ML101750130
| ML101750130 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/03/2010 |
| From: | Caruso J Operations Branch I |
| To: | Entergy Nuclear Northeast |
| HANSELL S | |
| Shared Package | |
| ML092470037 | List: |
| References | |
| TAC U01786 | |
| Download: ML101750130 (30) | |
Text
DRAFT FITZPATRICK RO OUTLINE ES*401 BWR RO Examination Outline Form ES*401*1 Date of Exam: May 2010 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G*
Total 1 2 3 4 5 6
1 2 3 4
Total
- 1.
20 N/A N/A Emergency &
Abnormal Plant 2
7 N/A N/A N/A Evolutions Tier Totals 27 N/A N/A N/A N/A
- 2.
Plant 2
N/A Systems Tier Totals 5
2 3
4 N/A
- 3. Generic Knowledge and Abilities 3
4 2
4 NtA Categories 3
2 2
3 10 N/
NI Nt A
A A
Note:
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the 'Tier Totals*
in each KIA 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.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important. site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KlAs having an importance rating (lR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7:
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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 table above; if fuel handling equipment IS sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2. Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3. select topics from Section 2 of the KIA catalog. and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
Page 1 of 12
DRAFT FITZPATRICK RO OUTLINE ES-401 Form ES-401-1 ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # I Name I Safety Function K
K K A A G KIA Topic(s)
IR 1
2 3
1 2 AK3.02 Knowledge of the operational 295001 Partial or Complete Loss X
3.7 1.
implications of Power/Flow distribution as it of Forced Core Flow Circulation /1 & 4 applies to PARTIAL OR COMPLETE LOSS OF 3.8 FORCED CORE FLOW CIRCULATION:
REACTOR POWER RESPONSE 295003 Partial or Complete Loss of AC X
AK3.01 Knowledge of the reasons for the 3.3
- 2.
16 following as they apply to PARTIAL OR 3.5 COMPLETE LOSS OF AC POWER MANUAL AND AUTO BUS TRANSFER 295004 Partial or Total Loss of DC Pwr X
AK3.03 Knowledge of the reasons for the 3.1
- 3.
/6 following responses as they apply to PARTIAL 3.5 OR COMPLETE LOSS OF D.C. POWER:
REACTOR SCRAM Ixl G2.1.32 Ability to explain and apply system limits 295005 Main Turbine Generator Trip / 3 3.8 4.
and precautions to MAIN TURBINE GENERATOR TRIP 4.0 295006 SCRAM 11 X
AK2.03 Knowledge of the interrelations between 3.7
- 5.
SCRAM and the following:
3.8 CRD HYDRAULIC
. 295016 Control Room Abandonment /
X AA1.05 Ability to operate and/or monitor the 2.8
- 6.
,7 following as they apply to CONTROL ROOM
2.9 ABANDONMENT
D.C. ELECTRICAL DISTRIBUTION 295018 Partial or Total Loss of CCW /
X AA1.01 Ability to operate and/or monitor the 3.3
- 7.
8 following as they apply to PARTIAL OR 3.4 COMPLETE LOSS OF COMPONENT COOLING WATER:
BACKUP SYSTEMS 295019 Partial or Total Loss of Inst. Air X
AA2.02 Ability to determine and/or interpret the 3.6
- 8.
18 following as they apply to PARTIAL OR 3.7 COMPLETE LOSS OF INSTRUMENT AIR:
STATUS OF SAFETY*RELATED INSTRUMENT AIR SYSTEM LOADS 295021 Loss of Shutdown Cooling 14 X
AA1.04 Ability to operate and/or monitor the 3.7
- 9.
following as they apply to LOSS OF 3.7 SHUTDOWN COOLING:
ALTERNATE HEAT REMOVAL METHODS Page 2 of 12
3.6 DRAFT FITZPATRICK RO OUTLINE ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # I Name I Safety Function K
K A A KIA Topic{s)
IR 1
3 1
2 295023 Refueling Acc I 8 X
AK1.02 Knowledge of the operational 3.2
- 10.
implications of the following concepts as they apply to REFUELING ACCIDENTS:
SHUTDOWN MARGIN EK3.01 Knowledge of the reasons for the 295024 High Drywell Pressure I 5 X
3.6 11.
following responses as they apply to HIGH DRYWELL PRESSURE:
4.0 Drywell spray operation G.2.2.22 Knowledge of limiting conditions for 295025 High Reactor Pressure / 3 X
4.0 12.
operations and safety limits: as it applies to High Reactor Pressure 4.7 295026 Suppression Pool High Water X
EK1.01 Knowledge of the operational 3.0
- 13.
Temp./5 implications of the following concepts as they 3.4 apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:
Pump NPSli 295027 High Containment Temperature N/ABL NIA N/A 15 295028 High Drywell Temperature 15 X
EA2.01 Ability to determine and/or interpret the 4.0
- 14.
following as they apply to HIGH DRYWELL
4.1 TEMPERATURE
DRYWELL TEMPERATURE 295030 Low Suppression Pool Water X
EK2.02 Knowledge of the interrelations between 3.7
- 15.
Level 15 LOW SUPPRESSION POOL WATER LEVEL 3.8 and the following:
RCle 295031 Reactor Low Water Levell 2 X
EA2.02 Ability to determine andlor interpret the 4.0
- 16.
following as they apply to REACTOR LOW 4.2 WATER LEVEL: Reactor Power 295037 SCRAM Condition Present and X
EK1.05 Knowledge of the operational 3.4
- 17.
Reactor Power Above APRM implications of the following concepts as they 3.6 Downscale or Unknown/1 apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:
Cold Shutdown Boron Weight 295038 High Off-site Release Rate / 9 X
EK3.02 Knowledge of the reasons for the 3.9
- 18.
following responses as they apply to HIGH OFF 4.2 SITE RELEASE RATE:
System Isolations 600000 Plant Fire On Site I 8 X
AK2.01 Knowledge of the interrelations between 2.6
- 19.
PLANT FIRE ON SITE and the following:
2.7 SENSORS/DETECTORS AND VALVES Page 3 of 12
DRAFT FITZPATRICK RO OUTLINE
Form E~
E/APE # I Name I Safety Function K
1 K
2 K
3 1
A 2
G KIA Topic(s)
I IR 700000 Generator Voltage and Electric Grid Disturbances I 6 X
AA1.03 Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRICAL GRID DISTURBANCES:
3.8 3.7
- 20.
Voltage regulator controls KIA Category Totals:
3 3 51 41 3 2 Group Point Total:
20/7 Page 4 of 12
DRAFT FITZPATRICK RO OUTLINE ES-401 Form ES-401-1 ES-401 E/APE # I Name I Safety Functio s of Main Condenser r Pressure I 3 295008 High Reactor Water Level 12 295009 Low Reactor Water Levell 2 295013 High Suppression Pool Temp.
15 295014 Inadvertent Reactivity Addition 11 295015 Incomplete SCRAM! 1 Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation I 5
&7 295022 Loss of CRD Pumps I 1 295029 High Suppression Pool Water Level 15 295032 High Secondary Containment AreaT 15 295033 High Secondary Containment Area Radiation Levels I 9 ondary Containment Radiation I 9 BWR Examination Outline KIA Topic(s) uate plant make operational judgements as they apply to HIGH REACTOR WATER LEVEL:
Reactor water level AK2.03 Knowledge of the reasons for the following responses as they apply to LOW REACTOR WATER LEVEL:
RECIRCULATION SYSTEM N/ABL AA1.03 Ability to operate and! or monitor the following as they apply to INCOMPLETE SCRAM:
RMCS AK2.03 Knowledge of the interrelations between LOSS OF CRD and the following:
ACCUMULATOR PRESSURES EK3.01 Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL:
EMERGENCY DEPRESSURIZATION nterpret following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS:
AREA RADIATION LEVELS IR 3.7
- 21.
3.7 3.1 22 3.2 3.6
- 23.
3.8 3.4 3.4 3.5
- 25.
3.9 3.8
- 26.
Page 5 of 12 3.9
DRAFT FITZPATRICK RO OUTLINE I ES-401 BWR Examination Outline and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
Safety Function K
1 K
2 K
3 A
1 A
2 G
KIA Topic(s)
IR 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High Sump/Area Water Levell 5 500000 High CTMT Hydrogen Cone. I 5
X EA2.01 Ability to determine and/or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:
3.1 3.5 27 oint Totals:
1 IWI HYDROGEN MONITORING SYSTEM AVAILABILITY Group Point Total:
7/3 II Page 6 of 12
DRAFT FITZPATRICK RO OUTLINE ES-401 Form ES-401-1 ES-401 System # I Name OO~
203000 RHR/LPCI:
X Injection Mode 205000 Shutdown Cooling 206000 HPCI 207000 Isolation (Emergency) Condenser 209001 LPCS 209002 HPCS 211000 SLC X
212000 RPS 2150031RM 215004 Source Range Monitor 215005 APRM I LPRM BWR Examination Outline Form E Plant Systems RO)
K A A A A G KIA Topic(s)
IR 6 1 2 3 4 K4.01 Knowledge of RHRfLPCI: INJECTION 4.2 28.
MODE design feature(s) and/or interlocks which provide for the following:
AUTOMATIC SYSTEM INITIATION/INJECTION X
A3.01 Ability to monitor automatic operations of 3.2
- 29.
the SHUTDOWN COOLING SYSTEM:
3.1 VALVE OPERATION X
A4.09 Ability to manually operate and lor monitor 3.8
- 30.
in the control room:
3.7 SUPPRESSION POOL LEVEL N/A BL N/A X G.2.1.28 Knowledge of the purpose and function 4.1
- 31.
of major system components and controls.
4.1 n AUTOMATIC SYSTEM INITIATION N/ABL N/A N/A K5.04 Knowledge of STANDBY LIQUID 3.1
- 32.
CONTROL SYSTEM design feature(s) and I or 3.2 interlocks which provide for the following:
EXPLOSIVE VAVLE OPERATION X
K6.04 Knowledge of the effect that a loss or 2.8
- 33.
malfunction of the following will have on the 3.1 REACTOR PROTECTION SYSTEM including:
DC ELECTRICAL DISTRIBUTION X
K6.02 Knowledge of the effect that a loss or 3.6
- 34.
malfunction of the following will have on the 3.8 INTERMEDIATE RANGE MONITORS (IRM)
SYSTEM:
24/48 VOLT D.C. POWER X
A1.02 Ability to predict and/or monitor changes in 3.6
- 35.
parameters associated with operating the 3.7 SOURCE RANGE MONITOR (SRM) SYSTEM controls including:
REACTOR POWER INDICATION X
A1.02 Ability to predict and/or monitor changes in 3.9
- 36.
parameters associated with operating the APRM 4.0 controls including:
RPS STATUS Page 7 of 12
DRAFT FITZPATRICK RO OUTLINE ES-401 System # I Name K
1 K
2 K
3 K
4 K
5 BWR Examination Outline Plant Systems - Tier 2/Group 1 (RO)
K A A A A G 6 1 2 3 4 KIA Topic(s)
Form ES-401-1 IR==;;=
217000 RCIC X
K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC):
3.4 3.5
- 37.
ELECTRICAL POWER 218000 ADS X
K5.01 Knowledge of the operational implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM:
3.8 3.8
- 38.
223002 PC IS/Nuclear Steam Supply Shutoff X
ADS LOGIC OPERATION A2.05 Ability to predict (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT*OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: NUCLEAR BOILER INSTRUMENTATION FAILURES 3.3 3.6
- 39.
239002 SRVs X
A3.02 Ability to monitor automatic operations of the RELIEF/SAEFTY VALVES including:
SRV OPERATION ON HIGH REACTOR PRESSURE 4.3 4.3
- 40.
259002 Reactor Water Level Control X
K3.01 Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on the following:
3.8 3.B
- 41.
REACTOR WATER LEVEL 261000 SGTS X
K1.03 Knowledge of physical connection and/or cause-effect relationship between STANDBY GAS TREATMENT SYSTEM and the following:
2.9 3.1
- 42.
SUPPRESSION POOL 262001 AC Electrical Distribution X
K4.02 Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature (s) and lor interloGks which provide for the following:
2.9 3.3
- 43.
CIRCUIT BREAKER AUTOMATIC TRIPS 262002 UPS (AC/DC)
X K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C.
D.C.)
2.7 2.9
- 44.
A.C. ELECTRICAL POWER 263000 DC Electrical Distribution X
K1.02 Knowledge of the physical connections and/or cause-effect relationships between D.C.
ELECTRICAL DISTRIBUTION and the following:
3.2 3.3
- 45.
BATTERY CHARGER AND BATTERY Page 8 of 12
I DRAFT FITZPATRICK RO OUTLINE ES-401 9WR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
System # I Name K
1 K
2 K
3 K
4 K
5 K A 6 I 1 A
2 A
3 ~Jj KIA Topic(s)
IR 264000 EDGs X
K1.04 Knowledge of the physical connections and/or cause-effect relationship between EMERGENCY GENERATORS (DIESEUJET) and the following:
3.2 3.3
- 46.
EDG COOLING WATER SYSTEM 300000 Instrument Air X
A2.01 Ability to (a) predict the impacts ofthe following on the INSTRUMENT AIR SYSTEM and (9) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
2.9 2.8
- 47.
AIR DRYER AND FILTER MALFUNCTIONS 400000 Component Cooling Water X
A2.02 Ability to (a) predict the impacts of the following on CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
2.8 3.0
- 48.
HIGH/LOW SURGE TANK LEVEL 203000 RHR/LPCI:
I njection Mode X
K1.07 Knowledge of the physical connections and/or cause-effect relationships between RHRlLPCI: INJECTION MODE and the following:
3.1 3.3
- 49.
D.C. ELECTRICAL POWER 206000 HPCI X
K5.05 Knowledge of the operational implications of the following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSTEM:
3.3 3.3
- 50.
TURBINE SPEED CONTROL 212000 RPS X
K2.01 Knowledge of electrical power supplies to the following:
RPS motor-generator sets 3.2 3.3
- 51.
218000 ADS X
K4.04 Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s}
and /01' interlocks which provide for the following:
3.5 3.6
- 52.
Insures adequate air supply to ADS valves:
Plant specific 264000 EDGs X
K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY DIESEL GENERATORS:
3.8 3.9
- 53.
STARTING AIR KIA Category Point Totals:
4 11 1 1 3 3 5 1 Group Point Total:
~6~
Page 9 of 12
DRAFT FITZPATRICK RO OUTLINE ES-401 Form ES-401-1 ES-401 BWR Examination Outline Plant Systems - Tier 2/Group 2. RO)
Form ES-401-1 System # I Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
KIA Topic(s)
IR 201001 CRD Hydraulic X
K2.02 Knowledge of electrical power supplies to the following:
3.6 3.7
- 54.
SCRAM VALVE SOLENOIDS 201002 RMCS X
K3.01 Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL CONTROL SYSTEM will have on the following:
3.4 3.4
- 55.
ABILITY TO MOVE CONTROL RODS 201006 RWM X
K4.01 Knowledge of ROD WORTH MINIMIZER SYSTEM design features(s) and/or interlocks which provide for the following:
3.4 3.5 56 202002 Recirculation Flow Control X
INSERT BLOCKS/ERRORS A4.01 Ability to manually operate and/or monitor in the control room: MG sets 3.3 3.1
- 57.
204000 RWCU X
K6.05 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER CLEANUP SYSTEM:
2.6 2.6
- 58.
A3.04 Ability to monitor automatic operations of the ROD BLOCK MONITOR SYSTEM including:
3.6 3.5
- 59.
VERIFICATION OR PROPER FUNCTIONING/OPERABILITY OF ROD BLOCK MONITOR 245000 Main Turbine Gen.lAux.
X G2.1.28 Knowledge of the purpose and function of major system components and controls as it applies to Main Turbine Gen/Aux 4.1 4.1
- 60.
290003 Control Room HVAC X
A4.04 Ability to manually operate and/or monitor in the control room:
Environmental conditions 2.8 3.0
- 61.
233000 Fuel Pool Cooling/Cleanup X
K3.01 Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLING AND CLEANUP will have on the following:
3.2 3.4
- 62.
FUEL POOL TEMPERATURE Page 10 of 12
DRAFT FITZPATRICK RO OUTLINE Form ES-401-1 System # 1Name 234000 Fuel Handling Equipment K K 1 2 x
KIA Topic(s)
K5.02 Knowledge of the operational implications of the following concepts as they apply to FUEL HANDLING EQUIPMENT:
FUEL HANDLING EQUIPMENT INTERLOCKS 214000 RPIS X
A3.02 Ability to monitor automatic operations of the ROD POSITION INFORMATION SYSTEM including:
Alarm and indicatin Ii hts 201003 Control Rod and Drive Mechanism X
K1.01 Knowledge of the physical connections and/or cause-effect relationships between CONTROL ROD AND DRIVE MECHANISM and the following: Control drive hydraulic s stem II KJACalteQ10ry PointTotals:
1 1 2 1 1 p Point Total:
IR 3.1
- 63.
3.7 3.2
- 64.
3.1 3.2
- 65.
3.3 121 3
Page 11 of 12
DRAFT FITZPATRICK SRO Outline ES*401 BWR Examination Outline Form ES*401*1 II Fitzpatrick Date of Exam:
May 2010 RO KIA Category Points SRO-Only Points I
Tier Group K K K K K K A A A A G A2 G*
Total 1 2 3 4 5 6 1 2 3 4 Total
- 1.
1 N/A 3
4 7
Emergency &
Abnormal Plant 2
2 1
3 Evolutions Tier Totals 5
5 10 1
N/A 2
3 5
- 2.
2 0
2 I
3 Plant Systems Tier Totals 4
4 8
- 3. Generic Knowledge and Abilities 1
2 3
4 3
4 N/A 7
Categories E
2 NA NA NA NA 2
1 2
Note:
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KiA categories.
7.*
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KiA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.
8, On the following pages, enter the KIA numbers, a brillf description of each topic, the topics' importance ratings (IRs) 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 table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
Page lof9
DRAFT FITZPATRICK SRO Outline ES.401 2
Form ES.401.1 ES-401 BWR Examination Outline Form ES-401-1 Emer!;enc 'Mmnt."""tioo,..
E/APE # / Name / Safety Function K K K KJA Topic(s)
IR 1 2 3 2
295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC X G.2.2.22 Knowledge of limiting conditions for 4.7
- 77.
/6 operations and safety limits in regards to:
PARTIAL OR COMPLETE LOSS OF AC 295004 Partial or Total Loss of DC Pwr
/6 295005 Main Turbine Generator Trip / 3 X
AA2.05 Ability to determine and/or interpret the 3.9
- 76.
following as they apply to MAIN TURBINE GENERATOR TRIP: REACTOR POWER 295006 SCRAM /1 295016 Control Room Abandonment /
X G.2.4.11 Knowledge of general operating crew 4.3
- 78.
7 responsibilities during emergency operations in regards to CONTROL ROOM ABANDONMENT 295018 Partial or Total Loss of CCW I 8
i 295019 Partial or Total Loss of Inst. Air
/8 295021 Loss of Shutdown Cooling / 4 X
AA2.01 Ability to determine and/or interpret the 3.6
- 79.
following as they apply to LOSS OF SHUTDOWN COOLING:
REACTOR WATER HEATUP/COOLDOWN RATE 295023 Refueling Ace I 8 X G.2.2.22 Knowledge of limiting conditions for 4.7
- 80.
operations and safety limits 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 X
EA2.05 Ability to determine and/or interpret the 3.6
- 81.
following as they apply to HIGH REACTOR PRESSURE: Decay heat generation 295026 Suppression Pool High Water Temp./5 295027 High Containment Temperature N/A 15 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Water X G.2.1.27 Knowledge of system purpose and/or 4.0
- 82.
Level/5 function in regards to LOW SUPPRESSION POOL WATER LEVEL 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown 11 295038 High Off-site Release Rate 19 Page 2 of9
DRAFT FITZPATRICK SRO Outline ES-401 BWR Examination Outline Form ES-401-1 Emergenc and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
EfAPE # f Name I Safety Function K
1 2 ~Jit KIA Topic(s)
IR 600000 Plant Fire On Site I 8 700000 Generator Voltage and Electric Grid Disturbances 16 ory Totals:
3 4
Group Point Total:
20n Page 3 of9
DRAFT FITZPATRICK SRO Outline i ""'" If\\,
BWR Examination Outline Form ES-401*1 Emergenc and Abnormal Plant Evolutions* Tier 1/Group 2 (SRO)
Function K K K A A G KIA Topic(s)
IR 1
2 3
1 2
I~
nser 295008 High Reactor Water Level 12 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure I 5 x
AA2.02 Ability to determine and lor interpret the 3.9 following as they apply to HIGH DRYWELL PRESSURE 295011 HiQh Containment Temp 15 N/A 295012 HiQh Drywell Temperature 15 295013 High Suppression Pool Temp.
15 295014 Inadvertent Reactivity Addition 11 295015 Incomplete SCRAM 11 X G.2.1.7 Ability to evaluate plant performance and
..7
- 88.
make operational judgements based on operating characteristics, reactor behavior and instrument interpretations as they apply to:
INCOMPLETE SCRAM 295017 HiQh Off-site Release Rate I 9
&7 11 1=
Pool Water 295032 High Secondary Containment Area Temperature 15 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High Differential Pressure I 5 I-295036 Secondary Containment High SumplArea Water Level 15 I-EA2.03 Ability to determine and lor interpret the 500000 High CTMT Hydrogen Conc. I x
3.8 85 following as they apply to HIGH PRIMARY 5
CONTAINMENT HYDROGEN CONCENTRATIONS: COMBUSTIBLE LIMITS FOR DRYWELL KIA Category Point Totals:
2 1 Group Point Total:
7/3 II Page 4 of9
DRAFT FITZPATRICK SRO Outline ES-401 BWR Examination Outline PI,,,,m 21Gm" 1 (SRO)
Form ES-401-1 System # I Name K
K K
K K
K A KIA Topic(s)
IR 1 2 3
4 5 6
1 203000 RHR/LPCI:
Injection Mode 205000 Shutdown Cooling H
206000 HPCI 207000 Isolation (Emergency) Condenser N/A 209001 LPCS X G.2.1.45 Ability to identify and interpret diverse 4.3
- 86.
indications to validate the response of another indication for LOW PRESSURE CORE SPRAY SYSTEM LINE BREAK PROTECTION 209002 HPCS N/A 211000SLC 212000 RPS X G.2.2.40 Ability to apply Technical Specifications 4.7
- 87.
for a system: RPS 2150031RM I
215004 Source Range X
~.2.1.40 Knowledge of refueling administrative Monitor requin3ments as they apply to SRM
~
215005 APRM I LPRM 217000 RCIC 218000 ADS I
223002 PC IS/Nuclear X
A2.04 Ability to (a) predict the impacts of the 3.2
- 90.
Steam Supply Shutoff following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT ~OFF (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
PROCESS RADIATION MONITORING SYSTEM FAILURES 259002 Reactor Water Level Control 261000 SGTS' 262001 AC Electrical X
A2.06 Ability to(a) predict the impacts of the 2.9
- 89.
Distribution following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
DE-ENERGIZING A PLANT BUS Page 5 of9
DRAFT FITZPATRICK SRO Outline ES-401 BWR Examination Qutlino Form ES-401-1 Plant S stems-System # I Name K K K A A A A KIA Topic(s)
IR 1 2 6
1 2 3
4
~ffi 262002 UPS (AC/DC) 263000 DC Electrical Distribution s
300000 Instrument Air
+/-H 400000 Component Cooling Water
"'oint Totals:
3 Group Point Total:
Page 6 of9
DRAFT FITZPATRICK SRO Outline ES-401 BWR Examination Outline Plant Systems - Tier 2/Group 2 (SRO)
Form ES-401-1 System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
KIA Topic(s)
IR 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism X
A2.10 Ability to(a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
3.4
- 91.
EXCESSIVE SCRAM TIME FOR A GIVEN DRIVE MECHANISM 201004 RSCS N/A 201005 RCIS N/A 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.
219000 RHRlLPCI:
Torus/Pool Cooling Mode 223001 Primary CTMT and Aux 226001 RHRlLPCI:CTMT Spray Mode.
230000 RHRlLPCI:
Torus/Pool Spray Mode.
233000 Fuel Pool cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control N/A Page7of9
DRAFT FITZPATRICK SRO Outline ES-401 System # I Name K
1 K
2 BWR Examination Outline Plant Systems Tier 2/Group 2 (SRO)
KTml KA A AI ~I G 3
6 1
2 3
4 KIA Topic(s)
Form ES-401-1
;r.
241000 ReactoriTurbine Pressure Regulator X
A2.04 Ability to(a) predict the impacts of the following on the REACTORITURBINE PRESSURE REGULATOR and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
3.8
- 93.
FAILED OPEN/CLOSED CONTROUGOVERNOR VALVE 245000 Main Turbine Gen.
t Aux.
256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 2710000ffgas 272000 Radiation Monitoring L
286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC X G.2.2.38 Knowledge of conditions and limitations in the license.
4.5
- 92.
290002 Reactor Vessel Internals I
I I I 2
- =;::
I 121 3
II Page 8 of9
DRAFT FITZPATRICK ES-401-3
~~
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form 1J)401-3:
Facility:
Fitzpatrick Date of Exam:
Category KIA #
Topic RO SRO-Only
- 1.
Conduct of Operations 2.1.5 2.1.20 2.1.32 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
Ability to interpret and execute procedure steps.
Ability to explain and apply system limits and precautions.
IR 2.9 4.6 3.8
- 66.
- 67.
- 68.
IR N/A N/A N/A N/A N/A N/A
- 2.
Equipment Control Subtotal
~OWledge of conditions and limitations in the facility ense Ability to perform pre-startup procedures for the 2.2.1 facility/including operating those controls associated equipment that could affect reactivity.
Subtotal 3.6 4.5 3
- 69.
- 70.
2 N/A N/A N/A
. N/A N/A N/A N/A N/A
- 3.
Radiation Control 2.3.12 2.3.11 Knowledge of radiological safety principles pertaining to licensed operator duties such as containment entry requirements, fuel handling responsibilities, ac;cess to locked high-radiation areas, aligning filters, etG.
Ability to Control Radiation Releases 3.2 3.8
- 71.
- 72.
N/A N/A N/A N/A Subtotal 2
N/A N/A
- 4.
2.4.6 Knowledge of EOP mitigation strategies.
3.7
- 73.
N/A N/A Emergency Procedures/Pia n
2.4.17 2.4.32 Knowledge of EOP terms and definitions Knowledge of operator response to loss of all annunciators 3.9 3.6
- 74.
- 75.
N/A N/A N/A N/A Subtotal 3
N/A 10 N/A Page 12 of 12
DRAFT FITZPATRICK SRO Outline Facility:
Fitzpatrick Date of Exam:
May 2010 Form.-401*3 II Category KIA #
Topic SRO-Only IR Knowledge of primary and secondary plant chemistry limits
- 1.
2.1.34 3.5 94 Conduct of 2.1.4 Knowledge of individual licensed operator responsibilities related to shift 3.8 95 Operations staffing, such as medical requirements, "no*solo" operation, maintenance of active license status, 10CFR55, etc.
Subtotal 2
- 2.
2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions 4.2 96 for operations and safety limits..
Equipment Control 2.2.44 Ability to interpret control room indications to verify the status and operation 4.4 97 of a system, and understand how operator actions and directives affect plant and system conditions.
Subtotal 2
- 3.
2.3.6 Ability to approve release permits.
3.8 98 Radiation Subtotal 1
Control
- 4.
2.4.29 Knowledge of the emergency plan.
4.4 99 Emergency 2.4.41 Knowledge of the emergency action level thresholds and classifications.
4.6 100 Procedures/Pia Subtotal 2
n Tier 3 Point Total 7
Page 9 of9
ES-401 Tier I Randomly Group Selected KIA 2/2 234000 Fuel Q63/RO Handling Equipment K5.02 3/1 G.2.1.20 Q67/RO 3/1 G.2.1.32 Q68/RO 1/2 500000 High Q85/SRO Containment Hydrogen Concentration EA2.03 31 G.2.1.34 094/SRO 3/
G.2.2.25 096/SRO Record of Rejected KlAs Form ES-401-4 Reason for Rejection During NRC review of proposed changes to question, determined that the question did not match the KIA as it applied to SROs only. KIA was changed to 201002 RMCS K1.03 Control rod block interlock/refueling (3.4)
During NRC review of proposed changes to question, determined that the question did not match the KIA. KIA was changed to G.2.1.:32.
During NRC review of proposed changes to question, determined that the question did not match the KIA. KIA was changed to G.2.1.20.
During NRC review of proposed changes to question, determined that the SRO only section of questions had been over-sampled with Technical Specification questions. KIA was changed to Loss of Condenser Vacuum. 295002;AA2.04 During NRC review of proposed changes to question, determined that the SRO only section of questions had been over-sampled with Technical Specification questions. KIA was changed to Knowledge of the Fuel Handling responsibilities for SROs G.2.1.35.
During NRC review of proposed changes to question, determined that the SRO only section of questions had been over-sampled with Technical Specification questions. KIA was changed to Knowledge of the process for making changes to procedures G.2.2.6.
ES-301 DRAFT Administrative Topics Outline Form ES-301-1 Facility:
James A. Fitzpatrick Date of Examination:
May 2010 Examination Level:
RO Operating Test Number:
1 Administrative Topic Type Describe activity to be performed Code *
(see Note)
Conduct of Operations N,R
- Determine Shell Warming Time KIA: 2.1.7 IR: 4.4 A-1 Conduct of Operations Not required for RO (only 4 out of 5 items necessary per note below)
Equipment Control N,R Track Inoperable Alarms KIA: 2.2.43 IR: 3.0 A-2 Radiation Control D,P,R Determine Visitor RCA Access Requirements KIA: 2.3.4 IR: 3.2 A-3
- Emergency Plan N,R Make EAP-1.1 Initial Event Offsite Notifications KIA: 2.4.43 IR: 3.2 A-4 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.
- Type Codes &Criteria:
(C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams (~ 1; randomly selected)
ES-301 DRAFT Administrative Outline Form ES-301-1 Facility:
James A.Fitzpatrick Date of Examination:
May 2010 Examination Level:
SRO Operating Test Number:
1 Administrative Topic (see Note)
Conduct of Operations A1-1 Conduct of Operations A1-2 Equipment Control A-2 Radiation Control A-3 Emergency Plan A-4 Type Code
- N,R D,R N,R D,P,R M,R Describe activity to be performed Knowledge of refueling administrative requirements KiA: 2.1.40 IR: 3.9 Ensure Adequate Shift Staffing KiA: 2.1.4 IR: 3.8 Initiate a Manual Tagging Clearance KiA: 2.2.13 IR: 4.3 Exposure Authorization KiA: 2.3.4 IR: 3.7 Make E-Plan Classification and PAR KiA 2.4.41 IR: 4.6 NOTE: All items (5 total) are required for SROs. R.G applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (.:s 3 for ROs;.:s 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (.::: 1)
(P)revious 2 exams (.:s 1; randomly selected)
(S)imulator
ES-301 DRAFT Control Room/In-Plant Systems Outline Facility:
James A. Fitzpatrick Date of Examination:
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 8-1 S-2 RCIC / Initiate RCIC in Pressure Control with Speed Failure RHRI A LPCI injection with min flow valve failuro 8-3 S-4 RPS / Reactor Scram With a Control Rod Insertion Failure RHR / Spray the Drywell 8-5 S-6 RBVS I Manual Isolation and Verification of RB Ventilation RWCU I SLC initiation with RWCU isolation failure S-7 SRM I Perform SRM Signal to Noise Ratio Determination Test; ST-5H; S-8 FP I Perform RPV Isolation During Plant Fire In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U>>
P-1 CRD / Change In-service CRD Pump Suction Filter P*2 HPCII EOP Isolation Interlock Overrides - HPCI System Isolation Valves on Low Steam Supply Pressure P-3 ADS I Alternate Depressurization using SRVs from PaneI02ADS-71 Type Code*
N,S,L,A N,S,A,EN D,S,L,A N,S,L,A D,S,L N,S,A D,S,L D,S N,R D
D,E,R Form ES-301-2 May 2010 1
Safety Function 4
Heat Removal 2
Inventory 1
Reactivity 5
Cntmt Integrity 9
Rad Release 4
Heat Removal 7
Instrumentation 8
Plant System 1
Reactivity 4
Heat Removal 3
Pressure All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO 1SRO-II SRO-U (A)ltemate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator Rev. 0 4-6/ 4-6 I 2-3 S9/S8/S4
~1/~1/~1 1 ~1 (control room system)
~1/~1/~1 C!:2/~2/C!:1 s 31 s 31 s 2 (randomly selected)
~1/C!:1/~1
ES-301 DRAFT Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
James A. Fitzpatrick Date of Examination:
Exam Level:
SRO-I Operating Test No.:
Control Room Systems@ (8 for RO; 7 for SRO-I; :2 or ~I for SRO-U)
System / JPM Title S-1 RCIC / Initiate RCIC in the Pressure Control with speed control failure S-2 RHRI A LPCI injection with min flow valve failurE)
$-3 RPS / Reactor Scram With a Control Rod Insertion Failure S-4 RHR / Spray the Drywell S-5 RBVS / Manual Isolation and Verification of RB Ventilation S-6 RWCU / SLC initiation with RWCU isolation failure S-7 SRM / Perform SRM Signal to Noise Ratio Determination Test; ST-5H.
S-8 RO ONLY In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U))
P-1 CRD / Change In-service CRD Pump Suction Filter P-2 HPCI / EOP Isolation Interlock Overrides - HPCI System Isolation Valves on Low Steam Supply Pressure P-3 ADS / Alternate Depressurization using SRVs from Pane102ADS-71 Type Code*
N,S,L,A N,S,A,EN D,S,L,A N,S,L,A D,S,L N,S,A D,S,L N,R D
D,E,R May 2010 1
Safety Function 4
Heat Removal 2
Inventory 1
Reactivity 5
Cntmt Integrity 9
Rad Release 4
Heat Removal 7
Instrumentation 1
Reactivity 4
Heat Removal 3
Pressure All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO 1SRO-I 1SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1Shutdown (N)ewor (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator Rev.O 4-6 1 4-6 1 2-3 s9/S8/S4
~1/~1/~1 1 ~1 (control room system)
~1/~1/~1
~2/~2/~1 s 31 s 31 s 2 (randomly selected)
~1/~1/~1
ES-301 DRAFT Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
James A. Fitzpatrick Date of May 2010 Examination:
Exam Level:
SRO-U Operating Test No.:
1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
Type Code" Safety System I JPM Title Function 8-1 Not required for SRO-Upgrade S-2 RHR I A LPCI injection with min flow valve failure N,S,A,EN 2
Inventory 8-3 Not required for SRO-Upgrade 8-4 RHR I Spray the Drywell N,S,L,A 5
Cntmt Integrity S-5 Not required for SRO-Upgrade 8-6 RWCU 1SLC initiation with RWCU isolation failure N,S,A 4
Heat Removal 8-7 Not required for SRO-Upgrade S-8 Not required for SRO-Upgrade In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U))
1 P-1 CRD/Change in-service CRD Pump Suction Filter N,R Reactivity P-2 Not required for SRO-Upgrade P-3 ADS 1Alternate Depressurization using SRVs from D,E,R 3
Pane102ADS-71 Pressure All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-II SRO-U (A)lternate path 4-6 I 4-6 { 2-3 (C)ontrol room (D)irect from bank s91s8/s4 (E)mergency or abnormal in-plant
~1/~1{~1 (EN)gineered safety feature
- I - / 21 (control room system)
(L)ow-Power I Shutdown 21/~1/<:1 (N)ew or (M)odified from bank including 1(A)
<:2/<:2/<:1 (P)revious 2 exams s 3 1s 3 I s 2 (randomly selected)
(R)CA
<:1/~1/<:1 (S}imulator Rev 2 Changed 3/15/10 following Inplant walkdown to reduce dose.
- 1. Changed SRO-U outline to perform P-2 instead of P-1.
Appendix D Scenario Outline Form ES-D-1 DRAFTREV.O Facility: Fitzpatrick Scenario No.: 1 Op-Test No.: 1 Examiners:
Operators:
Initial Conditions: Reactor startup is in progress with power at 90%. SWS pumps 46P-1A and 46P-16 are in service with 46P-1 C in standby.
Turnover: Continue power ascension to 100% lAW RAP-7.3.16. Maintenance is required on 46P-1A. Place 46P-1C in service.
Event Event Event No.
Type*
Description 1
N/A N-SNO Swap SWS pumps. Place 46P-1C in service and remove 46P-1A.
2 N/A R-ATC Raise power to 100% power using Rx recirc 3
RR23:A I-ATC TS-CRS
'N Recirc Flow unit failure. TS call I-SN02 4
RR19:6 TS-CRS Upscale failure of 06lT -526; FWLC level transmitter. TS call 5
TC07:A C-ATC EHC SYstem regulator oscillation RR15:A 6
RP01AA M-ALL Coolant leakage inside primary containment.
RP01A6 ED43 :A 7
ED43 :6 M-ALL Loss of offsite AC power DG03:A 8
DG03:C C-ATC Failure of 'A' EDG output breakers to close
- 9.
RC02 I-SN02 RCIC failure to auto start 10..
AD07:A C-SN02
'A' ADS fails to open (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix 0 Scenario Outline Form ES-D-1
~~~--------------~=========
DRAFTREV.O Facility: Fitzpatrick Scenario No.: 2 Op-Test No.: 1 Examiners:
Operators:
Initial Conditions: Reactor is in Mode 1 with power at 80%. Power ascension on hold for CRD pump swap.
Turnover: Swap CRD pumps. Place 'A' CRD pump in service and remove 'B' CRD pump from service.
Event Malt. No.
Event Event No.
Type*
Description N-SNO Place 'A' CRD pump in service and remove 'B' CRD pump from service.
TS-SRO 2
HP05 Inadvertent HPCI initiation C-SNO 3
1-PC05:N TS-SRO Upscale failure of Drywell pressure transmitter 10PT-101A.
4 FW13:A R-ATC 33E-6A Feedwater Heater Tube Leak.
C-SNO C-SNO 5
ED04:A Inverter failure 7'1-INV-3A failure TS-SRO MC01 C-ATC Main condenser air In-leakage; Loss of condenser vacuum RP01A RP01B 7
M-ALL Failure to scram; RPS is still energized, ARI fails to actuate.
RP09 SL01:A or 8
C-ATC of the in service SLC pump B
SL03:A or 9
C-A I \\,;
-=>L\\,; pump 'A' or 'B' relief 11-RV-39A or 11-39B lifts B
10 RC02 C-SNO RCIC Failure to auto start (N)ormal, (R)eactivity, (I)nstrument, (C)omponEmt, (M)ajor
Appendix 0 Scenario Outline Form ES-O-1 DRAFTREV.O Facility: Fitzpatrick Scenario No.: 4 Op-Test No.: 1 Examiners:
Operators:
Initial Conditions: Reactor power is 60%. ST-3PA, 'A Core Spray Valve 1ST' is marked as complete up to step 8.2.
Turnover: Power was lowered to 60% power to perform a rod pattern adjustment. Perform section 8.2 of ST -3PA for Core Spray Loop A Quarterly Operability Test (1ST), and then perform rod pattern adjustment.
Event Malf. No.
Event Event No.
Type*
Description N-SN02 1
OVR 1 TS-SRO Perform ST -3PA Sect 8.2 only. A Core Spray Valve 1ST 2
NA R-ATC Perform Rod Pattern adjustment.
3 RD03:B C-ATC B CRD Flow control valve fails partially closed. Swap to A valve.
4 RR22:A RP01AA TS-SRO I-SN02 Reactor Leve,1 Transmitter 02-3LT-101A fails low with failure to half scram.
5 ED10 C-Crew UPS Bus Failure causes loss of L 15, L25 and UPS.
ED03:C RX01 6
MS08B:C M-Crew Fuel failure leads to High Rad. MSL. Initiate Manual Isolation. One MSL fails to isolatE!.
MS08B:G 7
MS05 M-Crew MSL break. Enter Radioactivity Release Control EOP-6 8
OVR2 C-SN02 Turbine buildinQ ventilation trips 9
NA M-Crew Enter RPV control and EmerQency Depressurization prior to GE.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor