ML052300129
| ML052300129 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/25/2006 |
| From: | Division of Reactor Safety IV |
| To: | |
| References | |
| 50-285/05-301 | |
| Download: ML052300129 (86) | |
Text
Fort Calhoun Station 2005 NRC Hot License Exam Outline Submitted to Mr. Tom McKernon, Chief Examiner Scheduled Exam Dates : 7/8/05 - 7/15/05
2 Contents of Outline Proposed Schedule Outline Introduction Written Exam Outline RO Written Exam Sample Plan (ES-401-2 and ES-401-3 forms, standard and enhanced versions)
SRO Written Exam Sample Plan (ES-401-2 and ES-401-3 forms, standard and enhanced versions)
Record of Rejected K/As (enhanced form for ES-401-4)
Administrative Topics Outline Form ES-301-1 (RO)
Walk-Through Test Outline RO Form ES-301-2 SRO-I Form ES-301-2 SRO-U Form ES-301-2 Simulator Scenario Outline ES-D-1 forms for all scenarios ES-301-5 forms ES-301-6 forms Copy of Form ES 201 -3 security agreement as it exists to date Form ES-201-2 Examination Outline Quality Checklist
3 Preliminary Schedule for FCS Exam Friday - 07/08/05 0800- 1300 All take written exam Monday - 07/11/05 1300 - 1500 Simulator Scenario One ( USRO1, RO1, RO3) 1500 - 1700 Simulator Scenario One ( USRO2, RO4, RO6) 1700 - 1900 Simulator Scenario One ( ISRO2, ISRO1, ISRO3)
Tuesday - 07/12/05 0700 - 0900 Simulator Scenario Two (USRO1, RO2, RO1) 0900 - 1100 Simulator Scenario Two (USRO2, RO5, RO4) 1100 - 1200 Lunch 1200 - 1500 RO Admin 1500 - 1700 Simulator Scenario Two (ISRO3, ISRO2, ISRO1)
Wedensday - 07/13/05 0700 - 0900 Simulator Scenario Three (USRO1, RO3, RO2) 0900 - 1100 Simulator Scenario Three (USRO2, RO6, RO5) 1100 - 1200 Lunch 1200 - 1500 SRO Admin 1500 - 1700 Simulator Scenario Three (ISRO1, ISRO3, ISRO2)
Thursday - 07/14/05
4 0700 - 0900 Simulator JPM set 1 (RO1, RO2) 0900 - 1100 Simulator JPM set 1 (RO3, RO4) 1100 - 1200 Lunch 1200 - 1400 Simulator JPM set 1 (RO5, RO6) 1400 - 1600 Simulator JPM set 1 (USRO1, USRO2) 1600 - 1800 Simulator JPM set 1 (ISRO1, ISRO2) 1800 - 1900 Simulator JPM set 1 (ISRO3)
Friday - 07/15/05 0700 - 0900 Simulator JPM set 1 (RO1, RO2) In-Plant JPMs (USRO1, USRO2) 0900 - 1100 Simulator JPM set 1 (RO3, RO4) In-Plant JPMs (RO1, RO2) 1100 - 1200 Lunch 1200 - 1400 Simulator JPM set 1 (RO5, RO6) In-Plant JPMs (RO3, RO4) 1400 - 1600 Simulator JPM set 1 (ISRO1, ISRO2) In-Plant JPMs (RO5, RO6) 1600 - 1800 Simulator JPM set 1 (ISRO3) In Plant JPMs (ISRO1, ISRO2) 1800 - 1900 In-Plant JPMs (ISRO3)
5 Outline Development for 7/2005 Fort Calhoun NRC Exam This exam outline was developed in accordance with NUREG-1021, Rev 9.
Written Exam Outline Fort Calhoun has developed a methodology to ensure that the selection of K/A items for the written exam is random and unbiased. The written exam outline was developed using a Microsoft Access database. All K/A items from NUREG-1122, Rev 2 are contained in a table within the database. Items which clearly are not applicable to Fort Calhoun are assigned a flag to prevent them from being sampled. Flagged items are selected using guidance provided in ES-401, attachment 2. Flagged items include the Ice Condenser System K/A=s, Non-Combustion Engineering vender specific EPE/APE K/A=s, and K/A=s only associated with multi-unit plants.
The sample plan is developed as follows:
A module is run that assigns a random number to each item in the K/A catalog. This module uses a Arandomize@ routine to ensure that the pattern of random numbers is unique.
A query is run that presents K/A items belonging to the tier and group being sampled ordered by their associated random number. Minimum and maximum numbers are assigned to topics and categories to prevent over and under sampling. Items are entered in the sample plan as ordered, subject to the pre-established minimums and maximums. If a sampled K/A item has an importance value less than 2.5 with no FCS specific priority, is not applicable to Fort Calhoun or not appropriate for the written exam, it will be tagged and included in the Record of Rejected K/As along with the reason for rejection. This sampling process is repeated until the tier/group has the required number of items.
This procedure is repeated for each tier/group combination.
Additional items are selected for the SRO only questions to meet the SRO tier/group requirements. These items are also presented in order of their associated random number.
An additional requirement, for this step, is that the selected K/A items must be associated with 10 CFR 55.43 items.
In addition to the ES-401-2 and ES-401-3 forms, a more detailed listing of the selected K/A item including the full text and a cross reference to the applicable 10 CFR 55.41/43/45 items is provided.
6 Operating Exam Outline The Fort Calhoun APRA Summary Notebook@ was used as a resource to ensure that risk-significant items identified in the Fort Calhoun IPE are reflected in the exam. The following risk significant initiating events are included in the operating exams:
Steam Generator Tube Rupture Station Blackout Loss of Coolant Accident It also resulted in the following risk-significant operator actions being evaluated:
Manually opening a closed breaker to allow D/G to power vital bus.
Minimizing DC loads following a loss of offsite power.
Emergency Boration Emergency Start of a Diesel-Generator Determination of minimum HPSI flow in response to a clogged containment sump strainer All four simulator scenarios are new.
Audit Exam There will be no duplication of questions, scenarios, system JPMs or administrative JPMs between the audit exam and the license exam.
ES-401, Page 21 of 33 ES-401 PWR Examination Outline Form ES-401-2 l
Facility:
Date of Exam:
Tier Group RO K/A Category Points l
SRO-Only Points l
K 1
K 2
K 3
K 4
K 5
K 6
A 1
A 2
A 3
A 4
G Total A2 l
G*
l Total l
1.
Emergency &
Abnormal Plant Evolutions 1
N/A N/A 18 l
6 l
2 9
l 4
l Tier Totals 27 l
10 l
2.
Plant Systems 1
28 l
5 l
2 10 l
3 l
Tier Totals 38 l
8 l
- 3. Generic Knowledge and Abilities l
Categories l
1 2
3 4
10 l
1 l
2 l
3 l
4 l
7 l
l l
Note:
1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO l
and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals l
in each K/A category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
l 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply l
at the facility should be deleted and justified; operationally important, site-specific systems that are not included l
on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination l
of inappropriate K/A statements.
l 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group l
before selecting a second topic for any system or evolution.
l 5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
l Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
l 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
l 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 l
must be relevant to the applicable evolution or system.
l 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) l for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals l
for each category in the table above. Use duplicate pages for RO and SRO-only exams.
l 9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, l
and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
l 2
1 4
4 3
4 1
3 1
2 0
2 3
4 5
6 3
6 3
1 2
3 2
1 3
3 4
3 3
2 1
1 0
0 2
1 1
0 1
1 5
2 3
3 2
3 4
4 4
4 4
3 2
2 3
Fort Calhoun 07/11/05
03/29/2005 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 AA1.06 - Control of PZR level 3.6 1
X 000008 Pressurizer Vapor Space Accident /
3 EA2.08 - Letdown isolation valve position indication 2.9*
1 X
000009 Small Break LOCA / 3 2.4.6 - Knowledge symptom based EOP mitigation strategies.
3.1 1
X 000011 Large Break LOCA / 3 AA1.16 - Low-power reactor trip block status lights 3.2*
1 X
000015 RCP Malfunctions / 4 AA1.03 - PZR level trend 3.2 1
X 000022 Loss of Rx Coolant Makeup / 2 AK2.03 - Service water or closed cooling water pumps 2.7 1
X 000025 Loss of RHR System / 4 AK3.02 - The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 3.6 1
X 000026 Loss of Component Cooling Water /
8 AA2.07 - Makeup flow indication 3.1 1
X 000027 Pressurizer Pressure Control System Malfunction / 3 EK1.03 - Natural circulation 3.9 1
X 000038 Steam Gen. Tube Rupture / 3 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 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
3.9 1
X 000055 Station Blackout / 6 AA1.02 - ESF bus synchronization select switch to close bus tie breakers 4.0*
1 X
000056 Loss of Off-site Power / 6 AA2.01 - Safety injection tank pressure and level indicators 3.7 1
X 000057 Loss of Vital AC Inst. Bus / 6 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.0 1
X 000058 Loss of DC Power / 6 AK3.02 - The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 3.6 1
X 000062 Loss of Nuclear Svc Water / 4 AK3.08 - Actions contained in EOP for loss of instrument air 3.7 1
X 000065 Loss of Instrument Air / 8 1
03/29/2005 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 EK3.1 - Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics 3.2 1
X CE/E02 Reactor Trip - Stabilization -
Recovery / 1 EK1.1 - Components, capacity, and function of emergency systems 3.0 1
X CE/E05 Steam Line Rupture - Excessive Heat Transfer / 4 18 2
1 4
4 3
4 K/A Category Totals:
Group Point Total:
2
03/29/2005 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 AK2.08 - Individual rod display lights and indications 3.1 1
X 000001 Continuous Rod Withdrawal / 1 AK1.04 - Low temperature limits for boron concentration 2.8 1
X 000024 Emergency Boration / 1 AA1.13 - S/G blowdown radiation monitors 3.9 1
X 000037 Steam Generator Tube Leak / 3 AK2.02 - Auxiliary building ventilation system 2.7 1
X 000060 Accidental Gaseous Radwaste Rel. /
9 AK2.02 - Reactor trip system 3.7 1
X 000068 Control Room Evac. / 8 EA1.05 - PORV 3.9 1
X 000074 Inad. Core Cooling / 4 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
3.4 1
X CE/A11 RCS Overcooling - PTS / 4 2.1.30 - Ability to locate and operate components, including local controls.
3.9 1
X CE/A16 Excess RCS Leakage / 2 EK3.2 - Normal, abnormal and emergency operating procedures associated with (Functional Recovery) 3.2 1
X CE/E09 Functional Recovery 9
1 3
1 2
0 2
K/A Category Totals:
Group Point Total:
1
03/29/2005 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 A1.08 - Seal water temperature 2.5 1
X 003 Reactor Coolant Pump A3.04 - RCS flow 3.6 1
X 003 Reactor Coolant Pump A2.16 - T-ave. and T-ref.
deviations 3.2 1
X 004 Chemical and Volume Control A4.12 - Boration/dilution batch control 3.8 1
X 004 Chemical and Volume Control K4.02 - Modes of operation 3.2 1
X 005 Residual Heat Removal K5.02 - Need for adequate subcooling 3.4 1
X 005 Residual Heat Removal A3.06 - Valve lineups 3.9 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 K3.02 - CRDS 2.9 1
X 008 Component Cooling Water A1.09 - Tail pipe temperature and acoustic monitors 3.4 1
X 010 Pressurizer Pressure Control 2.1.32 - Ability to explain and apply all system limits and precautions.
3.4 1
X 012 Reactor Protection 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation.
3.0 1
X 013 Engineered Safety Features Actuation K1.12 - ED/G 4.1 1
X 013 Engineered Safety Features Actuation A2.04 - Loss of service water 2.9*
1 X
022 Containment Cooling K1.02 - Cooling water 4.1 1
X 026 Containment Spray K4.05 - Automatic isolation of steam line 3.7 1
X 039 Main and Reheat Steam K4.18 - Automatic feedwater reduction on plant trip 2.8*
1 X
059 Main Feedwater A3.06 - Feedwater isolation 3.2*
1 X
059 Main Feedwater A1.04 - AFW source tank level 3.9 1
X 061 Auxiliary/Emergency Feedwater 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.3 1
X 062 AC Electrical Distribution A4.03 - Battery discharge rate 3.0*
1 X
063 DC Electrical Distribution K1.02 - AC electrical system 2.7 1
X 063 DC Electrical Distribution 1
03/29/2005 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 K6.07 - Air receivers 2.7 1
X 064 Emergency Diesel Generator A2.11 - Conditions (minimum load) required for unloading an ED/G 2.6 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 K3.02 - Systems having pneumatic valves and controls 3.4 1
X 078 Instrument Air A3.01 - Containment isolation 3.9 1
X 103 Containment 28 3
1 2
3 3
3 K/A Category Totals:
3 2
1 4
3 Group Point Total:
2
03/29/2005 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 K1.05 - NIS and RPS 4.5 1
X 001 Control Rod Drive K6.03 - Reactor vessel level indication 3.1 1
X 002 Reactor Coolant K2.01 - Charging pumps 3.1 1
X 011 Pressurizer Level Control A4.02 - Control rod mode-select switch 3.4 1
X 014 Rod Position Indication K1.01 - Plant computer 3.2*
1 X
017 In-core Temperature Monitor A1.02 - Radiation monitoring systems 2.8 1
X 033 Spent Fuel Pool Cooling A2.06 - Small break LOCA 4.5 1
X 035 Steam Generator 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.0 1
X 041 Steam Dump/Turbine Bypass Control K3.01 - Remainder of the plant 2.9 1
X 045 Main Turbine Generator K6.04 - Fire, smoke, and heat detectors 2.6 1
X 086 Fire Protection 10 2
1 1
1 1
1 K/A Category Totals:
0 0
2 0
1 Group Point Total:
1
03/29/2005 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 K1.05 - NIS and RPS 4.5 1
X 001 Control Rod Drive K6.03 - Reactor vessel level indication 3.1 1
X 002 Reactor Coolant K2.01 - Charging pumps 3.1 1
X 011 Pressurizer Level Control A4.02 - Control rod mode-select switch 3.4 1
X 014 Rod Position Indication K1.01 - Plant computer 3.2*
1 X
017 In-core Temperature Monitor A1.02 - Radiation monitoring systems 2.8 1
X 033 Spent Fuel Pool Cooling A2.06 - Small break LOCA 4.5 1
X 035 Steam Generator 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.0 1
X 041 Steam Dump/Turbine Bypass Control K3.01 - Remainder of the plant 2.9 1
X 045 Main Turbine Generator K6.04 - Fire, smoke, and heat detectors 2.6 1
X 086 Fire Protection 10 2
1 1
1 1
1 K/A Category Totals:
0 0
2 0
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 03/29/2005 Printed:
PWR RO Examination Outline 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.
3.0 1
Conduct of Operations 2.1.3 Knowledge of shift turnover practices.
3.0 1
2.1.29 Knowledge of how to conduct and verify valve lineups.
3.4 1
3 Category Total:
2.2.13 Knowledge of tagging and clearance procedures.
3.6 1
Equipment Control 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
3.5 1
2 Category Total:
2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.
2.6 1
Radiation Control 2.3.2 Knowledge of facility ALARA program.
2.5 1
2 Category Total:
2.4.6 Knowledge symptom based EOP mitigation strategies.
3.1 1
Emergency Procedures/Plan 2.4.15 Knowledge of communications procedures associated with EOP implementation.
3.0 1
2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
2.8 1
3 Category Total:
10 Generic Total:
1
EPE/APE Tier 1 / Group 1 Pressurizer Vapor Space Accident 1
000008 1
Small Break LOCA 1
000009 1
Large Break LOCA 1
000011 1
Reactor Coolant Pump Malfunctions (Loss of RC Flow) 1 000017 1
Loss of Reactor Coolant Makeup 1
000022 1
Loss of Residual Heat Removal System 1
000025 1
Loss of Component Cooling Water 1
000026 1
Pressurizer Pressure Control System Malfunction 1
000027 1
Steam Generator Tube Rupture 1
000038 1
Loss of Main Feedwater 1
000054 1
Station Blackout 1
000055 1
Loss of Off-Site Power 1
000056 1
Loss of Vital AC Electrical Instrument Bus 1
000057 1
Loss of DC Power 1
000058 1
Loss of Nuclear Service Water 1
000062 1
Loss of Instrument Air 1
000065 1
Reactor Trip Recovery 1
CE-E02 1
Excess Steam Demand 1
CE-E05 1
2 1
4 4
3 4
18 EPE/APE Tier 1 / Group 2 Continuous Rod Withdrawal 1
000001 1
Emergency Boration 1
000024 1
Steam Generator Tube Leak 1
000037 1
Accidental Gaseous Radwaste Release 1
000060 1
Control Room Evacuation 1
000068 1
Inadequate Core Cooling 1
000074 1
RCS Overcooling 1
CE-A11 1
Excess RCS Leakage 1
CE-A16 1
Functional Recovery 1
CE-E09 1
1 3
1 2
2 9
3 4
5 6
3 6
Grand Total of EPE/APE K&A Selection:
27
PWR RO Written Examination Outline Summary System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Page 1 of 1 Mar 29, 2005 10:47 AM Points G
Plant System Tier 2 / Group 1 003000 Reactor Coolant Pump System 1
1 2
004000 Chemical and Volume Control System 1
1 2
005000 Residual Heat Removal System 1
1 2
006000 Emergency Core Cooling System 1
1 007000 Pressurizer Relief Tank / Quench Tank System 1
1 008000 Component Cooling Water System 1
1 010000 Pressurizer Pressure Control System 1
1 012000 Reactor Protection System 1
1 013000 Engineered Safety Features Actuation System 1
2 1
022000 Containment Cooling System 1
1 026000 Containment Spray System 1
1 039000 Main and Reheat Steam System 1
1 059000 Main Feedwater System 1
1 2
061000 Auxiliary / Emergency Feedwater System 1
1 062000 A.C. Electrical Distribution 1
1 063000 D.C. Electrical Distribution 1
1 2
064000 Emergency Diesel Generators 1
1 2
073000 Process Radiation Monitoring System 1
1 076000 Service Water System 1
1 078000 Instrument Air System 1
1 103000 Containment System 1
1 3
1 2
3 2
1 3
3 4
3 28 3
Plant System Tier 2 / Group 2 001000 Control Rod Drive System 1
1 002000 Reactor Coolant System 1
1 011000 Pressurizer Level Control System 1
1 014000 Rod Position Indication System 1
1 017000 In-Core Temperature Monitor System 1
1 033000 Spent Fuel Pool Cooling System 1
1 035000 Steam Generator System 1
1 041000 Steam Dump System and Turbine Bypass Control 1
1 045000 Main Turbine Generator System 1
1 086000 Fire Protection System 1
1 2
1 1
2 1
1 1
10 1
5 2
3 3
2 3
4 4
4 4
Grand Total of Plant System K&A Selection:
38 4
System/Mode System Title Cat 1 Cat 2 Cat 3 Cat 4 Points PWR RO Written Examination Outline Summary Page 1 of 1 Mar 29, 2005 10:47 AM Generic Knowledge and Abilities Tier 3 000000 Generic Knowledges and Abilities 3
2 2
3 10 3
2 2
3 10 3
2 2
3 Grand Total of Generic K&A Selection:
10
PWR RO Written Examination Outline Mar 29, 2005 10:47 AM Page 1 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 1
Group 1
000008 AA1.06 Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space Accident:: Control of PZR level 3.6 Pressurizer Vapor Space Accident 41.7 / 45.5 /
45.6 000009 EA2.08 Ability to determine or interpret the following as they apply to a small break LOCA:: Letdown isolation valve position indication 2.9*
Small Break LOCA 43.5 / 45.13 000011 2.4.06
- Knowledge symptom based EOP mitigation strategies.
3.1 Large Break LOCA 41.10 / 43.5 /
45.13 000017 AA1.16 Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):: Low-power reactor trip block status lights 3.2*
Reactor Coolant Pump Malfunctions (Loss of RC Flow) 41.7 / 45.5 /
45.6 000022 AA1.03 Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Pump Makeup:: PZR level trend 3.2 Loss of Reactor Coolant Makeup 41.7 / 45.5 /
45.6 000025 AK2.03 Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following:: Service water or closed cooling water pumps 2.7 Loss of Residual Heat Removal System 41.7 / 45.7 000026 AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water:: The automatic actions (alignments) within the CCWS/nuclear service water resulting from the actuation of the ESFAS 3.6 Loss of Component Cooling Water 41.5 / 41.10 /
45.6 / 45.13 000027 AA2.07 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions:: Makeup flow indication 3.1 Pressurizer Pressure Control System Malfunction 43.5 / 45.13 000038 EK1.03 Knowledge of the operational implications of the following concepts as they apply to the SGTR::
Natural circulation 3.9 Steam Generator Tube Rupture 41.8 / 41.10 /
45.3 000054 2.4.50
- Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.3 Loss of Main Feedwater 45.3 000055 2.1.23
- Ability to perform specific system and integrated plant procedures during all modes of plant operation.
3.9 Station Blackout 45.2 / 45.6
PWR RO Written Examination Outline (Continued)
Mar 29, 2005 10:47 AM Page 2 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 000056 AA1.02 Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power:: ESF bus synchronization select switch to close bus tie breakers 4.0*
Loss of Off-Site Power 41.7 / 45.5 /
45.6 000057 AA2.01 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:: Safety injection tank pressure and level indicators 3.7 Loss of Vital AC Electrical Instrument Bus 43.5 / 45.13 000058 2.4.04
- Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.0 Loss of DC Power 41.10 / 43.2 /
45.6 000062 AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 3.6 Loss of Nuclear Service Water 41.4,41.8/45.7 000065 AK3.08 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air::
Actions contained in EOP for loss of instrument air 3.7 Loss of Instrument Air 41.5 / 41.10 /
45.6 / 45.13 CE-E02 EK3.01 Knowledge of the reasons for the following responses as they apply to the (Reactor Trip Recovery): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
3.2 Reactor Trip Recovery 41.5 / 41.10 /
45.6 / 45.13 CE-E05 EK1.01 Knowledge of the operational implications of the following concepts as they apply to the (Excess Steam Demand): Components, capacity, and function of emergency systems.
3.0 Excess Steam Demand 41.8 / 41.10 /
45.3
PWR RO Written Examination Outline (Continued)
Mar 29, 2005 10:47 AM Page 3 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 1
Group 2
000001 AK2.08 Knowledge of the interrelations between the Continuous Rod Withdrawal and the following::
Individual rod display lights and indications 3.1 Continuous Rod Withdrawal 41.7 / 45.7 000024 AK1.04 Knowledge of the operational implications of the following concepts as they apply to Emergency Boration:: Low temperature limits for boron concentration 2.8 Emergency Boration 41.8 / 41.10 /
45.3 000037 AA1.13 Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak::
S/G blowdown radiation monitors 3.9 Steam Generator Tube Leak 41.7 / 45.5 /
45.6 000060 AK2.02 Knowledge of the interrelations between the Accidental Gaseous Radwaste Release and the following:: Auxiliary building ventilation system 2.7 Accidental Gaseous Radwaste Release 41.7 / 45.7 000068 AK2.02 Knowledge of the interrelations between the Control Room Evacuation and the following:: Reactor trip system 3.7 Control Room Evacuation 41.7 / 45.7 000074 EA1.05 Ability to operate and monitor the following as they apply to a Inadequate Core Cooling:: PORV 3.9 Inadequate Core Cooling 41.7 / 45.5 /
45.6 CE-A11 2.2.22
- Knowledge of limiting conditions for operations and safety limits.
3.4 RCS Overcooling 43.2 / 45.2 CE-A16 2.1.30
- Ability to locate and operate components, including local controls.
3.9 Excess RCS Leakage 41.7 / 45.7 CE-E09 EK3.02 Knowledge of the reasons for the following responses as they apply to the (Functional Recovery):
Normal, abnormal and emergency operating procedures associated with (Functional Recovery).
3.0 Functional Recovery 41.5 / 41.10 /
45.6 / 45.13
PWR RO Written Examination Outline (Continued)
Mar 29, 2005 10:47 AM Page 4 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 2
Group 1
003000 A1.08 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:: Seal water temperature 2.5 Reactor Coolant Pump System 41.5 / 45.5 003000 A3.04 Ability to monitor automatic operation of the RCPS, including:: RCS flow 3.6 Reactor Coolant Pump System 41.7 / 45.5 004000 A2.16 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: T-ave. and T-ref. deviations 3.2 Chemical and Volume Control System 41.5 / 43.5 /
45.3 / 45.5 004000 A4.12 Ability to manually operate and/or monitor in the control room:: Boration/dilution batch control 3.8 Chemical and Volume Control System 41.7 / 45.5 to 45.8 005000 K4.02 Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following:: Modes of operation 3.2 Residual Heat Removal System 41.7 005000 K5.02 Knowledge of the operational implications of the following concepts as they apply the RHRS::
Need for adequate subcooling 3.4 Residual Heat Removal System 41.5 / 45.7 006000 A3.06 Ability to monitor automatic operation of the ECCS, including:: Valve lineups 3.9 Emergency Core Cooling System 41.7 / 45.5 007000 K5.02 Knowledge of the operational implications of the following concepts as the apply to PRTS::
Method of forming a steam bubble in the PZR 3.1 Pressurizer Relief Tank / Quench Tank System 41.5 / 45.7 008000 K3.02 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:: CRDS 2.9 Component Cooling Water System 41.7 / 45.6 010000 A1.09 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including:: Tail pipe temperature and acoustic monitors 3.4 Pressurizer Pressure Control System 41.5 / 45.5 012000 2.1.32
- Ability to explain and apply all system limits and precautions.
3.4 Reactor Protection System 41.10 / 43.2 /
45.12
PWR RO Written Examination Outline (Continued)
Mar 29, 2005 10:47 AM Page 5 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 013000 2.1.02
- Knowledge of operator responsibilities during all modes of plant operation.
3.0 Engineered Safety Features Actuation System 41.10 / 45.13 013000 K1.12 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems:: ED/G 4.1 Engineered Safety Features Actuation System 41.2 to 41.9 /
45.7 to 45.8 022000 A2.04 Ability to (a) predict the impacts of the following malfunctions or operationson the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Loss of service water 2.9*
Containment Cooling System 41.5 / 43.5 /
45.3 / 45.13 026000 K1.02 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems:: Cooling water 4.1 Containment Spray System 41.2 to 41.9 /
45.7 to 45.8 039000 K4.05 Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following::
Automatic isolation of steam line 3.7 Main and Reheat Steam System 41.7 059000 A3.06 Ability to monitor automatic operation of the MFW, including:: Feedwater isolation 3.2*
Main Feedwater System 41.7 / 45.5 059000 K4.18 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following::
Automatic feedwater reduction on plant trip 2.8*
Main Feedwater System 41.7 061000 A1.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including:: AFW source tank level 3.9 Auxiliary / Emergency Feedwater System 41.5 / 45.5 062000 2.4.50
- Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.3 A.C. Electrical Distribution 45.3 063000 A4.03 Ability to manually operate and/or monitor in the control room:: Battery discharge rate 3.0*
D.C. Electrical Distribution 41.7 / 45.5 to 45.8 063000 K1.02 Knowledge of the physical connections and/or cause-effect relationships between the dc electrical system and the following systems:: AC electrical system 2.7 D.C. Electrical Distribution 41.2 to 41.9 /
45.7 to 45.8
PWR RO Written Examination Outline (Continued)
Mar 29, 2005 10:47 AM Page 6 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 064000 A2.11 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Conditions (minimum load) required for unloading an ED/G 2.6 Emergency Diesel Generators 41.5 / 43.5 /
45.3 / 45.13 064000 K6.07 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system::
Air receivers 2.7 Emergency Diesel Generators 41.7 / 45.7 073000 A4.03 Ability to manually operate and/or monitor in the control room:: Check source for operability demonstration 3.1 Process Radiation Monitoring System 41.7 / 45.5 to 45.8 076000 K2.01 Knowledge of bus power supplies to the following:: Service water 2.7*
Service Water System 41.7 078000 K3.02 Knowledge of the effect that a loss or malfunction of the IAS will have on the following:: Systems having pneumatic valves and controls 3.4 Instrument Air System 41.7 / 45.6 103000 A3.01 Ability to monitor automatic operation of the containment system, including:: Containment isolation 3.9 Containment System 41.7 / 45.5
PWR RO Written Examination Outline (Continued)
Mar 29, 2005 10:47 AM Page 7 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 2
Group 2
001000 K1.05 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the following systems:: NIS and RPS 4.5 Control Rod Drive System 41.2 to 41.9 /
45.7 to 45.8 002000 K6.03 Knowledge of the effect or a loss or malfunction on the following RCS components:: Reactor vessel level indication 3.1 Reactor Coolant System 41.7 / 45.7 011000 K2.01 Knowledge of bus power supplies to the following:: Charging pumps 3.1 Pressurizer Level Control System 41.7 014000 A4.02 Ability to manually operate and/or monitor in the control room:: Control rod mode-select switch 3.4 Rod Position Indication System 41.7 / 45.5 to 45.8 017000 K1.01 Knowledge of the physical connections and/or cause-effect relationships between the ITM system and the following systems:: Plant computer 3.2*
In-Core Temperature Monitor System 41.2 to 41.9 /
45.7 to 45.8 033000 A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including:: Radiation monitoring systems 2.8 Spent Fuel Pool Cooling System 41.5 / 45.5 035000 A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Small break LOCA 4.5 Steam Generator System 41.5 / 43.5 /
45.3 / 45.5 041000 2.4.04
- Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.0 Steam Dump System and Turbine Bypass Control 41.10 / 43.2 /
45.6 045000 K3.01 Knowledge of the effect that a loss or malfunction of the MT/G system will have on the following::
Remainder of the plant 2.9 Main Turbine Generator System 41.7 / 45.6 086000 K6.04 Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the :: Fire, smoke, and heat detectors 2.6 Fire Protection System 41.7 / 45.7
PWR RO Written Examination Outline (Last Page)
Mar 29, 2005 10:47 AM Page 8 of 8 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 3
Group 4
000000 2.1.02
- Knowledge of operator responsibilities during all modes of plant operation.
3.0 Generic Knowledges and Abilities 41.10 / 45.13 000000 2.1.03
- Knowledge of shift turnover practices.
3.0 Generic Knowledges and Abilities 41.10 / 45.13 000000 2.1.29
- Knowledge of how to conduct and verify valve lineups.
3.4 Generic Knowledges and Abilities 41.10 / 45.1 /
45.12 000000 2.2.13
- Knowledge of tagging and clearance procedures.
3.6 Generic Knowledges and Abilities 41.10 / 45.13 000000 2.2.30
- Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
3.5 Generic Knowledges and Abilities 45.12 000000 2.3.01
- Knowledge of 10CFR20 and related facility radiation control requirements.
2.6 Generic Knowledges and Abilities 41.12 / 43.4 /
45.9 / 45.10 000000 2.3.02
- Knowledge of facility ALARA program.
2.5 Generic Knowledges and Abilities 41.12 / 43.4 /
45.9 / 45.10 000000 2.4.06
- Knowledge symptom based EOP mitigation strategies.
3.1 Generic Knowledges and Abilities 41.10 / 43.5 /
45.13 000000 2.4.15
- Knowledge of communications procedures associated with EOP implementation.
3.0 Generic Knowledges and Abilities 41.10 / 45.13 000000 2.4.23
- Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
2.8 Generic Knowledges and Abilities 41.10 / 45.13
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline Page 1 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000025 AA1.13 Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System:SWS radiation monitors No Raw Water Rad monitor in service at FCS 1/1 000025 AA1.19 Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System:Block orifice bypass valve controller and indicators Not a FCS design feature 1/1 000029 EA1.05 Ability to operate and monitor the following as they apply to a ATWS:BIT outlet valve switches No BIT at FCS 1/1 000029 EK1.02 Knowledge of the operational implications of the following concepts as they apply to the ATWS:Definition of reactivity GFE Topic 1/1 000029 EK1.05 Knowledge of the operational implications of the following concepts as they apply to the ATWS:Definition of negative temperature coefficient as applied to large PWR coolant systems GFE Topic
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline Page 2 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000038 EA2.03 Ability to determine or interpret the following as they apply to a SGTR:Which S/G is ruptured Will be evaluated during operating exam.
1/1 000038 EA1.37 Ability to operate and monitor the following as they apply to a SGTR:Controlling of thermal shock during PZR spray operation No specific concern at FCS 1/1 000038 EA1.08 Ability to operate and monitor the following as they apply to a SGTR:Core cooling monitor Core cooling monitor?
1/1 000062 AA2.06 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water:The length of time after the loss of SWS flow to a component before that component may be damaged No specified time limits at FCS 1/2 000001 AA1.01 Ability to operate and / or monitor the following as they apply to the Continuous Rod Withdrawal:Bank select switch Redundant to sampled K/A 014000 A4.02
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline Page 3 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000001 AK1.19 Knowledge of the operational implications of the following concepts as they apply to Continuous Rod Withdrawal:Voids coefficient GFE Topic 1/2 000001 AK2.02 Knowledge of the interrelations between the Continuous Rod Withdrawal and the following:Controllers and positioners Rod control is manual only 1/2 000003 AK1.13 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod:Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS No ICS at FCS 1/2 000003 AK1.22 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod:Calculation of power defect: algebraic sum of moderator temperature and fuel temperature defects GFE Topic 1/2 000003 AK1.05 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod:CVCS response to dropped rod Low Importance, no FCS specific priority
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline Page 4 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000005 AA2.04 Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod:Interpretation of computer in-core TC map for dropped rod location Not used by operators to determine dropped rod location 1/2 000060 AK1.02 Knowledge of the operational implications of the following concepts as they apply to Accidental Gaseous Radwaste Release:Biological effects on humans of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure Not an RO task related to event 1/2 000060 AA2.03 Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste:The steps necessary to isolate a given radioactive-gas leak, using P&IDs Difficult to provide P&IDs of required size in written exam setting 1/2 000067 AA1.04 Ability to operate and / or monitor the following as they apply to the Plant Fire on Site:Bypass of a heat detector Not an FCS design feature 2/1 059000 K4.19 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following:Automatic feedwater isolation of MFW Redundant to sampled K/A 059000 A3.06
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline Page 5 Tier/Group Randomly Selected K/A Description Reason for Rejection 2/1 076000 K3.02 Knowledge of the effect that a loss or malfunction of the SWS will have on the following:Secondary closed cooling water No relationship 2/1 076000 K1.09 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems:Reactor building closed cooling water No separate reactor building CCW system at FCS 2/2 041000 A4.02 Ability to manually operate and/or monitor in the control room:Cooldown valves Not an FCS design feature 2/2 045000 K4.44 Knowledge of MT/G system design feature(s) and/or interlock(s) which provide for the following:Impulse pressure mode control of steam dumps Not used at FCS 2/2 071000 A4.19 Ability to manually operate and/or monitor in the control room:Bringing an empty WDGS decay tank on line and shutting down a full tank Not performed from control room
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline Page 6 Tier/Group Randomly Selected K/A Description Reason for Rejection 2/2 072000 K4.02 Knowledge of ARM system design feature(s) and/or interlock(s) which provide for the following:Fuel building isolation Not part of FCS design 2/2 086000 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
No immediate actions that would be performed prior to implementing procedure for this system
ES-401, Page 21 of 33 ES-401 PWR Examination Outline Form ES-401-2 l
Facility:
Date of Exam:
Tier Group RO K/A Category Points l
SRO-Only Points l
K 1
K 2
K 3
K 4
K 5
K 6
A 1
A 2
A 3
A 4
G Total A2 l
G*
l Total l
1.
Emergency &
Abnormal Plant Evolutions 1
N/A N/A 18 l
6 l
2 9
l 4
l Tier Totals 27 l
10 l
2.
Plant Systems 1
28 l
5 l
2 10 l
3 l
Tier Totals 38 l
8 l
- 3. Generic Knowledge and Abilities l
Categories l
1 2
3 4
10 l
1 l
2 l
3 l
4 l
7 l
l l
Note:
1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO l
and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals l
in each K/A category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
l 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply l
at the facility should be deleted and justified; operationally important, site-specific systems that are not included l
on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination l
of inappropriate K/A statements.
l 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group l
before selecting a second topic for any system or evolution.
l 5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
l Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
l 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
l 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 l
must be relevant to the applicable evolution or system.
l 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) l for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals l
for each category in the table above. Use duplicate pages for RO and SRO-only exams.
l 9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, l
and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
l 2
1 4
4 3
4 3
3 1
3 1
2 0
2 3
1 3
4 5
6 3
6 6
4 3
1 2
3 2
1 3
3 4
3 3
2 3
2 1
1 0
0 2
1 1
0 1
1 1 &K4FH 1
5 2
3 3
2 3
4 4
4 4
4 4
4 3
2 2
3 2
2 1
2 Fort Calhoun 07/11/05
03/29/2005 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 EA2.25 - Reactor trip setpoints 4.1 1
X 000009 Small Break LOCA / 3 2.1.32 - Ability to explain and apply all system limits and precautions.
3.8 1
X 000015 RCP Malfunctions / 4 AA2.07 - Pump cavitation 3.7 1
X 000025 Loss of RHR System / 4 AA2.02 - The cause of possible CCW loss 3.6 1
X 000026 Loss of Component Cooling Water /
8 2.4.30 - Knowledge of which events related to system operations/status should be reported to outside agencies.
3.6 1
X 000038 Steam Gen. Tube Rupture / 3 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
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
03/29/2005 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 AA2.10 - Source range count rate 4.4*
1 X
000068 Control Room Evac. / 8 EA2.02 - Availability of main or auxiliary feedwater 4.6 1
X 000074 Inad. Core Cooling / 4 2.1.14 - Knowledge of system status criteria which require the notification of plant personnel.
3.3 1
X 000076 High Reactor Coolant Activity / 9 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 4.4 1
X CE/E09 Functional Recovery 4
0 0
0 0
3 1
K/A Category Totals:
Group Point Total:
1
03/29/2005 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 A2.11 - Loss of IAS 4.2 1
X 004 Chemical and Volume Control 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
4.0 1
X 006 Emergency Core Cooling A2.05 - Exceeding PRT high-pressure limits 3.6 1
X 007 Pressurizer Relief/Quench Tank 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
4.1 1
X 063 DC Electrical Distribution 2.1.32 - Ability to explain and apply all system limits and precautions.
3.8 1
X 103 Containment 5
0 0
0 0
2 3
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1
03/29/2005 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 A2.13 - ATWS 4.6 1
X 001 Control Rod Drive 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
4.1 1
X 002 Reactor Coolant K4.01 - Fuel protection from binding and dropping 3.4 1
X 034 Fuel Handling Equipment 3
0 0
0 0
1 1
K/A Category Totals:
1 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 03/29/2005 Printed:
PWR SRO Examination Outline 2.1.4 Knowledge of shift staffing requirements.
3.4 1
Conduct of Operations 2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.
2.9 1
2 Category Total:
2.2.5 Knowledge of the process for making changes in the facility as described in the safety analysis report.
2.7 1
Equipment Control 2.2.19 Knowledge of maintenance work order requirements.
3.1 1
2 Category Total:
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
3.3 1
Radiation Control 1
Category Total:
2.4.29 Knowledge of the emergency plan.
4.0 1
Emergency Procedures/Plan 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.
3.6 1
2 Category Total:
7 Generic Total:
1
PWR SRO Written Examination Outline Mar 29, 2005 10:48 AM Page 1 of 5 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 1
Group 1
000009 EA2.25 Ability to determine or interpret the following as they apply to a small break LOCA:: Reactor trip setpoints 4.1 Small Break LOCA 43.5 / 45.13 000017 2.1.32
- Ability to explain and apply all system limits and precautions.
3.8 Reactor Coolant Pump Malfunctions (Loss of RC Flow) 41.10 / 43.2 /
45.12 000025 AA2.07 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System:: Pump cavitation 3.7 Loss of Residual Heat Removal System 43.5 / 45.13 000026 AA2.02 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water:: The cause of possible CCW loss 3.6 Loss of Component Cooling Water 43.5 / 45.13 000038 2.4.30
- Knowledge of which events related to system operations/status should be reported to outside agencies.
3.6 Steam Generator Tube Rupture 43.5 / 45.11 CE-E02 2.2.25
- Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
3.7 Reactor Trip Recovery 43.2
PWR SRO Written Examination Outline (Continued)
Mar 29, 2005 10:48 AM Page 2 of 5 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 1
Group 2
000068 AA2.10 Ability to determine and interpret the following as they apply to the Control Room Evacuation::
Source range count rate 4.4*
Control Room Evacuation 43.5 / 45.13 000074 EA2.02 Ability to determine or interpret the following as they apply to a Inadequate Core Cooling::
Availability of main or auxiliary feedwater 4.6 Inadequate Core Cooling 43.5 / 45.13 000076 2.1.14
- Knowledge of system status criteria which require the notification of plant personnel.
3.3 High Reactor Coolant Activity 43.5 / 45.12 CE-E09 EA2.01 Ability to determine and interpret the following as they apply to the (Functional Recovery): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
4.4 Functional Recovery 43.5 / 45.13
PWR SRO Written Examination Outline (Continued)
Mar 29, 2005 10:48 AM Page 3 of 5 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 2
Group 1
004000 A2.11 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Loss of IAS 4.2 Chemical and Volume Control System 41.5 / 43.5 /
45.3 / 45.5 006000 2.1.33
- Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
4.0 Emergency Core Cooling System 43.2 / 43.3 /
45.3 007000 A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Exceeding PRT high-pressure limits 3.6 Pressurizer Relief Tank / Quench Tank System 41.5 / 43.5 /
45.3 / 45.13 063000 2.2.22
- Knowledge of limiting conditions for operations and safety limits.
4.1 D.C. Electrical Distribution 43.2 / 45.2 103000 2.1.32
- Ability to explain and apply all system limits and precautions.
3.8 Containment System 41.10 / 43.2 /
45.12
PWR SRO Written Examination Outline (Continued)
Mar 29, 2005 10:48 AM Page 4 of 5 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 2
Group 2
001000 A2.13 Ability to (a) predict the impacts of the following malfunction or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: ATWS 4.6 Control Rod Drive System 41.5 / 43.5 /
45.3 / 45.13 002000 2.2.22
- Knowledge of limiting conditions for operations and safety limits.
4.1 Reactor Coolant System 43.2 / 45.2 034000 K4.01 Knowledge of design feature(s) and/or interlock(s) which provide for the following:: Fuel protection from binding and dropping 3.4 Fuel Handling Equipment System 41.7
PWR SRO Written Examination Outline (Last Page)
Mar 29, 2005 10:48 AM Page 5 of 5 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 3
Group 4
000000 2.1.04
- Knowledge of shift staffing requirements.
3.4 Generic Knowledges and Abilities 41.10 / 43.2 000000 2.1.34
- Ability to maintain primary and secondary plant chemistry within allowable limits.
2.9 Generic Knowledges and Abilities 41.10 / 43.5 /
45.12 000000 2.2.05
- Knowledge of the process for making changes in the facility as described in the safety analysis report.
2.7 Generic Knowledges and Abilities 43.3 / 45.13 000000 2.2.19
- Knowledge of maintenance work order requirements.
3.1 Generic Knowledges and Abilities 43.5 / 45.13 000000 2.3.10
- Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
3.3 Generic Knowledges and Abilities 43.4 / 45.10 000000 2.4.29
- Knowledge of the emergency plan.
4.0 Generic Knowledges and Abilities 43.5 / 45.11 000000 2.4.45
- Ability to prioritize and interpret the significance of each annunciator or alarm.
3.6 Generic Knowledges and Abilities 43.5 / 45.3 /
45.12
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 1 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000008 AA2.05 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:PORV isolation (block) valve switches and indicators not SRO level K/A 1/1 000017 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
RCP Malfunction would not be reported to outside agencies 1/1 000017 AA2.07 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):Calculation of expected values of flow in the loop with RCP secured Operators do not calculate flow in this situation 1/1 000022 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
Event would not be reported
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 2 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000038 EA2.05 Ability to determine or interpret the following as they apply to a SGTR:Causes and consequences of shrink and swell in S/Gs Difficult to write SRO level question 1/1 000056 AA2.29 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:Service water booster pump ammeter and flowmeter No service water booster pump at FCS 1/1 000056 AA2.28 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:Auxiliary building gas treatment indicator No AB gas treatment indicator at FCS 1/1 000062 AA2.06 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water:The length of time after the loss of SWS flow to a component before that component may be damaged No specified time limits at FCS
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 3 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000003 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
Will be evaluated in operating exam 1/2 000003 AA2.02 Ability to determine and interpret the following as they apply to the Dropped Control Rod:Signal inputs to rod control system Rod Control is manual at FCS 1/2 000005 AA2.04 Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod:Interpretation of computer in-core TC map for dropped rod location Not used by operators to determine dropped rod location 1/2 000028 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
No Tech Spec on pressurizer level
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 4 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000033 AA2.12 Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation:Maximum allowable channel disagreement No maximum allowable for wide range NI's, not used for RPS 1/2 000037 AA2.13 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak:Which S/G is leaking Will be evaluated in operating exam 1/2 000037 AA2.02 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak:Agreement/disagreement among redundant radiation monitors Will be evaluated during simulator scenario 1/2 CE-A13 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
RO level knowledge, Difficult to write SRO level question
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 5 Tier/Group Randomly Selected K/A Description Reason for Rejection 2/1 039000 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
Would not be reported to outside agencies 2/1 062000 A2.09 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:Consequences of exceeding current limitations Difficult to write operationally valid SRO level Question.
2/2 001000 A2.20 Ability to (a) predict the impacts of the following malfunction or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:Isolation of left coil on affected rod to prevent coil burnout Does not apply to FCS CRD system 2/2 056000 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
Not an SRO Task
3/29/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 6 Tier/Group Randomly Selected K/A Description Reason for Rejection 2/2 056000 A2.12 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:Opening of the heater string bypass valve Low SRO importance, no plant specific priority 3/4 000000 2.2.22 Knowledge of limiting conditions for operations and safety limits.
Already used as system generic 3/4 000000 2.3.06 Knowledge of the requirements for reviewing and approving release permits.
Will be evaluated in operating exam 3/4 000000 2.2.33 Knowledge of control rod programming.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun_______________ Date of Examination: __07/11/05___
Examination Level : RO Operating Test Number: __________
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations M
Administrative JPM - Calculate shutdown margin with a known inoperable CEA K/A 2.1.7 (RO 3.7)
Conduct of Operations N
Administrative JPM - Determine minimum HPSI flow required to remove decay heat following sump strainer blockage K/A 2.1.25 (RO 2.8)
Equipment Control N
Administrative JPM - Verify boration path during plant shutdown conditions with equipment out of service K/A 2.2.24 (RO 2.6)
Radiation Control M
Administrative JPM - RCA Entry and Exit (Discover spill of potentially radioactive liquid)
K/A 2.3.1 (RO 2.6)
(Conducted in Radiation Worker Training Facility)
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 all 5 are required.
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
(S)imulator
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun_______________ Date of Examination: __07/11/05___
Examination Level : SRO Operating Test Number: __________
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations M
Administrative JPM - Review shutdown margin calculation with a known inoperable CEA K/A 2.1.7 (SRO 3.7)
Conduct of Operations M
Administrative JPM - Determine equipment operability requirements during mode transition K/A 2.1.22 (SRO 3.3)
Equipment Control D
Administrative JPM - Review required shift surveillance OP-ST-SHIFT-0001 K/A 2.2.12 (SRO 3.4)
Radiation Control N
Administrative JPM - Authorize Waste Gas Decay Tank Release K/A 2.3.6 (SRO 3.1)
Administrative JPM - Classify Event and make Protective Action Recommendations K/A 2.4.41 (SRO 4.1), K/A 2.4.44 (SRO 4.0)
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.
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
(S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun _______________ Date of Examination: ___07/11/05____
Exam Level : RO 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
S, D 2
S, D 5
S, D 7
S, D, A 8
S, D 6
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
S, M, A, L 4P
S, N, L 4S
S, N 3
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
M, E 8
N, A, E 6
D, P, R, A 9
@ All control room (and in-plant) systems must be different and 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 (L)ow-Power (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 / > 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: ___07/11/05____
Exam Level : SRO-I 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
S, D 2
S, D 5
S, D 7
S, D, A 8
- e.
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
S, M, A, L 4P
S, N, L 4S
S, N 3
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
M, E 8
N, A, E 6
D, P, R, A 9
@ All control room (and in-plant) systems must be different and 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 (L)ow-Power (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 / > 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: ___07/11/05____
Exam Level : 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.
- b.
- c.
- d.
- e.
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
S, M, A, L 4P
S, N, L 4S
- h.
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
M, E 8
N, A, E 6
D, P, R, A 9
@ All control room (and in-plant) systems must be different and 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 (L)ow-Power (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 / > 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: 2005 - 1 Op-Test No. ___________
Examiners:
Operators:
Initial Conditions: 100% Power Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event No.
Malf No.
Event Type*
Event Description 1
I - ATC Letdown flow transmitter fails high - letdown isolates 2
I - BOP S/G pressure transmitter fails high - manual FW flow control required 3
C - BOP IA compressor trips, standby does not load 4
C - ATC Dropped CEA - T/S Entry 5
R - ATC N - BOP TS Required power reduction to 70%
6 C - ATC Instrument Bus Fails - T/S Entry 7
M - ALL Main steam line break inside containment 8
C - BOP Turbine fails to trip 9
I - ATC or BOP CPHS Fails to Actuate
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 2 Op-Test No. ___________
Examiners:
Operators:
Initial Conditions: 100% Power Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event No.
Malf No.
Event Type*
Event Description 1
I - ATC Power Range NI Channel Fails - T/S entry 2
I - BOP S/G flow transmitter fails low 3
C - BOP Bearing Water Pump Trips 4
I -ATC RCS T-hot fails - T/S entry 5
C - ATC Charging Pump degraded performance 6
M - ALL Steam Generator Tube Rupture 7
R - ATC 2 CEAs fail to insert - Emergency Boration Required 8
I - BOP RM-057 (Condenser offgas radiation monitor) fails as is (Aux Steam Isolation valve, RC-978, does not get close signal)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 3 Op-Test No. ___________
Examiners:
Operators:
Initial Conditions: 50% Power Turnover: Heater Drain pumps FW-5A and FW-5C are tagged out of service. Power held at 50%
pending repair of at least one of the heater drain pumps.
Event No.
Malf No.
Event Type*
Event Description 1
C - ATC or BOP D/G Radiator Leak - T/S Entry 2
I - BOP PT-910 Fails High 3
I - ATC Letdown heat exchanger temperature transmitter fails low 4
C - BOP Loss of 161 KV - T/S Entry 5
I - ATC Pressurizer pressure transmitter fails high 6
I - BOP S/G level transmitter fails high 7
C - ATC Raw Water header leak 8
M - ALL LOCA with Loss of offsite power 9
C-BOP Circulating Water Pump Breaker fails to open, D/G breaker does not close.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 4 (spare)
Op-Test No. ___________
Examiners:
Operators:
Initial Conditions: 50% Power Turnover: Heater Drain pumps FW-5A and FW-5C are tagged out of service. Power held at 50%
pending repair of at least one of the heater drain pumps.
Event No.
Malf No.
Event Type*
Event Description 1
I - ATC VCT Level Transmitter Fails Low 2
I - BOP S/G pressure transmitter fails low 3
I - ATC RCS Flow transmitter failure - T/S Entry 4
I - BOP Inadvertent AFAS actuation - T/S Entry 5
C - ATC Instrument air to containment isolates 6
C - BOP Loss of condenser vacuum 7
M - ALL Reactor Trip - no steam dump and bypass valves 8
C - BOP S/G safety valve sticks open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Simulator Scenario/Candidate Cross Reference Candidates Scenario One Position Scenario Two Position Scenario Three Position RO1 RO4 ATC BOP RO2 RO5 ATC BOP RO3 RO6 BOP ATC USRO1 USRO2 SRO SRO SRO ISRO1 ATC BOP SRO ISRO2 SRO ATC BOP ISRO3 BOP SRO ATC
WHAT CHANGED?
CHANGE Reason for Change SRO form ES-401-4 Removed K/A 062000 A2.09 from rejected K/A list.
Discussion with Lead Examiner SRO form ES-401-2 Replaced K/A 007000 A2.05 with 062000 A2.09 (Tier 2/Group 1)
Added previously rejected K/A back into exam (see above)
RO ES-301-2 Replaced Transfer Waste Gas JPM Lead Examiner Request Modified JPM-0042 to an alternate path and renamed it Too simple as written Changed JPM-0613A from M to D correction Changed JPM-0627 to A correction SRO-I ES-301-2 Replaced Transfer Waste Gas JPM Lead Examiner Request Replaced JPM-0778 with JPM-0042 To prevent overlap with Administrative JPM Modified JPM-0042 to an alternate path and renamed it Too simple as written Changed JPM-0613A from M to D correction Changed JPM-0627 to A correction SRO-U ES-301-2 Replaced Transfer Waste Gas JPM Lead Examiner Request Changed JPM-0613A from M to D correction SRO Form ES-301-1 Changed review SDM JPM from SDM with inoperable CEA to SDM with boron depletion Review SDM with inoperable CEA was used on last SRO exam Form ES-D-1 scenario 1
Changed event 2 from S/G pressure transmitter to S/G level.
Automatic control system handles failure without operator action
Form ES-D-1 scenario 2
Changed event 2 from S/G flow transmitter to S/G level.
Automatic control system handles failure without operator action Form ES-D-1 scenario 4 (spare)
Changed event 2 from S/G pressure transmitter to S/G level.
Automatic control system handles failure without operator action
5/30/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 1 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000008 AA2.05 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:PORV isolation (block) valve switches and indicators not SRO level K/A 1/1 000017 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
RCP Malfunction would not be reported to outside agencies 1/1 000017 AA2.07 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):Calculation of expected values of flow in the loop with RCP secured Operators do not calculate flow in this situation 1/1 000022 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
Event would not be reported
5/30/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 2 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000038 EA2.05 Ability to determine or interpret the following as they apply to a SGTR:Causes and consequences of shrink and swell in S/Gs Difficult to write SRO level question 1/1 000056 AA2.29 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:Service water booster pump ammeter and flowmeter No service water booster pump at FCS 1/1 000056 AA2.28 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:Auxiliary building gas treatment indicator No AB gas treatment indicator at FCS 1/1 000062 AA2.06 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water:The length of time after the loss of SWS flow to a component before that component may be damaged No specified time limits at FCS
5/30/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 3 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000003 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
Will be evaluated in operating exam 1/2 000003 AA2.02 Ability to determine and interpret the following as they apply to the Dropped Control Rod:Signal inputs to rod control system Rod Control is manual at FCS 1/2 000005 AA2.04 Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod:Interpretation of computer in-core TC map for dropped rod location Not used by operators to determine dropped rod location 1/2 000028 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
No Tech Spec on pressurizer level
5/30/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 4 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000033 AA2.12 Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation:Maximum allowable channel disagreement No maximum allowable for wide range NI's, not used for RPS 1/2 000037 AA2.13 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak:Which S/G is leaking Will be evaluated in operating exam 1/2 000037 AA2.02 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak:Agreement/disagreement among redundant radiation monitors Will be evaluated during simulator scenario 1/2 CE-A13 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
RO level knowledge, Difficult to write SRO level question
5/30/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 5 Tier/Group Randomly Selected K/A Description Reason for Rejection 2/1 039000 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
Would not be reported to outside agencies 2/2 001000 A2.20 Ability to (a) predict the impacts of the following malfunction or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:Isolation of left coil on affected rod to prevent coil burnout Does not apply to FCS CRD system 2/2 056000 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
Not an SRO Task 2/2 056000 A2.12 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:Opening of the heater string bypass valve Low SRO importance, no plant specific priority
5/30/2005 Enhanced Form ES-401-4 Record of Rejected K/As from SRO Outline Page 6 Tier/Group Randomly Selected K/A Description Reason for Rejection 3/4 000000 2.2.22 Knowledge of limiting conditions for operations and safety limits.
Already used as system generic 3/4 000000 2.3.06 Knowledge of the requirements for reviewing and approving release permits.
Will be evaluated in operating exam 3/4 000000 2.2.33 Knowledge of control rod programming.
05/30/2005 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:
07/11/2005 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
3 3
0 0
3 1
0 0
6 4
0 0
2 3
1 0
1 1
1 0
3 4
2 2
1 2
1 2
3 4
10 4
6 5
3 8
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
05/30/2005 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 EA2.25 - Reactor trip setpoints 4.1 1
X 000009 Small Break LOCA / 3 2.1.32 - Ability to explain and apply all system limits and precautions.
3.8 1
X 000015 RCP Malfunctions / 4 AA2.07 - Pump cavitation 3.7 1
X 000025 Loss of RHR System / 4 AA2.02 - The cause of possible CCW loss 3.6 1
X 000026 Loss of Component Cooling Water /
8 2.4.30 - Knowledge of which events related to system operations/status should be reported to outside agencies.
3.6 1
X 000038 Steam Gen. Tube Rupture / 3 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
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
05/30/2005 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 AA2.10 - Source range count rate 4.4*
1 X
000068 Control Room Evac. / 8 EA2.02 - Availability of main or auxiliary feedwater 4.6 1
X 000074 Inad. Core Cooling / 4 2.1.14 - Knowledge of system status criteria which require the notification of plant personnel.
3.3 1
X 000076 High Reactor Coolant Activity / 9 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 4.4 1
X CE/E09 Functional Recovery 4
0 0
0 0
3 1
K/A Category Totals:
Group Point Total:
1
05/30/2005 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 A2.11 - Loss of IAS 4.2 1
X 004 Chemical and Volume Control 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
4.0 1
X 006 Emergency Core Cooling A2.09 - Consequences of exceeding current limitations 3.0*
1 X
062 AC Electrical Distribution 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
4.1 1
X 063 DC Electrical Distribution 2.1.32 - Ability to explain and apply all system limits and precautions.
3.8 1
X 103 Containment 5
0 0
0 0
2 3
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1
05/30/2005 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 A2.13 - ATWS 4.6 1
X 001 Control Rod Drive 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
4.1 1
X 002 Reactor Coolant K4.01 - Fuel protection from binding and dropping 3.4 1
X 034 Fuel Handling Equipment 3
0 0
0 0
1 1
K/A Category Totals:
1 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 05/30/2005 Printed:
PWR SRO Examination Outline 2.1.4 Knowledge of shift staffing requirements.
3.4 1
Conduct of Operations 2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.
2.9 1
2 Category Total:
2.2.5 Knowledge of the process for making changes in the facility as described in the safety analysis report.
2.7 1
Equipment Control 2.2.19 Knowledge of maintenance work order requirements.
3.1 1
2 Category Total:
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
3.3 1
Radiation Control 1
Category Total:
2.4.29 Knowledge of the emergency plan.
4.0 1
Emergency Procedures/Plan 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.
3.6 1
2 Category Total:
7 Generic Total:
1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun _______________ Date of Examination: ___07/11/05____
Exam Level : RO 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
S, D 2
S, D 5
S, D 7
S, D, A 8
- e. 062 / JPM-0042 Transfer Clutch Power Supply/x-tie inst busses K/A 062000 A2.10 (RO 3.0 / SRO 3.3)
S, M, A 6
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
S, D, A, L 4P
S, N, L 4S
S, N, A 3
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
M, E 8
N, A, E 6
- k. 028 / JPM-0719M Startup Containment Hydrogen Purge and Makeup K/A 068000 A3.02 (RO 3.6 / SRO 3.6)
M, R, E 5
@ All control room (and in-plant) systems must be different and 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 (L)ow-Power (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 / > 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: ___07/11/05____
Exam Level : ISRO 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
S, D 2
S, D 5
- c.
S, D, A 8
- e. 062 / JPM-0042 Transfer Clutch Power Supply/x-tie inst busses K/A 062000 A2.10 (RO 3.0 / SRO 3.3)
S, M, A 6
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
S, D, A, L 4P
S, N, L 4S
S, N, A 3
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
M, E 8
N, A, E 6
- k. 028 / JPM-0719M Startup Containment Hydrogen Purge and Makeup K/A 068000 A3.02 (RO 3.6 / SRO 3.6)
M, R, E 5
@ All control room (and in-plant) systems must be different and 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 (L)ow-Power (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 / > 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: ___07/11/05____
Exam Level : USRO 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.
- b.
- c.
- d.
- e.
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
S, D, A, L 4P
S, N, L 4S
- h.
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
M, E 8
N, A, E 6
- k. 028 / JPM-0719M Startup Containment Hydrogen Purge and Makeup K/A 068000 A3.02 (RO 3.6 / SRO 3.6)
M, R, E 5
@ All control room (and in-plant) systems must be different and 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 (L)ow-Power (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 / > 1 / > 1
> 2 / > 2 / > 1
< 3 / < 3 / < 2 (randomly selected)
> 1 / > 1 / > 1
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun_______________ Date of Examination: __07/11/05___
Examination Level : SRO Operating Test Number: __________
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations M
Administrative JPM - Review shutdown margin calculation with boron depletion K/A 2.1.7 (SRO 3.7)
Conduct of Operations D
Administrative JPM - Determine equipment operability requirements during mode transition K/A 2.1.22 (SRO 3.3)
Equipment Control M
Administrative JPM - Review required shift surveillance OP-ST-SHIFT-0001 K/A 2.2.12 (SRO 3.4)
Radiation Control N
Administrative JPM - Authorize Waste Gas Decay Tank Release K/A 2.3.6 (SRO 3.1)
Administrative JPM - Classify Event and make Protective Action Recommendations K/A 2.4.41 (SRO 4.1), K/A 2.4.44 (SRO 4.0)
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.
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
(S)imulator
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 1 Op-Test No. ___________
Examiners:
Operators:
Initial Conditions: 100% Power IC#1
{ Preset malfunctions: COP RCAF2U1 0%, COP RCAF2U2 0%, MFP EHC02, MFP ESF02A OFF, MFP ESF02B OFF}
Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event No.
Malf No.
Event Type*
Event Description 1
(3:00)
COP T:F212 160 I - ATC Letdown flow transmitter fails high - letdown isolates 2
(10:00)
COP T:L903X 0%
60 sec ramp I - BOP S/G A level transmitter fails low - manual FW flow control required 3
(15:00)
COP NCAPCA1C TRIP C - BOP IA Compressor trips, standby does not load 4
(20:00)
MFP CRD06 R1G1 Deenergized C - ATC Dropped CEA - T/S Entry 5
N/A R - ATC N - BOP TS Required power reduction to 70%
6 (35:00)
MFP EDS04B C - ATC Instrument Bus Fails - T/S Entry 7
(45:00)
MSS01A 20%
2 min ramp M - ALL Main steam line break inside containment 8
Preset C - BOP Turbine fails to trip 9
Preset I - ATC or BOP CPHS Fails to Actuate
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 2 Op-Test No. ___________
Examiners:
Operators:
Initial Conditions: 100% Power (IC#1)
{PRESET MFP CRD05I untrip, MFP CRD05H untrip, COP T:R057 69, Start CH-1B, Stop CH-1C)
Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event No.
Malf No.
Event Type*
Event Description 1
(3:00)
MFP NIS04C I - ATC Power Range NI Channel C Fails - T/S entry 2
(10:00)
COP T:L906X 55%
I - BOP S/G B level transmitter fails to 55%
3 (16:00)
COP NBWPAC9 A trip C - BOP Bearing Water Pump AC-9A Trips 4
(20:00)
T:T122H2 665°F I -ATC RCS T-hot fails - T/S entry 5
(30:00)
MFP CVC16B C - ATC Charging Pump CH-1B degraded performance 6
(40:00)
MFP SGN01A 25%
M -
ALL Steam Generator Tube Rupture 7
Preset R - ATC 2 CEAs fail to insert - Emergency Boration Required 8
Preset I - BOP RM-057 (Condenser offgas radiation monitor) fails as is (Aux Steam Isolation valve, RC-978, does not get close signal)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2005 - 4 (spare)
Op-Test No. ___________
Examiners:
Operators:
Initial Conditions: 49% Power
{Preset MSS02F 100% E1 30 sec delay} { Place 1A1 and 1A2 on 22 KV, S/D CH-1A}
Turnover: Heater Drain pumps FW-5A and FW-5C are tagged out of service. Power held at 50%
pending repair of at least one of the heater drain pumps.
Event No.
Malf No.
Event Type*
Event Description 1
(3:00)
COP JLB218LL Fail_set I - ATC VCT Level Transmitter Fails Low 2
(8:00)
COP T:L903X 100% 45 sec ramp I - BOP S/G A Level transmitter fails high 3
(15:00)
COP T:F114YA 0
I - ATC RCS Flow transmitter failure - T/S Entry 4
(22:00)
MFP AFW05A I - BOP Inadvertent AFAS actuation - T/S Entry 5
(30:00)
COP RCAP 849A&B 0%
C - ATC Instrument air to containment isolates 6
(40:00)
MFP CND01 100% 300 sec ramp C - BOP Loss of condenser vacuum 7
N/A M - ALL Reactor Trip - no steam dump and bypass valves 8
Preset C - BOP S/G safety valve sticks open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor