ML14080A502

Draft-Outlines (Folder 2)

ML14080A502
Person / Time
Site:	Indian Point
Issue date:	12/10/2013
From:	Silk D M Operations Branch I
To:	Entergy Nuclear Indian Point 2
Jackson D E
Shared Package
ML13252A147	List: IR 05000247/2014301 ML14043A526 ML14080A500 ML14080A501 ML14080A502 ML14080A503 ML14080A504 ML14080A506 ML14080A507 ML14080A508 ML14091A692 ML14111A374 ML14111A375 ML14111A376
References
UO1890
Download: ML14080A502 (27)

Text

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

Indian Point Unit 2 Printed: 12/1 0/2013 Date Of Exam: 02/10/2014 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G* Total A2 G* 1. 1 3 3 3 3 3 3 18 3 3 Emergency 2 2 2 1 1 2 1 9 2 2 & N/A N/A Abnormal Tier Plant Evolutions Totals 5 5 4 4 5 4 27 5 5 2. 1 3 2 3 3 3 2 3 3 2 3 2 28 3 2 2 1 1 1 1 1 1 1 1 1 1 0 10 0 I 2 1 Plant Systems Tier 4 3 4 4 4 3 4 4 3 4 2 38 5 3 Totals 3. Generic Knowledge And 1 2 3 4 1 2 3 4 Abilities Categories 10 3 2 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable KJA 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 KJA 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 +/-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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KJA 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 KJAs 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 KJA categories.

7.

• The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KJAs. 8. On the following pages, enter the KJA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals(#)

on Form ES-401-3.

Limit SRO selections to KJAs that are linked to 10 CFR 55.43. NUKt:l;; *1 U..CI l Total 6 4 10 5 3 8 7 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 NRC Written Examination Outline ES-401 Emergency and Abnormal Plant Evolutions-Tier 1 I Group 1 Form ES-401-2 E/ APE #I Name I Safety Function I Kl I K2 I K3 I At I A2 I G I Number I KIA Topic I Imp. I Q# Knowledge of the operational implications of the 000007 Reactor Trip-Stabilization-Recovery I X I I I -EK1.03 1 following concepts as they apply to the reactor I 1 trip: -Reasons for closing the main turbine I 3.7 governor valve and the main turbine stop valve after a reactor triJ2 000007 Reactor Trip Stabilization

-Recovery I Conduct of Operations

-Ability to identifY and 1 interpret diverse indications to validate the I 4.3 I 76 res nse of another indication.

Ability to operate and/or monitor the following 000008 Pressurizer Vapor Space Accident I 3 I I I I X AA1.08 I as they apply to the Pressurizer Vapor Space I 3.8 2 Accident:

-PRT level eressure and temeeraturt:

000009 Small Break LOCA I 3 I I I I 2.4.18 I Knowledge of the I 4.0 I 78 000011 Large Break LOCA I 3 I X I I EK1.01 I .. .... *o ..

.. ... "I'I:J w ... .. -. ,.-................

..., . . . . . .. I 4.1 I 3 0000 15/0000 17 RCP Malfunctions I 4 I I X -AA1.12 I .. "I:'I:J w ..

• "'"!:' Malh * -* * -I 2.8 I 4 meters 000022 Loss of Rx Coolant Makeup I 2 I I I I -AK3.04 Knowledge of the reasons for the following X I responses as they apply to the Loss of Reactor I 3.2 I 5 Coolant Makeue: -Isolating letdown 000025 Loss ofRHR System I 4 I I X I I -AK2.05 I Knowledge of the interrelations between the Loss of Residual Heat Removal System and the I 2.6 I 6 :-Reactor Knowledge of the reasons for the following 000026 Loss of Component Cooling Water I 8 I I I I -AK3.02 responses as they apply to the Loss of X I Component Cooling Water:-The automatic I 3.6 I 7 actions (alignments) within the CCWS resulting from the actuation ofthe ESFAS 000038 Steam Gen. Tube Rupture I 3 I I I L' A '"l 1 0: I Ability to determine and interpret the following as they apply to a SGTR: -Pressure at which to I 4.2 I 9 maintain RCS during SIG cooldown 000040 Steam Line Rupture -Excessive Heat I I I I -AK1.01 I Knowledge of the operational implications of the Transfer I 4 X following concepts as they apply to Steam Line I 4.1 I 10 uences of PTS NUREG 1021 2 Facility:

Indian Pont Unit 2 ES-401 E/APE #I Name I Safety Function 000054 Loss of Main Feedwater I 4 000055 Station Blackout I 6 000055 Station Blackout I 6 000056 Loss of Off-site Power I 6 000056 Loss of Off-site Power I 6 000057 Loss of Vital AC Electrical Instrument Bus I 6 000058 Loss of DC Power I 6 000062 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air I 8 W /E04 LOCA Outside Containment I 3 NUREG 1021 PWR RO/SRO Examination Outline NRC Written Examination Outline Emer2ency and Abnormal Plant Evolutions

-Tier 1 I Group 1 Form ES-401-2 I Kl I K2 I K3 I Al I A2 I G I Number I KIA Topic X X X 3 Emergency Procedures/Plan

-Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, severe accident management lines. Emergency Procedures/Plan

-Knowledge of EOP terms and definitions.

Ability to determine and interpret the following as they apply to a Station Blackout:

-Actions to restore Equipment Control -Knowledge of bases in technical specifications for limiting conditions for ooerations and safetv limits. Ability to operate and/or monitor the following as they apply to the Loss of Offsite Power: -POR V block valve control switch Conduct of Operations

-Knowledge of procedures and limitations involved in core alterations.

Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: -Use of DC control oower bv ED/Gs Ability to determine and interpret the following as they apply to the Loss ofNuclear Service cause ofoossible SWS loss Ability to determine and interpret the following as they apply to the Loss of Instrument Air: -Whether backup nitrogen supply is controlling valve oosition Knowledge of the interrelations between the LOCA Outside Containment and the following:

-Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the of the facir L !1111!-I O# 3.5 14 3.9 12 4.7 79 4.2 77 3.3 13 3 8 3.4 11 3.6 80 2.8 15 3.8 16 Facility:

Indian Pont Unit 2 ES-401 EIAPE #I Name I Safety Function W lEOS Inadequate Heat Transfer -Loss of Secondary Heat Sink I 4 WIE05 Inadequate Heat Transfer-Loss of Secondary Heat Sink I 4 W IE 11 Loss of Emergency Coolant Recirc. I 4 NUREG 1021 PWR RO/SRO Examination Outline NRC Written Examination Outline Emergency and Abnormal Plant

-Tier 1 I G_r(>u_Q_l Form ES-401-2 I Kl I K2 I K3j AI I A2 I G I Number I KIA Topic X 4 Ability to determine and interpret the following as they apply to the Loss of Secondary Heat Sink: -Facility conditions ancl selection of appropriate procedures during abnormal and Knowledge of the interrelations between the Loss of Secondary Heat Sink and the following:

-Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Ability to determine and interpret the following as they apply to the Loss of Emergency Coolant Recirculation:

-Facility conditions and selection of appropriate procedures during abnormal and limp. I Q# 4.4 81 3.7 17 3.4 18 Facility:

Indian Pont Unit 2 ES-401 E/APE #I Name I Safety Function 000001 Continuous Rod Withdrawal I I 000003 Dropped Control Rod I 1 000005 Inoperable/Stuck Control Rod I 1 000033 Loss oflntermediate Range Nl I 7 000036 Fuel Handling Accident I 8 000037 Steam Generator Tube Leak/ 3 000060 Accidental Gaseous Radwaste Rei. I 9 000068 Control Room Evac. I 8 000069 Loss ofCTMT Integrity I 5 000074 Inad. Core Cooling I 4 NUREG 1021 PWR RO/SRO Examination Outline NRC Written Examination Outline Emergency and Abn_ormal Plant Evolutions

-Tier 1 I Group 2 Form ES-401-2 I Kl I K2 I K3 I AI I A2 I G I Number I KIA Topic X X X X X 5 Knowledge of the reasons for the following responses as they apply to the Inoperable/Stuck Control Rod: -Tech-Spec limits for rod mismatch Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation:

-Equivalency between source-range, intermediate-range, and channel Knowledge ofthe operational implications of the following concepts as they apply to Fuel Handling Incidents:

-Radiation exposure hazards Equipment Control -Ability to determine operability and/or availability of safety related Ability to determine and interpret the following as they apply to the Loss of Containment Integrity:

-Verification of automatic and manual means Of rpofcwincr intPcrritv Ability to operate and/or monitor the following as they apply to an Inadequate Core Cooling: -RCS temoerature and oressure indicators limp. I Qtf-3.8 19 2.6 20 3.6 21 3.0 22 3.5 23 4.6 82 2.7 24 4.8 83 3.9 25 4.1 26 Facility:

Indian Pont Unit 2 ES-401 EIAPE #I Name I SafetyFunction W /E02 SI Termination I 3 W IE03 LOCA Cool down -Depress. I 4 W/EIO Natural Circ. I 4 NUREG 1021 PWR RO/SRO Examination Outline NRC Written Examination Outline and Abnormal Plant Evolutions-Tier 1 I Group 2 Form ES-401-2 I KLLK2 I K3 I 1 A2 I G I Number I KIA Topic EA2.02 X EK2.02 EA2.0I 6 Ability to determine and interpret the following as they apply to the SI Termination:

-Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments Knowledge of the interrelations between the LOCA Cooldown and Depressurization and the following:

-Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the ooeration of the Ability to determine and interpret the following as they apply to the Natural Circulation with Steam Void in Vessel with/without Facility conditions and selection of appropriate procedures during abnormal and emergency I Imp. I Q# 4.0 84 3.7 27 3.9 85 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 003 Reactor Coolant Pump I X I I I I .. I -Kl.03 Knowledge of the physical connections and/or I cause-effect relationships between the RCPS and I 3.3 I 28 the following

-RCP seal 004 Chemical and Volume I Control I I I X I I Ill K6.31 I Knowledge ofthe effect of a loss or malfunction on the following eves components:

-Seal I 3 .I I 29 ection and limits on flow g 005 Residual Heat lx I I I I I I

• I Ill Kl.l2 I Knowledge of the physical connections and/or Removal cause-effect relationships between the RHRS I 3.1 I 30 and the Ability to (a) predict the impacts of the following malfunctions or operations on the 005 Residual Heat I I I I I I I

• I Ill A2.01 RHRS and (b) based on those predictions, use Removal I procedures to correct, control, or mitigate the I 2.9 I 86 consequences of those malfunctions or operations;

-Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation 006 Emergency Core Ability to predict a Cooling X Al.07 parameters (to pre\' ""11" '-'.1\."'"'"'""u*o

""'"'J'su IJlllUJ, I 3.3 I 31 associated with operating the ECCS control! includin : -Pressure, hi h and low 007 Pressurizer Ability to monitor automatic operation of the Relief/Quench Tank A3.01 PRTS, including:-

Components which discharge I 2.7 I 32 to the PRT 007 Pressurizer I I I I lx I I

• I

• K5.02 I Knowledge of the operational implications of the Relief/Quench Tank following concepts as they apply to the PRTS:-I 3.1 I 33 Method of forming a steam bubble in the PZR 008 Component Cooling I I lx I I I I

• I

• K3.01 I Knowledge of the effect that a loss or Water malfunction of the CCWS will have on the I 3.4 I 34 following:

-Loads cooled CCWS Ability to (a) predict the impacts of the 008 Component Cooling I I I I I I I

• I

• A2.02 following malfunctions or operations on the I CCWS and (b) based on tbose predictions, use Water proeedures to correct, control, or mitigate*

the I 3.5 I 87 consequences of those malfunctions or tank level 0 10 Pressurizer Pressure I I I I I lx I

• I Ill K6.01 I Knowledge ofthe effect of a loss or malfunction Control of the following will have on the PZR PCS:-I 2.7 I 35 Pressure detection NUREG 1021 7 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 012 Reactor Protection I I lx I I I I .. I -K3.04 Knowledge of the effect that a loss or I malfunction of the RPS will have on the 1 3.8 1 37 folio win : -ESF AS 013 Engineered Safety Conduct of Operations

-Ability to locate and Features Actuation 2.1.30 operate components, including local controls.

I 4.4 I 36 0 13 Engineered Safety Knowledge of bus power supplies to the Features Actuation X K2.01 following:

-ESF AS/safeguards equipment I 3.6 I 38 control 022 Containment Cooling I I I I I I --"')Af"\1"\

I Emergency Procedures/Plan-Knowledge of the bases for prioritizing emergency procedure I 3.4 I 39 ttation during oEerati 022 Containment Cooling I I I I I I v I -A"lf\1 I Ability to monitor automatic operation of the CCS, including:

-Initiation of safeguards mode I 4.1 I 40 of o2eration Ability to (a) predict the impacts of the following malfunctions or operations on the CSS 026 Containment Spray I I I I I I -I -A"'f\"l I and (b) based on those predictions, use I 4.1 I 41 procedures to correct, control, or mitigate the consequences of those malfunctions or :-Failure ofESF 039 Main and Reheat I I I I I I lx

• I Ill Al.06 1 Ability to predict and/or monitor changes in Steam parameters (to prevent exceeding design limits) I 3.0 I 42 associated with operating the MRSS controls including:

-Main steam Eressur 059 Main Feedwater lx I I I I .. -K3.04 Knowledge of the effect that a loss or malfunction of the MFW System will have on 3.6 43 the followin : -RCS 059 Main Feedwater Ability to manually operate and/or

... ... w *... I 3.1 I 44 the control room: -MFW turbine triE indicatio Knowledge of AFW System design feature(s) 061 Auxiliary

/Emergency I I I lx I I I

• I Ill K4.02 I and/or interlock(s) which provide for the Feed water following:

-AFW automatic start upon loss of I 4.5 I 45 MFW pump, S/G level, blackout, or safety .. ection NUREG 1021 8 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 Ability to (a) predict the impacts of the following malfunctions or operations on the 062 AC Electrical I I I I I I I

• I Ill A2.04 I A.C. Distribution System and (b) based on those Distribution predictions, use procedures to correct, control, or I 3.4 I 46 mitigate the consequences of those malfunctions or operations:

-Effect on plant of de-energizing a bus 062 AC Electrical Ability to manually operate and/or monitor in Distribution the control room: -Synchronizing and I 3.1 I 48 of different AC SUEElies 062 AC Electrical I I I I I I I

• I Ill 2.2.36 1 Equipment Control -Ability to analyze the effect Distribution of activities, such as degraded I 4 2 1 88 power sources, on the status oflimitjng

• conditions 063 DC Electrical Distribution Knowledge of bus power supplies to the I 2.9 I 47 following:

-Major DC loads 064 Emergency Diesel I I I lx I I I

• I 1 Knowledge ofED/G System design feature(s)

Generator K4.11 and/or interlock(s) which provide for the I 3.5 I 49 following:

-Automatic load sequencer:

ds 073 Process Radiation lx I I I I I I

• I

• Kl.Ol I Knowledge of the physical connections and/or Monitoring cause-effect relationships between the PRM I 3.6 I 50 System and the following systems: -Those served PRMs 073 Process Radiation I I I I lx I I

• I

• K5.02 1 Knowledge of the operational implications ofthe Monitoring following they_ apply to the I 2 5 I 51 System: -Radtatwn mtenstty changes wtth

• source distance Ability to (a) predict the impacts of the following malfunctions or operations on the 076 Service Water I I I I I I I -I -

I SWS and (b) based on those predictions, use procedures to correct, control, or mitigate the I 3.5 I 52 consequences of those malfunctions or -Loss ofSWS 076 Service Water I I I I I I I -I --*-I Emergency Procedures/Plan

• Knowledge of how abnormal operating procedures are used in I 4.5 I 89 EOPs, NUREG 1021 9 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 078 Instrument Air I I I IX I I I I .. K4.02 I Knowledge of lAS design feature(s) and/or interlock(s) which provide for the following:-

I 3.2 I 53 Cross-over to other air I 03 Containment I I I I I .. 1 .. -I Ability to manually operate ... ... w* ... I 2.7 I 54 the control room: -ESF slave rela):'S Ability to (a) predict the impacts of the following malfunctions or operations on the 103 Containment I I I I I I I -I -*---I Contaimnent System and (b) based on those I 3 8 I 90 predictions, use procedures to correct, control, or

• mitigate the consequences of those malfunctions or OQerations:

-Phase A and B isolation Ability to predict and/or monitor changes in I 03 Containment I I I I I IX I

• Al.Ol I parameters (to prevent exceeding design limits) associated with operating the Containment I 3.7 I 55 System controls including:

-Containment and NUREG 1021 10

• PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 001 Control Rod Drive IX I I I I I .. I -K2.03 I Knowledge of bus power supplies to the following:-

One-line diagram of power supplies I 2.7 I 56 to 1o ic circuits 002 Reactor Coolant Knowledge ofthe effect of a loss or malfunctiu

.. I on the following RCS com2onents:

-Pum2s 2*5 I 57 0 14 Rod Position I I I I lx I I

• I Ill K5.01 1 Knowledge of the operational implications of the Indication following concepts as they apply to the RPIS: -I 2 I 58 Reasons for differences between RPIS and step *7 counter Ability to (a) predict theimpacts of the 014 Rod Position I I I I I I I

• I .A2.04 I following or operations on the Indication RPIS and {b) based on those predictions, use I 3.9 I 93 procedures to correct, control, or mitigate the consequences of those malfunctions or tions:

• Misaligned rod 015 Nuclear I I lx I I I

• I Ill K4.03 1 Knowledge ofNIS design feature(s) and/or Instrumentation interlock(s) which provide for the following:

-I 3.9 I 59 Reading of source range/intermediate ran e/ ower ran e outside control room 016 Non-Nuclear Knowledge of the effect that a loss or Instrumentation System malfunction of the NNIS will have on the I 3.5 I 61 following:

-ESF AS Ability to (a) predict the impacts of the 017 In-core Temperature I I I I I I I

• I Ill A2.02 1 following malfunctions or operations on the ITM Monitor System and (b) based on those predictions, use I 60 procedures to correct, control, or mitigate the I 3*6 consequences of those malfunctions or :-Core 029 Containment Purge I I I I I I lx

• I

• Al.02 1 Ability to predict and/or monitor changes in System (CPS) parameters (to prevent exceeding design limits) I I 62 . d "h . h . 34 assoctate wit operatmg t e Contamment Purge

• controls including:

-Radiation levels Ability to (a) predict the impacts of the 034 Fuel Handling I I I I I I I

• I .A2.01 I following malfunctions or operations on the Fuel Equipment Handling System and (b) based on those I 91 predictions, use procedures to correct, control, or 1 4.4 mitigate the consequences of those malfunctions I 1 or operations:

-Dropped fuel element NUREG 1021 11 Generic Knowledge and Abilities Outline (Tier 3) PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 Form ES-401-3 Facility I Indian Point Unit 3 I Date of Exam Category KIA# Topic RO SRO-Only IR Q# IR Q# Ability to perform specific system and 2.1.23 integrated plant procedures during all modes 43 66 of plant operation.

2.1.40 Knowledge of refueling administrative requirements.

2.8 67 Ability to identify and interpret diverse I. Conduct of 2.1.45 indications to validate the response of another 4.3 68 Operations indication.

Conduct of Operations-Ability to interpret 2.1.25 reference materials such as graphs, curves, 4.2 94 tables etc; Conduct of Operations

-Knowledge of 2.1.36 procedures and limitations involved in core 4.1 95 alterations.

Subtotal 3 2 2.2.6 Knowledge of the process for making changes to procedures.

3.0 69 2.2.12 Knowledge of surveillance procedures.

3.7 70 Knowledge of bases in technical 2.2.25 specifications for limiting conditions for 3.2 75 operations and safety limits. 2. Equipment Equipment Control-Knowledge of the Control process for managing maintenance activities 2.2.17 during power operations, such as risk 3.8 96 assessments, work prioritazation, and coordination with the transmission system operator.

Equipment Control -Knowledge of the 2.2.18 process for managing maintenance activities 3.9 91 during shutdown operations, such as, risk assessments,*work prioritization, etc. Subtotal 3 2 NUREG 1021 13 Generic Knowledge and Abilities Outline (Tier 3) PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 2 Form ES-401-3 Facility I Indian Point Unit 3 I Date of Exam Category KIA# Topic RO SRO-Only IR Q# IR Q# Ability to use radiation monitoring systems, 2.3.5 such as fixed radiation monitors and alarms, portable survey instruments, personal 2.9 71 monitoring equipment, etc. Radiological Controls -Knowledge of 3. radiological safety principles pertaining to Radiological 2.3.12 licensed operator duties, such as containment Controls entry requirements, fuel handling 3.2 72 responsibilities, access to locked high-radiation areas, aligning filters, etc. Radiological Controls -Knowledge of 2.3.4 radiation exposure limits under normal and 3.7 98 emergency conditions.

Subtotal 2 I 2.4.13 Knowledge of crew roles and responsibilities during EOP usage. 4.0 73 Knowledge of events related to system operation/status that must be reported to 2.4.30 internal organizations or external agencies, 2.7 74 4. Emergency such as the State, the NRC, or the Procedures/plan transmission system operator.

2.4.32 Emergency Procedures/Plan

-Knowledge of 4.0 99 ..*. operator response to loss of all annunciators.

Emergency Procedures/Plan

-* Ability to 2.4.46 veritY that the alarms are consistent with the 4.2 100 plant conditions.

Subtotal 2 2 Tier 3 Point Totals to 7 NUREG 1021 14 Description of program used to generate IPEC Unit 2 February 10, 2014 Written Exam K/As Generated the RO and SRO sample plan using the "NKEG" Database Program, version 1.1, developed by Westinghouse Electric Company. This program will automatically produce a Random Sample Plan based on NUREG 1122, Rev. 2, Supplement 1 K/As. K/As were suppressed prior to the outline generation process as provided for in the examiner standard, the list of suppressed K/As is provided as required by the examiners standard.

Inappropriate and inapplicable K/As were discarded during the outline development process and are included in the record of rejected K/As. The replacement K/As were replaced using the random sample function of the NKEG database program. NUREG 1021 15

Record of t<.ejected K/As Form ES-At\.11-4 Tier I Randomly Selected KIA Group Reason for Rejection 0000082307 Radiological Controls -Ability to comply with Rejected because Generic KA is not R 1/1 Pressurizer Vapor radiation work permit requirements during normal applicable to Pressurizer Vapor Space Space Accident and abnormal conditions.

Accident 000029A104 Ability to operate and/or monitor the following as R 1/1 they apply to a ATWS:-BIT inlet valve switches Rejected because the BIT has been removed. ATWS Radiological Controls -Ability to use radiation 0000582305 monitoring systems, such as fixed radiation monitors Rejected because this Generic KA is not R 1/1 and alarms, portable survey instruments, personnel Loss of DC Power monitoring equipment, etc. applicable to Loss of DC Power. 0000622305 Emergency Procedures/Plan

-Knowledge of R 1/1 Loss of Nuclear emergency communications systems and Rejected because this Generic KA is not Service Water techniques.

applicable to Loss of Nuclear Service Water 0000272130 Pressurizer Conduct of Operations -Ability to locate and Rejected because this KA is best evaluated R 1/1 Pressure Control operate components, including local controls.

during Simulator or JPM examination.

Unable System to write a discriminatory RO question.

Malfunction 000054K301 Knowledge of the reasons for the following R 1/1 responses as they apply to the Loss of Main Loss of main Feedwater (MFW): -Reactor and/or turbine trip, Rejected due to overlap with question 1. Feedwater manual and automatic Equipment Control -Knowledge of less than or R 1/1 0000572239 equal to one hour technical specification action Rejected because there are no TS actions s statements for systems. one hour for vital AC. 0000052121 Conduct of Operations -Ability to verify the Rejected because this Generic KA is best R 1/2 Inoperable/Stuck controlled procedure copy. evaluated with a JPM. Unable to write a Control Rod discriminatory RO question.

ES-401 Record of t<ejected K/As Form ES-401-4 0060002114 Conduct of Operations

-Knowledge of criteria or conditions that require plant-wide announcements, Rejected because this Generic KA is best R 2/1 Emergency Core such as pump starts, reactor trips, mode changes, evaluated during simulator scenarios.

Unable Cooling etc. to write a discriminatory RO question.

0260002241 Equipment Control -Ability to obtain and interpret Rejected because this Generic KA is best R 2/1 evaluated with a JPM or during a simulator Containment station electrical and mechanical drawings.

scenario.

Unable to write a discriminatory RO Spray question.

010000K502 Knowledge of the operational implications of the R 2/1 Pressurizer following concepts as they apply to the PZR PCS: -Rejected due to overlap with question 2. Pressure Control Constant enthalpy expansion through a valve 064000A405 Ability to manually operate and/or monitor in the There are no controls for EDGs in the control R 2/1 Emergency Diesel control room:-Transfer of ED/G control between room at IPEC Unit 2. There is very limited manual and automatic indication.

Unable to write a discriminatory Generator RO question.

033000K302 Knowledge of the effect that a loss or malfunction of Rejected because at IPEC a loss of cooling R 2/2 Spent Fuel Pool the Spent Fuel Pool Cooling System will have on the without a loss of inventory will take an Cooling System following: -Area and ventilation radiation monitoring excessively long time to produce an effect on (SFPCS) systems radiation monitors.

Unable to write a discriminatory RO question.

035000A302 Ability to monitor automatic operation of the S/G, Rejected because MAD valves are not R 2/2 including:

-MAD valves Steam Generator applicable at IPEC. Knowledge of operator response to loss of all Rejected because the same Generic KA was R3 2.4.32 selected for SRO Only question.

Topic too annunciators.

narrow in scope to develop 2 independent questions.

OOWE062219 Equipment Control -Knowledge of maintenance Rejected because this Generic KA is not s 1/2 Inadequate Core work order requirements.

related to Inadequate Core Cooling. Unable to Cooling write a discriminatory SRO question.

ES-401 Record of t<ejected K/As Form ES-401-4 0000252240 Equipment Control -Ability to apply technical Rejected because action statements for loss s 2/1 of RHR are less than one hour (i.e., Loss of RHR specifications for a system immediately).

Unable to write a discriminatory System SRO question.

Ability to (a) predict the impacts of the following malfunctions or operations on the SAS and (b) 079000A201 based on those predictions, use procedures to Rejected because Station Air and Instrument s 2/2 correct, control, or mitigate the consequences of Air systems are normally cross connected at Station Air those malfunctions or operations:

-Cross-IPEC. This is not a malfunction.

connection with lAS S3 2.1.6 Conduct of Operations

-Ability to manage the Rejected because this Generic KA is best control room crew during plant transients.

evaluated during simulator scenarios.

Unable to write a discriminatory SRO question.

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

IPEC Unit 2 Date of Examination:

Feb 10, 2014 Examination Level: RO

• SRO D Operating Test Number: Administrative Topic Type Describe activity to be performed (see Note) Code* Replace a Watchstander Due to Illness Conduct of Operations M,R (KA GENERIC 2.1.5 R0-2.9 SR0-3.9) Determine Reactor Vessel Venting Time Per FR-1.3, Conduct of Operations M,R Attachment 1 (KA GENERIC 2.1.25 R0-3.9 SR0-4.2) Demonstrate Proficiency in use of Generator Capability Equipment Control M,R Curve (KA GENERIC 2.2.41 R0-3.5 SR0-3.9) Review a SG Tube Leakrate Determination using 2-Radiation Control M,R AOP-SG-1 (KA GENERIC 2.3.14 R0-3.4 SR0-3.8) Emergency Procedures/Plan NARO 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; ::; 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2:: 1) (P)revious 2 exams (s 1; randomly selected)

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

IPEC Unit 2 Date of Examination:

Feb 10, 2014 Examination Level: RO D SRO

• Operating Test Number: Administrative Topic Type Describe activity to be performed (see Note) Code* Replace a Watchstander Due to Illness Conduct of Operations M,R (KA GENERIC 2.1.5 R0-2.9 SR0-3.9) Determine Reactor Vessel Venting Time Per FR-1.3, Conduct of Operations M,R Attachment 1 (KA GENERIC 2.1.25 R0-3.9 SR0-4.2) Demonstrate Proficiency in use of Generator Capability Equipment Control M,R Curve (KA GENERIC 2.2.41 R0-3.5 SR0-3.9) Review a SG Tube Leakrate Determination using 2-Radiation Control M,R AOP-SG-1 (KA GENERIC 2.3.14 R0-3.4 SR0-3.8) Classify Emergency Events requiring Emergency Plan Emergency Procedures/Plan Implementation (Time Critical} (KA GENERIC 2.4.38 SR0-4.4) 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 3 for ROs; 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

IPEC Unit2 Date of Examination:

Feb 10, 2014 Examination Level: RO

• SRO D Operating Test Number: Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. Emergency Borate (004000A4.18 R0-4.3 SR0-4.1) A,S,M 1 b. Perform the Required Action to Align the Sl System for A,D,S,EN 2 Recirculation during Transfer to Cold Leg Recirculation (000011A1.11 R0-4.2 SR0-4.2) c. Respond to a Pressurizer Low Pressure Alarm A,N,S 3 (000027A1.01 R0-4.0 SR0-3.9) d. Transfer Main Feed from LFBV to MFRVs During Power N, S, L 4S Ascension (059000A4.03 R0-2.9 SR0-2.9) e. Perform the Required Actions to Reset FCU Services and D,S,EN 5 Ventilation (022000A4.01 R0-3.6 SR0-3.6) f. Transfer Buses 1, 2, 3, or 4 to the Unit Auxiliary D,S,L 6 Transformer (062000A4.01 R0-3.3 SR0-3.1) g. Respond to Instrument Failure (412A low Rods do not stop) A, D, S, 7 016000A2.01 R0-3.0 SR0-3.1) h. Start a Reactor Coolant Pump (003000A4.

06 R0-2.9 SRO-D, S, 4P 2.9) In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U) i. Align Nitrogen Bottle to the Atmospheric SO (016000A2.01 N,E 8 R0-4.3 SR0-4.5) j. Release a small gas decay tank (071000A4.05 R0-2.6 D,R 9 SR0-2.6) k. Perform the Required Actions to Locally Start 21 Charging A, D, R, E 2 Pump Without Instrument Air Available (000068A 106 RO-4.1 SR0-4.2) @ All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes I Criteria for RO I SR0-1 I SRO-U (A)Iternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator 4-6 I 4-6 12-3 :591:581:54

<!11<!11<!1

-I -I <!1 (control room system) <!11<!11<!1

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3 I

::; 3 I:::; 2 (randomly selected)

<!11<!11<!1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

IPEC Unit2 Date of Examination:

Feb 10, 2014 Examination Level: RO D SRO

• Operating Test Number: Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. Emergency Borate (004000A4.18 R0-4.3 SR0-4.1) A,S,M 1 b. Perform the Required Action to Align the Sl System for A,D,S,EN 2 Recirculation during Transfer to Cold Leg Recirculation (000011A 1.11 R0-4.2 SR0-4.2) c. Respond to a Pressurizer Low Pressure Alarm A, N,S 3 (000027A1.01 R0-4.0 SR0-3.9) d. Transfer Main Feed from LFBV to MFRVs During Power N,S, L 4S Ascension (059000A4.03 R0-2.9 SR0-2.9) e. Perform the Required Actions to Reset FCU Services and D,S,EN 5 Ventilation (022000A4.01 R0-3.6 SR0-3.6) f. Transfer Buses 1, 2, 3, or 4 to the Unit Auxiliary D,S, L 6 Transformer (062000A4.01 R0-3.3 SR0-3.1) g. Respond to Instrument Failure (412A low Rods do not stop) A, 0, S, 7 016000A2.01 R0-3.0 SR0-3.1) h. NASRO In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U) i. Align Nitrogen Bottle to the Atmospheric SO (016000A2.01 N,E 8 R0-4.3 SR0-4.5) j. Release a small gas decay tank (071000A4.05 R0-2.6 D,R 9 SR0-2.6) k. Perform the Required Actions to Locally Start 21 Charging A,D, R,E 2 Pump Without Instrument Air Available (000068A106 RO-4.1 SR0-4.2) @ All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes I Criteria for RO I SR0-1/ SRO-U (A)Iternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator 4-6 I 4-6 I 2-3 S91S81S4

-I -I (control room system)

3 I

::; 3 I:::; 2 (randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

IPEC Unit 2 Date of Examination: Feb 10, 2014 Examination Level: RO D SRO

• Operating Test Number: Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. NA SRO-U b. Perform the Required Action to Align the Sl System for A, D,S, EN 2 Recirculation during Transfer to Cold Leg Recirculation (000011A 1.11 R0-4.2 SR0-4.2) C. Respond to a Pressurizer Low Pressure Alarm A, N,S 3 (000027A1.01 R0-4.0 SR0-3.9) d. NASRO-U e. NASRO-U f. Transfer Buses 1, 2, 3, or 4 to the Unit Auxiliary D,S, L 6 Transformer (062000A4.01 R0-3.3 SR0-3.1) g. NASRO-U h. NASRO-U In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U) i. Align Nitrogen Bottle to the Atmospheric SD (016000A2.01 N,E 8 R0-4.3 SR0-4.5) j. Release a small gas decay tank (071000A4.05 R0-2.6 D, R 9 SR0-2.6) k. NA SRO-U @ All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO I SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :::;gl:::;81:::;4 (E)mergency or abnormal in-plant ;e:11;e:11;e:1 (EN)gineered safety feature -I -I ;e:1 (control room system) (l)ow-Power I Shutdown ;e:11;e:11;e:1 (N)ew or (M)odified from bank including 1 (A) ;e;21;e;21;e;1 (P)revious 2 exams :::; 3 I :::; 31 :::; 2 (randomly selected) (R)CA ;e:11;e:1/;e:1 (S)imulator Facility:

Indian Point 2 Scenario No.: 1 Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 90% power IC Load Simulator Schedule-Scenario1 The Plant is at 90% power. 22 Sl Pump is OOS Ensure 23 Charging Pump, 23 SWP and 26 SWP are in service Turnover:

Return plant to 100% power over the next hour. Event Malf. No. Event Event No. Type* Description 1 N/A R (ATC} N (CRS) Power Escalation N (BOP) 2 MOT-C(BOP) 23 SW Pump trips. SWS008A TS(CRS) 3 XMT-I (ATC) SGN034A I (CRS) PT-404 Steam Header Pressure fails high causing MBFPs to be placed in manual. 4 MAL-C (ALL) EPS007D TS(CRS) 480V Bus 6A fault. 5 MAL-M(ALL) Small Break LOCA RCS006A 6 BKR-PPL003/4 M(ALL) ATWS 7 MOC-C(CRS) AFW001 21 AFW Pump failure C(BOP) 8 RLY-PPL487/48 C(CRS) Automatic Safety Injection failure 8 9 RLY-C(CRS) PPL085/09 Phase A Isolation failure 0 C(BOP) * (N)ormal, (R)eactivity, (l)nstrument, _{C)omponent, (M)ajor U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 1 of 16 Facility:

Indian Point 2 Scenario No.: 2 Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 100% power IC Load Simulator Schedule-Scenario2 The Plant is at 1 00% power. Ensure 25 SWP and 22 Charging Pump in service. Turnover:

Perform power reduction to 90% for turbine valve testing. Event Malf. No. Event Event No. Type* Description 1 N/A R (ATC) N (CRS) Power Reduction N (BOP) 2 MOT-C (ALL) 21 Condensate Pump trip. TS for AFD. CFW001B TS(CRS) 3 SST-C(BOP) RCP Thermal Barrier CCW Return Valve (FCV-625) spurious CCW009A C(CRS) closure. 4 MAL-C (ALL) EPS007B TS(CRS) 480V Bus 3A fault. 5 CNH-C(ATC) PCS007D C(CRS) 22 FRY fails in auto. 6 CVH-M(ALL) 22 FRY fails in manual. CFW005A 7 MOC-AFW002 M(ALL) Failure of 22 and 23 AFW to start which along with other CVH-conditions leads to loss of heat sink. ATS0178 8 AOV-C(ALL) MSS036N Failure of Turbine Stop/Control Valve pair. CVH-MSS0308 9 AOV-C(ALL) RCS002A Failure of PORV requiring opening of reactor head vent valves * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page1of19 Facility:

Indian Point 2 Scenario No.: 3 Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 4% power IC Load Simulator Schedule-Scenario3 The Plant is at 4% power. 23 Charging Pump is OOS. 22 MBFP is OOS. PORV 456 is OOS Ensure 21 Charging Pump in service, Ensure 23 CCW Pump is in service Turnover:

Perform power ascension to 10% for turbine sync. Event Malf. No. Event Event No. Type* Description 1 N/A R {ATC) N (CRS) Power Ascension N (BOP) 2 MOT-C {ATC) CVC003B C(CRS) 21 Charging Pump trip TS(CRS) 3 MOC-C (BOP) 23 CCW pump trip with failure of other CCW pumps to CCW003A C (CRS) auto start 4 XMT-TS(CRS) Control Rod DB IRPI fails low. CRF012A 5 XMT-C (ALL) PT-408A fails high causing 21 MFW Pump to go to minimum CFW036A speed. 6 MAL-M(ALL) 21 MFW Pump trips. ATS005A 7 MAL-RCS014D M(ALL) 24 SGTR. 8 AOV-C(ALL) Failure of air to containment making PORVs required for CAS009A depressurization.

9 AOV-C(ALL) RCS002A PORV will not close causing team to transition to ECA-3.1 * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, i_Mlaj_or U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 1 of 19