ML041130155

2004 - Final Examination Outline

ML041130155
Person / Time
Site:	Fort Calhoun
Issue date:	04/16/2004
From:	Gody A Plant Support Branch Region IV
To:	Ridenoure R Omaha Public Power District
References
50-285/04-301 50-285/04-301
Download: ML041130155 (22)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 02/26/2004 Date Of Exam: 03/12/2004 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total K A A2 G*

1. 1 3 3 3 3 3 3 18 0 0 0 0 0 Emergency 2 0 2 2 2 1 2 9 0 0 0 0 0 Abnormal Plant Tier 3 5 5 5 4 5 27 0 0 0 0 0 Evolutions Totals 1 3 2 2 3 3 1 4 3 1 3 3 28 0 0 0 0 0 2.

2 1 0 1 1 1 1 1 1 1 1 1 10 0 0 0 0 0 Plant Systems Tier 0 4 2 3 4 4 2 5 4 2 4 4 38 0 0 0 0 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 K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.

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. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category /tier.

6.* 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) 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 columns labeled "K" and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

1

PWR RO Examination Outline Printed: 02/26/2004 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 EA2.03 - Reactor trip breaker position 4.2 1 Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 X AK3.04 - RCP tripping requirements 4.2 1 000009 Small Break LOCA / 3 X EA2.06 - Whether PZR water inventory 3.8 1 loss is imminent 000009 Small Break LOCA / 3 X EK3.21 - Actions contained in EOP for 4.2 1 small break LOCA/leak 000015 RCP Malfunctions / 4 X AK2.07 - RCP seals 2.9 1 000026 Loss of Component Cooling Water / X AA1.07 - Flow rates to the components 2.9 1 8 and systems that are serviced by the CCWS; interactions among the components 000027 Pressurizer Pressure Control System X 2.4.49 - Ability to perform without 4.0 1 Malfunction / 3 reference to procedures those actions that require immediate operation of system components and controls.

000029 ATWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1 disconnects 000038 Steam Gen. Tube Rupture / 3 X EK3.03 - Automatic actions associated 3.6* 1 with high radioactivity in S/G sample lines 000040 Steam Line Rupture - Excessive Heat X AK2.01 - Valves 2.6* 1 Transfer / 4 000040 Steam Line Rupture - Excessive Heat X AA1.24 - Main steam header pressure 3.8 1 Transfer / 4 gauges 000054 Loss of Main Feedwater / 4 X 2.4.50 - Ability to verify system alarm 3.3 1 setpoints and operate controls identified in the alarm response manual.

000055 Station Blackout / 6 X EK1.01 - Effect of battery discharge 3.3 1 rates on capacity 000056 Loss of Off-site Power / 6 X AA2.20 - AFW flow indicator 3.9 1 000057 Loss of Vital AC Inst. Bus / 6 X 2.4.50 - Ability to verify system alarm 3.3 1 setpoints and operate controls identified in the alarm response manual.

000057 Loss of Vital AC Inst. Bus / 6 X AA1.02 - Manual control of PZR level 3.8 1 CE/E02 Reactor Trip - Stabilization - X EK1.1 - Components, capacity, and 2.9 1 Recovery / 1 function of emergency systems CE/E06 Loss of Main Feedwater / 4 X EK1.3 - Annunciators and conditions 3.2 1 indicating signals, and remedial actions associated with the (Loss of Feedwater)

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 1

PWR RO Examination Outline Printed: 02/26/2004 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 AK2.04 - Pumps 2.6 1 000032 Loss of Source Range NI / 7 X AA1.01 - Manual restoration of power 3.1* 1 000036 Fuel Handling Accident / 8 X 2.4.49 - Ability to perform without 4.0 1 reference to procedures those actions that require immediate operation of system components and controls.

000060 Accidental Gaseous Radwaste Rel. / 9 X AK2.01 - ARM system, including the 2.6 1 normal radiation-level indications and the operability status 000061 ARM System Alarms / 7 X AA2.01 - ARM panel displays 3.5 1 000068 Control Room Evac. / 8 X AK3.17 - Injection of boric acid into the 3.7 1 RCS CE/A11 RCS Overcooling - PTS / 4 X 2.1.27 - Knowledge of system purpose 2.8 1 and or function.

CE/A13 Natural Circ. / 4 X EK3.3 - Manipulation of controls 3.4 1 required to obtain desired operating results during abnormal, and emergency situations CE/A16 Excess RCS Leakage / 2 X EA1.2 - Operating behavior 3.0 1 characteristics of the facility K/A Category Totals: 0 2 2 2 1 2 Group Point Total: 9 1

PWR RO Examination Outline Printed: 02/26/2004 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 K1.08 - Containment 2.7* 1 isolation 003 Reactor Coolant Pump X A1.07 - RCS temperature and 3.4* 1 pressure 004 Chemical and Volume Control X A2.09 - High primary and/or 3.0 1 secondary activity 004 Chemical and Volume Control X K6.15 - Reason for venting 2.8 1 VCT and pump casings while filling: vents must connect to LRS 005 Residual Heat Removal X A4.03 - RHR temperature, 2.8* 1 PZR heaters and flow, and nitrogen 005 Residual Heat Removal X K4.12 - Lineup for piggyback 3.1* 1 mode with CSS 006 Emergency Core Cooling X 2.1.33 - Ability to recognize 3.4 1 indications for system operating parameters which are entry-level conditions for technical specifications.

006 Emergency Core Cooling X A2.12 - Conditions requiring 4.5 1 actuation of ECCS 007 Pressurizer Relief/Quench Tank X A2.02 - Abnormal pressure 2.6 1 in the PRT 007 Pressurizer Relief/Quench Tank X A4.10 - Recognition of 3.6 1 leaking PORV/code safety 008 Component Cooling Water X A3.01 - Setpoints on 3.2* 1 instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS 010 Pressurizer Pressure Control X K1.05 - PRTS 3.4 1 010 Pressurizer Pressure Control X K5.01 - Determination of 3.5 1 condition of fluid in PZR, using steam tables 012 Reactor Protection X K1.08 - MFW 2.9* 1 012 Reactor Protection X K5.02 - Power density 3.1* 1 013 Engineered Safety Features X 2.1.32 - Ability to explain and 3.4 1 Actuation apply all system limits and precautions.

013 Engineered Safety Features X A1.02 - Containment 3.9 1 Actuation pressure, temperature, and humidity 026 Containment Spray X A1.03 - Containment sump 3.5 1 level 039 Main and Reheat Steam X K4.08 - Interlocks on MSIV 3.3 1 1

PWR RO Examination Outline Printed: 02/26/2004 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 and bypass valves 039 Main and Reheat Steam X K5.08 - Effect of steam 3.6 1 removal on reactivity 059 Main Feedwater X A4.11 - Recovery from 3.1 1 automatic feedwater isolation 061 Auxiliary/Emergency Feedwater X A1.02 - S/G pressure 3.3* 1 064 Emergency Diesel Generator X K2.03 - Control power 3.2* 1 064 Emergency Diesel Generator X K4.03 - Governor valve 2.5 1 operation 073 Process Radiation Monitoring X 2.4.50 - Ability to verify 3.3 1 system alarm setpoints and operate controls identified in the alarm response manual.

076 Service Water X K2.01 - Service water 2.7* 1 076 Service Water X K3.07 - ESF loads 3.7 1 078 Instrument Air X K3.02 - Systems having 3.4 1 pneumatic valves and controls K/A Category Totals: 3 2 2 3 3 1 4 3 1 3 3 Group Point Total: 28 2

PWR RO Examination Outline Printed: 02/26/2004 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 K4.23 - Rod motion inhibit 3.4 1 002 Reactor Coolant X A4.06 - Overflow level of the 2.9 1 RWST 011 Pressurizer Level Control X 2.1.2 - Knowledge of 3.0 1 operator responsibilities during all modes of plant operation.

015 Nuclear Instrumentation X K3.01 - RPS 3.9 1 028 Hydrogen Recombiner and X A2.03 - The hydrogen air 3.4 1 Purge Control concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment 029 Containment Purge X A3.01 - CPS isolation 3.8 1 033 Spent Fuel Pool Cooling X K1.02 - RHRS 2.5 1 035 Steam Generator X A1.02 - S/G pressure 3.5 1 041 Steam Dump/Turbine Bypass X K5.02 - Use of steam tables 2.5 1 Control for saturation temperature and pressure 086 Fire Protection X K6.04 - Fire, smoke, and heat 2.6 1 detectors K/A Category Totals: 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: 10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 02/26/2004 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.19 Ability to use plant computer to obtain and 3.0 1 evaluate parametric information on system or component status.

2.1.20 Ability to execute procedure steps. 4.3 1 2.1.28 Knowledge of the purpose and function of major 3.2 1 system components and controls.

Category Total: 3 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3.0 1 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 Category Total: 2 Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1 radiation control requirements.

2.3.11 Ability to control radiation releases. 2.7 1 Category Total: 2 Emergency Procedures/Plan 2.4.17 Knowledge of EOP terms and definitions. 3.1 1 2.4.24 Knowledge of loss of cooling water procedures. 3.3 1 2.4.31 Knowledge of annunciators alarms and 3.3 1 indications, and use of the response instructions.

Category Total: 3 Generic Total: 10 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 02/26/2004 Date Of Exam: 03/12/2004 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total K A A2 G*

1. 1 0 0 0 0 0 0 0 0 0 4 3 7 Emergency 2 0 0 0 0 0 0 0 0 0 2 3 5 Abnormal Plant Tier 0 0 0 0 0 0 0 0 0 6 6 12 Evolutions Totals 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 4 2.

2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 2 Plant Systems Tier 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 6 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 1 2 2 2 Note:

1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.

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. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category /tier.

6.* 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) 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 columns labeled "K" and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

1

PWR SRO Examination Outline Printed: 02/26/2004 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 / 3 X AA2.22 - Consequences of loss of 4.2 1 pressure in RCS; methods for evaluating pressure loss 000015 RCP Malfunctions / 4 X AA2.10 - When to secure RCPs on loss 3.7 1 of cooling or seal injection 000022 Loss of Rx Coolant Makeup / 2 X 2.1.14 - Knowledge of system status 3.3 1 criteria which require the notification of plant personnel.

000025 Loss of RHR System / 4 X 2.4.49 - Ability to perform without 4.0 1 reference to procedures those actions that require immediate operation of system components and controls.

000038 Steam Gen. Tube Rupture / 3 X EA2.08 - Viable alternatives for placing 4.4 1 plant in safe condition when condenser is not available 000055 Station Blackout / 6 X EA2.02 - RCS core cooling through 4.6 1 natural circulation cooling to S/G cooling 000056 Loss of Off-site Power / 6 X 2.1.33 - Ability to recognize indications 4.0 1 for system operating parameters which are entry-level conditions for technical specifications.

K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7 1

PWR SRO Examination Outline Printed: 02/26/2004 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 000051 Loss of Condenser Vacuum / 4 X AA2.01 - Cause for low vacuum 2.7* 1 condition 000069 Loss of CTMT Integrity / 5 X AA2.01 - Loss of containment integrity 4.3 1 000074 Inad. Core Cooling / 4 X 2.4.6 - Knowledge symptom based EOP 4.0 1 mitigation strategies.

000076 High Reactor Coolant Activity / 9 X 2.1.32 - Ability to explain and apply all 3.8 1 system limits and precautions.

CE/E09 Functional Recovery X 2.2.25 - Knowledge of bases in technical 3.7 1 specifications for limiting conditions for operations and safety limits.

K/A Category Totals: 0 0 0 0 2 3 Group Point Total: 5 1

PWR SRO Examination Outline Printed: 02/26/2004 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 022 Containment Cooling X 2.1.14 - Knowledge of 3.3 1 system status criteria which require the notification of plant personnel.

059 Main Feedwater X A2.04 - Feeding a dry S/G 3.4* 1 062 AC Electrical Distribution X A2.08 - Consequences of 3.0* 1 exceeding voltage limitations 063 DC Electrical Distribution X 2.4.6 - Knowledge symptom 4.0 1 based EOP mitigation strategies.

K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 2 Group Point Total: 4 1

PWR SRO Examination Outline Printed: 02/26/2004 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 016 Non-nuclear Instrumentation X 2.2.25 - Knowledge of bases 3.7 1 in technical specifications for limiting conditions for operations and safety limits.

071 Waste Gas Disposal X A2.05 - Power failure to the 2.6 1 ARM and PRM Systems K/A Category Totals: 0 0 0 0 0 0 0 1 0 0 1 Group Point Total: 2 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 02/26/2004 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.11 Knowledge of less than one hour technical 3.8 1 specification action statements for systems.

Category Total: 1 Equipment Control 2.2.18 Knowledge of the process for managing 3.6 1 maintenance activities during shutdown operations.

2.2.28 Knowledge of new and spent fuel movement 3.5 1 procedures.

Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits and 3.1 1 contamination control, including permissible levels in excess of those authorized.

2.3.8 Knowledge of the process for performing a 3.2 1 planned gaseous radioactive release.

Category Total: 2 Emergency Procedures/Plan 2.4.8 Knowledge of how the event-based 3.7 1 emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs.

2.4.33 Knowledge of the process used track inoperable 2.8 1 alarms.

Category Total: 2 Generic Total: 7 1

Appendix D Operator Actions Form ES-D-2 Facility: Fort Calhoun Scenario No: 1 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: IC# 1 100% Power BOC Turnover: Diesel Generator DG-1 and Charging Pump CH-1B are out of service. Maintain full power operation.

Event No. Malf No. Event Event Type* Description 1 (0 min) COP I - sec S/G steam flow transmitter output fails low T:F908 2 (5 min) COP I - pri Hot leg RTD fails high (tech spec entry)

T:122H2 3 (15 min) ORP C - sec Heater Drain Pump, FW-5B, trips X10I227 4 (20 min) COP I - pri VCT level transmitter fails low JLB218LL 5 (30 min) MFP C - pri CEA drop (tech spec entry)

CRD06 1 6 R - pri T. S. required power reduction N - sec 7 (42 min) ORP C - pri CCW pump, AC-3B, trips (tech spec entry)

X01I392 8 (47 min) MFP C - pri Second CEA drops - Manual Reactor Trip Required CRD06 5 9 (55 min) MFP M - all Steam Generator Tube Rupture SGN01A 10 (preset) COP C - sec MSIV on ruptured S/G will not close RSGH041A

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Actions Form ES-D-2 Facility: Fort Calhoun Scenario No: 2 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: IC #1 100% Power BOC Turnover: Diesel driven AFW pump, FW-54 and charging pump CH-1B are Out of Service.

Maintain power.

Event No. Malf No. Event Event Type* Description 1 (+2 min) COP I - sec PT-910 fails high causing turbine bypass valve to open T:P910 2 (+5 min) COP C - pri Charging Pump, CH-1C, Trips (tech spec entry)

NCVPCH1 C

3 (+10 min) MFP Wide Range NI channel D fails (tech spec entry)

NIS02D 4 (+15 min) COP I - pri Pressurizer Pressure channel, 103Y, fails low T:P103Y 5 (+20 min) MFP C - sec High turbine vibration caused by inadequate oil cooling TUR05F 6 (+28 min) MFP M - all Loss of Offsite Power SWD02A SWD02B 7 (preset) File M - all ATWS - manual trip required ATWAS_P LUS1 8 (preset) RFP C - sec Emergency Feedwater Storage Tank line is blocked AFW10A causing a total loss of Feedwater (once-through cooling required) 9 (20% WR M - all Initiate Once-Through Cooling level on both steam (Note: Examiner may direct simulator operator to run a file generators) to lower steam generator levels to 20%, once through cooling initiation level, if required for time limitations)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Actions Form ES-D-2 Facility: Fort Calhoun Scenario No: 3 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: IC# 7 BOC 50% Power, FW-54 Out of Service Turnover: Diesel driven FW pump, FW-54 is out of service. Maintain power Scenario objective: Evaluate ISRO candidates in the primary and secondary positions with a surrogate acting as SRO Event No. Malf No. Event Event Type* Description 1 (+2 min) COP I - pri Controlling pressurizer level channel, 101Y, fails low T:L101Y 2 (+7 min) COP I - sec Steam generator RC-2B level channel, 906Y, fails high T:L906Y 3 (+13 min) MFP C - pri Reactor Coolant Pump, RC-3B, lower seal failure RCP09B 4 (+18 min) COP I - pri Letdown pressure transmitter PT-210 fails low T:P210 5 (+24 min) MFP Reactor Coolant Pump, RC-3B, middle seal failure RCP10B 6 R - pri Emergency shutdown N - sec 7 (+35 min) RFP C - sec Running Bearing water pump, AC-9A, trips BCW10A 8 (+40 min) MFP M - all Loss of Coolant Accident RCS01C 0.2%

9 (preset) MFP C - sec Turbine trip failure EHC02 10 (preset) File C - pri HPSI loop injection valves fail to open HPSI-LOOP-INJ-PULL

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Actions Form ES-D-2 Facility: Fort Calhoun Scenario No: 4 (spare) Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: IC#1 100% Power BOC Ensure FW-5B and FW-5C are the running Heater Drain Pumps.

Turnover: LPSI pump SI-1B is Out of Service for bearing replacement Event No. Malf No. Event Event Type* Description 1 (+3 min) MFP I - pri Power range nuclear instrumentation channel C fails (tech NIS03F spec entry) 2 (+10 min) COP I - sec FW flow channel on RC-2A fails low T:F1101 3 (+15 min) MFP C - sec Diesel Generator, D/G-1, radiator leak (tech spec entry)

DSG06A 4 (+25 min) COP I - pri Letdown HX CCW outlet temperature transmitter fails low T:T2897 5 (+30 min) MFP C -sec Loss of 161 KV SWD02B 6 (+40 min) MFP M - all Steam line break inside containment MSS01B 25%

300 sec ramp 7 (preset) RFP C -sec CW-1C breaker fails to trip preventing D/G-2 breaker from CWS10N closing 8 (preset) MFP C - pri CPHS fails to actuate ESF02A ESF 02B

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Date of Examination: 3/15/04 Examination Level: RO / SRO Operating Test Number: _____________

Administrative Topic Describe activity to be performed (See Note)

Manually determine dilution volume needed to raise power level.

Conduct of Operations (K/A 2.1.25 - Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

RO Imp: 2.8; CFR: 41.10/43.5/45.12)

Determine maximum allowable Diesel/Generator load based on weather Conduct of Operations conditions.

(K/A 2.1.32 - Ability to explain and apply all system limits and precautions. RO Imp: 3.4; CFR: 41.10/43.2/45.12)

Use P&IDs to determine equipment affected by closure of instrument air Equipment Control valve.

(K/A 2.2.13 - Knowledge of tagging and clearance procedures. RO Imp:

3.6; CFR 41.10/45.13)

Radiation Area entry and exit with EAD alarm.

Radiation Control (K/A 2.3.1 - Knowledge of 10 CFR:20 and related facility radiation control requirements. RO Imp: 2.6; CFR: 41.12/43.4/45.9/45.10)

Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Date of Examination: 3/15/04 Examination Level: RO / SRO Operating Test Number: _____________

Administrative Topic Describe activity to be performed (See Note)

SRO Review of shutdown margin calculation with inoperable CEA.

Conduct of Operations (K/A: 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation; SRO Imp: 3.7; CFR: 43.5/45.12/45.13)

Determine Raw Water system operability based on technical specifications Conduct of Operations and TDB III.41.

(K/A: 2.1.12 - Ability to apply technical specifications for a system; SRO Imp: 4.0; CFR: 43.2/43.5/45.3)

SRO Review of Surveillance Test results.

Equipment Control (K/A: 2.2.12 - Knowledge of surveillance procedures; SRO Imp: 3.4; CFR:

41.10/45.13)

Determine primary to secondary leakage from plant parameters and actions Radiation Control required to control offsite releases (K/A: 2.3.11 - Ability to control radiation releases; SRO Imp: 3.2; CFR 45.9/45.10)

Emergency event classification and Protective Action Recommendations Emergency Plan (K/A 2.4.41 - Knowledge of the emergency action level thresholds and classifications. SRO Imp: 4.1; CFR 43.5/45.11) (K/A 2.4.44 - Knowledge of emergency plan protective action recommendations SRO Imp: 4.0; CFR 43.5/45.11)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination: 3/15/04 Exam Level: RO / SRO(I) / SRO(U) Operating Test No. _____________

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Establish Simultaneous Hot and Cold leg injection - new N, E, A ,S 2 (K/A 006000 A4.05 3.9/3.8)

b. Shutdown a Reactor Coolant Pump - 0613 (modified) M, A, S 4P (K/A 003000 A4.06 2.9/2.9)

c. Operate Containment Hydrogen Analyzer - 0156 D, E 5 (K/A 028000 A1.01 3.4/3.8) d.Restoration of offsite electrical power following loss of offsite D, E 6 power - 0026 (K/A 064000 A4.07 3.4/3.4)

e. Perform manual trip check - 0654 D, S 7 (K/A 012000 A4.01 4.5/4.5)

f. Raise RCS Pressure with PORV Open Failure - 0621 D, A 3 (K/A 010000 A2.03 4.1/4.2)

g. Recover misaligned Control Rod - new N, A 1 (K/A 001000 A2.03 3.5/4.2)

h. Startup Containment Purge - 0704 (modified) M, A, S 8 (K/A 029000 A2.03 2.7/3.1)

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

a. Establish RW Backup to SI Pumps - 0010-RW D, R, E 4S (K/A 076000 A4.04 3.5/3.5)

b. Emergency Start of Diesel Fire Pump - 0450 D, E, A 8 (K/A 086000 A4.01 3.3/3.3)

c. Minimize DC Loads - 0304 (time critical) D, E 6 (K/A 063000 A1.01 2.5/3.3)

• Type Codes: (D)irect from bank, (M)odified from Bank, (N)ew, (A)lternate path, (S)hutdown or low power, (R)CA , (E)mergency or abnormal condition

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination: 3/15/04 Exam Level: RO / SRO(I) / SRO(U) Operating Test No. _____________

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Establish Simultaneous Hot and Cold leg injection - new N, E, A, S 2 (K/A 006000 A4.05 3.9/3.8)

b. Shutdown a Reactor Coolant Pump - 0613 (modified) M, A, S 4P (K/A 003000 A4.06 2.9/2.9)

c. Operate Containment Hydrogen Analyzer - 0156 D, E 5 (K/A 028000 A1.01 3.4/3.8) d.Restoration of offsite electrical power following loss of offsite D, E 6 power - 0026 (K/A 064000 A4.07 3.4/3.4) e.

f. Raise RCS Pressure with PORV Open Failure - 0621 D, A 3 (K/A 010000 A2.03 4.1/4.2)

g. Recover misaligned Control Rod - new N, A 1 (K/A 001000 A2.03 3.5/4.2)

h. Startup Containment Purge - 0704 (modified) M, A, S 8 (K/A 029000 A2.03 2.7/3.1)

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

a. Establish RW Backup to SI Pumps - 0010-RW D, R, E 4S (K/A 076000 A4.04 3.5/3.5)

b. Emergency Start of Diesel Fire Pump - 0450 D, E, A 8 (K/A 086000 A4.01 3.3/3.3)

c. Minimize DC Loads - 0304 (time critical) D, E 6 (K/A 063000 A1.01 2.5/3.3)

• Type Codes: (D)irect from bank, (M)odified from Bank, (N)ew, (A)lternate path, (S)hutdown or low power, (R)CA , (E)mergency or abnormal condition

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination: 3/15/04 Exam Level: RO / SRO(I) / SRO(U) Operating Test No. _____________

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Establish Simultaneous Hot and Cold leg injection - new N, E, A, S 2 (K/A 006000 A4.05 3.9/3.8) b.

c. Operate Containment Hydrogen Analyzer - 0156 D, E 5 (K/A 028000 A1.01 3.4/3.8) d.

e.

f.

g.

h.

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

a. Establish RW Backup to SI Pumps - 0010-RW D, R, E 4S (K/A 076000 A4.04 3.5/3.5)

b. Emergency Start of Diesel Fire Pump - 0450 D, E, A 8 (K/A 086000 A4.01 3.3/3.3)

c. Minimize DC Loads - 0304 (time critical) D, E 6 (K/A 063000 A1.01 2.5/3.3)

• Type Codes: (D)irect from bank, (M)odified from Bank, (N)ew, (A)lternate path, (S)hutdown or low-Power, (R)CA , (E)mergency or abnormal condition