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 Date of Examination: 1/27/2020 Exam Level: RO Operating Test #: 2020 Administrative Topic Type Describe activity to be performed (see Note) Code*
Estimate Time to Boil Conduct of Operations R, D G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (RO-3.9)
Determine Shutdown Margin Conduct of Operations R, D G2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (RO-4.3)
Print Reading Equipment Control R, N 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 Date of Examination: 1/27/2020 Exam Level: RO Operating Test #: 2020 Control Room Systems:
Function
- a. SIM-1 Respond to a CEDS failure 001 Control Rod Drive System A, N 1 A4.03 CRDS mode control (RO-4.0)
- b. SIM-2 Verify Validity of CIS Actuation 013 Engineered Safety Features Actuation System D, EN 2 A3.01 Input channels and logic (RO-3.7)
- c. SIM-3 Verify HPSI/LPSI Flow 006 Emergency Core Cooling System A, EN, N, L 3 A4.07 ECCS pumps and valves (RO-4.4)
- d. SIM-4 Attempt to Correct the Abnormal SDC Condition 005 Residual Heat Removal System A, D, L 4P A4.01 Controls and indications for RHR pumps (RO-3.6)
- e. SIM-5 Align Saltwater Emergency Overboard 076 Service Water System N 4S A4.04 Emergency heat loads (RO-3.5)
- f. SIM-6 Pressurizer Vent Valve Testing 007 Pressurizer Relief Tank/Quench Tank System N, L 5 A4.04 PZR Vent Valve (RO-2.6)
- g. SIM-7 Rapid Shutdown of the Diesel 064 Emergency Diesel Generator System N 6 A4.06 Manual Start, loading, and stopping of the EDG (RO-3.9)
- h. SIM-8 Respond to RCS leakage into Component Cooling System 008 Component Cooling Water System A, N 8 A4.01 CCW indications and controls (RO-3.3)
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 D, E 4S 2.1.30 Ability to locate and operate components (RO-4.4)
- j. PLT-2 Operate MCC Load Breakers 068 Control Room Evacuation N, E, R 6 AA1.10 Power Distribution: ac and dc (RO-3.7)
- k. PLT-3 Respond to a Loss of Instrument Air 065 Loss of Instrument Air D, E 8 AA1.04 Emergency air compressor (RO-3.5)
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 4-6 / 4-6 / 2-3 [4]
(C)ontrol room (D)irect from bank 9 / 8 / 4 [4]
(E)mergency or abnormal in-plant 1 / 1 / 1 [3]
(EN)gineered safety feature 1 / 1 / 1 (control room system) [2]
(L)ow-Power / Shutdown 1 / 1 / 1 [3]
(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 [7 including 3(A)]
(P)revious 2 exams 3 / 3 / 2 (randomly selected) [0]
(R)CA 1 / 1 / 1 [1]
(S)imulator
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 1/27/2020 Exam Level: SRO-I Operating Test #: 2020 Administrative Topic Type Describe activity to be performed (see Note) Code*
Evaluate Overtime Work Request Conduct of Operations R, N G2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (SRO-3.9)
Supervisory Review of Shutdown Margin Conduct of Operations R, D G2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (SRO-4.6)
Print Reading and Application of Tech Specs Equipment Control R, N G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (SRO-3.9)
Administrative Requirements for RMS Inoperability Radiation Control R, N 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)
Perform Shift Emergency Director Functions Emergency Plan R, D 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 Date of Examination: 1/27/2020 Exam Level: SRO-I Operating Test #: 2020 Control Room Systems:
Function
- a. SIM-1 Shutdown CEA Free Movement Test 001 Control Rod Drive System A, N 1 A4.03 CRDS mode control (SRO-3.7)
- b. SIM-2 Verify Validity of CIS Actuation 013 Engineered Safety Features Actuation System D, EN 2 A3.01 Input channels and logic (SRO-3.9)
- c. SIM-3 Verify HPSI/LPSI Flow 006 Emergency Core Cooling System A, EN, N, L 3 A4.07 ECCS pumps and valves (SRO-4.4)
- d. SIM-4 Attempt to Correct the Abnormal SDC Condition 005 Residual Heat Removal System A, D, L 4P A4.01 Controls and indications for RHR pumps (SRO-3.4)
- e. SIM-5 Align Saltwater Emergency Overboard 076 Service Water System N 4S A4.04 Emergency heat loads (SRO-3.5)
- f. SIM-7 Rapid Shutdown of the Diesel 064 Emergency Diesel Generator System N 6 A4.06 Manual Start, loading, and stopping of the EDG (SRO-3.9)
- g. SIM-8 Respond to RCS leakage into Component Cooling System 008 Component Cooling Water System A, N 8 A4.01 CCW indications and controls (SRO-3.1)
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 D, E 4S 2.1.30 Ability to locate and operate components (SRO-4.4)
- i. PLT-2 Operate MCC Load Breakers 068 Control Room Evacuation N, E, R 6 AA1.10 Power Distribution: ac and dc (SRO-3.9)
- j. PLT-3 Respond to a Loss of Instrument Air 065 Loss of Instrument Air D, E 8 AA1.04 Emergency air compressor (SRO-3.4)
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 4-6 / 4-6 / 2-3 [4]
(C)ontrol room (D)irect from bank 9 / 8 / 4 [4]
(E)mergency or abnormal in-plant 1 / 1 / 1 [3]
(EN)gineered safety feature 1 / 1 / 1 (control room system) [2]
(L)ow-Power / Shutdown 1 / 1 / 1 [2]
(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 [6 including 3(A)]
(P)revious 2 exams 3 / 3 / 2 (randomly selected) [0]
(R)CA 1 / 1 / 1 [1]
(S)imulator
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 1/27/2020 Exam Level: SRO-U Operating Test #: 2020 Administrative Topic Type Describe activity to be performed (see Note) Code*
Evaluate Overtime Work Request Conduct of Operations R, N G2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (SRO-3.9)
Supervisory Review of Shutdown Margin Conduct of Operations R, D G2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (SRO-4.6)
Print Reading and Application of Tech Specs Equipment Control R, N G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (SRO-3.9)
Administrative Requirements for RMS Inoperability Radiation Control R, N 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)
Perform Shift Emergency Director Functions Emergency Plan R, D 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 Date of Examination: 1/27/2020 Exam Level: SRO-U Operating Test #: 2020 Control Room Systems:
Function
- a. SIM-2 Verify Validity of CIS Actuation 013 Engineered Safety Features Actuation System D, EN 2 A3.01 Input channels and logic (SRO-3.9)
- b. SIM-3 Verify HPSI/LPSI Flow 006 Emergency Core Cooling System A, EN, N, L 3 A4.07 ECCS pumps and valves (SRO-4.4)
- c. SIM-8 Respond to RCS leakage into Component Cooling System 008 Component Cooling Water System A, N 8 A4.01 CCW indications and controls (SRO-3.1)
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 D, E 4S 2.1.30 Ability to locate and operate components (SRO-4.4)
- e. PLT-2 Operate MCC Load Breakers 068 Control Room Evacuation N, E, R 6 AA1.10 Power Distribution: ac and dc (SRO-3.9)
- 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 4-6 / 4-6 / 2-3 [2]
(C)ontrol room (D)irect from bank 9 / 8 / 4 [2]
(E)mergency or abnormal in-plant 1 / 1 / 1 [2]
(EN)gineered safety feature 1 / 1 / 1 (control room system) [2]
(L)ow-Power / Shutdown 1 / 1 / 1 [1]
(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 [3 including 2(A)]
(P)revious 2 exams 3 / 3 / 2 (randomly selected) [0]
(R)CA 1 / 1 / 1 [1]
(S)imulator
ES-401 PWR Examination Outline Form ES-401-2 Facility: Calvert Cliffs Date of Exam: January 2020 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total
- 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency and Abnormal Plant 2 2 2 2 N/A 1 1 N/A 1 9 2 2 4 Evolutions Tier Totals 5 5 5 4 4 4 27 5 5 10 1 3 2 3 2 2 2 3 3 2 3 3 28 3 2 5 2.
Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 0 2 1 3 Systems Tier Totals 4 2 4 3 3 3 4 4 3 4 4 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 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 #
Relationship of emergency feedwater flow to S/G 000007 (EPE 7; BW E02&E10; CE E02) 6 and decay heat removal following reactor trip 3.7 1 Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space 6 Control of PZR level 3.6 2 Accident / 3 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 1 Natural circulation in a nuclear reactor power 4.4 5 Malfunctions / 4 plant Relationship of charging flow to pressure 000022 (APE 22) Loss of Reactor Coolant 2 differential between charging and RCS 2.7 6 Makeup / 2 000025 (APE 25) Loss of Residual Heat 4 Location and isolability of leaks 3.3 7 Removal System / 4 000026 (APE 26) Loss of Component 1 Location of a leak in the CCWS 2.9 8 Cooling Water / 8 000027 (APE 27) Pressurizer Pressure 2 SCR-controlled heaters in manual mode 3.1 9 Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient 2.4.6 Knowledge symptom based EOP mitigation 3.7 10 Without Scram / 1 strategies.
Actions contained in EOP for RCS water 000038 (EPE 38) Steam Generator Tube 6 inventory balance, S/G tube rupture, and plant 4.2 11 Rupture / 3 shutdown procedures 000040 (APE 40; BW E05; CE E05; W E12) 2 Sensors and detectors 2.6 12 Steam Line RuptureExcessive Heat Transfer / 4 000055 (EPE 55) Station Blackout / 6 2 RCS core cooling through natural circulation 4.4 13 cooling to S/G cooling Knowledge of annunciators alarms, indications or 000056 (APE 56) Loss of Offsite Power / 6 2.4.31 response procedures 4.2 14 Feedwater pump speed to control pressure and 000057 (APE 57) Loss of Vital AC 3 level in S/G 3.6 15 Instrument Bus / 6 Ability to identify post-accident instrumentation.
000058 (APE 58) Loss of DC Power / 6 2.4.3 3.7 16 Loss of Salt Water 2 The automatic actions (alignments) within the 3.6 17 salt water system resulting from the actuation of the ESFAS.
Facility s heat removal systems, including 000054 (CE E06) Loss of Main Feedwater 2 primary coolant, emergency coolant, the decay 3.5 18
/4 heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Ability to verify that the alarms are consistent 000007 (EPE 7; BW E02&E10; CE E02) 2.4.46 with the plant conditions. 4.2 76 Reactor Trip, Stabilization, Recovery / 1 Whether charging line leak exists 000022 (APE 22) Loss of Reactor Coolant 1 3.8 77 Makeup / 2 Knowledge of limiting conditions for operations 000027 (APE 27) Pressurizer Pressure 2.2.22 and safety limits. 4.7 78 Control System Malfunction / 3 125V dc bus voltage, low/critical low, alarm 000058 (APE 58) Loss of DC Power / 6 2 3.6 79
ES-401 3 Form ES-401-2 Ability to locate and operate components, 000062 (APE 62) Loss of Nuclear Service 2.1.30 including local controls. 4.0 80 Water / 4 When to commence plant shutdown if instrument 000065 (APE 65) Loss of Instrument Air / 8 5 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 1 Power supplies, including 2.7 21 Instrumentation / 7 proper switch positions 000051 (APE 51) Loss of Condenser Vacuum / 4 2.2.44 Ability to interpret control room 4.2 22 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 000061 (APE 61) Area Radiation Monitoring System Alarms 1 Automatic actuation 3.6 23
/7 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / 7 The difference between a 4.1 24 4 LOCA and inadequate core cooling from trends and indicators (CE A11**; W E08) RCS OvercoolingPressurized Thermal 1 Components, and functions of 3.2 25 Shock / 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 1 Facility operating 3.4 26 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.
(CE E09) Functional Recovery 3 Manipulation of controls 3.7 27 required to obtain desired operating results during abnormal, and emergency situations.
000005 (APE 5) Inoperable/Stuck Control Rod / 1 2.2.40 Ability to apply Technical 4.7 82 Specifications for a system.
000028 (APE 28) Pressurizer (PZR) Level Control 14 The effect on indicated PZR 2.8 83 Malfunction / 2 levels, given a change in ambient pressure and temperature of reflux boiling 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 2.4.34 Knowledge of RO tasks 4.1 84 performed outside the main control room during an emergency and the resultant operational effects.
(CE A16) Excess RCS Leakage / 2 1 Facility conditions and 3.5 85 selection of appropriate procedures during abnormal and emergency operations.
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 3 RCP seal system 3.3 28 Pump Effects of RCP shutdown on secondary 003 (SF4P RCP) Reactor Coolant 4 parameters, such as steam pressure, 3.2 29 Pump steam flow and feed flow 004 (SF1; SF2 CVCS) Chemical and 1 Importance of oxygen control in RCS 2.7 30 Volume Control 005 (SF4P RHR) Residual Heat 3 RHR heat exchanger 2.5 31 Removal 006 (SF2; SF3 ECCS) Emergency 6 Water hammer 3.3 32 Core Cooling 007 (SF5 PRTS) Pressurizer 3 RCS 3.0 33 Relief/Quench Tank 007 (SF5 PRTS) Pressurizer 1 Containment 3.3 34 Relief/Quench Tank 008 (SF8 CCW) Component Cooling 1 Loads cooled by CCWS 3.4 35 Water 010 (SF3 PZR PCS) Pressurizer 3 Over pressure control 3.8 36 Pressure Control 012 (SF7 RPS) Reactor Protection 7 M/G set breakers 3.9 37 Knowledge of operational implications of 013 (SF2 ESFAS) Engineered 2.4.20 EOP warnings, cautions and notes. 3.8 38 Safety Features Actuation Containment equipment subject to 022 (SF5 CCS) Containment Cooling 1 damage by high or low temperature, 2.9 39 humidity and pressure 022 (SF5 CCS) Containment Cooling 5 Containment cooling after LOCA destroys 2.6 40 ventilation ducts 026 (SF5 CSS) Containment Spray 4 Failure of spray pump 3.9 41 039 (SF4S MSS) Main and Reheat 4 Malfunctioning steam dump 3.4 42 Steam Ability to explain and apply all system 039 (SF4S MSS) Main and Reheat 2.1.32 limits and precautions. 3.8 43 Steam Power level restrictions for operation of 059 (SF4S MFW) Main Feedwater 3 MFW pumps and valves. 2.7 44 061 (SF4S AFW) 3 Interactions when multi-unit systems are 3.1 45 Auxiliary/Emergency Feedwater cross tied 061 (SF4S AFW) 2 AFW electric drive pumps 3.7 46 Auxiliary/Emergency Feedwater Operation of inverter (e.g. precharging 062 (SF6 ED AC) AC Electrical 4 synchronizing light,static transfer) 2.7 47 Distribution 063 (SF6 ED DC) DC Electrical 1 Meters, annunciators, dials, recorders 2.7 48 Distribution and indicating lights 064 (SF6 EDG) Emergency Diesel 1 Local and remote operation of the ED/G 4.0 49 Generator 064 (SF6 EDG) Emergency Diesel 8 Fuel oil storage tanks 3.2 50 Generator
ES-401 6 Form ES-401-2 073 (SF7 PRM) Process Radiation 1 Radiation levels 3.2 51 Monitoring 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 Ability to perform specific system and 103 (SF5 CNT) Containment 2.1.23 integrated plant procedures during all 4.3 55 modes of plant operation.
004 (SF1; SF2 CVCS) Chemical and 13 Low RWST 3.9 86 Volume Control Ability to recognize system parameters 008 (SF8 CCW) Component Cooling 2.2.42 that are entry-level conditions for 4.6 87 Water Technical Specifications 010 (SF3 PZR PCS) Pressurizer 2.4.46 Ability to verify that the alarms are 4.2 88 Pressure Control consistent with the plant conditions.
013 (SF2 ESFAS) Engineered 4 Loss of instrument bus 4.2 89 Safety Features Actuation 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 4 Operation of PZR level controllers 3.1 56 Level Control 014 (SF1 RPI) Rod Position 1 Rod selection control 3.3 57 Indication 016 (SF7 NNI) Nonnuclear 1 Separation of control and protection 2.7 58 Instrumentation circuits 029 (SF8 CPS) Containment Purge 2 Containment entry 2.9 59 033 (SF8 SFPCS) Spent Fuel Pool 2 RHRS 2.5 60 Cooling 035 (SF 4P SG) Steam Generator 1 S/ G water level control 4.0 61 045 (SF 4S MTG) Main Turbine 5 Expected response of primary plant 3.8 62 Generator parameters (temperature and pressure) following T/G trip 068 (SF9 LRS) Liquid Radwaste 4 Failure of automatic isolation 3.3 63 017 (SF7 ITM) In-Core Temperature 2.4.21 Knowledge of the parameters and logic 4.0 64 Monitor used to assess the status of safety functions 086 Fire Protection 2 Maintenance of fire header pressure 3.0 65 016 (SF7 NNI) Nonnuclear 2 Loss of power supply 3.2 91 Instrumentation 045 (SF 4S MTG) Main Turbine 2.1.20 Ability to execute procedure steps. 4.6 92 Generator 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 #
2.1.42 Knowledge of new and spent fuel movement procedures 2.5 66 Ability to identify and interpret diverse indications to validate 2.1.45 the response of another indication 4.3 67 2.1.44 Knowledge of RO duties in the control room during fuel 3.9 68 handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems
- 1. Conduct of operated from the control room in support of fueling operations, Operations and supporting instrumentation.
Knowledge of industrial safety procedures (such as 2.1.26 rotating equipment, electrical, high temperature, high pressure, 3.6 94 caustic, chlorine, oxygen and hydrogen).
Subtotal 3 1 2.2.13 Knowledge of tagging and clearance procedures. 4.1 69 (multi-unit) Ability to explain the variations in control board 2.2.4 layouts, systems, instrumentation and procedural actions 3.6 70 between units at a facility.
- 2. Equipment Control Knowledge of the process for controlling temporary design 2.2.11 changes. 3.3 95 (multi-unit license) Knowledge of the design, procedural and 2.2.3 operational differences between units. 3.9 96 Subtotal 2 2 2.3.11 Ability to control radiation releases. 3.8 71 Knowledge of radiation or contamination hazards that 2.3.14 may arise during normal, abnormal, or emergency conditions or 3.4 72 activities 2.3.5 Ability to use radiation monitoring systems 2.9 73
- 3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or 3.7 97 emergency conditions.
2.3.6 Ability to aprove release permits 3.8 98 Subtotal 3 2 Knowledge of facility protection requirements including fire 2.4.26 brigade and portable fire fighting equipment usage. 3.1 74 2.4.27 Knowledge of "fire in the plant" procedures. 3.4 75
- 4. Emergency Procedures/Plan 2.4.14 Knowledge of general guidelines for EOP usage. 4.5 99 Knowledge of how abnormal operating procedures are used in 2.4.8 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 / Randomly Reason for Rejection Group Selected K/A 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) Cannot write an operationally valid question regarding flow Loss of readings in the instrument air system Instrument Air A2.02 Randomly reselected 065 Loss of Instrument Air, A2.05 SRO Question
- 81 2/2 011 (SF2 PZR Cannot write an operationally valid question regarding LCS) Pressurizer demand signal indication on charging pump flow valve Level Control controller to the valve position.
K6.06 Randomly reselected 011 Pressurizer Level Control, K6.04 RO Question #56 2/2 068 (SF9 LRS) Cannot write an operationally valid question regarding Liquid Radwaste insufficient sampling frequency of the boric acid in the evaporator bottoms.
A2.03 Randomly reselected 068 Liquid Radwaste, A2.04 RO Question #63
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 C-ALL 1 ceds012_01 Dropped CEA / AOP-1B T-SRO 2 hdv001_02 C-BOP/SRO 12 Heater Drain Tank Pump trips / AOP-3G C-BOP/SRO 3 srw003_02 12 SRW Pump Trip / AOP-7B T-SRO 480v003_04 C-BOP/SRO 4 Loss of MCC-116 / AOP-7I Downpower R-ATC rps005 5 C-ATC/SRO 11B RCP Trip / ATWS / EOP-0 rcs006_02 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 I-BOP/SRO 1 rcs004_03 11A Loop TCOLD 1-TT-112CC Fails High T-SRO C-ALL 2 480v001_08 Loss of 14B 480V Bus / AOP-7I T-SRO Rapid N-BOP/SRO Call from TSO to reduce load to <825 MWE in 3
Downpower R-ATC <15 minutes C-BOP/SRO 4 ccw002_01 11 CCW Pump Breaker Failure / AOP-7C T-SRO 12 4KV Bus / AOP-7I 5 4kv001_02 C-ATC/SRO EOP-0 tg005_01 6 C-BOP/SRO MTSV-1/MTCV-1 fail as-is / SGIS Failure esfa012 7 ms010_02 M-ALL Steam Line Rupture in Containment / EOP-4 esfa004_01/02 8 I-ATC/SRO CSAS Auto and Manual Failure esfa005_01/02
- (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 N-SRO 1 N/A Raise Reactor Power R-ATC I-BOP/SRO NI-RPS Ch C Wide Range NI High Volt Power 2 ni002_03 T-SRO Supply fails 3 cvcs006 C-ATC/SRO CVC-516 Fails Shut 4 cw001_01 C-BOP/SRO 11 CWP Breaker Failure/AOP-7L C-ALL RCS Leak Unisolated/AOP-2A 5 rcs003 T-SRO 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 N-BOP/SRO 1 N/A 13 IRU Shift Disconnects T-SRO C-ATC/SRO 2 rcs027_02 PORV-404 Leakage T-SRO 3 480v001_04 C-BOP/SRO Loss of 12B 480V Bus/AOP-7I tg017 C-BOP/SRO 4 High Turbine Vibrations/AOP-7E Downpower R-ATC 5 cvcs014_01 C-ATC/SRO 11 Boric Acid Pump Trips EOP-0 6 swyd002 M-ALL 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