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
06/30/2005 Printed:
ES-401 Facility:
Fort Calhoun PWR Examination Outline Form ES-401-2 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
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 28 18 9
27 10 38 10 1.
Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.
6.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the columns labeled "K" and "A".
Use duplicate pages for RO and SRO-only exams.
SRO-Only Points K
A A2 G*
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 2
3 4
0 0
0 0
0 0
0 8.
For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9.
Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
1
06/30/2005 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 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 AA2.18 - Operable control channel 3.4 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 AA2.03 - RPS panel alarm annunciators and trip 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
06/30/2005 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 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
06/30/2005 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 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
06/30/2005 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 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
06/30/2005 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 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
06/30/2005 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 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 06/30/2005 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
06/30/2005 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
06/30/2005 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
06/30/2005 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
06/30/2005 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
06/30/2005 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 06/30/2005 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 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 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
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 9
- 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 9
- 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.
S, D, A 9
- e.
- f.
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
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 No.
Malf No.
Event Type*
Event Description 1
(3:00)
COP T:F212 160 I - ATC Letdown flow transmitter fails high - letdown isolates 2
(12:00)
COP T:L903X 0%
60 sec ramp I - BOP S/G A level transmitter fails low - manual FW flow control required 3
(18:00)
COP NCAPCA1C TRIP C - BOP IA Compressor trips, standby does not load 4
(24:00)
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 (40:00)
MFP EDS04B C - ATC Instrument Bus Fails - T/S Entry 7
(50:00)
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)
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 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 15% 120s ramp 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 - 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 No.
Malf No.
Event Type*
Event Description 1
(3:00)
MFP DSG06A 100%
C - ATC or BOP D/G #1 Radiator Leak - T/S Entry 2
(12:00)
COP T:P910 1000 psi I - BOP PT-910 Fails High 3
(18:00)
COP T:T2897 50°F I - ATC Letdown heat exchanger temperature transmitter fails low 4
(25:00)
MFP SWD02B C - BOP Loss of 161 KV - T/S Entry 5
(35:00)
COP T:P103Y 2556 90 sec ramp I - ATC Pressurizer pressure transmitter PT-103Y fails high 6
(40:00)
COP T:
L906Y 100% 60 sec ramp I - BOP S/G B level transmitter LT-906Y fails high (Manual control using Aux controller required) 7 (45:00)
MFP RWS01B 25%
C - ATC Raw Water header leak 8
(55:00)
MFP RCS01C 5%
M - ALL LOCA with Loss of offsite power 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 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 30%
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
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 with 000027 AA2.18 No connection between K/A event and K/A item Replaced K/A 000057 AA2.01 with 000057 AA2.03 Operators not expected to know by memory. Providing reference would be direct lookup.
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 Changed safety function on JPM d from 8 to 9 correction Replaced JPM g with new JPM Exam security 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 Changed safety function on JPM d from 8 to 9 correction Replaced JPM g with new JPM Exam security SRO-U ES-301-2 Replaced Transfer Waste Gas JPM Lead Examiner Request Changed JPM-0613A from M to D correction 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 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