ML15167A545
| ML15167A545 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/05/2015 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Luminant Generation Co |
| References | |
| 50-445/OL-15, 50-446/OL-15 | |
| Download: ML15167A545 (26) | |
Text
ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:Comanche Peak Date of Exam:June 8, 2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4
- 1 3 3 3 3 3 3 18 3 3 6
- 1. Emergency Abnormal 2 1 1 2 N/A 2 2 N/A 1 9 2 2 4 Plant Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 1 4 2 3 3 2 2 2 3 3 1 3 28 3 2 5 2.
2 1 1 1 1 1 1 1 1 1 1 0 10 0 2 1 3 Plant Systems Tier Totals 5 3 4 4 3 3 3 4 4 2 3 38 5 3 8 1 2 3 4 1 2 3 4
- 3. Generic Knowledge and Abilities 10 7 Categories 3 2 2 3 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 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).
Note: 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.
Note: 3. Systems/evolutions 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 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.
Note: 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.
Note: 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.
Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
Note: 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.
Note: 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 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.
Note: 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.
ES-401, 21 of 33
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2
- 04. Ability to prioritize and interpret the significance of each 39 000007 Reactor Trip - Stabilization - Recovery / 1 annunciator or alarm.
4.1 1 45 0
40 000008 Pressurizer Vapor Space Accident / 3 RCP tripping requirements 4.2 1 4
0 41 000009 Small Break LOCA / 3 S/Gs 3.0 1 3
0 42 000011 Large Break LOCA / 3 Significance of charging pump operation 3.3 1 5
000015 RCP Malfunctions / 4 0 43 Consequences of an RCPS failure 3.7 1 000017 RCP Malfunctions (Loss of RC Flow) / 4 2 0
55 000022 Loss of Rx Coolant Makeup / 2 Relationship between charging flow and PZR level 3.0 1 3
0 44 000025 Loss of RHR System / 4 Service water or closed cooling water pumps 2.7 1 3
0 The CCWS surge tank, including level control and level alarms, 45 000026 Loss of Component Cooling Water / 8 and radiation alarm 3.1 1 5
000027 Pressurizer Pressure Control System 0 46 Controllers and positioners 2.6 1 Malfunction / 3 3 Ability to interpret control room indications to verify the status and 02.
47 000029 ATWS / 1 operation of a system, and understand how operator actions and 4.2 1 44 directives affect plant and system conditions.
0 48 000038 Steam Gen. Tube Rupture / 3 Criteria for securing/throttling ECCS 4.1 1 9
000040 Steam Line Rupture - Excessive Heat Transfer 0 Occurrence and location of a steam line rupture from pressure 49 and flow indications 4.2
/4 1 1
WE12 Uncontrolled Depressurization of all Steam Generators / 4 0
50 000054 (CE/E06) Loss of Main Feedwater / 4 AFW controls, including the use of alternate AFW sources 4.5 1 1
0 Instruments and controls operable with only dc battery power 51 000055 Station Blackout / 6 available 3.7 1 4
0 52 000056 Loss of Off-site Power / 6 CCW pump 3.3 1 9
000057 Loss of Vital AC Inst. Bus / 6 0 0
53 000058 Loss of DC Power / 6 Battery charger equipment and instrumentation 2.8 1 1
000062 Loss of Nuclear Svc Water / 4 0
- 01. Knowledge of the purpose and function of major system 54 000065 Loss of Instrument Air / 8 components and controls.
4.1 1 28 W/E04 LOCA Outside Containment / 3 0 0 Manipulation of controls required to obtain desired operating 56 W/E11 Loss of Emergency Coolant Recirc. / 4 results during abnormal, and emergency situations 3.8 1 3
BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0
Secondary Heat Sink / 4 000077 Generator Voltage and Electric 0
Grid Disturbances / 6 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 ES-401, 22 of 33
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 Knowledge of the parameters and logic used to assess the 04.
57 000003 Dropped Control Rod / 1 status of safety functions, such as reactivity control, core cooling 4.0 1 21 and heat removal reactor coolant system integrity containment Stuck or inoperable rod from in-core and ex-core NIS, in-core or 58 000005 Inoperable/Stuck Control Rod / 1 01 loop temperature measurements 3.3 1 59 000024 Emergency Boration / 1 02 Actions contained in EOP for emergency boration 4.2 1 000028 Pressurizer Level Malfunction / 2 0 000032 Loss of Source Range NI / 7 0 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 0 Comparison of makeup flow and letdown flow for various modes 61 000037 Steam Generator Tube Leak / 3 03 of operation 3.1 1 62 000051 Loss of Condenser Vacuum / 4 02 Conditions requiring reactor and/or turbine trip 3.9 1 000059 Accidental Liquid RadWaste Rel. / 9 0 63 000060 Accidental Gaseous Radwaste Rel. / 9 02 Auxiliary building ventilation system 2.7 1 000061 ARM System Alarms / 7 0 64 000067 Plant Fire On-site / 8 01 Fire classifications, by type 2.9 1 65 000068 Control Room Evac. / 8 03 S/G level 4.1 1 000069 Loss of CTMT Integrity / 5 0
W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 W/E06 Degraded Core Cooling / 4 0 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9 0 W/E01 Rediagnosis / 3 0
W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0 W/E15 Containment Flooding / 5 0 W/E16 High Containment Radiation / 9 0 60 W/E03 LOCA Cooldown - Depress. / 4 02 Operating behavior characteristics of the facility 3.7 1 W/E09 Natural Circulation Operations / 4 0
W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 W/E08 RCS Overcooling - PTS / 4 0 K/A Category Totals: 1 1 2 2 2 1 Group Point Total: 9 ES-401, 23 of 33
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 Effects of RCP coastdown on RCS parameters; RCP seals 2.8; 22,1 003 Reactor Coolant Pump 02 02 and seal water supply 2
2.7 0 1 3.3; 2,23 004 Chemical and Volume Control Charging pumps; Inadvertent boration/dilution 2 3 0 3.9 0 0 Refueling operations; Detection of and response to 3.2; 27,3 005 Residual Heat Removal presence of water in RHR emergency sump 2
7 5 3.3 1 0 3.8; 28,4 006 Emergency Core Cooling Safety Injection valve interlocks; Cooling water systems 2 7 4 3.8 0
5 007 Pressurizer Relief/Quench Tank RCS 3.0 1 3
0 6 008 Component Cooling Water High/low CCW temperature 3.0 1 3
0 7 010 Pressurizer Pressure Control RPS 4.0 1 2
0 01. Trip setpoint adjustment; Ability to explain and apply 2.9; 24,8 012 Reactor Protection system limits and precautions.
2 1 32 3.8 013 Engineered Safety Features 0 9 Safety system logic and reliability 2.9 1 Actuation 2 0
10 022 Containment Cooling CCS fans 3.6 1 1
025 Ice Condenser 0 0
11 026 Containment Spray Cooling water 4.1 1 2
0 12 039 Main and Reheat Steam Condenser steam dump 3.1 1 6
0 13 059 Main Feedwater Programmed levels of the S/G 2.9 1 2
0 0 4.2; 25,14 061 Auxiliary/Emergency Feedwater S/G; Pumps 2 2 2 2.6 0
15 062 AC Electrical Distribution Major system loads 3.3 1 1
Ability to interpret control room indications to verify the 02.
16 063 DC Electrical Distribution status and operation of a system, and understand how 4.2 1 44 operator actions and directives affect plant and system 0 0 Starting air system; Operating unloaded, lightly loaded, and 3.4; 26,17 064 Emergency Diesel Generator highly loaded time limit 2
5 6 2.9 0
18 073 Process Radiation Monitoring Release termination when radiation exceeds setpoint 4.0 1 1
0 19 076 Service Water Emergency heat loads 3.7 1 2
01.
20 078 Instrument Air Knowledge of system purpose and/or function. 3.9 1 27 0
21 103 Containment Personnel access hatch and emergency access hatch 2.5 1 4
0 K/A Category Totals: 4 2 3 3 2 2 2 3 3 1 3 Group Point Total: 28 ES-401, Page 24 of 33
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 1
29 001 Control Rod Drive 1 Determination of SDM 3.5 1 0
30 002 Reactor Coolant 4 RCS vent valves 2.5 1 0
31 011 Pressurizer Level Control 2 PZR heaters 3.1 1 0
32 014 Rod Position Indication 2 RPIS independent of demand position 2.8 1 0
33 015 Nuclear Instrumentation 7 Permissives 3.7 1 0
34 016 Non-nuclear Instrumentation 6 AFW System 3.6 1 0 Indications of normal, natural, and interrupted circulation of 35 017 In-core Temperature Monitor 1 RCS 3.6 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 0
Control 029 Containment Purge 0 0
36 033 Spent Fuel Pool Cooling 3 Abnormal spent fuel pool water level or loss of water level 3.1 1 034 Fuel Handling Equipment 0 035 Steam Generator 0 0
37 041 Steam Dump/Turbine Bypass Control 2 RCS 3.8 1 045 Main Turbine Generator 0 055 Condenser Air Removal 0 056 Condensate 0 068 Liquid Radwaste 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 0
38 086 Fire Protection 2 Fire water storage tank level 3.0 1 K/A Category Totals: 1 1 1 1 1 1 1 1 1 1 0 Group Point Total: 10 ES-401, Page 25 of 33
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000007 Reactor Trip - Stabilization - Recovery / 1 0 000008 Pressurizer Vapor Space Accident / 3 0 000009 Small Break LOCA / 3 0 1
76 000011 Large Break LOCA / 3 Verification of adequate core cooling 4.7 1 0
000015 RCP Malfunctions / 4 0
000017 RCP Malfunctions (Loss of RC Flow) / 4 000022 Loss of Rx Coolant Makeup / 2 0 000025 Loss of RHR System / 4 0 01.
78 000026 Loss of Component Cooling Water / 8 Ability to interpret and execute procedure steps. 4.6 1 20 000027 Pressurizer Pressure Control System 0
Malfunction / 3 000029 ATWS / 1 0 000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture - Excessive Heat Transfer
/4 0
WE12 Uncontrolled Depressurization of all Steam Generators / 4 000054 (CE/E06) Loss of Main Feedwater / 4 0 04.
79 000055 Station Blackout / 6 Knowledge of EOP mitigation strategies. 4.7 1 06 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0 000058 Loss of DC Power / 6 0
- 04. Knowledge of local auxiliary operator tasks during an emergency 80 000062 Loss of Nuclear Svc Water / 4 and the resultant operational effects.
4.0 1 35 000065 Loss of Instrument Air / 8 0 W/E04 LOCA Outside Containment / 3 0 W/E11 Loss of Emergency Coolant Recirc. / 4 0 BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0 Facility conditions and selection of appropriate procedures 77 during abnormal and emergency operations 4.4 1 Secondary Heat Sink / 4 1 000077 Generator Voltage and Electric 0 81 Generator frequency limitations 3.5 1 Grid Disturbances / 6 6 K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 ES-401, 22 of 33
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 0 000005 Inoperable/Stuck Control Rod / 1 0
- 04. Knowledge of the operational implications of EOP warnings, 82 000024 Emergency Boration / 1 cautions, and notes.
4.3 1 20 000028 Pressurizer Level Malfunction / 2 0 000032 Loss of Source Range NI / 7 0 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 0 83 000037 Steam Generator Tube Leak / 3 11 When to isolate one or more S/Gs 3.8 1 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 04.
84 000067 Plant Fire On-site / 8 Knowledge of abnormal condition procedures. 4.2 1 11 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0
W/E14 High Containment Pressure / 5 The effect of turbine bypass valve operation on RCS 85 000074 Inad. Core Cooling / 4 08 temperature and pressure 4.6 W/E06 Degraded Core Cooling / 4 1 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9 0 W/E01 Rediagnosis / 3 0
W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0 W/E15 Containment Flooding / 5 0 W/E16 High Containment Radiation / 9 0 W/E03 LOCA Cooldown - Depress. / 4 0 W/E09 Natural Circulation Operations / 4 0
W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 W/E08 RCS Overcooling - PTS / 4 0 K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401, 23 of 33
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0 Ability to evaluate plant performance and make operational 01.
86 004 Chemical and Volume Control judgments based on operating characteristics, reactor 4.7 1 07 behavior, and instrument interpretation.
005 Residual Heat Removal 0 006 Emergency Core Cooling 0 0
87 007 Pressurizer Relief/Quench Tank Stuck-open PORV or code safety 4.2 1 1
008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 012 Reactor Protection 0 013 Engineered Safety Features 0
Actuation 022 Containment Cooling 0 025 Ice Condenser 0 0
88 026 Containment Spray Failure of chemical addition tanks to inject 4.1 1 5
039 Main and Reheat Steam 0 059 Main Feedwater 0 061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0 063 DC Electrical Distribution 0 064 Emergency Diesel Generator 0 073 Process Radiation Monitoring 0 076 Service Water 0 0
89 078 Instrument Air Air dryer and filter malfunctions 2.9 1 1
- 04. Knowledge of the emergency action level thresholds and 90 103 Containment classifications.
4.6 1 41 0
K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 24 of 33
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0 002 Reactor Coolant 0 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 0
Control 029 Containment Purge 0 033 Spent Fuel Pool Cooling 0 034 Fuel Handling Equipment 0 0
92 035 Steam Generator 1 Faulted or ruptured S/Gs 4.6 1 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0 055 Condenser Air Removal 0 0
91 056 Condensate Condenser tube leakage 2.5 1 5
068 Liquid Radwaste 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 02.
93 086 Fire Protection Knowledge of conditions and limitations in the facility license. 4.5 1 38 K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 25 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Comanche Peak Date of Exam:June 8, 2015 RO SRO-Only Category K/A # Topic Q# IR # IR #
Ability to use procedures related to shift staffing, such as minimum crew complement, overtime 66 2.1. 05 limitations, etc. 2.9 1 67 2.1. 08 Ability to coordinate personnel activities outside the control room. 3.4 1 68 1. 2.1. 13 Knowledge of facility requirements for controlling vital/controlled access. 2.5 1 Conduct of 94 Operations 2.1. 37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. 4.6 1 2.1.
2.1.
Subtotal 3 1 69 2.2. 12 Knowledge of surveillance procedures. 3.7 1 70 2.2. 13 Knowledge of tagging and clearance procedures. 4.1 1 95 2.2. 05 Knowledge of the process for making design or operating changes to the facility. 3.2 1 2.
Equipment Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety 96 2.2. 25 limits. 4.2 1 Control 2.2.
2.2.
Subtotal 2 2 71 2.3. 07 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5 1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable 72 2.3. 15 survey instruments, personnel monitoring equipment, etc. 2.9 1 73 2.3. 06 Ability to approve release permits. 3.8 1 3.
Radiation Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or 97 2.3. 14 emergency conditions or activities. 3.8 1 Control 98 2.3.
2.3.
Subtotal 2 2 74 2.4. 12 Knowledge of general operating crew responsibilities during emergency operations. 4.0 1 75 2.4. 22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. 3.6 1 99 4. 2.4. 46 Ability to verify that the alarms are consistent with the plant conditions. 4.2 1 Emergency 100 Procedures / 2.4. 18 Knowledge of the specific bases for EOPs. 4.0 1 Plan 2.4. 32 Knowledge of operator response to loss of all annunciators. 4.0 1 2.4.
Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33
ES-401 Record of Rejected K/As Form ES-401-4 Tier/Group Randomly Reason for Rejection Selected K/A RO Exam 1/1 015/017 AK1.02 Question 43 Reactor Coolant Pump Malfunctions: Could not write a discriminating question based on the content of the original K/A. Replaced K/A 015/017 AK1.05 with K/A 015/017 AK1.02 1/1 038 K3.09 Question 48 Steam Generator Tube Rupture: Could not write a discriminating question which did not overlap the operational exam. Replaced K/A 038 K3.05 with K/A 038 K3.09.
1/1 022 AK1.03 Question 55 LOCA Outside Containment: Original K/A resulted in question overlap when attempting to develop operationally valid question. Randomly replaced K/A W/E04 AK1.03 with 022 AK1.03.
1/1 W/E11 EK3.03 Question 56 Generator Voltage and Electric Grid Distrubances: Unable to write operationally valid question for original K/A. Randomly replaced K/A 077 AK3.02 with W/E011 EK3.03.
1/2 W/E03 EA1.02 Question 60 Loss of Intermediate Range NI: Unable to write discriminating question regarding a 2 position switch. Replaced K/A 033 AA1.02 with K/A W/E03 EA1.02.
2/1 022 A4.01 Question 10 Loss of CCS pump: Unable to write an operationally valid question based on CPNPP design for the original K/A.
Replaced K/A 022 A2.06 with K/A 022 A4.01.
2/1 063 G.2.2.44 Question 16 DC Electrical Distribution: Unable to write discriminating question for original K/A. Replaced K/A 063 A4.03 with K/A 063 G.2.2.44.
2/1 064 A2.06 Question 17 Emergency Diesel Generator: Replaced K/A as overlap was identified to the operating examination. Randomly replaced K/A 064.A2.19 with K/A 064 A2.06.
2/1 006 K4.17 Question 28 Ability to monitor ECCS Valve lineups: Tier 2 Group 1 also sampled ECCS with A3.04, which resulted in over sampling A3 for ECCS. Replaced K/A 006 A3.06 with K/A 006 K4.17.
2/2 017 A3.01 Question 35 Monitor the ITM system: Task not performed by operators; unable to write an operationally valid question for the original K/A. Replaced K/A 017 A3.02 with K/A 017 A3.01.
2/2 033 A2.03 Question 36 Spent Fuel Pool Cooling: Unable to write operationally valid question for the original K/A. Randomly replaced K/A 033 G.2.4.08 with K/A 033 A2.03.
ES-401 Record of Rejected K/As Form ES-401-4 2/2 041 K3.02 Question 37 Steam Dump System: Could not write an acceptable question for the original K/A. Replace K/A 041 K3.01 with K/A 041 K3.02.
2/2 086 A1.02 Question 38 Fire Protection, Fire Dampers: Could not write a discriminatory, operationally valid question for the original K/A.
Replaced K/A 086 A1.04 with K/A 086 A1.02.
3 G.2.4.46 Question 73 Unable to write satisfactory RO level question to original K/A.
Replaced K/A G.2.3.11 with K/A G.2.4.46.
SRO Exam 1/1 W/E05 AA2.01 Question 77 Loss of RHR System: Unable to write a satisfactory SRO level question to the original K/A. Replaced K/A 025 AA2.04 with K/A W/E05 AA2.01.
1/1 026 G.2.1.20 Question 78 Loss of Component Cooling Water: Original K/A is not allowed for selection in Tier 1 and Tier 2. Replaced K/A 026 G.2.1.45 with K/A 026 G.2.1.20.
1/1 055 G.2.4.06 Question 79 Loss of DC Power: Original K/A is not allowed for selection in Tier 1 and Tier 2. Replaced K/A 058 G2.2.23 with K/A 055 G.2.4.06.
1/1 062 G.2.4.35 Question 80 Loss of Instrument Air local operator actions: Original sample plan resulted in Instrument Air system and malfunctions being over sampled (five occurrences). Replaced K/A 065 G.2.4.35 with K/A 062 G.2.4.35.
1/2 067 G.2.4.11 Question 84 Knowledge of Fire Protection Procedures: Original K/A is not allowed for selection in Tier 1 and Tier 2. Replaced K/A 067 G.2.4.25 with K/A 067 G.2.4.11.
1/2 074 EA2.08 Question 85 Inadequate Core Cooling: Unable to write operationally valid question for original selected K/A. Replaced K/A 074 EA2.01 with randomly selected K/A from same area K/A 074 EA2.08.
2/1 004 G.2.1.7 Question 86 Chemical and Volume Control System: Original K/A is not allowed for selection in Tier 1 and Tier 2. Replaced K/A 004 G.2.1.45 with K/A 004 G.2.1.7.
2/1 026 A2.05 Question 88 AC Electrical Distribution: Unable to write operationally valid question for original selected K/A. Replaced K/A 062 A2.12 with randomly selected K/A 026 A2.05.
2/1 103 G.2.4.41 Question 90 Containment Generic Radiological procedures: Original K/A is not allowed for selection in Tier 1 and Tier 2. Replaced K/A 103 G2.3.13 with K/A 103 G.2.4.41.
ES-401 Record of Rejected K/As Form ES-401-4 2/2 035 A2.01 Question 92 Waste Gas Disposal (Generic): Original K/A is not allowed for selection in Tier 1 and Tier 2. Replaced K/A 071 G2.3.11 with K/A 035 A2.01.
2/2 086 G.2.2.38 Question 93 Fire Protection (Generic): Original K/A is not allowed for selection in Tier 1 and Tier 2. Replaced K/A 086 G2.4.26 with K/A 086 G.2.2.38.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: CPNPP Units 1 and 2 Date of Examination: June 2015 Examination Level: RO SRO Operating Test Number: NRC Administrative Topic Type Code* Describe activity to be performed (See Note) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes Conduct of Operations of plant operation. (4.3).
(RA1) M,R JPM: Perform Power Change Worksheet Calculation. (RO1302B) 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo Conduct of Operations operation, maintenance of active license (RA2) N,R status, 10CFR55, etc. (3.3).
JPM: Determine RO License Status. (RO5001) 2.2.12 Knowledge of surveillance procedures. (3.7).
Equipment Control (RA3) D,R JPM: Perform Axial Flux Difference Surveillance.
(RO1808) 2.3.11 Ability to control radiation releases. (3.8).
Radiation Control (RA4) M,R JPM: Determine Maximum Allowable Venting Time. (RO7030A)
Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
ES-301-1 CPNPP 2015 NRC RO Administratives Topics Outline
ES-301 Administrative Topics Outline Form ES-301-1 Task Summary RA1 The applicant will determine boron/dilution requirements to lower power from 100% to 50% equilibrium per IPO-003A, Power Operations, Attachment 3, Power Change Worksheet. The calculations include Power Defect, Rod Worth, Xenon Worth, change in Boron concentration and boration/dilution quantity. The critical steps are to determine the reactivity change for power defect, the rod position change, equilibrium xenon, and the total reactivity change for these parameters, the required change in boron concentration, and the amount of boration needed.
This is a modified bank JPM.
RA2 The applicant will be presented with a detailed record (in table form) of watch standing and other activities performed by 3 individual Reactor Operators over a period of 4 to 6 weeks. The applicant will be required to analyze the work records of these three operators, and apply the guidance of ODA-315, Licensed Operator Maintenance Tracking, to evaluate and determine if the RO license status is active or inactive for each of the three operators. The critical steps are to determine that the RO licenses for two of the three operators are NOT active.
This is a new JPM.
RA3 The applicant will be presented with Power Range Nuclear Instrument Axial Flux Difference data and will perform a manual Axial Flux Difference calculation using OPT-403, Axial Flux Difference. The critical steps are to determine whether at least 3 of 4 PR FLUX channels are within the Acceptable Operation region of NUC-204-6, Axial Flux Difference as a Function of Rated Thermal Power. This is a direct from bank JPM.
RA4 The applicant will determine the maximum allowable venting time for venting the reactor vessel using FRI-0.3A, Response to Voids in Reactor Vessel, Attachment
- 5. Critical steps include various stages of the calculation, including the final determination of allowable venting time. This is a modified bank JPM.
ES-301-1 CPNPP 2015 NRC RO Administratives Topics Outline
ES-301 Administrative Topics Outline Form ES-301-1 Facility: CPNPP Units 1 and 2 Date of Examination: June 2015 Examination Level: RO SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (See Note) Code*
2.1.25 Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc. (4.2).
(SA1) D,R JPM: Loss of RHR Time / Tech Specs. (SO1101) 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, Conduct of Operations such as medical requirements, no-solo (SA2) N,R operation, maintenance of active license status, 10CFR55, etc. (3.8).
JPM: Determine SRO License Status.
2.2.23 Ability to track Technical Specification Equipment Control limiting conditions for operations. (4.6).
(SA3) M,R JPM: Complete Manual LCOAR for Motor Driven AFW Pump. (SO1024D) 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
Radiation Control (3.7).
(SA4) D,R JPM: Select Volunteer for Emergency Exposure.
(SO1142A) 2.4.44 Knowledge of emergency plan protective Emergency action recommendations. (4.4).
Procedures/Plan M,P,R (SA5) JPM: Determine Protective Action Recommendations. (SO1140A)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
ES-301-1 CPNPP 2015 NRC SRO Administrative Topics Outline
ES-301 Administrative Topics Outline Form ES-301-1 Task Summary SA1 The applicant is presented with Loss of RHR conditions and then uses ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure to determine Time to Saturation, Time to Core Uncovery, and Containment Closure Time. The critical steps are to determine Time to Saturation, Time to Core Uncovery, Containment Closure Time, and identify any Technical Specification required actions associated with the loss of the standby RHR pump. This is a direct from bank JPM.
SA2 The applicant is presented with a detailed record (in table form) of watch standing and other activities performed by 3 individual Senior Reactor Operators over a period of 4 to 6 weeks. The applicant will be required to analyze the work records of these three operators, and apply the guidance of ODA-315, Licensed Operator Maintenance Tracking, to evaluate and determine if the SRO license status is active or inactive for each of the three operators. The critical steps are to determine that the SRO licenses for two of the three operators are NOT active.
This is a new JPM.
SA3 The applicant will be presented with conditions involving a Motor Driven AFW pump which is removed from service and will use ODA-308, LCO Tracking Program, and Technical Specification 3.7.5 Auxiliary Feedwater System, to complete a Manual LCOAR. The critical steps consist of various determinations on the Manual LCOAR form, including correct information in required fields to pass the JPM. This is a modified bank JPM.
SA4 The applicant is given accident conditions involving the need for a volunteer to attempt a lifesaving activity. Using the guidance in EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, the applicant will evaluate a series of potential volunteers and select the preferred volunteer from this list.
The critical steps are evaluation and elimination of volunteers who do not meet the criteria required for the activity, and then final selection of the preferred volunteer. This is a direct from bank JPM.
ES-301-1 CPNPP 2015 NRC SRO Administrative Topics Outline
ES-301 Administrative Topics Outline Form ES-301-1 Task Summary SA5 The applicant will determine the appropriate Protective Action Recommendations for an emergency. This JPM is designated as a "P" because a form of it was used on the 2013 NRC exam. This JPM will be modified to include different conditions, including severity and meteorological parameters. The "random selection" aspect was performed due to limited topics available for SRO A.4 category, the fact that this JPM meets the requirements of NUREG-1021, and to avoid overlap with the Audit Exam. The critical steps will include several determinations the SRO must make, such as release duration, core damage, and identification of affected sectors. This is a modified bank JPM.
ES-301-1 CPNPP 2015 NRC SRO Administrative Topics Outline
ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: CPNPP Units 1 and 2 Date of Examination: June 2015 Exam Level: RO SRO(I) SRO (U) Operating Test Number: NRC Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety System / JPM Title Type Code*
Function 001 -Control Rod Drive System (RO1030) D,S 1 S-1 Respond to Control Rods Below Insertion Limit 006 -Emergency Core Cooling System (RO1506D) A,EN,L,M,S 2 S-2 Transfer ECCS to Cold Leg Recirculation 006 -Emergency Core Cooling System (RO1511) A,EN,L,N,S 3 S-3 Isolate SI Accumulators Following a LOCA 005 -Residual Heat Removal System (RO1402) L,N,S 4P S-4 Alternate Residual Heat Removal Trains 045 -Main Turbine Generator System (RO3149) L,N,S 4S S-5 Roll Main Turbine to 1800 RPM (RO Only) 022 -Containment Cooling System (RO2101A) A,N,S 5 S-6 Alternate Containment Recirculation Units(CACRS) 064 -Emergency Diesel Generator System (RO4302D) A,D,S 6 S-7 Load Emergency Diesel Generator 008 -Component Cooling Water System (RO3603C) M,S 8 S-8 Rotate Component Cooling Water Pumps In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 007 -Reactor Trip (AO6439B) D,E,R 1 P-1 Trip the Reactor and Stop MG Sets 068 -Control Room Evacuation (AO6413B) A,M,E,L,R 8 P-2 Respond to a Fire in the Control Room or Cable Spreading Room, NEO #2 Actions 062 -AC Electrical Distribution System (AO4204D) N,E 6 P-3 Transfer Inverter IVuPC1 from Bypass to Normal Page 1 of 4 ES-301-2 CPNPP 2015 RO & SRO System JPM Outline
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 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / > 1(control room system)
(L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3 <3 / < 2 (randomly selected)
(R)CA >1 / >1 / >1 (S)imulator NRC JPM Examination Summary Description S-1 Following a turbine runback, due to a trip of a Heater Drain Pump from 100%
power, the applicant will determine that control rods are below the required rod insertion limit by using ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Section 4.0, Heater Drain Pump Trip. This JPM, requiries the applicant to manually determine the required boration using the Reactivity Briefing Sheet. The critical steps include determination of how much boration is needed, and the various control board manipulations needed to perform the boration. This is a direct from bank JPM under Control Rod Drive System - Reactivity Control Safety Function. (K/A 001.A4.05 - IR 3.7 / 3.7)
S-2 The applicant will be required to use EOS-1.3A, Transfer to Cold Leg Recirculation following a Large Break LOCA. This is an Alternate Path JPM because one of the RHR pump suction valves will NOT open, and the applicant will need to perform alternate steps for system realignment, including shutting off one pump and ensuring the other RHR pump is running. The critical steps include recognition of one RHR pump suction valve failing to open, and various control board manipulations needed for realignment in order to achieve cold leg recirculation.
This is a PRA significant action. This is a modified from bank JPM under the Emergency Core Cooling System - Reactor System Inventory Control Safety Function. (K/A 006.A4.05 - IR 3.7 / 3.6)
Page 2 of 4 ES-301-2 CPNPP 2015 RO & SRO System JPM Outline
ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S-3 Using EOS-1.2A, Post LOCA Cooldown and Depressurization, the applicant will be required to continue with Step 26 for determining if SI accumulators should be isolated and to isolate the accumulators. This is an Alternate Path JPM and requires the applicant to determine that one of the accumulator injection valves will NOT close. This will require the applicant to vent off this accumulator to minimize the consequences of undesired injection, since the accumulator cannot be isolated. The critical steps include restoring power to the injection valves, operation of the accumulator injection valves, and venting of the accumulator that cannot be isolated. This is a new JPM under the Emergency Core Cooling System
- Reactor Pressure Control Safety Function. (K/A 006.A4.02 - IR 4.0 / 3.8)
S-4 The applicant will use SOP-102A, Residual Heat Removal System, Section 5.6 Alternating RHR Trains in MODE 5, 6, or Defueled to perform the task. The critical steps will include various control board manipulations required for making the swap such as starting and stopping RHR pumps, operation of control valves, and requirements for temperature control. This is a new JPM under the Residual Heat Removal System - Primary System Heat Removal from Reactor Core Safety Function. (K/A 005.A4.01 - IR 3.6 / 3.4)
S-5 The applicant will use IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator, beginning at Step 5.1.18 and completing Step 5.1.21. This involves setting up the turbine control for rolling the turbine to 1800 RPM. The Overspeed Trip test will NOT be required. The critical steps include setting up the turbine control panel to open the HP and LP stop valves, an interim step of holding at 500 RPM, placing of bearing lift oil pumps to AUTO, and then continuing to 1800 RPM where the JPM will terminate. This is a new JPM under the Main Turbine Generator System - Secondary System Heat Removal from Reactor Core Safety Function. RO Only.
(K/A 045.A4.02 - IR 2.7 / 2.6)
S-6 With a Containment Vent in progress, the applicant is directed to alternate Containment Recirculation Units using SOP-801A, Containment Ventilation System, Section 5.1.3. During the swap Containment Air Gaseous radiation monitor goes into Alert. This is an alternate path JPM requiring action to manually initiate isolation of the Containment Vent. The critical steps include starting the desired cooling unit and manual operation of several valves for isolation of the Containment Vent evolution. This is a new JPM under the Containment Cooling System - Containment Integrity Safety Function. (K/A 022.A4.01 - IR 3.6 / 3.6)
S-7 With OPT-214A, Diesel Generator Operability Test in progress and following a fast start of Diesel Generator 1-01, the applicant is to continue with the surveillance.
This involves beginning to load the diesel generator. This is an Alternate Path JPM. When loading is raised to approximately 2.2 MW, the Station Service Water Pump 1-01 will trip. This will result in the diesel generator running loaded with no cooling water. The applicant is required to shut down the diesel generator. The critical steps are proper loading of the diesel generator and shutting down the diesel generator to prevent equipment damage. This is a direct from bank JPM under the Emergency Diesel Generator System - Electrical Safety Function.
(K/A 064.A4.06 - IR 3.9 / 3.9)
Page 3 of 4 ES-301-2 CPNPP 2015 RO & SRO System JPM Outline
ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S-8 The applicant is directed to swap Component Cooling Water Pumps from Train A to Train B, using SOP-502A, Component Cooling Water System. The critical steps include establishing required system flow, control board manipulations required for the swap, starting the idle pump, and shutting down the pump to be idled. This is a modified from bank JPM under the Component Cooling Water System - Plant Service Systems Safety Function.
(K/A 008.A4.01 - IR 3.3 / 3.1)
P-1 With an Anticipated Transient Without Trip in progress on Unit 1, the applicant is required to locally trip the Unit 1 reactor, and to stop both Rod Drive Motor Generator Sets, in accordance with FRS-0.1A, Response to Nuclear Power Generator/ATWT, Step 6a RNO. Through a series of simulated operations and examiner cues, the applicant will open RTA and RTB trip breakers as critical steps.
The bypass breakers will not be considered critical steps. When that is complete, the applicant will de-energize both MG Sets by opening associated breakers, each of which is a critical step. This is a PRA significant action. This is a direct from bank JPM under the Reactor Trip System - Reactivity Control Safety Function.
(K/A 007.EA2.02 - IR 4.3 / 4.6)
P-2 During a Control Room evacuation due a fire, the applicant is required to take action to place the plant in control of the operators from outside the control room.
Actions will be performed using ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room, Attachment 4, Nuclear Equipment Operator No.
2 Actions to Achieve Hot Shutdown. The critical steps include starting the Safety Chiller, Isolating RHR from the RWST and controlling AFW flow to the Steam Generators. This is a PRA significant action. This is a modified from bank JPM under the Control Room Evacuation System - Plant Service Systems Safety Function.
(K/A 068.AA1.26 - IR 3.6 / 3.8)
P-3 The applicant will be directed to perform SOP-607A/B, 118 VAC Distribution System and Inverters, Section 5.5.9 Transferring Inverter IVuPC1 from Bypass to Normal Operation. The critical steps will include operating the Static Transfer Switch to make the swap, and aligning the inverter to complete the operation. This is a new JPM under the AC Electrical Distribution System - Electrical Safety Function. (K/A 062.A4.04 - IR 2.6 / 2.7)