ML15110A390

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Final Outlines (Folder 3)
ML15110A390
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 02/25/2015
From: Isham P
Exelon Generation Co
To: Todd Fish
Operations Branch I
Shared Package
ML14238A301 List:
References
TAC U01905
Download: ML15110A390 (22)
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Text

ES-401 Written Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 1 Date of Exam: March 2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • 1 3 3 3 4 3 4 20 4 3 7 1.

Emergency

& 2 2 1 1 1 1 1 7 1 2 3 Plant Evolutions Tier 5 4 4 5 4 5 27 5 5 10 Totals 1 2 2 2 3 2 3 2 2 2 3 3 26 3 2 5 2.

Plant 2 1 1 1 1 1 2 1 1 1 1 1 12 0 1 2 3 Systems Tier 3 3 3 4 3 5 3 3 3 4 4 38 4 4 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 2 2 3 3 2 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 (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).
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 that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding 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 KAs 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) KIAs 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 KIA's

8. On the following pages, enter the KIA 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 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 KIAs that are linked to 10CFR55.43

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AA2.03 - Ability to determine and/or interpret the following as they apply to 295023 Refueling Accidents I 8 x REFUELING ACCIDENTS: Airborne 3.8 76 contamination levels AA2.04 - Ability to determine and/or 295004 Partial or Complete interpret the following as they apply to Loss of DC Power I 6 x PARTIAL OR COMPLETE LOSS OF 3.3 77 D.C. POWER: Svstem lineups AA2.06 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to Trip/ 3 x MAIN TURBINE GENERATOR TRIP:

2.7 78 Feedwater temperature 2.2.40 - Equipment Control: Ability to 295003 Partial or Complete Loss of AC Power I 6 x apply technical specifications for a 4.7 79 system.

2.4.31 - Emergency Procedures I Plan:

295006 SCRAM / 1 x Knowledge of annunciator alarms, 4.1 80 indications, or response procedures.

2.1.31 - Conduct of Operations: Ability to locate control room switches, 295026 Suppression Pool High Water Temperature I 5 x controls, and indications, and to 4.3 81 determine that they correctly reflect the desired plant lineup.

EA2.01 - Ability to determine and/or 295025 High Reactor Pressure I interpret the following as they apply to 3

x HIGH REACTOR PRESSURE: Reactor 4.3 82 pressure AK1 .03 - Knowledge of the operational implications of the following concepts as 295005 Main Turbine Generator Trip/ 3 x they apply to MAIN TURBINE 3.5 39 GENERATOR TRIP: Pressure effects on reactor level AK1 .03 - Knowledge of the operational implications of the following concepts as 295004 Partial or Complete Loss of DC Power I 6 x they apply to PARTIAL OR COMPLETE 2.9 40 LOSS OF D.C. POWER: Electrical bus divisional separation EK1 .01 - Knowledge of the operational implications of the following concepts as 295024 High Drywell Pressure I 5

x they apply to HIGH DRYWELL 4.1 41 PRESSURE: Drywell integrity: Plant-Specific EK2.09 - Knowledge of the interrelations 295038 High Off-site Release between HIGH OFF-SITE RELEASE Rate/ 9 x RATE and the following: Post accident 2.9 42 sample system (PASS): Plant-Specific AK2.02 - Knowledge of the interrelations between PARTIAL OR COMPLETE 295018 Partial or Complete Loss of CCW I 8 x LOSS OF COMPONENT COOLING 3.4 43 WATER and the following: Plant operations EK2.05 - Knowledge of the interrelations between SCRAM CONDITION 295037 SCRAM Conditions PRESENT AND REACTOR POWER Present and Reactor Power ABOVE APRM DOWNSCALE OR Above APRM Downscale or x UNKNOWN and the following: CRD 4.0 44 Unknown/ 1 hydraulic system

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AK3.06 - Knowledge of the reasons for the following responses as they apply to 295006 SCRAM I 1 x SCRAM: Recirculation pump speed 3.2 45 reduction: Plant-Specific EK3.01 - Knowledge of the reasons for the following responses as they apply to 295031 Reactor Low Water Level I 2 x REACTOR LOW WATER LEVEL: 3.9 46 Automatic depressurization system actuation EK3.03 - Knowledge of the reasons for 295028 High Drywell the following responses as they apply to Temperature I 5 x HIGH DRYWELL TEMPERATURE:

3.6 47 Drywell spray operation: Mark-1&11 AA 1.07 - Ability to operate and/or 295001 Partial or Complete monitor the following as they apply to Loss of Forced Core Flow x PARTIAL OR COMPLETE LOSS OF 3.1 48 Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION:

Nuclear boiler instrumentation svstem AA 1.03 - Ability to operate and/or monitor the following as they apply to 295019 Partial or Complete Loss of Instrument Air I 8 x PARTIAL OR COMPLETE LOSS OF 3.0 49 INSTRUMENT AIR: Instrument air compressor power supplies EA 1.03 - Ability to operate and/or 295025 High Reactor Pressure I monitor the following as they apply to 3

x HIGH REACTOR PRESSURE:

4.4 50 Safety/relief valves: Plant-Specific AA2.06 - Ability to determine and/or 295021 Loss of Shutdown interpret the following as they apply to Cooling I 4 x LOSS OF SHUTDOWN COOLING:

3.2 51 Reactor pressure AA2.04 - Ability to determine and/or 295003 Partial or Complete interpret the following as they apply to Loss of AC Power I 6 x PARTIAL OR COMPLETE LOSS OF 3.5 52 A.C. POWER: System lineups AA2.16 - Ability to determine and interpret the following as they apply to 600000 Plant Fire On-site I 8 x PLANT FIRE ON SITE: Vital equipment 3.0 53 and control systems to be maintained and operated during a fire 2.2.37 - Equipment Control: Ability to 295026 Suppression Pool High Water Temperature I 5 x determine operability and I or availability 3.6 54 of safety related eauipment.

2.2.42 - Equipment Control: Ability to 700000 Generator Voltage and recognize system parameters that are Electric Grid Disturbances x entry-level conditions for Technical 3.9 55 Specifications.

2.1.20 - Conduct of Operations: Ability 295016 Control Room Abandonment I 7 x to interpret and execute procedure 4.6 56 steps.

EA 1.01 - Ability to operate and/or monitor the following as they apply to 295030 Low Suppression Pool Water Level I 5 x LOW SUPPRESSION POOL WATER 3.6 57 LEVEL: ECCS systems (NPSH considerations): Plant-Specific 2.4.6 - Emergency Procedures I Plan:

295023 Refueling Accidents I 8 x Knowledae of EOP mitiaation strateaies.

3.7 58 KIA Category Totals: 3 3 3 4 3/4 4/3 Group Point Total:

I 2017

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EA2.02 - Ability to determine and/or 295034 Secondary interpret the following as they apply to Containment Ventilation High x SECONDARY CONTAINMENT 4.2 83 Radiation 19 VENTILATION HIGH RADIATION:

Cause of high radiation levels 295032 High Secondary 2.4.18 - Emergency Procedures I Plan:

Containment Area Temperature x Knowledge of the specific bases for 4.0 84 15 EOPs.

2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system 295017 High Off-site Release operation I status that must be reported Rate 19 x to internal organizations or external 4.1 85 agencies, such as the state, the NRC, or the transmission system operator.

AK1 .01 - Knowledge of the operational implications of the following concepts as 295015 Incomplete SCRAM/ 1 x they apply to INCOMPLETE SCRAM:

3.6 59 Shutdown marain AK2.02 - Knowledge of the interrelations 295010 High Drywell Pressure I between HIGH DRYWELL PRESSURE 5

x and the following: Drywell/suppression 3.3 60 chamber differential pressure: Mark-1&11 AK3.04 - Knowledge of the reasons for 295008 High Reactor Water the following responses as they apply to Level/ 2 x HIGH REACTOR WATER LEVEL:

3.3 61 Reactor feed pump trip: Plant-Specific EA1 .01 -Ability to operate and/or 295029 High Suppression Pool monitor the following as they apply to Water Level I 5 x HIGH SUPPRESSION POOL WATER 3.4 62 LEVEL: HPCI: Plant-Specific EA2.01 - Ability to determine and/or interpret the following as they apply to 295036 Secondary SECONDARY CONTAINMENT HIGH Containment High Sump/Area x SUMP/AREA WATER LEVEL:

3.0 63 Water Level I 5 Operability of components within the affected area 295032 High Secondary 2.4.1 - Emergency Procedures I Plan:

Containment Area Temperature x Knowledge of EOP entry conditions and 4.6 64 15 immediate action steps.

AK1 .02 - Knowledge of the operational implications of the following concepts 295022 Loss of CRD Pumps I 1 x as they apply to LOSS OF CRD 3.6 65 PUMPS: Reactivity control KIA Category Totals: 2 1 1 1 1/1 1/2 Group Point Total: 713 I

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A2.06 - Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use 206000 HPCI x procedures to correct, control, or 3.5 86 mitigate the consequences of those abnormal conditions or operations: Inadequate system flow: BWR-2,3,4 A2.01 - Ability to (a) predict the impacts of the following on the ISOLATION (EMERGENCY)

CONDENSER; and (b) based on 207000 Isolation those predictions, use (Emergency) Condenser x procedures to correct, control, or 4.5 87 mitigate the consequences of those abnormal conditions or operations: Tube bundle leak:

BWR-2,3 2.4.8 - Emergency Procedures I Plan: Knowledge of how 205000 Shutdown Cooling x abnormal operating procedures 4.5 88 are used in conjunction with EOPs.

2.4.47 - Emergency Procedures I Plan: Ability to diagnose and recognize trends in an accurate 211000 SLC x and timely manner utilizing the 4.2 89 appropriate control room reference material.

A2.07 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those 215005 APRM I LPRM x predictions, use procedures to 3.4 90 correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation flow channels flow mismatch K1 .01 - Knowledge of the physical connections and/or cause-effect relationships 211000 SLC x between STANDBY LIQUID 3.0 1 CONTROL SYSTEM and the following: Core spray line break detection: Plant-Specific K1 .04 - Knowledge of the physical connections and/or cause-effect relationships 264000 EDGs x between EMERGENCY 3.2 2 GENERATORS (DIESEUJET) and the following: Emergency generator cooling water system

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System# I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 K2.01 - Knowledge of electrical 205000 Shutdown Cooling x power supplies to the following: 3.1 3 Pump motors K2.02 - Knowledge of electrical 212000 RPS x power supplies to the following: 2.7 4 Analoa trip system logic cabinets K3. 02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC 218000 ADS x DEPRESSURIZATION SYSTEM 4.5 5 will have on following: Ability to rapidlv deoressurize the reactor K3.02 - Knowledge of the effect that a loss or malfunction of the 215004 Source Range SOURCE RANGE MONITOR Monitor x (SRM) SYSTEM will have on 3.4 6 following: Reactor manual control: Plant-Soecific K4.01 - Knowledge of CCWS design feature(s) and or 400000 Component Cooling Water x interlocks which provide for the 3.4 7 following: Automatic start of standby pump K4.02 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) 261000 SGTS x and/or interlocks which provide 2.6 8 for the following: Charcoal bed decay heat removal K5.05 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE 215005 APRM I LPRM x MONITOR/LOCAL POWER 3.6 9 RANGE MONITOR SYSTEM:

Core flow effects on APRM trip setpoints K5.03 - Knowledge of the operational implications of the following concepts as they apply 215003 IRM x to INTERMEDIATE RANGE 3.0 10 MONITOR (IRM) SYSTEM:

Chanaina detector position K6.02 - Knowledge of the effect that a loss or malfunction of the 262001 AC Electrical Distribution x following will have on the AC. 3.6 11 ELECTRICAL DISTRIBUTION:

Off-site oower K6.04 - Knowledge of the effect that a loss or malfunction of the 259002 Reactor Water Level following will have on the Control x REACTOR WATER LEVEL 3.1 12 CONTROL SYSTEM: Reactor feedwater flow inout

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System #I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 262002 UPS (AC/DC) x UNINTERRUPTABLE POWER 2.5 13 SUPPLY (A.C./D.C.) controls including: Motor generator outputs A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the 209001 LPCS x LOW PRESSURE CORE 3.7 14 SPRAY SYSTEM controls includino: Reactor pressure A2.03 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, 239002 SRVs x use procedures to correct, 4.1 15 control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM; and (b) based on those predictions, use procedures to 300000 Instrument Air x correct, control, or mitigate the 2.9 16 consequences of those abnormal conditions or operations: Air dryer and filter malfunctions A3.03 - Ability to monitor automatic operations of the 206000 HPCI x HIGH PRESSURE COOLANT 3.9 17 INJECTION SYSTEM including:

Svstem lineup: BWR-2,3,4 A3.02 - Ability to monitor automatic operations of the 207000 Isolation (Emergency) Condenser x ISOLATION (EMERGENCY) 3.8 18 CONDENSER including:

Reactor pressure: BWR-2,3 A4.04 - Ability to manually 263000 DC Electrical operate and/or monitor in the Distribution x control room: Ground detection 3.0 19 circuit: Plant-Specific A4.02 - Ability to manually 223002 PCIS/Nuclear Steam operate and/or monitor in the Supply Shutoff x control room: Manually initiate 3.9 20 the svstem 2.1.23 - Conduct of Operations:

Ability to perform specific system 206000 HPCI x and integrated plant procedures 4.3 21 during all modes of plant operation.

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 2.1.7 - Conduct of Operations:

Ability to evaluate plant performance and make 259002 Reactor Water Level Control x operational judgments based on 4.4 22 operating characteristics, reactor behavior, and instrument interoretation.

2.4.21 - Emergency Procedures I Plan: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity 264000 EDGs x control, core cooling and heat 4.0 23 removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

K4.01 - Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM 215003 IRM x design feature(s) and/or 3.7 24 interlocks which provide for the followina: Rod withdrawal blocks K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 223002 PCIS/Nuclear Steam PRIMARY CONTAINMENT Supply Shutoff x ISOLATION 3.3 25 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Nuclear boiler instrumentation A4.08 - Ability to manually operate and/or monitor in the 218000 ADS x control room: Suppression pool 3.7 26 level KIA Category Totals: 2 2 2 3 2 3 2 2/3 2 3 3/2 Group Point Total:

I 26/5

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A2.01 - Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use 239001 Main and Reheat Steam x procedures to correct, control, 3.9 91 or mitigate the consequences of those abnormal conditions or operations: Malfunction of reactor turbine pressure regulating system 2.4.9 - Emergency Procedures I Plan: Knowledge of low power I 234000 Fuel Handling shutdown implications in Equipment x accident (e.g., loss of coolant 4.2 92 accident or loss of residual heat removal) mitigation strategies.

2.4.11 - Emergency Procedures 271000 Off-gas x I Plan: Knowledge of abnormal 4.2 93 condition procedures.

K1 .04 - Knowledge of the physical connections and/or cause-effect relationships 202002 Recirculation Flow between RECIRCULATION Control x FLOW CONTROL SYSTEM and 3.1 27 the following: Reactor/turbine pressure regulating system:

Plant-Specific K2.01 - Knowledge of electrical 239001 Main and Reheat power supplies to the following:

Steam x Main steam isolation valve 3.2 28 solenoids K3 .01 - Knowledge of the effect that a loss or malfunction of the 233000 Fuel Pool Cooling/Cleanup x FUEL POOL COOLING AND 3.2 29 CLEAN-UP will have on followino: Fuel pool temperature K4.05 - Knowledge of CONTROL ROD AND DRIVE 201003 Control Rod and MECHANISM design feature(s)

Drive Mechanism x and/or interlocks which provide 3.2 30 for the following: Rod position indication K5.06 - Knowledge of the operational implications of the following concepts as they apply 201006 RWM x to ROD WORTH MINIMIZER 2.8 31 SYSTEM (RWM) (PLANT SPECIFIC): Rod groups and steps: P-Spec(Not-BWR6l K6.03 - Knowledge of the effect that a loss or malfunction of the 272000 Radiation Monitoring x following will have on the 2.8 32 RADIATION MONITORING SYSTEM: A.C. power

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A System #I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A1 .07 -Ability to predict and/or monitor changes in parameters associated with operating the 219000 RHR/LPCI: RHR/LPCI:

Torus/Pool Cooling Mode x TORUS/SUPPRESSION POOL 3.2 33 COOLING MODE controls including: Emergency generator loading A2.01 - Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS; 245000 Main Turbine and (b) based on those Generator and Auxiliary x predictions, use procedures to 3.7 34 Systems correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine trip A3.06 -Ability to monitor automatic operations of the 286000 Fire Protection x FIRE PROTECTION SYSTEM 3.0 35 including: Fire dampers A4.12 - Ability to manually 226001 RHR/LPCI: operate and/or monitor in the Containment Spray Mode x control room:

3.8 36 ContainmenUdrywell pressure 2.4.46 - Ability to verify that the 259001 Reactor Feedwater x alarms are consistent with the 4.2 37 plant conditions.

K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the 201001 CRD Hydraulic x CONTROL ROD DRIVE 3.0 38 HYDRAULIC System: Plant air systems KIA Category Totals: 1 1 1 1 1 2 1 1/1 1 1 1/2 Group Point Total:

I 12/3

ES-401 Generic Knowledges and Abilities Outline (Tier 3) Form ES-401-3 Facility: Nine Mile Point Unit 1 Date: March 2015 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Knowledge of the fuel-handling 2.1.35 3.9 94 responsibilities of SROs.

Knowledge of conservative decision making 2.1.39 4.3 100 practices.

1. Knowledge of the purpose and function of 2.1.28 4.1 66 Conduct major system components and controls.

of Operations Ability to locate control room switches, controls, and indications, and to determine 2.1.31 4.6 67 that they correctly reflect the desired plant lineup.

Subtotal 2 2 Ability to perform pre-startup procedures for the facility, including operating those controls 2.2.1 4.4 95 associated with plant equipment that could affect reactivity.

Knowledge of the process for controlling 2.2.14 4.3 98 equipment configuration or status.

2.

Equipment Control Ability to determine Technical Specification 2.2.35 3.6 68 Mode of Operation.

2.2.12 Knowledge of surveillance procedures. 3.7 69 Subtotal 2 2 2.3.11 Ability to control radiation releases. 4.3 96 2.3.11 Ability to control radiation releases. 3.8 70 Knowledge of Radiological Safety Procedures 3.

pertaining to licensed operator duties, such as Radiation response to radiation monitor alarms, Control 2.3.13 3.4 71 containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 75 conditions.

Subtotal 3 1 Knowledge of the emergency action level 2.4.41 4.6 97 thresholds and classifications.

Ability to take actions called for in the facility 2.4.38 emergency plan, including supporting or 4.4 99 acting as emergency coordinator if required.

4.

Emergency Ability to prioritize and interpret the 2.4.45 4.1 72 Procedures I significance of each annunciator or alarm.

Plan Knowledge of local auxiliary operator tasks 2.4.35 during emergency and the resultant 3.8 73 operational effects.

Knowledge of crew roles and responsibilities 2.4.13 4.0 74 during EOP usage.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected KlAs Form ES-401-4 Randomly Selected KIA Reason for Rejection Question 41 The facility has a Mark-I containment, not a Mar-Ill containment.

295024 High Drywell Pressure Randomly re-selected KIA 295024 High Drywell EK1 .02 - Knowledge of the Pressure EK1 .01 - Knowledge of the operational implications of the 1I 1 operational implications of the following following concepts as they concepts as they apply to HIGH DRYWELL_ .

apply to HIGH DRYWELL PRESSURE: Drywell integrity: Plant-Spec1f1c.

PRESSURE: Containment building integrity: Mark-Ill Question 37 The randomly selected generic KIA overlaps with those selected for Questions 64 and 74 259001 Reactor Feedwater and has the least applicability with this 2.4.1 - Emergency Procedures I question.

212 Plan: Knowledge of EOP entry Randomly re-selected KIA 259001 Reactor conditions and immediate action Feedwater 2.4.46 - Ability to verify that the steps.

alarms are consistent with the plant conditions.

Question 29 A discriminating question could not be developed without testing generic fundamentals 233000 Fuel Pool knowledge.

Cooling/Cleanup Randomly re-selected KIA 233000 Fuel Pool K3.05 - Knowledge of the effect Cooling/Cleanup K3.01 - Knowledge of the 212 that a loss or malfunction of the effect that a loss or malfunction of the FUEL FUEL POOL COOLING AND POOL COOLING AND CLEAN-UP will have on CLEAN-UP will have on following: Fuel pool temperature.

following: Fuel pool water fission product concentration

Question 32 Due to limited interrelation between Radiation Monitoring and DC power at the facility, an 272000 Radiation Monitoring acceptable question could not be developed K6.02 - Knowledge of the effect without testing minutia.

that a loss or malfunction of the Randomly re-selected KIA 272000 Radiation 2/2 following will have on the Monitoring K6.03 - Knowledge of the effect that RADIATION MONITORING a loss or malfunction of the following will have SYSTEM: D.C. power on the RADIATION MONITORING SYSTEM:

A.C. power.

Question 45 A question could not be developed without testing Generic Fundamentals knowledge or 295006 SCRAM overlapping aspects of Questions 27 and 39.

AK3.03 - Knowledge of the Randomly re-selected KIA 295006 SCRAM 1I 1 reasons for the following AK3.06 - Knowledge of the reasons for the responses as they apply to following responses as they apply to SCRAM:

SCRAM: Reactor pressure Recirculation pump speed reduction: Plant-response Specific.

Question 69 An acceptable RO level question could not be developed for the randomly selected KIA.

2.2.15 - Ability to determine the expected plant configuration Randomly re-selected KIA 2.2.12 - Knowledge using design and configuration of surveillance procedures.

3 control documentation, such as drawings, line-ups, tag-outs, etc.

Question 74 The randomly selected KIA overlaps with the KIA for Question 64.

2.4.1 - Knowledge of EOP entry conditions and immediate action Randomly re-selected KIA 2.3.13 - Knowledge 3

steps. of crew roles and responsibilities during EOP usage.

Question 84 An acceptable question could not be developed for the randomly selected KIA due to limited 295032 High Secondary Secondary Containment area temperature Containment Area Temperature instrumentation installed at the facility.

2.4.3 - Ability to identify post-1I 2 Randomly re-selected KIA 295032 High accident instrumentation.

Secondary Containment Area Temperature 2.4.18 - Knowledge of the specific bases for EOPs.

Question 89 There are no RO-specific tasks performed outside of the control room during an 211000 SLC emergency related to SLC at the facility.

2.4.34 - Knowledge of RO tasks Randomly re-selected KIA 211000 SLC 2.4.47 -

2/ 1 performed outside the main Ability to diagnose and recognize trends in an control room during an accurate and timely manner utilizing the emergency and the resultant appropriate control room reference material.

operational effects.

Question 67 An acceptable RO level question could not be developed for the randomly selected KIA.

2.1.6 - Ability to manage the 3 control room crew during plant Randomly re-selected KIA 2.1.31 -Ability to transients. locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point Unit 1 Date of Examination: March 2015 Examination Level: SRO Operating Test Number: LC1 13-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Review Reactor Water Level Instrument Checks and P,D,R Determine Technical Specification Impact Conduct of Operations 2013 NRC N1-ST-DO, KIA 2.1.7 (4.7)

Determine Personnel Overtime Availability Conduct of Operations M,R CNG-SE-1.01.1002, KIA 2.1.5 (3.9)

Perform Daily Thermal Limit Surveillance Equipment Control D,R N1-RESP-1A, KIA2.2.12 (4.1)

Determine Radiation Controls - Emergency Exposure for Local MSIV Closure Radiation Control D, R GAP-RPP-07, CNG-EP-1.01-1014, KIA 2.3.4 (3.7)

Classify an Emergency Event and Perform Initial Notifications Emergency Procedures/Plan M,R CNG-EP-1.01-1013, KIA2.4.41 (4.6)

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 (:5 3 for ROs; :s; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (:5 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point Unit 1 Date of Examination: March 2015 Examination Level: RO Operating Test Number: LC1 13-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform Reactor Water Level Instrument Checks P, D, S Conduct of Operations 2013 NRG N1-ST-DO, KIA 2.1.7 (4.4)

Determine Personnel Overtime Availability Conduct of Operations M,R CNG-SE-1.01.1002, KIA 2.1.5 (2.9)

Perform Daily Thermal Limit Surveillance Equipment Control D, R N1-RESP-1A, KIA 2.2.12 (3.7)

Perform CRO Firefighting Checklist Emergency Procedures/Plan N, S EPIP-EPP-28, KIA 2.4.27 (3.4)

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 & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (=::; 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Nine Mile Point Unit 1 Date of Examination: March 2015 Exam Level: RO/SR0-1/SRO-U Operating Test No.: LC1 13-01 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Place SOC in service, Pump trips D,A,S, L 4 KIA 205000 A4.01 (3.7/3.7), N1-0P-4
b. Vent the Drywell Prior to Personnel Entry <212 N,S,L 5 KIA 223001 A4.03 (3.4/3.4), N1-0P-9
c. Partial MSIV Stroke test P,S, D 3

KIA 239001 A4.01 (4.2/4.0), N1-ST-Q26 NRC 2010

d. Transfer House Loads from Reserve to Normal N,S 6 KIA 262001 A4.04 (3.6/3.7) N1-0P-30
e. Swap RBV Fans 11to12, Fan 12 low amps (Faulted)

D,S 9 KIA 288000 A4.01 (3.1/2.9), N1-0P-10

f. Control Rod Exercising Operability Test N,S,A 7 KIA 214000 A4.02 (3.8/3.8), N1-ST-W1, N1-0P-5
g. Place Second RWCU Pump in Service (RO Only)

D,S 2 KIA 204000 A4.01 (3.1/3.0), N1-0P-3

h. Inject LP, RWCU Fails to Isolate D,EN,S 1 KIA 211000 A1.08 (3.7/3.8), N1-EOP-HC In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. DFP Start with No Control Power D,R 8 KIA 286000 A3.01 (3.4/3.4)
j. Perform OATC Actions for Control Room Evacuation-Hot EOG M,A,R 6 KIA 295003 AA1.02 (4.2/4.3)
k. Initiate ECs from the RSP, Level Control Fails D,A,E,R, 7

KIA 295016 AA1.09 (4.0/4.0) N1-SOP-21.2 EN

@ 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.

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-2 Op-Test No.: LC1 13-01 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 50-55% power. Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.

Turnover: Start Circulating Water pump 11. Raise Reactor power with Recirculation flow.

Event Malf. Event Event No. No. Type* Description N- Start Circulating Water Pump 11 1 N/A BOP, SRO N1-0P-19 R- Raise Reactor Power with Recirculation Flow 2 NIA ATC, SRO N1-0P-1, N1-0P-43B Recirculation Flow Unit Fails Upscale 3 NM36A I-SRO ARP F2-2-6, Technical Specifications I-BOP, Emergency Condenser 12 Inadvertent Initiation 4 EC03B SRO ARP K1-1-5, N1-0P-13, Technical Specifications Fuel Failure 5 RX01 C-All N1-SOP-25.2, N1-SOP-1.1, N1-SOP-1 Main Steam Line Break in Turbine Building 6 MS01 M-All N1-EOP-2, N1-EOP-6 Powerboard 12 Fails to Fast Transfer and Feedwater Pump 11 ED27 7 C-BOP Trips FW03A N1-SOP-30.2, N1-SOP-1 MS13A Two MSIVs Fail to Close 8 C-All MS13C N1-EOP-6, N1-EOP-8 Turbine Building Ventilation Exhaust Fan Trips 9 Override C-ATC N1-EOP-6, N1-EOP-8

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-3 Op-Test No.: LC1 13-01 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 85% power. Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.

Turnover: Shutdown Condensate Pump 11 for maintenance due to a motor oil leak and place in Pull-To-Lock. Then Perform a Rod Sequence Exchange.

Event Malf. Event Event No. No. Type* Description N-BOP, Condensate Pump 11 shutdown 1 N/A SRO N1-0P-15A, Tech Spec 3.1.8 R-ATC, Rod Sequence Exchange 2 N/A SRO N1-0P-5, RMI I-BOP, Main Steam Line Radiation Monitor Failure 3 RM51A SRO ARP F1-2-7, Tech Spec 3.6.2.h I-BOP, RBCLC Temperature Controller fails to minimum cooling 4 CW19 SRO N1-SOP-11.1 C-ATC, RPS MG Set trip 5 RP01B SRO N1-0P-48, N1-SOP-16.1, Tech Spec 3.6.12 RD34 Instrument air leak, Reactor scram required 6 C-All IA01 N1-SOP-20.1, N1-SOP-1 ATWS 7 RD33 M-All N1-EOP-2, N1-EOP-3 Feedwater Isolation Valves 11 and 12 fail to isolate 8 Overrides C-All N1-EOP-3

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-0-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-4 Op-Test No.: LC1 13-01 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 90% Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.

Turnover: Recirc Pump 11 MG set has been repaired and is ready to be returned to service. Lower reactor power per the RMI and restore 11 recirc pump to service.

After starting Recirc Pump 11 MG set and placing in service, operate it for one hour while maintenance takes readings before returning to 100% power.

Event Malf. Event Event No. No. Type* Description N/A R-ATC, Lower power to permit returning Recirc Pump 11 to service 1

SRO N/A N-BOP, Restore Recirc Pump 11 to service 2

SRO C-BOP, Reactor Building Exhaust Fan 11 trips. Requires RBEVS initiation.

3 HV01A SRO L 1-3-4, L 1-1-5, N1-EOP-5, N1-0P-10, Technical Specifications RR65E RR pump 15 Blind Controller failure and delayed pump trip 4 I-All RR09E N1-SOP-1.3, Tech Spec3.1.7 EC01 Steam leak inside Drywell 5 M-All N1-EOP-2, N1-EOP-4 Failed open vacuum breaker 6 PC10 C-All N1-EOP-4 FW28A HPCI fails to initiate, Core Spray fails to auto-inject C-BOP, 7 FW28B N1-EOP-2 SRO CS07 C-ATC, Containment Spray pump 111 trips CT01A 8 SRO N1-EOP-8

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-5 Op-Test No.: LC1 13-01 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 100% power. Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.

Turnover: Remove Line 4 from service.

Event Malf. Event Event No. No. Type* Description N- Remove Line 4 from Service 1 N/A BOP, SRO N 1-0P-33A, Technical Specifications C-BOP, ERV Inadvertently Opens 2 ADOS SRO N1-SOP-1.4, N1-SOP-1.1, Technical Specifications R-ATC C- Powerboard 16A Electrical Fault 3 ED12A BOP, SRO ARP L4-3-6, N1-EOP-4 CW04A All RBCLC Pumps Trip 4 CW04B C-All N1-SOP-11.1, N1-SOP-1, N1-EOP-2 CW04C FW03A Feedwater Pumps Fail to Operate 5 FW03B C-All N1-EOP-2 FW06 CU01 Coolant Leak Inside Primary Containment 6 M-All EC01 N1-EOP-2, N1-EOP-4 VICP201 Fuel Zone Level Instrument Sporadic Indication 7 I-All 68/69 N1-EOP-2, N1-EOP-7

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior
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