prior to RCS subcooling being less than 20°F for 4 minutes.
- 3. Establishes at least one train of HPSI pump flow to the RCS within 15 minutes of the loss of HPSI flow.
Event #
Malfunction #
Event Type*
Event Description 1
N/A N-SRO R-ATC Raise Reactor Power 2
ni002_03 I-BOP/SRO T-SRO NI-RPS Ch C Wide Range NI High Volt Power Supply fails 3
cvcs006 C-ATC/SRO CVC-516 Fails Shut 4
cw001_01 C-BOP/SRO 11 CWP Breaker Failure/AOP-7L 5
rcs003 C-ALL T-SRO RCS Leak Unisolated/AOP-2A EOP-0 6
rcs002 M-ALL LOCA (600 gpm)/EOP-5 7
si002_03 C-ATC/SRO 13 HPSI Pump trips (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec
Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Examiners:
Operators:
Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.
Turnover: 12 Boric Acid Pump is OOS, 0C DG is OOS.
Instructions to the crew: The Shift Manager has directed the crew to shift disconnects for 13 IRU to the 14B 480V Bus per OI-5B Section 6.2.
Critical Tasks
- 1. Establishes AFW flow to at least one S/G prior to S/G levels going below (-)350 inches.
- 2. Shuts MSIVs to stop cooldown prior to 432°F TCOLD.
Event #
Malfunction #
Event Type*
Event Description 1
N/A N-BOP/SRO T-SRO 13 IRU Shift Disconnects 2
rcs027_02 C-ATC/SRO T-SRO PORV-404 Leakage 3
480v001_04 C-BOP/SRO Loss of 12B 480V Bus/AOP-7I 4
tg017 Downpower C-BOP/SRO R-ATC High Turbine Vibrations/AOP-7E 5
cvcs014_01 C-ATC/SRO 11 Boric Acid Pump Trips 6
swyd002 M-ALL EOP-0 Loss of Offsite Power/EOP-2 7
dg001_02 C-ALL 1B EDG Trips 8
dg002_02 M-ALL Station Blackout/EOP-7 (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec