ML103430563

2010-09-Final Outlines

ML103430563
Person / Time
Site:	Fort Calhoun  (DPR-040)
Issue date:	09/17/2010
From:	Brian Larson Operations Branch IV
To:	Omaha Public Power District
References
50-285/10-301, ES-401, ES-401-2 50-285/10-301
Download: ML103430563 (26)

Text

09/02/2010 Printed:

ES-401 Facility:

Fort Calhoun PWR Examination Outline Form ES-401-2 3

3 3

3 3

3 2

1 2

1 1

2 5

4 5

4 4

5 3

2 3

3 3

2 1

3 2

4 2

0 1

1 1

1 1

1 1

1 1

1 3

3 4

4 4

3 2

4 3

5 3

3 3

2 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:

09/17/2010 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

09/02/2010 10:13:27 am Revision 2

09/02/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Fort Calhoun E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 AA2.19 - PZR spray valve failure, using plant parameters 3.4 1

X 000008 Pressurizer Vapor Space Accident /

3 EK2.03 - S/Gs 3.0 1

X 000009 Small Break LOCA / 3 AK3.01 - Potential damage from high winding and/or bearing temperatures 2.5 1

X 000015/000017 RCP Malfunctions / 4 2.4.6 - Knowledge of EOP mitigation strategies.

3.7 1

X 000022 Loss of Rx Coolant Makeup / 2 AA1.10 - LPI pump suction valve and discharge valve indicators 3.1*

1 X

000025 Loss of RHR System / 4 AA1.05 - The CCWS surge tank, including level control and level alarms, and radiation alarm 3.1 1

X 000026 Loss of Component Cooling Water /

8 AK2.03 - Controllers and positioners 2.6 1

X 000027 Pressurizer Pressure Control System Malfunction / 3 2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

4.6 1

X 000029 ATWS / 1 EK3.04 - Automatic actions provided by each PRM 3.9 1

X 000038 Steam Gen. Tube Rupture / 3 AK1.01 - MFW line break depressurizes the S/G (similar to a steam line break) 4.1 1

X 000054 Loss of Main Feedwater / 4 2.4.1 - Knowledge of EOP entry conditions and immediate action steps.

4.6 1

X 000055 Station Blackout / 6 AA2.86 - Main steam pressure meter scale 2.7*

1 X

000056 Loss of Off-site Power / 6 AK3.01 - Actions contained in EOP for loss of vital ac electrical instrument bus 4.1 1

X 000057 Loss of Vital AC Inst. Bus / 6 AK1.01 - Battery charger equipment and instrumentation 2.8 1

X 000058 Loss of DC Power / 6 AA2.02 - The cause of possible SWS loss 2.9 1

X 000062 Loss of Nuclear Svc Water / 4 AK2.01 - Motors 3.1 1

X 000077 Generator Voltage and Electric Grid Disturbances / 6 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the (Reactor Trip Recovery) 3.0 1

X CE/E02 Reactor Trip - Stabilization -

Recovery / 1 1

09/02/2010 10:12:45 am Revision 2

09/02/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Fort Calhoun E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.9 1

X CE/E05 Steam Line Rupture - Excessive Heat Transfer / 4 18 3

3 3

3 3

3 K/A Category Totals:

Group Point Total:

2 09/02/2010 10:12:45 am Revision 2

09/02/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Fort Calhoun E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AA2.01 - Rod position indication to actual rod position 3.7 1

X 000003 Dropped Control Rod / 1 2.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems.

3.9 1

X 000036 Fuel Handling Accident / 8 2.2.22 - Knowledge of limiting conditions for operations and safety limits.

4.0 1

X 000037 Steam Generator Tube Leak / 3 AK3.04 - Actions contained in EOP for accidental liquid radioactive-waste release 3.8 1

X 000059 Accidental Liquid RadWaste Rel. /

9 AK1.01 - Detector limitations 2.5*

1 X

000061 ARM System Alarms / 7 AK2.03 - Controllers and positioners 2.9 1

X 000068 Control Room Evac. / 8 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the (RCS Overcooling) 3.0 1

X CE/A11 RCS Overcooling - PTS / 4 EA1.2 - Operating behavior characteristics of the facility 3.1 1

X CE/A13 Natural Circ. / 4 EK3.2 - Normal, abnormal and emergency operating procedures associated with (Excess RCS Leakage) 2.8 1

X CE/A16 Excess RCS Leakage / 2 9

2 1

2 1

1 2

K/A Category Totals:

Group Point Total:

1 09/02/2010 10:12:53 am Revision 2

09/02/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Fort Calhoun PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K6.02 - RCP seals and seal water supply 2.7 1

X 003 Reactor Coolant Pump A4.08 - RCP cooling water supplies 3.2 1

X 003 Reactor Coolant Pump 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

4.2 1

X 004 Chemical and Volume Control A1.07 - Maximum specified letdown flow 2.7 1

X 004 Chemical and Volume Control K5.03 - Reactivity effects of RHR fill water 2.9*

1 X

005 Residual Heat Removal K6.03 - Safety Injection Pumps 3.6 1

X 006 Emergency Core Cooling K5.02 - Method of forming a steam bubble in the PZR 3.1 1

X 007 Pressurizer Relief/Quench Tank 2.1.28 - Knowledge of the purpose and function of major system components and controls.

4.1 1

X 008 Component Cooling Water A2.03 - High/low CCW temperature 3.0 1

X 008 Component Cooling Water K1.08 - PZR LCS 3.2 1

X 010 Pressurizer Pressure Control K5.02 - Power density 3.1*

1 X

012 Reactor Protection A3.05 - Single and multiple channel trip indicators 3.6 1

X 012 Reactor Protection K4.03 - Main Steam Isolation System 3.9 1

X 013 Engineered Safety Features Actuation A4.01 - ESFAS-initiated equipment which fails to actuate 4.5 1

X 013 Engineered Safety Features Actuation A3.01 - Initiation of safeguards mode of operation 4.1 1

X 022 Containment Cooling K2.01 - Containment spray pumps 3.4*

1 X

026 Containment Spray K1.02 - Atmospheric relief dump valves 3.3 1

X 039 Main and Reheat Steam A4.01 - Main steam supply valves 2.9*

1 X

039 Main and Reheat Steam A2.04 - Feeding a dry S/G 2.9*

1 X

059 Main Feedwater K1.02 - MFW System 3.4 1

X 061 Auxiliary/Emergency Feedwater K4.14 - AFW automatic isolation 3.5*

1 X

061 Auxiliary/Emergency Feedwater K3.02 - ED/G 4.1 1

X 062 AC Electrical Distribution 1

09/02/2010 10:13:03 am Revision 2

09/02/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Fort Calhoun PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K3.01 - ED/G 3.7*

1 X

063 DC Electrical Distribution A2.03 - Parallel operation of ED/Gs 3.1 1

X 064 Emergency Diesel Generator A4.03 - Check source for operability demonstration 3.1 1

X 073 Process Radiation Monitoring K2.01 - Service water 2.7*

1 X

076 Service Water K3.01 - Containment air system 3.1*

1 X

078 Instrument Air K4.06 - Containment isolation system 3.1 1

X 103 Containment 28 3

2 3

1 3

2 K/A Category Totals:

3 3

2 2

4 Group Point Total:

2 09/02/2010 10:13:03 am Revision 2

09/02/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Fort Calhoun PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 K2.02 - One-line diagram of power supply to trip breakers 3.6 1

X 001 Control Rod Drive A3.03 - Pressure, temperatures, and flows 4.4 1

X 002 Reactor Coolant K6.04 - Operation of PZR level controllers 3.1 1

X 011 Pressurizer Level Control A1.01 - Core exit temperature 3.7 1

X 017 In-core Temperature Monitor A4.01 - Containment purge flow rate 2.5 1

X 029 Containment Purge K4.03 - Overload protection 2.6 1

X 034 Fuel Handling Equipment A2.02 - Reactor trip/turbine trip 4.2 1

X 035 Steam Generator K3.01 - Remainder of the plant 2.9 1

X 045 Main Turbine Generator 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.3 1

X 056 Condensate K5.03 - Effect of water spray on electrical components 3.1 1

X 086 Fire Protection 10 0

1 1

1 1

1 K/A Category Totals:

1 1

1 1

1 Group Point Total:

1 09/02/2010 10:13:12 am Revision 2

Facility:

Fort Calhoun Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 09/02/2010 Printed:

PWR RO Examination Outline 2.1.21 Ability to verify the controlled procedure copy.

3.5*

1 Conduct of Operations 2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

4.6 1

2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

4.1 1

3 Category Total:

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

4.5 1

Equipment Control 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

2.6 1

2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

3.5 1

3 Category Total:

2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

2.9 1

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.

3.4 1

2 Category Total:

2.4.9 Knowledge of low power /shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

3.8 1

Emergency Procedures/Plan 2.4.37 Knowledge of the lines of authority during implementation of the emergency plan.

3.0 1

2 Category Total:

1 09/02/2010 10:13:20 am Revision 2

Facility:

Fort Calhoun Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 09/02/2010 Printed:

PWR RO Examination Outline 10 Generic Total:

2 09/02/2010 10:13:20 am Revision 2

ES-401-4-RO REV 2 RO Exam Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection 2/1 013000 2.4.41 EAL classification not a RO task at FCS

( Replaced with 008000 2.1.28) 2/1 026000 K4.04 Containment Spray System does not start automatically during a LOCA at FCS. (Replaced with 039000 K1.02) 2/1 076000 2.1.19 No system specific plant computer interface (Replaced with007000 K4.01) 3 000000 2.2.39 K/A addresses system specific topic, not amenable to Tier 3 question. (Replaced with 000000 2.1.43) 3 000000 2.2.44 K/A addresses system specific topic, not amenable to Tier 3 question. (Replaced with 000000 2.2.41) 3 000000 2.3.15 K/A addresses system specific topic, not amenable to Tier 3 question. (Replaced with 000000 2.4.9) 3 000000 2.3.12 Redundant to 2.3.13 which is included in outline (replaced by 2.3.5) 3 000000 2.4.02 K/A addresses system specific topic, not amenable to Tier 3 question. (Replaced with 000000 2.2.18) 1/2 000076 Ak2.01 No RCS activity radiation monitor (Replaced with 000068 AK2.03) 2/1 078000 A4.01 Topic has been addressed adequately in this exam and last NRC exam (Replaced with 013000 A4.01) 3 000000 2.1.45 K/A addresses system specific topic, not amenable to Tier 3 question. (Replaced with 000000 2.1.21) 2/1 064000 A2.14 Could not write a discriminating question fitting this K/A (Replaced with 064000 A2.03) 2/1 073000 A1.01 Could not write a discriminating question fitting this K/A that had not already been used on audit exam (Replaced with 073000 A4.03) 2/1 007000 K4.01 Could not write a discriminating question fitting this K/A (Replaced with 061000 K4.14)

07/28/2010 Printed:

ES-401 Facility:

Fort Calhoun 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:

09/17/2010 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

07/28/2010 6:04:37 pm Revision 1

07/28/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Fort Calhoun E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.

4.3 1

X 000008 Pressurizer Vapor Space Accident /

3 AA2.05 - Limitations on LPI flow and temperature rates of change 3.5*

1 X

000025 Loss of RHR System / 4 2.4.11 - Knowledge of abnormal condition procedures.

4.2 1

X 000029 ATWS / 1 AA2.05 - When to commence plant shutdown if instrument air pressure is decreasing 4.1 1

X 000065 Loss of Instrument Air / 8 2.4.18 - Knowledge of the specific bases for EOPs.

4.0 1

X 000077 Generator Voltage and Electric Grid Disturbances / 6 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 3.7 1

X CE/E02 Reactor Trip - Stabilization -

Recovery / 1 6

0 0

0 0

3 3

K/A Category Totals:

Group Point Total:

1 07/28/2010 6:04:00 pm Revision 1

07/28/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Fort Calhoun E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 AA2.04 - Comparison of RCS fluid inputs and outputs, to detect leaks 3.7 1

X 000037 Steam Generator Tube Leak / 3 AA2.01 - Cause for low vacuum condition 2.7*

1 X

000051 Loss of Condenser Vacuum / 4 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

4.4 1

X 000074 Inad. Core Cooling / 4 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 1

X CE/E09 Functional Recovery 4

0 0

0 0

2 2

K/A Category Totals:

Group Point Total:

1 07/28/2010 6:04:08 pm Revision 1

07/28/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Fort Calhoun PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.13 - Inadvertent SIS actuation 4.2 1

X 006 Emergency Core Cooling 2.1.32 - Ability to explain and apply system limits and precautions.

4.0 1

X 012 Reactor Protection A2.01 - LOCA 4.8 1

X 013 Engineered Safety Features Actuation A2.03 - Indications and alarms for main steam and area radiation monitors (during SGTR) 3.7 1

X 039 Main and Reheat Steam 2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.

4.2 1

X 061 Auxiliary/Emergency Feedwater 5

0 0

0 0

3 2

K/A Category Totals:

0 0

0 0

0 Group Point Total:

1 07/28/2010 6:04:16 pm Revision 1

07/28/2010 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Fort Calhoun PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

4.1 1

X 028 Hydrogen Recombiner and Purge Control K1.04 - NIS 3.5 1

X 034 Fuel Handling Equipment A2.01 - Loss of intake structure 3.2 1

X 075 Circulating Water 3

1 0

0 0

1 1

K/A Category Totals:

0 0

0 0

0 Group Point Total:

1 07/28/2010 6:04:23 pm Revision 1

Facility:

Fort Calhoun Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 07/28/2010 Printed:

PWR SRO Examination Outline 2.1.34 Knowledge of primary and secondary plant chemistry limits.

3.5 1

Conduct of Operations 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

4.3 1

2 Category Total:

2.2.6 Knowledge of the process for making changes to procedures.

3.6 1

Equipment Control 1

Category Total:

2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

3.7 1

Radiation Control 2.3.11 Ability to control radiation releases.

4.3 1

2 Category Total:

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

4.5 1

Emergency Procedures/Plan 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

4.4 1

2 Category Total:

7 Generic Total:

1 07/28/2010 6:04:30 pm Revision 1

ES-401 REV 1 SRO Exam Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection 1/1 000027 2.4.01 No EOP entry condition related to Pressurizer Pressure Control System Malfunction. (Replaced with 000062 AA2.02) 1/1 000038 EA2.11 No FCS procedure for local steam line radiation readings (Replaced with 000077 2.4.18) 1/2 000003 2.4.35 No local auxiliary operator task for dropped control rod (Replaced with 000074 2.4.49) 1/2 000059 AA2.01 No specific failure indication light arrangement for waste liquid release at FCS (Replaced with 000051 AA2.01) 1/2 000060 2.4.47 Will be tested during a simulator scenario event. (Replaced with CE E09 2.4.47) 3 000000 2.1.32 K/A addresses system specific topic, not amenable to Tier 3 question. (Replaced with 000000 2.1.43) 1/1 000062 AA2.02 Already sampled in RO Outline (Replaced with CE-E02 EA 2.01)

[Question 78]

2/1 062000 2.4.01 Not amenable to SRO only question (Replaced with 012000 2.1.32)[Question 90]

3 000000 2.1.06 Not amenable to written exam question, evaluated during simulator scenarios (Replaced with 000000 2.1.34) [Question 94]

3 000000 2.2.25 K/A addresses system specific topic, not amenable to Tier 3 question. (Replaced with 000000 2.2.06) [Question 96]

3 000000 2.3.05 Not amenable to SRO only question. Ability expected for both RO and SRO (Replaced with 000000 2.3.11) [Question 98]

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun______________

Date of Examination: 9/20/2010 Examination Level: RO Revision Number: 3 Administrative Topic (see Note)

Type Code*

Describe activity to be performed A-1 Conduct of Operations N, R Determine Boron Addition Rate Without Using ERF Computer KA: 2.1.37 (4.3)

A-2 Conduct of Operations D, R Determine Maximum Diesel Generator Load Based on Weather Conditions KA: 2.1.32 (3.8)

A-3 Equipment Control M, R Use P&IDs to Determine Equipment Affected by Closure of Instrument Air Valve KA: 2.2.41 (3.5)

A-4 Radiation Control N, R Read a Survey Map and Apply RWP Requirements KA: 2.3.7 (3.5)

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 all 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 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun______________

Date of Examination: 9/20/2010 Examination Level: SRO Revision Number: 2 Administrative Topic (see Note)

Type Code*

Describe activity to be performed A-5 Conduct of Operations M, R Approve Movement of Spent Fuel Assemblies KA : 2.1.42 (3.4)

A-6 Conduct of Operations D, R SRO Review of Surveillance Test Results KA: 2.1.25 (4.2)

A-7 Equipment Control D, R Determine Equipment Operability Requirements during Mode Change KA: 2.2.37 (4.6)

A-8 Radiation Control D, R Approve Gas Decay Tank Release KA: 2.3.6 (3.8)

A-9 Emergency Procedures/Plan M, R Classify Emergency Action Levels and make Protective Action Recommendations KA: 2.4.41 (4.6)

KA: 2.4.44 (4.4)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 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 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________

Date of Examination: 9/20/2010 Exam Level: RO Revision Number.: 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function S-1. Emergency Boration with Loss of BASTs / KA: 004000 A2.14 (3.8/3.9)

M, A, L, S 1

S-2. Transfer Clutch Power Supply/X-Tie Instrument Buses / KA 062000 A4.01 (3.3/3.1)

D, S 6

S-3 Lower RCS Pressure with a Steam Bubble in the Pressurizer /

KA 010000 A4.03 (4.0/3.8)

N,A,S 3

S-4. Alternate Decay Heat Removal using S/G's (shutdown cooling)/

KA 041000 A4.06 (2.9/3.1)

N,A,L,S 4S S-5 Rotate CEDM Cooling Fans K/A 022000 A4.01 (3.6/3.6)

N, A, S 5

S-6 Adjust T-Cold Calibration / KA 012000 A4.02 (3.3/3.4)

D, S 7

S-7 LPSI (SDC) Pump Operability Test / KA 005000 A4.01 (3.6/3.4)

N, EN,S 4P S-8. Align HPSI Pump, SI-2C, for Automatic Start /KA 013000 A3.02 (4.1/4.2)

N, S, EN 2

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 Minimize DC Loads / KA 000055 EA1.04 (3.5/3.9)

D, E,L 6

P-2 Manual Operation of Raw Water Strainer to clear blockage /

076000 A2.01 (3.5/3.7)

N, A 4S P-3 Fire Protection System Backup Cooling for CCW /

KA 008000 A2.03 (3.0/3.2)

N, R, E, A 8

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________

Date of Examination: 9/20/2010 Exam Level: ISRO Revision Number.: 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function S-1. Emergency Boration with Loss of BASTs / KA: 004000 A2.14 (3.8/3.9)

M, A, L, S 1

S-2. Transfer Clutch Power Supply/X-Tie Instrument Buses / KA 062000 A4.01 (3.3/3.1)

D, S 6

S-3 Lower RCS Pressure with a Steam Bubble in the Pressurizer /

KA 010000 A4.03 (4.0/3.8)

N,A,S 3

S-4. Alternate Decay Heat Removal using S/G's (shutdown cooling)/

KA 041000 A4.06 (2.9/3.1)

N,A,L,S 4S S-5 Rotate CEDM Cooling Fans K/A 022000 A4.01 (3.6/3.6)

N, A, S 5

S-6 Adjust T-Cold Calibration / KA 012000 A4.02 (3.3/3.4)

D, S 7

S-7 LPSI (SDC) Pump Operability Test / KA 005000 A4.01 (3.6/3.4)

N, EN,S 4P In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 Minimize DC Loads / KA 000055 EA1.04 (3.5/3.9)

D, E,L 6

P-2 Manual Operation of Raw Water Strainer to clear blockage /

076000 A2.01 (3.5/3.7)

N, A 4S P-3 Fire Protection System Backup Cooling for CCW /

KA 008000 A2.03 (3.0/3.2)

N, R, E, A 8

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________

Date of Examination: 9/20/2010 Exam Level: USRO Revision Number.: 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function S-3 Lower RCS Pressure with a Steam Bubble in the Pressurizer /

KA 010000 A4.03 (4.0/3.8)

N,A,S 3

S-8. Align HPSI Pump, SI-2C, for Automatic Start /KA 013000 A3.02 (4.1/4.2)

N, S, EN 2

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 Minimize DC Loads / KA 000055 EA1.04 (3.5/3.9)

D, E,L 6

P-2 Manual Operation of Raw Water Strainer to clear blockage /

KA 076000 A2.01 (3.5/3.7)

N, A 4S P-3 Fire Protection System Backup Cooling for CCW /

KA 008000 A2.03 (3.0/3.2)

N, R, E, A 8

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2010-1 Revision: 3 Examiners:

Operators:

Initial Conditions: Plant at 100% power. Auxiliary Feedwater Pump, FW-54, OOS. HPSI Pump, SI-2B, OOS. S/G "A" Blowdown Radiation Monitor, RM-054A, OOS, Containment Cooling Fan, VA-3B OOS, RM-054B lined up to sample both S/G's.

Turnover: A Tornado Watch has been issued, AOP-01 has been entered. Shift Manager directs that rotation of Charging Pumps be continued at beginning of shift. (CH-1B on and CH-1A off)

Event No.

Malf No.

Event Type*

Event Description 1

N-ATCO Rotate Charging Pumps 2

I-ATCO VCT Level Transmitter Fails Low.

3 N-BOPO A Tornado Warning is issued for the plant 4

C-BOPO Condensate pump FW-2B trips, no backup autostart 5

C-ATCO T-CRS Charging Pump, CH-1B, Degraded Performance 6

C-ATCO T-CRS Component Cooling Water Pump AC-3A trips, No autostart 7

M-All Steam Generator A Tube Rupture 8

C-ATCO HPSI Pump, SI-2A, Fails to start

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Total malfunctions (5-8) 6

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2010-2 Revision: 2 Examiners:

Operators:

Initial Conditions: Plant at 50% due to only having one condensate pump available Turnover: Diesel Generator D-2 out of service. Condensate Pumps FW-2A and FW-2C tagged out. FW-10 Surveillance Test OP-ST-AFW-0004 in Progress.

Event No.

Malf No.

Event Type*

Event Description 1

N-BOPO T-CRS FW-10 Surveillance Test (fails) 2 C-ATCO T-CRS CR HVAC Unit VA-46B Fails 3

I-ATCO T-CRS WR NI Channel "D" Fails Low 4

C-ALL Waste Gas Decay Tank "D" Ruptures 5

C-ATCO Two Reactor Coolant Pumps Seals Fail on RC-3A 6

R-ATCO N-BOPO AOP-05 Power Reduction 7

M-ALL Steam line Break inside Containment from S/G A 8

I-ATCO CPHS Fails to actuate

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2010-3 Revision: 2 Examiners:

Operators:

Initial Conditions: Plant at 100% Power.

Turnover: Diesel Generator D-1 out of service. Power Range NI channel "A" Out of Service Event No.

Malf No.

Event Type*

Event Description 1

C-ATCO T-CRS Leak at discharge of CCW Pump. AC-3C 2

C-BOPO Instrument Air Compressor CA-1C Trips, backup fails to load 3

I-ATCO T-CRS Pressurizer Level Transmitter, LT-101Y, fails high 4

C-ATCO T-CRS Power Range NI Channel "C" Upper Detector Failure 5

R-ATCO N-BOPO OP-4 Power Reduction 6

M-ALL Turbine trip / Reactor Trip 7

M-ALL Pressurizer Safety Valve fails open 8

I-ATCO PPLS Fails to actuate, Diesel Generator D-2 Fails to start 9

M-ALL Loss of 161 KV - Station Blackout

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Total malfunctions (5-8) 8

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 2

4. Major transients (1-2) 2

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 3

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2010-4 Revision: 3 Examiners:

Operators:

Initial Conditions: Plant Operating at 100% Power.

Turnover: Continue Full Power Operation Event No.

Malf No.

Event Type*

Event Description 1

I-ATCO T-CRS RCS DP Transmitter C/114Y Fails low 2

C-ATCO Letdown Backpressure Controller, PIC-210, fails which closes PCV-210 3

I-ALL T-CRS Loss of Instrument Bus "C" 4

C-BOPO FW Pump trips. Backup Pumps fail to auto start 5

C-BOPO Bearing Water Pump, AC-9A trips, AC-9B shaft shears 6

M-All R-ATCO Manual Reactor Trip, 2 CEAs fail to insert 7

C-BOPO Condenser steam dump valves TCV-909-1 and TCV-909-2 Fail Open (SGLS Fails to actuate)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Total malfunctions (5-8) 6

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3