ML090790362
| ML090790362 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/06/2009 |
| From: | Brian Larson Operations Branch IV |
| To: | |
| References | |
| 50-275/09-301, 50-323/09-301, DC-2009-02 | |
| Download: ML090790362 (23) | |
Text
02/04/2009 Printed:
ES-401 Facility:
Diablo Canyon Power Plant PWR Examination Outline Form ES-401-2 3
3 3
3 3
3 1
2 2
1 1
2 4
5 5
4 4
5 3
2 3
3 3
2 1
3 2
3 3
1 1
1 1
1 1
1 0
1 1
1 4
3 4
4 4
3 2
3 3
4 4
2 3
3 2
RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*
1.
Emergency Abnormal Plant Evolutions 1
1 2
2 Tier Totals Tier Totals 2.
Plant Systems 1
2 3
4
- 3. Generic Knowledge And Abilities Categories 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.
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.
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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
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:
Date Of Exam:
02/06/2009 28 18 9
27 10 38 10 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).
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' 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.
SRO-Only Points A2 G*
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1
2 3
4 0
0 0
0 0
0 0
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.
6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
N/A N/A Total 0
0 1
02/04/2009 7:52:36 am Rev 1
02/04/2009 KA Topic Printed:
Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 Change in leak rate with change in pressure AK1.02 000008 Pressurizer Vapor Space Accident / 3 Charging pump ammeter EA2.12 000009 Small Break LOCA / 3 Securing of RCPs EA1.03 000011 Large Break LOCA / 3 Relationship between charging flow and PZR level AK1.03 000022 Loss of Rx Coolant Makeup / 2 Pump cavitation AA2.07 000025 Loss of RHR System / 4 Controllers and positioners AK2.03 000027 Pressurizer Pressure Control System Malfunction / 3 Breakers, relays, and disconnects EK2.06 000029 ATWS / 1 Use of steam tables EK1.01 000038 Steam Gen. Tube Rupture / 3 Sensors and detectors AK2.02 000040 Steam Line Rupture - Excessive Heat Transfer / 4 AFW controls, including the use of alternate AFW sources AA1.01 000054 Loss of Main Feedwater / 4 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
2.1.31 000055 Station Blackout / 6 1
02/04/2009 7:52:00 am
02/04/2009 KA Topic Printed:
Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 T-cold and T-hot indicators (wide range)
AA2.19 000056 Loss of Off-site Power / 6 Knowledge of operational implications of EOP warnings, cautions, and notes.
2.4.20 000057 Loss of Vital AC Inst. Bus / 6 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector AA1.02 000058 Loss of DC Power / 6 The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS AK3.02 000062 Loss of Nuclear Svc Water / 4 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
2.4.47 000065 Loss of Instrument Air / 8 RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated EK3.4 W/E04 LOCA Outside Containment / 3 Normal, abnormal and emergency operating procedures associated with Loss of Secondary Heat Sink EK3.2 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink
/ 4 2
02/04/2009 7:52:00 am
02/04/2009 KA Topic Printed:
Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 Startup termination on source-range loss AK3.01 000032 Loss of Source Range NI / 7 Equivalency between source-range, intermediate-range, and power-range channel readings AA2.01 000033 Loss of Intermediate Range NI / 7 SDM AK1.02 000036 Fuel Handling Accident / 8 Knowledge of limiting conditions for operations and safety limits.
2.2.22 000059 Accidental Liquid RadWaste Rel. / 9 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
2.4.50 000060 Accidental Gaseous Radwaste Rel. / 9 Tripping RCPs EK3.04 000074 Inad. Core Cooling / 4 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility EK2.2 W/E08 RCS Overcooling - PTS / 4 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EA1.1 W/E13 Steam Generator Over-pressure / 4 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility EK2.2 W/E14 Loss of CTMT Integrity / 5 1
02/04/2009 7:52:07 am
Sys/Evol # / Name 02/04/2009 KA Topic Printed:
ES - 401 Comment Facility:
Diablo Canyon Power Plant KA Plant Systems - Tier 2 / Group 1 PWR RO Examination Outline Form ES-401-2 Containment isolation K1.08 003 Reactor Coolant Pump Ion exchange bypass A3.03 004 Chemical and Volume Control Thermal stress, brittle fracture, pressurized thermal shock K5.11 004 Chemical and Volume Control Need for adequate subcooling K5.02 005 Residual Heat Removal Ability to locate and operate components, including local controls.
2.1.30 006 Emergency Core Cooling Pumps K6.13 006 Emergency Core Cooling Quench tank cooling K4.01 007 Pressurizer Relief/Quench Tank High/low surge tank level A2.02 008 Component Cooling Water CCW pump, including emergency backup K2.02 008 Component Cooling Water PZR spray valve A4.01 010 Pressurizer Pressure Control PZR sprays and heaters K6.03 010 Pressurizer Pressure Control Incorrect channel bypassing A2.03 012 Reactor Protection Knowledge of annunciator alarms, indications, or response procedures.
2.4.31 013 Engineered Safety Features Actuation CPS K1.10 013 Engineered Safety Features Actuation 1
02/04/2009 7:52:16 am
Sys/Evol # / Name 02/04/2009 KA Topic Printed:
ES - 401 Comment Facility:
Diablo Canyon Power Plant KA Plant Systems - Tier 2 / Group 1 PWR RO Examination Outline Form ES-401-2 CCS fans A4.01 022 Containment Cooling Fan motor over-current A2.01 022 Containment Cooling Containment spray pumps K2.01 026 Containment Spray Isolation of the MRSS A3.02 039 Main and Reheat Steam Feedwater control during power increase and decrease A4.03 059 Main Feedwater RCS K3.04 059 Main Feedwater AFW turbine exhaust/drains K1.11 061 Auxiliary/Emergency Feedwater DC system K3.03 062 AC Electrical Distribution Battery capacity as it is affected by discharge rate A1.01 063 DC Electrical Distribution Systems controlled by automatic loader K3.01 064 Emergency Diesel Generator Radiation theory, including sources, types, units, and effects K5.01 073 Process Radiation Monitoring Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
2.4.4 076 Service Water Securing of SAS upon loss of cooling water K4.03 078 Instrument Air 2
02/04/2009 7:52:16 am
Sys/Evol # / Name 02/04/2009 KA Topic Printed:
ES - 401 Comment Facility:
Diablo Canyon Power Plant KA Plant Systems - Tier 2 / Group 1 PWR RO Examination Outline Form ES-401-2 Vacuum breaker protection K4.01 103 Containment 3
02/04/2009 7:52:16 am
Sys/Evol # / Name 02/04/2009 KA Topic Printed:
ES - 401 Comment Facility:
Diablo Canyon Power Plant KA Plant Systems - Tier 2 / Group 2 PWR RO Examination Outline Form ES-401-2 One-line diagram of power supply to M/G sets K2.01 001 Control Rod Drive Movement of the pressure control valve, using manual controller A4.02 011 Pressurizer Level Control Ability to explain and apply system limits and precautions.
2.1.32 014 Rod Position Indication NIS calibration by heat balance A1.01 015 Nuclear Instrumentation Sources of hydrogen within containment K5.03 028 Hydrogen Recombiner and Purge Control Area and ventilation radiation monitoring systems K3.02 033 Spent Fuel Pool Cooling Radiation monitoring systems K6.02 034 Fuel Handling Equipment S/G water level control A3.01 035 Steam Generator Heat sink K4.01 075 Circulating Water IAS K1.01 079 Station Air 1
02/04/2009 7:52:23 am
Facility:
Diablo Canyon Power Plant Generic Category KA KA Topic Comment Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 02/04/2009 Printed:
PWR RO Examination Outline 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
Conduct of Operations 2.1.39 Knowledge of conservative decision making practices.
2 Category Total:
2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
Equipment Control 2.2.6 Knowledge of the process for making changes to procedures.
2.2.13 Knowledge of tagging and clearance procedures.
3 Category Total:
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
Radiation Control 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3 Category Total:
2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.
Emergency Procedures/Plan 2.4.32 Knowledge of operator response to loss of all annunciators.
2 Category Total:
10 Generic Total:
1 02/04/2009 7:52:30 am Rev 1
02/04/2009 Printed:
ES-401 Facility:
Diablo Canyon Power Plant PWR Examination Outline Form ES-401-2 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*
1.
Emergency Abnormal Plant Evolutions 1
1 2
2 Tier Totals Tier Totals 2.
Plant Systems 1
2 3
4
- 3. Generic Knowledge And Abilities Categories 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.
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.
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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
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:
Date Of Exam:
02/06/2009 0
0 0
0 0
0 0
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).
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' 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.
SRO-Only Points A2 G*
3 3
2 2
5 5
3 2
1 1
3 2
1 2
2 1
2 3
4 10 4
6 5
3 8
7 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.
6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
N/A N/A Total 1
5 1
02/04/2009 8:02:22 am Rev 1
02/04/2009 KA Topic Printed:
Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 Occurrence of a reactor trip EA2.06 000007 Reactor Trip - Stabilization - Recovery / 1 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
2.2.36 000026 Loss of Component Cooling Water / 8 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
2.4.4 000055 Station Blackout / 6 Knowledge of EOP mitigation strategies.
2.4.6 000056 Loss of Off-site Power / 6 Generator overheating and the required actions AA2.10 000077 Generator Voltage and Electric Grid Disturbances / 6 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments EA2.2 W/E11 Loss of Emergency Coolant Recirc. / 4 1
02/04/2009 8:01:49 am
02/04/2009 KA Topic Printed:
Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 Knowledge of abnormal condition procedures.
2.4.11 000024 Emergency Boration / 1 Knowledge of conditions and limitations in the facility license.
2.2.38 000076 High Reactor Coolant Activity / 9 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments EA2.2 W/E01 Rediagnosis / 3 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments EA2.2 W/E07 Inad. Core Cooling / 4 1
02/04/2009 8:01:56 am
Sys/Evol # / Name 02/04/2009 KA Topic Printed:
ES - 401 Comment Facility:
Diablo Canyon Power Plant KA Plant Systems - Tier 2 / Group 1 PWR SRO Examination Outline Form ES-401-2 Problems with RCP seals, especially rates of seal leak-off A2.01 003 Reactor Coolant Pump Abnormal pressure in the PRT A2.02 007 Pressurizer Relief/Quench Tank Knowledge of conditions and limitations in the facility license.
2.2.38 012 Reactor Protection Knowledge of conditions and limitations in the facility license.
2.2.38 059 Main Feedwater Loss of dc power A2.03 061 Auxiliary/Emergency Feedwater 1
02/04/2009 8:02:02 am
Sys/Evol # / Name 02/04/2009 KA Topic Printed:
ES - 401 Comment Facility:
Diablo Canyon Power Plant KA Plant Systems - Tier 2 / Group 2 PWR SRO Examination Outline Form ES-401-2 Load limits A1.01 034 Fuel Handling Equipment Steam valve stuck open A2.02 041 Steam Dump/Turbine Bypass Control Knowledge of abnormal condition procedures.
2.4.11 055 Condenser Air Removal 1
02/04/2009 8:02:08 am
Facility:
Diablo Canyon Power Plant Generic Category KA KA Topic Comment Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 02/04/2009 Printed:
PWR SRO Examination Outline 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.
Conduct of Operations 2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.
2 Category Total:
2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.
Equipment Control 1
Category Total:
2.3.11 Ability to control radiation releases.
Radiation Control 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
2 Category Total:
2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
Emergency Procedures/Plan 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.
2 Category Total:
7 Generic Total:
1 02/04/2009 8:02:15 am Rev 1
ES-401, Page 27 of 33 ES-401 Record of Rejected K/As Form ES-401-4 l
Tier /
Group Randomly Selected K/A Reason for Rejection RO-T2/G1 061 K2.03 KA is knowledge of the power supply to AFW diesel driven pump.
This is not applicable at DCPP Replaced with 061 K1.11 interrelationship between AFW/Turbine exh/drains, IR 2.7 RO-T2/G1 076 A1.02 KA is to predict and monitor changes in reactor and turbine building closed cooling water temperatures.
At DCPP, Service Water is ASW which is not supplied to either building. It only supplies cooling to CCW pumps.
Replaced with 008 K2.02-Power to pumps, including emergency B/U IR 3.0*
SRO -
W/E12 G2.4.1 KA tests knowledge of EOP entry conditions and immediate actions. There are no T1/G1 immediate actions in the Steam Line Rupture (E-2) EOP.
Replaced with APE 056 2.4.6 - EOP mitigation strategies IR 4.7 SRO APE 005 G2.4.20 knowledge of eop warning, notes, cautions, for stuck rod, T1/G2 not testable at SRO level. replaced with APE 076 G2.2.38 RO T1G1 APE 017G2.2.38 This is a Tech Spec KA, for RCPs there are no Tech Specs (ie <1hr) that are RO knowledge. Replaced with EPE055.G2.1.31 RO T1G2 APE 003AK1.17 theory KA that is not site specific and category 1. Replaced with E14.EK2.2 rev 1 modifications 23 January, 2009 - rev1 RO T2G2 033 K3.02 no testable tie for DCPP. randomly selected from the remaining K3's.
New KA 033 K3.03 - effect of loss of SFP cooling on SFP temperature RO T2G2 071A1.06 Randomly, using the KA program, resampled for a new KA.
Original did not apply to DCPP. Using the program to randomly sample assured the balance of the sample plan would be maintained. (015A1.01)
Continued on next page Rev 1
ES-401, Page 27 of 33 ES-401 Record of Rejected K/As Form ES-401-4 l
Tier /
Group Randomly Selected K/A Reason for Rejection 23 January, 2009 rejected KA's continued - rev1 SRO T3/4 G2.4.47 Not at SRO level. used the KA program to randomly sample for new KA to ensure balance to sample plan maintained. NEW KA 2.4.38 SRO T3/1 G2.1.13 original KA only required basic RO knowledge of radiation levels.
Resampled using the KA program to maintain sample plan balance.
NEW KA G2.1.4 Rev 1