ML051320135

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Draft - Outlines (Folder 2)
ML051320135
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/16/2005
From: Godley R
Constellation Energy Group
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
ES-401, ES-401-1
Download: ML051320135 (37)
v • d • e


Text

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 Tier 1.

E m ergency

& Abnormal Plant Evolutions 2.

Plant Systems 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 k1 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 K/A 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 K/As that are linked to 10 CFR ES401, Page 1 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Drafl Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (RO)

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

E/APE # / Name / Safety Function 3.6 RO 01 295001 Partial or Complete Loss of Forced 3.2 Core Flow Circulation / 1 & 4 RO 02 295003 Partial or Complete Loss of AC / 6 RO 03 295004 Partial or Total Loss of DC Pwr I 6 AA1.02 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Emergency generators.

AA1.02 Ability to operate and/or monitor the I 4.2 3.8 1

1 following as they apply to PARTIAL OR COMPLETE RO 04 LOSS OF D.C. POWER: Systems necessary to assure safe Dlant shutdown 295005 Main Turbine Generator Trip I 3 AA1.01 Ability to operate andlor monitor the 3.1 following as they apply to MAIN TURBINE GENERATOR TRIP: Recirculation system.

AK2.02 Knowledge of the interrelations between 3.8 RO 06 295016 Control Room Abandonment / 7 I 121 I I I I SCRAM and the following Reactor water level control system. I I I AK2.01 Knowledge of the interrelations between 4.4 I CONTROL ROOM ABANDONMENT and the RO 07 following: Remote shutdown panel.

295018 Partial or Total Loss of CCW / 8 AKI .01 Knowledge of the operational implications of 3.5 1 the following concepts as they apply to PARTIAL OR RO 08 COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on comoonenVsvstem oDerations.

295019 Partial or Total Loss of Inst. Air I 8 AK2.03 Knowledge of the interrelations between 3.2 1 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 3.7 1 following as they apply to LOSS OF SHUTDOWN RO 10 COOLING: Alternate heat removal methods.

295023 Refueling Acc Cooling Mode I 8 Knowledge of the operational implications of concepts as they apply to REFUELING 295025 High Reactor Pressure / 3 EA2.01 Ability to determine and/or interpret the following as they apply to HIGH REACTOR RO 13 PRESSURE. Reactor Dressure ppression Pool High Water Temp.

RO 15 ES 401, Page 2 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (RO) 295037 SCRAM Condition Present and EA2 03 Ability to determine and/

Power Above APRM Downscale or Unknown 11 R 0 1 8 following as they apply to HIGH OFF-SITE RO 19 RELEASE RATE: Stack-gas monitoring system.

600000 Plant Fire On Site I 8 AK3.04 Knowledge of the re responses as they apply to PLANT FIRE ON SITE:

RO 20 Actions contained in the abnormal procedure for 20 ES401,Page3of10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, March 16.2005

UNIT 2 NRC (RO)

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

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

1 2 3 1 2

:  : Ill I 295009 Low Reactor Water Level / 2 AA2.02 Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER RO 21 LEVEL: Steam flowlfeed flow mismatch. 3.6 1 295012 High Drywell Temperature / 5 nowledge of the interrelations between HIGH 3.6 1 L TEMPERATURE and the following. Drywell 295014 Inadvertent Reactivity Addition / 1 4.1 1 295015 Incomplete SCRAM I 1 perational implications of 3.6 1 ey apply to INCOMPLETE RO 24 Ill 295022 Loss of CRD Pumps / 1 3.9 1 RO 25

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295033 High Secondary Containment Area EA2.01 Ability to determine and/or interpret the 3.8 1 Radiation Levels / 9 following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS Area radiatron levels EA1.03 Ability to operate and/or monitor the following 2.9 1 as they apply to HIGH SUPPRESSION POOL WATER LEVEL RHRlLPCl ES 401, Page 4 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (RO)

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

WA Topic@) IR #

2.4.31 Knowledge of annunciators alarms and 3.3 1 indications I and use of the response instructions.

K5.02 Knowledge of the operational 2.8 1 implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Valve operation.

K4.07 Knowledge of LOW PRESSURE CORE 2.8 1 SPRAY SYSTEM design feature@) and/or interlocks which provide for the following:

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

A4.11 Ability to manually operate and/or 3.8 1 monitor in the control room: System flow.

A3.06 Ability to monitor automatic operations 4.0 1 of the STANDBY LIQUID CONTROL SYSTEM including: RWCU system isolation: Plant-Specific.

K5.02 Knowledge of the operational 3.3 1 implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM:

Specific logic arrangements.

K3.01 Knowledge of the effect that a loss or 3.9 1 malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following: RPS.

2.4.50 Ability to verify system alarm setpoints 3.3 1 and operate controls identified in the alarm response manual.

A1.04 Ability to predict andlor monitor 4.1 1 changes in parameters associated with operating the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including:

SCRAM and rod block trip setpoints.

K2.01 Knowledge of electrical power supplies 2.8 1 to the following: Motor operated valves.

2.1.23 Ability to perform specific system and 3.9 1 integrated plant procedures during different modes of plant operation.

A4.02 Ability to manually operate and/or 4.2 1 monitor in the control room: ADS logic initiation ES 401, Page 5 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Drafl Submittal Drafl Exam Submittal Wednesday, March 16,2005

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

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

239002 SRVs K1.03 Knowledge of the physical connections and/or cause effect relationships between RO 42 RELIEF/SAFETY VALVES and the following:

Nuclear boiler instrument system 259002 Reactor Water Level Al.04 Ability to predict and/or monitor 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 Control malfunction of the following will have on the REACTOR WATER LEVEL CONTROL RO 44 SYSTEM: AC power.

261000 SGTS A2 05 Ability to (a) predict the impacts of the 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 Distribution following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those RO 46 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).

262002 UPS (ACIDC) AX01 Ability to monitor automatic operations of the UNINTERRUPTABLE POWER RO 47 I I SUPPLY (A.C./D.C.) including: Transfer from preferred to alternate source.

(Repeat KIA, 2002 NRC RO Written exam).

I1 263000 DC Electrical A3.01 Ability to monitor automatic operations Distribution of the D.C. ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, RO 48 and indicating Lights.

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

264000 EDGs Al.01 Ability to predict and/or monitor changes in parameters associated with RO 50 operating the EMERGENCY GENERATORS (DIESEL/JET) controls including: Lube Oil Temperatu re.

ES 401, Page 6 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (RO)

-- K3.02 Knowledge of the effect that a loss or 3.3 1 malfunction of the INSTRUMENT AIR SYSTEM will have on the following: Systems having pneumatic valves and controls.

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

3'0 Al.04 Ability to predict and / or monitor 2.8 1 changes in parameters associated with operating the CCWS controls including: Surge Tank Level Group Point Total: 1 26 ES401,Page7of10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (RO)

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

System # / Name WA Topic(s) IR 201001 CRD Hydraulic A2.07Ability to (a) predict the impacts of 3.2 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 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 FlowlReactor 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 system.

21 9000 RHR/LPCI: ToruslPool K5.04 Knowledge of the operational 2.9 1 Cooling Mode implications of the following concepts as they apply to RHRILPCI:

RO 59 TORUSlSUPPRESSlON POOL COOLING MODE: Heat exchanger operation.

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

Prevention of control rod movement during core alterations.

241000 Reactornurbine Pressure A4.18 Ability to manually operate and/or 2.9 Regulator monitor in the control room: Turbine shell warming RO 61 271000 Offgas 2.1.23 Ability to perform specific system 3.9 and integrated plant procedures during RO 62 different modes of plant operation.

272000 Radiation Monitoring K2.03 Knowledge of electrical 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, March 16,2005

UNIT 2 NRC (RO)

RO 64 RO 65 ES401,Page9of10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Drafl Submittal Drafl Exam Submittal Wednesday, March 16,2005

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UNIT 2 NRC (RO) is-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 I ES 401, Page 10 of 10 2005 U2 Test 2 (NRC) - RO Written Exam Outline All Tiers Draft Submittal Draft Exam Submittal Wednesday, March 16,2005

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UNIT 2 NRC (SRO)

ES-401 BWR Examination Outline Form ES-401-1 I 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 k1 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 I O CFR 55.43.

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ES 401, Page 1 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Drafl Exam Submittal Wednesday, March 16,2005

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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 WA Topic(s) IR Function 295003 Partial or Total Loss of 2.2.25 Knowledge of bases in 3.7 AC/6 technical specifications for limiting conditions for operations and safety SRO 01 limits.

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295016 Control Room AA2.02 Ability to determine and/or 4.3 Abandonment I 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 Containment Isolation interpret the following as they apply to INADVERTENT CONTAINMENT SRO 03 ISOLATlO N: DryweII/cont a inment temperature.

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

SRO 04 295037 SCRAM Condition EA2.01 Ability to determine and/or 4.3 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 andlor 4.3 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 criteria which require the notification SRO 07 of plant personnel.

WA Category Totals: Group Point Total:

ES 401, Page 2 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (SRO)

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

E/APE # / Name / Safety Function WA Topic(s) 2.2.22 Knowledge of limiting conditions I IR 4.1

/3 for operation and safety limits.

SRO 08 295014 Inadvertent Reactivity 2.1.32 Ability to explain and apply 3.8 Addition / I system limits and precautions.

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

K/A Category Point Totals: 0 ES 401, Page 3 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (SRO)

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 1 events related to system SRO 11 operationslstatus should be reported to outside agencies.

212000 RPS 2.2.22 Knowledge of limiting 4.1 1 conditions for operations and SRO 12 safety limits.

215004 Source Range A2.02 Ability to (a) predict the 3.7 1 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 PC IS/Nuclear A2.08 Ability to (a) predict the 3.1 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 A271 1 Ability to (a) predictthe 3.6 1 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 voltages. - -

K/A Category Point Group Point Total: 5 Totals:

ES 401, Page 4 of 6 2005 U2 Test 2 (NRC)- SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday. March 16,2005

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UNIT 2 NRC (SRO)

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

System # / Name I; WA Topic(s)

IR 201006 RWM I A2.05 Ability to (a) predict the impacts of the following on 3.5 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 rod movement.

21 6000 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 Totals: Io Group Point Total:

ES 401, Page 5 of 6 2005 U2 Test 2 (NRC) - SRO Written Exam Outline All Tiers Draft Exam Submittal Wednesday, March 16,2005

UNIT 2 NRC (SRO)

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FOUTI ES-401-3 Facility: Nine Mile Point Unit 2 Date of Exam: May 9,2005 Category K/A # Topic 2.1.1 1 Knowledge of less than one hour technical 1 1.

specification action statements for systems.

Conduct of (Evaluate LCO 3.0.3)

Operations SRO 19

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

SRO 20 Subtotal 2 2.2.24 Ability to analyze the affect of maintenance 1 2.

activities on LCO status.

Equipment Cont ro I SR021 2.2.29 Knowledge of SRO fuel handling 1 responsibilities.

SRO 22

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Subtotal 2 2.3.10 Ability to perform procedures to reduce 3.

excessive levels of radiation and guard Rad iat ion against personnel exposure. SRO 23 Control Subtotal 2.4.38 Ability to take actions called for in the facility 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 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, March 16,2005

UNIT 2 NRC (RO)

Facility: Nine Mile Point Unit 2 Date of Exam: May 9,2005 ES-40 1 Record of Rejected WAS (RO) Form ES-401-4 Tier / Group I Randomly Selected WA I Reason for Rejection Per ES-401, Attachment 1, #1: Review each group and delete those items [Emergency/AbnormalPlant 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:

TlGI NA 295027 High Containment Temperature. Not applicable to facility.

T1G2 NA 295011 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 design.

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

TlGl 295024 2.1.28 Rejected based on low cognitive level and low difficulty level.

TIGI 295026 2.1.28 Rejected based on low cognitive level and low difficulty level.

TlGl 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.

TI

. G7 .NONF._ .NONF.-

T2G1 1 215004 2.2.25 Rejected based on tech spec bases are SRO only level knowledge.

T2G1 264000 A I .07. A I .08. Rejected based on WA importance rating <2.5.

AI n7 Per ES-401 D.l .d: After completing the outline, check the selected WAS for balance of coverage within and across the three tiers.

Ensure that every applicable WA category is sampled at least twice within each of the three tiers.

NONE I NONE I NnNF T1 G I 295004 2.1.2 Rejected based on the Generic KA statement is not relevant to the applicable evolution 295004 Partialmotal loss of DC. Randomly selected new KA AA1.02 (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 overlapped Scenario 1 Event 3. Randomly selected K6.07 (RO 57)

Changes made during draft development afler outline submittal and NRC review. (2118105- 3118/05)

T2G2 241 000 A4.08 Replaced based on overlap with Operating Test JPM 6. Randomly selected from the A4 topic area A4.18 (RO 61)

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)

T1 G2 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 771 T2G2 I 201002 2.1.2 I Replaced. unable to develop an amrotxiate discriminatina auestion. The aeneric I statement does not fit the system. Randomly selected new KA K1.01 (RO55)

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

Randomly selected new KA A1 .Ob (RO 53).

ES 401, Page 1 of 1 2005 U2 Test 2 (NRC) - RO Written Record of Rejected KAs Wednesday, March 16,2005

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 Randomly Selected WA I Reason for Rejection Per ES-401, Attachment 1, # I : 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:

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

T I 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 T I G1 600000 2.4.31 Rejected based on this WA not linked to 10CFR55.43.

TIGI 60000 2.1.23 Rejected based on this WA not linked to 10CFR55.43.

T I G2 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 Reiected based on avoidina Dossible double ieoDardv and over samolino with Per ES-401 D . l .d: Afler completing the outline, check the selected WAS for balance of coverage within and across the three tiers.

Ensure that every applicable WA category is sampled at least twice within each of the three tiers.

NONE I NONE I NONE TlGI 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)

ES 401, Page 1 of 1 2005 U2 Test 2 (NRC) - SRO Written Record of Rejected KAs Draft Exam Submittal Wednesday, March 16,2005

ES-301 Administrative ToDics Outline Form ES-301-1

'acility: NINE MILE POINT 2 Date of Examination: May 2, 2005 Ixamination Level (circle one): RO Operating Test Number: NRC-01 Administrative Type Describe activity to be performed Topic Code*

Conduct of N EVALUATE SHIFT LOG READING DATA.

Operations 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 / a n d 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 RCIC/MAIN 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-CS; N2-EOP-6 Attachment 2 GE DWG 807El73TY SHEET3 and 9 ESK 8SPUO2; ESK lllCSO5 Radiation N RADIOL OGICAL REQUIREMENTS RELA TED TO OPERA TOR 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

?takingonly the administrative topics, when all 5 are required.

Type Codes 8, Criteria: (C)ontrol Room (D)irect from bank (I3 for ROs; I 4 for SROs 8, 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 Adrnistrative Topic Outline Draft Submittal Draft Submittal Wednnsdav March 16 3005

ES-30 1 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 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 RCIC 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 UNSA TISFACTORY 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(4.1) 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 table top discussion.

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

JOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only Page 2 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Modified Adrnistrative Topic Outline Draft Submittal Draft Submittal Wednendnv March Ifi 7005

ES-301 Administrative Topics Outline Form ES-301-1 1 the administrative topics, when all 5 are required. I

  • Type Codes & Criteria: (C)ontrol Room (D)irect from bank ( s 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)irnulator SRO Admin 2: Removed reference to KA 2.1.12 due to being not applicable to this test item.

Page 3 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Modified Admistrative Topic Outline Draft Submittal Draft Submittal Wednnsdav March 16 7clclfi

ES-301 Control RoomAn-Plant Svstems 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-Of Control Room Systems@(8 for RO; 7 for SRO-I; 3 for SRO-U shaded)

System / JPM Title Type Code* Safety Function

a. JPM IDOWNSHIFT REACTOR RECIRC PUMPS 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
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: 217-003-01-01 JPM Bank: 02-OPS-SJE-217-2-05
c. JPM 3 RESTORE SHUTDOWN COOLING FOLL- S . D. A, (SD) 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 d JPM 4 INITIATE CONTAINMENT VENTING TO SBGT UNDER S , D, E, ESF 5 ACCIDENT C0NDIT IONS 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 I

e. JPM 5 ENERGIZE RESERVE STATION TRANSFORMER S. N 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 (PRAI Page 1 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline RO Draft Submittal Wednesday, March 16,2005

Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): RO Operating Test Number: NRC-07 I Control Room Systems@(8 for RO; 7 for SRO-I; 3 for SRO-U shaded) I System / JPM Title Type Code* I Safety Function I f JPM 6 PERFORM TURBINE CONTROL VALVE (CV1)

SURVEILLANCE INSTRUMENTS During testing CV1will fail to generate the required RPS channel trip, requires inserting a % scram signal in associated trip system.

System. EHCIRPS Procedure. N2-OSP-RPS-QOOI ; N2-SOP-97 KA: 212000 A2.03 3.513.5 Task. 212-905-02-01

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

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 3.613.8 JPM Bank NRC 2000 JPM J1-I JPM Setup Plan A JPM 3 then JPM 7 single for each candidate (Short), if performing plant JPMs with 2 evaluators JPM 2 and 5Post Line Loss and shutdown JPM 4 and 6 Power operations JPM 1 and 8 40% Power JPM Setup Plan B JPM 1 and 7 40% power JPM 2 and 5Post Line Loss and shutdown JPM 3 and 8 Plant shutdown JPM 4 and 6 Power operations Page 2 of 3 NUREG-102 1, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline RO Draft Submittal Wednesday, March 16,2005

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

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

KA: 295015 AA1.01 3.8/3.9 JPM Bank: 02-OPS-PJE-200-2-69

j. JPM 10 ALIGN FIRE WATER SYSTEM TO INJECT TO RHR 2 RX WATER A@)* 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 11 PERFORM LOWER CONTROL BUILDING OPERATOR 6 IMMEDIATE ACTION PER N2-SOP-78, CONTROL ROOM ELECTRICAL EVACUAT10 N.

System: ENS Procedure: N2-SOP-78 Task: 296-904-01-04 KA: 295016 AA1.04 3.113.2 All control room (and in-plant) systems must be different and serve different safety 1 nctions; I

RO-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 3 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline RO Draft Submittal Wednesday, March 16,2005

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-Instants Operating Test Number: NRC-07 Control Room Systems@(8 for RO; 7 for SRO-I; 3 for SRO-U shaded)

System / JPM Title I Typecode*

Safety Function 1

REACTIVITY System, RCS CONTROL Procedure N2-OP-29 G.l 0 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) C0NT R0L System: RClC Procedure: N2-OP-35 F.2.0 KA: 217000 A2.10 2.9/3.0 Task: 2 17-003-01-01 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: 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 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 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-I 021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-I Draft Submittal Wednesday, March 16,2005

Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): SRO-Instants Operating Test Number: NRC-07 Control Room Systems@(8 for RO; 7 for SRO-I; 3 for SRO-U shaded) I System / JPM Title 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 JPM Setup Plan A JPM 3 then JPM 7 single for each candidate (Short), if performing plant JPMs with 2 eva Iuato rs JPM 2 and 5Post Line Loss and shutdown JPM 4 and 6 Power operations JPM 1 and 8 40% Power JPM Setup Pian B JPM 1 and 7 40% power JPM 2 and 5Post Line Loss and shutdown JPM 3 and 8 Plant shutdown JPM 4 and 6 Power operations Page 2 of 3 NUREG-I 021, Revision 9 2005 U2 Test 2 (NRC) - Sirn In plant JPM Outline SRO-I Draft Submittal Wednesday, March 16,2005

Facility: Nine Mile Point 2 Date of Examination: May 2, 2005 Examination Level (circle one): SRO-Instants Operating Test Number: NRC-07 In-Plant Systems@(3 for RO; 3 for SRO-I; 2 for SRO-U shaded) I System I JPM Title Safety Function I

h. 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: 295015 AA1.01 3.813.9 JPM Bank: 02-OPS-PJE-200-2-69

i. JPM 10 ALIGN FIRE WATER SYSTEM TO INJECT TO RHR 2 RX WATER A(Bh 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)
i. JPM 11 PERFORM LOWER CONTROL BUILDING OPERATOR N, A, E IMMEDIATE ACTION PER N2-SOP-78, CONTROL ROOM ELECTRICAL EVACUATION.

System: ENS Procedure: N2-SO P-78 Task: 296-904-01-04 KA: 295016 AA1.04 3.113.2

@ All control room (and in-plant) systems must be different and serve different safety RO-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 3 of 3 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-I Draft Submittal Wednesday, March 16,2005

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-01 Control Room Systems@(8 for RO; 7 for SRO-I; 3 for SRO-U shaded)

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.l .O KA: 202001 A4.01 3.7/3.7 Task: 202-915-01-01
b. JPM 3 RESTORE SHUTDOWN COOLING FOLLOWING S. D. A, (SD)' 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

~ ~ ~

c 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 d JPM 10 ALIGN FIRE WATER SYSTEM TO INJECT TO RHR A. 2 System RHS RX WATER INVENTORY Procedure N2-EOP-6 Attachment 6 CONTROL Task 200-930-05-01 KA 295031 EA1 08 3 813 9 JPM Bank: 02-NLO-PJE-205-2-02(04)

e. JPM 11 PERFORM LOWER CONTROL BUILDING OPERATOR 6 IMMEDIATE ACTION PER N2-SOP-78, CONTROL ROOM ELECTRICAL EVACUATION.

System: ENS Procedure: N2-SOP-78 Task: 296-904-01-04 KA: 295016 AA1.04 3.1/3.2 Page 1 of 2 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Sim In plant JPM Outline SRO-U Draft Submittal Wednesday, March 16,2005

SRO-U performs Simulator JPMs 1, 3, 4 and Plant JPMs IO,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 Draft Submittal Wednesday, March 16.2005

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. All OPRMs are inoperable
2. 100% 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

N (SRO) the High Pressure Core Spray System and add makeup water to the Suppression Pool from the Condensate Storage Tanks per normal operating procedure 2 RR08B I, TS (SRO) diagnosis, instrument bypass and SRO Tech Spec implementation.

N2-ARP-01 N2-OP-92 3 FW03A C (BOP)

RR31 R (SRO) B runback failure due to trip of hydraulics (TS 3.4.1). FCV lockup RR30 R (ATC) results in failure to automatically reduce power to within single Feedwater pump capacity. Rapid Power Reduction with Cram Rods is required to prevent automatic scram on Low RPV Water Level FW35 resulting in water level transient. Require taking manual contol of Feedwater to stabilize level.

N2-SOP-6 Feedwater Failures Override C (BOP) ADS/SRV 121 fails opens due to ADS Division I control switch Switch C,TS failure. Valve closes when fuses pulled (TS 3.5.1 .E, F, and H /

P628-B22C- (SRO) TS 3.0.3)

S4A-A N2-SOP-34 Stuck Open SRV TU02 9% M (ALL) The main turbine vibration degrades and a small amount of Main 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 N2-ARP-01 Time 3 N2-SOP-9 minutes N2-EOP-RPV Page 1 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Draft Submittal Draft Submittal Tuesday, March 15,2005

NRC EXAM Loss of main condenser vacuum. The degrading vibration causes a main condenser vacuum leak that degrades rapidly once the 8 RD17Z

@I 7 (Insert to position 17)

RPI 2A RPI 2B 9 CU08 l--t---

L FWO2C

--.- * (N)ormal, (R)eac

--.- * (N)ormal, (R)eac tivity, (I)nstrument, (C)omponent, (M)ajor I Facility: Nine Mile Point 2 Scenario No.: NRC-01 OD-Test No.: NRC-01 I TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO: SEE SECTION D.5.d)

1. Total malfunctions (5-8)

I ACTUAL ATTRIBUTES 6

I Events 2.3.4.5.8.9

2. Malfunctions after EOP entry (1-2) 2 Events 9 , l O
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 enteredhequiring substantive actions (1-2)

Event 6 and 7 EOP-RPV. EOP-PC I 2 I

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

Event 8 EOP-CS. Event 10 EOP-C2

7. Critical tasks (2-3) 2 4

I CRITICAL TASK DESCRIPTIONS:

CT-1.O Close ADS valve prior t o SPT reaching 110°F CT-2.0 Avoid exceeding HCTL CT-3.0 Restore and maintain RPV water level above MSCRWL (-39 inches)

CT-4.0 Fully insert control rods Page 2 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Draft Submittal Draft Submittal Tuesday, March 15,2005

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% (103%)

Turnover:

1. Place RDS-PIB in service Event Malf. No Event No.

1 RR16A

@.25 1 min ramp (SRO) A to stop the leak. (TS 3.4.1)

RR16A Cram Rod insertion is required to reduce rod line below 100%.

@ 75 1 min With inoperable OPRMs additional actions are required to monitor (ATC) for power oscillations while in the Heightened Awareness Zone.

ramp N2-SOP-29. I, Reactor Recirc Pump Seal Failure N2-SOP-29, Sudden Reduction In Core Flow 3 RD18 RD063419 RD062227 trol Rod Drive Failures 4 ED02A DG04A TS (SRO) start on bus undervoltage. Division I DG manual start is CS03 performed to avoid the requirement to initiate a manual scram.

Crew will restore Service Water system to allow continued plant operation per SOP 3. SRO enters Tech Specs and with both High and Low Pressure Core Spray systems inoperable, enters LCO 3.0.3 which requires plant shutdown. High Pressure Core Spray is also unavailable as an injection source later in scenario.

N2-SOP-3, Loss of AC Power Tech Specs 3.5. I LCO 3.0.3 3.7.I, 3.8.1, 3.8.8 5 RR20

@ I .5%

RR20@10% maintained above TAF by manually starting failed ECCS systems.

Containment Spray is required.

10 min ramp after scram N2-EOP-RPV, N2-EOP-PC

. Page 3 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Draft Submittal Draft Submittal Tuesday, March 15,2005

NRC EXAM (BOP) Manual Start and injection is required to restore RPV water level above TAF. Failure also complicates ability for the crew to initiate Drywell Sprays PRA Tasks.

Division I Low Pressure ECCS systems (Low Pressure Core I I

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Facility: Nine Mile Point 2 Scenario No.: NRC-02 )p-Test No.: NRC-01 I TARGET QUANTITATIVE ATTRIBUTES I ACTUAL ATTRIBUTES I (PER SCENARIO; SEE SECTION D.5.d) I
1. Total malfunctions (5-8) 5 Events 2,3,4,5,7
2. Malfunctions after EOP entry (1-2) 2 Events 73'
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)

Event 5 5 EOPs entered/requiring substantive acbons (1-2)

I 1 2

Event 5 EOP-RPV. EOP-PC 6 EOP contingencies requiring substantive acbons (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 TAF with LP ECCS systems Page 4 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Draft Submittal Draft Submittal Tuesday, March 15.2005

NRC EXAM Awendix 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-I 0 with additional rods withdrawn to raise power to about 4%. Low Power Scenario Reactor startup in progress per N2-OP-101A.

Reactor power approximately 4%.

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

Continue the startup, transfer the reactor mode switch to run after APRM downscale condition is cleared p

(above 4%). EHC Pump B is out of service for motor repairs.

Event 7 Malf. No. Event Event Description I (SRO) instrument and reset the resulting RPS c6annel trip. (TS determination for 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 N2-OP-3 R (ATC)

R (SRO) control rods must be withdrawn to raise power to clear the APRM downscale condition.

N2-OP-IOIA N (ALL) Transfer Reactor Mode Switch in RUN N2-OP-IOIA t Control Rod 34-27 Drift Out. N2-SOP-8 will be executed to fully r

34-27 C (SRO) insert and isolate the control rod. With power level below RWM setpoint the RWM must be bypassed to insert the drifting rod.

N2-SOP-8 Tech Spec 3.1.5 Service Water Pump A trip occurs requiring a standby pump to be C (SRO) placed in service.

N2-OP-11 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 Draft Submittal Draft Submittal Tuesday, March 15,2005

NRC EXAM 8 RC12 M (ALL) RClC Steam Leak into Reactor Building with Failure to isolate.

25% 10 Automatic and manual attempts to isolate the RClC steam line will 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 RCI 1 Valve capability, if used to anticipate RPV Blowdown.

TC15A N2-EOP-RPV TC15B 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. ADS/SRV 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-c2 N2-EOP-C2

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TARGET QUANTITATIVE ATTRIBUTES ACTUAL ATTRIBUTES (PER SCENARIO; SEE SECTION D.5.d) 1 Total malfunctions (5-8) 6 Events 1.2.5.6.9.10

~

2. Malfunctions after EOP entry (1-2) 2 Events 9.10
3. Abnormal events (2-4) 2 Event 2 SOP-6 Event 5 SOP-8
4. Major transients (1-2)

Event 8

5. EOPs enteredlrequiring substantive actions (1-2)

Event 8 EOP-RPV. EOP-SC 6 . EOP contingencies requiring substantive actions (0-2)

Event 10 EOP-C2

7. Critical tasks (2-3) I 2 I CRITICAL TASK DESCRIPTIONS:

CT-1.O: Scram and Blowdown with Primary System discharging t o Secondary Containment CT-2.0: Given unisolable steam leak into the Secondary Containment and failure of Reactor Building t o isolate, the crew will manually isolate RB ventilation and start GTS.

Page 6 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Draft Submittal Draft Submittal Tuesday, March 15,2005

NRC EXAM Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point 2 Scenario No.: NRC-04 (ALTERNATE) Op-Test No.: NRC-01 Examiners: Operators:

Initial Conditions: 100% power (IC-20)

Turnover: Division II liesel Genei :or is inoperable for pre-planned maintenance.

Event Malf. No. Event Event No. Type* Descriotion

~ ___ r -

N (BOP) Perform Drywell to Suppression Chamber Vacuum Breaker Surveillance Test, N2-OSP-ISC-M@002.

sticks open during testing. Requires entry into Tech Spec 3.6.1.7 C (BOP)

TS(SR0) system declared inoperable and then returned standby.

R(B0P) Feedwater Heating and Feedwater Level Controller failed as-is.

Requires FWLC to be placed in manual, and requires power reduction with Recirc Flow Steam leakage inside Drywell requires manual scram and subsequent entry into EOP-PC on High Drywell Pressure MS04 @ N2-EOP-PC 30%

ramp to 75%

Shutdown. Crew is required to scram using manual scram pushbuttons which also does not trip RPS After entering N2-EOP-C5 and manually initiating RRCSIARI, all control rods will fully insert by the ARI function of RRCS.

N2-SOP- 101C N2-EOP-RPV

-! ED02B C (BOP) results in loss of 4160 VAC Emergency Switchgear 2ENS*SWG103 and loss of Division II Low Pressure ECCS systems, complicating subsequent RPV Flooding and Containment FIG= I (ALL) RPV water level instrument reference leg flashing. Requires crew to determine RPV Blowdown and RPV Flooding is required.

N2-EOP-C4 Page 7 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Draft Submittal Draft Submittal Tuesday, March 15,2005

NRC EXAM Injection from RHS Loop A can be restored after dispatching operators for local valve operation.

1 Emergency 2.1.2 1

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TARGET QUANTITATIVE ATTRIBUTES ACTUAL EXAM OPS FACILITY (PER SCENARIO; SEE SECTION D.5.d) ATTRIBUTES DEVELOPER REVIEW REVIEW
1. Total malfunctions (5-8) 5 Events 3,4,6,8,9
2. Malfunctions after EOP entry (1-2) 3 Events 6.8,9
3. Abnormal events (2-4) 2 Events 3 N2-SOP-6 ; Event 4 N2-SOP4
4. Major transients (1-2) 1 Event 5
5. EOPs enteredhequiring substantive actions (1-2) 2 Event 5 and 6 EOP-RPV and EOP-PC
6. EOP contingencies requiring substantive actions (0-2) 2 Event 6 EOP-CS: Event 8 EOP-C4
7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:

Page 8 of 8 NUREG-1021, Revision 9 2005 U2 Test 2 (NRC) - Scenario Outline Draft Submittal Draft Submittal Tuesday, March 15,2005

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