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| number = ML090290246
| number = ML090290246
| issue date = 10/30/2008
| issue date = 10/30/2008
| title = Calvert Cliffs -Final Outlines (Folder 3)
| title = Final Outlines (Folder 3)
| author name =  
| author name =  
| author affiliation = Calvert Cliffs Nuclear Power Plant, Inc
| author affiliation = Calvert Cliffs Nuclear Power Plant, Inc
Line 14: Line 14:
| document type = License-Operator, Part 55 Examination Related Material
| document type = License-Operator, Part 55 Examination Related Material
| page count = 20
| page count = 20
| project = TAC:U01779
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:ES-401 PWR Examination Outline Form; s-4016 dl Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRC'r- only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall n:)t be less than two). 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 fl 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not include4 on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements. 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. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.
{{#Wiki_filter:ES-401                                       PWR Examination Outline                                               Form;     s-4016   dl Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO           and SRCr-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall n:)t be less than two).
the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 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 f l 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevar to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals  
: 3. Systemslevolutionswithin each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specificsystems/evolutionsthat are not include4 on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
(#)for each system and category.
: 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.
Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in 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. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
: 5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.     Usr the RO and SRO ratings for the RO and SRO-only portions, respectively.
Limit SRO selections to WAS that are linked to 10 CFR 55.43. Usr PWR Examination Outline Form ES-401-2 ES-401 Emergency and - - # IR - 3.5 3.1 - - 4.4 4.2 2.9 32 39 34 45 31 "_ 41 32 43 35 35 31 29 3.9 11 ElAPE # / Name I Safety Function I! AG KIA Topic(s) 2 EE(2.03 - Reactor trip status panel 000007 (CE/E02) Reactor Trip - A Stabilization - Recovery I 1 000008 Pressurizer Vapor Space Accident I3 I 000009 Small Break LOCA I3 AK1.02 - Change in leak rate with change in pressure EK3.26 - Maintenance of RCS subcooling 2.2.44 - Ability to interpret control room indications to verify the status and operation X ? - of' a system, and understand how operator actions and directives affect plant and system conditions.
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
AK2.07 - RCP seals AA1.03 - PZR level trend AK1.01 - Loss of RHRS during all modes of operation 2.2.40 - Ability to apply technical Specifications for a system.
7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevar to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS.
EA1.08 - Reactor trip switch pushbutton 1 EK1.01 - Use of steam tables 00001 1 Large Break LOCA I3 11 000015/17 RCP Malfunctions I 4 I 11 000022 Loss of Rx Coolant Makeup I2 I 000025 Loss of RHR System / 4 I 000026 Loss of Component Cooling Water I8 I 11 000029 ANVS I 1 I 11 000038 Steam Gen. Tube Rupture I3 I : CK- 2.4.45 - Ability to prioritize and interpret the obtain desired operating results during abnormal and emergency situations.
: 8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (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 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.
000040 (CEIEOS) Steam Line Rupture - Excessive Heat Transfer 1 4 000054 (CEIEO6) Loss of Main Feedwater I 4 000055 Station Blackout I6 EK3.02 - Actions contained in EOP for loss of offsite and onsite power AA2.73 - PZR heater odoff Y AA1.06 - Manual control of components for which automatic control is lost AA2.01 - That a loss of dc power has occurred; verification that substitute power sources have come on line 000057 Loss of Vital AC Inst. Bus 16 - X 000058 Loss of DC Power I6 000065 Loss of Instrument Air I8 AA2.01 - Cause and effect of low-pressure instrument air alarm  
: 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
~_______ ~ 000077 Generator Voltage and Electric Grid Disturbances I6 AK2.06 - Reactor power 11 KIA Category Totals: I 3 I 3 I 3 I 3 I 3 I Group Point Total:
 
11 ES-401 PWR Examination Outline Form ES-401.gI - I-401 PWR Examination Outline Form ES-401-2 000074 (W/E06&E07)
PWR Examination Outline ES-401                                                                                                                Form ES-401-2 Emergency and                                                                                       -
Inad. Core Cooling I4 CE/A13 - Natural Circ.
1 ElAPE # / Name I Safety Function          I!              A 2
I4 instrumentation, signals, interlocks, odes, and automatic and manual - IR 2.9 3.4 3.9 - - - 3.7 2.8 - 4.0 - 3.0 3.0 - 4.2 Form ES-401 ES-401 PWR Examination Outline amination Outline Form ES-401-2 11 ES-401 PWR 1 ~p 1- Reactor Operator K/A Topic(s) K6.14 - Starting Requirements  
G                        KIA Topic(s)                     IR      #
# 11 System # I Name 003 Reactor Coolant Pump v 2.6 2.1.3 1 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. 4.6 003 Reactor Coolant Pump H X K5.14 - Reduction process of gas concentration in RCS: vent- accumulated non-condensable gases from PZR bubble space, depressurized during cooldown or by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)
A  000007 (CE/E02)Reactor Trip -
K5.02 - Need for adequate subcooling 004 Chemical and Volume Control 2.5 - 3.4 005 Residual Heat Removal 006 Emergency Core Cooling 006 Emergency Core Cooling 007 Pressurizer ReliefIQuench Tank 008 Component Cooling Water I I A3.04 - Cooling water systems 3.8 2.5 K2.02 - Valve operators for accumulators I I K3.01- Containment 3.3 3.0 K2.02 - CCW pump, including emergency backup 008 Component Cooling Water 010 Pressurizer Pressure I-- Control 2.4.1 - Knowledge of EOP entry condition and immediate action steps. 4.6 X 3.1 Al.06 - RCS heatup and cooldown effect on pressure I I K6.10 - Permissive circuits 3.3 012 Reactor Protection 013 Engineered Safety Features Actuation 3.7 K1.18 - Premature reset of ESF actuation 2.8 K4.04 - Cooling of control rod drive motors 022 Containment Cooling K3 .O 1 - Containment equipment subject to damage by high or low temperature, humidity, and pressure 2.9 022 Containment Cooling 4.2 - 3.6 - - 026 Containment Spray 2.2.37 - Ability to determine safety related equipment.
Stabilization - Recovery I 1 EE(2.03 - Reactor trip status panel                3.5 I 000008 Pressurizer Vapor Space                                     AK1.02 - Change in leak rate with change in Accident I 3                                  ?                    pressure                                           3.1 000009 Small Break LOCA I 3                                        EK3.26 - Maintenance of RCS subcooling X                                                                    4.4        -
026 Containment Spray PWR Examination Outline Form ES-401-2 11 II 11 11 ES-401 PWR Examination Outline Form ES-401 Form ES-401- d1 - ES-401 PWR Examination Outline ES-401 PWR Examination Outline Form ES-401 - 000015/17 RCP Malfunctions  
2.2.44 - Ability to interpret control room indications to verify the status and operation 00001 1 Large Break LOCA I 3                                        ofa system, and understand how operator           4.2 actions and directives affect plant and system conditions.
/ 4 I - -
1 000015/17 RCP Malfunctions I 4            I                        AK2.07 - RCP seals                                 2.9 1 000022 Loss of Rx Coolant Makeup I 2 I                              AA1.03 - PZR level trend                             32 AK1.01 - Loss of RHRS during all modes of I  000025 Loss of RHR System / 4                                      operation                                           39 000026 Loss of Component Cooling Water I 8                                I                        2.2.40 - Ability to apply technical Specifications for a system.                         34 1 000029 ANVS I 1                            I                        EA1.08 - Reactor trip switch pushbutton             45 1 000038 Steam Gen. Tube Rupture I 3        I:                    1 EK1.01 - Use of steam tables                         31 000040 (CEIEOS) Steam Line Rupture -
11 ES-401 PWR Examination Outline Form ES-401-2 11 It ES-401 I Emergency and Abnormal F I E/APE # / Name / Safety Function 11 000001 Continuous Rod Withdrawal  
Excessive Heat Transfer 1 4 000054 (CEIEO6) Loss of Main Feedwater I 4 CK-                  2.4.45 - Ability to prioritize and interpret the obtain desired operating results during abnormal and emergency situations.
/ 1 I 000003 Dropped Control Rod / 1 00005 1 Loss of Condenser Vacuum 000033 Loss of Intermediate Range NI / 7 11 KIA Category Point Totals: 'R Ex it Evc 4 tion Outline Form ES-401-2 WA Topic(s) AA2.04 - Reactor power and its trend 4.3 3.6 2.4.1 - Knowledge of EOP entry conditions and immediate action steps.
41 32 EK3.02 - Actions contained in EOP for loss 000055 Station Blackout I 6                                        of offsite and onsite power                         43 Y        AA2.73 - PZR heater odoff                           35 AA1.06 - Manual control of components for 000057 Loss of Vital AC Inst. Bus 16                                                                                    35
AA2.01- Cause of low vacuum
                                                            -          which automatic control is lost AA2.01 - That a loss of dc power has 000058 Loss of DC Power I 6                                X        occurred; verification that substitute power         31 sources have come on line AA2.01 - Cause and effect of low-pressure 000065 Loss of Instrument Air I 8                                  instrument air alarm                                 29
'1 I condition I 2.7 I I- 2.4.20 - Knowledge of operational and notes.
      ~_______         ~
X implications of EOP warnings, cautions, 4.3 2 I 2 I Group Point Total: 141 I- ll I ES-401 PWR Examination Outline Form ES-401-.dI - 11 ES-401 System #I Name Ir 005 Residual Heat Removal I 013 Engineered Safety Features Actuation 06 1 AuxiliaryEmergency Feedwater 073 Process Radiation Monitoring w 078 Instrument Air PV amination Outline Form ES-401-2 II WA Topic(s) A2.02 - Pressure transient protection during cold shutdown X 2.1.45 - Ability to identify and interpret diverse indications to validate the response of another indication.
000077 Generator Voltage and Electric                             AK2.06 - Reactor power Grid Disturbances I 6                                                                                                  3.9 1 KIA Category Totals:                       I   3 I 3 I 3 I 3 I 3 I Group Point Total:
A2.08 - Flow rates expected from various combinations of AFW pump discharge valves 2.4.6 - Knowledge of EOP mitigation strategies.
 
A2.01 - Air dryer and filter malfunctions Group Point Total:
1 ES-401                                     PWR Examination Outline                                   Form ES-401.gI -
02 IR 3.7 4.3 2.9 - 4.7 - 2.9 #
I - 4 0 1                                      PWR Examination Outline Form ES-401-2 IR
1G11 4 PWR Examina AG X :ion Outline 61 00 11 ES-401 KA PW stems - ' KK 45 23 X X Examination Out1 AA >erator WA Topic(s) A2.04 - Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs. control rod reactivity changes A2.17 - Malfunction of electrohydraulic control 2.2.31 -Ability to determine operability and/or availability of safetv related eauinment.
                                                                                                            -2.9
Form ES-401-2 Group Point Total: - IK - 3.8 - 2.9 - 4.6 KIA # Topic ~~ ~ Subtotal 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.  
                                                                                                            -3.4 3.9
~ 2.3.6 2.3.15 r ~~ ~ ~~ - Ability to approve release permits. radiation monitors and alarms, portable survey 3.8 Knowledge of radiation monitoring systems, such as fixed instruments, personnel monitoring equipment, etc.
                                                                                                            -3.7 2.8 000074 (W/E06&E07) Inad. Core Cooling I 4 4.0 CE/A13 - Natural Circ. I 4 instrumentation, signals, interlocks,       3.0 odes, and automatic and manual 3.0 4.2
3.1 Subtotal 2.4.3 I Ability to identify post-accident instrumentation. - 3 2 3.7 Form ES-401 ES-401 Generic Knowledge
                                                                                                            - 9
& Abilities Outline Facility:
 
Calvert Category 08 RO +P- 2.1.3 I Knowledge of shift or short-term relief turnover practices.
ES-401                         PWR Examination Outline                                       Form ES-401-   41 1 ES-401                           PWR 1 amination Outline
2.1.17 I Ability to make accurate, clear, and concise verbal reports 3.9 I -I - 1. Conduct of Operations 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. Ability to interpret and execute procedure steps.
                                                ~p 1- Reactor Operator Form ES-401-2 1
2.1.20 2.1.40 I Knowledge of refueling administrative requirements.  
v System # I Name                                                K/A Topic(s)                       #
+"- Subtotal 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.  
003 Reactor Coolant Pump                              K6.14 - Starting Requirements           2.6 2.1.3 1 - Ability to locate control room switches, controls, and H
: 2. Equipment Control 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. Knowledge of the process used to track inoperable alarms. 2.2.43 -I - 21 I 3.2 I Knowledge of radiation exposure limits under normal or 2.3-4 I emergency conditions.
003 Reactor Coolant Pump                        X    indications, and to determine that     4.6 they correctly reflect the desired plant lineup.
1 3. Radiation Control 2.3.1 1 I Ability to control radiation releases.  
K5.14 - Reduction process of gas concentration in RCS: vent-accumulated non-condensable gases from PZR bubble space, 004 Chemical and Volume depressurized during cooldown or       2.5 Control by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)
: 4. Emergency Procedures I Plan 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
K5.02 - Need for adequate 005 Residual Heat Removal                                                                     3.4 subcooling 006 Emergency Core Cooling                       I I A3.04 - Cooling water systems             3.8 K2.02 - Valve operators for 006 Emergency Core Cooling                                                                    2.5 accumulators 007 Pressurizer ReliefIQuench Tank I I K3.01- Containment                         3.3 K2.02 - CCW pump, including 008 Component Cooling Water                                                                     3.0 emergency backup I--
3.7 2.4.1 1 F 2.4.45 ~~ Knowledge of abnormal condition procedures. Ability to prioritize and interpret the significance of each annunciator or alarm.
2.4.1 - Knowledge of EOP entry 008 Component Cooling Water                        X    condition and immediate action         4.6 steps.
I Subtotal 12 - - Tier 3 Point Total 7
010 Pressurizer Pressure                            Al.06 - RCS heatup and cooldown 3.1 Control                                    effect on pressure 012 Reactor Protection                      I I K6.10 - Permissive circuits               3.3 013 Engineered Safety                             K1.18 - Premature reset of ESF         3.7 Features Actuation                                actuation K4.04 - Cooling of control rod         2.8 022 Containment Cooling drive motors K3 .O 1 - Containment equipment subject to damage by high or low       2.9 022 Containment Cooling temperature, humidity, and pressure 026 Containment Spray                                                                      4.2 2.2.37 - Ability to determine 026 Containment Spray                                                                      3.6 safety related equipment.
ES-401 Record of Rejected WAS Form ES-401 11 Randomly Selected K/A EA1.02 025 K2.02 A3.01 2.1.43 2.4.26 005 AA2.01 2.4.26 Reason for Rejection Replaced 029, EA1.02 with 029, EA1.08. WA EA1.02 is an inappropriate match for the E/APE # selected. CCNPP standard post-trip actions for an ATWS do not include boration from the RWST. Replaced 025, K3.01 with 022, K3.01. Calvert Cliffs does not have ice condensers. Replaced K2.02 with K3.04. Calvert Cliffs does not have an Integrated Control System.
 
Replaced A3.01 with A3.02. Calvert Cliffs Reactor Coolant Waste Evaporators are retired-in-place Replaced 2.1.43 with 2.1.19. Poor WAmatch to system Replaced KJA 2.4.26 with WA 2.4.1. WA 2.4.26 is an inappropriate match for the E/APE # selected.
PWR Examination Outline Form ES-401-2 1 II                                           1 1 1 ES-401 PWR Examination Outline             41 Form ES-401--
WA 2.4.26 pairel knowledge of facility fire protection with a Dropped Control Rod. WA 2.4.1 pairs knowledge of EOP entry conditions and immediate action steps with a Dropped Control Rod.
 
Replaced 005 AA2.01 with 051 AA2.01 due to over sampling of CEA Malfunctions.
ES-401                         PWR Examination Outline   Form ES-401- -  d1 ES-401                          PWR Examination Outline   Form ES-401-2 000015/17 RCP Malfunctions / 4 I
Replaced KJA 2.4.26 with 2.2.37. WA 2.4.26 is an inappropriat match for the E/APE # selected.
 
WA 2.4.26 paired knowledge of facility fire protection with Area Radiation Monitoring.
1 ES-401                                       PWR Examination Outline                                     Form ES-401-2     1 It ES-401                                           I 'R Ex  tion Outline                                  Form ES-401-2 Emergency and Abnormal F it Evc 4
WA 2.2.37 pairs the ability to determine operability and/or availability of safety related equipment with Area Radiation Monitoring.
I                               WA Topic(s)
CCNPP LOI-2206 Retake Exam Data ES-401 PWR Examination Outline Form ES-401 - Facility: Calvert Cliffs Date of Exam: December 10,2008 I I II Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two). 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. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do na apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutionr 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.
E/APE # / Name / Safety Function 1  000001 Continuous Rod Withdrawal / 1 I                   AA2.04 - Reactor power and its trend      4.3 2.4.1 - Knowledge of EOP entry 000003 Dropped Control Rod / 1                                                                                3.6 conditions and immediate action steps.
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.
00005 1 Loss of Condenser Vacuum 1' I    AA2.01- Cause of low vacuum condition 2.4.20 - Knowledge of operational I 2.7 I    I-000033 Loss of Intermediate Range NI / 7                       X implications of EOP warnings, cautions,    4.3 and notes.
Absent a plant-specific priority, only those VAS having an importance rating (IR) of 2.5 or higher shall be selected.
1  KIA Category Point Totals:                                 2 II2  Group Point Total:
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
1 4 1
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 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 applicablr K/As. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals  
 
(#) for each system and category.
I ES-401
Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in othwr than Category A2 or G* on the SRO-only exam, enter it on the lei? side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- I                                                                                                      ll PWR Examination Outline                                  Form ES-401-.dI -
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals  
1  ES-401                      PV  amination Outline                                   Form ES-401-2 I    I I r      System # I Name                                          WA Topic(s)             IR I  005 Residual Heat Removal A2.02 - Pressure transient protection during cold shutdown 3.7 2.1.45 - Ability to identify and 013 Engineered Safety                              interpret diverse indications to X                                          4.3 Features Actuation                                validate the response of another indication.
(#) on Form ES-401-3.
A2.08 - Flow rates expected from 06 1 AuxiliaryEmergency                            various combinations of AFW          2.9 Feedwater                                          pump discharge valves w
Limit SRO selections to K/As that are linked to 10 CFR 55.43.
073 Process Radiation                              2.4.6 - Knowledge of EOP            4.7 Monitoring                                        mitigation strategies.
CCNPP LOI-2206 Retake Exam Data K/A Imp Vision Topics # ID E/APE # / Name / Safety Function Tier l/Group 1- Reactor Ope Cognitive
A2.01 - Air dryer and filter 078 Instrument Air                                malfunctions
# Level #ator 000007 (CE/EO2) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 EK2.03 3.5 420274 B 3 1( AK1.02 3.1 450851 N 2 21 EK3.26 4.4 426519 B 1 000022 Loss of Rx Coolant Makeup 1 2 000025 Loss of RHR System / 4 000011 Large Break LOCA / 3 I 2.2.44 I 4.2 AA1.03 3.2 AK1.O1 3.9 000015/17 RCP Malfunctions  
                                                                                            -2.9 0  2              Group Point Total:
/ 4 I AK2.07 I 2.9 000026 Loss of Component Cooling Water / 8 000029 ATWS 1 1 000038 Steam Gen. Tube Rupture
                                                                                            - 5
/ 3 2.2.40 3.4 450770 M 1 1 EA1.08 4.5 450651 M 2 27 EK1.O1 3.1 423208 B 2 2, 53 2.4.45 000040 (CEIEO5) Steam Line Rupture - Excessive Heat Transfer / 4 420393 I B I 2 I ! 4.1 450950 N 3 53 000054 (CE/E06) Loss of Main Feedwater  
 
/ 4 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 EK3.3 3.2 428472 B 2 12 EK3.02 4.3 440704 B 1 < AA2.73 3.5 418107 B 2 t5 ~~ 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000065 Loss of Instrument Air / 8 AA1.06 3.5 450852 N 2 25 AA2.01 3.7 451132 N 2 23 AA2.01 2.9 451150 M 2 000077 Generator Voltage  
1        G                              1                                      1 PWR Examina :ion Outline 11 ES-401 K
& Electric Grid Disturbances  
PW Examination Out1 stems - '
/ 6 AK2.06 3.9 450730 N 1 7 K/A Tooics E/APE # / Name / Safety Function Tier l/Group 2- Reactor OPI Imp # Vision ID Cognitive  
K    K A  A  A  A G
# - Type Level - 000067 Plant Fire On-site / 8 000059 Accidental Liquid RadWaste Rel.  
                                        >erator WA Topic(s)
/ 9 000061 ARM System Alarms  
Form ES-401-2 IK 4    5    6 1   2  3  4 A2.04 - Effects on axial flux density of control rod alignment and sequencing, X           xenon production and          3.8 decay, and boron vs.
/ 7 I 2-2-42 I 3.9 AA2.02 2.9 AK3.02 3.4 000068 (BW/A06) Control Room Evac.  
control rod reactivity changes                      -
/ 8 000069 Loss of CTMT Integrity  
A2.17 - Malfunction of X          electrohydraulic control      2.9 2.2.31 -Ability to X determine operability and/or availability of        4.6 safetv related eauinment.
/ 5 000074 (W/E06&E07)
0 0              Group Point Total:
Inad. Core Cooling 14 CE/A13 - Natural Circ. / 4 AK2.02 3.7 AA1.03 2.8 EA2.06 4.0 CE/A16 Excess RCS Leakage / 2 I AK1-2 I 3.0 CE/E09 Functional Recovery I m1.1 I 4.2 !rator 450933 I N I 2 I 13 440348 1 B I 2 I :4 ;i 425068 B
                                                                    - 3
- - CCNPP LOI-2206 Retake Exam Data CCNPP LOI-2206 Retake Exam Data Tier 2 / Group 2 - Reactor Operator E/APE # / Name / Safety Function 001 Control Rod Drive 027 Containment Iodine Removal 033 Spent Fuel Pool Cooling 035 Steam Generator 041 Steam DumpDurbine Bypass Control 055 Condenser Air Removal ~ ~~ ~ ~ 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal ~~ ~ 086 Fire Protection -A+ b4.02
 
* K5.07 K1.06 I 2.6 2.4.6 1 A3.02 K3.04 I 2.7 K4.02 I 3.0 Vision 1 I Cognitive 1 Exan ID Type Level 451032 N 3 E3 451130 B 1 Ll 451050 N 2 i2 428225 B 2 ;3 428429 I B I 3 I 2 1 451033 451051 I N I 2 I ; 1 434432 I B I 1 1 ;8 CCNPP LOI-2206 Retake Exam Data Imp Vision ID Type E/APE # / Name / Safety Function I Tier 1 / Group I - Sr. Reactor Operator Cognitive  
ES-401                                  Generic Knowledge & Abilities Outline                                    Form ES-401 Facility: Calvert                                                                                  08 Category              KIA #                                    Topic                                    RO 2.1.3 2.1.17 I Knowledge of shift or short-term relief turnover practices.
~ -- Level -- E/APE # / Name / Safety Function 000001 Continuous Rod Withdrawal
I Ability to make accurate, clear, and concise verbal reports
/ 1 000003 Dropped Control Rod / 1 000051 Loss of Condenser Vacuum 000033 Loss of Intermediate Range NI / 7 000015/17 RCP Malfunctions
                                                                                                  +P- 3.9 I          - I  -
/ 4 AA2.04 4.3 419089 B 1 82 (7) 2.4.1 3.6 451078 B 1 8:! (8) AA2.01 2.7 441651 M 2 88 (13) 2.4.20 4.3 451082 N 2 87 (12) -- .- 000027 Pressurizer Pressure Control System Malfunction
1.
/ 3 Imp Vision ID Type E/APE # / Name / Safety Function 005 Residual Heat Removal A2.02 3.7 451100 N 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000054 Loss of Main Feedwater
Conduct              2.1.44        Knowledge of RO duties in the control room during fuel of Operations                        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.
/ 4 Cognitive  
                                                                                                                  +"-
# 3 99 (24) Level ---- 000062 Loss of Nuclear Svc Water / 4 CE/EO2 Reactor Trip - Stabilization - Recovery / 1 4ifF AA2.10 3.6 2.4.23 I AA2.01 - Cognitive Exan # Vision ID Level 89 14) 77 :2) Tier 1 / Group 2 - Sr. Reactor Operator Tier 2 / Group 1 - Sr. Reactor Operator 013 Engineered Safety Features Actuation I 2.1.45 1 4.3 I 451076 I N I 3 I 81) (5) 061 Auxiliary/Emergency Feedwater I A2.08 1 2.9 I 451098 I N I 2 I 93 (22) ~~ ~~ ____~ 073 Process Radiation Monitoring 2.4.6 4.7 451110 M 2 1C') (25) 078 Instrument Air A2.01 2.9 451097 M 2 9F (21)
2.1.20        Ability to interpret and execute procedure steps.
CCNPP LOI-2206 Retake Exam Data 015 Nuclear Instrumentation 045 Main Turbine Generator 072 Area Radiation Monitoring Tier 2 / Group 2 - Sr. Reactor Operator A2.04 3.8 451079 N 3 85 10) A2.17 2.9 425257 B 2 95 20) 2.2.37 4.6 451073 N 2 79 (4) - - K/A Imp Vision # Cognitive
2.1.40  I      Knowledge of refueling administrative requirements.
-- Topics # -Type* ID E/APE # / Name / Safety Function Category RO RO RO SRO SRO RO Equipment Control RO SRO RO RO RO SRO SRO RO RO SRO SRO Emergency procedures
Subtotal 2.2.1        Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
/ Plan Imp Vision Cognitive
: 2.                   2.2.17        Knowledge of the process for managing maintenance Equipment                            activities during power operations, such as risk Control                              assessments, work prioritization, and coordination with the transmission system operator.
# K/A 2.1.3 3.7 450870 N 1 I9 2.1.17 3.9 426067 B 1 3 - Topics # ID Type Level 2.1.44 3.9 450934 N 1 14 2.1.20 4.6 445189 0 1 94 (19) 2.1.40 3.9 420627 B 1 7( (1) 2.2.1 4.5 425936 B 2 32 2.2.17 2.6 451170 N 1 34 2.2.43 3.3 451099 N 1 9E (23) 2.3.4 3.2 417947 B 1 70 2.3.11 3.8 420605 B 1 73 2.3.14 3.7 450890 M 2 31 2.3.6 3.8 Q51080 N 1 8 + (9) 2.3.15 3.1 424714 B 2 8t (11) 2.4.3 3.7 424951 B 1 30 ~- "- "- 2.4.5 3.7 419570 B 2 74 2.4.11 4.2 Q51095 N 2 9 (17) 2.4.45 4.3 451090 N 3 9tr (15) A Generic Knowledge
2.2.43        Knowledge of the process used to track inoperable                - I  -
& Abilities Conduct of Ops Radiation Control CCNPP LOI-2206 Retake Exam Data ~ Bank Questions (Maximum of 75%) Modified Questions Parameter 43 (!j7O/o) 8 (32%) 8 (11~0) 3 (12%) I Reactor Operator Test 1 Sr. Reactor Operator Test I Memory 30 (40%) 7 (28%) New Questions (Minimum of 10 questions - 8 RO, 2 24 (32%) 14 (56%) Comprehension
alarms.
/ Analysis (50 - 60% for RO exam) I 45 (60%) 18 (72%) 450993 451016 ~ Modified Questions 450990 420397 I Modified Question # I Original Question # 451110 451097 I Q50992 I 414583 428787 450364 450770 I 420383 QS065 1 I 419256 450930 I 424994 441651 441 134 Q50890 442268 Q51150 420290 CCNPP LOI-2206 Retake Exam Data Key to symbols / abbreviations:
                  ~~  ~
Type: B = Bank Question M = Modified Question N = New Question Cognitive Level: 1 = Fundamental knowledge or simple memory (stpts, definitions, facts) 0 2 = Comprehension (recognition of system interactions) 0 3 = Analysis / Synthesis  
Subtotal                                                                        2 1 2.3-4 2.3.1 1 II    Knowledge of radiation exposure limits under normal or emergency conditions.
/ Application (use of info to predict an event or outcome or to solve a problem)}}
Ability to control radiation releases.
I   3.2 I       1 - 1    -
3.
Radiation            2.3.14        Knowledge of radiation or contamination hazards that Control                              may arise during normal, abnormal, or emergency conditions or activities.
                            ~
r  ~~    ~        ~~
2.3.6        Ability to approve release permits.                                            3.8 2.3.15        Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey                                3.1 instruments, personnel monitoring equipment, etc.
Subtotal                                                                         3              2         -
2.4.3    I Ability to identify post-accident instrumentation.                 3.7 2.4.5        Knowledge of the organization of the operating
: 4.                                  procedures network for normal, abnormal, and emergency          3.7 Emergency F
evolutions.
Procedures I                      ~~
Plan                  2.4.1 1        Knowledge of abnormal condition procedures.
2.4.45        Ability to prioritize and interpret the significance of each annunciator or alarm.
I Subtotal                                                                    1    2 Tier 3 Point Total                                                                                                    7
 
ES-401              Record of Rejected WAS                        Form ES-401-4 -1 Randomly                          Reason for Rejection Selected K/A Replaced 029, EA1.02 with 029, EA1.08. WA EA1.02 is an inappropriate match for the E/APE # selected. CCNPP standard EA1.02 post-trip actions for an ATWS do not include boration from the RWST.
Replaced 025, K3.01 with 022, K3.01. Calvert Cliffs does not 025 have ice condensers.
Replaced K2.02 with K3.04. Calvert Cliffs does not have an K2.02 Integrated Control System.
Replaced A3.01 with A3.02. Calvert Cliffs Reactor Coolant A3.01 Waste Evaporators are retired-in-place 2.1.43  Replaced 2.1.43 with 2.1.19. Poor WAmatch to system Replaced KJA 2.4.26 with WA 2.4.1. WA 2.4.26 is an inappropriate match for the E/APE # selected. WA 2.4.26 pairel 2.4.26  knowledge of facility fire protection with a Dropped Control Rod. WA 2.4.1 pairs knowledge of EOP entry conditions and immediate action steps with a Dropped Control Rod.
Replaced 005 AA2.01 with 051 AA2.01 due to over sampling of 005 AA2.01 CEA Malfunctions.
Replaced KJA 2.4.26 with 2.2.37. WA 2.4.26 is an inappropriat match for the E/APE # selected. WA 2.4.26 paired knowledge of facility fire protection with Area Radiation Monitoring. WA 2.4.26 2.2.37 pairs the ability to determine operability and/or availability of safety related equipment with Area Radiation Monitoring.
 
CCNPP LOI-2206Retake Exam Data ES-401                                   PWR Examination Outline                                     Form ES-401-2 Facility: Calvert Cliffs                                 Date of Exam: December 10,2008                                           -
I                 I                                                           II 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two).
: 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 associated outline; systems or evolutions that do na apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutionr 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 VAShaving 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 1and 2 from the shaded systems and K/A categories.
7.*  The generic (G) K/As in Tiers 1and 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 applicablr K/As.
: 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (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 othwr than Category A2 or G* on the SRO-only exam, enter it on the lei? 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.
 
CCNPP LOI-2206Retake Exam Data Tier l/Group 1- Reactor Ope #ator K/A      Imp    Vision          Cognitive        #
E/APE # / Name / Safety Function                 Topics      #     ID              Level 000007 (CE/EO2) Reactor Trip - Stabilization - Recovery / 1   EK2.03     3.5 420274     B         3         1(
000008 Pressurizer Vapor Space Accident / 3                    AK1.02     3.1 450851     N         2         21 000009 Small Break LOCA / 3                                    EK3.26     4.4 426519     B         1 000011 Large Break LOCA / 3                                 I 2.2.44 I   4.2 000015/17 RCP Malfunctions / 4                             I AK2.07 I   2.9 000022 Loss of Rx Coolant Makeup 1 2                          AA1.03     3.2                                 53 000025 Loss of RHR System / 4                                  AK1.O1      3.9  420393  I  B  I    2      I  !
000026 Loss of Component Cooling Water / 8                    2.2.40      3.4  450770    M        1          1 000029 ATWS 1 1                                                EA1.08     4.5 450651     M         2         27 000038 Steam Gen. Tube Rupture / 3                            EK1.O1     3.1 423208     B         2         2, 000040 (CEIEO5) Steam Line Rupture - Excessive Heat 2.4.45      4.1 450950     N         3         53 Transfer / 4 000054 (CE/E06) Loss of Main Feedwater / 4                     EK3.3     3.2 428472     B         2         12 000055 Station Blackout / 6                                    EK3.02     4.3 440704     B         1           <
000056 Loss of Off-site Power / 6                              AA2.73     3.5 418107     B         2         t5
                                      ~~
000057 Loss of Vital AC Inst. Bus / 6                         AA1.06     3.5 450852     N         2         25 000058 Loss of DC Power / 6                                    AA2.01     3.7 451132     N         2         23 000065 Loss of Instrument Air / 8                              AA2.01     2.9 451150     M         2 000077 Generator Voltage & Electric Grid Disturbances / 6     AK2.06     3.9 450730     N         1           7 Tier l/Group 2- Reactor OPI!rator E/APE # / Name / Safety Function                   K/A Tooics Imp Vision ID   Type Cognitive Level   --     #
000059 Accidental Liquid RadWaste Rel. / 9                     AA2.02      2.9  450933  I  N  I      2    I  13 000061 ARM System Alarms / 7                                   AK3.02      3.4 000067 Plant Fire On-site / 8                              I   2-2-42 I   3.9 000068 (BW/A06) Control Room Evac. / 8                         AK2.02      3.7 000069 Loss of CTMT Integrity / 5                             AA1.03      2.8 1      I            I i                              ;
000074 (W/E06&E07) Inad. Core Cooling 1 4                      EA2.06      4.0 440348      B        2        :4 CE/A13 - Natural Circ. / 4 CE/A16 Excess RCS Leakage / 2                               I AK1-2   I   3.0 CE/E09 Functional Recovery                                   I m1.1   I   4.2 425068     B
 
CCNPP LOI-2206 Retake Exam Data -
CCNPP LOI-2206Retake Exam Data Tier 2 / Group 2 - Reactor Operator
~
E/APE # / Name / Safety Function 001 Control Rod Drive 027 Containment Iodine Removal 033 Spent Fuel Pool Cooling 035 Steam Generator 041 Steam DumpDurbine Bypass Control 055 Condenser Air Removal
          ~~
056 Condensate 068 Liquid Radwaste
                      ~         ~
                                                    +A- b4.02 K5.07 K1.06 2.4.6 A3.02 I
1 2.6 Vision ID 451032 451130 451050 428225 428429 451033 1
I Type N
B N
B B
I I
Cognitive Level 3
1 2
2 3
1 I
Exan E3 L l i2
                                                                                                    ;3 21 071 Waste Gas Disposal                                  K3.04 I 2.7 451051  I  N  I   2     I   ;1 I    434432 I       I           1
~~        ~
086 Fire Protection                                    K4.02  3.0            B      1           ;8
 
CCNPP LOI-2206Retake Exam Data I                                    Tier 1/ Group I         - Sr. Reactor Operator                                           -
4ifF Vision              Cognitive E/APE # / Name / Safety Function                                         ID                Level Exan        #
000015/17 RCP Malfunctions / 4                                                                                      89 14) 000027 Pressurizer Pressure Control System Malfunction / 3 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000054 Loss of Main Feedwater / 4 AA2.10 2.4.23 AA2.01 I  3.6                                       77 :2) 000062 Loss of Nuclear Svc Water / 4 CE/EO2 Reactor Trip - Stabilization - Recovery / 1 Tier 1/ Group 2       - Sr. Reactor Operator E/APE # / Name / Safety Function 000001 Continuous Rod Withdrawal / 1                        AA2.04 Imp 4.3 Vision I D 419089
                                                                                              - Type -
B Cognitive Level 1
                                                                                                                    --  82 (7)
                                                                                                                                  ~
000003 Dropped Control Rod / 1                               2.4.1      3.6    451078        B          1          8:! (8) 000051 Loss of Condenser Vacuum                              AA2.01      2.7    441651        M          2       88 (13) 000033 Loss of Intermediate Range NI / 7                    2.4.20      4.3    451082        N          2        87 (12)
Tier 2 / Group 1 Sr. Reactor Operator E/APE # / Name / Safety Function                            Imp      Vision I D Type Cognitive Level 3       99 (24) 005 Residual Heat Removal                                    A2.02      3.7    451100        N 013 Engineered Safety Features Actuation                  I  2.1.45  1  4.3  I 451076     I   N I       3     I     81) (5) 061 Auxiliary/Emergency Feedwater                         I   A2.08   1   2.9   I 451098   I   N I~~
2     I 93 (22)
                                                                                                                        ~~       ____~
073 Process Radiation Monitoring                             2.4.6       4.7     451110       M           2       1C') (25) 078 Instrument Air                                           A2.01       2.9     451097       M         2       9F (21)
 
CCNPP LOI-2206 Retake Exam Data Tier 2 / Group 2 - Sr. Reactor Operator Cognitive E/APE #  / Name / Safety Function          K/A Topics Imp
                                                                #  -TypVision e*I D                --
015 Nuclear Instrumentation                          A2.04   3.8   451079   N     3       85 10) 045 Main Turbine Generator                          A2.17   2.9   425257   B     2       95 20) 072 Area Radiation Monitoring                        2.2.37   4.6   451073   N     2       79 (4)
A                                        Generic Knowledge & Abilities K/A   Imp       Vision     Cognitive          #
Category Topics   #         ID  Type   Level RO     2.1.3  3.7    450870    N      1            I9 RO     2.1.17  3.9    426067    B      1           3 Conduct of Ops                    RO    2.1.44  3.9   450934     N     1           14 SRO    2.1.20   4.6   445189     0     1     94 (19)
SRO    2.1.40   3.9   420627     B     1       7( (1)
RO      2.2.1   4.5   425936     B     2           32 Equipment Control                  RO    2.2.17   2.6   451170     N     1           34 SRO    2.2.43   3.3     451099   N     1     9E (23)
                                                                                                    ~-
RO      2.3.4   3.2     417947   B     1           70 RO    2.3.11   3.8     420605   B     1           73 Radiation Control                  RO    2.3.14   3.7     450890   M     2           31 SRO      2.3.6   3.8     Q51080   N     1       8 + (9)
SRO    2.3.15   3.1     424714   B     2     8t (11)
RO      2.4.3   3.7     424951   B     1           30 RO      2.4.5   3.7   419570     B     2           74 Emergency procedures / Plan SRO    2.4.11   4.2     Q51095   N     2     9 (17)
SRO    2.4.45   4.3     451090   N     3       9tr (15)
 
CCNPP LOI-2206 Retake Exam Data
  ~
Parameter                I  Reactor Operator Test 1 Sr. Reactor Operator Test I Bank Questions                                 43  (!j7O/o)             8 (32%)
(Maximum of 75%)
Modified Questions                              8 (11~0)                 3 (12%)
New Questions (Minimum of 10 questions - 8 RO, 2             24 (32%)                 14 (56%)
Memory                                        30 (40%)                  7 (28%)
I Comprehension / Analysis                      45 (60%)                 18 (72%)
(50 - 60% for RO exam)
                    ~
Modified Questions I   Modified Question #           I Original Question #
I           Q50992                 I       414583 450770                  I      420383 QS065 1                I      419256 450930                  I      424994 450993                          450990 451016                          420397 451110                          428787 451097                          450364 441651                          441134 Q50890                          442268 Q51150                          420290
 
CCNPP LOI-2206 Retake Exam Data Key to symbols / abbreviations:
Type:
B = Bank Question M = Modified Question N = New Question Cognitive Level:
1 = Fundamental knowledge or simple memory (stpts, definitions, facts) 0   2 = Comprehension (recognition of system interactions) 0   3 = Analysis / Synthesis / Application (use of info to predict an event or outcome or to solve a problem)}}

Latest revision as of 17:42, 12 March 2020

Final Outlines (Folder 3)
ML090290246
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Site: Calvert Cliffs  Constellation icon.png
Issue date: 10/30/2008
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Text

ES-401 PWR Examination Outline Form; s-4016 dl Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRCr-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall n:)t be less than two).

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 f l 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. Systemslevolutionswithin each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specificsystems/evolutionsthat are not include4 on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA 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 WAS having an importance rating (IR) of 2.5 or higher shall be selected. Usr 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 WA categories.

7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevar to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS.

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (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 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 WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

PWR Examination Outline ES-401 Form ES-401-2 Emergency and -

1 ElAPE # / Name I Safety Function I! A 2

G KIA Topic(s) IR #

A 000007 (CE/E02)Reactor Trip -

Stabilization - Recovery I 1 EE(2.03 - Reactor trip status panel 3.5 I 000008 Pressurizer Vapor Space AK1.02 - Change in leak rate with change in Accident I 3  ? pressure 3.1 000009 Small Break LOCA I 3 EK3.26 - Maintenance of RCS subcooling X 4.4 -

2.2.44 - Ability to interpret control room indications to verify the status and operation 00001 1 Large Break LOCA I 3 ofa system, and understand how operator 4.2 actions and directives affect plant and system conditions.

1 000015/17 RCP Malfunctions I 4 I AK2.07 - RCP seals 2.9 1 000022 Loss of Rx Coolant Makeup I 2 I AA1.03 - PZR level trend 32 AK1.01 - Loss of RHRS during all modes of I 000025 Loss of RHR System / 4 operation 39 000026 Loss of Component Cooling Water I 8 I 2.2.40 - Ability to apply technical Specifications for a system. 34 1 000029 ANVS I 1 I EA1.08 - Reactor trip switch pushbutton 45 1 000038 Steam Gen. Tube Rupture I 3 I: 1 EK1.01 - Use of steam tables 31 000040 (CEIEOS) Steam Line Rupture -

Excessive Heat Transfer 1 4 000054 (CEIEO6) Loss of Main Feedwater I 4 CK- 2.4.45 - Ability to prioritize and interpret the obtain desired operating results during abnormal and emergency situations.

41 32 EK3.02 - Actions contained in EOP for loss 000055 Station Blackout I 6 of offsite and onsite power 43 Y AA2.73 - PZR heater odoff 35 AA1.06 - Manual control of components for 000057 Loss of Vital AC Inst. Bus 16 35

- which automatic control is lost AA2.01 - That a loss of dc power has 000058 Loss of DC Power I 6 X occurred; verification that substitute power 31 sources have come on line AA2.01 - Cause and effect of low-pressure 000065 Loss of Instrument Air I 8 instrument air alarm 29

~_______ ~

000077 Generator Voltage and Electric AK2.06 - Reactor power Grid Disturbances I 6 3.9 1 KIA Category Totals: I 3 I 3 I 3 I 3 I 3 I Group Point Total:

1 ES-401 PWR Examination Outline Form ES-401.gI -

I - 4 0 1 PWR Examination Outline Form ES-401-2 IR

-2.9

-3.4 3.9

-3.7 2.8 000074 (W/E06&E07) Inad. Core Cooling I 4 4.0 CE/A13 - Natural Circ. I 4 instrumentation, signals, interlocks, 3.0 odes, and automatic and manual 3.0 4.2

- 9

ES-401 PWR Examination Outline Form ES-401- 41 1 ES-401 PWR 1 amination Outline

~p 1- Reactor Operator Form ES-401-2 1

v System # I Name K/A Topic(s) #

003 Reactor Coolant Pump K6.14 - Starting Requirements 2.6 2.1.3 1 - Ability to locate control room switches, controls, and H

003 Reactor Coolant Pump X indications, and to determine that 4.6 they correctly reflect the desired plant lineup.

K5.14 - Reduction process of gas concentration in RCS: vent-accumulated non-condensable gases from PZR bubble space, 004 Chemical and Volume depressurized during cooldown or 2.5 Control by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)

K5.02 - Need for adequate 005 Residual Heat Removal 3.4 subcooling 006 Emergency Core Cooling I I A3.04 - Cooling water systems 3.8 K2.02 - Valve operators for 006 Emergency Core Cooling 2.5 accumulators 007 Pressurizer ReliefIQuench Tank I I K3.01- Containment 3.3 K2.02 - CCW pump, including 008 Component Cooling Water 3.0 emergency backup I--

2.4.1 - Knowledge of EOP entry 008 Component Cooling Water X condition and immediate action 4.6 steps.

010 Pressurizer Pressure Al.06 - RCS heatup and cooldown 3.1 Control effect on pressure 012 Reactor Protection I I K6.10 - Permissive circuits 3.3 013 Engineered Safety K1.18 - Premature reset of ESF 3.7 Features Actuation actuation K4.04 - Cooling of control rod 2.8 022 Containment Cooling drive motors K3 .O 1 - Containment equipment subject to damage by high or low 2.9 022 Containment Cooling temperature, humidity, and pressure 026 Containment Spray 4.2 2.2.37 - Ability to determine 026 Containment Spray 3.6 safety related equipment.

PWR Examination Outline Form ES-401-2 1 II 1 1 1 ES-401 PWR Examination Outline 41 Form ES-401--

ES-401 PWR Examination Outline Form ES-401- - d1 ES-401 PWR Examination Outline Form ES-401-2 000015/17 RCP Malfunctions / 4 I

1 ES-401 PWR Examination Outline Form ES-401-2 1 It ES-401 I 'R Ex tion Outline Form ES-401-2 Emergency and Abnormal F it Evc 4

I WA Topic(s)

E/APE # / Name / Safety Function 1 000001 Continuous Rod Withdrawal / 1 I AA2.04 - Reactor power and its trend 4.3 2.4.1 - Knowledge of EOP entry 000003 Dropped Control Rod / 1 3.6 conditions and immediate action steps.

00005 1 Loss of Condenser Vacuum 1' I AA2.01- Cause of low vacuum condition 2.4.20 - Knowledge of operational I 2.7 I I-000033 Loss of Intermediate Range NI / 7 X implications of EOP warnings, cautions, 4.3 and notes.

1 KIA Category Point Totals: 2 II2 Group Point Total:

1 4 1

I ES-401

- I ll PWR Examination Outline Form ES-401-.dI -

1 ES-401 PV amination Outline Form ES-401-2 I I I r System # I Name WA Topic(s) IR I 005 Residual Heat Removal A2.02 - Pressure transient protection during cold shutdown 3.7 2.1.45 - Ability to identify and 013 Engineered Safety interpret diverse indications to X 4.3 Features Actuation validate the response of another indication.

A2.08 - Flow rates expected from 06 1 AuxiliaryEmergency various combinations of AFW 2.9 Feedwater pump discharge valves w

073 Process Radiation 2.4.6 - Knowledge of EOP 4.7 Monitoring mitigation strategies.

A2.01 - Air dryer and filter 078 Instrument Air malfunctions

-2.9 0 2 Group Point Total:

- 5

1 G 1 1 PWR Examina :ion Outline 11 ES-401 K

PW Examination Out1 stems - '

K K A A A A G

>erator WA Topic(s)

Form ES-401-2 IK 4 5 6 1 2 3 4 A2.04 - Effects on axial flux density of control rod alignment and sequencing, X xenon production and 3.8 decay, and boron vs.

control rod reactivity changes -

A2.17 - Malfunction of X electrohydraulic control 2.9 2.2.31 -Ability to X determine operability and/or availability of 4.6 safetv related eauinment.

0 0 Group Point Total:

- 3

ES-401 Generic Knowledge & Abilities Outline Form ES-401 Facility: Calvert 08 Category KIA # Topic RO 2.1.3 2.1.17 I Knowledge of shift or short-term relief turnover practices.

I Ability to make accurate, clear, and concise verbal reports

+P- 3.9 I - I -

1.

Conduct 2.1.44 Knowledge of RO duties in the control room during fuel of Operations 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.

+"-

2.1.20 Ability to interpret and execute procedure steps.

2.1.40 I Knowledge of refueling administrative requirements.

Subtotal 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

2. 2.2.17 Knowledge of the process for managing maintenance Equipment activities during power operations, such as risk Control assessments, work prioritization, and coordination with the transmission system operator.

2.2.43 Knowledge of the process used to track inoperable - I -

alarms.

~~ ~

Subtotal 2 1 2.3-4 2.3.1 1 II Knowledge of radiation exposure limits under normal or emergency conditions.

Ability to control radiation releases.

I 3.2 I 1 - 1 -

3.

Radiation 2.3.14 Knowledge of radiation or contamination hazards that Control may arise during normal, abnormal, or emergency conditions or activities.

~

r ~~ ~ ~~

2.3.6 Ability to approve release permits. 3.8 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey 3.1 instruments, personnel monitoring equipment, etc.

Subtotal 3 2 -

2.4.3 I Ability to identify post-accident instrumentation. 3.7 2.4.5 Knowledge of the organization of the operating

4. procedures network for normal, abnormal, and emergency 3.7 Emergency F

evolutions.

Procedures I ~~

Plan 2.4.1 1 Knowledge of abnormal condition procedures.

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

I Subtotal 1 2 Tier 3 Point Total 7

ES-401 Record of Rejected WAS Form ES-401-4 -1 Randomly Reason for Rejection Selected K/A Replaced 029, EA1.02 with 029, EA1.08. WA EA1.02 is an inappropriate match for the E/APE # selected. CCNPP standard EA1.02 post-trip actions for an ATWS do not include boration from the RWST.

Replaced 025, K3.01 with 022, K3.01. Calvert Cliffs does not 025 have ice condensers.

Replaced K2.02 with K3.04. Calvert Cliffs does not have an K2.02 Integrated Control System.

Replaced A3.01 with A3.02. Calvert Cliffs Reactor Coolant A3.01 Waste Evaporators are retired-in-place 2.1.43 Replaced 2.1.43 with 2.1.19. Poor WAmatch to system Replaced KJA 2.4.26 with WA 2.4.1. WA 2.4.26 is an inappropriate match for the E/APE # selected. WA 2.4.26 pairel 2.4.26 knowledge of facility fire protection with a Dropped Control Rod. WA 2.4.1 pairs knowledge of EOP entry conditions and immediate action steps with a Dropped Control Rod.

Replaced 005 AA2.01 with 051 AA2.01 due to over sampling of 005 AA2.01 CEA Malfunctions.

Replaced KJA 2.4.26 with 2.2.37. WA 2.4.26 is an inappropriat match for the E/APE # selected. WA 2.4.26 paired knowledge of facility fire protection with Area Radiation Monitoring. WA 2.4.26 2.2.37 pairs the ability to determine operability and/or availability of safety related equipment with Area Radiation Monitoring.

CCNPP LOI-2206Retake Exam Data ES-401 PWR Examination Outline Form ES-401-2 Facility: Calvert Cliffs Date of Exam: December 10,2008 -

I I II 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two).

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 associated outline; systems or evolutions that do na apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutionr 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 VAShaving 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 1and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1and 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 applicablr K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (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 othwr than Category A2 or G* on the SRO-only exam, enter it on the lei? 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.

CCNPP LOI-2206Retake Exam Data Tier l/Group 1- Reactor Ope #ator K/A Imp Vision Cognitive #

E/APE # / Name / Safety Function Topics # ID Level 000007 (CE/EO2) Reactor Trip - Stabilization - Recovery / 1 EK2.03 3.5 420274 B 3 1(

000008 Pressurizer Vapor Space Accident / 3 AK1.02 3.1 450851 N 2 21 000009 Small Break LOCA / 3 EK3.26 4.4 426519 B 1 000011 Large Break LOCA / 3 I 2.2.44 I 4.2 000015/17 RCP Malfunctions / 4 I AK2.07 I 2.9 000022 Loss of Rx Coolant Makeup 1 2 AA1.03 3.2 53 000025 Loss of RHR System / 4 AK1.O1 3.9 420393 I B I 2 I  !

000026 Loss of Component Cooling Water / 8 2.2.40 3.4 450770 M 1 1 000029 ATWS 1 1 EA1.08 4.5 450651 M 2 27 000038 Steam Gen. Tube Rupture / 3 EK1.O1 3.1 423208 B 2 2, 000040 (CEIEO5) Steam Line Rupture - Excessive Heat 2.4.45 4.1 450950 N 3 53 Transfer / 4 000054 (CE/E06) Loss of Main Feedwater / 4 EK3.3 3.2 428472 B 2 12 000055 Station Blackout / 6 EK3.02 4.3 440704 B 1 <

000056 Loss of Off-site Power / 6 AA2.73 3.5 418107 B 2 t5

~~

000057 Loss of Vital AC Inst. Bus / 6 AA1.06 3.5 450852 N 2 25 000058 Loss of DC Power / 6 AA2.01 3.7 451132 N 2 23 000065 Loss of Instrument Air / 8 AA2.01 2.9 451150 M 2 000077 Generator Voltage & Electric Grid Disturbances / 6 AK2.06 3.9 450730 N 1 7 Tier l/Group 2- Reactor OPI!rator E/APE # / Name / Safety Function K/A Tooics Imp Vision ID Type Cognitive Level -- #

000059 Accidental Liquid RadWaste Rel. / 9 AA2.02 2.9 450933 I N I 2 I 13 000061 ARM System Alarms / 7 AK3.02 3.4 000067 Plant Fire On-site / 8 I 2-2-42 I 3.9 000068 (BW/A06) Control Room Evac. / 8 AK2.02 3.7 000069 Loss of CTMT Integrity / 5 AA1.03 2.8 1 I I i  ;

000074 (W/E06&E07) Inad. Core Cooling 1 4 EA2.06 4.0 440348 B 2 :4 CE/A13 - Natural Circ. / 4 CE/A16 Excess RCS Leakage / 2 I AK1-2 I 3.0 CE/E09 Functional Recovery I m1.1 I 4.2 425068 B

CCNPP LOI-2206 Retake Exam Data -

CCNPP LOI-2206Retake Exam Data Tier 2 / Group 2 - Reactor Operator

~

E/APE # / Name / Safety Function 001 Control Rod Drive 027 Containment Iodine Removal 033 Spent Fuel Pool Cooling 035 Steam Generator 041 Steam DumpDurbine Bypass Control 055 Condenser Air Removal

~~

056 Condensate 068 Liquid Radwaste

~ ~

+A- b4.02 K5.07 K1.06 2.4.6 A3.02 I

1 2.6 Vision ID 451032 451130 451050 428225 428429 451033 1

I Type N

B N

B B

I I

Cognitive Level 3

1 2

2 3

1 I

Exan E3 L l i2

3 21 071 Waste Gas Disposal K3.04 I 2.7 451051 I N I 2 I ;1 I 434432 I I 1

~~ ~

086 Fire Protection K4.02 3.0 B 1 ;8

CCNPP LOI-2206Retake Exam Data I Tier 1/ Group I - Sr. Reactor Operator -

4ifF Vision Cognitive E/APE # / Name / Safety Function ID Level Exan #

000015/17 RCP Malfunctions / 4 89 14) 000027 Pressurizer Pressure Control System Malfunction / 3 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000054 Loss of Main Feedwater / 4 AA2.10 2.4.23 AA2.01 I 3.6 77 :2) 000062 Loss of Nuclear Svc Water / 4 CE/EO2 Reactor Trip - Stabilization - Recovery / 1 Tier 1/ Group 2 - Sr. Reactor Operator E/APE # / Name / Safety Function 000001 Continuous Rod Withdrawal / 1 AA2.04 Imp 4.3 Vision I D 419089

- Type -

B Cognitive Level 1

-- 82 (7)

~

000003 Dropped Control Rod / 1 2.4.1 3.6 451078 B 1 8:! (8) 000051 Loss of Condenser Vacuum AA2.01 2.7 441651 M 2 88 (13) 000033 Loss of Intermediate Range NI / 7 2.4.20 4.3 451082 N 2 87 (12)

Tier 2 / Group 1 Sr. Reactor Operator E/APE # / Name / Safety Function Imp Vision I D Type Cognitive Level 3 99 (24) 005 Residual Heat Removal A2.02 3.7 451100 N 013 Engineered Safety Features Actuation I 2.1.45 1 4.3 I 451076 I N I 3 I 81) (5) 061 Auxiliary/Emergency Feedwater I A2.08 1 2.9 I 451098 I N I~~

2 I 93 (22)

~~ ____~

073 Process Radiation Monitoring 2.4.6 4.7 451110 M 2 1C') (25) 078 Instrument Air A2.01 2.9 451097 M 2 9F (21)

CCNPP LOI-2206 Retake Exam Data Tier 2 / Group 2 - Sr. Reactor Operator Cognitive E/APE # / Name / Safety Function K/A Topics Imp

  1. -TypVision e*I D --

015 Nuclear Instrumentation A2.04 3.8 451079 N 3 85 10) 045 Main Turbine Generator A2.17 2.9 425257 B 2 95 20) 072 Area Radiation Monitoring 2.2.37 4.6 451073 N 2 79 (4)

A Generic Knowledge & Abilities K/A Imp Vision Cognitive #

Category Topics # ID Type Level RO 2.1.3 3.7 450870 N 1 I9 RO 2.1.17 3.9 426067 B 1 3 Conduct of Ops RO 2.1.44 3.9 450934 N 1 14 SRO 2.1.20 4.6 445189 0 1 94 (19)

SRO 2.1.40 3.9 420627 B 1 7( (1)

RO 2.2.1 4.5 425936 B 2 32 Equipment Control RO 2.2.17 2.6 451170 N 1 34 SRO 2.2.43 3.3 451099 N 1 9E (23)

~-

RO 2.3.4 3.2 417947 B 1 70 RO 2.3.11 3.8 420605 B 1 73 Radiation Control RO 2.3.14 3.7 450890 M 2 31 SRO 2.3.6 3.8 Q51080 N 1 8 + (9)

SRO 2.3.15 3.1 424714 B 2 8t (11)

RO 2.4.3 3.7 424951 B 1 30 RO 2.4.5 3.7 419570 B 2 74 Emergency procedures / Plan SRO 2.4.11 4.2 Q51095 N 2 9 (17)

SRO 2.4.45 4.3 451090 N 3 9tr (15)

CCNPP LOI-2206 Retake Exam Data

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Parameter I Reactor Operator Test 1 Sr. Reactor Operator Test I Bank Questions 43 (!j7O/o) 8 (32%)

(Maximum of 75%)

Modified Questions 8 (11~0) 3 (12%)

New Questions (Minimum of 10 questions - 8 RO, 2 24 (32%) 14 (56%)

Memory 30 (40%) 7 (28%)

I Comprehension / Analysis 45 (60%) 18 (72%)

(50 - 60% for RO exam)

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Modified Questions I Modified Question # I Original Question #

I Q50992 I 414583 450770 I 420383 QS065 1 I 419256 450930 I 424994 450993 450990 451016 420397 451110 428787 451097 450364 441651 441134 Q50890 442268 Q51150 420290

CCNPP LOI-2206 Retake Exam Data Key to symbols / abbreviations:

Type:

B = Bank Question M = Modified Question N = New Question Cognitive Level:

1 = Fundamental knowledge or simple memory (stpts, definitions, facts) 0 2 = Comprehension (recognition of system interactions) 0 3 = Analysis / Synthesis / Application (use of info to predict an event or outcome or to solve a problem)

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