ML090790362

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DC-2009-02-Final Outlines
ML090790362
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
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

ES-401 PWR Examination Outline Form ES-401-2 Facility: Diablo Canyon Power Plant Printed: 02/04/2009 Date Of Exam: 02/06/2009 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 0 0 0 Emergency 2 1 2 2 N/A 1 1 2 9 0 0 0

& N/A Abnormal Tier Plant Totals 4 5 5 4 4 5 27 0 0 0 Evolutions 1 3 2 3 3 3 2 1 3 2 3 3 28 0 0 0 2.

2 1 1 1 1 1 1 1 0 1 1 1 10 0 0 0 0 Plant Systems Tier 0 0 0 4 3 4 4 4 3 2 3 3 4 4 38 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 10 0 Abilities Categories 2 3 3 2 0 0 0 0 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 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.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

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

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' 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 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.

02/04/2009 7:52:36 am Rev 1 1

PWR RO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function KA KA Topic Comment 000008 Pressurizer Vapor Space Accident / 3 AK1.02 Change in leak rate with change in pressure 000009 Small Break LOCA / 3 EA2.12 Charging pump ammeter 000011 Large Break LOCA / 3 EA1.03 Securing of RCPs 000022 Loss of Rx Coolant Makeup / 2 AK1.03 Relationship between charging flow and PZR level 000025 Loss of RHR System / 4 AA2.07 Pump cavitation 000027 Pressurizer Pressure Control System Malfunction / 3 AK2.03 Controllers and positioners 000029 ATWS / 1 EK2.06 Breakers, relays, and disconnects 000038 Steam Gen. Tube Rupture / 3 EK1.01 Use of steam tables 000040 Steam Line Rupture - Excessive Heat Transfer / 4 AK2.02 Sensors and detectors 000054 Loss of Main Feedwater / 4 AA1.01 AFW controls, including the use of alternate AFW sources 000055 Station Blackout / 6 2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

02/04/2009 7:52:00 am 1

PWR RO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function KA KA Topic Comment 000056 Loss of Off-site Power / 6 AA2.19 T-cold and T-hot indicators (wide range) 000057 Loss of Vital AC Inst. Bus / 6 2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes.

000058 Loss of DC Power / 6 AA1.02 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector 000062 Loss of Nuclear Svc Water / 4 AK3.02 The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air / 8 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

W/E04 LOCA Outside Containment / 3 EK3.4 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 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink EK3.2 Normal, abnormal and emergency operating

/4 procedures associated with Loss of Secondary Heat Sink 02/04/2009 7:52:00 am 2

PWR RO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function KA KA Topic Comment 000032 Loss of Source Range NI / 7 AK3.01 Startup termination on source-range loss 000033 Loss of Intermediate Range NI / 7 AA2.01 Equivalency between source-range, intermediate-range, and power-range channel readings 000036 Fuel Handling Accident / 8 AK1.02 SDM 000059 Accidental Liquid RadWaste Rel. / 9 2.2.22 Knowledge of limiting conditions for operations and safety limits.

000060 Accidental Gaseous Radwaste Rel. / 9 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

000074 Inad. Core Cooling / 4 EK3.04 Tripping RCPs W/E08 RCS Overcooling - PTS / 4 EK2.2 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility W/E13 Steam Generator Over-pressure / 4 EA1.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E14 Loss of CTMT Integrity / 5 EK2.2 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 02/04/2009 7:52:07 am 1

PWR RO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name KA KA Topic Comment 003 Reactor Coolant Pump K1.08 Containment isolation 004 Chemical and Volume Control A3.03 Ion exchange bypass 004 Chemical and Volume Control K5.11 Thermal stress, brittle fracture, pressurized thermal shock 005 Residual Heat Removal K5.02 Need for adequate subcooling 006 Emergency Core Cooling 2.1.30 Ability to locate and operate components, including local controls.

006 Emergency Core Cooling K6.13 Pumps 007 Pressurizer Relief/Quench Tank K4.01 Quench tank cooling 008 Component Cooling Water A2.02 High/low surge tank level 008 Component Cooling Water K2.02 CCW pump, including emergency backup 010 Pressurizer Pressure Control A4.01 PZR spray valve 010 Pressurizer Pressure Control K6.03 PZR sprays and heaters 012 Reactor Protection A2.03 Incorrect channel bypassing 013 Engineered Safety Features Actuation 2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

013 Engineered Safety Features Actuation K1.10 CPS 02/04/2009 7:52:16 am 1

PWR RO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name KA KA Topic Comment 022 Containment Cooling A4.01 CCS fans 022 Containment Cooling A2.01 Fan motor over-current 026 Containment Spray K2.01 Containment spray pumps 039 Main and Reheat Steam A3.02 Isolation of the MRSS 059 Main Feedwater A4.03 Feedwater control during power increase and decrease 059 Main Feedwater K3.04 RCS 061 Auxiliary/Emergency Feedwater K1.11 AFW turbine exhaust/drains 062 AC Electrical Distribution K3.03 DC system 063 DC Electrical Distribution A1.01 Battery capacity as it is affected by discharge rate 064 Emergency Diesel Generator K3.01 Systems controlled by automatic loader 073 Process Radiation Monitoring K5.01 Radiation theory, including sources, types, units, and effects 076 Service Water 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

078 Instrument Air K4.03 Securing of SAS upon loss of cooling water 02/04/2009 7:52:16 am 2

PWR RO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name KA KA Topic Comment 103 Containment K4.01 Vacuum breaker protection 02/04/2009 7:52:16 am 3

PWR RO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name KA KA Topic Comment 001 Control Rod Drive K2.01 One-line diagram of power supply to M/G sets 011 Pressurizer Level Control A4.02 Movement of the pressure control valve, using manual controller 014 Rod Position Indication 2.1.32 Ability to explain and apply system limits and precautions.

015 Nuclear Instrumentation A1.01 NIS calibration by heat balance 028 Hydrogen Recombiner and Purge Control K5.03 Sources of hydrogen within containment 033 Spent Fuel Pool Cooling K3.02 Area and ventilation radiation monitoring systems 034 Fuel Handling Equipment K6.02 Radiation monitoring systems 035 Steam Generator A3.01 S/G water level control 075 Circulating Water K4.01 Heat sink 079 Station Air K1.01 IAS 02/04/2009 7:52:23 am 1

Generic Knowledge and Abilities Outline (Tier 3) Printed: 02/04/2009 PWR RO Examination Outline Form ES-401-3 Facility: Diablo Canyon Power Plant Generic Category KA KA Topic Comment Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.39 Knowledge of conservative decision making practices.

Category Total: 2 Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

2.2.6 Knowledge of the process for making changes to procedures.

2.2.13 Knowledge of tagging and clearance procedures.

Category Total: 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

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.

Category Total: 3 Emergency Procedures/Plan 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.

2.4.32 Knowledge of operator response to loss of all annunciators.

Category Total: 2 Generic Total: 10 Rev 1 02/04/2009 7:52:30 am 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Diablo Canyon Power Plant Printed: 02/04/2009 Date Of Exam: 02/06/2009 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 N/A 0 0 0 0 2 2 4

& N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

2 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 3 Plant Systems Tier 5 3 8 0 0 0 0 0 0 0 0 0 0 0 0 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 2 1 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).
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 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.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

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

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' 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 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.

02/04/2009 8:02:22 am Rev 1 1

PWR SRO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function KA KA Topic Comment 000007 Reactor Trip - Stabilization - Recovery / 1 EA2.06 Occurrence of a reactor trip 000026 Loss of Component Cooling Water / 8 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

000055 Station Blackout / 6 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

000056 Loss of Off-site Power / 6 2.4.6 Knowledge of EOP mitigation strategies.

000077 Generator Voltage and Electric Grid Disturbances / 6 AA2.10 Generator overheating and the required actions W/E11 Loss of Emergency Coolant Recirc. / 4 EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 02/04/2009 8:01:49 am 1

PWR SRO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function KA KA Topic Comment 000024 Emergency Boration / 1 2.4.11 Knowledge of abnormal condition procedures.

000076 High Reactor Coolant Activity / 9 2.2.38 Knowledge of conditions and limitations in the facility license.

W/E01 Rediagnosis / 3 EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments W/E07 Inad. Core Cooling / 4 EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 02/04/2009 8:01:56 am 1

PWR SRO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name KA KA Topic Comment 003 Reactor Coolant Pump A2.01 Problems with RCP seals, especially rates of seal leak-off 007 Pressurizer Relief/Quench Tank A2.02 Abnormal pressure in the PRT 012 Reactor Protection 2.2.38 Knowledge of conditions and limitations in the facility license.

059 Main Feedwater 2.2.38 Knowledge of conditions and limitations in the facility license.

061 Auxiliary/Emergency Feedwater A2.03 Loss of dc power 02/04/2009 8:02:02 am 1

PWR SRO Examination Outline Printed: 02/04/2009 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name KA KA Topic Comment 034 Fuel Handling Equipment A1.01 Load limits 041 Steam Dump/Turbine Bypass Control A2.02 Steam valve stuck open 055 Condenser Air Removal 2.4.11 Knowledge of abnormal condition procedures.

02/04/2009 8:02:08 am 1

Generic Knowledge and Abilities Outline (Tier 3) Printed: 02/04/2009 PWR SRO Examination Outline Form ES-401-3 Facility: Diablo Canyon Power Plant Generic Category KA KA Topic Comment Conduct of Operations 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.

2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Category Total: 2 Equipment Control 2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.

Category Total: 1 Radiation Control 2.3.11 Ability to control radiation releases.

2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Category Total: 2 Emergency Procedures/Plan 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.

2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

Category Total: 2 Generic Total: 7 Rev 1 02/04/2009 8:02:15 am 1

ES-401 Record of Rejected K/As Form ES-401-4 l Tier / Randomly Reason for Rejection Group Selected K/A 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 ES-401, Page 27 of 33 Rev 1

ES-401 Record of Rejected K/As Form ES-401-4 l Tier / Randomly Reason for Rejection Group Selected K/A 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 ES-401, Page 27 of 33 Rev 1