ML063380390

Draft - Outlines (Folder 2)

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

Text

PWR RO Examination Outline Form ES-401-2 ES-401 3. Generic Knowledge and Abilities Note: 1. 2. 3. 4. 5. 6. 7.* 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). 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. 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. 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. 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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

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-40 1 -2 I I 8. On the following pages, enter the WA numbers, a brief description of each topic, 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. 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 topics' importance ratings for the applicable license level, and the point totals l 9. IP 3 - RO Outline Rev 0 Page 2 of 12 NUREG-1021, Revision 9

INDIAN POINT UNIT 3 I- I EIAPE #I Name I Safety Function K1 K2 K3 AI A2 G Number KIA Topic(s) Imp. Q# RO I Es-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier I/Group 1 (RO) I Form ES-40 1 -2 000007 (BWIE02 & E10; CE/E02) / Reactor Trip - Stabilization - Recoverv / 1 R EA1.04 Ability to operate and monitor RCP operation and flow rates as 3.6 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 and the SGs 000009 / Small Break LOCA I3 R EK2.03 Knowledge of the interrelations between the small break LOCA 3.0 I I 00001 1 / Large Break LOCA / 3 00001 5/17 RCP Malfunctions

/ 4 000025 / Loss of RHR System

/ 4 000026 / Loss of Component Cooling Water

/ 8 000027 / Pressurizer Pressure Control System Malfunction I3 000029 / Anticipated Transient w/o Scram / 1 R R EA2.14 G2.1.28 Ability to determine or interpret the actions to be taken if limits for PTS are violated as they apply to the Large Break LOCA Knowledge of the purpose and function of major system comDonents and controls 3.6 3.2 AKI .01 Knowledge of the operational implications of consequences of thermal shock to RCP seals as it applies to Loss of Reactor Coolant Pump Makeup Not Selected The ability to determine and interpret the length of time after the loss of CCW flow to a component before that component may be damaged AK2.03 Knowledge of the interrelations between the Pressurizer

2.6 Pressure

Control Malfunction and controllers and positioners EKI .01 Knowledge of the operational implications of reactor nucleonics 2.8 and thermo-hydraulics behavior as they apply to the ATWS 2.8 AA2.06 2.8 000038 / Steam Generator Tube Rupture

/ 3 R 000040 (BW/EO5; CE/E05; W/E12)

/ Steam Line 1 Rupture - Excessive Heat Transfer

/ 4 ' 000054 (CEIEO6) I Loss of Main Feedwater

/ 4 R 000055 / Station Blackout

/ 6 R secondary PORV controllers and indicators as they apply to a break depressurizes the SG (similar to a steam line break) as cooling by natural convection as they apply to Loss of Offsite Not Selected Not Selected Not Selected 000057 / Loss of Vital AC Elec. Inst.

Bus / 6 000058 / Loss of DC Power

/ 6 000062 / Loss of Nuclear Service Water I4 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.

RO I 000065 I Loss of instrument Air I8 Q# W/E04 I LOCA Outside Containment I3 W/EI 1 / Loss of Emergency Coolant Recirc.

I4 Loss of Secondary Heat Sink

/ 4 KIA Cateaotv Point Totals: 42 Ability to operate and I or monitor the RPS as it applies to the 3.3 3.6 Loss of Instrument Air Ability to operate and

/or monitor operating behavior characteristics of the facility as they apply to a LOCA Outside Containment selection of appropriate procedures during abnormal and emergency operations as it applies to the Loss of emergency Coolant Recis Ability to determine and interpret the facility conditions and 3.4 Knowledge of operational implications of EOP warnings, 3.3 cautions and notes Group Point Total: 18 NUREG-1021, Revision 9 Page 4 of 13 INDIAN POINT UNIT 3 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO) Form ES-401-2 ES-401 PWR Examination Outline 1 ElAPE ##I Name I Safety Function K1 K2 K3 AI A2 G Number KIA Topic(s) imp.

Q# - 000001 / Continuous Rod Withdrawal

/ 1 000003 / Dropped Control Rod / 1 00005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration I 1 000028 / Pressurizer Level Malfunction

/ 2 000032 / Loss of Source Range NI I 7 000033 I Loss of Intermediate Range NI I7 I 000036 (BW/A08)

/ Fuel Handling Accident

/ 8 I 000037 I Steam Generator Tube Leak

/ 3 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 Not Selected Not Selected R AK2.02 R AK1.O1 Not Selected Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and sensors and detectors Not Selected Knowledge of the operational implications of the effects of voltage changes on performance as they apply to Loss of Intermediate Range Nuclear Instrumentation 2.6 2.7 I I I 1 I I I Not Selected I I IRI 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 I I applies to the Steam Generator Tube Leak 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. I9 000060 / Accidental Gaseous Radwaste Rel. / 9 000061 / ARM System Alarms I7 000067 I Plant Fire On-site I 9 Not Selected Not Selected Not Selected Not Selected 000068 (BWIAO6) I Control Room Evac. / 8 R AA2.06 000069 (WIE14)

I Loss of CTMT Integrity

/ 5 R AK3.01 Ability to determine and interpret RCS pressure as they apply to the Control Room Evacuation Knowledge of the reasons for guidance contained in EOP for loss of containment intearitv 4.1 3.8 I I I I I I I -- 000074 (W/E06

& E07) / Inad. Core Cooling I4 I I I I Not Selected I 000076 I High Reactor Coolant Activity / 9 R AA1.04 WE/OI & 02 / Rediagnosis

& SI Termination 13 W/E13 / Steam Generator Over-oressure I4 Ability to operate and / or monitor the failed fuel-monitoring equipment as they apply to the High Reactor Coolant Activity Not Selected 3.2 Not Selected I I IIIIIII ~~ ~ 1 W/E15 I Containment Floodinq

/ 5 ~ W/E16 / High Containment Radiation

/ 9 BW/AOI / Plant Runback / 1 BW/AO4 /Turbine Trio / 4 BW/AO2 & A03 I LOSS of NNI-XN I7 BWIAOS I Emergency Diesel Actuation I6 BW/A07 / Flooding / 8 NUREG-1021, Revision 9 Page 5 of 13 Not Selected Not Selected Not Selected

~~ Not Selected I I Not Selected Not Selected Not Selected ES-401 ElAPE #I Name I Safety Function KI K2 K3 AI A2 G Number KIA Topic(s) ~ INDIAN POINT UNIT 3 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO) Imp. Q# Form ES-401-2 NUREG-I 021, Revision 9 Page 6 of 13 INDIAN POINT UNIT 3 Plant Systems - Tier 2/Group 1 (RO) ES-40 1 PWR Examination Outline Form ES-401-2 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 failure on PZR PCS and on those predictions, use procedures to correct, control or mitinate the consequences of R A2.02 Ability to predict the impacts of a spray valve

3.9 those

malfun&ons or operations Ability to predict and I or monitor changes in AI .01 2.9 II parameters exceeding design limit associated with oDerating the RPS controls I I II I including trip setpoint adjustments Ability to predict and I or monitor changes in AI .09 3.4 parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including T-hot. Knowledge of the effects that a loss or malfunction of the ESFAS will have on the containment Knowledge of power supplies to the containment cooling fans Not Selected 4.3 K3.03 3.0 K2.01 of 13 INDIAN POINT UNIT 3 Plant Systems - Tier 2/Group 1 (RO) ES-401 PWR Examination Outline Form ES-401-2 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# IIIII 059 Main Feedwater I 4.3 I I Ability to monitor automatic operation of the CSS including pump starts and correct MOV positioning ~ ~~ ~ Knowledge of the operational implications of the effect of steam removal on reactivity as it amlies to the MRSS Knowledge of the physical connections and I or cause-effect relationships between the 3.6 - 3.4 I I MRSS and the AFW system I I I I I I I I I I I I I have on components using DC control power I 064 Emergency Diesel Generator R 073 Process Radiation Monitoring R 076 Service Water R 078 Instrument Air bus power supplies to the the PRM system and those systems sewed NUREG-1021, Revision 9 Page 8 of 13 INDIAN POINT UNIT 3 Plant Systems - Tier 2/Group 1 (RO) Form ES-401-2 ES-401 PWR Examination Outline 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 Plant Systems - Tier 2IGroup 2 Form ES-401-2 I I System # / Name K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G Number KIA Topic(s) Imp.

Q# K3.02 K6.02 K5.15 3.4 Knowledge of the effect that a loss or malfunction of the CRDS will have on the RCS Knowledge of the effect or a loss or malfunction of the RCP on the RCS Knowledge of the operational implications of PZR level indication when RCS is saturated as 3.6 3.6 K1.02 K5.02 A2.03 it applies to the PZR LCS Knowledge of the physical connections and / or cause effect relationships between the RPlS and the NIS Knowledge of the operational implications of discriminator/compensation operation concepts as they apply to the NIS Not Selected I 3.0 2.7 Not Selected Not Selected 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 K4.03 Not Selected Knowledge of design features and

/ or interlocks which provide anti-siphon devices Not Selected Not Selected 2.6 I + AI .06 K3.01 iL Not Selected Ability to predict and / or monitor changes in parameters associated with operating the MT/G 3.3 system controls including expected response of secondary plant parameters following T/G trip Knowledge of the effects that a loss or malfunction of the CARS will have on the main condenser Not Selected Page 10 of 13 NUREG-1021 , Revision 9 INDIAN POINT UNIT 3 Plant Systems - Tier 2IGroup 2 ES-401 PWR RO Examination Outline Form ES-401-2 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 079 Station Air 086 Fire Protection Not Selected Not Selected Not Selected K/A Category Point Totals:

NUREG-9021, Revision 9 ~- ~ 1 0 2 1 2 1 1 1 1 0 0 Group PointTotal:

IO Page 11 of 13 ES-401 Generic Knowledge and Abilities Outline (Tier

3) Form ES-401-3 WA # G2.1 .I G2.1.32 ~~ ~ ~~ ~ Facility: Indian Point Unit 3 Date of Exam: 10/23/06 Exam Level: RO Topic Imp. Q# Knowledge of conduct of operations 3.7 3.4 requirements Ability to expJain and apply all system limits and precautions Category G2.3.10 Conduct of Operations Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure 2.9 G2.3.9 I Total Knowledge of the process for performing a containment purge 2.5 2 Equipment Control G2.4.18 G2.4.1 G2.2.1 G2.2.11 Knowledge of the specific bases for EOPs immediate action steps 2.7 4.3 Knowledge of EOP entry conditions and

' Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could effect reactivity Knowledge of the process for controlling temporary changes G2.4.7 G2.2.28 1 I Knowledge of event based EOP mitigation strategies

3.1 Knowledge

of new and spent fuel movement Procedures I Total I Total I3 3 Radiation Control Total I Emergency Procedures

/ Plan 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 Tier 1. Emergency

& Abnormal Plant Evo I u t io ns 2. Plant Systems oint 3 Date of Exam: 10/23/2006 Exam Level: SRO 3. Generic Knowledge and Abilities Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. 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). 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. 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. 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. 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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 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. 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

1. I does not apply). Use duplicate pages for RO and SRO-only exams. 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 WAS that 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 Imp. Q# ElAPE #I Name I Safety Function Kl K2 K3 A1 A2 G Number WA Topic(s) SRO NUREG-I 021, Revision 9 Page 2 of 9 lEs-40' PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 (SRO) 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 AA2.03 I 000033 / Loss of Intermediate Range NI / 7 IIIIII S ' 000036 (BWlAO8) I Fuel Handling Accident 18 000037 / Steam Generator Tube Leak / 3 000051 / Loss of Condenser Vacuum I4 Knowledge of the refueling process 3.5 G2.2.27 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 I9 000068 (BW/AO6) / Control Room Evac. / 8 I I 000069 (WIE14)

/ Loss of CTMT Integrity I5 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.

Ability to evaluate plant performance and make operational

4.4 judgments

based on operating characteristics, reactor behavior and instrument interpretation I G2.1.7 I I I I I BWIAO2 & A03 I Loss of NNI-X'Y 17 I I I I I 1 BW/A04 I Turbine Trip I4 IIIIII BW/AOS / Emergency Diesel Actuation

/ 6 BWlA07 I Flooding 18 BW/E03 I Inadequate Subcooling Margin

/ 4 BWlE08; WlE03 / LOCA Cooldown I DeDress. I4 t BWIEO9; CEIAI 3; WIE09 & 10 Natural Circ.14 I I 1- I NUREG-1021, Revision 9 Pag !3of9 Form ES-401-2 ES-40 1 PWR Examination Outline 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:

1131 I Group Point Total: 4 I NUREG-I 021, Revision 9 Page 4 of 9 Form ES-40 1 -2 ' ES-40 1 PWR Examination Outline Plant Systems - Tier 2/Group 1 (SRO) ~ ~ System # / Name ~~ K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G Number K/A Topic(s)

I 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.

NUREG-1021, Revision 9 Q# Page 6 of 9

. ... ~ 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 2.2.26 Facility: Indian Point Unit 3 Date of Exam: 10/23/06 Knowledge of refueling administrative

3.7 requirements

SRO II 2.2.24 Category Ability to analyze the affects of maintenance

3.8 activities

on LCO status Conduct of Operations Total Equipment Control 2 WA # Radiation Control 2.1.11 2.3.6 Knowledge of the requirements for reviewing and

3.1 Total

1 approving release permits - 2.1.33 Topic Knowledge of less than one hour technical specifications for a system Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications II Total Emergency Procedures

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

\ ES-40 1 Record of Rejected WAS (SRO) Form ES-401-4 Tier / Group Randomly Selected WA Reason for Rejection NONE NUREG-I 021, Revision 9 Page 10 of 9 ES-301 Administrative Topics Outline Form ES-301-1 Administrative Topic (see Note) Conduct of Operations Facility: Indian Point Unit 3 Date of Examination:

1 W3106 Examination Level: RO SRO 0 Operating Test Number:

1 Type Code* Describe activity to be performed Determine Reactor Vessel Venting Time (FR-1.3) Using attachments 4 and 5 of FR-1.3, Response to Voids in Reactor 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.

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

D, R Generate a Manual Tagout Candidate will prepare a manual tagout (normal means using the 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.

M, Radiation Control Emergency Plan CCR Offsite Communicator - NUE Notification Given completed forms for initial notification following a NUE 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).

s' 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 ~ ~ Facility: Indian Point Unit 3 Examination Level: RO 0 SRO Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code* D. R D, R N, R S, M, P Operating Test Number: 1 . Describe activity to be performed Determine Reactor Vessel Venting Time (FR-1.3) Using attachments 4 and 5 of FR-1.3, Response to Voids in Reactor 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 shutdown margin using graphs and reactivity data. Review/Approve a Tagging Order (Faulted)

Candidate will review P&IDs and associated components identified on the tagout required to provide protection.

An error will be identifed (and corrected) by the candidate. Review/Approve a Gaseous Release Permit (Faulted)

Candidate will review a completed permit that contains a calculation error. EAL Classification and Part 1 Form Following the simulator scenario, the CRS candidate will classifiy the 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 Type Code* . . Indian Point Unit 3 Facility:

_______ Exam Level:

RO ~%~~u-~R8~~~

Safety Function Date of Examination:

1 OQ3/06 Operating Test No.: I N, S L, N, S d. RCP #2 Seal Failure Actions

e. Transfer from AFW Feed to Low Flow Bypass Feed ~~ ~ Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) I I 4P 4s System / JPM Title N, s N, s f, Align Containment Spray System During Loss of Emergency Coolant Recirculation

g. Restore Steam Flow Channel to Service 5 7 Emergency Borate

a. A, D Open Steam Supply Valves to 32 ABFP i. b. Reset SI Using Key Switches 4s C. Realign SI For High Head Recirculation

j. Start the Appendix R Diesel k. Align Backup Cooling to the Charging Pumps A, E, N 6 A, E, N, R 8

• Type Codes (A)lternate path (D)irect from bank (C)ontrol room (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A) (RW (P)revious 2 exams (S)imulator ~~~~ ~ h. Adjust R-20 Process Radiation Monitor Setpoints Criteria for RO / SRO-I I SRO-U 4-6 I 4-6 12-3 <9/~8/r;4 21 12 112 I 2 112 I/> 1 22/22/21 2 112 1/21 < 3 I s 3 I 2 (randomly selected)

ES-301, Page 23 of 27 ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 C. Realign SI For High Head Recirculation Date of Examination:

10/23/06 - Operating Test No.: --I A, D, S 3 ~~ ~ Control Room Systems@

(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) N, S N, S f. Align Containment Spray System During Loss of Emergency Coolant Recirculation

g. Restore Steam Flow Channel to Service h. System / JPM Title 5 7 Type Code* Function I I Safety A, D i. Open Steam Supply Valves to 32 ABFP Emergency Borate

a. 4s b. Reset SI Using Key Switches j. Start the Appendix R Diesel k. Align Backup Cooling to the Charging Pumps ~ I I A, E, N 6 A, E, N, R 8

• Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including I(A) (VCA (P)revious 2 exams (S)imulator

d. RCP #2 Seal Failure Actions Criteria for RO I SRO-I I SRO-U 4-6 14-6 12-3 < 91< 8i1; 4 2 1 I2 112 I 2 112 Ilr 1 221~21~1 1; 3 I 2 3 I < 2 (randomly selected) 2 1 I2 1 Is 1 e. Transfer from AFW Feed to Low Flow Bypass Feed I LN,S I 4s ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 System I JPM Title Type Code*

Date of Examination:

10/23/06 Operating Test No.: 1 Safety Function N, S f. Align Containment Spray System During Loss of Emergency Coolant Recirculation

a. 5 I I j. Start the Appendix R Diesel k. Align Backup Cooling to the Charging Pumps C. I I A, E, N 6 A, E, N, R 8 d.

• TvDe Codes ~~ ~ ~ e. Transfer from AFW Feed to Low Flow Bypass Feed Criteria for RO I SRO-I I SRO-U I L, N,S 1 4s h. In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) I I 1. -~ ~ (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including I(A) (P)revious 2 exams Wimulator (RKA 4-6 14-6 I 2-3 5 912 811 4 :, 1 I:, 1 I:, 1 2 1 I:, 1 I:, 1 1212 212 1 5 3 I 5 3 I 5 2 (randomly selected)

, 112 112 1 ~ ~~~ ~ ~

ES-301, Page 23 of 27 Amendix D Scenario Outline Form ES-D-1 4 5 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.

MAL-SGN005D MAL-EPSOO6 Turnover: Continue with the startup. Synchronize the unit to the grid and increase power at 150 MW per hour. 7 Event Malf. MAL-SGN004P I -3 I MAL-SGN005D C (ATC) SG safety fails open on ruptured SG MAL-SIS004A MAL-S ISOO4C Event Type* N (BOP) N (CRS) R (CRS) R (ATC) I (ALL) Event Description Sync turbine and raise power Thot fails high. CRS references TS C (ALL) I SG Tube Leak. CRS references TS M (ALL) SGTR - Manual reactor trip and manual SI actuation ~ ~~ C (BOP) Loss of offsite power when 6.9 KV busses transfer C (BOP) 31 and 33 SI pump auto start failure

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-I Facility: Indian Point 3 Scenario No: 2 I Op-Test No: 1 Examiners: Operators: 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 No: 1 2 3 4 5 6 7 Malf. No. MAL-SWSOOI C M AL-EPS005C NIA MAL-EPSOO 1 MAL-DSG001 A MAL-PRS003D MAL-SWS001 E Event Type* C (BOP) C (ALL) R (ATC) R (CRS) N (BOP) N (CRS) M (ALL) C (BOP) C (ATC) C (BOP) Event Description 33 SWP trips 480V Bus 5A Fault TS required shutdown Station Blackout

~~ 31 EDG fail to start PRZ PORV Fails Open 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 MAL-RCS007C MAL-RCSO12C Facility: Indian Point 3 Scenario No: 3 C (ALL) Op-Test No: 1 MAL-SIS001 A MAL-SIS0013 Examiners: Operators:

C (ATC) Initial Conditions: The scenario begins at 100% power steady state conditions and no equipment 00s. MAL-SIS004B Turnover: Maintain current plant conditions. C (BOP) Event No: 1 2 3 4 5 6 7 8 9 Malf. Event NIA R (ATC) R (CRS) N (BOP) N (CRS) MAL-RCS002C M (ATC) -I- MAL-RCS001 K M (ALL) Event Descri Dtio n PRZR pressure Instrument PT-455 fails high. Spray valves open and actual pressure lowers until manual action is taken. PORV 455C fails open. Block valve can be manually closed to isolate the leak.

Loss of RWST level. Fork truck crashes into RWST resulting in level lowering to about 11 feet over 40 minutes. ~~ ~~ ~ ~~ ~~ Tech Spec Required Shutdown - Due to inoperable RWST, team commences a shutdown.

RCP Seal malfunction - High vibrations and

1. 1 seal degradation. During shutdown, indications of RCP malfunction occur. 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 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 Event No: 1 Facility:

Indian Point 3 Scenario No: 4 r Malf. Event No. Type* XMT-MSSOI 9 I (ATC) R (ATC) R (CRS) Op-Test No: 1 2 3 Opera to rs : I Examiners:

XMT-MSSO19 C (BOP) R (ATC) R (CRS) AL-CFWOOSC C (ALL) I 6 7 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 MAL-CfW001 C C(B0P) MAL-CFW001 B C(B0P) I 4 1 MAL-CFWOIS 1 M (ALL) I 5 1 MAL-RPS002A 1 C(ATC) Event Description PT-412A fails low Loss of Condenser Vacuum Condensate Pump trip FW rupture in Turbine bldg Auto reactor trip failure MDAFP 33 fails to start rDAFP trip