ML101740426

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J.A. Fitzpatrick - Final Outlines (Folder 3)
ML101740426
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/09/2010
From: Caruso J G
Operations Branch I
To:
Entergy Nuclear Northeast
HANSELL S L
Shared Package
ML092470037 List:
References
50-333/10-301, ES-401, ES-401-1, TAC U01786 50-333/10-301
Download: ML101740426 (30)
v • d • e


Text

FINAL FITZPATRICK RO BWR RO Examination Outline Form ES-401-1 Facility:

Fitzpatrick Date of Exam: May 2010 Tier Group K 1 K 2 K 3 R K 4 O K K 5 IA Category PoinK A A A 6 1 2 3 ts A 4 G

  • Total A2 SRO-Only Points G* Total 1. 1 3 3 5 4 3 2 20 N/A N/A N/A Emergency

& N/A N/A Abnormal Plant 2 0 2 1 1 2 1 7 N/A N/A N/A Evolutions Tier Totals 3 I 5 6 5 5 3 27 N/A N/A N/A 1 4 1 3 3 5 2 3 2 1 1 26 N/A N/A N/A 2. 2 2 1 1 1 0 0 2 2 1 12 NI NI N/A N/A Plant Systems A A Tier Totals 2 3 4 6 2 3 4 3 2 38 N/A N/A N/A Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 N/A Categories 10 3 2 2 NI NI NI NI A A A A Note: Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., 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). 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. 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. 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. 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. Select SRO topics for Tiers 1 and 2 from the shaded sysltems and KIA categories. 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. Hefer to Section D.1.b of ES-401 for the applicable KlAs. 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. For Tier 3, select topics from Section 2 of the KIA 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 FINAL FITZPATRICK RO 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 # / Name / Safety K K K A A G K/A 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 FORGED CORE FLOW CIRCULATION:

REAGTOR POWER RESPONSE 295003 Partial or Complete Loss of AC X AK3.01 Knowledge of the reasons for the 3.3 2. /6 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 G2.1.32 Ability to explain and apply system limits 295005 Main Turbine Generator Trip / 3 X 3.8 4.and precautions to MAIN TURBINE GENERATOR TRIP 4.0 295006 SCRAM /1 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. /8 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 / 4 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 FINAL

FITZPATRICK RO BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 1 (RO) E/APE # I Name I Safety K K K A A G KIA Topic(s) IR # 1 2 3 1 2 295023 Refueling Acc I 8 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 I 3 X 4.0 12.operations and safety limits: as it applies to High Reactor Pressure 4.7 295026 Suppression Pool High Water X EKU)1 Knowledge of the operational 3.0 13. Temp. 15 implications of the following concepts as they 3.4 apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

Pump NPSH 295027 High Containment Temperature N/ABL N/A N/A /5 295028 High Drywell Temperature / 5 EA2.01 Ability to determine and/or interpret the 4.0 14. following as they apply to HIGH DRYWELL 4.1 TEMPERATURE:

DRYWELLTEMPERATURE 295030 Low Suppression Pool Water X EK2.02 Knowledge of the interrelations between 3.7 15. Level /5 LOW SUPPRESSION POOL WATER LEVEL 3.8 and the following:

RCIC 295031 Reactor Low Water Level / 2 EA2.02 Ability to determine and/or 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 Downscale or Unknown/1 apply to SCRAM CONDITION PRESENT AND 3.6 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Cold Shutdown Boron Weight 295038 High Off-site Release Rate / 9 EK3.02 Knowledge of the reasons for the 3.9 18. following responses as they apply to HIGH 4.2 SITE RELEASE RATE: System Isolations 600000 Plant Fire On Site / 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 FINAL FITZPATRICK RO ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 1 (RO) KKK ill EIAPE # I Name I Safety Function 123 KIA Topic{s) IR # 700000 Generator Voltage and Electric x AA1.03 Ability to operate and/or monitor the 3.8 20. Grid Disturbances I 6 following as they apply to GENERATOR VOLTAGE AND ELECTRICAL GRID 3.7 DISTURBANCES:

Volt lator controls . KIA Category Totals: 3 3 5 4 3 2 Group Point Total: Page 4 of 12 FINAL FITZPA"rRICK RO OUTLINE Form ES-401-1 ES-401 BWR Examination Outline Form PI mt Evolutions

-Tier 1/Group 2 L.1""'I!m

! E/APE # 1 Name 1 Safety Function G KIA Topic(s) IR #295002 Loss of Main Condenser

  • Vacuum 13
  • 295007 High Reactor Pressure I 3 U G.2.1.7 Ability to evaluate plant t-'VI lIall"'l::

and

  • 295008 High Reactor Water Level 12 3.7 21.make operational judgements as they apply to HIGH REACTOR WATER LEVEL: 3.7 Reactor water level 295009 Low Reactor Water Levell 2 AK2.03 Knowledge of the reasons for the following 3.1 22 responses as they apply to LOW REACTOR 3.2 WATER LEVEL: RECIRCULATION 295010 High Drywell Pressure 295011 High Containment Temp 15 295012 High Drywell '1::IlIIJt:I(:IlUre 15 295013 High Suppression Pool 295014 Inadvertent Reactivity I 11 295015 Incomplete SCRAM 11 AA 1.03 Ability to operate and! or monitor the 3.6 23. following as they apply to INCOMPLETE SCRAM: 3.8 RMCS 295017 High Off-site Release Rate / 9
  • 295020 Inadvertent Cont. Isolation

/ 5 *&7 295022 Loss of CRD Pumps I 1 X AK2.0:S Knowledge of the interrelations between 3.4 24. LOSS OF CRD and the following:

3.4 ACCUMULATOR

PRESSURES I

  • 295029 High Suppression Pool Water X EK3.01 Knowledge of the reasons for the following 3.5 25. Level 15 responses as they apply to HIGH SUPPRESSION 3.9 POOL WATER LEVEL: :NCY DEPRESSURIZATION 295032 High Secondary Containment Area T t:1l11Jt:lature 15 EA2.0'1 Ability to determine and/or interpret the 295033 High Secondary Containment X 3.8 26.following as they apply to HIGH Area Radiation Levels / CONTAINMENT AREA RADIATION LEVELS: 3.9 AREA RADIATION LEVELS 295034 Secondary Containment Ventilation High Radiation 19 Page 5 of 12 FINAL FITZPATRICK RO BWR Examination Outline Form ES-401-1 Emer! ency and Abnormal Plant Evolutions

-Tier 1/Group 2 (RO) E/APE # I Name I Safety Function K 1 K 2 1 A 2 G KJA Topic(s) IR # 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level/5 500000 High CTMT Hydrogen Conc. 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 HYDROGEN MONITORING SYSTEM AVAILABILITY KJA Category Point Totals: 0 2 I 2 I Group Point Total: 7/3 Page 6 of 12 FINAL FITZPATRICK RO ES-401 Form ES-401-1 ES-401 BWR Examination Outline Plant Systems -Tier 2/Group 1 (RO) System # I Name 203000 RHRlLPCI:

Injection Mode K 1 K 2 K 3 K 4 X K 5 K 6 A 1 A 2 A 3 A 4 G KIA Topic(s) K4.01 Knowledge of RHR/LPCI:

INJECTION MODE design feature(s) and/or interlocks which provide for the following:

AUTOMATIC SYSTEM INITIATIONIINJECTION 4.2 4.2 28. 205000 Shutdown Cooling X A3.01 Ability to monitor automatic operations of the SHUTDOWN COOLING SYSTEM: VALVE OPERATION 3.2 3.1 29. 206000 HPCI A4.09 Ability to manually operate and lor monitor in the control room: SUPPRESSION POOL LEVEL 3.8 3.7 30. 207000 Isolation (Emergency}

Condenser N/ABL N/A N/A 209001 LPCS X G.2.1.28 Knowledge of the purpose and function of major system components and controls.

AUTOMATIC SYSTEM INITIATION 4.1 4.1 31. 209002 HPCS N/ABL NIA N/A 211000SLC X K5.04 Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and lor interlocks which provide for the following:

3.1 3.2 32. EXPLOSIVE VAVLE OPERATION 212000 RPS X K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR PROTECTION SYSTEM including:

2.8 3.1 33. DC ELECTRICAL DISTRIBUTION 2150031RM X K6.02 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITORS (IRM) SYSTEM: 3.6 3.8 34. :24/48 VOLT D.C. POWER 215004 Source Range Monitor X ,/:\1.02 Ability to predict and/or monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM Gontrols including:

3.6 3.7 35. IREACTOR POWER INDICATION 215005 APRM I LPRM X ,M .02 Ability to predict and/or monitor changes in parameters associated with operating the APRM controls including:

3.9 4.0 36. IRPS STATUS Page 7 of 12 FINAL FITZPATRICK RO ES-401 BWR Examination Outline Plant Systems -Tier 2/Group 1 (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 K/A Topic(s) IR # 217000 RCIC X K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the IREACTOR CORE ISOLATION COOLING SYSTEM (RCIC): 3.4 3.5 37. IELECTRICAL 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 PCIS/Nuclear Steam Supply Shutoff X ADS LOGIC OPERATION A2.05 Ability to predict (a) predict the impacts of the following on the PRIMARY CONTAINMENT IISOLA TION 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 IPRESSURE 4.3 4.3 40. 259002 Reactor Water Level Control X IK3.01 Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on the following:

3.8 3.8 41. IREACTOR WATER LEVEL 261000 SGTS X IK1.03 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 interlocks 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 FINAL FITZPATRICK RO __ MH 8WR Examination Form ES-401-1 Plant systm'System # / Name K K K K A A KIA Topic{s) IR # 1 2 3 4 5 612 264000 EDGs K1.04 Knowledge of the physical connections 3.2 46. and/or cause-effect relationship between 3.3 EMERGENCY GENERATORS (DIESEUJET) and the following:

EDG COOLING WATER SYSTEM 300000 Instrument Air A2.01 Ability to (a) predict the impacts ofthe 2.9 47. following on the INSTRUMENT AIR SYSTEM and 2.8 (8) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

AIR DRYER AND FILTER MALFUNCTIONS 400000 Component Cooling X A2.02 Ability to (a) predict the impacts of the 2.8 48. Water following on CCWS and (b) based on those 3.0 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

HIGH/LOW SURGE TANK LEVEL 203000 RHRlLPCI:

X K1.07 Knowledge of the physical connections 3.1 49. Injection Mode and/or cause-effect relationships between 3.3 RHR/LPCI:

INJECTION MODE and the following:

D.C. ELECTRICAL POWER 206000 HPCI K5.05 Knowledge of the operational implications of 3.3 50. the following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSTEM: TURBINE SPEED CONTROL 212000 RPS K2.01 Knowledge of electrical power supplies to 3.2 51. the following:

3.3 RPS motor-generator sets 218000 ADS K4.04 Knowledge of AUTOMATIC 3.5 52. DEPRESSURIZATION SYSTEM design feature(s) 3.6 and lor interlocks which provide for the following:

Insures adequate air supply to ADS valves: Plant speCific 264000 EDGs K6.01 Knowledge of the effect that a loss or 3.8 53. malfunction of the following will have on the 3.9 EMERGENCY DIESEL GENERATORS:

18 STARTING AIR KIA Category Point Totals: 4 1 1 3 3 5 2 3 2 Page 9 of 12

3.7 FINAL

FITZPATRICK RO Form ES-401-1 BWR Examination Outline mm -TIer 21Group 2 (RO) System # / Name K A A G K/A Topic{s) IR # 134 201001 CRD Hydraulic K2.02 Knowledge of electrical power 3.6 54. supplies to the following:

SCRAM VALVE SOLENOIDS 201002 RMCS t(3.01 Knowledge of the effect that a 3.4 55. loss or malfunction of the REACTOR 3.4 MANUAL CONTROL SYSTEM will have on the following:

ABILITY TO MOVE CONTROL RODS 201006 RWM K4.01 Knowledge of ROD WORTH 3.4 MINIMIZER SYSTEM design features(s) 3.5 and/or interlocks which provide for the I following:

INSERT BLOCKS/ERRORS A4.01 Ability to manually operate and/or 202002 Recirculation Flow 3.3 57.monitor in the control room: MG sets Control 3.1 204000 RWCU K6.05 Knowledge of the effect that a 2.6 58. loss or malfunction of the following will 2.6 have on the REACTOR WATER CLEANUP SYSTEM: AC POWER 215002 RBM A3.04 Ability to monitor automatic 3.6 59. operations of the ROD BLOCK 3.5 MONITOR SYSTEM including:

VERIFICATION OR PROPER FUNCTIONING/OPERABILITY OF ROD BLOCK MONITOR 245000 Main Turbine X (;2.1.28 Knowledge of the purpose 4.1 60. Gen.lAux.

and function of major system 4.1 components and controls as it applies to Main Turbine Gen/Aux 290003 Control Room X A4.04 Ability to manually operate 2.8 61. HVAC and/or monitor in the control room: 3.0 Environmental conditions 233000 Fuel Pool K3.01 Knowledge of the effect that a 3.2 62.

loss or malfunction of the FUEL POOL COOLING AND CLEANUP will have on the following:

FUEL POOL TEMPERATURE Page 10 of 12 56 3.4 1 FINAL FITZPATRICK RO BWR Examination Outline Form ES-401-1 Plant Systems -Tier 2/Group 2 (RO) System # / Name 201002 RMCS K 1 X K 2 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G KIA Topic(s) K1.03 Knowledge of the physical connections and/or cause-effect relationship between REACTOR MANUAL CONTROL SYSTEM and the IR 3.4 3.6 # 63. following:

CONTROL ROD BLOCK INTERLOCKS/POWER OPERATION REFUELING 214000 RPIS X A3.02 Ability to monitor automatic operations of the ROD POSITION INFORMATION SYSTEM including:

Alarm and indicating lights 3.2 3.1 64. 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 l3fIfBTI the following:

Control drive hydraulic system 3.2 3.3 65. 121 3 Page 11 of12 FINAL FITZPATRICK SRO Outline BWR Examination Outline Form ES-401-1 Facility:

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. i'J/A 3 4 7 Emergency Abnormal 2 2 I 3 Evolutions Tier 5 5 10 N/A 2 3 5 2 0 2 I 3 Systems Tier 4 4 8 Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 N/A 7 Categories NA NA NA NA 2 2 I 2 Note: Ensure that at least two topics from every applicable KJA category are sampled within each tier of the and SRO-only outlines (i.e., except for one in Tier 3 of the SRO-only outline, the "Tier in each KIA category shall not be less than 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 thEl SRO-only exam must total 25 points. 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. 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. Absent a plant-specific priority, only those KJAs 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. Select SRO topics for Tiers 1 and 2 from the shaded systems and KJA categories.

7'-The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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. 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. For Tier 3, select topics from Section 2 of the KiA catalog, and enter the KJA 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 of9 FINAL FITZPATRICK SRO Outline ES*401 2 Form ES*401*1 ES-401 BWR Examination Outline Form E volutions

-Tier 1/Group 1 EIAPE # I Name I Safety Function A G KJA Topic(s) IR # 1 2 295001 Partial or Complete of Forced Core Flow Circulation 11 & 295003 Partial or Complete Loss of AC X G.2.2.22 Knowledge of limiting conditions for 4.7 77. 16 operations and safety limits in regards to: PARTIAL OR COMPLETE LOSS OF AC 295004 Partial or Total Loss of DC Pwr 16 295005 Main Turbine Generator Trip I 3 AA2.05 Ability to determine and/or interpret the 3.9 16. following as they apply to MAIN TURBINE GENERATOR TRIP: REACTOR POWER 295006 SCRAM 11 DI 295016 Control Room Abandonment I X G.2.4.12 Knowledge of general operating crew 4.3 18. 7 responsibilities during emergency operations in regards to CONTROL ROOM ABANDONMENT 295018 Partial or Total Loss of CCW 295019 Partial or Total Loss of Inst. Air 18 295021 Loss of Shutdown Cooling 14 AA2.01 Ability to determine andlor interpret the 3.6 19. following as they apply to LOSS OF SHUTDOWN COOLING: REACTOR WATER HEATUP/COOLDOWN RATE 295023 Refueling Acc I 8 G.2.2.22 Knowledge of limiting conditions for 4.7 80. operations and safety limits 295024 HiQh Drywell Pressure I 5 295025 High Reactor Pressure / 3 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 Temp. /5 295027 High Containment Temperature 295028 High Drywell Temperature 15 295030 Low Suppression Pool Water X G.2.1.21 Knowledge of system purpose and/or 4.0 82. Level 15 function in regards to LOW SUPPRESSION POOL WATER LEVEL 295031 Reactor low Water Level 12 295037 SCRAM Condition and Reactor Power Above Downscale or Unknown f e Rate 19 Page 2 of9 FINAL FITZPATRICK SRO Outline ES-401 BWR Examination Outline Form ES-401-1 Emergenc and Abnormal Plant Evolutions

-Tier 1/Group 1 (SRO) E/APE # I Name I Safety Function K 1 K 2 K 3 A 1 A 2 G KIA Topic(s) IR # 600000 Plant Fire On Site I 8 700000 Generator Voltage and Electric Grid Disturbances I 6 KIA Category Totals: 3 4 Group Point Total: 20/7 Page 3 of9 FINAL FITZPATRICK SRO Outline ES*401 BWR Examination Outline Form ES*40H Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2 (SRO) EIAPE # I Name I Safety Function Klll K AJj KIA #A1 3 1 I 295002 Loss of Main Condenser AA2.04 Ability to determine and/or interpret the 2.9 85. Vacuum following as they apply to LOSS OF CONDENSER VACUUM:

OFFGAS 295007 High Reactor Pressure I 295008 High Reactor Water Levell 295009 Low Reactor Water Level r= 295010 High Drywell Pressure 15 AA2.06 Ability to determine and lor interpret the 3.6 84. following as they apply to HIGH DRYWELL PRESSURE:DRYWELLTEMPERATURE 295011 High Containment Temp 15 295012 High Drywell Temperature 295013 High Suppression Pool 15 295014 Inadvertent Reactivity I 295015 Incomplete SCRAM 11 G.2.1.7 Ability to evaluate plant performance and 4.7 88. make operational judgements based on operating characteristics, reactor behavior and instrument interpretations as they apply to: INCOMPLETE SCRAM 295017 High Off-site Release Rate / 9 I 295020 Inadvertent Cont. Isolation / =L ! !I 295022 Loss of CRD Pumps 11 295029 High Suppression Pool 295032 High Secondary Area Temperature IJ 295033 High Secondary Area Radiation Levels / 295034 Secondary Ventilation High Radiation 295035 Secondary Containment High I I Differential Pressure 1 5 295036 Secondary Containment Sump/Area Water Level / 500000 High CTMT Hydrogen Cone. ory Point Totals: 1 Group Point 7/3 tcl2 Page 4 of9 FINAL FITZPATRICK SRO Outline BWR Examination Outline Form ES*401*1 Plant S stems* Tier 1 (SRO) ame K K K K A A KIA Topic(s) IR # 3 4 5 6 1 2 3 ill 203000 RHRlLPCI:

Injection Mode 205000 Shutdown Cooling 206000 HPCI 207000 Isolation N/A (Emen:;Jency)

Condenser 209001 LPCS 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 N/A 211000 SLC 212000 o Ability to apply Technical Specifications 4.7 87. stem: RPS 2150031RM 215004 Source Range X G.2.1.40 Knowledge of refueling administrative 4.2 83. Monitor requirements as they apply to SRM 215005 APRM I ! 217000 RCIC 218000 ADS 223002 PC IS/Nuclear A2.04 Ability to (a) predict the impacts of the 3.2 90. Steam Supply 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 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical A2.06 Ability to(a) predict the impacts of the 2.9 89.

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 FINAL FITZPATRICK SRO Outline ES-401 BWR Examination Outline Form ES-401-1 Plant S stems -Tier :UGroup 1 (SRO) 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 # 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water KIA Category Point Totals: 2 3 Group Point Total: 261 5 Page6of9 FINAL FITZPATRICK SRO Outline BWR Examination Outline Plant Systems Tier 2/GrQUp 2 (SRO) F II System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G KiA Toph;;(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 RHR/LPCI:CTMT Spray Mode. 230000 RHR/LPCI:

Torus/Pool Spray Mode. 233000 Fuel Pool cooling/Cleanu 234000 Fue Equipment 23900 Steam 239003 MSIV Leakage Control N/A Page 70f9 FINAL FITZPATRICK SRO Outline ES-401 BWR Examination Outline Form ES-401-1 S stems -Tier 2/G=f=OU;;!;P;.;;2=(!::S

...R ... O"===========::;====r

.......-=l1 System # I Name 241000 ReactoriTurbine Pressure Regulator 245000 Main Turbine Gen. I Aux. KKK K 1 234 KIA Topic(s) A2.04 Ability lo(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:

FAILED OPEN/CLOSED CONTROL/GOVERNOR VALVE IR 3.8 # 93. 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 2710000ffgas 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC X Gi.2.2.38 Knowledge of conditions and limitations in the license. 4.5 92. KIA Category Point Totals: 2 I I IGirOll.lp Point Total: Page 8 of9 ES*401 FINAL RO Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3 Facility:

Fitzpatrick Date of Exam: Category K/A# Topic RO SRO-Only 1. Conduct of Operations 2.1.5 2.1.32 2.1.20 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Ability to explain and apply system limits and precautions.

Ability to interpret and execute procedure steps. IR 2.9 4.6 3.8 # 66. 67. 68. IR N/A N/A N/A # N/A N/A N/A Subtotal 3 N/A N/A 2. Equipment Control 2.2.38 2.2.1 Knowledge of conditions and limitations in the facility license Ability to perform pre-startup procedures for the facility/including operating those controls associated with elant eguiement that could affect reactivity.

3.6 4.5 69. 70. N/A N/A N/A N/A Subtotal 2 N/A N/A 3. Radiation Control 2.3.12 2.3.11 Knowledge of radiological safety principlles pertaining to licensed operator duties such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. 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 Tier 3 Point Total 10 N/A Page 12 of 12 FINAL FITZPATRICK SRO Outline Facility:

Fitzpatrick Date of Exam: May 2010 Form ES-401-3 Category KfA# Topic SRO-Only 1. 2.1.35 Knowledge of the fuel handling responsibilities of SROs IR 3.9 # 94 Conduct of Operations

2.1.4 Knowledge

of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. 3.8 95 Subtotal 2 2. 2.2.6 KnowledQe of the process for makinQ chanQes to procedures.

3.6 96 Equipment Control 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect elant and slstem conditions.

4.4 97 Subtotal 2 3. 2.3.6 Ability to approve release permits. 3.8 98 Radiation Control Subtotal 1 4. 2.4.29 Knowledge ofthe emerQency plan. 4.4 99 Emergency ProcedureS/Pia n 2.4.41 Subtotal Knowledge of the emergency action thresholds and classifications.

4.6 100 2 II Tier 3 Point Total 7 Page 9 of9 ES*401 Record of Rejected K/As Form ES*401*4 Tier 1 Randomly Reason for Rejection Group Selected KIA 2/2 234000 Fuel During NRC review of proposed changes to question, Q63/RO Handling Equipment determined that the question did not match the KIA as it applied to SROs only. KIA was changed to 201002 RMCS K5.02 K1.03 Control rod block interlock/refueling (3.4) 3/1 G.2.1.20 During NRC review of proposed changes to question, Q67/RO determined that the question did not match the KIA. KIA was changed to G.2.1.32.

3/1 G.2.1.32 During NRC review of proposed changes to question, Q68/RO determined that the question did not match the KIA. KIA was changed to G.2.1.20.

1/2 500000 High During NRC review of proposed changes to question, Q85/SRO Containment Hydrogen determined that the SRO only section of questions had been over-sampled with Technical Specification questions.

KIA Concentration was changed to Loss of Condenser Vacuum. 295002;AA2.04 EA2.03 31 G.2.1.34 During NRC review of proposed changes to question, Q94/SRO 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.

31 G.2.2.25 During NRC review of proposed changes to question, Q96/SRO 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.

Topics Outline Form ES*301*1 Facility:

James A.

Date of Examination:

May 2010 Examination Level: Operating Test Number: 1 Administrative Topic Type Describe activity to be Code (see Note) Conduct of N,R Core Thermal Power Calculated Manually A-1-1 KIA: 2.1.18 1R:3.6 Conduct of N,R Work Hour Restrictions KIA: 2.1.5 IR: 2.9 A-1-2 Equipment N,R Initiate a manual tagout KIA: 2.2.13 IR: 4.1 A-2 Radiation D,R Liquid Radwaste Potentiometer Settings KIA: 2.3.11 IR: 3.8 A-3 Emergency Plan Not required for RO (only 4 out of 5 items necessary per note below) 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 for ROs; 4 for SROs and RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams 1; randomly selected)

Rev. 1 3/01110 Administrative Topics Outline Form ES*301*1 Facility:

James A.

Date of Examination:

May 2010 Examination Level: Operating Test Number: 1 Administrative Topic Type Describe activity to be performed Code * (see Note) Conduct of Operations Core Power Calculated Manually KIA: 2.1.18 IR: 3.8 A1-1 Cond uct of Operations Determine Required Event Followup CONTAINS SElVSlTIVE INFORMATION-NOT FOR A1-2 PUBLIC DISCLOSURE KIA: 2.1.20 IR: 4.6 Equipment Control N,R Use station drawings to predict impact of component failure and evaluate technical specification implications A-2 KIA: 2.2.15 IR: 4.3 Radiation Control N,R Determine Radiation Controls.

KIA: 2.3.4 IR: 3.7 A-3 A Dl\.UNISTER A-3 AND A-4 SRO JPMs AS A PAIR I Emergency Plan Determine Protective Action Recommendations and Complete Event Notification Form KIA IR: 4.4 A DlHlNISTER A-3 AND A-4 SRO JPMs AS A PAIR I 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 for ROs; 4 for SROs and RO retakes) (N)ew or (M)odified from bank (.::: 1) (P)revious 2 exams 1; randomly selected) (S)imulator

______________

________

Facility:

James A. Fitzpatrick Date of Examination:

May 2010 ! Exam Level: RO Operating Test No.: 1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) System I JPM Title S-1 RCIC I Initiate RCIC in Pressure Control with Speed Failure S-2 HPCII Full Flow Test S-3 RPS I Reactor Scram With a Control Rod Insertion Failure S-4 RHR I Spray the Drywell S-5 RBVS I Manual Isolation and Verification of RB Ventilation S-6 EDG I Perform Diesel Operability Test with Failure of ESW S-7 SRM I Perform SRM Signal to Noise Ratio Determination Test; S-8 FP I Perform RPV Isolation During Plant In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for P-1 CRD I Change In-service CRD Pump Suction P-2 HPCII EOP Isolation Interlock Overrides HPCI Isolation Valves on Low Steam Supply P-3 ADS I Alternate Depressurization using SRVs from 02ADS-71 Type Code* Safety Function N,S,L,A 4 Heat Removal N,S,A,EN 2 Inventory D,S,L,A 1 Reactivity N,S,L,A 5 Cntmt Integrity D,S,L 9 Rad Release N,S,A 6 Electrical D,S,L 7 Instrumentation u,S 8 Plant System N,R 1 Reactivity D 4 Heat Removal D,E,R 3 Pressure All RO and SRO-l 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 Criteria for RO I SRO-II SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1 Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 I 4-6 I 2-3 s9/S8/S4 :!:1/:!:1/:!:1 -I -I :!:1 (control room system) :!:1 I:!: 1 I:!: 1 :!: 2/:!:2 I:!: 1 s 31 s 3 IS 2 (randomly selected)
!:1/:!:1 Il!: 1 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

James A. Fitzpatrick Date of Examination:

May 2010 Exam Level: SRO-I Operating Test No.: 1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for System I JPM S-1 RCIC I Initiate RCIC in the Pressure Control with speed control failure S-2 HPCII Full Flow Test S-3 RPS I Reactor Scram With a Control Rod Insertion Failure S-4 RHR I Spray the Drywell S-5 RBVS I Manual Isolation and Verification of RB Ventilation

_. EDG I Perform Diesel Operability Test with Failure of ESW S-7 SRM I Perform SRM Signal to Noise Ratio Determination Test; ST-SH. S-8 RO ONLY In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U>> P-1 CRD I 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 Panel 02ADS-71 Type Code* Safety Function N,S,L,A 4 Heat Removal N,S,A,EN 2 Inventory D,S,L,A 1 Reactivity N,S,L,A 5 Cntmt Integrity D,S,L 9 Rad Release N,S,A 6 Electrical D,S,L 7 Instrumentation N,R 1 Reactivity D 4 Heat Removal D,E,R 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 Criteria for RO 1 SRO-I I SRO-U (A)lternate path (C)ontrol room (O)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1 Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 1 4-6 1 2-3 :!:9/:!:8/s4 / (control room system) <:1/<:1/<:1

<:2/;;:2/;;:1

!: 3/ s 3/ s 2 (randomly selected)
1/;;
1/;;
1

--Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:

James A. Fitzpatrick Date of Examination:

May 2010 Exam 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 Function System I JPM Title Not required for SRO-Upgrade S-2 HPCII Full Flow Test N,S,A,EN 2 Inventory S-3 RPS I Reactor Scram With a Control Rod Insertion Failure D,S,L,A 1 Reactivity S-4 RHR I Spray the Drywell N,S,L,A 5 Cntmt Integrity Not required for SRO-Upgrade Not required for SRO-Upgrade Not required for SRO-Upgrade Not required for SRO-Upgrade In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U>> P-1 CRD I Change In-service CRD Pump Suction Filter N,R 1 Reactivity Not required for SRO-Upgrade r .........,-.Iternate Depressurization using SRVs from Panel D,E,R 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 Criteria for RO 1 SRO-II SRO-U (A)lternate path 4-6 1 4-6 1(C)ontrol (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature 1 (control room (l}ow-Power 1 Shutdown (Nlew or (M)odified from bank including 1 (Al (P)revious 2 exams 5 3 / 5 3 I 5 2 (randomly (R)CA Appendix D Scenario Outline Form ES-D-1 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-1B 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-1 A. Place 46P-1 C in service . ....E ..... Event .. I Type'"

A N-SNO Swap SWS pumps. Place 46P-1C in service and remove 46P-1A. I A R-SNO Raise power to 100% power using Rx 3. 'A' Recire Flow unit failure. TS call4. RR19:B TS-CRS Upscale failure of 06LT-52B; FWLC level transmitter.

TS call R-ATC 5. FW01:B Trip of 'B' RFPT; Rx Recirc runbacks to 44% speed. C-SN02 RR15:A Coolant leakage inside primary containment.

Defeat Auto Scram 6. RP01AA M-ALL Loss of offsite AC power. Failure of 'A' and 'C' EDG output 7. M-ALL breakers to close. 8. AD07:A C-SN02 'A' ADS fails to open

  • eactivity, ( I)nstrument, (C)orn ponent, (M}ajor NRC Scenario #1-2010 Fitzpatrick Operating Test Page 1 of 29 Appendix Scenario Outline Form ES-D-1 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 Malf. No. Event Event No. Type" Description 1 N/A N-SN02 Place 'A' CRD pump in service and remove 'B' CRD pump from service. TS-SRO 2 HP05 Inadvertent HPCI initiation C-SN02 3 FW13:A R-ATC 33E-6A Feedwater Heater Tube Leak. C-SN02 C-SN02 4 ED04:A Inverter failure 71-INV-3A failure TS-SRO MC01 C-ATC Main condenser air In-leakage; Loss of condenser vacuum RP01A RP018M-ALL Failure to scram; RPS is still energized, ARI fails to actuate. RP09 SL01:A or 8 Trip of the in service SLC pump with SLC pump 'A' or 'B'C-ATC relief 11-RV-39A or 11-398 lifts SL03:A or B * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario #2 -2010 Fitzpatrick Operating Pqge 1 of 26 Appendix D Scenario Outline Form ES*D*1 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 RD11 :18: 15 R-ATC C-ATC Perform Rod Pattern adjustment and uncoupled control rod 18 : 15 3 RD03:B C-SN02 B CRD Flow control valve fails partially closed. Swap to A valve. 4 RR22:A RP01AA TS-SRO I-SN02 Reactor Level Transmitter 02-3L T-1 01A falls low with failure to half scram. 5 ED10 C-Crew UPS Bus Failure causes loss of L 15, L25 and UPS. ED03:C 6 RX01 M-Crew Fuel failure leads to High Rad. MSL. 7 MS05 M-Crew MSL break. Enter Radioactivity Release Control EOP-6 and Emergency Depressurization.

MS08B:C 8 C-SN02 Initiate Manual MSL isolation.

One MSL fails to isolate MS08B:G * (N)ormal (R)eactivity, (l}nstrument, (C)omponent, (M)ajor NRC Scenario #4 -2010 Fitzpatrick Operating Test Page 1 of 26

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