ML063380390

Draft - Outlines (Folder 2)

ML063380390
Person / Time
Site:	Indian Point
Issue date:	09/07/2006
From:	Entergy Nuclear Operations
To:	David Silk Operations Branch I
Sykes, Marvin D.
References
Download: ML063380390 (32)

Text

ES-401 PWR RO Examination Outline Form ES-401-2

3. Generic Knowledge and Abilities Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO 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

f. 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site -specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

4. Select topics from 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.

IP 3 - RO Outline Rev 0 Page 1 of 12 NUREG-1021, Revision 9

ES-401 PWR RO Examination Outline Form ES-401-2 I 8. On the following pages, enter the WA numbers, a brief description of each topic, I the topics importance ratings for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G*on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, l Group (Note #I does not apply). 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.

IP 3 - RO Outline Rev 0 Page 2 of 12 NUREG-1021, Revision 9

INDIAN POINT UNIT 3 I

I-Es-401 EIAPE # I Name I Safety Function K1 K2 K3 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier I/Group 1 (RO)

AI A2 G Number KIA Topic(s)

Form ES-401-2 Imp. Q#

I I

RO 000007 (BWIE02 & E10; CE/E02) / Reactor Trip - R EA1.04 Ability to operate and monitor RCP operation and flow rates as 3.6 Stabilization- Recoverv / 1 they amly to a reactor trip 000008 / Pressurizer Vapor Space Accident / 3 R AA2.20 Ability to determine and interpret the effect of an open PORV on 3.4 code safety, based on observation of plant parameters as they apply to the Pressurizer Vapor Space Accident 000009 / Small Break LOCA I 3 R EK2.03 Knowledge of the interrelations between the small break LOCA 3.0 and the SGs I 000011 / Large Break LOCA / 3 I EA2.14 Ability to determine or interpret the actions to be taken if limits for PTS are violated as they apply to the Large Break LOCA 3.6 000015/17 RCP Malfunctions / 4 G2.1.28 Knowledge of the purpose and function of major system 3.2 comDonents and controls AKI .01 Knowledge of the operational implications of consequences of 2.8 thermal shock to RCP seals as it applies to Loss of Reactor Coolant Pump Makeup 000025 / Loss of RHR System / 4 Not Selected 000026 / Loss of Component Cooling Water / 8 AA2.06 The ability to determine and interpret the length of time after the 2.8 loss of CCW flow to a component before that component may be damaged 000027 / Pressurizer Pressure Control System R AK2.03 Knowledge of the interrelations between the Pressurizer 2.6 MalfunctionI 3 Pressure Control Malfunction and controllers and positioners 000029 / Anticipated Transient w/o Scram / 1 R EKI .01 Knowledge of the operational implications of reactor nucleonics 2.8 and thermo-hydraulics behavior as they apply to the ATWS 000038 / Steam Generator Tube Rupture / 3 R secondary PORV controllers and indicators as they apply to a 000040 (BW/EO5; CE/E05; W/E12) / Steam Line 1 Rupture - Excessive Heat Transfer / 4 000054 (CEIEO6) I Loss of Main Feedwater/ 4 R break depressurizes the SG (similar to a steam line break) as 000055 / Station Blackout / 6 R cooling by natural convection as they apply to Loss of Offsite 000057 / Loss of Vital AC Elec. Inst. Bus / 6 Not Selected 000058 / Loss of DC Power / 6 Not Selected 000062 / Loss of Nuclear Service Water I 4 Not Selected NUREG-I 021, Revision 9 Page 3 of 13

ElAPE # I Name I Safety Function KI K2 K3 AI A2 G Number KIA Topic(s) Imp. Q#

RO I 000065 ILoss of instrument Air I 8 Ability to operate and I or monitor the RPS as it applies to the Loss of Instrument Air 3.3 W/E04 ILOCA Outside Containment I 3 Ability to operate and /or monitor operating behavior 3.6 characteristics of the facility as they apply to a LOCA Outside Containment W/EI 1 / Loss of Emergency Coolant Recirc. I4 Ability to determine and interpret the facility conditions and 3.4 selection of appropriate procedures during abnormal and emergency operations as it applies to the Loss of emergency Coolant Recis Knowledge of operational implications of EOP warnings, 3.3 Loss of Secondary Heat Sink / 4 cautions and notes KIA Cateaotv Point Totals: 4 2 Group Point Total: 18 NUREG-1021, Revision 9 Page 4 of 13

INDIAN POINT UNIT 3 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)

-1 ElAPE ##I Name I Safety Function K1 K2 K3 AI A2 G Number KIA Topic(s) imp. Q#

000001 / Continuous Rod Withdrawal / 1 R AKI .06 Knowledge of the operational implications of the relationship of 4.0 reactivity and reactor power to rod movement as it applies to the continuous rod withdiawal 000003 / Dropped Control Rod / 1 Not Selected 00005 Inoperable/Stuck Control Rod / 1 Not Selected 000024 Emergency Boration I 1 Not Selected 000028 / Pressurizer Level Malfunction / 2 R AK2.02 Knowledge of the interrelations between the Pressurizer Level 2.6 Control Malfunctions and sensors and detectors 000032 / Loss of Source Range NI I 7 Not Selected 000033 I Loss of Intermediate Range NI I 7 R AK1.O1 Knowledge of the operational implications of the effects of 2.7 voltage changes on performance as they apply to Loss of Intermediate Range Nuclear Instrumentation I 000036 (BW/A08) / Fuel Handling Accident / 8 I I I 1 I I I Not Selected I I I 000037 I Steam Generator Tube Leak / 3 I R I 1 M2.12 I Ability to determine and interpret the flow rate of leak as it I 3.3 I I I I I I applies to the Steam Generator Tube Leak I I 000051 / Loss of Condenser Vacuum 14 I R I G2.2.12 [ Knowledge of the surveillance procedures I 3.0 I 000059 I Accidentalliquid Radwaste Rel. I 9 Not Selected 000060 / Accidental Gaseous Radwaste Rel. / 9 Not Selected 000061 / ARM System Alarms I 7 Not Selected 000067 I Plant Fire On-site I 9 Not Selected 000068 (BWIAO6) I Control Room Evac. / 8 R AA2.06 Ability to determine and interpret RCS pressure as they apply 4.1 to the Control Room Evacuation 000069 (WIE14) I Loss of CTMT Integrity / 5 R AK3.01 Knowledge of the reasons for guidance contained in EOP for 3.8 I I I I I I I loss of containment intearitv

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000074 (W/E06 & E07) / Inad. Core Cooling I 4 I I I I Not Selected I 000076 I High Reactor Coolant Activity / 9 R AA1.04 Ability to operate and / or monitor the failed fuel-monitoring 3.2 equipment as they apply to the High Reactor Coolant Activity WE/OI & 02 / Rediagnosis & SI Termination 1 3 Not Selected W/E13 / Steam Generator Over-oressure I 4 Not Selected I I 1 W/E15 I Containment Floodinq / 5

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I I I I I I I Not Selected W/E16 / High Containment Radiation / 9 Not Selected BW/AOI / Plant Runback / 1 ~~

Not Selected BW/AO2 & A03 I LOSSof NNI-XN I 7 Not Selected I I BW/AO4 /Turbine Trio / 4 Not Selected BWIAOS I Emergency Diesel Actuation I 6 Not Selected BW/A07 / Flooding / 8 Not Selected NUREG-1021, Revision 9 Page 5 of 13

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INDIAN POINT UNIT 3 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)

ElAPE # I Name I Safety Function KI K2 K3 AI A2 G Number KIA Topic(s) Imp. Q#

NUREG-I 021, Revision 9 Page 6 of 13

INDIAN POINT UNIT 3 ES-40 1 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) parameters to prevent exce associated with oDerating the including PZR level and pressure R G2.1.32 Ability to explain and apply all system limits 3.4 and precautions K1.04 Knowledge of the physical connections and I 3.3 or cause-effect relationship between the CCWS and the RCS, in order to determine sources(s) of RCS leakage into the CCWS R A2.02 Ability to predict the impacts of a spray valve 3.9 failure on PZR PCS and on those predictions, use procedures to correct, control or mitinate the consequences of those malfun&ons or operations A I .01 Ability to predict and I or monitor changes in 2.9 I I I I I parameters exceeding design limit associated with oDerating the RPS controls including trip setpoint adjustments I I A I .09 Ability to predict and I or monitor changes in 3.4 parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including T-hot.

K3.03 Knowledge of the effects that a loss or 4.3 malfunction of the ESFAS will have on the containment K2.01 Knowledge of power supplies to the 3.0 containment cooling fans Not Selected of 13

INDIAN POINT UNIT 3 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

System # I Name K1 K2 K3 K4 K5 K6 AI A2 1 A3 A4 1 G 1 Number I KIA Topic(s) I Imp. 1 Q#

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Ability to monitor automatic operation of the CSS including pump starts and correct MOV positioning

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Knowledge of the operational implications of I I I 4.3 3.6 the effect of steam removal on reactivity as it amlies to the MRSS

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Knowledge of the physical connections and I 3.4 or cause-effect relationships between the I I I I I I I MRSS and the AFW system I I I 059 Main Feedwater I I I I I I I I I I have on components using DC control power I 064 Emergency Diesel Generator R bus power supplies to the 073 Process Radiation Monitoring R the PRM system and those systems sewed 076 Service Water R 078 Instrument Air NUREG-1021, Revision 9 Page 8 of 13

INDIAN POINT UNIT 3 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G Number K/A Topic(s) Imp. Q#

NUREG-I 021, Revision 9 Page 9 of 13

INDIAN POINT UNIT 3 ES-401 PWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2IGroup 2 I

I System # / Name K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G Number KIA Topic(s) Imp. Q#

K3.02 Knowledge of the effect that a loss or 3.4 malfunction of the CRDS will have on the RCS K6.02 Knowledge of the effect or a loss or malfunction 3.6 of the RCP on the RCS K5.15 Knowledge of the operational implications of 3.6 PZR level indicationwhen RCS is saturated as it applies to the PZR LCS I K1.02 Knowledge of the physical connections and / or 3.0 cause effect relationships between the RPlS and the NIS K5.02 Knowledge of the operational implications of 2.7 discriminator/compensationoperation concepts as they apply to the NIS Not Selected Not Selected Not Selected A2.03 Malfunctions or operations on the HRPS; and based on those predictions use procedures to correct, control or mitigate the consequences of the hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment Not Selected K4.03 Knowledge of design features and / or 2.6 interlocks which provide anti-siphon devices

+

Not Selected Not Selected I

Not Selected A I .06 Ability to predict and / or monitor changes in 3.3 parameters associated with operating the MT/G iL system controls including expected response of secondary plant parameters following T/G trip K3.01 Knowledge of the effects that a loss or malfunction of the CARS will have on the main condenser Not Selected NUREG-1021, Revision 9 Page 10 of 13

INDIAN POINT UNIT 3 ES-401 PWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2IGroup 2 System # I Name K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G Number WA Topic(s) Imp. Q#

072 Area Radiation Monitoring ARM system including changes in ventilation 075 Circulating Water Not Selected 079 Station Air Not Selected 086 Fire Protection Not Selected

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K/A Category Point Totals: 1 0 2 1 2 1 1 1 1 0 0 Group PointTotal: IO NUREG-9021, Revision 9 Page 11 of 13

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

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Facility: Indian Point Unit 3 Date of Exam: 10/23/06 Exam Level: RO Category WA # Topic Imp. Q#

G2.1.I Knowledge of conduct of operations 3.7 requirements Conduct of G2.1.32 Ability to expJain and apply all system limits and 3.4 Operations precautions I Total Equipment G2.2.1 ' Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could effect reactivity Control G2.2.11 Knowledge of the process for controlling temporary changes G2.2.28 1 Knowledge of new and spent fuel movement Procedures I Total I 3 G2.3.10 Ability to perform procedures to reduce excessive 2.9 levels of radiation and guard against personnel exposure Radiation G2.3.9 Knowledge of the process for performing a 2.5 Control containment purge 2

Total I G2.4.18 Knowledge of the specific bases for EOPs 2.7 Emergency G2.4.1 Knowledge of EOP entry conditions and 4.3 Procedures / immediate action steps Plan I G2.4.7 Knowledge of event based EOP mitigation 3.1 strategies I Total 3 Tier 3 Point Total RO I 10 NUREG-I 021,Revision 9 Page 12 of 13

ES-401 Record of Reiected WAS Form ES-401-4 Tier / Group Randomly Selected WA Reason for Rejection NONE NUREG-1021, Revision 9 Page 13 of 13

ES-401 PWR Examination Outline Form ES-401-2 Facility: Indian oint 3 Date of Exam: 10/23/2006 Exam Level: SRO Tier 1.

Emergency &

Abnormal Plant EvoIut ions 2.

Plant Systems

3. Generic Knowledge and Abilities Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO and SRO 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 f: 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systemslevolutions 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 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 KfA 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 for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group (Note #I does not apply). 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 K/A numbers, descriptions, IRs, and point totals on form ES-401-3. Limit SRO selections to WASthat are linked to 10 CFR 55.43.

I NUREG-I 021, Revision 9 Page 1 of 9

ES-401 PWR Examination Outline Form ES-401-2

• Emergency and Abnormal Plant Evolutions - Tier 1IGroup I(SRO)

I ElAPE # I Name I Safety Function Kl K2 K3 A1 A2 G Number WA Topic(s) Imp. Q#

SRO NUREG-I 021, Revision 9 Page 2 of 9

lEs-40 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 (SRO)

AA2.03 Ability to determine and interpret the required actions if more 4.4 than one rod is stuck or inoperable as they apply to the inoperable / Stuck Rod I 000036 000033 / Loss of Intermediate Range NI / 7 (BWlAO8) I Fuel Handling Accident 18 I I I I I I S G2.2.27 Knowledge of the refueling process 3.5 000037 / Steam Generator Tube Leak / 3 000051 / Loss of Condenser Vacuum I 4 I 0000591Accidental Liquid RadwasteRel./9 I I ~1 I I ~ I I I 000060 / Accidental Gaseous Radwaste Rel. / 9 000061 / ARM System Alarms / 7 000067 I Plant Fire On-site I 9 I I 000068 (BW/AO6) / Control Room Evac. / 8 000069 (WIE14) / Loss of CTMT Integrity I 5 000074 (WlE06 & E07) I Inad. Core Cooling / 4 S G2.4.4 Ability to recognize abnormal indications for system operating 4.3 parameters which are entry-level conditions for emergency and

, abnormal operating procedures.

G2.1.7 Ability to evaluate plant performance and make operational 4.4 judgments based on operating characteristics, reactor behavior and instrument interpretation I I I I I BWIAO2 & A03 I Loss of NNI-XY 1 7 I I I I I I 1 BW/A04 I Turbine Trip I 4 I I I I I I BW/AOS / Emergency Diesel Actuation / 6 BWlA07 I Flooding18 BW/E03 I Inadequate Subcooling Margin / 4 t

BWlE08; WlE03 / LOCA Cooldown I DeDress. I 4 BWIEO9; CEIAI 3; WIE09 & 10 Natural Circ.14 I I 1- I NUREG-1021, Revision 9 Pag ! 3 o f 9

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

EIAPE # I Name I Safety Function WA Topic(s) Imp.

I I I I I I I I KIA Category Point Totals: I 1 1 3 1 I Group Point Total: 4 NUREG-I021, Revision 9 Page 4 of 9

ES-401 PWR Examination Outline Form ES-401-2 '

Plant Systems - Tier 2/Group 1 (SRO)

I

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System # / Name K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G Number K/A Topic(s) Imp. Q#

064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water S A2.01 Ability to predict the impacts of loss of SWS 3.7 and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations

System # I Name K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G Number WA Topic(s) Imp. Q#

NUREG-1021, Revision 9 Page 6 of 9

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Plant Systems - Tier 2IGroup 2 (SRO)

NUREG-1021, Revision 9 Page 7 of 9

ES-401 Generic Knowledge and Abilities Outline (Tier 3) (SRO) Form ES-401-3 Facility: Indian Point Unit 3 Date of Exam: 10/23/06 SRO I Category WA # Topic 2.1.11 Knowledge of less than one hour technical Conduct of specifications for a system Operations 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications Total I

2.2.26 Knowledge of refueling administrative 3.7 Equipment requirements Control 2.2.24 Ability to analyze the affects of maintenance 3.8 activities on LCO status Total 2 Radiation 2.3.6 Knowledge of the requirements for reviewing and 3.1 Control - approving release permits Total 1

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Emergency 2.4.41 Knowledge of emergency actionlevel thresholds and classifications Procedures / 2.4.28 Knowledge of procedures relating to emergency Plan remonse to sabotaae Total Tier 3 Point Total SRO I 7 It NUREG-1021, Revision 9 Page 9 of 9

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ES-401 Record of Rejected WAS (SRO) Form ES-401-4 Tier / Group Randomly Selected WA Reason for Rejection NONE NUREG-I021, Revision 9 Page 10 of 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Indian Point Unit 3 Date of Examination: 1W3106 Examination Level: RO SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Reactor Vessel Venting Time (FR-1.3)

Using attachments 4 and 5 of FR-1.3, Response to Voids in Reactor Conduct of Operations D, R Vessel and using given data for plant conditions, the candidate performs a manual calculation to determine how long the reactor vessel should be vented to remove non-condensible gases.

Calculate Shutdown Margin With plant at 100% power and one stuck rod, the candidate calculates Conduct of Operations D, R shutdown margin using graphs and reactivity data.

Generate a Manual Tagout Candidate will prepare a manual tagout (normal means using the Equipment Control M, SOMs computer application is not available). Candidate will review drawings and tagout points and enter the points and desired positionkondition onto the manual tagout form.

Radiation Control CCR Offsite Communicator- NUE Notification Given completed forms for initial notification following a NUE Emergency Plan s declaration, the candidate simulates performing the initial Control Room NUE Notification Checklist. An alternate path will be used. The normal method for notifications to state and local government will not function requiring use of alternate means (local government radio).

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( S 3 for ROs; 5 4 for SROs & RO retakes)

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

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

ES-301, Page 22 of 27

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

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Facility: Indian Point Unit 3 Examination Level: RO 0 SRO Operating Test Number: 1 .

Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Reactor Vessel Venting Time (FR-1.3)

Using attachments 4 and 5 of FR-1.3, Response to Voids in Reactor Conduct of Operations D. R Vessel and using given data for plant conditions, the candidate performs a manual calculation to determine how long the reactor vessel should be vented to remove non-condensible gases.

Calculate Shutdown Margin With plant at 100% power and one stuck rod, the candidate calculates Conduct of Operations D, R shutdown margin using graphs and reactivity data.

Review/Approvea Tagging Order (Faulted)

Candidate will review P&IDs and associated components identified on Equipment Control the tagout required to provide protection. An error will be identifed (and corrected) by the candidate.

Review/Approvea Gaseous Release Permit (Faulted)

Candidate will review a completed permit that contains a calculation Radiation Control N, R error.

EAL Classification and Part 1 Form Following the simulator scenario, the CRS candidate will classifiy the S , M, P Emergency Plan event (highest level EAL achieved if the classification escalated during the scenario) and complete the NY State par( 1 form.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required, Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( L 3 for ROs; s 4 for SROs & RO retakes)

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

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

ES-301, Page 22 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

.. Indian Point Unit 3 Date of Examination: 1OQ3/06 Facility: _______

Exam Level: RO ~  % ~ ~ u - ~ ROperating 8 Test ~ No.: ~ ~

I

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Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

I I System / JPM Title Type Code* Safety Function Emergency Borate a.

b. Reset SI Using Key Switches C. Realign SI For High Head Recirculation

d. RCP #2 Seal Failure Actions N, S 4P

e. Transfer from AFW Feed to Low Flow Bypass Feed L, N , S 4s f, Align Containment Spray System During Loss of Emergency Coolant Recirculation N, s 5

g. Restore Steam Flow Channel to Service N, s 7

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h. Adjust R-20 Process Radiation Monitor Setpoints

i. Open Steam Supply Valves to 32 ABFP A, D 4s

j. Start the Appendix R Diesel A, E,N 6

k. Align Backup Cooling to the Charging Pumps A, E, N, R 8

• Type Codes Criteria for RO / SRO-I I SRO-U (A)lternate path 4-6I 4-612-3 (C)ontrol room (D)irect from bank <9/~8/r;4 (E)mergency or abnormal in-plant 2 1 1 2 112 I (L)ow-Power I Shutdown 2 112 I/> 1 (N)ew or (M)odifiedfrom bank including 1(A) 22/22/21 (P)revious2 exams < 3 I s 3 I 2 (randomly selected)

(RW 2 112 1 / 2 1 (S)imulator ES-301,Page 23 of 27

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Date of Examination: 10/23/06 -

Operating Test No.: --I

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Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

a. Emergency Borate System / JPM Title I Type Code*

I Function Safety

b. Reset SI Using Key Switches

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I I C. Realign SI For High Head Recirculation A, D, S 3

d. RCP #2 Seal Failure Actions

e. Transfer from AFW Feed to Low Flow Bypass Feed I LN,S I 4s

f. Align Containment Spray System During Loss of Emergency Coolant 5 Recirculation N, S

g. Restore Steam Flow Channel to Service N, S 7 h.

i. Open Steam Supply Valves to 32 ABFP A, D 4s

j. Start the Appendix R Diesel A, E,N 6

k. Align Backup Cooling to the Charging Pumps A, E, N, R 8

• Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank < 91< 8i1; 4 (E)mergency or abnormal in-plant 2 1 I 2 112 I (L)ow-Power I Shutdown 2 112 I l r 1 (N)ew or (M)odified from bank including I(A) 2 2 1 ~ 2 1 ~ 1 (P)revious 2 exams 1; 3I 2 3 I < 2 (randomly selected)

(VCA 2 1I 2 1I s 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Date of Examination: 10/23/06 Operating Test No.: 1 System I JPM Title Type Code* Safety Function

a. I I C.

I I d.

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e. Transfer from AFW Feed to Low Flow Bypass Feed I L, N,S 1 4s

f. Align Containment Spray System During Loss of Emergency Coolant Recirculation N, S 5 h.

I I In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 1.

j. Start the Appendix R Diesel A, E, N 6

k. Align Backup Cooling to the Charging Pumps A, E, N, R 8

• TvDe Codes Criteria for RO I SRO-I I SRO-U

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(A)lternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank 5 912 811 4 (E)mergency or abnormal in-plant  :, 1 I : , 1 I:, 1 (L)ow-Power I Shutdown 2 1 I:, 1 I:, 1 (N)ew or (M)odified from bank including I(A) 1 2 1 2 212 1 (P)revious 2 exams 5 3I 5 3 I 5 2 (randomly selected)

(RKA  :, 1 1 2 1 1 2 1 Wimulator

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ES-301, Page 23 of 27

Amendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No: 1 Op-Test No: 1 Examiners: Operators:

Initial Conditions:

Scenario begins at 6% power with turbine close to sync speed. The team will continue with the startup by synchronizing the unit to the grid and increasing power.

Turnover:

Continue with the startup. Synchronize the unit to the grid and increase power at 150 MW per hour.

Event Malf. Event Event Type* Description N (BOP) Sync turbine and raise power N (CRS)

R (CRS)

R (ATC)

I (ALL) Thot fails high. CRS references TS I - 3 I MAL-SGN005D C (ALL) I SG Tube Leak. CRS references TS 4 MAL-SGN005D M (ALL) SGTR - Manual reactor trip and manual SI actuation

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5 MAL-EPSOO6 C (BOP) Loss of offsite power when 6.9 KV busses transfer MAL-SIS004A C (BOP) 31 and 33 SI pump auto start failure MAL-SISOO4C 7 MAL-SGN004P C (ATC) SG safety fails open on ruptured SG

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

Appendix D Scenario Outline Form ES-D-I I Facility: Indian Point 3 Examiners:

Scenario No: 2 Operators:

Op-Test No: 1 Initial Conditions:

The scenario begins at 100% power with 32 EDG out of service due to malfunctioning governor.

Turnover:

32 EDG out of service due to malfunctioning governor.

Maintain current plant conditions.

Event Malf. Event Event No: No. Type* Description 1 MAL-SWSOOIC C (BOP) 33 SWP trips 2 MAL-EPS005C C (ALL) 480V Bus 5A Fault 3 NIA R (ATC) TS required shutdown R (CRS)

N (BOP)

N (CRS) 4 MAL-EPSOO1 M (ALL) Station Blackout

~~

5 MAL-DSG001A C (BOP) 31 EDG fail to start 6 MAL-PRS003D C (ATC) PRZ PORV Fails Open 7 MAL-SWS001E C (BOP) SW pump does not auto start after bus energized

~

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

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No: 3 Op-Test No: 1 Examiners: Operators:

Initial Conditions:

The scenario begins at 100% power steady state conditions and no equipment 00s.

Turnover:

Maintain current plant conditions.

Event Malf. Event Event No: DescriDtion 1 PRZR pressure Instrument PT-455 fails high. Spray valves open and actual pressure lowers until manual action is taken.

2 PORV 455C fails open. Block valve can be manually closed to isolate the leak.

3 Loss of RWST level. Fork truck crashes into RWST resulting in level lowering to about 11 feet over 40 minutes.

~~ ~~ ~ ~~ ~~

4 NIA R (ATC) Tech Spec Required Shutdown - Due to inoperable RWST, team commences a shutdown.

R (CRS)

N (BOP)

N (CRS) 5 MAL-RCS007C C (ALL) RCP Seal malfunction - High vibrations and #1 seal degradation.

During shutdown, indications of RCP malfunction occur.

MAL-RCSO12C 6

7 8

-IMAL-RCS002C MAL-RCS001K MAL-SIS001A M (ATC)

M (ALL)

C (ATC)

While team is investigating RCP malfunction the affected RCP trips. Auto reactor trip does not occur but manual trip is successful Seal LOCA on affected RCP occurs resulting in eventual Low Pressure SI actuation SI fails to auto actuate, but manual SI is successful MAL-SIS0013 9 MAL-SIS004B C (BOP) 32 SI Pump fails to auto start and 34 and 35 FCU dampers do not auto reposition to incident mode.

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

Appendix D Scenario Outline Form ES-D-I rI Facility: Indian Point 3 Examiners:

Scenario No: 4 Operato rs:

Op-Test No: 1 I

Initial Conditions:

Scenario begins with the plant stable at 100% power. 31 ABFP has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for bearing inspections with an expected return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Turnover:

31 AGFP has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for bearing inspections with an expected return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Maintain Current Plant Conditions Event Malf. Event Event No: No. Type* Description 1 XMT-MSSOI 9 I (ATC) PT-412A fails low R (ATC)

R (CRS) 2 XMT-MSSO19 C (BOP) Loss of Condenser Vacuum R (ATC)

R (CRS) 3 AL-CFWOOSC C (ALL) Condensate Pump trip I 4 1 MAL-CFWOIS 1M (ALL) FW rupture in Turbine bldg I 5 1 MAL-RPS002A 1 C(ATC) Auto reactor trip failure 6 MAL-CfW001 C C(B0P) MDAFP 33 fails to start 7 MAL-CFW001B C(B0P) rDAFP trip