ML051570306

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Final - Outlines (Folder 3)
ML051570306
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 04/06/2005
From: Godley R
Constellation Energy Group
To: Todd Fish
Operations Branch I
Conte R
References
Download: ML051570306 (35)
v • d • e


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UNIT 2 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 2 Date of Exam: May 9,2005 Note 1 Ensure that at least two topics from every WA 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 WA 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 +I 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 ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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 WAS 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 WA categories 7 *The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system 8 On the following pages, enter the WA 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 Use duplicate pages for RO and SRO-only exams 9 For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals on Form ES-401-3 Limit SRO selections to WAS that are linked to 10 CFR 55 43 ES401,Page 1 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal DraH Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO)

ES-401 BWR Examination Outline F o ES-401-1

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Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (RO)

E/APE # / Name / Safety Function WA Topic@)

295001 Partial or Complete Loss of Forced AK1.03 Knowledge of the operational implications of 3.6 1 Core Flow Circulation / 1 8 4 the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW RO 01 CIRCULATION: tThermal limits.

295001 Partial or Complete Loss of Forced AA2.06 Ability to determine and/or interpret the 3.2 Core Flow Circulation I1 & 4 followng as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

RO 02 Nuclear boiler Instrumentation.

295003 Partial or Complete Loss of AC / 6 AA1.02 Ability to operate and/or monitor the 4.2 following as they apply to PARTIAL OR COMPLETE RO 03 LOSS OF A.C. POWER: Emergency generators.

i 295004 Partial or Total Loss of DC Pwr I 6 AA1.02 Ability to operate and/or monitor the 3.8 following as they apply to PARTIAL OR COMPLETE RO 04 LOSS OF D.C. POWER: Systems necessary to assure safe plant shutdown 295005 Main Turbine Generator Trip / 3 AA1.01 Ability to operate andlor monitor the 3.1 following as they apply to MAIN TURBINE RO 05 GENERATOR TRIP: Recirculation system.

295006 SCRAM / 1 AK2.02 Knowledge of the interrelations between 3.8 SCRAM and the following: Reactor water level RO 06 control system.

295016 Control Room Abandonment / 7 AK2.01 Knowledge of the interrelations between 4.4 CONTROL ROOM ABANDONMENT and the RO 07 following: Remote shutdown panel.

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295018 Partial or Total Loss of CCW / 8 AK1.01 Knowledge of the operational implications of 3.5 the following concepts as they apply to PARTIAL OR RO 08 COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on componenVsystem operations.

T 295019 Partial or Total Loss of Inst. Air / 8 AK2.03 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT RO 09 AIR and the following: Reactor feedwater.

295021 Loss of Shutdown Cooling / 4 AA1.04 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN RO 10 COOLING: Alternate heat removal methods.

295023 Refueling Acc Cooling Mode / 8 AK1.01 Knowledge of the operational implications of the following concepts as they apply to REFUELING RO 11

- ACCIDENTS: Radiation exposure hazards.

295024 High Drywell Pressure / 5 X 2.1.32 Ability to explain and apply system limits and precautions.

RO 12 295025 High Reactor Pressure 13 0 EA2.01 Ability to determine and/or interpret the 4.3 1 1 following as they apply to HIGH REACTOR RO 13 PRESSURE: Reactor pressure.

295026 Suppression Pool High Water Temp.

/ 5 R014 I I I I I xI 2.2.22 Knowledge of limiting condibons for operaeons and safety limits I I 3.4 295028 High D w e l l Temperature / 5 0 EK2 03 Knowledge of the interrelations between 3.6 1 3 HIGH DRYWELL TEMPERATURE and the RO 15 following: Reactor water level indicabon

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295030 Low Suppression Pool Wtr Lvl I 5 X 2.4.6 Knowledge symptom based EOP mitigabon 3.1 1 strategies.

RO 16

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UNIT 2 NRC (RO) 295031 Reactor Low Water Level I 2 EA2.04 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER RO 17 LEVEL: Adequate core cooling.

295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown IIII EA2.03 Ability to determine andlor interpret the following as they apply to SCRAM CONDITION 4.3 1 11 R 0 1 8 I I I I PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC tank level.

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295038 High Off-site Release Rate I 9 a EA1.01 Ability to operate and/or monitor the I following as they apply to HIGH OFF-SITE RO 19 RELEASE RATE: Stack-gas monitoring system.

600000 Plant Fire On Site I 8 0 AK3.04 Knowledge of the reasons for the following 2.8 1 4 responses as they apply to PLANT FIRE ON SITE:

RO 20 Actions contained in the abnormal procedure for plant fire on site.

WA Category Totals: 3 4 1 5 3 I Group Point Total: I 20 ES 401, Page 3 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)

ElAPE # I Name / Safety Function K K K A A G 1 2 3 1 2 WA Topic@)

PRI

  • 295009 Low Reactor Water Level I 2 295012 High Drywell Temperature I 5 AA2.02 Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL: Steam flowlfeed flow mismatch.

AK2.02 Knowledge of the interrelations between HIGH I I 3.6 3.6 1 DRYWELL TEMPERATURE and the following: Drywell RO 22 cooling.

1 295014 Inadvertent Reacbvity Addition I 1 R023 I I I I AK3.01 Knowledge of the reasons for the following responses as they apply to INADVERTENT REACTIVITY ADDITION: Reactor SCRAM.

4.1 1 295015 IncomDlete SCRAM I 1 lo1 I I I I AK1.O1 Knowledge of the operational implicabons of 3.6 1 RO 24 Ill I I I I the following concepts as they apply to INCOMPLETE SCRAM: Shutdown margin.

1 295022 Loss of CRD Pumps I 1

~ 0 2 5 llllllx 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation.

3.9 1 I

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I I I 1 PI 295033 High Secondary Containment Area EA2.01 Ability to determine andlor interpret the Radiation Levels / 9 followng as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS Area RO26 I 295029 High Suppression Pool Water Level 1 1 1 I0I I I l5 I I I 131 I RO 27 WA Category Point Totals: 1 1 1 1 2 1 ES 401, Page 4 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Drafl Submittal Drafl Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

System # / Name 1 :I: WA Topic(s) 11 203000 RHR/LPCI: Injection 2.4.31 Knowledge of annunciators alarms and 3.3 1 Mode indications / and use of the response instructions.

RO 28 205000 Shutdown Cooling K5.02 Knowledge of the operational implications of the following concepts as they RO 29 apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Valve operation.

209001 LPCS K4.07 Knowledge of LOW PRESSURE CORE 2.8 1 SPRAY SYSTEM design feature(s) and/or RO 30 interlocks which provide for the following:

Pump operability testing 209002 HPCS 1 K1.11 Knowledge of the physical connections 3.8 1 1 andlor cause effect relationships between RO 31 HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) and the following: Adequate core cooling.

209002 HPCS A4.11 Ability to manually operate and/or monitor in the control room: System flow.

RO 32 21 1000 SLC RO 33 II A3.06 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM 4.0 I

including: RWCU system isolation: Plant-Specific.

212000 RPS K5.02 Knowledge of the operational 3.3 implications of the following concepts as they RO 34 apply to REACTOR PROTECTION SYSTEM:

Specific logic arrangements.

215003 IRM I I K3.01 Knowledge of the effect that a loss or 3.9 z7-l malfunction of the INTERMEDIATE RANGE RO 35 MONITOR (IRM) SYSTEM will have on following: RPS.

215004 Source Range Monitor 2.4.50 Ability to verify system alarm setpoints 3.3 and operate controls identified in the alarm response manual.

Al.04 Ability to predict and/or monitor 1 4.1 1 changes in parameters associated with operating the AVERAGE POWER RANGE MONlTORlLOCAL POWER RANGE MONITOR SYSTEM controls including:

SCRAM and rod block triD seboints.

217000 RClC RO 38 217000 RClC I I: K2.01 Knowledge of electrical power supplies to the following: Motor operated valves.

2.1.23 Ability to perform specific system and I I 2'8 3.9 RO 39 integrated plant procedures during different modes of plant operation.

c 4.2 218000 ADS RO 40 IT A4.02 Ability to manually operate and/or monitor in the control room: ADS logic initiation 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, April 20,2005

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UNIT 2 NRC (RO) 223002 PCIS/Nuclear Steam K4.08 Knowledge of PRIMARY 3.3 1 Supply Shutoff CONTAINMENT ISOLATION SYSTEM

/NUCLEAR STEAM SUPPLY SHUT-OFF RO 41 design feature(s) and/or interlocks which provide for the following: tManual defeating of selected isolations during specified emergency conditions.

239002 SRVs 0 K1.03 Knowledge of the physical connections 3.5 1 and/or cause effect relationships between RO 42 RELlEFlSAFETY VALVES and the following:

1 3 Nuclear boiler instrument system 259002 Reactor Water Level A1.04 Ability to predict and/or monitor 3.6 1 Control changes in parameters associated with operating the REACTOR WATER LEVEL RO 43 CONTROL SYSTEM controls including:

Reactor water level control controller indications 259002 Reactor Water Level K6.02 Knowledge of the effect that a loss or 3.3 1 Control malfunction of the following will have on the REACTOR WATER LEVEL CONTROL RO 44 SYSTEM: AC power.

261 000 SGTS A2.05 Ability to (a) predict the impacts of the 3.0 1 following on the STANDBY GAS TREATMENT RO 45 SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fan trips.

262001 AC Electrical A2.03 Ability to (a) predict the impacts of the 3.9 1 Distribution following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those RO 46 predictions, use procedures to correct, control, 7

or mitigate the consequences of those abnormal conditions or operations: Loss of off-site power.

(Repeat WA, 2000 NRC RO Written exam).

262002 UPS (ACIDC) A3.01 Ability to monitor automatic operations 2.8 1 of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) including: Transfer from preferred to alternate source.

(Repeat WA, 2002 NRC RO Written exam).

263000 DC Electrical A3.01 Ability to monitor automatic operations 3.2 1 Distribution of the D.C. ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, RO 48 and indicating Lights.

264000 EDGs K4.02 Knowledge of EMERGENCY 4.0 1 GENERATORS (DIESELIJET) design RO 49 feature(s) and/or interlocks which provide for the following: Emergency generator trips (emergency/LOCA).

264000 EDGs A1 01 Ability to predict and/or monitor 3.0 1 changes in parameters associated with RO 50 operating the EMERGENCY GENERATORS (DIESEL/JET) controls including Lube Oil Temperature ES 401, Page 6 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO)

I 300000 Instrument Air K3.02 Knowledge of the effect that a loss or 1 malfunction of the INSTRUMENT AIR RO 51 SYSTEM will have on the following: Systems having pneumatic valves and controls.

400000 Component Cooling K6.05 Knowledge of the effect that a loss or 1 Water malfunction of the following will have on the CCWS: Pumps.

RO 52 400000 Component Cooling Al.04 Ability to predict and / or monitor 2.8 1 Water changes in parameters associated with operating the CCWS controls including: Surge RO 53 Tank Level K/A Category Point Totals: I2 2 1 3 I Group Point Total: I 26 ES 401, Page 7 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Plant S, ems - 'ier ZGroup 2 (RO) 1 System # / Name K K k A G K/A Topic(s) IR #

3 4 5 4

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201001 CRD Hydraulic A2.07Ability to (a) predict the impacts of 3.2 1 the following on the CONTROL ROD RO 54 DRIVE HYDRAULIC SYSTEM ; and (b) based on those predictions, use procedures to correct, control. or mitigate the consequences of those abnormal conditions or operations: Flow control valve failure.

201002 RMCS K1.01 Knowledge of the physical 3.2 1 connections and/or cause-effect RO 55 relationships REACTOR MANUAL CONTROL SYSTEM and the following:

Control rod hydraulic system 201006 RWM K1.04 Knowledge of the physical 3.1 1 connections and/or cause effect RO 56 relationships between ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) and the following: Steam Flow/Reactor Power 202001 Recirculation K6.07 Knowledge of the effect that a loss 3.3 1 or malfunction of the following will have RO 57 on the RECIRCULATION SYSTEM:

Feedwater flow.

215001 TIP K6.04 Knowledge of the effect that a loss 3.1 1 or malfunction of the following will have RO 58 on the TRAVERSING IN-CORE PROBE:

Primary containment isolation svstem.

219000 RHRILPCI: ToruslPool 0 K5.04 Knowledge of the operational 2.9 1 Cooling Mode 4 implications of the following concepts as they apply to RHR/LPCI:

RO 59 TORUS/SUPPRESSION POOL COOLING MODE: Heat exchanger operation.

234000 Fuel Handling Equipment 0 K4.02 Knowledge of FUEL HANDLING 3.3 1 2 EQUIPMENT design feature(s) and/or RO 60 interlocks which provide for the following:

Prevention of control rod movement during core alterations.

241000 Reactorrurbine Pressure A4.18 Ability to manually operate and/or 2.9 1 Regulator monitor in the control room: Turbine shell warming RO 61 I

271000 Offgas 2.1.23 Ability to perform specific system 3.9 1 and integrated plant procedures during RO 62 different modes of olant oDeration 11 I 272000 Radiation Monitoring K2.03 Knowledge of electrical power 2.5 1 supplies to the following: Stack gas RO 63 radiation monitoring system.

ES 401, Page 8 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO) 290001 Secondary Containment

- RO 64 or malfuncbon of SECONDARY CONTAINMENT will have on the following. Off-site radioacbve release 290003 Control Room HVAC 4 changes in parameters associated with RO 65 operating the CONTROL ROOM HVAC controls including Control Room Pressure WA Category Point Totals ES 401, Page 9 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO)

ES-401 Generic Knowledge and Abilities Outline (Tier 3) (RO) Form ES-401-3 Facility: Nine Mile Point Unit 2 Date of Exam: May 9,2005 Category KIA # Topic RO SRO IR # IR 1.

Knowledge of conduct of operations Conduct of requirements. RO 66 Operations I I I Knowledge of how to conduct and verify valve lineups. RO 67

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.25 Ability to obtain and interpret station reference 2.8 . 1 materials such as graphs / monographs / and tables which contain performance data.

RO 68 Subtotal 3

2. 2.2.12 Knowledge of surveillance procedures. 3.0 1 Equipment (Repeat KIA, 2002 NRC RO Written Exam) RO 69 Control 2.2.13 2.2.22 1 Knowledge of tagging and clearance procedures. RO 70 ~~

Knowledge of limiting conditions for operation

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I I I 3.6 3.4

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and safety limits. RO 71 Subtotal 3

3. 2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control / including permissible Radiation levels in excess of those authorized. RO 72 Control 2.3.10 Ability to perform procedures to reduce 2.9 1 excessive levels of radiation and guard against personnel exposure. RO 73 Subtotal 2
4. 2.4.20 Knowledge of operational implications of EOP 33 1 warnings / cautions / and notes. RO 74 Emergency Knowledge of the RO's responsibilities in 2.4.39 3.3 1 Procedures / emergency plan implementation. RO 75 Plan Subtotal 2 Tier 3 Point Total I 110 I ES 401, Page 10 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (RO)

Facility: Nine Mile Point Unit 2 Date of Exam: May 9,2005 ES-401 Record of Reiected WAS (RO) Form ES-401-4 TlGl 295024 2.1.28 Rejected based on low cognitive level and low difficulty level.

T1 G1 295026 2.1.za Rejected based on low cognitive level and low difficulty level.

T1G1 295030 2.1.14 Rejected based on those reports limited to the RO and not the SRO are better evaluated during the simulator scenarios. SRO internal and external reporting might be appropriate for the written examination.

T1 G2 NONE NONE T2G1 215004 2.2.25 Rejected based on tech spec bases are SRO only level knowledge.

T2G1 264000 Al.07, Al.08. Rejected based on WA importance rating <2.5.

A1 07 I Facility Outline Review T1 G1 295004 2.1.2 Rejected based on the Generic KA statement is not relevant to the applicable evolution 295004 PartiallTotal loss of DC. Randomly selected new KA AAl.02 (RO 04)

T2G1 259002 A2.01 Rejected based on overlap with Operating Test Scenario 1 Event 4. Randomly selected new KA Al.04 (RO 43)

T2G2 202001 A2.10. K4.11 Rejected based on overlap with Operating Test Scenario 2 Event 2. Randomly selected K4.11 which OVerlaDDed Scenario 1 Event 3. Randomlv selected K6.07 T2G2 241000 A4.08 Replaced based on overlap with Operating Test JPM 6. Randomly selected from the A4 topic area A4.18 (RO61)

T2G2 290001 A2.02 Replaced based on overlap with RO 45. Both are topic A2 and ultimately test the same concept of positive containment pressure. Randomly selected new KA K3.01 (RO 64)

T1G2 295035 2 4.31 Replaced based on overlap with RO 45 and 64 and over-sampling of Secondary Containment parameters. Randomly selected new KA 295007 and rejected it due to overlap with KA 295025 (R013). Randomly selected new KA 295029 EA1.03 (RO 27)

T2G2 201002 2.1.2 Replaced, unable to develop an appropriate discriminating question. The generic statement does not fit the system. Randomly selected new KA K1.01 (RO 55)

T2G1 400000 Al.03 Replaced based on overlap with previous question KA 400000 K6.05 for RO 52.

Randomly selected new KA Al.04 (RO 53)

ES 401, Page 1 of 1 2005 U2 Test 2 (NRC) - RO Written Record of Rejected KAs Wednesday, April 20,2005

UNIT 2 NRC (SRO)

ES-401 BWR Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 2 Date of Exam: May 9,2005 Note: 1. Ensure that at least two topics from every K/A 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 WA 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 k l 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 ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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 WAS 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 WA categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the WA 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. Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

ES 401,Page 1 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, April 20.2005

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UNIT 2 NRC {SRO)

ES-40 1 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (SRO)

E/APE # / Name / Safety K/A Topic(s) IR #

Function 295003 Partial or Total Loss of 2.2.25 Knowledge of bases in 3.7 1 AC/6 technical specifications for limiting conditions for operations and safety SRO 01 limits.

295016 Control Room AA2.02 Ability to determine and/or 4.3 1 Abandonment / 7 interpret the following as they apply to CONTROL ROOM ABANDONMENT:

SRO 02 Reactor water level. -

295020 Inadvertent AA2.02 Ability to determine and/or 3.4 1 Containment Isolation interpret the following as they apply to INADVERTENT CONTAINMENT SRO 03 ISOLATION: Drywell/containment tem perat ure.

295031 Reactor Low Water 2.4.6 Knowledge symptom based 4.0 1 Level I 2 EOP mitigation strategies.

SRO 04 295037 SCRAM Condition EA2.01 Ability to determine and/or 4.3 1 Present and Power Above interpret the following as they apply to APRM Downscale or Unknown / SCRAM CONDITION PRESENT AND 1 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

SRO 05 Reactor power.

295038 High Off-site Release EA2.03 Ability to determine and/or 4.3 1 Rate I 9 interpret the following as they apply to HIGH OFF-SITE RELEASE RATE:

SRO 06 tRadiation levels. --

600000 Plant Fire On Site / 8 2.1.14 Knowledge of system status 3.3 1 SRO 07 criteria which require the notification of plant personnel.

KIA Category Totals: Group Point Total: 7 ES 401, Page 2 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, April 20,2005

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UNIT 2 NRC (SRO)

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 (SRO)

I E/APE # / Name / Safety Function 295007 High Reactor Pressure

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KIA Topic(s)

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2.2.22 Knowledge of limiting

/ I R / #

113 for operation and safety limits.

I SRO08 HI/

295014 Inadvertent Reactivity 2.1.32 Ability to explain and apply 3.8 1 Addition / 1 system limits and precautions.

SRO 09 295033 High Secondary 0 EA2.01 Ability to determine and/or 3.9 1 Containment Area Radiation 3 interpret the following as they apply to Levels / 5 HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS:Area SRO 10 radiation levels.

1 KIA Category Point Totals: Io1 01 01 c 1 2 Group Point Total: 3 ES 401, Page 3 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, April 20,2005

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UNIT 2 NRC (SRO)

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ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO) -

System ## / Name WA Topic(s) IR

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209002 HPCS 2.4.30 Knowledge of which 3.6 events related to system SRO I 1 operations/status should be reported to outside agencies.

212000 RPS 2.2.22 Knowledge of limiting 4.1 conditions for operations and SRO 12 safety limits.

215004 Source Range A2.02 Ability to (a) pred.ict the 3.7 Monitor impacts of the following on the SOURCE RANGE MONITOR SRO 13 (SRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: SRM inop condition. -

223002 PCIS/Nuclear A2.08 Ability to (a) predict the 3.1 Steam Supply Shutoff impacts of the following on the PRIMARY CONTAINMENT SRO 14 ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

tSurveillance testing. -

262001 AC Electrical A2.11 Ability to (a) predict the 3.6 Distribution impacts of the following on the A.C. ELECTRICAL SRO 15 DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Degraded system voltaaes.

K/A Category Point Group Point Total:

Totals:

ES 401, Page 4 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, April 20,2005

ES-401 BWR Examination Outline Form ES-401-1 Plant {stems - Tier 2/Gm I 2 (SRO)

System # / Name K/A Topic(s) IR 201006 RWM A2.05 Ability to (a) predict the 3.5 impacts of the following on SRO 16 the ROD WORTH MINIMIZER SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Out of sequence

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rod movement.

216000 Nuclear Boiler 2.2.25 Knowledge of bases in 3.7 Inst. technical specifications for SRO 17 limiting conditions for operations and safety limits.

234000 Fuel Handling A2.01 Ability to (a) predict the 3.7 Equipment impacts of the following on the FUEL HANGLING SRO 18 EQUIPMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Interlock failure.

KIA Category Point Group Point Total:

Totals:

ES 401, Page 5 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, April 20,2005

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UNIT 2 NRC (SRO)

ES-40 1 Generic Knowledge and Abilities Outline (Tier 3) F O SES-401-3

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Facility: Nine Mile Point Unit 2 Date of Exam: May 9,2005 Category WA # Topic RO SRO-Only IR # IR #

2.1.1 1 Knowledge of less than one hour technical 3.8 1.

specification action statements for systems.

Conduct of (Evaluate LCO 3.0.3) 0perat io ns SRO 19 2.1.34 Ability to maintain primary and secondary 2.9 plant chemistry within allowable limits.

SRO 20 2.2.24 Ability to analyze the affect of maintenance 3.8 2.

activities on LCO status.

Equipment SR021 Control 2.2.29 Knowledge of SRO fuel handling 3.8 responsibilities.

SRO 22 2

2.3.9 Knowledge of the process for performing a 3.4 1 3.

containment purge. SRO 23 Radiation Control 1

2.4.38 Ability to take actions called for in the facility 4.0 1 4.

emergency plan / including (if required)

Emergency supporting or acting as emergency Procedures / coordinator. SRO 24 Plan 2.4.41 Subtotal 1 Knowledge of action level thresholds and classifications. SRO 25 4.1 1 2

Tier 3 Point Total 7 ES 401, Page 6 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, April 20,2005

UNIT 2 NRC (SRO)

Facility: Nine Mile Point Unit 2 Date of Exam: May 9, 2005 ES-401 Record of Rejected WAS (SRO) Form ES-401-4 I Tier / Group I 5

Randomly Selected K/A 1 I

Reason for Rejection I Per ES-401, Attachment 1, #1: Review each group and delete those items [Emergency/Abnormal Plant Evolutions (E/APEs) for Tier 1 and systems for Tier 21 that clearly do not apply to the facility for which the examination is being written. They are:

1 TlGl NA 295027 High Containment Temperature. Not applicable to facility.

T1G2 NA 29501 1 High Containment Temperature. Not applicable to facility.

T2G1 NA 206000 High Pressure Coolant Injection (HPCI). Not applicable to facility design.

T2G1 NA 207000 Isolation (Emergency Condenser). Not applicable to facility design.

T2G2 NA 201005 Rod Control and Information System (RCIS). Not applicable to facility I I design.

T2G2 I NA I 239003 MSlV Leakage Control System. Not applicable to facility design.

Per ES-401. Attachment 2 #5: Except as noted in ES-401, Attachment 2, Item 1, all KA statements that are eliminated afler they have been randomly selected to fill an examination outline shall be documented on Form ES-401-4. "Record of Rejected KAs," or equivalent. They are:

TlGl 600000 2.4.31 Rejected based on this KIA not linked to 10CFR55.43.

TlGl 60000 2.1.23 Rejected based on this K/A not linked to 10CFR55.43.

T1G2 295014 2.1.2 Rejected based on this WA not linked to 10CFR55.43.

T1G2 295014 2.4.50 Rejected based on this WA not linked to 10CFR55.43.

T3 2.4.31 Rejected based on this WA not linked to 10CFR55.43.

T3 2.4.25 Rejected based on avoiding possible double jeopardy and over sampling with 600000 2.1.23. Rejected based on this K/A not linked to 10CFR55.43.

T3 2.4.40 Rejected based on this K/A not linked to 10CFR55.43.

T3 2.4.44 Replaced KA for SRO 25 because of double jeopardy and over-sampling. This topic is covered in SRO Admin JPM topics. Randomly selected 2.4.41 Per ES-401 D . l .d: After completing the outline. check the selected K/As for balance of coverage within and across the three tiers.

Ensure that every applicable K/A category is sampled at least twice within each of the three tiers. 1 T1G1 295024 AA2.02 Replaced KA. unable to write an acceptable discriminating question at SRO level.

Randomly selected new KA 295020 AA2.02 (SRO 3)

T3 2.3.4 Replaced KA based on overlap with RO 72. Randomly selected from generic 2.3s new KA 2.3.10 (SRO 23)

Changes made as a result of NRC review of drafl exam submittal T3 2.3.10 Replaced KA. unable to write an acceptable discriminating question at SRO level.

Randomly selected new KA 2.3.9 (SRO 23)

ES 401, Page 1 of 1 2005 U2 Test 2 (NRC) - SRO Written Record of Rejected KAs Drafl Exam Submittal Wednesday, April 20,2005

ES-301 Administrative Topics Outline Form ES-301-1 acility: NINE MILE POINT 2 Date of Examination: May 2, 2005 xamination Level (circle one): RO Operating Test Number: NRC-01 4dm inistrative Topic Conduct of Operations i Code*

Type N

Describe activity to be performed EVALUATE SHIFT LOG READING DATA.

Given control room instrument readings for various daily checks required Logs by Technical Specifications enter the instrument readings into the RO ADMIN 1 applicable sections of the control room log sheet(s) and take appropriate actions based on those checks.

2.1.18 (2.9) Ability to make accurate / clear and concise logs / records /

status boards / and reports.

GAP-OPS-01; 3. IO, N2-OSP-LOG-DO01 Conduct of N REVIEW SHIFT TURNOVER DOCUMENTS.

Operations Evaluate conditions provided in S-PM-DO01 Control Room System Lineup Shift Turnover Verification and determine the required corrective actions.

RO ADMIN 2 2.1.3 (3.0) Knowledge of shift turnover practices.

OPERATIONS MANUAL, Section OM 2.2 S-PM-DO01 Control Room System Lineup Verification Equipment N DEFEAT RCWMAIN TURBINE TRIP PER EOP-6. ELECTRICAL Control PRINT READING.

Use of Piping Determine appropriate EOP support procedure to be used, then trace md Instrument through various station electrical drawings (GE prints and ESK's) to Drawings identify components and describe how and why procedure RO ADMIN3 implementation defeats the main turbine trip with RClC initiation signal present.

2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.

N2-EOP-C5; N2-EOP-6 Attachment 2 GE DWG 807El73TY SHEET 3 and 9 ESK 8SPUO2; ESK I llCSO5 Radiation N RADIOLOGICAL REQUIREMENTS RELATED TO OPERATOR Control INSPECTION OF HIGH RAD AREAS.

RO ADMIN 4 Given radiological conditions related to an area to be inspected as shown on a survey map, and other applicable conditions such as the RWP, ensure the appropriate radiological aspects of the job are met prior to performance of the inspection.

2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

GAP-RPP-01; 3.5, 3.6, 3.7, GAP-RPP-02; 3.1, 3,3, GAP-RPP-08; 3.2,3.3, U2 HIGH RAD AREA INSPECTIONS IOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are

?taking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol Room (D)irect from bank (I3 for ROs; 5 4 for SROs & retakes)

(N)ew or (M)odified from bank ( 2 1)

(P)revious 2 exams (I1; randomly selected)

(S)imulator Page 1 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Modified Admistrative Topic Outline Draft Submittal Draft Submittal Werinnsrlav Anril70 7005

ES-301 Administrative Topics Outline Form ES-301-1

=acility: NINE MILE POINT 2 Date of Examination: May 2, 2005

!xamination Level (circle one): SRO Operating Test Number: NRC-01 Administrative Type Describe activity to be performed Topic Code*

Conduct of N DETERMINE REQUIRED ACTIONS FOR RClC ROOM UNIT Operations COOLERS OUT OF SERVICE DURING PLANT STARTUP.

SRO ADMIN 1 Given plant conditions during startup and failure of RClC Room Unit Coolers HVR*UC412A and B,determine required compensatory actions per Operating Procedures and Tech Specs, including systems required to be declared inoperable and the effect on continuing the reactor startup and heatup.

2.1.23 (4.0) Ability to perform specific system and integrated plant procedures during different modes of plant operation.

N2-OP-52; N2-OP-78; TECH SPEC 3.5.3. and 3.6.4.3 Conduct of DETERMINATION OF REACTIVITY EVENT SEVERITY LEVEL AND Operations SUPPORTING ACTIONS IN RESPONSE TO THE EVENT.

SRO ADMIN 2 Given plant conditions related to a reactivity event, determine the event severity level and the appropriate compensatory actions and notifications in response to the event.

2.1.7 (4.4) Ability to evaluate plant performance and make operational judgements based on operating characteristics /reactor behavior / and instrument interpretation.

GAP-OPS-05; 3.13, Tech Specs Equipment REVIEW SURVEILLANCE DATA INCLUDING ACTIONS FOR Control UNSATISFACTORY CONDITIONS.

SRO ADMIN 3 Given a completed surveillance with out of specification parameters, transfer the data from the surveillance procedure to the acceptance test work sheet, evaluate the data, and take action including the surveillance paperwork for an unsatisfactory test and determining the TS implication for unsatisfactory conditions.

2.2.12 (3.4) Knowledge of surveillance procedures.

2.2.24 (3.8) Ability to analyze the effect of maintenance activities on LCO status. (3.8) 2.2.22(4. I ) Knowledge of limiting conditions for operations ans safety limits.

N2-OSP-ICS-Q@002, Technical Specifications Radiation OFFSITE DOSE CALCALCULATON MANUAL (ODCM)

Control ASSESSMENT AND REPORTABILITY FOR RADIOLOGICAL SRO ADMIN 4 EFFLUENTS.

Given conditions related to requirements within the ODCM and must determine the applicable actions and reporting requirements.

2.3.1 (3.0) Knowledge of 10CFR20 and related facility radiation control requirements.

EPIP-EPP- 15, ODCM Emergency N EMERGENCY EAL CLASSIFICATION (POST SCENARIO).

Plan Based on events that occurred within SRO Simulator Scenario as SRO, SRO ADMIN 5 classify the emergency event. May be performed post scenario or as (5-1, 5-2, 5-3) table top discussion.

2.4.40 (4.0) Knowledge of the SROs responsibilities in emergency plan implementation.

Page 2 of 3 NUREG-I 021, Revision 9 2005 U2 Test 2 (NRC) - Modified Admistrative Topic Outline Draft Submittal Draft Submittal Werlnesrlnv And313 30135

ES-30 1 Administrative ToDics Outline Form ES-301-1 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 (D)irect from bank ( 5 3 for ROs; I4 for SROs & retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (I 1; randomly selected)

(S)imulator SRO Admin 2: Removed reference to KA 2.1.12 due to being not applicable to this test item.

Page 3 of 3 NUREG-I 021, Revision 9 2005 U2 Test 2 (NRC) - Modified Adrnistrative Topic Outline Draft Submittal Draft Submittal Wednesrlav A n r i l 7 0 713135

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): RO Operating Test Number: NRC-07 Control Room Systems@8 for RO System / JPM Title Type Code* Safety Function

a. JPM 1 DOWNSHIFT REACTOR RECIRC PUMPS S. N 1 REACTIVITY System: RCS CONTROL Procedure N2-OP-29 G.1.O KA: 202001 A4.01 3.7/3.7 Task: 202-915-01-01
b. JPM 2 RClC INJECTION WITH OSCILLATIONS S , D, A. P 2 Randomly REACTOR After manually starting RCIC, malfunctioning flow controller selected from WATER requires placing controller in manual to establish rated system previous 2 INVENTORY flow. exams (2002) CONTROL System: RClC Procedure: N2-OP-35 F.2.0 KA: 217000 A2.10 2.9/3.0 Task: 21 7-003-01-01 JPM Bank: 02-OPS-SJE-217-2-05
c. JPM 3 RESTORE SHUTDOWN COOLING FOLLOWING 4 PLANNED SHUTDOWN HEAT REMOVAL FROM After starting RHS pump, failure of throttle valve results in inability REACTOR to establish proper system flow, requires pump trip. CORE System: SDCIRHS Procedure: N2-OP-31 H.4.0 KA : 205000 A2.12 2.9/3.0 Task: 205-003-01-01 JPM Bank: 02-OPS-SJE-205-2-11
d. JPM 4 INITIATE CONTAINMENT VENTING TO SBGT UNDER S. D, E, ESF 5 ACCIDENT CONDITIONS CONTAINMENT INTEGRITY System: GTS Procedure N2-OP-61A H . l .O KA: 223001 A2.07 4.2/4.1 Task: 200-942-05-01 (PRA)

JPM Bank: 02-OPS-SJE-261-2-02

e. JPM 5 ENERGIZE RESERVE STATION TRANSFORMER S. N 6 FROM LINE 6 and ENERGIZE NPS-SWG003 FROM RESERVE ELECTRICAL STATION TRANSFORMER 1B System: NPS Procedure N2-SOP3 Attachments 6 & 7 KA: 262001 A4.01 3.4/3.7 Task: 200-035-05-01 (PRA)

Page 1 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline RO Final Final Submittal Wednesday, April 20,2005

Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): RO Operating Test Number: NRC-01 Control Room Systems@8 for RO System / JPM Title Type Code* Safety Function

f. JPM 6 PERFORM TURBINE CONTROL VALVE (CV2 and 3) 7 SURVEILLANCE INSTRUMENTS During testing CV3 will fail to generate the required RPS channel trip, requires inserting a % scram signal in associated trip system.

System: EHClRPS Procedure: N2-OSP-RPS-(2001; N2-SOP-97 KA: 212000 A2.03 3.513.5 Task: 2 12-905-02-01

g. JPM 7 SHIFT INSTRUMENT AIR COMPRESSORS S, N. A 8 PLANT Compressor trip during swap requires entry into N2-SOP-19 and SERVICE manual start of another air compressor. SYSTEMS System: IAS Procedure: N2-OP-19 F.2.0; N2-SOP-19 KA: 295019 AA2.01 3.513.6 Task: 278-004-01 -01
h. JPM 8 MANUAL INITIATION OF CONTROL BUILDING D. S, P 9 SPECIAL FILTER TRAIN Randomly RADIOACTIVITY selected from RELEASE System: HVC previous 2 Procedure: N2-OP-53A exams (2000)

Task: 288-004-01-01 KA: 295038 EA1.07 3.6/3.8 JPM Bank NRC 2000 JPM J1-1 Page 2 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sirn In plant JPM Outline RO Final Final Submittal Wednesday, April 20,2005

Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): RO Operating Test Number: NRC-07 Implant Systems@3 for RO System I JPM Title Type Code* Safety Function

i. JPM 9 VENT CONTROL ROD OVERPISTON VOLUME. D, E, R, P 1 Randomly REACTIVITY System: RDS CONTROL selected from Procedure: N2-EOP-6 Attachment 14 previous 2 Task: 200-962-05-01 exams (1999)

KA: 29501 5 AA1.01 3.8/3.9 JPM Bank: 02-OPS-PJE-200-2-69 2

j . JPM 10 ALIGN FIRE WATER SYSTEM TO INJECT TO RHR RX WATER A(B). INVENTORY System: RHS CONTROL Procedure: N2-EOP-6 Attachment 6 Task: 200-930-05-01 KA: 295031 EA1.08 3.813.9 JPM Bank: 02-NLO-PJE-205-2-02(04)

k. JPM 1ILOCAL START OF DIVISION I DIESEL GENERATOR 6 WITH EMERGENCY STOP. ELECTRICAL System: ENS Procedure: N2-OP-1OOA Task: 264-908-04-01 KA: 264000 G2.1.30 3.913.4

@ All control room (and in-plant) systems must be different and serve different safety functions; in-Dlant svstems and functions mav overlaD those tested in the control room.

SRO-U performs Simulator JPMs 1, 3, 4 and Plant JPMs 10, 11 (Safety Functions 1, 2, 4, 5, 6)

SRO-I performs all JPMs except Simulator JPM 8

  • (SD) Shutdown (JPM 3) per ES 301 4.b page 14, ...one of the tasks shall be related to a SHUTDOWN OR low power condition.. JPM 3 is related to SHUTDOWN condition.

.I Page 3 of 3 NUREG-I 021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline RO Final Final Submittal Wednesday, April 20,2005

ES-30 I Control Room/ln-Plant Systems Outline Form ES-301-2

'acility: Nine Mile Point 2 Date of Examination: May 2, 2005 ixamination Level (circle one): SRO-lnsfanfs Operating Test Number: NRC-07

ontrol Room Systems@7 for SRO-I System / JPM Title Type Code* Safety Function

. JPM 1 DOWNSHIFT REACTOR RECIRC PUMPS S. N 1 REACTIVITY System: RCS CONTROL Procedure N2-OP-29 G . l .O KA: 202001 A4.01 3.7/3.7 Task: 202-915-01-01

. JPM 2 RClC INJECTION WITH OSCILLATIONS 2 Randomly REACTOR After manually starting RCIC, malfunctioning flow controller selected from WATER requires placing controller in manual to establish rated system previous 2 INVENTORY flow. exams (2002) CONTROL System: RClC Procedure: N2-OP-35 F.2.0 KA: 217000 A2.10 2.9/3.0 Task: 21 7-003-01-01 JPM Bank: 02-OPS-SJE-217-2-05

. JPM 3 RESTORE SHUTDOWN COOLING FOLLOWING 4 PLANNED SHUTDOWN HEAT REMOVAL FROM After starting RHS pump, failure of throttle valve results in inability REACTOR to establish proper system flow, requires pump trip. CORE System: SDC/RHS Procedure: N2-OP-31 H.4.0 KA: 205000 A2.12 2.9/3.0 Task: 205-003-01-01 JPM Bank: 02-OPS-SJE-205-2-11

. JPM 4 INITIATE CONTAINMENT VENTING TO SBGT UNDER S , D, E. ESF 5 ACCIDENT CON DIT1ONS CONTAINMENT INTEGRITY System: GTS Procedure N2-OP-61A H.1.O KA: 223001 A2.07 4.2/4.1 Task: 200-942-05-01 (PRA)

JPM Bank: 02-OPS-SJE-261-2-02

~~ ~ ~

JPM 5 ENERGIZE RESERVE STATION TRANSFORMER 6 FROM LINE 6 and ENERGIZE NPS-SWG003 FROM RESERVE ELECTRICAL STATION TRANSFORMER 1B System: NPS Procedure N2-SOP3 Attachments 6 & 7 KA: 262001 A4.01 3.4/3.7 Task: 200-035-05-01 (PRA)

Page 1 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-I Final Final Submittal Wednesday, April 20,2005

Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): SRO-lnstants Operating Test Number: NRC-Of

.- Control Room Systems@7 for SRO-I System / JPM Title I Type Code* I Safety Function

f. JPM 6 PERFORM TURBINE CONTROL VALVE (CV2 and 3) I S, N, A I 7 SURVElLLANCE INSTRUMENTS During testing CV3 will fail to generate the required RPS channel trip, requires inserting a YZscram signal in associated trip system.

System: EHC/RPS Procedure: N2-OSP-RPS-Q001; N2-SOP-97 KA: 212000 A2.03 3 . 9 3 . 5 Task: 212-905-02-01 g JPM 7 SHIFT INSTRUMENT AIR COMPRESSORS 8 PLANT Compressor trip during swap requires entry into N2-SOP-19 and SERVICE manual start of another air compressor SYSTEMS System IAS Procedure N2-OP-19 F 2 0, N2-SOP-19 KA 295019 AA2 01 3 513 6 Task 278-004-01-01 Page 2 of 3 NUREG-I 021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-I Final Final Submittal Wednesday, April 20,2005

Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): SRO-lnstants Operating Test Number: NRC-07 Implant Systems@3 for SRO-I System I JPM Title I Typecode* I Safety Function

h. JPM 9 VENT CONTROL ROD OVERPISTON VOLUME.

REACTIVITY System: RDS selected from Procedure: N2-EOP-6 Attachment 14 Task, 200-962-05-01 KA: 29501 5 AA1.01 3.813.9 JPM Bank: 02-OPS-PJE-200-2-69 RX WATER INVENTORY System: RHS Procedure: N2-EOP-6 Attachment 6 Task: 200-930-05-01 KA: 295031 EA1.08 3.813.9 JPM Bank: 02-NLO-PJE-205-2-02 ELECTRICAL System: ENS Procedure: N2-OP-1OOA Task: 264-908-04-01 in-plant systems and functions may overlap those tested in the control room.

SRO-I performs all JPMs except Simulator JPM 8

  • (SD) Shutdown (JPM 3) per ES 301 4.b page 14, ...one of the tasks shall be related to a SHUTDOWN OR low power condition ... JPM 3 is related to SHUTDOWN condition.

Page 3 of 3 NUREG-I 021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-I Final Final Submittal Wednesday, April 20,2005

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): SRO-Upgrades Operating Test Number: NRC-07

~~

Control Room Systems@3 for SRO-U System / JPM Title I Type Code* I Safety Function

a. JPM 1 DOWNSHIFT REACTOR RECIRC PUMPS S. N 1 REACTIVIlY System: RCS CONTROL Procedure N2-OP-29 G . l .O KA: 202001 A4.01 3.713.7 Task: 202-91 5-01-01
b. JPM 3 RESTORE SHUTDOWN COOLING FOLLOWING 4 PLANNED SHUTDOWN HEAT REMOVAL FROM After starting RHS pump, failure of throttle valve results in inability REACTOR to establish proper system flow, requires pump trip. CORE System: SDC/RHS Procedure: N2-OP-31 H.4.0 KA: 205000 A2.12 2.9/3.0 Task: 205-003-01-01 JPM Bank: 02-OPS-SJE-205-2-11 ACCIDENT CONDITIONS CONTAINMENT INTEGRITY System: GTS Procedure N2-OP-61A H . l .O UA: 223001 A2.07 4.2/4.1 Task: 200-942-05-01 (PRA)

RX WATER INVENTORY Procedure: N2-EOP-6 Attachment 6 CONTROL Task: 200-930-05-01 WITH EMERGENCY STOP. ELECTRICAL System: ENS Procedure: N2-OP-1OOA Task: 264-908-04-01 KA: 264000 G2.1.30 3.9/3.4 Page 1 of 2 NUREG-I 021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-U Final Final Submittal Wednesday, April 20,2005

@ All control room (and in-plant) systems must be different and serve different safety functions; in-Dlant svstems and functions may overlap those tested in the control room. I SRO-U performs Simulator JPMs 1, 3, 4 and Plant JPMs 10, 11 (Safety Functions 1, 2, 4, 5, 6)

SRO-I performs all JPMs except Simulator JPM 8

  • (SD) Shutdown (JPM 3) per ES 301 4.b page 14, "...one of the tasks shall be related to a SHUTDOWN OR low power condition.. ." JPM 3 is related to SHUTDOWN condition.

Page 2 of 2 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-U Final Final Submittal Wednesday, April 20,2005

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

Initial Conditions: Simulator IC-20

1. 96% Power Rod Line >loo% (103%)

Turnover:

1. Raise Suppression Pool water level to 200 feet using CSH Pump per N2-OP-33 Event Malf. No. Event Event No. Type* DescriDtion 1

i 2 RR08B 3 FW03A RR31 RR30 Switch P628-022C-S4A-A NZ-SOP-34 Stuck Open SRV 6 TU02 9%

and Condenser air in-leakage results in a slight drop in vacuum.

MCOl Because of the rising turbine vibration, the crew will insert a 15%, manual reactor scram and trip the main turbine Ramp Time 3 minutes NZ-EOP-RPV Page 1 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) Scenario Outline Final Submittal Final Submittal Thursday, April 21,2005

NRC EXAM 7 MCO1@ M (Major Loss of main condenser vacuum. The degrading vibration causes 100% event a main condenser vacuum leak that degrades rapidly once the Ramp continued reactor is scrammed and results in automatic closure of MSIVs.

Time % but not The loss of the main condenser as a heat sink requires manual minutes counted) operation of SRVs for pressure control and contributes to challenging the Heat Capacity Temperature Limit. Rising Suppression Pool temperature requires entry into N2-EOP-PC.

NP-EOP-PC

~ ~-

Incomplete Scram. When the crew scrams the reactor control RP12A C (BOP) rods fail to insert due to hydraulic lock. Reactor power will lower to RP12B C (SRO) about 18% to 23% by APRM indication. The crew will be able to manually insert control rods using RMCS Additional manual scrams will be successful in inserting control rods 1 FWOIA C(ALL)

N2-EOP-C5 N2-EOP-6 Attachment 14 initiate and WCS to isolate when SLC is manually initiated.

FWOI B capability after terminate and prevent injection is performed. The FWOIC crew will be required to perform RPV Blowdown when RPV water level cannot be maintained above MSCWL. The use of Alternate Injection systems such as low pressure ECCS systems is then required to maintain adequate core cooling.

SRO ADMIN JPM 5-1 SRO classifies the event as Site Area Emergency 2.2.2 (N)ormal, (R)eactivity, (I)nGrument, (C)omponent, (M)ajor TARGET QUANTITATIVE ATTRIBUTES ACTUAL (PER SCENARIO; SEE SECTION D.5.d) ATTRIBUTES

1. Total malfunctions (5-8) 6 Events 2,3,4.5,8,9
2. Malfunctions afler EOP entry (1-2) 2 Events 9.10 3 Abnormal events (2-4) 2 Event 4 SOP-6, Event 5 SOP-34 4 Major transients (1-2) 1 Event 6 (and 7 only counted once) 5 EOPs entered/requiring substantive acbons (1-2) 2 Event 6 and 7 EOP-RPV, EOP-PC 6 EOP conbngenctes requiring substantive achons (0-2) 2 Event 8 EOP-C5, Event 10 EOP62 7 Critical tasks (2-3) 4 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Close ADS valve prior to SPT reaching 110°F CT-2.0 Avoid exceeding HCTL CT-3.0 Restore and maintain RPV water level above MSCRWL (-39 inches)

CT4.0 Fully insert control rods Page 2 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Final Submittal Final Submittal Thursday, April 21.2005

NRC EXAM Appendix D Scenario Outline Form ES-D-1 Facility. Nine Mile Point 2 Scenario No.: NRC-02 Op-Test No. NRC-01 Examiners: Operators:

Initial Conditions: Simulator IC-20

1. Division I Low Pressure ECCS systems CSL and RHS are inoperable for maintenance.
2. 100% Power Rod Line >loo% (106%)

Malf. No.

@.25 1 min c, R, TS leakage requires removal from service and isolation of RCS Pump ramp (SRO) A to stop the leak. (TS 3.4.1 )

RRl6A Cram Rod insertion is required to reduce rod line below 100%.

@ .75 1 min With inoperable OPRMs additional actions are required to monitor

( A ~ ~ for

) power oscillations while in the Heightened Awareness Zone.

I I ramp N2-SOP-29. I , Reactor Recirc Pump Seal Failure N2-SOP-29, Sudden Reduction In Core Flow RD063419 RD062227 ED02A DG04A CS03 5 RR20

@1.5%

RR20@10%

10 min ramp afterscram , I Page 3 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Final SuMttal Final Submittal Thursday, April 21.2005

NRC EXAM I (Bop) I all feedwater and loss of all normal station power except Emergency Bus supplied by the operating DGs.

I 3.1.1

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Facilitv: Nine Mile Point 2 Scenario No.: NRC-02 Op-Test No.: NRC-01 1 TARGET QUANTITATIVE ATTRIBUTES ACTUAL ATTRIBUTES (PER SCENARIO; SEE SECTION D.5.d)
1. Total malfunctions (5-8) 5 Event! 2 3 4 5 7

~~

2. Malfunctionsafter EOP entry (1-2) 2 Events 7.8'
3. Abnormal events (2-4) 3 Event 2 SOP-29.1 and SOP-29. Event 3 SOP-30 Event 4 SOP-3
4. Major transients (1-2) 1 Event 5
5. EOPs enteredkequiring substantive actions (1-2) 2 Event 5 EOP-RPV. EOP-PC
6. EOP contingencies requiring Substantive actions (0-2) 1 Event 9 EOP-C2
7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1.0: Restart CRD pump within 20 minutes with inoperable control rod accumulators.

CT-2.0: Restore and maintain RPV water level above I

TAF with LP ECCS systems I I Event 8* Not counted in Total Malfunctions but counted as Malfunction After EOP entry per Appendix D C.2.c page 9. System out of service influences the mitigation strategy by reducing the number of available injection and containment spray systems to one. Crew must now prioritize use of remaining system to inject to restore water level before using RHR B for containment spray.

Page 4 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Final Submittal Final Submlttal Thursday, April 21,2005

NRC EXAM Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point 2 Scenario No.: NRC-03 Op-Test No.: NRC-01 Examiners. Operators:

Initial Conditions: Simulator IC-10 with additional rods withdrawn to raise power to about 4.5%. Reactor startup in progress per N2-OP-IOIA.

+

Turnover: Continue power ascension; N2-OP-101A; Section E.3.0, Step 3.3.

Continue the startup, transfer the reactor mode switch to run after APRM downscale condition is cleared (above 4%). EHC Pump B is out of service for motor repairs.

Event Malf. No. Event I Event Type* Description R (ATCI Withdraw control rods raise reactor power to above 5%. Several R {SRO) control rods must be withdrawn to raise power to clear the APRM I downscale condition.

N2-OP-101A TS (SRO) placed in service. With less than 4 operating pumps, an additional pumps must be started with 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> COMPLETION TIME.

N2-OP-11 Tech Spec 3.7.1 C (SRO) insert and isolate the control rod. With power level below RWM setpoint the RWM must be bypassed to insert the drifting rod.

N2SOP-8 Tech Spec 3.1.5 I (SRO) Narrow Range level input to FWLC failed as-is. RPV water level transient results requiring crew to take manual control of level control valve to prevent an automatic protective function then transfer to redundant Narrow Range transmitter before returning FWLC to automatic control.

N2-SOP-6 N 2 b-.

P TS (SRO) (SRO) MCC 302 Feeder Breaker to ICSMOV128 RClC Steam Line Containment Isolation Valve trips open. Prevents isolation valve from closing on subsequent steam leak.

Page 5 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) Scenario Outline Final Submittal Final Submittal Wednesday, April 20.2005

NRC EXAM 8 RCI 2 IMO RClC Steam Leak into Reactor Building with Failure to isolate.

Automatic and manual attempts to isolate the RClC steam line will 25% 10 min be unsuccessful. Entry in EOP-SC is required and the reactor will ramp be manually scrammed. EHC Pump trip results in loss of Bypass RC11 Valve capability, if used to anticipate RPV Blowdown.

TCI 5A N2-EOP-RPV TC15B N2-EOP-SC

, _1 .

9 PC06 Reactor Building Ventilation System failure to isolate on high radiation level. Requires action to close Secondary Containment Isolation Dampers and manually start Standby Gas Treatment systems to terminate a potential ground level release pathway.

N2-OP-52 10 AD08C C (BOP) When Reactor Building temperatures exceed 212°F an RPV Blowdown is required. ADSlSRV PSV 126 fails to open during RPV Blowdown due to Loss of N2supply. Requires operator action to open an additional SRV to obtain the number directed by EOP-c2 N2-EOP-C2

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I Facilitv: Nine Mile Point 2 Scenario No.: NRC-03 OD-Test No.: NRC-01 I I TARGET QUANTITATIVE AlTRIBUTES fPER SCENARIO: SEE SECTION D.5.d)

I ACTUAL ATTRIBUTES I

I 1. Total malfunctions (5-8)

Events 2.3.6.7.9.10

2. Malfunctions after EOP entry (1-2) 6 2

Events 8.10 I 3. Abnormal events (2-4) I 2 I

4. Major transients (1-2) 1 Event 8
5. EOPs enteredlrequiring substantive actions (1-2) 2 Event 8 EOP-RPV. EOP-SC I

I

6. EOP contingencies requiring substantive actions (0-2)

Event 10 EOP-C2 7 . Critical tasks (2-3)

II 1 3

II Page 6 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) Scenario Outline Final Submittal Final Submittal Wednesday, April 20.2005

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