ML103090636

Draft - Outlines (Folder 2)

ML103090636
Person / Time
Site:	Nine Mile Point
Issue date:	08/17/2010
From:	Todd Fish Operations Branch I
To:	Constellation Energy Nuclear Group
Hansell S
Shared Package
ML101900599	List: IR 05000410/2010302 ML102140374 ML103090619 ML103090636 ML103090647 ML103120049 ML103640250 ML103640338 ML103640340 ML103640349 ML110310468
References
50-410/10-302, TAC U01790
Download: ML103090636 (36)

Text

ES-401 Written Examination Outline (NRC) Form ES-401-1 Facility: Nine Mile Point Unit 2 Date of Exam: November 2010 Tier Group RO KIA Category Points SRO-Only Points K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G

• Total A2 G* Total 1. Emergency

& Plant Evaluations 1 3 4 4 3 3 3 20 4 3 7 2 1 2 1 1 1 1 7 2 1 3 Tier Totals 4 6 5 4 4 4 27 6 4 10 2. Plant Systems 1 2 2 3 3 2 2 2 3 2 2 3 26 3 2 5 2 2 0 1 2 1 1 1 1 1 1 1 12 0 1 2 3 Tier Totals 4 2 4 5 3 3 3 4 3 3 4 38 4 4 8 3. Generic Knowledge

& Abilities 1 2 3 4 10 1 2 3 4 7 2 3 2 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. 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 KIA's 8. On the following pages , enter the KIA numbers , a brief description of each top i c , the topics' importance ratings (lR) 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 10CFR55.43 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group KIA Topic(s) EAPE#/Name Safety Function 700000 Generator Voltage and Electric Grid Disturbances AA2.05-Ability to determine and/or Interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES

' Operational status of offsite circuit 3.8 76 295019 Partial or Total Loss of Inst. Air / 8 AA2.01 -Ability to determine and/or interpret the follOWing as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : Instrument air system pressure 3.6 77 295001 Partial or Complete Loss of Forced Core Flow Circulation 1 1 & 4 AA2.04 -Ability to detennine and/or i nterpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION

Individual jet pump flows: Not-BWR1&2 3 1 78 295021 Loss of Shutdown Cooling /4 2.2.38 -Equipment Control: Knowledge of conditions and limitations in the faCility license. 4.5 79 295016 Control Room Abandonment I 7 2.4.34 -Emergency Procedures I Plan. Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. 4.1 80 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown 1 1 2.4.6. -Emergency Procedures I Plan: Knowledge of EOP MItigation strategies 4.7 81 295023 Refueling Accidents

/8 AA2.03 -Ability to determine and/or Interpret the following as they apply to REFUELING ACCIDENTS . Airborne contam i nation levels 3.8 82 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group EAPE#/Name Safety Funct i on KiA Topic(s) 295024 High Drywell Pressure / 5 X EK1 .01 -Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE:

Drywell integrity: Plant-Specific 4.1 39 295025 High Reactor Pressure / 3 X EK1 .03 -Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE : Safety/relief valve tailpipe temperature/pressure relationships 3.6 40 600000 Plant Fire On-site / 8 X AK3.04 -Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on s i te 2.8 41 295019 Partial or Total Loss of Inst. Air / 8 X AK2.08 -Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following

Plant Ventilation 2.8 42 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown /1 X EK2.09 -Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following:

Reactor Water level 4.0 43 295028 High Drywell Temperature / 5 X EK2.03 -Knowledge of the interrelations between HIGH DRYWE L L TEMPE'RA TURE and the following

Reactor water level indication 3.6 44 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group EAPE#/Name Safety Function KJA Topic(s) 295021 Loss of Shutdown Cooling /4 X AK3.01 -Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING: Raising reactor water level 3.3 45 295023 Refueling Accidents / 8 X AK3.03 -KnowleQge of the reasons for the following responses as they apply to REFUELING ACCIDENTS:

Ventilation isolation 3.3 46 295030 Low Suppression Pool Water Level / 5 X EK3.03 -Knowledge of the reasons for the following responses as they apply to LOW SUPPRESSION POOL WATER LEVEL: RCIC operation:

Plant-Specific 3.6 47 700000 Generator Voltage and Electric Grid Disturbances X AA 1.01 -Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:

Grid frequency and voltage. 3.6 48 295026 Suppression Pool High Water Temp. /5 X EA 1.02 -Ability to operate and/or monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

Suppression pool spray: Plant-Specific 3.6 49 295003 Partial or Complete Loss of AC / 6 X AA 1.01 -Abi lity to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: A.C. electrical distribution 3.7 50 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X AA2.03 -Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Actual core flow 3.3 51 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group EAPE#/Name Safety Function KJA Topic(s) 295018 Partial or Total Loss of CCW / 8 X AA2.04 -Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System flow 2.9 52 295005 Main Turbine Generator Trip / 3 X AA2.03 -Ability to determine and/or interpret the following as they apply to MAl N TURBINE GENERATOR TRIP : Turbine valve position 3.1 53 295004 Partial or Total Loss of DC Pwr / 6 X AK2.03 -Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the DC Bus loads 3.3 54 295038 High Off-site Release Rate / 9 X 2.2.25 -Equipment Control: Knowledge of bases in Technical Specifications for limiting conditions for operations and safety limits. 3.2 55 295006 SCRAM / 1 X 2.4.50 -Emergency Procedures

/ Plan: Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 4.2 56 295016 Control Room Abandonment / 7 X 2.4.9 -Emergency Procedures

/ Plan: Knowledge of low power / shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

3.8 57 295031 Reactor Low Water Level/2 X EK1.01 -Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling 4.6 58 KJA CategoryTotals 3 4 4 3 31 31 Group Point Total: I 20/7 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group KIA Topic(s) EAPE#/Name Safety Function 295015 Incomplete SCRAM / 1 AA2.02 -Ability to determme and/or i nterpret the following as they apply to INCOMPLETE SCRAM ; Control rod posit i on 4.2 83 295014 Inadvertent Reactivity Addition / 1 X 2.4.31 -Emergency Procedures I Plan: Knowledge of annunciator alarms , indications , or 4.1 84 295007 High Reactor Pressure AA2.01 -Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE : Reactor pressure 4.1 85 295022 Loss of CRD Pumps /1 X AK1.01 -Knowledge of the operational

.implications of the following concepts as they apply to LOSS OF CRD PUMPS: Reactor pressure vs. rod insertion capability 3.3 59 295009 Low Reactor Water Level / 2 X AK2.03 -Knowledge of the interrelations between LOW REACTOR WATER LEVEL and the following

Recirculation system 3.1 60 295020 Inadvertent Cant. Isolation / 5 & 7 X AK3.02 -Knowledge of the reasons for the following responses as they apply to INADVERTENT CONTAINMENT ISOLATION: Drywell/containment 3.3 61 295036 Secondary Containment High Sump/Area Water Level / 5 X EA 1.01 -Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL : Secondary containment equipment and floor drain systems 3.2 62 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group 1 EAPE#/Name Safety Function

__-_-KIA Topic(s) 295007 High Reactor Pressure 13 ,X* .. ; AA2.02 -Ability to determine andlor interpret the following as they apply to HIGH REACTOR PRESSURE:

4.1 63 295002 Loss of Main Condenser Vac I 3 295029 High Suppression Pool Water Levell 5 X , .... , . .' " X* . ; . .,'::, ,': ',; -. " . '. ..*.. '. Reactor BQwer .-i--.--2.4.11 -Emergency Procedures I Plan: Knowledge of abnormal 4.0 64 condition procedures.

EK2.07 -Knowledge of the interrelations between HIGH SUPPRESSION POOL WATER LEVEL and the 3.1 65 following:

Dryweillcontainment water level KIA CategoryTotals 1 2 1 j 1 112 111 Group Point Total: _L713 __

ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group System #/Name KJA Topic(s) 211000 SLC A2.0S -Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on those predictions , use procedures to correct , 3.4 86 I control , or mitigate the consequences of those abnormal conditions or operations

Loss of SBlC tank heaters 218000 ADS X A2.03 -Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based on those predIctions , use procedures to correct , control , or mItigate the consequences of those abnormal conditions or operations

loss of air supply to ADS valves: Plant-Specific 3.6 87 215005 APRM I lPRM X A2.05 -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 predictions , use procedures to correct , control, or mitigate the consequences of those abnormal conditions or operations

' loss of recirculation flow signal 3.6 88 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group System #lName K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic(s) Imp. I Q#J 2.1.23 -Conduct of Operations

Ability to 400000 Component perform specific system X and integrated plant 4.4 89 Cooling Water procedures during all modes of plant olleration. 2.2.40 -Equipment 203000 RHR/LPCI: Control' Ability to apply 4.7 90 Injection Mode Technical Specifications for a system. K1 .06 -Knowledge of the physical connections and/or cause-effect relationships between 239002 SRVs X RELIEF/SAFETY 3.4 VALVES and the following: Drywell instrument air/ drywell p neumatics:

Plant-Specific K1.05 -Knowledge of the physical connections and/or cause-effect relationships between 218000 ADS X AUTOMATIC 3.9 2 DEPRESSURIZATION SYSTEM and the following:

Remote shutdown system: Plant-Specific K2.02 -Knowledge of 212000 RPS X electrical power supplies 2.7 3 to the following:

Analog trip system logic cabinets K2.01 -Knowledge of 215004 Source X electrical power supplies 2.6 4 Range Monitor to the following

SRM channels/detectors ES-401 Nine Mile Point Unit 2 Written Examination Outline (NRC) Plant Systems -Tier 2 Group 1 Form ES-401-1

=riS1 1 K21 K3 I K41 K5 A2 1

___KJ_A_T_o_p._iC_(S_)

__--,-I._'m_p_.

-'-..I_Q#-.JI K3.03 -Knowledge of the effect that a loss or malfunction of the D.C. 263000 DC ELECTRICAL Electrical X DISTRIBUTION will have 3.4 5 Distribution on following:

Systems ! with D.C. components i I (i.e. valves, motors, I i solenoids, etc.) ! I K3.05 -Knowledge of the effect that a loss or malfunction of the 262002 UPS UNINTERRUPTABLE (ACID C) X POWER SUPPL Y 2.9 6 (A.C.lD.C.)

will have on I I i following:

Rod worth I i minimizer: . Specific ! K4.02 -Knowledge of SHUTDOWN COOLING SYSTEM (RHR 205000 Shutdown SHUTDOWN COOLING ,Cooling X MODE) design feature(s) 3.7 7 and/or interlocks which ! provide for the following:

! ! ! ! ! High pressure isolation: . Plant-Specific K4.05 -Knowledge of STANDBY LIQUID CONTROL SYSTEM 211000 SLC X design feature(s) and/or .3.4 8 interlocks which provide I! I I for the following:

I ! Dispersal of boron upon ! i I injection into the vessel K5.02 -Knowledge of the operational 262001 AC implications of the Electrical X following concepts as 2.6 9 Distribution

! they apply to A.C. I ELECTRICAL I ! DISTRIBUTION:

Breaker i control i i ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group i A2 IA3ELiL__ K.JATO_p_iC(_S)

__

K5.03 -Knowledge of the operational implications of the following concepts as 2150031RM X they apply to 3.0 10 INTERMEDIATE RANGE MONITOR I I (IRM) SYSTEM: I Changing detector position K6.01 -Knowledge of the effect that a loss or malfunction of the 259002 Reactor X following will have on the .3.2 11 Water Level Control REACTOR WATER I I LEVEL CONTROL I i SYSTEM: Plant air system_s_.. K6.01 -Knowledge of 400000 Component the effect that a loss or X malfunction of the 2.7 12* Cooling Water I I following will have on the i ! I i I CCWS: Valves . A 1.03 -Ability to predict and/or monitor changes in parameters associated 209001 LPCS X with operating the LOW 3.8 .13 PRESSURE CORE I I SPRAY SYSTEM I controls including:

I i I Reactor water level A 1.01 -Ability to predict and/or monitor changes in parameters associated with operating the 217000 RCIC X REACTOR CORE 3.7 ! 14 I I ISOLATION COOLING I I SYSTEM (RCIC) i controls including:

RCIC I i I ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group System #/Name KIA I A2.05 -Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; 261000 SGTS X and (b) based on those predictions, use 3.0 15 i procedures to correct, control, or mitigate the consequences of those abnormal conditions or 0Qerations:

Fan triQs A2.02 -Ability to (a) i I predict the impacts of the following on the RHR/LPCI:

INJECTION MODE (PLANT 203000 RHRlLPCI:

Injection Mode X SPECIFIC)

and (b) based on those predictions, use 3.5 ! 16 I i i I procedures to correct, control, or mitigate the consequences of those i abnormal conditions or operations

Pump trips A3.04 -Ability to monitor automatic operations of the EMERGENCY 264000 EDGs X GENERATORS (DIESEL/JET) including:

3.1 : 17 Operation of the governor control system I i

• on freq uency and I voltage control A3.04 -Ability to monitor automatic operations of 209002 HPCS X the HIGH PRESSURE CORE SPRAY SYSTEM. 3.7 18 i i i i I I (HPCS) including:

• System flow: BWR-5,6 I A4.04 -Ability to i : 215005 APRM / LPRM i i X

• manually operate and/or I monitor in the control 3 2 room: LPRM back panel: . switches, meters and I 19 I I I I i i I : indicating lights I I ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group System #/Name KIA Topic(s) 2150031RM I 223002 PCIS/Nuclear

Steam Supply I Shutoff I 205000 Shutdown Cooling I 215004 Source I Range Monitor 262001 AC Electrical Distribution I 212000 RPS X I I I I A4.04 -Ability to manually operate and/or X monitor in the I control room: IRM back I panel switches, meters, I and indicating lights 2.2.12 -Equipment X Control: Knowledge of I I surveillance procedures.

I I 2.1.28 -Conduct of Operations:

Knowledge X of the purpose and function of major system I I components and I controls.

2.4.46 -Emergency Procedures

/ Plan: Ability X to verify that the alarms I I are consistent with the I plant conditions.

A2.07 -Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those X predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or I operations:

Energizing a I I dead bus K3.09 -Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on following:

The magnitude of heat energy that must be absorbed by the containment during I accident/transient I conditions 3.1 20 3.7 : 21 i 4.1 22 I 4.2 23 I 3.0 24 3.2 25 I ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group System #/Name KIA Topic(s) 300000 Instrument Air X K4.03 -Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following

Securing of lAS upon loss of cooling water 2.8 26 KIA Category Totals 2 2 3 3 2 2 2 3/ 2 2 31 Group Point Total: l 26/5 ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group System #lName KIA Topic(s) 290002 Reactor Vessel Internals 201003 Control Rod and Drive Mechanism 259001 Reactor Feedwater 271000 Off-gas X 216000 Nuclear Boiler Inst. X A2.04 -Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTERNALS

and (b) based on those X predictions , use procedures to correct , control , or mitigate the consequences of those abnormal conditions or operations. Excessive heatup/cooldown rate 2.2.22 -Equipment Control

Knowledge of I limiting conditions for I operations and safety limits. 2.1.19 -Conduct of Operations

Ability to use X plant computers to evaluate system or component status. K1.04 -Knowledge of the physical connections and/or cause-effect relationships between OFFGAS SYSTEM and the following:

Condensate system K1.02 -Knowledge of the physical connections and/or cause effect relationships between NUCLEAR BOILER INSTRUMENTATION and the following

PCIS/NSSSS 4.1 91 4.7 92 3.8 93 2.7 27 3.8 28 i ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group System #/Name KIA Topic(s) 201002 RMCS X '239001 Main and Reheat Steam 204000 RWCU 201006 RWM i i i ,233000 Fuel Pool Cooling/Cleanup i K3.03 -Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL CONTROL SYSTEM will have on following:

Ability to process rod block signals K4.06 -Knowledge of MAIN AND REHEAT STEAM SYSTEM design feature(s) and/or X interlocks which provide for the following:

Allows for removal or prevents escape of radioactive steam from systems that have leaky MSIV's K5.04 -Knowledge of the operational implications of the X following concepts as they apply to REACTOR WATER CLEANUP SYSTEM : Heat i exchanger operation K6.05 -Knowledge of the effect that a loss or malfunction of the following will have on the X ROD WORTH MINIMIZER SYSTEM i (RWM) (PLANT i SPECIFIC)

Steam flow input:

BWR6) A 1.07 -Ability to predict and/or monitor changes in parameters associated X with operating the FUEL POOL COOLING AND i I I CLEAN-UP controls i including:

System i I temperature 2.9 29 3.1 30 ! 2.7 31 ! 2.7 32 2.7 33 I ES-401 Form ES-401-1 Nine Mile Point Unit Written Examination Outline Plant Systems -Tier 2 Group KIA Topic(s) System #/Name 202002 Recirculation Flow Control 215001 Traversing I I,n-core Probe 201003 Control Rod 'and Drive I Mechanism 1215002 RBM 234000 Fuel Handling Equipment KIA Category Totals A2.08 -Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b) based on those predictions, use 3.3 34 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

FCV Lockup BWR-5,6 A3.03 -Ability to monitor automatic operations of the TRAVERSING 2.5 CORE PROBE Valve operation: A4.02 -Ability manually operate and/or I monitor in the control 3.5 36 room: CRD mechanism osition: Plant-S ecific 2.1.20 -Conduct of Operations:

Ability to 4.6 *37 I interpret and execute rocedure ste s. K4.03 -Knowledge of FUEL HANDLING EQUIPMENT design feature(s) and/or interlocks which provide x 3.4 38 for the following:

Protection against inadvertently lifting radioactive components out of the water Group Point Total: 35 ES-401 Nine Mile Point Unit 2 Form ES-401-3 Written Examination Outline (NRC) Generic Knowledge and Abilities Outline (Tier 3) Facility:

NMP2 N Date: Category KA# Topic RO SRO-Only 1. Conduct of Operations I , R Q# 66 IR Q# 2.1.41 Knowledge of the refueling process. 2.8 2.1.36 Knowledge of procedures and limitations involved in core alterations. 3.0 67 2.1.5 Ability to use procedures related to shift staffing , such as minimum crew complement , overtime limitations, etc. 3.9 94 2.1 32 Ability to explain and apply all system limits and precautions. 4.0 100 Subtotal 2 2 2. Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. 4.6 68 2.2.13 Knowledge of tagging and clearance I procedures.

4.1 69 2.2.38 Knowledge of conditions and limitations in the facility license. 3.6 74 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations , such as risk assessments , work prioritization, etc. 39 95 2.236 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limitina.

conditions for operations. 4.2 99 Subtotal 3 2 ES-401 Nine Mile Point Unit 2 Form ES-401-3 Written Examination Outline (NRC) Generic Knowledge and Abilities Outline (Tier 3) 3. Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.4 70 2.3.12 Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. 3.2 71 2.3.13 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties , such as response to radiation monitor alarms , containment entry requirements , fuel handling responsibilities , access to locked high radiation areas , aligning filters , etc. 3.8 96 Subtotal 2 1 4. Emergency Procedures

/ Plan 2.4.17 Knowledge of EOP terms and definitions.

3.9 72 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.

4.0 73 2.4.29 Knowledg_e of the emergency 21an. 3.1 75 2.4.20 Knowledge of operational implications of EOP wamings, cautions, and notes. 4.3 97 2.4.22 Knowledge of the bases for prioritizing safety functions during operations. 4.4 98 Subtotal 3 2 Tier 3 Point Total: 10 7 ES-401 Record of Rejected KiA's Form ES-401-4 Tier / Group 1 / 1 Randomly Selected KA 600000/ AK1.01 Reason for Rejection Question 41, Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Classifications by type. Low level of difficulty. Randomly selected AK3.04 -Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site 1 /2 295002 / 2.2.4 Question 64, Equipment Control: (multi-unit license) Ability to explain the variations in control board layouts , systems , instrumentation and procedural actions between units at a facility. (Loss of Main Condenser Vac). NMP2 is not a multi-unit license. Randomly selected G2.4.11 -Emergency Procedures

/ Plan: Knowledge of abnormal condition procedures. 2/1 215005/2.2.4 Question 88 , Equipment Control: (multi-unit license) Ability to explain the variations In control board layouts , systems , instrumentation and procedural actions between units at a facility (APRMs). NMP2 is not a multi-unit facility. Randomly selected A2.05 -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 predictions , use procedures to correct , control , or mitigate the consequences of those abnormal conditions or operations

Loss of recirculation flow signal 2/1 400000 I 2.1.27 Question 89 , Conduct of Operations

Knowledge of system purpose and 1 or function (Component cooling water). Not discriminatory at the SRO level. Randomly selected G2.1.23 -Conduct of Operations

Ability to perfonn specific system and integrated plant procedures dunng all modes of plant operation. 2/2 268000/ K5.01 Question 31, Knowledge of the operational implications of the following concepts as they apply to RADWASTE:

Units of radiation, dose and dose rate. Low level of difficulty.

Randomly selected 204000 K5.04 -Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER CLEANUP SYSTEM: Heat exchanger operation ES-401 Record of Rejected KIA's Form ES-401-4 2/2 2010061 K6 .02 Question 32 , Knowledge of the effect that a loss or malfunction of the following will have on the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC):

Reactor water level control input: P-Spec(Not-BWR6) . NMP2 is not a not a BWR6. Randomly selected K6.05 -Steam flow input:

BWR6) 3/2 G2 1 2.2 .17 Question 69 , Knowledge of the process for managing maintenance activities during power operations, such as risk assessments , work prioritization, coordination with the transmission system operator. This is an SRO function per NMP2 procedures.

Randomly selected G2 .2.13 -Knowledge of tagging and clearance procedures 1 1 1 2950191 AK2.13 Question 42 , Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following

Isolation condenser: Plant-Specific. NMP2 does not have isolation condensers. Randomly selected AK2 .08 -Plant Ventilation 2/1 295007 I AP\2.02 Question 85 , Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor power. Same KA as RO #63. Randomly selected AP\2 01 -Reactor pressure 2/1 3000001 A4.01 Question 20, Ability to manually operate and/or monitor in the contro l room: Pressure gauges. Instrument Air oversampled throughout exam. (42,77 , 87) Randomly selected 215003 A4.04 -Ability to manually operate and/or monitor in the control room : IRM back panel switches , meters , and indicating lights 2/1 215003/2.2.40 Question 90. Equipment Control Ability to apply Techn i cal Specifications for a system. Nuclear Instrumentation is oversampled throughout exam. Randomly selected 203000 2.2.40-RHR/LPCI. Injection Mode , EqUipment Control' Ability to apply Technical Specifications for a system

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ES-401 Record of Rejected KiA's Form ES-401-4 Question 15. Ability to (a) predict the impac ts of the following on the STANDBY GAS TREATMENT SYSTE M ; and (b) based on those predictions, use procedures to corre ct, control, or mitigate 2/1 261000/A2.04 1--. 216000/K2.01 2/2 2/2 202002/ A2.03 1 11 295037/ EK2,12 1 11 2950261 EA 1.03 2950051 AA2,07 the consequences of those abnormal condi tions or operations:

High train moisture content. Low discrimina tory value at the license operator level. Randomly selected A2.05 -Fan Trips Question 28. Knowledge of electrical powe r supplies to the following:

Analog trip system: Plant-Specifi c, Analog trip system does not apply at NMP2 Randomly selected K1.02 -Knowledge of t he physical connections and/or cause effect relationshi ps between NUCLEAR BOILER INSTRUMENTATION and the following:

PCIS/NSSSS Question 34, Ability to (a) predict the impac ts of the following on the RECIRCULATION FLOW CONTROL S YSTEM ; and (b) based on those predictions, use procedure s to correct, control, or mitigate the consequences of those abnor mal conditions or operations:

Loss of D.C. DC control for sys tem does not apply at NMP2, Randomly selected A2,08 -FCV Lockup Question 43, Knowledge of the interrelation s between SCRAM CONDITION PRESENT AND REACTOR P OWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following:

Rod control and information system: Rod contr 01 and information system: Plant-Specific.

RCIS does not appl y at NMP2. Randomly selected EK2.09 -Reactor water level Question 49, Ability to operate and/or moni tor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

Temperature monitoring, Low level of difficulty, Randomly selected EA1 ,02 -Suppression pool spray, ---------------

Question 53, Ability to determine and/or int erpret the following as they apply to MAIN TURBINE GENERATO R TRIP: Reactor water level. The tie between reactor level a nd turbine trip is the high level trip to prevent moisture carryover and subsequent shrink/swell.

This is a low level of difficulty t opic, Randomly selected AA2,03 -Turbine valve position ES-401 Record of Rejected KIA's Form ES-401-4 1 / 1 295004/2.2.38 Question 54, Equipment Control: Knowledge of conditions and limitations in the facility license. Although there are procedural and TS requirements for this system there are no limitations in the facility license. Other KAs would address TS. Randomly selected AK2.03 DC Bus loads (Partial or complete loss of DC) 1/1 700000 / AA2.06 Question 76 , Ability to determine and/or mterpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES. Generatorfrequency limitations. Topic similar to RO#48. Randomly selected AA2.05 -Operational status of offsite circuit 1 / 1 295037 I 2.2.36 Question 81 , Equipment Control Ability to analyze the effect of maintenance activities , such as degraded power sources, on the status of limiting conditions for operations.

An operationally valid question could not be written because the topic does not align w i th the APE , SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown , In this situation , EOP Implementation is the concem , not LCO status. Randomly selected 2.4.6 -Knowledge of EOP mitigation Strategies 3/3 G2/ G2.3.6 Question 99 , Ability to approve release permits. This function is rarely done and is mainly performed thru chemistry and radwaste procedures. Randomly selected G2.2.36 -Ability to analyze the effect of maintenance activities , such as degraded power sources , an the status of IImitin9_ conditions for operations.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:__----:.N:.;..M""P'-'2'---...:.N=R=C"__ Examination Level: RO Date of Examination:

11/10 Operating Test Number: 1 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations N,R Verification of License Requirements Given information related to maintenance of active license status for three operators, the candidate will determine which operator(s), if any, is(are) qualified to relieve the watch. 2.1.4 (3.3) Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. S-ODP-TQS-O 1 01-R0050 Conduct of Operations D,R Determine Core Thermal Power lAW N2-REP-11 The candidate will determine core thermal power using turbine first stage pressure in accordance with N2-REP-11 KJA 2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Equipment Control M,R Develop a Tagging Request for the "B" TBCLCW Pump The candidate will develop and document a tagging request for the "8" T8CLCW Pump. KJA 2.2.13 (4.3) Knowledge of tagging and clearance procedures.

CNG-OP-1.01-1007 Emergency Plan M,S Actions For External Security Threats Given plant conditions, respond to a security threat per EPP-10, Attachment 2, Security Contingency Event (CSO Checklist) 2.4.28 (3.2) Knowledge of procedures relating to a security event (non-safeguards information).

EPIP-EPP-10 Attachment 2 SAME AS UNIT 1 EXAM 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 (P)revious 2 exams (:::1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility:__

__ Examination Level: SRO Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Type Code* M,R D,R N,R P,R Date of Examination:

11/10 Operating Test Number:___-=l__ Describe activity to be performed Review Daily Checks Log lAW N2-0SP-LOG-D001 The candidate will review a completed portion of control room daily logs. Identify deficiencies and TS requirements.

KIA 2.1.18 (3.8) Ability to make accurate, clear, and concise logs, records, status boards, and reports. Evaluate Plant Chemistry Report (GAP-CHE-01, TS) Review plant daily status report, which includes plant chemistry, identify and determine required actions in response to out-of-specification reactor coolant chemistry parameters.

KIA 2.1.34 (3.S) Ability to maintain the primary and secondary plant chemistry within allowable limits. Review of Completed Surveillance Test 0001, Primary Containment Purge System Valve Operability Test. The candidate will review a completed surveillance test to determine acceptability KIA 2.2.12 (4.3) Knowledge of surveillance procedures Emergency Exposure Authorization Review and Approval The candidate will review the exposure status of personnel to determine expected radiation exposure and the need for an Emergency Exposure Authorization.

KIA 2.3.4 (3.7) Knowledge of radiation exposure limits under normal or emergency conditions.

SAME JPM ON UNIT 1 EXAM Emergency Plan D,R Classify Emergency Event Given plant conditions, evaluate emergency event. KJA 2.4.44 (4.4) Knowledge of emergency plan protective action recommendations.

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 (,53 for ROs; ,5 4 for SROs & RO retakes) {N)ew or {M)odified from bank

{P)revious 2 exams (,51; randomly selected)

ES-301 Facility:

Nine Mile Point Unit 2 Date of Examination:

November 2010 Exam Level: RO/SRO Operating Test No.: Control Room Systems@ (8 for RO; 2 or 3 for SRO-U, including 1 ESF) System 1 JPM Title Type I Safety Function .

..

S-1 Start the DIV1 H2/02 Monitoring from the Suppression O,EN,S 5 Chamber Post LOCA CONTAIMENT INTEGRITY The candidate will restart the H2/02 monitoring system post LOCA and sample from the suppression chamber lAW OP-82 Sections F.1.0 and H.2.0 KIA 223001 A4.04 3.5/3.6 S-2 Add Air to a De-inerted Drywell M,L,S 9 RADIOACTIVITY The candidate will raise drywell pressure using the RELEASE primary containment purge fan lAW N2-0P-61A Section H.3.0 KIA 261001 A4.04 3.3/3.4

..S-3 Securing and Restart of Shutdown Cooling M,A,L,S 4 HEAT REMOVAL The candidate will secure SDC for a short period of time and FROM RXCORE then restart the pump. During the restart, a failure of the throttle valve results in the inability to establish required flow and a pump trip is required lAW N2-0P-31 Sections H.3.0 & 4.0 KIA 205000 A4.01 3.7/3.7 S-4 Return WCS to Normal O,A,S 2 REACTOR WATER The candidate will return WCS to normal following INVENTORY feeedwater stratification operation lAW N2-0P-37.

Actions CONTROL will be required due to an isolation signal lAW the ARP. KIA 204000 A4.03 3.2/3.1

...Start and Load Division I Diesel 0 A S S-5 , , 6 ELECTRICAL The candidate will start and load the Division I Diesel lAW N2-0P-100A, Section FAO. A loss of SW will occur requiring a diesel shutdown.

KIA 264000 A4.04 (3.7/3.7)

S-6 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Place Main Turbine Shell Warming in service 3 M,L,S REACTOR RO PRESSURE The candidate will place Main Turbine Shell Warming in ONLY CONTROL service lAW N2-0P-21, Section E.3.0. KiA 241000 A4.18 2.9/2.8 I I S-7 Transfer Recirc Pumps from High to Low speed 1 D,S REACTIVITY CONTROL The candidate will transfer Recirc Pumps from high speed low speed per N2-0P-29 section KiA 202001 A4.01 3.7/3.7 I S-8 Shift RBCLCW and TBCLCW Pumps P,A,S 8 PLANT SERVICE The candidate will shift RBCLCW Pumps from "A" to "C", SYSTEMS then shift TBCLCW Pumps from "A" to "c" lAW N2-0P-13 & 14. Actions will be required due to a failure of the temperature KA 400000 A4.01 3.1/3.0 I J " : In-Plant Systems@ (3 for RO; 3 or 2 for SRO-U) 8 PLANT SERVICE SYSTEMS P-1 Start the Diesel Fire Pump Locally M The candidate will start the Diesel Fire Pump locally lAW OP-43 Section I KiA 286000 2.1.30 4.4/4.0 P-2 Hydro Pump Boron Injection The candidate will Commence boron injection with the hydro pump lined up to 2SLS"P1A piping in accordance with 6, Attachment

15. KiA 295037 EA 1.10 3.7/3.9 D,E,R I 1 REACTIVITY CONTROL P-3 II Reset an EPA Breaker The candidate will Reset EPA Breaker 2VBS*ACB2A with an Overvoltage condition present lAW N2-S0P-97 KA 262001 2.1.234.3/4.4 I D,R I 6 ELECTRICAL I

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 @ 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. I

• Type Codes (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 Criteria for RO I SRO-II SRO-U 4-6/4-6 12-3 s9/s8/S4 ;::1/;::1/;::1 / ;::1 (control room system) ;::1/;::1/;::1 s 31 s 31 s 2 (randomly selected)

1/;

:1/;::1 I:

Appendix D Scenario Outline Form ES-D-1 Facility:

Nine Mile Point Unit 2 Scenario No.: NRC-01 Op-Test No.: 11/2010 Examiners:

Operators:

__________ Initial Conditions:

Simulator IC-21 or equivalent

1. Reactor Power 95% Turnover:

1. 95% power. 2. Add water to the sunnro",c,."n Event Malf. No. Event No. Type* 1 N/A 2 CS08 3 TC03A 5 RH13A ED05A 9 Override N (BOP) N (SRO) TS (SRO) TS (SRO) with CSH lAW N2-0P-33 Event Descri I Add water to the suppression pool with CSH o CSH Min Flow Valve Fails Closed TS 3.5.1 EHC Oscillations

-Power reduction required ... (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 1 -1 November 2010 Facility' Nine Mile Point Unit 2 Scenario No: NRC-01 Op-Test No.: 11/2010 1. Total malfunctions (5-8) 8 Events 2,3,4,5,6,7,8,9

2. Malfunctions after EOP entry (1-2) 2 Events 8&9 3. Abnormal events (2-4) 4 Events 3,4,5,6 1 Events 7 4. Major transients (1-2) I ! 5. EOPs entered/requiring substantive actions (1-2) Events 7 & 8 (EOP-RPV, EOP-PC) 2 6. EOP contingencies requiring substantive actions (0-2) 0 7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT -1.0 -Restore power to DlV II vital bus by cloSing the DlV II EDG output breaker lAW SOP-03 CT-2.0 -Initiate Drywell spray when suppression chamber pressure is >10 psig to prevent exceeding the Pressure Suppression Pressure Limit i NRC Scenario 1 2-November 2010 Appendix 0 Scenario Outline Form ES-O-1 Facility:

Nine Mile Point Unit 2 Scenario No.: NRC-02 Op-Test No.: 11/2010 Examiners:

Operators:

__________ Initial Conditions:

Simulator IC-21 or equivalent

1. Reactor Power 100% Turnover: 1. 10:0% . 2. Perform section. 8.2 of N2-0SP-RPS-W002, Manual Scram Test Channel "An Event . Malf. No. I Event I Event No. , I Type* : Description Perform section 8.2 of N2-0SP-RPS-W002, Manual Scram Override N (BOP) N (SRO) TS (SRO) Test Channel "An only Indication Failure during test at step 8.2.11 -Annunciator remains in alarm I TS 3.3.1.1 2 CS01B Remote RD12A Spurious start of HPCS 1A motor electric fau 6 7 RR46A RR10B EOP-C5 * (N)onmal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 2 November 2010 Facility:

Nine Mile Point Unit 2 Scenario No.: NRC-02 No.: 11/2010 1. Total malfunctions (5-8) Events 1 thru 8 2. Malfunctions after EOP entry (1-2) Event 8 3. Abnormal events (2-4) Event 2,3,4,5,6

4. Major transients (1-2) Event 7 5. EOPs entered/requiring sUbstantive Event 7 (EOP-RPV)

! 6. EOP contingencies requiring sUbstantive actions Event 7 2 7. Critical tasks (2-3) 'CRITICAL TASK DESCRIPTIONS:

CT*1.0 -Given a failure of the reactor to with power above 4% or unknown, the will terminate and prevent all except boron, CRD and CT*2.0 -Given a failure of the reactor to scram, crew will lower power by inserting rods or injecting boron lAW EOP*C5 to NRC Scenario 2 November 2010 Appendix D Scenario Outline Form ES-D-1 Facility:

Nine Mile Point Unit 2 Scenario No.: NRC-OS Op-Test No.: 11/2010 Examiners:

Operators:

__________ Initial Conditions:

IC-11 or equivalent

1. Reactor Power 4.5% Turnover:

1. For a PMT, perform OW to SC Vacuum Bkr test N2-0SP-ISC-M@002 for 2ISC*RV33A

& 2ISC*RV33A 1 N/A 2 N/A NM060 4 ROO? 5 N/A 6 E004G ? Override 8 Event Type* N (BOP) N (SRO) C (RO) I C (SRO) N (RO) N (SRO) C (BOP) C (SRO) TS TS (SRO) M (ALL) Event Description Perform OW to SC Vacuum Bkr test N2-0SP-ISC-M@002 Continue Startup Transfer Mode Switch to Run OP-101A Loss of Power to Oiv II switchgear RCIC Steam Line Isolation Valve ICS*MOV128 breaker trips open I TS 3.6.1.3 RCIC steam leak into reactor building fails to isolate EHC pumps trip EOP-RPV, EOP*SC, EOP*C2, SOP*101C I C (BOP) I Condensate Booster pumps trip 9 ,FW02A,B,C i C (SRO) EOP-RPV (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 5 November 2010 I Facility:

Nine Mile Point Unit 2 Scenario No.: NRC-OS Op-Test No.: 1112010 -----j 1. Total malfunctions (5-8) Events 3, 4, 6, 7 ,8, 9 6 2, Malfunctions after EOP entry (1-2) Event 9 I I 1 3. Abnormal events (2-4) Events 3, 4, 6 I 3 I 4. Major transients (1-2) I Event 8 1 I 5, EOPs entered/requiring substantive actions (1-2) 8 -(EOP-RPV, EOP-SC) 2 I 6. EOP contingencies requiring substantive actions (0-2) i Event 8 -(EOP-C2) 1 7, Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Given an unisolabJe RCIC steam leak and secondary containment temperature approaching maximum safe values in one area, the crew will enter EOP-RPV and initiate a manual reactor scram CT-2.0 Given an unisolable RCIC steam leak and I seconda ry containment temperature above ' maximum safe values in two or more I L areas, the crew will perform an Blowdown per

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,-----NRC Scenario 5 November 201 0