ML051090100
| ML051090100 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/16/2004 |
| From: | Gody A Operations Branch IV |
| To: | Randolph G Union Electric Co |
| References | |
| 50-483/04-301 50-483/04-301 | |
| Download: ML051090100 (20) | |
Text
ES-401 2004 Callaway Examination Outline Form ES-401-2 Facility: Callaway Date of Exam: February 2004 RO K/A Category Points SRO-Only Tier Group K K K K K K A A A A G Total K A A2 G Total 1 2 3 4 5 6 1 2 3 4 *
- 1. 1 3 2 2 4 2 5 18 0 0 4 3 7 Emergency
& Abnormal 2 1 1 2 3 1 1 9 0 0 3 2 5 Plant Evolutions Tier 4 3 4 7 3 6 27 0 0 7 5 12 Totals
- 2. 1 4 2 3 2 2 1 3 5 2 2 2 28 0 0 3 1 4 Plant Systems 2 0 0 0 3 1 2 2 0 1 1 0 10 0 0 0 2 2 Tier 4 2 3 5 3 3 5 5 3 3 2 38 0 0 3 3 6 Totals 1 2 3 4
- 3. Category 1 2 3 4 Generic Knowledge and Abilities Tier Totals 2 2 3 3 10 2 2 1 2 7 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the Tier Totals in each K/A category shall not be less than two).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 75 points for RO and 100 points for SRO.
- 3. Select topics from many systems; avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
- 6.
- The generic 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.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings for the appropriate license level, and the point totals for each system and category. Enter the tier totals for each category in the table above.
NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
007 Reactor Trip-Stabilization-Recovery / 1 X 06 Rx Trip: verification that the control 4.4 / 4.5 1 rods are in after the trip 009 Small Break LOCA / 3 X 01 Natural Circulation and Cooling, 4.2 / 4.7 2 including reflux boiling (IPE/PRA) 011 Large Break LOCA / 3 X 08 Flowpath for sump recirculation 3.9 / 4.1 3 (IPE/PRA) 015/17 RCP Malfunctions / 4 X 03 Sequence of events for manually 3.7 / 4.0 4 tripping reactor and RCP as a result of an RCP malfunction 022 Loss of Reactor Coolant Makeup / 2 X 2.1.30 Ability to locate and operate 3.9 / 3.4 5 components (IPE/PRA) 025 Loss of RHR System / 4 X 07 Pump cavitation (IPE/PRA) 3.4 / 3.7 6 026 Loss of Component Cooling Water/8 X 05 The CCW surge tank, including level 3.1 / 3.1 7 control and level alarms, and radiation alarm (IPE/PRA) 027 Pressurizer Pressure Control System X 2.1.28 Knowledge of the purpose and 3.2 / 3.3 8 Malfunction / 3 function of major system components and controls 040 Steam Line Rupture - Excessive X 06 High-energy steam line break 3.7 / 3.8 9 Heat Transfer / 4 considerations 054 Loss of Main Feedwater / 4 X 01 MFW line break depressurizes the S/G 4.1 / 4.3 10 (similar to a steam line break) 055 Station Blackout / 6 X 2.1.23 Ability to perform specific system 3.9 / 4.0 11 and integrated procedures during all modes of operation (IPE/PRA) 056 Loss Of Off-Site Power / 6 X 31 PZR heater group control switches 3.3 / 3.3 12 057 Loss of Vital AC Elec. Inst. Bus / 6 X 04 RWST and VCT valves 3.5 / 3.6 13 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
058 Loss of DC Power / 6 X 2.1.27 Knowledge of system purpose and or 2.8 / 2.9 14 function (IPE/PRA) 062 Loss of Nuclear Svc Water / 4 X 04 Normal values and upper limits for the 2.5 / 2.9 15 temperatures of the components cooled by SWS (IPE/PRA) 065 Loss Of Instrument Air / 8 X 2.4.50 Ability to verify system alarm 3.3 / 3.3 16 setpoints and operate controls identified in the alarm response manual W/E04 LOCA Outside Containment / 3 X 02 Heat removal systems and the 3.8 / 4.0 17 relationship between their proper operation and the operation of the facility W/E05 Inadequate Heat Transfer - Loss of X 02 Facilitys heat removal systems, 3.9 / 4.2 18 Secondary Heat Sink / 4 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility K/A Category Totals: 3 2 2 4 2 5 Group Point Total: 18 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
001 Continuous Rod Withdrawal / 1 X 02 Rod in-out-hold switch 3.6 / 3.4 19 003 Dropped Control Rod / 1 X 05 Reactor Power-Turbine Power 4.1 / 4.1 20 037 Steam Generator Tube Leak / 3 X 12 Flow rate of leak 3.3 / 4.1 21 059 Accidental Liquid Radwaste Rel. / 9 X 01 Termination of a release of radioactive 3.5 / 3.9 22 liquid 060 Accidental Gaseous Radwaste Rel. / 9 X 02 Biological effects of various types of 2.5 / 3.1 23 radiation, exposure levels that are acceptable for personnel in a nuclear power plant; units used for radiation intensity measurements and for radiation 061 ARMS System Alarms / 7 X 2.4.31 Knowledge of annunciators alarms 3.3 / 3.4 24 and indications, and use of response instructions W/E02 SI Termination / 3 X 01 Components, and functions of control 3.4 / 3.9 25 and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E13 Steam Generator Over-pressure / 4 X 04 RO function within the control room 3.1 / 3.3 26 team that procedures are adhered to and the limitations in the facility license amendments are not violated W/E03 LOCA Cooldown-Depress / 4 X 02 Operating behavior characteristics of 3.7 / 3.9 27 the facility K/A Category Point Totals: 1 1 2 3 1 1 Group Point Total: 9 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
003 Reactor Coolant Pump X 2.4.4 Ability to recognize abnormal 4.0 / 4.3 28 indications for system operating parameters which are entry conditions for emergency and abnormal operating procedures 004 Chemical and Volume Control X 11 Temperature/pressure control in 3.1 / 3.6 29 letdown line: prevent boiling, lifting reliefs, hydraulic shock, piping damage, and burst (IPE/PRA) 004 Chemical and Volume Control X 24 Malfunction of controllers and 2.5 / 2.6 30 positioners (IPE/PRA) 005 Residual Heat Removal X 01 Controls and indication for RHR 3.6 / 3.4 31 pumps (IPE/PRA) 006 Emergency Core Cooling X 06 Relationship between ECCS flow 3.5 / 3.9 32 and RCS pressure 007 Pressurizer Relief/Quench Tank X 03 Monitoring quench tank 2.6 / 2.7 33 temperature 008 Component Cooling Water X 02 Bus power supplies to CCW 3.0 / 3.2 34 pump, including emergency backup (IPE/PRA) 008 Component Cooling Water X 04 Surge tank level (IPE/PRA) 3.1 / 3.2 35 010 Pressurizer Pressure Control X 02 Constant enthalpy expansion 2.6 / 3.0 36 through a valve 012 Reactor Protection X 06 Trip logic 3.7 / 3.7 37 013 Engineered Safety Feature Actuation X 07 AFW System 4.1 / 4.4 38 022 Containment Cooling X 03 Fan motor thermal overload / 2.6 / 3.0 39 high-speed operation 026 Containment Spray X 02 Cooling Water 4.1 / 4.1 40 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
039 Main and Reheat Steam X 04 Malfunctioning Steam Dump 3.4 / 3.7 41 056 Condensate X 03 MFW 2.6 / 2.6 42 056 Condensate X 04 Loss of condensate pumps 2.6 / 2.8 43 059 Main Feedwater X 02 AFW system (IPE/PRA) 3.6 / 3.7 44 059 Main Feedwater X 11 Failure of feedwater control 3.0 / 3.3 45 system 061 Auxiliary/Emergency Feedwater X 02 Loss effect on S/G (IPE/PRA) 4.2 / 4.4 46 062 AC Electrical Distribution X 03 Effect on instrumentation and 2.5 / 2.8 47 controls of switching power supplies 063 DC Electrical Distribution X 03 Battery charger and battery 2.9 / 3.5 48 063 DC Electrical Distribution X 01 Major DC loads 2.9 / 3.1 49 064 Emergency Diesel Generator X 10 Automatic load sequencer: 3.5 / 4.0 50 blackout (IPE/PRA) 073 Process Radiation Monitoring X 2.1.32 Ability to explain and apply 3.4 / 3.8 51 all system limits and precautions 076 Service Water X 05 RHR components, controls, 3.0 / 3.2 52 sensors, indicators, and alarms, including rad monitors (IPE/PRA) 076 Service Water X 01 SWS pumps (IPE/PRA) 2.9 / 2.9 53 078 Instrument Air X 01 Monitor automatic operation, 3.1 / 3.2 54 including air pressure 103 Containment X 03 Phase A and B isolation 3.5 / 3.8 55 K/A Category Totals: 4 2 3 2 2 1 3 5 2 2 2 Group Point Total: 28 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
011 Pressurizer Level Control X 12 Criteria and purpose of PZR 2.7 / 3.3 56 level program 014 Rod Position Indication X 06 Individual and group 3.4 / 3.7 57 misalignment 015 Nuclear Instrumentation X 02 Discriminator/ Compensation 2.6 / 2.9 58 circuits 017 In-core Temperature Monitor X 01 Indication of normal, natural, and 3.6 / 3.8 59 interrupted circulation of RCS 028 H2 Recombiner and Purge Control X 01 Hydrogen concentration 3.4 / 3.8 60 029 Containment Purge X 03 Automatic purge isolation 3.2 / 3.5 61 034 Fuel Handling Equipment X 01 Fuel protection from binding and 2.6 / 3.4 62 dropping 068 Liquid Radwaste X 10 Radiation monitors 2.5 / 2.9 63 072 Area Radiation Monitoring X 01 Radiation levels 3.4 / 3.6 64 086 Fire Protection X 01 Fire water pumps 3.3 / 3.3 65 K/A Category Totals: 0 0 0 3 1 2 2 0 1 1 0 Group Point Total: 10 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline - SRO - Only Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
008 Pressurizer Vapor Space Accident / 3 X 12 PZR level indicators 3.7 76 038 Steam Gen. Tube Rupture / 3 X 01 When to isolate one or more S/Gs 4.7 77 (IPE/PRA) 055 Station Blackout / 6 X 2.4.44 Knowledge of emergency plan 4.0 78 protective action recommendations (IPE/PRA) 056 Loss Of Off-Site Power / 6 X 73 PZR heater on/off (IPE/PRA) 3.6 79 057 Loss of Vital AC Inst Bus / 6 X 2.4.4 Ability to recognize abnormal 4.3 80 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures 065 Loss Of Instrument Air / 8 X 2.4.48 Ability to interpret control room 3.8 81 indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions W/E04 LOCA Outside Containment / 3 X 01 Facility conditions and selection of 4.3 82 appropriate procedures during abnormal and emergency operations K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline - SRO - Only Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#
003 Dropped Control Rod / 1 X 2.2.22 Knowledge of limiting conditions for 4.1 83 operations and safety limits 033 Loss of Intermediate Range NI / 7 X 09 Conditions which allow bypass of IR 3.7 84 level trip switch 036 Fuel Handling Accident / 8 X 2.4.10 Knowledge of annunciator 3.1 85 response procedures 068 Control Room Evacuation / 8 X 05 Availability of a heat sink 4.3 86 W/E08 RCS Overcooling - PTS / 4 X 01 Facility conditions and selection of 4.2 87 appropriate procedures during abnormal and emergency operations K/A Category Point Totals: 0 0 0 0 3 2 Group Point Total: 5 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline - SRO-Only Form ES-401-2 Plant Systems - Tier 2 / Group 1 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
003 Reactor Coolant Pump X 02 Conditions which exist for an 3.9 88 abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 005 Residual Heat Removal X 02 Pressure transient protection 3.7 89 during cold shutdown (IPE/PRA) 062 AC Electrical Distribution X 2.2.22 Knowledge of limiting 4.1 90 conditions for operation and safety limits 103 Containment X 04 Containment evacuation 3.6 91 (including recognition of the alarm)
K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 1 Group Point Total: 4 NUREG-1021 Draft Revision 9
ES-401 2004 Callaway Examination Outline - SRO-Only Form ES-401-2 Plant Systems - Tier 2 / Group 2 E/APE # / Name / Safety Function K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Q#
002 Reactor Coolant X 2.1.32 Ability to explain and apply 3.8 92 all system limits and precautions 041 Steam Dump / Turbine Bypass Control X 2.4.49 Ability to perform without 4.0 93 reference to procedures those actions that require immediate operation of system components and controls K/A Category Totals: 0 0 0 0 0 0 0 0 0 0 2 Group Point Total: 2 NUREG-1021 Draft Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: March 2004 Examination Level: RO Operating Test Number:
Administrative Topic Describe activity to be performed (see Note)
Conduct of Operations/ Determine Boration/Dilution Requirement For A Power Increase Interpret Reference G 2.1.25 2.8 A1 RO/SRO Materials Bank-Modified Conduct of Operations/ Perform Channel Checks On MCB Indicators Recognize System G 2.1.33 3.4 A2 RO Operating Indications Bank-Modified Equipment Control/ Determine WPA Requirements For Pump Maintenance Tagging & Clearance G 2.2.13 3.6 A3 RO Procedures Bank-Modified Radiation Control/ Determination Of Radiological Requirements To Enter A High Perform Procedures To Rad Area Guard Against Personnel G 2.3.10 2.9 A4 RO/SRO Exposure Bank 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.
FACILITY REPRESENTATIVE: DATE:
CHIEF EXAMINER: DATE:
NUREG-1021 Revision 8
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- Callaway Date of Examination: March 2004 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 Safety Code
- Function
- a. Place Containment H2 Analyzer In Service D, S 5 028A4.03 3.1/3.3 S1
- c. Prepare For Hot Leg Recirculation N, S 4-P 011EA1.11 4.2/4.2 S3
- d. Place Ctmt Shutdown Purge In Service N, S 8 029A2.03 2.7/3.1 S4
- e. Place Steam Dumps In Steam Pressure Mode D, A, L, S 4-S 041A4.08 3.0/3.1 S5
- f. Cross-Connecting Load Centers D, A, L, S 6 062A4.01 3.3/3.1 S6
- g. Perform Control Rod Partial Movement Test D, L, S 1 001A4.03 4.0/3.7 S7
- h. Respond To A Failed Power Range Instrument D, C 7 015A4.03 3.8/3.9 C1 Initiate Cold Overpressure Mitigation B/U 010A2.03 4.1/4.2 Backup D, A, L, S 3 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. Shift An Instrument Bus From Backup to Normal Power D, P 6 062A4.04 2.6/2.7 P1
- j. Locally Close Valves For A CIS-B D, R, P 5 103A2.03 3.5/3.8 P2
- k. Maintain Fire System Pressure D, A, P 8 086A4.01 3.3/3.3 P3
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (P)lant NUREG-1021 Page 1 of 2 Revision Draft Rev 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 FACILITY REPRESENTATIVE: DATE:
CHIEF EXAMINER: DATE:
NUREG-1021 Page 2 of 2 Revision Draft Rev 9
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: March 2004 Examination Level: SRO Operating Test Number:
Administrative Topic Describe activity to be performed (see Note)
Conduct of Operations/ Determine Boration/Dilution Requirement For A Power Increase Interpret Reference G 2.1.25 3.1 A1 RO/SRO Materials Bank-Modified Conduct of Operations/ Determine Reportability Requirements Make Accurate Reports G 2.1.18 3.0 A2 SRO New Equipment Control/ Review Surveillance For Test Results Tagging & Clearance G 2.2.12 3.4 A3 SRO Procedures New Radiation Control/ Determination Of Radiological Requirements To Enter A High Knowledge Of Rad Area Surveillance Procedures G 2.3.10 3.3 A4 RO/SRO Bank Emergency Plan/ Emergency Event Classification RERP Notifications G 2.4.41 4.1 A5 SRO Bank 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.
FACILITY REPRESENTATIVE: DATE:
CHIEF EXAMINER: DATE:
NUREG-1021 Revision 8
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Callaway Date of Examination: March 2004 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 Safety Code
- Function
- a. Place Containment H2 Analyzer In Service D, S 5 028A4.03 3.1/3.3 S1
- c. Prepare For Hot Leg Recirculation N, A, S 4-P 011EA1.11 4.2/4.2 S3
- d. Place Ctmt Shutdown Purge In Service N, S 8 029A2.03 2.7/3.1 S4
- e. Place Steam Dumps In Steam Pressure Mode D, A, L, S 4-S 041A4.08 3.0/3.1 S5
- f. Cross-Connecting Load Centers D, A, L, S 6 062A4.01 3.3/3.1 S6
- h. Respond To A Failed Power Range Instrument D, C 7 015A4.03 3.8/.9 C1 B/U. Initiate Cold Overpressure Mitigation D, A, L, S 3 010A2.03 4.1/4.2 Backup In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. Shift An Instrument Bus From Backup To Normal Power D, P 6 062A4.04 2.6/2.7 P1
- j. Locally Close Valves For A CIS-B D, R, P 5 103A2.03 3.5/3.8 P2
- k. Maintain Fire System Pressure D, A, P 8 086A4.01 3.3/3.3 P3
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (P)lant FACILITY REPRESENTATIVE: DATE:
CHIEF EXAMINER: DATE:
NUREG-1021 Page 1 of 2 Revision Draft Rev 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Callaway Date of Examination: March 2004 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 Safety Code
- Function
- b. Prepare For Hot Leg Recirculation N, A, S 4-P 011EA1.11 4.2/4.2 S3
- c. Place Steam Dumps In Steam Pressure Mode D, A, L, S 4-S 041A4.08 3.0/3.1 S5 Initiate Cold Overpressure Mitigation B/U 010A2.03 4.1/4.2 Backup D, A, L, S 3 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- d. Locally Close Valves For A CIS-B D, R, P 5 103A2.03 3.5/3.8 P2
- e. Maintain Fire System Pressure D, A, P 8 086A4.01 3.3/3.3 P3
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (P)lant FACILITY REPRESENTATIVE: / DATE:
CHIEF EXAMINER: DATE:
NUREG-1021 Page 1 of 1 Revision Draft Rev 9
Callaway Rev. 0, Nov. 25, 2003 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - March 2004 SCENARIO # ILE2004DS-1 EXAMINERS: APPLICANTS:
INITIAL CONDITIONS: 80% Reactor Power, 'A' CCP OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type
B C Letdown Isolation Valve Fails Closed 004A2.07 (RO, SRO) (3.4 / 3.7)
C N Place Excess Letdown In Service 028AA1.05 (RO, SRO) (2.8 / 2.9)
D C A RCP High Vibration 015AA1.
(ALL) (3.1 / 3.2)
N (BOP)
E Plant Shutdown Due To RCP High Vibration 004A4.01 R
(3.8 / 3.9)
(RO/SRO)
F C A S/G PORV Failure 041A4.06 (BOP, SRO) (2.9 / 3.1)
G M Loss Of Off-Site Power And NB02 056AA2.44 PRE (ALL) (4.3 / 4.5)
H C Auto Reactor Trip Failure 029EA1.12 PRE (ALL) (4.1 / 4.0)
I C TDAFP Fails To Auto Start 061A2.04 PRE (ALL) (3.4 / 3.8)
J C Loss Of All AC Due To NE01 Failure (IPE/PRA) 055EA2.02 PRE (ALL) (4.4 / 4.6)
- (N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE: DATE:
CHIEF EXAMINER: DATE:
NUREG -1021 Draft Revision 9
Callaway Rev. 0, Nov. 25, 2003 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - March 2004 SCENARIO # ILE2004DS-2 EXAMINERS: APPLICANTS:
INITIAL CONDITIONS: 100% Reactor Power, 'A' CCP OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type
B I B S/G Pressure Channel Failure Low 035A2.03 (BOP, SRO) (3.4 / 3.6)
C I Loop 1 Hot Leg RTD Failure High 016A2.01 (RO, SRO) (3.0 / 3.1)
D C RCP Seal Failure 003A2.01 (ALL) (3.5 / 3.9)
E M LOCA A Cold Leg (IPE/PRA) 011EA1.13 (ALL) (4.1 / 4.2)
F C Auto SI Initiation Failure 013A4.03 PRE (ALL) (4.5 / 4.7)
G C CCP Start Failure 006A3.02 PRE (ALL) (4.1 / 4.1)
H C EJ HIS8804B Valve Loss Of Power 005A2.04 PRE (ALL) (2.9 / 2.9)
I C A RHR Pump Trip 005A4.01 PRE (ALL) (3.6 / 3.4)
- (N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE: DATE:
CHIEF EXAMINER: DATE:
NUREG -1021 Draft Revision 9
Callaway Rev. 0, Nov. 25, 2003 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - March 2004 SCENARIO # ILE2004DS-BU EXAMINERS: APPLICANTS:
INITIAL CONDITIONS: 100% Reactor Power, 'A' CCP OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No. Type
B I Pressurizer Pressure Channel Failure High 027AA2.15 (RO, SRO) (3.7 / 4.0)
C I B S/G Level Channel Failure Low 035A2.03 (BOP, SRO) (3.4 / 3.6)
D M Multiple Rod Drop 003AA2.01 (ALL) (3.7 / 3.9)
E C NB02 Bus Lockout 062A3.05 PRE (ALL) (3.5 / 3.6)
F C Auto Turbine Trip Failure 045A3.04 PRE (BOP) (3.4 / 3.6)
G C A CCW Pump Trip With Auto Start Failure Of C CCW 008A2.01 PRE (ALL) Pump (3.3 / 3.6)
H M Loss Of All Feedwater (IPE/PRA) E05EA1.1 PRE (ALL) (4.1 / 4.0)
- (N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE: DATE:
CHIEF EXAMINER: DATE:
NUREG -1021 Draft Revision 9