ML051570306

Final - Outlines (Folder 3)

ML051570306
Person / Time
Site:	Nine Mile Point
Issue date:	04/06/2005
From:	Godley R Constellation Energy Group
To:	Todd Fish Operations Branch I
Conte R
References
Download: ML051570306 (35)

Text

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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 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 9

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) 0 3

3.6 1

EK2 03 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following: Reactor water level indicabon strategies.

X 2.4.6 Knowledge symptom based EOP mitigabon 3.1 1

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

F o

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ES-401-1 E/APE # / Name / Safety Function WA Topic@)

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

1 3.6 3.2 4.2 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 RO 02 295003 Partial or Complete Loss of AC / 6 RO 03 AA2.06 Ability to determine and/or interpret the followng as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Nuclear boiler Instrumentation.

AA1.02 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Emergency generators.

295004 Partial or Total Loss of DC Pwr I 6 RO 04 i

3.8 3.1 AA1.02 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Systems necessary to assure safe plant shutdown AA1.01 Ability to operate andlor monitor the following as they apply to MAIN TURBINE GENERATOR TRIP: Recirculation system.

295005 Main Turbine Generator Trip / 3 RO 05 295006 SCRAM / 1 RO 06 3.8 AK2.02 Knowledge of the interrelations between SCRAM and the following: Reactor water level control system.

295016 Control Room Abandonment / 7 RO 07 4.4 3.5 AK2.01 Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following: Remote shutdown panel.

AK1.01 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on componenVsystem operations.

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295018 Partial or Total Loss of CCW / 8 RO 08 295019 Partial or Total Loss of Inst. Air / 8 RO 09 T

AK2.03 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: Reactor feedwater.

AA1.04 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING: Alternate heat removal methods.

295021 Loss of Shutdown Cooling / 4 RO 10 295023 Refueling Acc Cooling Mode / 8 RO 11 AK1.01 Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS: Radiation exposure hazards.

2.1.32 Ability to explain and apply system limits and precautions.

X 295024 High Drywell Pressure / 5 RO 12 295025 High Reactor Pressure 13 RO 13 0

1 EA2.01 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor pressure.

1 4.3 295026 Suppression Pool High Water Temp.

/ 5 R014 I 3.4 I x 2.2.22 Knowledge of limiting condibons for I I I I I I operaeons and safety limits 295028 High D w e l l Temperature / 5 RO 15

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295030 Low Suppression Pool Wtr Lvl I 5 RO 16

295031 Reactor Low Water Level I 2 RO 17 EA2.03 Ability to determine andlor interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC tank level.

I I I I 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown 11 R 0 1 8 4.3 1

I I I I 295038 High Off-site Release Rate I 9 RO 19 600000 Plant Fire On Site I 8 RO 20 WA Category Totals:

a I 0

4 3

4 1

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UNIT 2 NRC (RO)

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.

EA2.04 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling.

2.8 1

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EA1.01 Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE: Stack-gas monitoring system.

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)

ElAPE # I Name / Safety Function ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)

K K

K A

A G

1 2

3 1

2 AK2.02 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following: Drywell cooling.

AK3.01 Knowledge of the reasons for the following responses as they apply to INADVERTENT REACTIVITY ADDITION: Reactor SCRAM.

AK1.O1 Knowledge of the operational implicabons of the following concepts as they apply to INCOMPLETE SCRAM: Shutdown margin.

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

295009 Low Reactor Water Level I 2 295012 High Drywell Temperature I 5 RO 22 3.6 1

4.1 1

3.6 1

3.9 1

295014 Inadvertent Reacbvity Addition I 1 1 R023 RO 27 WA Category Point Totals:

I I

I I

295015 IncomDlete SCRAM I 1 l o 1 I I I I RO 24 1

1 1

1 2

1 I l l I I I I 295022 Loss of CRD Pumps I 1 1 ~ 0 2 5 l l l l l l x I I I 1 PI 295033 High Secondary Containment Area Radiation Levels / 9 I RO26 I 295029 High Suppression Pool Water Level 1 1

1 I 0 I I

I l5 I I I 131 I PRI

• WA Topic@)

I 3.6 I AA2.02 Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL: Steam flowlfeed flow mismatch.

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EA2.01 Ability to determine andlor interpret the followng as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS Area 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) 1 :I:

System # / Name WA Topic(s) 1 1 1 203000 RHR/LPCI: Injection Mode RO 28 2.4.31 Knowledge of annunciators alarms and indications / and use of the response instructions.

3.3 K5.02 Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Valve operation.

205000 Shutdown Cooling RO 29 209001 LPCS RO 30 K4.07 Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) and/or interlocks which provide for the following:

Pump operability testing 2.8 1

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

3.8 1

1 1

209002 HPCS RO 32 A4.11 Ability to manually operate and/or monitor in the control room: System flow.

21 1000 SLC RO 33 I I 4.0 3.3 A3.06 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including: RWCU system isolation: Plant-Specific.

K5.02 Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM:

Specific logic arrangements.

I 212000 RPS RO 34 I I 215003 IRM K3.01 Knowledge of the effect that a loss or malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following: RPS.

2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

3.9 3.3 RO 35 z 7 - l 215004 Source Range Monitor Al.04 Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONlTORlLOCAL POWER RANGE MONITOR SYSTEM controls including:

SCRAM and rod block triD seboints.

1 4.1 1

217000 RClC RO 38 I I:

I 2'8 I '

K2.01 Knowledge of electrical power supplies to the following: Motor operated valves.

21 7000 RClC RO 39 3.9 c 4.2 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation.

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

223002 PCIS/Nuclear Steam Supply Shutoff RO 41 239002 SRVs 0

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UNIT 2 NRC (RO) 3.3 3.5 1

1 K4.08 Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM design feature(s) and/or interlocks which provide for the following: tManual defeating of selected isolations during specified emergency conditions.

K1.03 Knowledge of the physical connections and/or cause effect relationships between RELlEFlSAFETY VALVES and the following:

Nuclear boiler instrument system

/NUCLEAR STEAM SUPPLY SHUT-OFF RO 42 1 3 A1.04 Ability to predict and/or monitor changes in parameters associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including:

Reactor water level control controller indications 3.6 3.3 1

1 259002 Reactor Water Level Control RO 43 K6.02 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM: AC power.

259002 Reactor Water Level Control RO 44 261 000 SGTS RO 45 A2.05 Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fan trips.

3.0 3.9 2.8 3.2 1

1 1

A2.03 Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of off-site power.

(Repeat WA, 2000 NRC RO Written exam).

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

(Repeat WA, 2002 NRC RO Written exam).

262001 AC Electrical Distribution RO 46 7 262002 UPS (ACIDC) 263000 DC Electrical Distribution RO 48 1

A3.01 Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, and indicating Lights.

264000 EDGs RO 49 4.0 3.0 1

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

264000 EDGs RO 50 A1 01 Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEL/JET) controls including Lube Oil Temperature 1

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

300000 Instrument Air RO 51 2.8 Al.04 Ability to predict and / or monitor changes in parameters associated with operating the CCWS controls including: Surge Tank Level 400000 Component Cooling Water RO 52 400000 Component Cooling Water RO 53 1

K/A Category Point Totals:

I 2 I UNIT 2 NRC (RO)

K3.02 Knowledge of the effect that a loss or malfunction of the INSTRUMENT AIR SYSTEM will have on the following: Systems having pneumatic valves and controls.

K6.05 Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: Pumps.

1 1

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)

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K/A Topic(s)

ES-401 BWR Examination Outline Form ES-401-1

'ier ZGroup 2 (RO)

Plant S, ems -

IR -

3.2 3.2 3.1 3.3 3.1 2.9 3.3 2.9 3.9 2.5 System # / Name 1

A 4 -

G -

K K

k 3

4 5

0 4

0 2

201001 CRD Hydraulic RO 54 A2.07Ability to (a) predict the impacts of the following on the CONTROL ROD 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.

1 201 002 RMCS RO 55 K1.01 Knowledge of the physical connections and/or cause-effect relationships REACTOR MANUAL CONTROL SYSTEM and the following:

Control rod hydraulic system 1

1 201006 RWM RO 56 K1.04 Knowledge of the physical connections and/or cause effect relationships between ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) and the following: Steam Flow/Reactor Power 202001 Recirculation RO 57 1

1 K6.07 Knowledge of the effect that a loss or malfunction of the following will have on the RECIRCULATION SYSTEM:

Feedwater flow.

K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the TRAVERSING IN-CORE PROBE:

Primary containment isolation svstem.

215001 TIP RO 58 21 9000 RHRILPCI: ToruslPool Cooling Mode RO 59 1

1 1

1 -

1 K5.04 Knowledge of the operational implications of the following concepts as they apply to RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE: Heat exchanger operation.

K4.02 Knowledge of FUEL HANDLING EQUIPMENT design feature(s) and/or interlocks which provide for the following:

Prevention of control rod movement during core alterations.

A4.18 Ability to manually operate and/or monitor in the control room: Turbine shell warming 234000 Fuel Handling Equipment RO 60 241 000 Reactorrurbine Pressure Regulator RO 61 271000 Offgas RO 62 2.1.23 Ability to perform specific system and integrated plant procedures during I different modes of olant oDeration 272000 Radiation Monitoring RO 63 1 1 K2.03 Knowledge of electrical power supplies to the following: Stack gas I

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 CONTAINMENT will have on the following. Off-site radioacbve release or malfuncbon of SECONDARY CONTAINMENT will have on the following. Off-site radioacbve release changes in parameters associated with operating the CONTROL ROOM HVAC controls including Control Room 290003 Control Room HVAC RO 65 4

changes in parameters associated with 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)

KIA #

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 Topic RO SRO IR IR Category

.25

1.

Conduct of Operations

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

RO 68

2.

Equipment Control Subtotal 2.2.12 Knowledge of surveillance procedures.

(Repeat KIA, 2002 NRC RO Written Exam) RO 69

3.

3 3.0 1

Radiation Control 2.2.22

4.

Emergen cy Procedures /

Plan

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Knowledge of limiting conditions for operation 3.4 1

and safety limits. RO 71 Subtotal 2.3.4 Knowledge of radiation exposure limits and 2.5 contamination control / including permissible levels in excess of those authorized. RO 72 2.3.10 Ability to perform procedures to reduce 2.9 excessive levels of radiation and guard against personnel exposure. RO 73 Knowledge of conduct of operations requirements. RO 66 3

1 1

I I

I Subtotal 2.4.20 2.4.39 Subtotal Knowledge of operational implications of EOP warnings / cautions / and notes. RO 74 emergency plan implementation. RO 75 Knowledge of the RO's responsibilities in Knowledge of how to conduct and verify valve lineups. RO 67 2

3 3 1

3.3 1

2 2.2.13 Knowledge of tagging and clearance 1 procedures. RO 70 I 3.6 I I

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 T l G l T1 G1 T1G1 295024 2.1.28 295026 2.1.za 295030 2.1.14 Rejected based on low cognitive level and low difficulty level.

Rejected based on low cognitive level and low difficulty level.

Rejected based on those reports limited to the RO and not the SRO are better T1 G2 T2G1 T2G1 I Facility Outline Review evaluated during the simulator scenarios. SRO internal and external reporting might be appropriate for the written examination.

Rejected based on tech spec bases are SRO only level knowledge.

Rejected based on WA importance rating <2.5.

NONE NONE 215004 2.2.25 264000 Al.07, Al.08.

A1 07 T1 G1 T2G1 T2G2 295004 2.1.2 259002 A2.01 202001 A2.10. K4.11 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)

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

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 ES 401, Page 1 of 1 T2G2 T2G2 T1G2 T2G2 T2G1 2005 U2 Test 2 (NRC) - RO Written Record of Rejected KAs Wednesday, April 20,2005 241000 A4.08 290001 A2.02 Replaced based on overlap with Operating Test JPM 6. Randomly selected from the A4 topic area A4.18 (RO

61)

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)

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)

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

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

Randomly selected new KA Al.04 (RO 53) 295035 2 4.31 201002 2.1.2 400000 Al.03

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.*

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.

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the WA 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 Function 295003 Partial or Total Loss of A C / 6 SRO 01 295016 Control Room Abandonment / 7 SRO 02 295020 Inadvertent Containment Isolation SRO 03 295031 Reactor Low Water Level I 2 SRO 04 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown /

1 SRO 05 295038 High Off-site Release Rate I 9 SRO 06 600000 Plant Fire On Site / 8 SRO 07 KIA Category Totals:

K/A Topic(s) 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

AA2.02 Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT:

Reactor water level.

AA2.02 Ability to determine and/or interpret the following as they apply to INADVERTENT CONTAINMENT ISOLATION: Drywell/containment tem pe ra t u re.

2.4.6 Knowledge symptom based EOP mitigation strategies.

EA2.01 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

Reactor power.

EA2.03 Ability to determine and/or interpret the following as they apply to tRadiation levels.

2.1.14 Knowledge of system status criteria which require the notification of plant personnel.

HIGH OFF-SITE RELEASE RATE:

Group Point Total:

IR 3.7 -

4.3 3.4 4.0 4.3 4.3 3.3 1 -

1 1

1 1

1 1

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

E/APE # / Name / Safety Function 0

3 1

295007 High Reactor Pressure 113 EA2.01 Ability to determine and/or 3.9 1

interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area radiation levels.

2 Group Point Total:

3 I SRO08 H I /

295014 Inadvertent Reactivity Addition / 1 SRO 09 295033 High Secondary Containment Area Radiation Levels / 5 SRO 10 1 KIA Category Point Totals:

Io1 01 01 c

/ I R / #

KIA Topic(s)

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2.2.22 Knowledge of limiting for operation and safety limits.

2.1.32 Ability to explain and apply system limits and precautions.

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-40 1 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)

System ## / Name

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209002 HPCS SRO I 1 212000 RPS SRO 12 215004 Source Range Monitor SRO 13 223002 PCIS/Nuclear Steam Supply Shutoff SRO 14 262001 AC Electrical Distribution SRO 15 K/A Category Point Totals:

WA Topic(s) 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.

2.2.22 Knowledge of limiting conditions for operations and safety limits.

A2.02 Ability to (a) pred.ict the impacts of the following on the SOURCE RANGE MONITOR (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.

A2.08 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

tSurveillance testing.

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

STEAM SUPPLY SHUT-OFF; Group Point Total:

IR 3.6 -

4.1 3.7 3.1 3.6 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 Plant System # / Name 201006 RWM SRO 16

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21 6000 Nuclear Boiler Inst.

SRO 17 234000 Fuel Handling Equipment SRO 18 KIA Category Point Totals:

BWR Examination Outline

{stems - Tier 2/Gm I 2 (SRO)

Form ES-401-1 K/A Topic(s)

A2.05 Ability to (a) predict the impacts of the following on the ROD WORTH MINIMIZER SYSTEM ; and (b) based on those predict ions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Out of sequence rod movement.

2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

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

Group Point Total:

IR 3.5 -

3.7 3.7 ES 401, Page 5 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, April 20,2005

IR 2.2.24 2.2.29 Ability to analyze the affect of maintenance activities on LCO status.

SR021 Knowledge of SRO fuel handling responsibilities.

SRO 22 2.3.9 Knowledge of the process for performing a containment purge. SRO 23 2.4.38 Ability to take actions called for in the facility emergency plan / including (if required) supporting or acting as emergency coordinator. SRO 24

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UNIT 2 NRC (SRO)

ES-40 1 Generic Knowledge and Abilities Outline (Tier 3)

F O S ~

ES-401-3 Facility:

Nine Mile Point Unit 2 Date of Exam: May 9,2005 Category WA #

Topic RO SRO-Only IR

1.

Conduct of 0 pe ra t i o n s 2.1.1 1 Knowledge of less than one hour technical specification action statements for systems.

(Evaluate LCO 3.0.3)

SRO 19 Ability to maintain primary and secondary plant chemistry within allowable limits.

SRO 20 3.8 2.9 2.1.34

2.

Equipment Control 3.8 3.8 2

3.

Radiation Control 1

3.4 1

1 4.0

4.

Eme rg ency Procedures /

Plan 2.4.41 Knowledge of action level thresholds and 1 classifications. SRO 25 1

4.1 Subtotal 2

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

Facility:

Nine Mile Point Unit 2 1

T l G l NA 295027 High Containment Temperature. Not applicable to facility.

T1 G2 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 UNIT 2 NRC (SRO)

Date of Exam: May 9, 2005 T l G l T l G l T1G2 T1 G2 T3 T3 T3 T3 ES-401 Record of Rejected WAS (SRO)

Form ES-401-4 I Tier / Group I Randomly Selected K/A 1 Reason for Rejection I

600000 2.4.31 60000 2.1.23 295014 2.1.2 295014 2.4.50 2.4.31 2.4.25 2.4.40 2.4.44 Rejected based on this KIA not linked to 10CFR55.43.

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

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

Rejected based on this WA not linked to 1 OCFR55.43.

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

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.

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

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 5

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:

T1G1 T3 Changes made T3 295024 AA2.02 2.3.4 as a result of NRC review of drafl exam submittal 2.3.10 Replaced KA. unable to write an acceptable discriminating question at SRO level.

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

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

Replaced KA. unable to write an acceptable discriminating question at SRO level.

Randomly selected new KA 2.3.9 (SRO 23)

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:

1 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.

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 xamination Level (circle one): RO Date of Examination: May 2, 2005 Operating Test Number: NRC-01 Code*

i Type 4dm in istrat ive Topic Conduct of Operations Logs RO ADMIN 1 Conduct of Operations Shift Turnover RO ADMIN 2 Equipment Control Use of Piping md Instrument Drawings RO ADMIN3 Radiation Control RO ADMIN 4 N

N N

N Describe activity to be performed EVALUATE SHIFT LOG READING DATA.

Given control room instrument readings for various daily checks required by Technical Specifications enter the instrument readings into the 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 REVIEW SHIFT TURNOVER DOCUMENTS.

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

2.1.3 (3.0) Knowledge of shift turnover practices.

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

Determine appropriate EOP support procedure to be used, then trace through various station electrical drawings (GE prints and ESK's) to identify components and describe how and why procedure 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 RADIOLOGICAL REQUIREMENTS RELATED TO OPERATOR INSPECTION OF HIGH RAD AREAS.

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 (I 3 for ROs; 5 4 for SROs & retakes)

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

(P)revious 2 exams (I 1; 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

!xamination Level (circle one): SRO Date of Examination: May 2, 2005 Operating Test Number: NRC-01 Administrative Topic Conduct of Operations SRO ADMIN 1 Conduct of Operations SRO ADMIN 2 Equipment Control SRO ADMIN 3 Radiation Control SRO ADMIN 4 Emergency Plan SRO ADMIN 5 (5-1, 5-2, 5-3)

Type Code*

N N

Describe activity to be performed DETERMINE REQUIRED ACTIONS FOR RClC ROOM UNIT COOLERS OUT OF SERVICE DURING PLANT STARTUP.

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 DETERMINATION OF REACTIVITY EVENT SEVERITY LEVEL AND SUPPORTING ACTIONS IN RESPONSE TO THE EVENT.

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 REVIEW SURVEILLANCE DATA INCLUDING ACTIONS FOR UNSATISFACTORY CONDITIONS.

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 OFFSITE DOSE CALCALCULATON MANUAL (ODCM)

ASSESSMENT AND REPORTABILITY FOR RADIOLOGICAL 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 1 OCFR20 and related facility radiation control requirements.

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

Based on events that occurred within SRO Simulator Scenario as SRO, classify the emergency event. May be performed post scenario or as 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 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only I the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol Room (D)irect from bank (5 3 for ROs; I 4 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 Anril70 713135

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

a. JPM 1 DOWNSHIFT REACTOR RECIRC PUMPS System:

RCS Procedure N2-OP-29 G. 1.O KA:

202001 A4.01 3.7/3.7 Task:

202-91 5-01-01

b. JPM 2 RClC INJECTION WITH OSCILLATIONS After manually starting RCIC, malfunctioning flow controller requires placing controller in manual to establish rated system flow.

System:

RClC Procedure: N2-OP-35 F.2.0 KA:

217000 A2.10 2.9/3.0 JPM Bank: 02-OPS-SJE-217-2-05 Task:

21 7-003-01 -01

c. JPM 3 RESTORE SHUTDOWN COOLING FOLLOWING PLANNED SHUTDOWN After starting RHS pump, failure of throttle valve results in inability to establish proper system flow, requires pump trip.

System:

SDCIRHS Procedure: N2-OP-31 H.4.0 KA :

205000 A2.12 2.9/3.0 JPM Bank: 02-OPS-SJE-205-2-11 Task:

205-003-01 -01

d. JPM 4 INITIATE CONTAINMENT VENTING TO SBGT UNDER ACCIDENT CONDITIONS System:

GTS Procedure N2-OP-61A H. l.O KA:

223001 A2.07 4.2/4.1 JPM Bank: 02-OPS-SJE-261-2-02

e. JPM 5 ENERGIZE RESERVE STATION TRANSFORMER FROM LINE 6 and ENERGIZE NPS-SWG003 FROM RESERVE STATION TRANSFORMER 1B System:

NPS Procedure N2-SOP3 Attachments 6 & 7 KA:

262001 A4.01 3.4/3.7 Task:

200-942-05-01 (PRA)

Task:

200-035-05-01 (PRA)

Type Code*

S. N S, D, A. P Randomly selected from previous 2 exams (2002)

S. D, E, ESF S. N Safety Function 1

REACTIVITY CONTROL 2

REACTOR WATER INVENTORY CONTROL 4

HEAT REMOVAL FROM REACTOR CORE 5

CONTAINMENT INTEGRITY 6

ELECTRICAL Page 1 of 3 NUREG-1 021, 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 Examination Level (circle one): RO Date of Examination: May 2, 2005 Operating Test Number: NRC-01 Control Room Systems@ 8 for RO System / JPM Title

f. JPM 6 PERFORM TURBINE CONTROL VALVE (CV2 and 3)

SURVEILLANCE 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

g. JPM 7 SHIFT INSTRUMENT AIR COMPRESSORS Compressor trip during swap requires entry into N2-SOP-19 and manual start of another air compressor.

System:

IAS Procedure: N2-OP-19 F.2.0; N2-SOP-19 KA:

295019 AA2.01 3.513.6 Task:

2 1 2-905-02-0 1 Task:

278-004-01 -01

h. JPM 8 MANUAL INITIATION OF CONTROL BUILDING SPECIAL FILTER TRAIN System:

HVC Procedure: N2-OP-53A KA:

295038 EA1.07 3.6/3.8 JPM Bank Task:

288-004-01 -01 NRC 2000 JPM J1-1 Type Code*

S, N. A D. S, P Randomly selected from previous 2 exams (2000)

Safety Function 7

INSTRUMENTS 8

PLANT SERVICE SYSTEMS 9

RADIOACTIVITY RELEASE 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 Examination Level (circle one): RO Date of Examination: May 2, 2005 Operating Test Number: NRC-07 Implant Systems@ 3 for RO System I JPM Title

i. JPM 9 VENT CONTROL ROD OVERPISTON VOLUME.

System:

RDS Procedure: N2-EOP-6 Attachment 14 KA:

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

200-962-05-01

j. JPM 10 ALIGN FIRE WATER SYSTEM TO INJECT TO RHR System:

RHS Procedure: N2-EOP-6 Attachment 6 KA:

295031 EA1.08 3.813.9 JPM Bank: 02-NLO-PJE-205-2-02(04)

A(B).

Task:

200-930-05-01

k. JPM 1 I LOCAL START OF DIVISION I DIESEL GENERATOR WITH EMERGENCY STOP.

System:

ENS Procedure: N2-OP-1 OOA KA:

264000 G2.1.30 3.913.4 Task:

264-908-04-01 Type Code*

D, E, R, P Randomly selected from previous 2 exams (1999)

Safety Function 1

REACTIVITY CONTROL 2

RX WATER INVENTORY CONTROL 6

ELECTRICAL

@ 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... I 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 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 ixamination Level (circle one): SRO-lnsfanfs Operating Test Number: NRC-07 Date of Examination: May 2, 2005

ontrol Room Systems@ 7 for SRO-I System / JPM Title

. JPM 1 DOWNSHIFT REACTOR RECIRC PUMPS System:

RCS Procedure N2-OP-29 G. l.O KA:

202001 A4.01 3.7/3.7 Task:

202-91 5-01-01

. JPM 2 RClC INJECTION WITH OSCILLATIONS After manually starting RCIC, malfunctioning flow controller requires placing controller in manual to establish rated system flow.

System:

RClC Procedure: N2-OP-35 F.2.0 KA:

217000 A2.10 2.9/3.0 JPM Bank: 02-OPS-SJE-217-2-05 Task:

21 7-003-01 -01

. JPM 3 RESTORE SHUTDOWN COOLING FOLLOWING PLANNED SHUTDOWN After starting RHS pump, failure of throttle valve results in inability to establish proper system flow, requires pump trip.

System:

SDC/RHS Procedure: N2-OP-31 H.4.0 KA:

205000 A2.12 2.9/3.0 JPM Bank: 02-OPS-SJE-205-2-11 Task:

205-003-01 -01

. JPM 4 INITIATE CONTAINMENT VENTING TO SBGT UNDER ACCIDENT CON DIT1 ONS System:

GTS Procedure N2-OP-61 A H. 1.O KA:

223001 A2.07 4.2/4.1 JPM Bank: 02-OPS-SJE-261-2-02 Task:

200-942-05-01 (PRA)

~~

~

~

JPM 5 ENERGIZE RESERVE STATION TRANSFORMER FROM LINE 6 and ENERGIZE NPS-SWG003 FROM RESERVE STATION TRANSFORMER 1 B System:

NPS Procedure N2-SOP3 Attachments 6 & 7 KA:

262001 A4.01 3.4/3.7 Task:

200-035-05-01 (PRA)

Type Code*

S. N Randomly selected from previous 2 exams (2002)

S, D, E. ESF Safety Function 1

REACTIVITY CONTROL 2

REACTOR WATER INVENTORY CONTROL 4

HEAT REMOVAL FROM REACTOR CORE 5

CONTAINMENT INTEGRITY 6

ELECTRICAL 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 Examination Level (circle one): SRO-lnstants Date of Examination: May 2, 2005 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 SU RVEl LLAN C E During testing CV3 will fail to generate the required RPS channel trip, requires inserting a YZ scram signal in associated trip system.

System:

EHC/RPS Procedure: N2-OSP-RPS-Q001 ; N2-SOP-97 KA:

212000 A2.03 3.93.5 Task:

21 2-905-02-01 INSTRUMENTS 8

PLANT SERVICE SYSTEMS g JPM 7 SHIFT INSTRUMENT AIR COMPRESSORS Compressor trip during swap requires entry into N2-SOP-19 and manual start of another air compressor 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 Examination Level (circle one): SRO-lnstants Date of Examination: May 2, 2005 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.

System:

RDS Procedure: N2-EOP-6 Attachment 14 KA:

29501 5 AA1.01 3.813.9 JPM Bank: 02-OPS-PJE-200-2-69 REACTIVITY selected from

Task, 200-962-05-01 RX WATER INVENTORY System:

RHS Procedure: N2-EOP-6 Attachment 6 KA:

295031 EA1.08 3.813.9 JPM Bank: 02-NLO-PJE-205-2-02 Task:

200-930-05-0 1 ELECTRICAL System:

ENS Procedure: N2-OP-1 OOA 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 Examination Level (circle one): SRO-Upgrades Date of Examination: May 2, 2005 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 System:

RCS Procedure N2-OP-29 G.l.O KA:

202001 A4.01 3.713.7 Task:

202-91 5-01 -01 S. N 1

REACTIVIlY CONTROL

b. JPM 3 RESTORE SHUTDOWN COOLING FOLLOWING PLANNED SHUTDOWN After starting RHS pump, failure of throttle valve results in inability to establish proper system flow, requires pump trip.

System:

SDC/RHS Procedure: N2-OP-31 H.4.0 KA:

205000 A2.12 2.9/3.0 JPM Bank: 02-OPS-SJE-205-2-11 Task:

205-003-01 -01 4

HEAT REMOVAL FROM REACTOR CORE CONTAINMENT INTEGRITY ACCIDENT CONDITIONS System:

GTS Procedure N2-OP-61A H.l.O UA:

223001 A2.07 4.2/4.1 Task:

200-942-05-01 (PRA)

Procedure: N2-EOP-6 Attachment 6 Task:

200-930-05-01 WITH EMERGENCY STOP.

System:

ENS Procedure: N2-OP-1 OOA KA:

264000 G2.1.30 3.9/3.4 Task:

264-908-04-01 RX WATER INVENTORY CONTROL ELECTRICAL 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

Appendix D Scenario Outline NRC EXAM Form ES-D-1 i

Facility: Nine Mile Point 2 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 Scenario No.: NRC-01 Op-Test No.: NRC-01 Event No.

1 2

3 6

Malf. No.

RR08B FW03A RR31 RR30 Switch S4A-A P628-022C-TU02 9%

and MCOl 15%,

Ramp Time 3 minutes Event Type*

Event DescriDtion NZ-SOP-34 Stuck Open SRV Condenser air in-leakage results in a slight drop in vacuum.

Because of the rising turbine vibration, the crew will insert a manual reactor scram and trip the main turbine 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

7 MCO1@

M (Major 100%

event Ramp continued Time %

but not minutes counted)

TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION D.5.d)

1. Total malfunctions (5-8)

Events 2,3,4.5,8,9 Events 9.10

2. Malfunctions afler EOP entry (1-2)

RP12A C (BOP)

RP12B C (SRO)

ACTUAL ATTRIBUTES 6

2 1

FWOIA C(ALL) 3 Abnormal events (2-4) 4 Major transients (1 -2)

Event 4 SOP -6, Event 5 SOP-34 Event 6 (and 7 only counted once) 5 Event 6 and 7 EOP-RPV, EOP-PC 6

Event 8 EOP-C5, Event 10 EOP62 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 CT4.0 Fully insert control rods EOPs entered/requiring substantive acbons (1-2)

EOP conbngenctes requiring substantive achons (0-2) 7 Critical tasks (2-3)

MSCRWL (-39 inches)

FWOI B FWOIC 2

1 2

2 4

NRC EXAM Loss of main condenser vacuum. The degrading vibration causes a main condenser vacuum leak that degrades rapidly once the reactor is scrammed and results in automatic closure of MSIVs.

The loss of the main condenser as a heat sink requires manual 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 rods fail to insert due to hydraulic lock. Reactor power will lower to 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 N2-EOP-6 Attachment 14 N 2-EOP-C5 initiate and WCS to isolate when SLC is manually initiated.

capability after terminate and prevent injection is performed. The 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 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 c, R, TS (SRO)

( A ~ ~ )

Facility. Nine Mile Point 2 Scenario No.: NRC-02 Op-Test No. NRC-01 Examiners:

Operators:

Initial Conditions: Simulator IC-20

1.

2.

Division I Low Pressure ECCS systems CSL and RHS are inoperable for maintenance.

100% Power Rod Line >loo% (106%)

Malf. No.

leakage requires removal from service and isolation of RCS Pump A to stop the leak. (TS 3.4.1 )

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

With inoperable OPRMs additional actions are required to monitor for power oscillations while in the Heightened Awareness Zone.

N2-SOP-29. I, Reactor Recirc Pump Seal Failure N2-SOP-29, Sudden Reduction In Core Flow

@.25 1 min ramp RRl6A

@.75 1 min I

I ramp 5

RD063419 RD062227 ED02A DG04A CS03 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 1

TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION D.5.d)

1. Total malfunctions (5-8)

Event! 2 3 4 5 7 all feedwater and loss of all normal station power except Emergency Bus supplied by the operating DGs.

I (Bop) I ACTUAL ATTRIBUTES 5

I 3.1.1

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

3. Abnormal events (2-4)

Event 2 SOP-29.1 and SOP-29. Event 3 SOP-30 Event 4 SOP-3

4. Major transients (1-2)

Event 5

5. EOPs enteredkequiring substantive actions (1-2)

Event 5 EOP-RPV. EOP-PC Facilitv: Nine Mile Point 2 Scenario No.: NRC-02 Op-Test No.: NRC-01 3

1 2

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

Event 9 EOP-C2

7. Critical tasks (2-3)

CRITICAL TASK DESCRIPTIONS:

~~

2. Malfunctionsafter EOP entry (1-2)

Events 7.8' 1

2 2

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

CT-2.0: Restore and maintain RPV water level above 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 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-101 A; 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.

Scenario No.: NRC-03 Op-Test No.: NRC-01 Event Malf. No. +

I Event I

Event Type*

R (ATCI R {SRO)

Description Withdraw control rods raise reactor power to above 5%. Several control rods must be withdrawn to raise power to clear the APRM downscale condition.

N2-OP-101 A 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.

Tech Spec 3.7.1 N2-OP-11 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 N2bP-3 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

8

4. Major transients (1-2) 9 1

10 Event 8 Event 8 EOP-RPV. EOP-SC

5. EOPs enteredlrequiring substantive actions (1-2)

RCI 2 min ramp RC11 TCI 5A TC15B 25% 10 2

_1.

PC06 AD08C IMO C (BOP)

NRC EXAM RClC Steam Leak into Reactor Building with Failure to isolate.

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

N2-EOP-RPV N2-EOP-SC 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 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 N2 supply. Requires operator action to open an additional SRV to obtain the number directed by EOP-c 2 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

1. Total malfunctions (5-8)

I Events 2.3.6.7.9.10 6

2. Malfunctions after EOP entry (1-2)

Events 8.10 2

I 3. Abnormal events (2-4)

I 2

I I

1 I

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

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

I 3

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