ML12325A388

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Fc 2012-09 Draft Outlines
ML12325A388
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 09/21/2012
From: Vincent Gaddy
Operations Branch IV
To:
Omaha Public Power District
References
ES-401, ES-401-2 50-282/12-009
Download: ML12325A388 (15)


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 07/10/2012 Date Of Exam: 09/21/2012 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 4 2 3 18 0 0 0 Emergency 2 2 1 2 N/A 1 2 1 9 0 0 0

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

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

3. Generic Knowledge And 10 0 Abilities Categories 3 2 2 3 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.

07/10/2012 10:36:40 am 1

PWR RO Examination Outline Printed: 07/10/2012 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - X EA2.02 - Proper actions to be taken if 4.3 1 Recovery / 1 the automatic safety functions have not taken place 000008 Pressurizer Vapor Space Accident / X AA1.06 - Control of PZR level 3.6 1 3

000009 Small Break LOCA / 3 X EK2.03 - S/Gs 3.0 1 000011 Large Break LOCA / 3 X EK3.12 - Actions contained in EOP for 4.4 1 emergency LOCA (large break) 000015/000017 RCP Malfunctions / 4 X 2.1.30 - Ability to locate and operate 4.4 1 components, including local controls.

000022 Loss of Rx Coolant Makeup / 2 X AK1.03 - Relationship between 3.0 1 charging flow and PZR level 000025 Loss of RHR System / 4 X AK1.01 - Loss of RHRS during all 3.9 1 modes of operation 000026 Loss of Component Cooling Water / X AA1.02 - Loads on the CCWS in the 3.2 1 8 control room 000027 Pressurizer Pressure Control System X AK2.03 - Controllers and positioners 2.6 1 Malfunction / 3 000029 ATWS / 1 X EK1.01 - Reactor nucleonics and 2.8 1 thermo-hydraulics behavior 000038 Steam Gen. Tube Rupture / 3 X 2.4.31 - Knowledge of annunciator 4.2 1 alarms, indications, or response procedures.

000040 Steam Line Rupture - Excessive X AK2.02 - Sensors and detectors 2.6* 1 Heat Transfer / 4 000054 Loss of Main Feedwater / 4 X 2.1.20 - Ability to interpret and execute 4.6 1 procedure steps.

000056 Loss of Off-site Power / 6 X AA1.09 - CCW pump 3.3 1 000057 Loss of Vital AC Inst. Bus / 6 X AK3.01 - Actions contained in EOP for 4.1 1 loss of vital ac electrical instrument bus 000058 Loss of DC Power / 6 X AK3.02 - Actions contained in EOP for 4.0 1 loss of dc power 000065 Loss of Instrument Air / 8 X AA2.08 - Failure modes of air-operated 2.9* 1 equipment 000077 Generator Voltage and Electric Grid X AA1.03 - Voltage regulator controls 3.8 1 Disturbances / 6 K/A Category Totals: 3 3 3 4 2 3 Group Point Total: 18 07/10/2012 10:36:02 am 1

PWR RO Examination Outline Printed: 07/10/2012 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000001 Continuous Rod Withdrawal / 1 X AA2.04 - Reactor power and its trend 4.2 1 000024 Emergency Boration / 1 X 2.1.7 - Ability to evaluate plant 4.4 1 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000028 Pressurizer Level Malfunction / 2 X AK1.01 - PZR reference leak 2.8* 1 abnormalities 000051 Loss of Condenser Vacuum / 4 X AK3.01 - Loss of steam dump 2.8* 1 capability upon loss of condenser vacuum 000059 Accidental Liquid RadWaste Rel. / X AK3.04 - Actions contained in EOP for 3.8 1 9 accidental liquid radioactive-waste release 000060 Accidental Gaseous Radwaste Rel. / X AA1.02 - Ventilation system 2.9 1 9

000061 ARM System Alarms / 7 X AK2.01 - Detectors at each ARM 2.5* 1 system location CE/A11 RCS Overcooling - PTS / 4 X EK1.1 - Components, capacity, and 3.1 1 function of emergency systems CE/E09 Functional Recovery X EA2.2 - Adherence to appropriate 3.5 1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 2 1 2 1 2 1 Group Point Total: 9 07/10/2012 10:36:10 am 1

PWR RO Examination Outline Printed: 07/10/2012 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K2.01 - RCPS 3.1 1 004 Chemical and Volume Control X A4.08 - Charging 3.8 1 005 Residual Heat Removal X 2.4.1 - Knowledge of EOP 4.6 1 entry conditions and immediate action steps.

006 Emergency Core Cooling X K4.30 - Containment 3.6 1 isolation 006 Emergency Core Cooling X A1.15 - RWST Level and 3.3 1 temperature 007 Pressurizer Relief /Quench X A2.05 - Exceeding PRT 3.2 1 Tank high-pressure limits 008 Component Cooling Water X A3.08 - Automatic actions 3.6* 1 associated with the CCWS that occur as a result of a safety injection signal 010 Pressurizer Pressure Control X K1.01 - RPS 3.9 1 010 Pressurizer Pressure Control X K6.03 - PZR sprays and 3.2 1 heaters 012 Reactor Protection X K2.01 - RPS channels, 3.3 1 components, and interconnections 013 Engineered Safety Features X K6.01 - Sensors and 2.7* 1 Actuation detectors 022 Containment Cooling X K3.02 - Containment 3.0 1 instrumentation readings 022 Containment Cooling X 2.2.22 - Knowledge of 4.0 1 limiting conditions for operations and safety limits.

026 Containment Spray X A1.03 - Containment sump 3.5 1 level 039 Main and Reheat Steam X K5.08 - Effect of steam 3.6 1 removal on reactivity 039 Main and Reheat Steam X K1.08 - MFW 2.7* 1 059 Main Feedwater X K3.02 - AFW System 3.6 1 061 Auxiliary/Emergency X K5.02 - Decay heat sources 3.2 1 Feedwater and magnitude 061 Auxiliary/Emergency X A2.03 - Loss of dc power 3.1 1 Feedwater 062 AC Electrical Distribution X K4.10 - Uninterruptable ac 3.1 1 power sources 063 DC Electrical Distribution X A1.01 - Battery capacity as 2.5 1 it is affected by discharge rate 064 Emergency Diesel Generator X A3.05 - Operation of the 2.8 1 governor control of frequency and voltage control in parallel operation 07/10/2012 10:36:19 am 1

PWR RO Examination Outline Printed: 07/10/2012 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 064 Emergency Diesel Generator X K4.05 - Incomplete-start 2.8 1 relay 073 Process Radiation Monitoring X A4.02 - Radiation 3.7 1 monitoring system control panel 073 Process Radiation Monitoring X K5.03 - Relationship 2.9* 1 between radiation intensity and exposure limits 076 Service Water X K2.01 - Service water 2.7* 1 078 Instrument Air X K1.04 - Cooling water to 2.6 1 compressor 103 Containment X K3.02 - Loss of containment 3.8 1 integrity under normal operations K/A Category Totals: 3 3 3 3 3 2 3 2 2 2 2 Group Point Total: 28 07/10/2012 10:36:19 am 2

PWR RO Examination Outline Printed: 07/10/2012 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K3.02 - RCS 3.4* 1 011 Pressurizer Level Control X K2.02 - PZR heaters 3.1 1 014 Rod Position Indication X 2.4.4 - Ability to recognize 4.5 1 abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

017 In-core Temperature Monitor X K6.01 - Sensors and 2.7 1 detectors 027 Containment Iodine Removal X A2.01 - High temperature in 3.0* 1 the filter system 028 Hydrogen Recombiner and X A1.02 - Containment 3.4* 1 Purge Control pressure 035 Steam Generator X K4.06 - S/G pressure 3.1 1 041 Steam Dump/Turbine Bypass X K1.05 - RCS 3.5 1 Control 068 Liquid Radwaste X K5.03 - Units of radiation, 2.6 1 dose, and dose rate 079 Station Air X A4.01 - Cross-tie valves 2.7 1 with IAS K/A Category Totals: 1 1 1 1 1 1 1 1 0 1 1 Group Point Total: 10 07/10/2012 10:36:27 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 07/10/2012 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.1 Knowledge of conduct of operations 3.8 1 requirements.

2.1.13 Knowledge of facility requirements for 2.5 1 controlling vital / controlled access.

2.1.37 Knowledge of procedures, guidelines, or 4.3 1 limitations associated with reactivity management.

Category Total: 3 Equipment Control 2.2.6 Knowledge of the process for making changes to 3.0 1 procedures.

2.2.25 Knowledge of the bases in Technical 3.2 1 Specifications for limiting conditions for operations and safety limits.

Category Total: 2 Radiation Control 2.3.5 Ability to use radiation monitoring systems, such 2.9 1 as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

2.3.14 Knowledge of radiation or contamination hazards 3.4 1 that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 2 Emergency Procedures/Plan 2.4.2 Knowledge of system set points, interlocks and 4.5 1 automatic actions associated with EOP entry conditions.

2.4.8 Knowledge of how abnormal operating 3.8 1 procedures are used in conjunction with EOPs.

2.4.25 Knowledge of fire protection procedures. 3.3 1 Category Total: 3 Generic Total: 10 07/10/2012 10:36:34 am 1

ES-401 REV-0 RO Exam Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 000029 EA2.08 No Rod Bank Step Counters (resampled 000029 EK1.01) 1/2 000032 AA1.01 Power is not removed to FCS Source Range Detectors (resampled CE-A11 AK1.01) 2/1 003000 A3.01 FCS RCPs do not have seal injection (resampled 064000 K4.05) 2/1 076000 K3.03 No Reactor Building Closed Cooling Water System (resampled 078000 K1.04) 2/1 103000 A2.03 No phase A&B containment Isolation (resampled 103000 K3.02) 2/1 059000 2.2.42 No TS LCO associated with main FW (resampled 059000 K3.02) 3/1 000000 2.1.27 Not appropriate for a tier 3 question since it must be associated with a system (resampled 000000 2.1.37)

ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 07/09/2012 Date Of Exam: 09/21/2012 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 0 2 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 2 1 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.

07/09/2012 4:42:39 pm 1

PWR SRO Examination Outline Printed: 07/09/2012 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X AA2.23 - Criteria for throttling 4.3 1 3 high-pressure injection after a small LOCA 000009 Small Break LOCA / 3 X EA2.11 - Containment temperature, 4.1 1 pressure, and humidity 000027 Pressurizer Pressure Control System X 2.1.25 - Ability to interpret reference 4.2 1 Malfunction / 3 materials, such as graphs, curves, tables, etc.

000054 Loss of Main Feedwater / 4 X AA2.02 - Differentiation between loss 4.4 1 of all MFW and trip of one MFW pump 000058 Loss of DC Power / 6 X 2.1.7 - Ability to evaluate plant 4.7 1 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000065 Loss of Instrument Air / 8 X 2.1.32 - Ability to explain and apply 4.0 1 system limits and precautions.

K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 07/09/2012 4:42:10 pm 1

PWR SRO Examination Outline Printed: 07/09/2012 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000024 Emergency Boration / 1 X 2.2.37 - Ability to determine operability 4.6 1 and/or availability of safety related equipment.

000033 Loss of Intermediate Range NI / 7 X AA2.10 - Tech-Spec limits if both 3.8 1 intermediate-range channels have failed 000036 Fuel Handling Accident / 8 X 2.4.18 - Knowledge of the specific 4.0 1 bases for EOPs.

000067 Plant Fire On-site / 9 X AA2.12 - Location of vital equipment 3.9 1 within fire zone K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 07/09/2012 4:42:16 pm 1

PWR SRO Examination Outline Printed: 07/09/2012 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X 2.1.28 - Knowledge of the 4.1 1 purpose and function of major system components and controls.

010 Pressurizer Pressure Control X A2.03 - PORV failures 4.2 1 013 Engineered Safety Features X A2.02 - Excess steam 4.5 1 Actuation demand 064 Emergency Diesel Generator X 2.4.20 - Knowledge of 4.3 1 operational implications of EOP warnings, cautions, and notes.

078 Instrument Air X A2.01 - Air dryer and filter 2.9 1 malfunctions K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 07/09/2012 4:42:22 pm 1

PWR SRO Examination Outline Printed: 07/09/2012 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 014 Rod Position Indication X 2.4.8 - Knowledge of how 4.5 1 abnormal operating procedures are used in conjunction with EOPs.

015 Nuclear Instrumentation X A2.05 - Core void formation 3.8 1 056 Condensate X A2.04 - Loss of condensate 2.8* 1 pumps K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 07/09/2012 4:42:28 pm 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 07/09/2012 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, 3.9 1 such as minimum crew complement, overtime limitations, etc.

2.1.13 Knowledge of facility requirements for 3.2 1 controlling vital / controlled access.

Category Total: 2 Equipment Control 2.2.7 Knowledge of the process for conducting special 3.6 1 or infrequent tests.

2.2.22 Knowledge of limiting conditions for operations 4.7 1 and safety limits.

Category Total: 2 Radiation Control 2.3.12 Knowledge of radiological safety principles 3.7 1 pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Category Total: 1 Emergency Procedures/Plan 2.4.6 Knowledge of EOP mitigation strategies. 4.7 1 2.4.40 Knowledge of SRO responsibilities in emergency 4.5 1 plan implementation.

Category Total: 2 Generic Total: 7 07/09/2012 4:42:34 pm 1

ES-401 REV -0 SRO Exam Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/2 000076 2.2.38 There are no conditions or limitations in the facility license associated with high RCS activity. Tech Spec LCOs fall under a different K/A. (resampled 000036 2.4.18) 2/1 007000 2.4.01 Knowledge of entry conditions and immediate action steps is more appropriate for a RO level question. (resampled 064000 2.4.20) 2/1 059000 2.1.27 Knowledge of system purpose and/or function is more appropriate for a RO level question. (resampled 010000 A2.03) 2/2 079000 A2.01 Redundant to K/A 079000 A4.01 used in RO exam outline (resampled 015000 A2.05)