ML14080A502

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Draft-Outlines (Folder 2)
ML14080A502
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 12/10/2013
From: David Silk
Operations Branch I
To:
Entergy Nuclear Indian Point 2
Jackson D
Shared Package
ML13252A147 List:
References
UO1890
Download: ML14080A502 (27)
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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* Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency

& 2 2 2 1 N/A 1 2 N/A 1 9 2 2 4 Abnormal Tier Plant Evolutions Totals 5 5 4 4 5 4 27 5 5 10 2.

1 3 2 3 3 3 2 3 3 2 3 2 28 3 2 5 Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 0 I 2 1 3 Systems Tier Totals 4 3 4 4 4 3 4 4 3 4 2 38 5 3 8

3. Generic Knowledge And 1 2 3 4 1 2 3 4 Abilities Categories 10 7 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

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 following concepts as they apply to the reactor 000007 Reactor Trip- Stabilization- Recovery X -EK1.03 trip: - Reasons for closing the main turbine I 3.7 I1 I I I I 1 governor valve and the main turbine stop valve after a reactor triJ2 Conduct of Operations - Ability to identifY and 000007 Reactor Trip .~ Stabilization - Recovery I 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 Eme~!e~cy Pr~ce~~:_s!Pian- Knowledge of the I 4.0 I 78 I - .. ..... *o

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000011 Large Break LOCA I 3 I X I I EK1.01 ,.- ................ ..., . . I 4.1 I 3 0000 15/0000 17 RCP Malfunctions I 4 X -AA1.12 I ..Malh

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  • I 2.8 I 4 I I meters Knowledge of the reasons for the following 000022 Loss of Rx Coolant Makeup I 2 I I I X I -AK3.04 I responses as they apply to the Loss of Reactor I 3.2 I 5 Coolant Makeue: - Isolating letdown I Knowledge of the interrelations between the 000025 Loss ofRHR System I 4 I I X I I -AK2.05 Loss of Residual Heat Removal System and the I 2.6 I 6
-Reactor Knowledge of the reasons for the following responses as they apply to the Loss of 000026 Loss of Component Cooling Water I 8 I I I X I -AK3.02 I Component Cooling Water:- The automatic I 3.6 I 7 actions (alignments) within the CCWS resulting from the actuation ofthe ESFAS I Ability to determine and interpret the following 000038 Steam Gen. Tube Rupture I 3 I I I L' A '"l 1 0:

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 Knowledge of the operational implications of the Transfer I 4 I X I I I -AK1.01 following concepts as they apply to Steam Line I 4.1 I 10 uences of PTS NUREG 1021 2

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline ES-401 Emer2ency 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 Al I A2 I G I Number I KIA Topic L!1111!- I O#

Emergency Procedures/Plan - Knowledge of EOP implementation hierarchy and coordination 000054 Loss of Main Feedwater I 4 with other support procedures or guidelines such 3.5 14 as, operating procedures, abnormal operating procedures, severe accident management lines.

000055 Station Blackout I 6 Emergency Procedures/Plan - Knowledge of 3.9 12 EOP terms and definitions.

Ability to determine and interpret the following 000055 Station Blackout I 6 as they apply to a Station Blackout: - Actions 4.7 79 to restore Equipment Control - Knowledge of bases in 000056 Loss of Off-site Power I 6 technical specifications for limiting conditions 4.2 77 for ooerations and safetv limits.

Ability to operate and/or monitor the following 000056 Loss of Off-site Power I 6 X as they apply to the Loss of Offsite Power: - 3.3 13 POR V block valve control switch Conduct of Operations - Knowledge of 000057 Loss of Vital AC Electrical Instrument procedures and limitations involved in core 3 8 Bus I 6 alterations.

Knowledge of the reasons for the following 000058 Loss of DC Power I 6 X responses as they apply to the Loss of DC 3.4 11 Power: - Use of DC control oower bv ED/Gs Ability to determine and interpret the following 000062 Loss of Nuclear Svc Water I 4 as they apply to the Loss ofNuclear Service 3.6 80 cause ofoossible SWS loss Ability to determine and interpret the following 000065 Loss of Instrument Air I 8 as they apply to the Loss of Instrument Air: -

2.8 15 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 W/E04 LOCA Outside Containment I 3 X primary coolant, emergency coolant, the decay 3.8 16 heat removal systems, and relations between the proper operation of these systems to the nn~*~*;nn of the facir NUREG 1021 3

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline ES-401 Emergency and Abnormal Plant Evolu~iQI!s - Tier 1 I G_r(>u_Q_l Form ES-401-2 EIAPE #I Name I Safety Function I Kl I K2 I K3j AI I A2 I G I Number I KIA Topic limp. I Q#

Ability to determine and interpret the following WlEOS Inadequate Heat Transfer - Loss of as they apply to the Loss of Secondary Heat Secondary Heat Sink I 4 Sink: - Facility conditions ancl selection of 4.4 81 appropriate procedures during abnormal and Knowledge of the interrelations between the Loss of Secondary Heat Sink and the following:

WIE05 Inadequate Heat Transfer- Loss of

- Components, and functions of control and Secondary Heat Sink I 4 X 3.7 17 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 WIE 11 Loss of Emergency Coolant Recirc. I 4 Recirculation: - Facility conditions and selection 3.4 18 of appropriate procedures during abnormal and NUREG 1021 4

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline ES-401 Emergency and Abn_ormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 E/APE #I Name I Safety Function I Kl I K2 I K3 I AI I A2 I G I Number I KIA Topic limp. I Qtf-000001 Continuous Rod Withdrawal I I 3.8 19 000003 Dropped Control Rod I 1 X 2.6 20 Knowledge of the reasons for the following responses as they apply to the Inoperable/Stuck 000005 Inoperable/Stuck Control Rod I 1 X 3.6 21 Control Rod: -Tech-Spec limits for rod mismatch Ability to determine and interpret the following as they apply to the Loss of Intermediate Range 000033 Loss oflntermediate Range Nl I 7 Nuclear Instrumentation: - Equivalency between 3.0 22 source-range, intermediate-range, and power-channel rP>'~nin<>'<

Knowledge ofthe operational implications of the 000036 Fuel Handling Accident I 8 following concepts as they apply to Fuel X 3.5 23 Handling Incidents: - Radiation exposure hazards Equipment Control - Ability to determine 000037 Steam Generator Tube Leak/ 3 operability and/or availability of safety related 4.6 82 000060 Accidental Gaseous Radwaste Rei. I 9 X 2.7 24 000068 Control Room Evac. I 8 4.8 83 Ability to determine and interpret the following 000069 Loss ofCTMT Integrity I 5 as they apply to the Loss of Containment 3.9 25 Integrity: - Verification of automatic and manual means Of rpofcwincr intPcrritv Ability to operate and/or monitor the following 000074 Inad. Core Cooling I 4 X as they apply to an Inadequate Core Cooling: - 4.1 26 RCS temoerature and oressure indicators NUREG 1021 5

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline ES-401 Emeq~ency and Abnormal Plant Evolutions- Tier 1 I Group 2 Form ES-401-2 EIAPE #I Name I SafetyFunction I KLLK2 I K3 I ~! 1 A2 I G I Number I KIA Topic I Imp. I Q#

Ability to determine and interpret the following as they apply to the SI Termination: - Adherence W/E02 SI Termination I 3 EA2.02 to appropriate procedures and operation within 4.0 84 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, WIE03 LOCA Cool down - Depress. I 4 X EK2.02 including primary coolant, emergency coolant, 3.7 27 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 W/EIO Natural Circ. I 4 Steam Void in Vessel with/without RVLIS:-

EA2.0I 3.9 85 Facility conditions and selection of appropriate procedures during abnormal and emergency NUREG 1021 6

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 003 Reactor Coolant Pump 004 Chemical and Volume IX I I

I I I .. I -

Ill Kl.03 Knowledge of the physical connections and/or I cause-effect relationships between the RCPS and the following s~stems: - RCP seal ~

I Knowledge ofthe effect of a loss or malfunction on the following eves components: - Seal I 3.3 I 28 Control I I I X I I K6.31 I 3 .I I 29 ection s~stem and limits on flow g I Knowledge of the physical connections and/or 005 Residual Heat Removal lx I I I I I I I Ill Kl.l2 cause-effect relationships between the RHRS and the I 3.1 I 30 Ability to (a) predict the impacts of the following malfunctions or operations on the 005 Residual Heat Removal I I I I I I I

  • I Ill A2.01 I RHRS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; - Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation Ability to predict a I 2.9 I 86 006 Emergency Core parameters (to pre\' ""11" '-'.1\."'"'"'""u*o ""'"'J'su Cooling X Al.07 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 I Knowledge of the operational implications of the 007 Pressurizer Relief/Quench Tank I I I I lx I I I

  • K5.02 following concepts as they apply to the PRTS:-

Method of forming a steam bubble in the PZR I 3.1 I 33 I Knowledge of the effect that a loss or 008 Component Cooling Water I I lx I I I I I

  • K3.01 malfunction of the CCWS will have on the following: - Loads cooled b~ CCWS I 3.4 I 34 Ability to (a) predict the impacts of the 008 Component Cooling Water I I I I I I I
  • I
  • A2.02 I following malfunctions or operations on the CCWS and (b) based on tbose predictions, use proeedures to correct, control, or mitigate* the consequences of those malfunctions or I 3.5 I 87 tank level I Knowledge ofthe effect of a loss or malfunction 0 10 Pressurizer Pressure Control I I I I I lx I I Ill K6.01 of the following will have on the PZR PCS:-

Pressure detection I 2.7 I 35 NUREG 1021 7

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 012 Reactor Protection 013 Engineered Safety Features Actuation I I lx I I I I .. I - K3.04 2.1.30 Knowledge of the effect that a loss or I malfunction of the RPS will have on the folio win : - ESF AS Conduct of Operations - Ability to locate and 1 3.8 I 4.4 1 37 I 36 operate components, including local controls.

0 13 Engineered Safety Knowledge of bus power supplies to the Features Actuation following: - ESF AS/safeguards equipment I 3.6 I 38 X K2.01 control I Emergency Procedures/Plan- Knowledge of the 022 Containment Cooling I I I I I I -"')Af"\1"\

bases for prioritizing emergency procedure I 3.4 I 39 ttation during emergenc~ oEerati I Ability to monitor automatic operation of the 022 Containment Cooling I I I I I I v I -A"lf\1 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 Ability to predict and/or monitor changes in 039 Main and Reheat Steam I I I I I I lx I Ill Al.06 1 parameters (to prevent exceeding design limits) associated with operating the MRSS controls I 3.0 I 42 including: - Main steam Eressur Knowledge of the effect that a loss or 059 Main Feedwater lx I I I I - K3.04 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)

I and/or interlock(s) which provide for the 061 Auxiliary /Emergency Feed water I I I lx I I I I Ill K4.02 following: - AFW automatic start upon loss of MFW pump, S/G level, blackout, or safety I 4.5 I 45 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 A.C. Distribution System and (b) based on those Distribution I I I I I I I I Ill A2.04 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 Equipment Control - Ability to analyze the effect 062 AC Electrical Distribution I I I I I I I I Ill 2.2.36 of maintenanc~ activities, such as degraded 1 power sources, on the status oflimitjng I

4 2 1 88 conditions 063 DC Electrical Knowledge of bus power supplies to the Distribution I 2.9 I 47 following: - Major DC loads 064 Emergency Diesel Generator I I I lx I I I

  • I K4.11 1 Knowledge ofED/G System design feature(s) and/or interlock(s) which provide for the following: - Automatic load sequencer:

ds I 3.5 I 49 073 Process Radiation Monitoring lx I I I I I I

  • I
  • Kl.Ol I Knowledge of the physical connections and/or cause-effect relationships between the PRM System and the following systems: - Those served b~ PRMs I 3.6 I 50 073 Process Radiation Monitoring I I I I lx I I
  • I
  • K5.02 1 Knowledge of the operational implications ofthe following con~e~ts ~s they_ apply to the ~RM System: - Radtatwn mtenstty changes wtth I

25 I 51 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 I 3.5 I 52 procedures to correct, control, or mitigate the 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 03 Containment I I I

I I

IX I

I I

I I

I

.. - I 1 ..

. . K4.02

    • ~-

I Knowledge of lAS design feature(s) and/or interlock(s) which provide for the following:-

Cross-over to other air I 3.2 I Ability to manually operate ~*~* ~* ... ~ ... w * ... I 2.7 I 53 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 8 predictions, use procedures to correct, control, or 3

I 90 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 I parameters (to prevent exceeding design limits)

IX I

  • Al.Ol associated with operating the Containment I 3.7 I 55 System controls including: - Containment and NUREG 1021 10

Facility: Indian Pont Unit 2 PWR RO/SRO Examination Outline

  • 001 Control Rod Drive 002 Reactor Coolant IX I I I I I .. I - K2.03 I Knowledge of bus power supplies to the following:- One-line diagram of power supplies to 1o ic circuits Knowledge ofthe effect of a loss or malfunctiu ..

I 2.7 I

25 I 56 I 57 on the following RCS com2onents: - Pum2s

  • Knowledge of the operational implications of the 0 14 Rod Position Indication I I I I lx I I I Ill K5.01 1 following concepts as they apply to the RPIS: -

Reasons for differences between RPIS and step I

27 I 58 counter I

Ability to (a) predict theimpacts of the 014 Rod Position Indication I I I I I I I I .A2.04 following malfunction~ or operations on the RPIS and {b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or I 3.9 I 93 tions:

  • Misaligned rod Knowledge ofNIS design feature(s) and/or 015 Nuclear Instrumentation I I lx I I I I Ill K4.03 1 interlock(s) which provide for the following: -

Reading of source range/intermediate I 3.9 I 59 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 following malfunctions or operations on the ITM 017 In-core Temperature Monitor I I I I I I I I Ill A2.02 1 System and (b) based on those predictions, use procedures to correct, control, or mitigate the I 3 *6 I 60 consequences of those malfunctions or

-Core 029 Containment Purge System (CPS) I I I I I I lx
  • I
  • Al.02 I

1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)

. d wit"h operatmg assoctate . th e Contamment

. Purge controls including: - Radiation levels Ability to (a) predict the impacts of the I

34*

I 62 034 Fuel Handling Equipment I I I I I I I

  • I I

.A2.01 following malfunctions or operations on the Fuel Handling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions 1 or operations: - Dropped fuel element 14

.4 I 91 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 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Ability to perform specific system and 2.1.23 integrated plant procedures during all modes 43 66 of plant operation.

Knowledge of refueling administrative 2.1.40 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 Knowledge of the process for making changes 2.2.6 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.

Equipment Control- Knowledge of the

2. Equipment process for managing maintenance activities Control during power operations, such as risk 2.2.17 3.8 96 assessments, work prioritazation, and coordination with the transmission system operator.

Equipment Control - Knowledge of the process for managing maintenance activities 2.2.18 during shutdown operations, such as, risk 3.9 91 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 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.5 portable survey instruments, personal 2.9 71 monitoring equipment, etc.

Radiological Controls - Knowledge of

3. radiological safety principles pertaining to Radiological licensed operator duties, such as containment 2.3.12 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 Knowledge of crew roles and responsibilities 2.4.13 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 such as the State, the NRC, or the

4. Emergency transmission system operator.

Procedures/plan Emergency Procedures/Plan - Knowledge of 2.4.32 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

E~-401 Record of t<.ejected K/As Form ES-At\.11-4 Tier I Randomly Selected KIA Reason for Rejection Group 0000082307 Radiological Controls - Ability to comply with Rejected because Generic KA is not R 1/1 radiation work permit requirements during normal applicable to Pressurizer Vapor Space Pressurizer Vapor and abnormal conditions. Accident Space 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 applicable to Loss of DC Power.

monitoring equipment, etc.

0000622305 Emergency Procedures/Plan - Knowledge of emergency communications systems and Rejected because this Generic KA is not R 1/1 Loss of Nuclear techniques. applicable to Loss of Nuclear Service Water 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 Knowledge of the reasons for the following 000054K301 responses as they apply to the Loss of Main R 1/1 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 equal to one hour technical specification action Rejected because there are no TS actions s R 1/1 0000572239 statements for systems. one hour for vital AC.

0000052121 Rejected because this Generic KA is best Conduct of Operations -Ability to verify the 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 Conduct of Operations - Knowledge of criteria or 0060002114 Rejected because this Generic KA is best conditions that require plant-wide announcements, 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 Rejected because this Generic KA is best Equipment Control -Ability to obtain and interpret evaluated with a JPM or during a simulator R 2/1 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 following concepts as they apply to the PZR PCS: - Rejected due to overlap with question 2.

Pressurizer Constant enthalpy expansion through a valve Pressure Control 064000A405 Ability to manually operate and/or monitor in the There are no controls for EDGs in the control control room:- Transfer of ED/G control between room at IPEC Unit 2. There is very limited R 2/1 Emergency Diesel 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 the Spent Fuel Pool Cooling System will have on the without a loss of inventory will take an R 2/2 Spent Fuel Pool excessively long time to produce an effect on following: -Area and ventilation radiation monitoring Cooling System radiation monitors. Unable to write a systems (SFPCS) 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.

Rejected because the same Generic KA was Knowledge of operator response to loss of all selected for SRO Only question. Topic too R3 2.4.32 annunciators. narrow in scope to develop 2 independent questions.

OOWE062219 Rejected because this Generic KA is not Equipment Control - Knowledge of maintenance 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 Rejected because action statements for loss Equipment Control -Ability to apply technical of RHR are less than one hour (i.e.,

s 2/1 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 IPEC. This is not a malfunction.

those malfunctions or operations: - Cross-connection with lAS Conduct of Operations - Ability to manage the Rejected because this Generic KA is best S3 2.1.6 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 Administrative Topic D SRO Type

  • Operating Test Number:

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 Criteria for RO I SR0-1 I SRO-U I

(A)Iternate path 4-6 I 4-6 12-3 (C)ontrol room (D)irect from bank :591:581:54 (E)mergency or abnormal in-plant <!11<!11<!1 (EN)gineered safety feature - I - I <!1 (control room system)

(L)ow-Power I Shutdown <!11<!11<!1 (N)ew or (M)odified from bank including 1(A) <!21<!21<!1 (P)revious 2 exams  :::; 3 I :::; 3 I:::; 2 (randomly selected)

(R)CA <!11<!11<!1 (S)imulator

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 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant ~11~11~1 (EN)gineered safety feature - I - I ~1 (control room system)

(L)ow-Power I Shutdown ~11~11~1 (N)ew or (M)odified from bank including 1 (A) ~21~21~1 (P)revious 2 exams  :::; 3 I:::; 3 I:::; 2 (randomly selected)

(R)CA ~11~11~1 (S)imulator

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 R (ATC}

1 N/A N (CRS) Power Escalation N (BOP) 2 MOT- C(BOP)

TS(CRS) 23 SW Pump trips.

SWS008A 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 480V Bus 6A fault.

TS(CRS) 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.

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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 100% 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 R (ATC) 1 N/A N (CRS) Power Reduction N (BOP) 2 MOT- C (ALL)

TS(CRS) 21 Condensate Pump trip. TS for AFD.

CFW001B 3 SST- C(BOP) RCP Thermal Barrier CCW Return Valve (FCV-625) spurious CCW009A C(CRS) closure.

4 MAL- C (ALL)

EPS007B 480V Bus 3A fault.

TS(CRS) 5 CNH- C(ATC)

PCS007D 22 FRY fails in auto.

C(CRS) 6 CVH-M(ALL) 22 FRY fails in manual.

CFW005A 7 MOC-AFW002 Failure of 22 and 23 AFW to start which along with other M(ALL)

CVH- conditions leads to loss of heat sink.

ATS0178 8 AOV-MSS036N C(ALL)

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.

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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 R {ATC) 1 N/A 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)

CAS009A Failure of air to containment making PORVs required for 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.

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