ML061070593
| ML061070593 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/30/2005 |
| From: | Gody A Operations Branch IV |
| To: | Omaha Public Power District |
| References | |
| 50-285/05-301 | |
| Download: ML061070593 (25) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 06/30/2005 Date Of Exam: 07/11/2005 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total K A A2 G*
- 1. 1 2 1 4 4 3 4 18 0 0 0 0 0 Emergency 2 1 3 1 2 0 2 9 0 0 0 0 0 Abnormal Plant Tier 3 4 5 6 3 6 27 0 0 0 0 0 Evolutions Totals 1 3 1 2 3 2 1 3 3 4 3 3 28 0 0 0 0 0 2.
2 2 1 1 0 0 2 1 1 0 1 1 10 0 0 0 0 0 Plant Systems Tier 5 2 3 3 2 3 4 4 4 4 4 38 0 0 0 0 0 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowledge And 10 0 Abilities Categories 3 2 2 3 0 0 0 0 Note:
- 1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category /tier.
6.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the columns labeled "K" and "A".
Use duplicate pages for RO and SRO-only exams.
- 8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
- 9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
1
PWR RO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X AA1.06 - Control of PZR level 3.6 1 3
000009 Small Break LOCA / 3 X EA2.08 - Letdown isolation valve 2.9* 1 position indication 000011 Large Break LOCA / 3 X 2.4.6 - Knowledge symptom based EOP 3.1 1 mitigation strategies.
000015 RCP Malfunctions / 4 X AA1.16 - Low-power reactor trip block 3.2* 1 status lights 000022 Loss of Rx Coolant Makeup / 2 X AA1.03 - PZR level trend 3.2 1 000025 Loss of RHR System / 4 X AK2.03 - Service water or closed 2.7 1 cooling water pumps 000026 Loss of Component Cooling Water / X AK3.02 - The automatic actions 3.6 1 8 (alignments) within the CCWS resulting from the actuation of the ESFAS 000027 Pressurizer Pressure Control System X AA2.18 - Operable control channel 3.4 1 Malfunction / 3 000038 Steam Gen. Tube Rupture / 3 X EK1.03 - Natural circulation 3.9 1 000054 Loss of Main Feedwater / 4 X 2.4.50 - Ability to verify system alarm 3.3 1 setpoints and operate controls identified in the alarm response manual.
000055 Station Blackout / 6 X 2.1.23 - Ability to perform specific 3.9 1 system and integrated plant procedures during all modes of plant operation.
000056 Loss of Off-site Power / 6 X AA1.02 - ESF bus synchronization 4.0* 1 select switch to close bus tie breakers 000057 Loss of Vital AC Inst. Bus / 6 X AA2.03 - RPS panel alarm annunciators 3.7 1 and trip indicators 000058 Loss of DC Power / 6 X 2.4.4 - Ability to recognize abnormal 4.0 1 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
000062 Loss of Nuclear Svc Water / 4 X AK3.02 - The automatic actions 3.6 1 (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air / 8 X AK3.08 - Actions contained in EOP for 3.7 1 loss of instrument air 1
PWR RO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points CE/E02 Reactor Trip - Stabilization - X EK3.1 - Facility operating 3.2 1 Recovery / 1 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 CE/E05 Steam Line Rupture - Excessive X EK1.1 - Components, capacity, and 3.0 1 Heat Transfer / 4 function of emergency systems K/A Category Totals: 2 1 4 4 3 4 Group Point Total: 18 2
PWR RO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000001 Continuous Rod Withdrawal / 1 X AK2.08 - Individual rod display lights 3.1 1 and indications 000024 Emergency Boration / 1 X AK1.04 - Low temperature limits for 2.8 1 boron concentration 000037 Steam Generator Tube Leak / 3 X AA1.13 - S/G blowdown radiation 3.9 1 monitors 000060 Accidental Gaseous Radwaste Rel. / X AK2.02 - Auxiliary building ventilation 2.7 1 9 system 000068 Control Room Evac. / 8 X AK2.02 - Reactor trip system 3.7 1 000074 Inad. Core Cooling / 4 X EA1.05 - PORV 3.9 1 CE/A11 RCS Overcooling - PTS / 4 X 2.2.22 - Knowledge of limiting 3.4 1 conditions for operations and safety limits.
CE/A16 Excess RCS Leakage / 2 X 2.1.30 - Ability to locate and operate 3.9 1 components, including local controls.
CE/E09 Functional Recovery X EK3.2 - Normal, abnormal and 3.2 1 emergency operating procedures associated with (Functional Recovery)
K/A Category Totals: 1 3 1 2 0 2 Group Point Total: 9 1
PWR RO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X A1.08 - Seal water 2.5 1 temperature 003 Reactor Coolant Pump X A3.04 - RCS flow 3.6 1 004 Chemical and Volume Control X A2.16 - T-ave. and T-ref. 3.2 1 deviations 004 Chemical and Volume Control X A4.12 - Boration/dilution 3.8 1 batch control 005 Residual Heat Removal X K4.02 - Modes of operation 3.2 1 005 Residual Heat Removal X K5.02 - Need for adequate 3.4 1 subcooling 006 Emergency Core Cooling X A3.06 - Valve lineups 3.9 1 007 Pressurizer Relief/Quench X K5.02 - Method of forming 3.1 1 Tank a steam bubble in the PZR 008 Component Cooling Water X K3.02 - CRDS 2.9 1 010 Pressurizer Pressure Control X A1.09 - Tail pipe 3.4 1 temperature and acoustic monitors 012 Reactor Protection X 2.1.32 - Ability to explain 3.4 1 and apply all system limits and precautions.
013 Engineered Safety Features X 2.1.2 - Knowledge of 3.0 1 Actuation operator responsibilities during all modes of plant operation.
013 Engineered Safety Features X K1.12 - ED/G 4.1 1 Actuation 022 Containment Cooling X A2.04 - Loss of service 2.9* 1 water 026 Containment Spray X K1.02 - Cooling water 4.1 1 039 Main and Reheat Steam X K4.05 - Automatic isolation 3.7 1 of steam line 059 Main Feedwater X K4.18 - Automatic 2.8* 1 feedwater reduction on plant trip 059 Main Feedwater X A3.06 - Feedwater isolation 3.2* 1 061 Auxiliary/Emergency X A1.04 - AFW source tank 3.9 1 Feedwater level 062 AC Electrical Distribution X 2.4.50 - Ability to verify 3.3 1 system alarm setpoints and operate controls identified in the alarm response manual.
063 DC Electrical Distribution X A4.03 - Battery discharge 3.0* 1 rate 063 DC Electrical Distribution X K1.02 - AC electrical 2.7 1 system 1
PWR RO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 064 Emergency Diesel Generator X K6.07 - Air receivers 2.7 1 064 Emergency Diesel Generator X A2.11 - Conditions 2.6 1 (minimum load) required for unloading an ED/G 073 Process Radiation Monitoring X A4.03 - Check source for 3.1 1 operability demonstration 076 Service Water X K2.01 - Service water 2.7* 1 078 Instrument Air X K3.02 - Systems having 3.4 1 pneumatic valves and controls 103 Containment X A3.01 - Containment 3.9 1 isolation K/A Category Totals: 3 1 2 3 2 1 3 3 4 3 3 Group Point Total: 28 2
PWR RO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K1.05 - NIS and RPS 4.5 1 002 Reactor Coolant X K6.03 - Reactor vessel level 3.1 1 indication 011 Pressurizer Level Control X K2.01 - Charging pumps 3.1 1 014 Rod Position Indication X A4.02 - Control rod 3.4 1 mode-select switch 017 In-core Temperature Monitor X K1.01 - Plant computer 3.2* 1 033 Spent Fuel Pool Cooling X A1.02 - Radiation 2.8 1 monitoring systems 035 Steam Generator X A2.06 - Small break LOCA 4.5 1 041 Steam Dump/Turbine Bypass X 2.4.4 - Ability to recognize 4.0 1 Control abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
045 Main Turbine Generator X K3.01 - Remainder of the 2.9 1 plant 086 Fire Protection X K6.04 - Fire, smoke, and 2.6 1 heat detectors K/A Category Totals: 2 1 1 0 0 2 1 1 0 1 1 Group Point Total: 10 1
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all 3.0 1 modes of plant operation.
2.1.3 Knowledge of shift turnover practices. 3.0 1 2.1.29 Knowledge of how to conduct and verify valve 3.4 1 lineups.
Category Total: 3 Equipment Control 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 2.2.30 Knowledge of RO duties in the control room 3.5 1 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.
Category Total: 2 Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1 radiation control requirements.
2.3.2 Knowledge of facility ALARA program. 2.5 1 Category Total: 2 Emergency Procedures/Plan 2.4.6 Knowledge symptom based EOP mitigation 3.1 1 strategies.
2.4.15 Knowledge of communications procedures 3.0 1 associated with EOP implementation.
2.4.23 Knowledge of the bases for prioritizing 2.8 1 emergency procedure implementation during emergency operations.
Category Total: 3 Generic Total: 10 1
ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 06/30/2005 Date Of Exam: 07/11/2005 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total K A A2 G*
- 1. 1 0 0 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 0 0 0 0 0 0 3 1 4 Abnormal Plant Tier 0 0 0 0 0 0 0 0 0 6 4 10 Evolutions Totals 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 3 5 2.
2 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 1 3 Plant Systems Tier 0 0 0 0 0 0 0 0 0 0 0 0 1 0 3 4 8 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 2 2 1 2 Note:
- 1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category /tier.
6.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the columns labeled "K" and "A".
Use duplicate pages for RO and SRO-only exams.
- 8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
- 9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
1
PWR SRO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000009 Small Break LOCA / 3 X EA2.25 - Reactor trip setpoints 4.1 1 000015 RCP Malfunctions / 4 X 2.1.32 - Ability to explain and apply all 3.8 1 system limits and precautions.
000025 Loss of RHR System / 4 X AA2.07 - Pump cavitation 3.7 1 000026 Loss of Component Cooling Water / X AA2.02 - The cause of possible CCW 3.6 1 8 loss 000038 Steam Gen. Tube Rupture / 3 X 2.4.30 - Knowledge of which events 3.6 1 related to system operations/status should be reported to outside agencies.
CE/E02 Reactor Trip - Stabilization - X 2.2.25 - Knowledge of bases in 3.7 1 Recovery / 1 technical specifications for limiting conditions for operations and safety limits.
K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 1
PWR SRO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000068 Control Room Evac. / 8 X AA2.10 - Source range count rate 4.4* 1 000074 Inad. Core Cooling / 4 X EA2.02 - Availability of main or 4.6 1 auxiliary feedwater 000076 High Reactor Coolant Activity / 9 X 2.1.14 - Knowledge of system status 3.3 1 criteria which require the notification of plant personnel.
CE/E09 Functional Recovery X EA2.1 - Facility conditions and 4.4 1 selection of appropriate procedures during abnormal and emergency operations K/A Category Totals: 0 0 0 0 3 1 Group Point Total: 4 1
PWR SRO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 004 Chemical and Volume Control X A2.11 - Loss of IAS 4.2 1 006 Emergency Core Cooling X 2.1.33 - Ability to recognize 4.0 1 indications for system operating parameters which are entry-level conditions for technical specifications.
062 AC Electrical Distribution X A2.09 - Consequences of 3.0* 1 exceeding current limitations 063 DC Electrical Distribution X 2.2.22 - Knowledge of 4.1 1 limiting conditions for operations and safety limits.
103 Containment X 2.1.32 - Ability to explain 3.8 1 and apply all system limits and precautions.
K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 3 Group Point Total: 5 1
PWR SRO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X A2.13 - ATWS 4.6 1 002 Reactor Coolant X 2.2.22 - Knowledge of 4.1 1 limiting conditions for operations and safety limits.
034 Fuel Handling Equipment X K4.01 - Fuel protection 3.4 1 from binding and dropping K/A Category Totals: 0 0 0 1 0 0 0 1 0 0 1 Group Point Total: 3 1
Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline Printed: 06/30/2005 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.4 Knowledge of shift staffing requirements. 3.4 1 2.1.34 Ability to maintain primary and secondary plant 2.9 1 chemistry within allowable limits.
Category Total: 2 Equipment Control 2.2.5 Knowledge of the process for making changes in 2.7 1 the facility as described in the safety analysis report.
2.2.19 Knowledge of maintenance work order 3.1 1 requirements.
Category Total: 2 Radiation Control 2.3.10 Ability to perform procedures to reduce 3.3 1 excessive levels of radiation and guard against personnel exposure.
Category Total: 1 Emergency Procedures/Plan 2.4.29 Knowledge of the emergency plan. 4.0 1 2.4.45 Ability to prioritize and interpret the significance 3.6 1 of each annunciator or alarm.
Category Total: 2 Generic Total: 7 1
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 Type Describe activity to be performed (see Note) Code*
Administrative JPM - Calculate shutdown margin with a Conduct of Operations M known inoperable CEA K/A 2.1.7 (RO 3.7)
Administrative JPM - Determine minimum HPSI flow Conduct of Operations N required to remove decay heat following sump strainer blockage K/A 2.1.25 (RO 2.8)
Administrative JPM - Verify boration path during plant Equipment Control N shutdown conditions with equipment out of service K/A 2.2.24 (RO 2.6)
Administrative JPM - RCA Entry and Exit (Discover spill Radiation Control M 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 Type Describe activity to be performed (see Note) Code*
Administrative JPM - Review shutdown margin Conduct of Operations M calculation with boron depletion K/A 2.1.7 (SRO 3.7)
Administrative JPM - Determine equipment operability Conduct of Operations D requirements during mode transition K/A 2.1.22 (SRO 3.3)
Administrative JPM - Review required shift surveillance Equipment Control M OP-ST-SHIFT-0001 K/A 2.2.12 (SRO 3.4)
Administrative JPM - Authorize Waste Gas Decay Tank Radiation Control N Release K/A 2.3.6 (SRO 3.1)
Administrative JPM - Classify Event and make Protective Emergency Plan M 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
- b. 022 / JPM-0718 Place Containment Cooling Unit in Service S,D 5 K/A 022000 A4.01 (RO 3.6 / SRO 3.6)
- d. 086 JPM-0726 Restore CR Ventilation following smoke alarm S, D, A 9 K/A 000067 AA1.05 (RO 3.0 / SRO 3.1)
- e. 062 / JPM-0042 Transfer Clutch Power Supply/x-tie inst busses S, M, A 6 K/A 062000 A2.10 (RO 3.0 / SRO 3.3)
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump S, D, A, L 4P K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
- g. 061 / JPM-R AFW Operability Verification From AI-179 S, N, L 4S K/A 061000 K1.01 (RO 4.1 / SRO 4.1)
- h. 003 / JPM-0627 Reduce RCS Pressure using Auxiliary Spray S, N, A 3 K/A 010000 A4.01 (RO 3.7 / SRO 3.5)
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- j. 064 / JPM-0356 Local Emergency Start of a Diesel Generator N, A, E 6 K/A 064000 A4.06 (RO 3.9 / SRO 3.9)
- k. 028 / JPM-0719M Startup Containment Hydrogen Purge and M, R, E 5 Makeup K/A 068000 A3.02 (RO 3.6 / SRO 3.6)
@ 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (L)ow-Power >1/>1/>1 (N)ew or (M)odified from bank including 1(A) >2/>2/>1 (P)revious 2 exams < 3 / < 3 / < 2 (randomly selected)
(R)CA >1/>1/>1 (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 : 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
- b. 022 / JPM-0718 Place Containment Cooling Unit in Service S,D 5 K/A 022000 A4.01 (RO 3.6 / SRO 3.6) c.
- d. 086 JPM-0726 Restore CR Ventilation following smoke alarm S, D, A 9 K/A 000067 AA1.05 (RO 3.0 / SRO 3.1)
- e. 062 / JPM-0042 Transfer Clutch Power Supply/x-tie inst busses S, M, A 6 K/A 062000 A2.10 (RO 3.0 / SRO 3.3)
- f. 003 / JPM-0613A Shutdown a Reactor Coolant Pump S, D, A, L 4P K/A 003000 A4.06 (RO 2.9 / SRO 2.9)
- g. 061 / JPM-R AFW Operability Verification From AI-179 S, N, L 4S K/A 061000 K1.01 (RO 4.1 / SRO 4.1)
- h. 003 / JPM-0627 Reduce RCS Pressure using Auxiliary Spray S, N, A 3 K/A 010000 A4.01 (RO 3.7 / SRO 3.5)
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- j. 064 / JPM-0356 Local Emergency Start of a Diesel Generator N, A, E 6 K/A 064000 A4.06 (RO 3.9 / SRO 3.9)
- k. 028 / JPM-0719M Startup Containment Hydrogen Purge and M, R, E 5 Makeup K/A 068000 A3.02 (RO 3.6 / SRO 3.6)
@ 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (L)ow-Power >1/>1/>1 (N)ew or (M)odified from bank including 1(A) >2/>2/>1 (P)revious 2 exams < 3 / < 3 / < 2 (randomly selected)
(R)CA >1/>1/>1 (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 : 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. 086 JPM-0726 Restore CR Ventilation following smoke alarm S, D, A 9 K/A 000067 AA1.05 (RO 3.0 / SRO 3.1) e.
f.
- g. 061 / JPM-R AFW Operability Verification From AI-179 S, N, L 4S K/A 061000 K1.01 (RO 4.1 / SRO 4.1) h.
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- j. 064 / JPM-0356 Local Emergency Start of a Diesel Generator N, A, E 6 K/A 064000 A4.06 (RO 3.9 / SRO 3.9)
- k. 028 / JPM-0719M Startup Containment Hydrogen Purge and M, R, E 5 Makeup K/A 068000 A3.02 (RO 3.6 / SRO 3.6)
@ 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (L)ow-Power >1/>1/>1 (N)ew or (M)odified from bank including 1(A) >2/>2/>1 (P)revious 2 exams < 3 / < 3 / < 2 (randomly selected)
(R)CA >1/>1/>1 (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}
Place protected equipment tags on FW-6 and FW-10. Cover simulator fidelity items.
Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event Malf Event Event No. No. Type* Description 1 COP T:F212 I - ATC Letdown flow transmitter fails high - letdown isolates 160 (3:00) 2 COP I - BOP S/G A level transmitter fails low - manual FW flow control T:L903X 0%
(12:00) 60 sec ramp required 3 COP C - BOP IA Compressor trips, standby does not load NCAPCA1C (18:00) TRIP 4 MFP CRD06 C - ATC Dropped CEA - T/S Entry R1G1 (24:00) Deenergized 5 N/A R - ATC TS Required power reduction to 70%
N - BOP 6 MFP C - ATC Instrument Bus Fails - T/S Entry EDS04B (40:00) 7 MSS01A M - ALL Main steam line break inside containment 20%
(50:00) 2 min ramp 8 Preset C - BOP Turbine fails to trip 9 Preset I - ATC CPHS Fails to Actuate or BOP
- (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)
Hang protected equipment tags on FW-6 and FW-10.
Turnover: CCW-Pump, AC-3A and Diesel Driven AFW pump FW-54 are tagged out of service Maintain Power Operations Event Malf Event Event No. No. Type* Description 1 MFP I - ATC Power Range NI Channel C Fails - T/S entry NIS04C (3:00) 2 COP I - BOP S/G B level transmitter fails to 55%
T:L906X (10:00) 55%
3 COP C - BOP Bearing Water Pump AC-9A Trips NBWPAC9 (16:00) A trip 4 T:T122H2 I -ATC RCS T-hot fails - T/S entry 665°F (20:00) 5 MFP C - ATC Charging Pump CH-1B degraded performance CVC16B (30:00) 6 MFP M- Steam Generator Tube Rupture SGN01A (40:00) 15% 120s ALL ramp 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 - 3 Op-Test No. ___________
Examiners: _________________________ Operators: _________________________
Initial Conditions: 49% Power (IC#4)
{PRESET RFP CWS10N CLOSED} {Power 1A1 and 1A2 from 22KV, S/D CH-1A)
Protected equipment tag on FW-5B RunScreens file 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. PCMINT is not available.
Event Malf Event Event No. No. Type* Description 1 MFP C - ATC D/G #1 Radiator Leak - T/S Entry DSG06A (3:00) 100% or BOP 2 COP T:P910 I - BOP PT-910 Fails High 1000 psi (12:00) 3 COP I - ATC Letdown heat exchanger temperature transmitter fails low T:T2897 (18:00) 50°F 4 MFP C - BOP Loss of 161 KV - T/S Entry SWD02B (25:00) 5 COP I - ATC Pressurizer pressure transmitter PT-103Y fails high T:P103Y (35:00) 2556 90 sec ramp 6 COP T: I - BOP S/G B level transmitter LT-906Y fails high (Manual control L906Y (40:00) 100% 60 using Aux controller required) sec ramp 7 MFP C - ATC Raw Water header leak RWS01B (45:00) 25%
8 MFP M - ALL LOCA with Loss of offsite power RCS01C 5%
(55:00) 9 Preset C-BOP Circulating Water Pump Breaker does not open so the 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: 49% Power
{Preset MSS02F 100% E1 30 sec delay} { Place 1A1 and 1A2 on 22 KV, S/D CH-1A}
Protected equipment tags on FW-5B 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. PCMINT is not available.
Event Malf Event Event No. No. Type* Description 1 COP I - ATC VCT Level Transmitter Fails Low JLB218LL (3:00) Fail_set 2 COP I - BOP S/G A Level transmitter fails high T:L903X (8:00) 100% 45 sec ramp 3 COP I - ATC RCS Flow transmitter failure - T/S Entry T:F114YA (15:00) 0 4 MFP I - BOP Inadvertent AFAS actuation - T/S Entry AFW05A (22:00) 5 COP RCAP C - ATC Instrument air to containment isolates 849A&B (30:00) 0%
6 MFP C - BOP Loss of condenser vacuum CND01 30%
(40:00) 300 sec ramp 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
List of Outline changes from initial to final outline WHAT CHANGED? CHANGE Reason for Change RO form ES-401-2 Replaced K/A 000027 AA2.07 No connection between K/A with 000027 AA2.18 event and K/A item Replaced K/A 000057 AA2.01 Operators not expected to with 000057 AA2.03 know by memory. Providing reference would be direct lookup.
SRO form ES-401-4 Removed K/A 062000 A2.09 Discussion with Lead from rejected K/A list. Examiner SRO form ES-401-2 Replaced K/A 007000 A2.05 Added previously rejected with 062000 A2.09 (Tier K/A back into exam (see 2/Group 1) above)
RO ES-301-2 Replaced Transfer Waste Gas Lead Examiner Request JPM Modified JPM-0042 to an Too simple as written alternate path and renamed it Changed JPM-0613A from correction M to D Changed JPM-0627 to A correction Changed safety function on correction JPM d from 8 to 9 Replaced JPM g with new JPM Exam security SRO-I ES-301-2 Replaced Transfer Waste Gas Lead Examiner Request JPM Replaced JPM-0778 with JPM- To prevent overlap with 0042 Administrative JPM Modified JPM-0042 to an Too simple as written alternate path and renamed it Changed JPM-0613A from correction M to D
Changed JPM-0627 to A correction Changed safety function on correction JPM d from 8 to 9 Replaced JPM g with new JPM Exam security SRO-U ES-301-2 Replaced Transfer Waste Gas Lead Examiner Request JPM Changed JPM-0613A from correction M to D Replaced JPM f with JPM d Lead Examiner Request Replaced JPM g with new JPM Exam security SRO Form ES-301-1 Changed review SDM JPM Review SDM with inoperable from SDM with inoperable CEA was used on last SRO CEA to SDM with boron exam depletion Form ES-D-1 scenario Changed event 2 from S/G Automatic control system 1 pressure transmitter to S/G handles failure without level. operator action Form ES-D-1 scenario Changed event 2 from S/G Automatic control system 2 flow transmitter to S/G level. handles failure without operator action Form ES-D-1 scenario Changed event 2 from S/G Automatic control system 4 (spare) pressure transmitter to S/G handles failure without level. operator action