ML041130155
| 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
02/26/2004 Printed:
ES-401 Facility:
Fort Calhoun PWR Examination Outline Form ES-401-2 3
3 3
3 3
3 0
2 2
2 1
2 3
5 5
5 4
5 3
2 2
3 3
1 4
3 1
3 3
1 0
1 1
1 1
1 1
1 1
1 4
2 3
4 4
2 5
4 2
4 4
3 2
2 3
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.
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.
Note:
Date Of Exam:
03/12/2004 28 18 9
27 10 38 10 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.
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.
SRO-Only Points K
A A2 G*
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
1 2
3 4
0 0
0 0
0 0
0 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
02/26/2004 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 EA2.03 - Reactor trip breaker position 4.2 1
X 000007 Reactor Trip - Stabilization -
Recovery / 1 AK3.04 - RCP tripping requirements 4.2 1
X 000008 Pressurizer Vapor Space Accident / 3 EA2.06 - Whether PZR water inventory loss is imminent 3.8 1
X 000009 Small Break LOCA / 3 EK3.21 - Actions contained in EOP for small break LOCA/leak 4.2 1
X 000009 Small Break LOCA / 3 AK2.07 - RCP seals 2.9 1
X 000015 RCP Malfunctions / 4 AA1.07 - Flow rates to the components and systems that are serviced by the CCWS; interactions among the components 2.9 1
X 000026 Loss of Component Cooling Water /
8 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.0 1
X 000027 Pressurizer Pressure Control System Malfunction / 3 EK2.06 - Breakers, relays, and disconnects 2.9*
1 X
000029 ATWS / 1 EK3.03 - Automatic actions associated with high radioactivity in S/G sample lines 3.6*
1 X
000038 Steam Gen. Tube Rupture / 3 AK2.01 - Valves 2.6*
1 X
000040 Steam Line Rupture - Excessive Heat Transfer / 4 AA1.24 - Main steam header pressure gauges 3.8 1
X 000040 Steam Line Rupture - Excessive Heat Transfer / 4 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.3 1
X 000054 Loss of Main Feedwater / 4 EK1.01 - Effect of battery discharge rates on capacity 3.3 1
X 000055 Station Blackout / 6 AA2.20 - AFW flow indicator 3.9 1
X 000056 Loss of Off-site Power / 6 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.3 1
X 000057 Loss of Vital AC Inst. Bus / 6 AA1.02 - Manual control of PZR level 3.8 1
X 000057 Loss of Vital AC Inst. Bus / 6 EK1.1 - Components, capacity, and function of emergency systems 2.9 1
X CE/E02 Reactor Trip - Stabilization -
Recovery / 1 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Feedwater) 3.2 1
X CE/E06 Loss of Main Feedwater / 4 18 3
3 3
3 3
3 K/A Category Totals:
Group Point Total:
1
02/26/2004 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 AK2.04 - Pumps 2.6 1
X 000024 Emergency Boration / 1 AA1.01 - Manual restoration of power 3.1*
1 X
000032 Loss of Source Range NI / 7 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.0 1
X 000036 Fuel Handling Accident / 8 AK2.01 - ARM system, including the normal radiation-level indications and the operability status 2.6 1
X 000060 Accidental Gaseous Radwaste Rel. / 9 AA2.01 - ARM panel displays 3.5 1
X 000061 ARM System Alarms / 7 AK3.17 - Injection of boric acid into the RCS 3.7 1
X 000068 Control Room Evac. / 8 2.1.27 - Knowledge of system purpose and or function.
2.8 1
X CE/A11 RCS Overcooling - PTS / 4 EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations 3.4 1
X CE/A13 Natural Circ. / 4 EA1.2 - Operating behavior characteristics of the facility 3.0 1
X CE/A16 Excess RCS Leakage / 2 9
0 2
2 2
1 2
K/A Category Totals:
Group Point Total:
1
02/26/2004 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 K1.08 - Containment isolation 2.7*
1 X
003 Reactor Coolant Pump A1.07 - RCS temperature and pressure 3.4*
1 X
003 Reactor Coolant Pump A2.09 - High primary and/or secondary activity 3.0 1
X 004 Chemical and Volume Control K6.15 - Reason for venting VCT and pump casings while filling: vents must connect to LRS 2.8 1
X 004 Chemical and Volume Control A4.03 - RHR temperature, PZR heaters and flow, and nitrogen 2.8*
1 X
005 Residual Heat Removal K4.12 - Lineup for piggyback mode with CSS 3.1*
1 X
005 Residual Heat Removal 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
3.4 1
X 006 Emergency Core Cooling A2.12 - Conditions requiring actuation of ECCS 4.5 1
X 006 Emergency Core Cooling A2.02 - Abnormal pressure in the PRT 2.6 1
X 007 Pressurizer Relief/Quench Tank A4.10 - Recognition of leaking PORV/code safety 3.6 1
X 007 Pressurizer Relief/Quench Tank A3.01 - Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS 3.2*
1 X
008 Component Cooling Water K1.05 - PRTS 3.4 1
X 010 Pressurizer Pressure Control K5.01 - Determination of condition of fluid in PZR, using steam tables 3.5 1
X 010 Pressurizer Pressure Control K1.08 - MFW 2.9*
1 X
012 Reactor Protection K5.02 - Power density 3.1*
1 X
012 Reactor Protection 2.1.32 - Ability to explain and apply all system limits and precautions.
3.4 1
X 013 Engineered Safety Features Actuation A1.02 - Containment pressure, temperature, and humidity 3.9 1
X 013 Engineered Safety Features Actuation A1.03 - Containment sump level 3.5 1
X 026 Containment Spray K4.08 - Interlocks on MSIV 3.3 1
X 039 Main and Reheat Steam 1
02/26/2004 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 and bypass valves K5.08 - Effect of steam removal on reactivity 3.6 1
X 039 Main and Reheat Steam A4.11 - Recovery from automatic feedwater isolation 3.1 1
X 059 Main Feedwater A1.02 - S/G pressure 3.3*
1 X
061 Auxiliary/Emergency Feedwater K2.03 - Control power 3.2*
1 X
064 Emergency Diesel Generator K4.03 - Governor valve operation 2.5 1
X 064 Emergency Diesel Generator 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.3 1
X 073 Process Radiation Monitoring K2.01 - Service water 2.7*
1 X
076 Service Water K3.07 - ESF loads 3.7 1
X 076 Service Water K3.02 - Systems having pneumatic valves and controls 3.4 1
X 078 Instrument Air 28 3
2 2
4 3
3 K/A Category Totals:
3 3
1 1
3 Group Point Total:
2
02/26/2004 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 K4.23 - Rod motion inhibit 3.4 1
X 001 Control Rod Drive A4.06 - Overflow level of the RWST 2.9 1
X 002 Reactor Coolant 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation.
3.0 1
X 011 Pressurizer Level Control K3.01 - RPS 3.9 1
X 015 Nuclear Instrumentation A2.03 - The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment 3.4 1
X 028 Hydrogen Recombiner and Purge Control A3.01 - CPS isolation 3.8 1
X 029 Containment Purge K1.02 - RHRS 2.5 1
X 033 Spent Fuel Pool Cooling A1.02 - S/G pressure 3.5 1
X 035 Steam Generator K5.02 - Use of steam tables for saturation temperature and pressure 2.5 1
X 041 Steam Dump/Turbine Bypass Control K6.04 - Fire, smoke, and heat detectors 2.6 1
X 086 Fire Protection 10 1
0 1
1 1
1 K/A Category Totals:
1 1
1 1
1 Group Point Total:
1
Facility:
Fort Calhoun Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 02/26/2004 Printed:
PWR RO Examination Outline 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status.
3.0 1
Conduct of Operations 2.1.20 Ability to execute procedure steps.
4.3 1
2.1.28 Knowledge of the purpose and function of major system components and controls.
3.2 1
3 Category Total:
2.2.12 Knowledge of surveillance procedures.
3.0 1
Equipment Control 2.2.13 Knowledge of tagging and clearance procedures.
3.6 1
2 Category Total:
2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.
2.6 1
Radiation Control 2.3.11 Ability to control radiation releases.
2.7 1
2 Category Total:
2.4.17 Knowledge of EOP terms and definitions.
3.1 1
Emergency Procedures/Plan 2.4.24 Knowledge of loss of cooling water procedures.
3.3 1
2.4.31 Knowledge of annunciators alarms and indications, and use of the response instructions.
3.3 1
3 Category Total:
10 Generic Total:
1
02/26/2004 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.
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.
Note:
Date Of Exam:
03/12/2004 0
0 0
0 0
0 0
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.
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.
SRO-Only Points K
A A2 G*
0 0
4 3
0 0
2 3
0 0
6 6
0 0
2 2
0 0
1 1
0 0
3 3
1 2
2 2
1 2
3 4
12 5
7 4
2 6
7 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
02/26/2004 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 AA2.22 - Consequences of loss of pressure in RCS; methods for evaluating pressure loss 4.2 1
X 000008 Pressurizer Vapor Space Accident / 3 AA2.10 - When to secure RCPs on loss of cooling or seal injection 3.7 1
X 000015 RCP Malfunctions / 4 2.1.14 - Knowledge of system status criteria which require the notification of plant personnel.
3.3 1
X 000022 Loss of Rx Coolant Makeup / 2 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.0 1
X 000025 Loss of RHR System / 4 EA2.08 - Viable alternatives for placing plant in safe condition when condenser is not available 4.4 1
X 000038 Steam Gen. Tube Rupture / 3 EA2.02 - RCS core cooling through natural circulation cooling to S/G cooling 4.6 1
X 000055 Station Blackout / 6 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
4.0 1
X 000056 Loss of Off-site Power / 6 7
0 0
0 0
4 3
K/A Category Totals:
Group Point Total:
1
02/26/2004 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 AA2.01 - Cause for low vacuum condition 2.7*
1 X
000051 Loss of Condenser Vacuum / 4 AA2.01 - Loss of containment integrity 4.3 1
X 000069 Loss of CTMT Integrity / 5 2.4.6 - Knowledge symptom based EOP mitigation strategies.
4.0 1
X 000074 Inad. Core Cooling / 4 2.1.32 - Ability to explain and apply all system limits and precautions.
3.8 1
X 000076 High Reactor Coolant Activity / 9 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
3.7 1
X CE/E09 Functional Recovery 5
0 0
0 0
2 3
K/A Category Totals:
Group Point Total:
1
02/26/2004 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 2.1.14 - Knowledge of system status criteria which require the notification of plant personnel.
3.3 1
X 022 Containment Cooling A2.04 - Feeding a dry S/G 3.4*
1 X
059 Main Feedwater A2.08 - Consequences of exceeding voltage limitations 3.0*
1 X
062 AC Electrical Distribution 2.4.6 - Knowledge symptom based EOP mitigation strategies.
4.0 1
X 063 DC Electrical Distribution 4
0 0
0 0
2 2
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1
02/26/2004 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 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
3.7 1
X 016 Non-nuclear Instrumentation A2.05 - Power failure to the ARM and PRM Systems 2.6 1
X 071 Waste Gas Disposal 2
0 0
0 0
1 1
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1
Facility:
Fort Calhoun Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 02/26/2004 Printed:
PWR SRO Examination Outline 2.1.11 Knowledge of less than one hour technical specification action statements for systems.
3.8 1
Conduct of Operations 1
Category Total:
2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations.
3.6 1
Equipment Control 2.2.28 Knowledge of new and spent fuel movement procedures.
3.5 1
2 Category Total:
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
3.1 1
Radiation Control 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.
3.2 1
2 Category Total:
2.4.8 Knowledge of how the event-based emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs.
3.7 1
Emergency Procedures/Plan 2.4.33 Knowledge of the process used track inoperable alarms.
2.8 1
2 Category Total:
7 Generic Total:
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 Type*
Event Description 1 (0 min)
COP T:F908 I - sec S/G steam flow transmitter output fails low 2 (5 min)
COP T:122H2 I - pri Hot leg RTD fails high (tech spec entry) 3 (15 min)
ORP X10I227 C - sec Heater Drain Pump, FW-5B, trips 4 (20 min)
COP JLB218LL I - pri VCT level transmitter fails low 5 (30 min)
MFP CRD06 1 C - pri CEA drop (tech spec entry) 6 R - pri N - sec T. S. required power reduction 7 (42 min)
ORP X01I392 C - pri CCW pump, AC-3B, trips (tech spec entry) 8 (47 min)
MFP CRD06 5 C - pri Second CEA drops - Manual Reactor Trip Required 9 (55 min)
MFP SGN01A M - all Steam Generator Tube Rupture 10 (preset)
COP RSGH041A C - sec MSIV on ruptured S/G will not close
- (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 Type*
Event Description 1 (+2 min)
COP T:P910 I - sec PT-910 fails high causing turbine bypass valve to open 2 (+5 min)
COP NCVPCH1 C
C - pri Charging Pump, CH-1C, Trips (tech spec entry) 3 (+10 min)
MFP NIS02D Wide Range NI channel D fails (tech spec entry) 4 (+15 min)
COP T:P103Y I - pri Pressurizer Pressure channel, 103Y, fails low 5 (+20 min)
MFP TUR05F C - sec High turbine vibration caused by inadequate oil cooling 6 (+28 min)
MFP SWD02A SWD02B M - all Loss of Offsite Power 7 (preset)
File ATWAS_P LUS1 M - all ATWS - manual trip required 8 (preset)
RFP AFW10A C - sec Emergency Feedwater Storage Tank line is blocked causing a total loss of Feedwater (once-through cooling required) 9 (20% WR level on both steam generators)
M - all Initiate Once-Through Cooling (Note: Examiner may direct simulator operator to run a file 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 Type*
Event Description 1 (+2 min)
COP T:L101Y I - pri Controlling pressurizer level channel, 101Y, fails low 2 (+7 min)
COP T:L906Y I - sec Steam generator RC-2B level channel, 906Y, fails high 3 (+13 min)
MFP RCP09B C - pri Reactor Coolant Pump, RC-3B, lower seal failure 4 (+18 min)
COP T:P210 I - pri Letdown pressure transmitter PT-210 fails low 5 (+24 min)
MFP RCP10B Reactor Coolant Pump, RC-3B, middle seal failure 6
R - pri N - sec Emergency shutdown 7 (+35 min)
RFP BCW10A C - sec Running Bearing water pump, AC-9A, trips 8 (+40 min)
MFP RCS01C 0.2%
M - all Loss of Coolant Accident 9 (preset)
MFP EHC02 C - sec Turbine trip failure 10 (preset)
File HPSI-LOOP-INJ-PULL C - pri HPSI loop injection valves fail to open
- (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 Type*
Event Description 1 (+3 min)
MFP NIS03F I - pri Power range nuclear instrumentation channel C fails (tech spec entry) 2 (+10 min)
COP T:F1101 I - sec FW flow channel on RC-2A fails low 3 (+15 min)
MFP DSG06A C - sec Diesel Generator, D/G-1, radiator leak (tech spec entry) 4 (+25 min)
COP T:T2897 I - pri Letdown HX CCW outlet temperature transmitter fails low 5 (+30 min)
MFP SWD02B C -sec Loss of 161 KV 6 (+40 min)
MFP MSS01B 25%
300 sec ramp M - all Steam line break inside containment 7 (preset)
RFP CWS10N C -sec CW-1C breaker fails to trip preventing D/G-2 breaker from closing 8 (preset)
MFP ESF02A ESF 02B C - pri CPHS fails to actuate
- (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 (See Note)
Describe activity to be performed Conduct of Operations Manually determine dilution volume needed to raise power level.
(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)
Conduct of Operations Determine maximum allowable Diesel/Generator load based on weather 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)
Equipment Control Use P&IDs to determine equipment affected by closure of instrument air valve.
(K/A 2.2.13 - Knowledge of tagging and clearance procedures. RO Imp:
3.6; CFR 41.10/45.13)
Radiation Control Radiation Area entry and exit with EAD alarm.
(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 (See Note)
Describe activity to be performed Conduct of Operations SRO Review of shutdown margin calculation with inoperable CEA.
(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)
Conduct of Operations Determine Raw Water system operability based on technical specifications 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)
Equipment Control SRO Review of Surveillance Test results.
(K/A: 2.2.12 - Knowledge of surveillance procedures; SRO Imp: 3.4; CFR:
41.10/45.13)
Radiation Control Determine primary to secondary leakage from plant parameters and actions 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 Plan Emergency event classification and Protective Action Recommendations (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 (K/A 006000 A4.05 3.9/3.8)
N, E, A,S 2
- b. Shutdown a Reactor Coolant Pump - 0613 (modified)
(K/A 003000 A4.06 2.9/2.9)
M, A, S 4P
- c. Operate Containment Hydrogen Analyzer - 0156 (K/A 028000 A1.01 3.4/3.8)
D, E 5
d.Restoration of offsite electrical power following loss of offsite power - 0026 (K/A 064000 A4.07 3.4/3.4)
D, E 6
- e. Perform manual trip check - 0654 (K/A 012000 A4.01 4.5/4.5)
D, S 7
D, A 3
- g. Recover misaligned Control Rod - new (K/A 001000 A2.03 3.5/4.2)
N, A 1
- h. Startup Containment Purge - 0704 (modified)
(K/A 029000 A2.03 2.7/3.1)
M, A, S 8
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
D, R, E 4S
- b. Emergency Start of Diesel Fire Pump - 0450 (K/A 086000 A4.01 3.3/3.3)
D, E, A 8
- c. Minimize DC Loads - 0304 (time critical)
(K/A 063000 A1.01 2.5/3.3)
D, E 6
- 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 (K/A 006000 A4.05 3.9/3.8)
N, E, A, S 2
- b. Shutdown a Reactor Coolant Pump - 0613 (modified)
(K/A 003000 A4.06 2.9/2.9)
M, A, S 4P
- c. Operate Containment Hydrogen Analyzer - 0156 (K/A 028000 A1.01 3.4/3.8)
D, E 5
d.Restoration of offsite electrical power following loss of offsite power - 0026 (K/A 064000 A4.07 3.4/3.4)
D, E 6
- e.
D, A 3
- g. Recover misaligned Control Rod - new (K/A 001000 A2.03 3.5/4.2)
N, A 1
- h. Startup Containment Purge - 0704 (modified)
(K/A 029000 A2.03 2.7/3.1)
M, A, S 8
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
D, R, E 4S
- b. Emergency Start of Diesel Fire Pump - 0450 (K/A 086000 A4.01 3.3/3.3)
D, E, A 8
- c. Minimize DC Loads - 0304 (time critical)
(K/A 063000 A1.01 2.5/3.3)
D, E 6
- 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 (K/A 006000 A4.05 3.9/3.8)
N, E, A, S 2
- b.
- c. Operate Containment Hydrogen Analyzer - 0156 (K/A 028000 A1.01 3.4/3.8)
D, E 5
- d.
- e.
- f.
- g.
- h.
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
D, R, E 4S
- b. Emergency Start of Diesel Fire Pump - 0450 (K/A 086000 A4.01 3.3/3.3)
D, E, A 8
- c. Minimize DC Loads - 0304 (time critical)
(K/A 063000 A1.01 2.5/3.3)
D, E 6
- 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