ML14080A506

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Final Outlines (Folder 3)
ML14080A506
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/07/2014
From: David Silk
Operations Branch I
To:
Entergy Nuclear Indian Point 2
Jackson D
Shared Package
ML13252A147 List:
References
UO1890
Download: ML14080A506 (29)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facilitl£: 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 K5 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 2 N/A 1 2 N/A 0 9 2 2 4 Abnormal Tier Plant Evolutions Totals 5 5 5 4 5 3 27 5 5 10 1 3 2 3 3 3 2 3 3 2 3 2 28 3 2 5 2.

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;; 1UL1 I

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline ES-401 Emergency and Abnormal Plant Evolutions- Tier 1 I Grol!I!_ 1 Form ES-401-2 EIAPE #I Name I Safe!y Function I KllK2 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 I1 X trip:- Reasons for closing the main turbine I 3.7 governor valve and the main turbine stop valve after a reactor 000007Reactor I *. .Trip

  • Stabilization
  • .*.* - Recovery./

.*. .. 4.3 76 000008 Pressurizer Vapor Space Accident I 3 3.8 2 000009 Slll;all }3rea.k LOCA I 3 000011 Large Break LOCA I 3 X 4.1 3 u.pp*) ................... .1.'-"""'-""""-'1.  !,..I.J.J.&p I

U..,;J .... .._) '-V'VUA*.t.II. ..._

0000151000017 RCP Malfunctions I 4 X AAl.l2 2.8 4 Malfunctions: -Reactor coolant loop flow meters Knowledge of the reasons for the following 000022 Loss ofRx Coolant Makeup I 2 X AK3.04 resoonses as they apply to the Loss of Reactor 3.2 5 eu : - lsolatin letdown Knowledge of the interrelations between the 000025 Loss of RHR System I 4 I I X I I -AK2.05 I Loss of Residual Heat Removal System and the I 2.6 I 6

- Reactor building sum~

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 I 1:' A,..., 1 C as they apply to a SGTR: - Pressure at which to I 4.2 I 9 maintain RCS durin SIG cooldown 000040 Steam Line Rupture - Excessive Heat Knowledge of the operational implications of the Transfer /4 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 Emergency and Abnormal Plant Evolutions- Tier 1/ Group 1 Form ES-401-2 EIAPE #I Name I Safety Function I Kl I K2 I K3 I Al I A2 I G I Number I KIA Topic I !!I!I!-1_Q#

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 000055 Station Blackout I 6 3.9 12 00005,5 Station Black9\lt I 6 79 000056 Loss of Off-site Power /p Ability to operate and/or monitor the following 000056 Loss of Off-site Power I 6 as they apply to the Loss of Offsite Power: - I 3.3 I 13 PORV block valve control switch Conduct of Operations - Knowledge of 000057 Loss of Vital AC Electrical Instrument Bus I 6 procedures and limitations involved in core I 3 I 8 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 I 3.4 I ll Power:- Use of DC control Eower bv ED/Gs Apility to Q.etermine and interpret 000062 Loss ofN\JClear Svc Water I 4 w as they apply the Loss ofNuclear Service- I I 3.6 80 Water:

Ability to determine and interpret the following 000065 Loss of Instrument Air I 8 as they apply to the Loss oflnstrument Air: -

I 2.8 I 15 Whether backup nitrogen supply is controlling valve Eosition 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 I 3.8 I 16 heat removal systems, and relations between the proper operation of these systems to the of the NUREG 1021 3

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 EIAPE #I Name I Safe!Y_ Function ] Kl IJ.au] K3 TAl I AT] G I Number I KIA Topic I Imp. I Q#

.Apility to d~~rmine and interpret the follow in& .

WIE05 Ina(leqUfi!e Heat Transfer- Loss of . as tll~Y. apply t9tlle Lo$S of Seconctm-Y Heat

  • S~Qndary HeatJSinkl 4 . . Sink:~.J?acility coJld,itions and selection of l 4..4 81 aooronriate proce4Ure~ duriJ!i ~bnortllll1 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 Emer2ency and Abnormal 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 At I A2 I G I Number I KIA Topic I Imp. I Q#

Knowledge of the operational implications ofthe 000003 Dropped Control Rod I 1 following concepts as they apply to Dropped X I 2.6 I 20 Control Rod: - Definitions of core quadrant tilt Knowledge of the reasons for the following responses as they apply to the Inoperable/Stuck 000005 Inoperable/Stuck Control Rod I 1 X I 3.6 I 21 Control Rod: - Tech-Spec limits for rod mismatch Ability to determine and interpret the following as they apply to the Loss oflntermediate Range 000033 Loss oflntermediate Range NI I 7 Nuclear Instrumentation:- Equivalency between I 3.0 I 22 source-range, intermediate-range, and power-channel readings Knowledge of the operational implications of the 000036 Fuel Handling Accident I 8 following concepts as they apply to Fuel X I 3.5 I 23 Handling Incidents: - Radiation exposure hazards Equipment Control - Ability to determine

. 00003 7 Steant G~eratQr Wbe ~I 3 operability and/or availability of safe~ related ent.

Knowledge of the interrelations between the 000060 Accidental Gaseous Radwaste Rei. I 9 Accidental Gaseous Radwaste Release and the X 2.7 24 000068 Control Room Evac. I 8 tbe

!llSll;:fltlj.

4.8 83 Ability to determine and interpret the following 000069 Loss of CTMT Integrity I 5 as they apply to the Loss of Containment I 39 I 25 Integrity: - Verification of automatic and manual

  • means of Ability to operate and/or monitor the following 000074 Inad. Core Cooling I 4 X as they apply to an Inadequate Core Cooling: - I 4.1 I 26 RCS temEerature and Eressure indicators
  • Ability to determine and interpret tbe following as tbey apply to tbe Sl Termination: -: A9J:ieren(;e WIE02 *SI Termination I 3 appropriate procedures and operation witbiq *. * *.I 4.0 **J ~4
  • tbe limitations in the facility's license and NUREG 1021 5

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline ES-401 Emergency and Abnormal Plant EvQll!tions- 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 I Imp. I Q#

Knowledge of the interrelations between the LOCA Cooldown and Depressurization and the following: - Facility's heat removal systems, W/E03 LOCA Cool down - Depress. I 4 EK2.02 including primary coolant, emergency coolant, I 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 the. N~ Circul~tiori ~ith

~

'~< .3$ they. applyto Wlf;JO Natur~ Circ. I 4 :steamVoid in V~~ wi~wit~RV11S:-.

EA2.01 ~~

Facility conditions and selection ofappropriate procedures during abnollllal and emergency Knowledge of the reasons for the following responses as they apply to the Natural Circulation with Steam Void in Vessel W/ElO Natural Circ. I 4 K3.02 with/without RVLIS:- Normal, abnormal and I 3.2 19 emergency operating procedures associated with Natural Circulation with Steam Void in Vessel with/without RVLIS 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 .. I - K1.03 I Knowledge of the physical connections and/or cause-effect relationships between the RCPS and I 3.3 the followin s stems: - RCP seal Knowledge ofthe effect of a loss or malfunction I 28 Control on the following CVCS components:- Seal I 3.1 I 29 in* ection s stem and limits on flow 005 Residual Heat Knowledge of the physical connections and/or Removal cause-effect relationships between the RHRS I 3.1 I 30 and the following !

Abiljty tQ (a) pr¢ict tlte impacts of the I - 111"~2.01 I followjng m!llfunctions or operations on the

, .. IUIR.Sand (b)based on tl1ose predictions, use

  • 005 ResiQ,ual H~

Removal ',1 -n l I pr()(;edw:es to correct, control* or tpitig_llte the

~quen~s of those malfunctjop~;qr **

  • I 29 I 86

'-"'-' o~(ms: -Failure m~Jorpre~re. flow.

pump motor amps, mot0r~ature. and tank.

  • vel instrumentation* * ., .:"
  • Ability to predict and/or monitor changes in X III'IIAL07 I parameters (to prevent exceeding design limits)

I I 3.3 I 31 associated with operating the ECCS controls includin : - Pressure, hi h and low 007 Pressurizer Ability to monitor automatic operation of the Relief/Quench Tank PRTS, including:- Components which discharge I 2.7 I 32 to the PRT 007 Pressurizer I Knowledge of the operational implications of the Relief/Quench Tank I I I I lx I I I

  • K5.02 following concepts as they apply to the PRTS:- I 3.1 Method of formin a steam bubble in the PZR I 33 008 Component Cooling Knowledge of the effect that a loss or Water malfunction of the CCWS will have on the I 3.4 34 1

g - Loads cooled b~ CCWS Ability to (a) predict the imp~s ofthe

. f following malfunctions or o~i()ns on tbe 008 C01nponent CooJing Water I I I J I I I .

~ .. \

..  :.A2.02 * .._(;CWS 11t1d (b) based on tho&!' llftldictio~ use proc~es to, 9orrect,. control; *or mitiga~. tlt~-

I 3.5 I 87 conseqli~~~~pfthose malfunctions or

  • 0 *ons:~Hi ow sur e tank level*

010 Pressurizer Pressure 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 K3.04 Knowledge of the effect that a loss or malfunction of the RPS will have on the 1 3.8 I 37 followin : - ESF AS 013 Engineered Safety Conduct of Operations - Ability to locate and Features Actuation 2.1.30 I 4.4 I 36 operate components, including local controls.

013 Engineered Safety Knowledge of bus power supplies to the Features Actuation X K2.01 following: - ESF AS/safeguards equipment I 3.6 I 38 022 Containment Cooling 022 Containment Cooling I

I I

I I

I I

I I

I I

I I

I

- v I

I

-'"')A'"')"'l

- A'Jf\1 control I Emergency Procedures/Plan- Knowledge of the bases for prioritizing emergency procedure ttation during emergenc~ o~eratior I Ability to monitor automatic operation of the CCS, including: - Initiation of safeguards mode of o~eration I 3.4 I 4.1 I 39 I 40 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 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 o erations: - Failure of ESF Ability to predict and/or m 039 Main and Reheat parameters (to prevent exceeomg oes1gn umusJ Steam X Al.06 associated with operating the MRSS controls 3.0 I 42 includin : - Main steam ressure Knowledge of the effect that a loss or 059 Main Feedwater X K3.04 malfunction of the MFW System will have on 3.6 I 43 the followin : - RCS 059 Main Feedwater I I I ~ " ...... ~

Ability to manually operate and/or ... ~ ... w ....

I 3.1 I 44 the control room: - MFW turbine tri~ indication Knowledge of AFW System design feature(s)

I and/or interlock(s) which provide for the 061 Auxiliary/Emergency Feedwater I I I lx I I I I II K4.02 following: - AFW automatic start upon loss of MFW pump, S/G level, blackout, or safety I 4.5 I 45 on Knowledge of the operational implications of the 061 Auxiliary/Emergency Feed water I I I I lx I I I II K5.01 1 following concepts as they apply to the AFW System: - Relationship between AFW flow and I

36 I 51 RCS heat transfer 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 I A.C. Distribution System and (b) based on those 062 AC Electrical Distribution I I I I I I I I Ill A2.04 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions I 3.4 I 46 or operations: - Effect on plant of de-energizing a bus I Abili 062 AC Electrical Distribution I I I I I I I lx

  • A4.07 the control room: - Svnchromzm!! and I 3.1 I 48 062 AC Electrical DiStribution I I I t I l I

- I ---2.2.36 1 VJ. ~Q.II~.Jo~l~~n...'-i a~t.~~'V..IU~~;t~ ~:>U\.<J:~~ ":"~~~"'v~

! 4.2 I' 88 063 DC Electrical Distribution 064 Emergency Diesel Generator I lx I I X

I I I

- I

  • K2.0l K4.ll 1 Knowledge of bus power supplies to the following: - Major DC loads Knowledge ofED/G System design feature(s) and/or interlock(s) which provide for the following: - Automatic load sequencer:

I 2.9 I 3.5 I 47 I 49 safe uard Knowled~

073 Process Radiation CaUSe-effe_,t I ClllllUH:>llip:>

Monitoring X Kl.Ol - ~ . .... .. . UCl V¥<0<011 111<0 r 1'\..lVl

~*

I 3.6 I 50 076 Service Water 3.5 52 Procequres/Plan - Knowledge of 076 Service_ Water nnernt:ing procedures are .I.JSed in 4.5. 89 Knowledge ofiAS design feature(s) and/or 078 Instrument Air interlock(s) which provide for the following:- 3.2 53 X

Cross-over to other air l 03 Containment Ability to manually operate 2.7 54 the control room: - ESF NUREG 1021 9

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 Abi,Jity to (a) predict th9 iJtlpacts following malt\mctions or opeTPtions on lbe l 03 Containment CogtaiJunent System and (b) biised on tlJ9se

~.8 .* I 90 predictionS, use proeedures to ~t, control, or mitip1:e the consequences of those Dlali~mctions '/

103 Containment X 3.7 I 55 NUREG 1021 10

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 001 Control Rod Drive 002 Reactor Coolant I IX I I I I I .. I - K2.03 Knowledge of bus power supplies to the I following:- One-line diagram of power supplies to I 2.7 56 57 014 Rod Position Indication X K5.02 following concepts as they apply to the RPIS: - 58 RPIS inde endent of demand osition Knowledge ofNIS design feature(s) and/or 015 Nuclear I interlock(s) which provide for the following:-

Instrumentation I IX I K4.03 I 3.9 I 59 Reading of source range/intermediate range outside control room 016 Non-Nuclear Knowledge of the effect that a loss or Instrumentation System X K3.09 malfunction of the NNIS will have on the I 3.5 I 61 (NNIS followin : - ESF AS 017 In-core Temperature Monitor 029 Containment Purge I I I I I I I

- I - A2.02 I

f'n.llnu.r1nn- rn"lllf'** nrot-i

~J~*~m

~

~u~ \VJ v~~~~ vu mv~~

p*~~*~uvu~,

..w~~

I 3.6 I 60 System (CPS) X 3.4 62 034 Fuel Handling

.~'}uipment .

035 Steam Generator System (S/GS)

NUREG 1021 11

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 Form ES-401-2 045 Main Turbine I I

- I

- 1 Ability to monitor automatic operation of the MT/G System, including: - T/G trip 3.4 63 r'IIA':t D"P./V!>A.-Itt:f"Acf0Ja'rt _ ,y n.n1.-s.t1AI'inA .~"~of" f"hJ:!o 4.0 92 086 Fire Protection lx I I I I I I .. I - K1.03 1

mrot room: - Ma or com onems Knowledge of the physical connections and/or cause-effect relationships between the Fire Protection System and the following systems: -

AFW 2.5 I 3.4 64 I 65 NUREG 1021 12

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

1. Conduct of 2.1.45 indications to validate the response of another 4.3 68 Operations indication.

Con<Juct ofOpenU,ions 7 Ability.lQ interp~~; .  :..*

2.1.25 . referencematerialksucll as graphs; curv., .' .l . 4.2. 94

  • tables etc. .* * *. ** * ** " * * *.,. I  :
  • Conductof()perations- Knowledge of *..:::*~ * : * ,** : >>

I**>********

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.

2. Equipment
      • Equipment Cofitrol- Knowledge of the i:Y .;;?<  ::;':*" < .

process for managing maintenance activities Control  :;

2.2.11. durin~ P?wer operations, suchas~isk . . .*.

  • ..3;~:: .96 assessm~nts; worK; priQd~otr,~:~(~~.J~;:.;; *.

coordination with :tbe * * * **

operator. . . * .

EqUipment Control - Knowledge of the 2.2.18 process for managing maintenance activities i:* i~*j: 97 during shutdown operations:, such as risk

    • . i .. : . 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 - ~owledge of 2.3.4 radiation exposure limits tinder normatand 3.7 98 emergency conditions. , * .... * *. ** ...

  • Subtotal 2 1 Emergency Procedures/Plan - Knowledge of local auxiliary operator tasks during an 2.4.35 emergency and the resultant operational 3.8 73 effects ..

Knowledge of events related to system operation/status that must be reported to 2.4.30 internal organizations or external agencies,

4. Emergency 2.7 74 such as the State, the NRC, or the Procedures/plan transmission system operator.
  • .~ .Em~rg~(:Y Procedure.s!Pian- Knowledg.e of .

2.4.32 .* *~ . . . 4.0 .*~. .

  • . 1 Emergency Procedures/Plan to .

2.4:46 verifY ~at the alaptU are consistent witht plant conditions. ..

  • Subtotal 2 2 Tier 3 Point Totals 10 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

ES-401 Record of Rejected K/As Form ES-401-4 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 AlWS: - BIT inlet valve switches Rejected because the BIT has been removed.

AlWS 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 applicable to Loss of DC Power.

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 Rejected K/As Form ES-401-4 IPEC Unit 2 has defeated automatic rod 0000012132 withdrawal and manual uncontrolled rod Ability to explain and apply all system limits and withdrawal requires a reactor trip. Due to R 1/2 Continuous Rod precautions. equipment configuration unable to write a Withdrawal discriminatory RO question that does not overlap with an existing JPM 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.

Knowledge of the operational implications of the following concepts as they apply to the PRM R 2/1 073000K502 System:- Radiation intensity changes with source distance Knowledge of the operational implications of the following concepts as they apply to the RPIS: -

R 2/2 014000K501 Reasons for differences between RPIS and step counter

ES-401 Record of Rejected KlAs Form ES-401-4 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 R2/2 Spent Fuel Pool following:- Area and ventilation radiation monitoring excessively long time to produce an effect on 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 R2/2 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.

Knowledge of crew roles and responsibilities during Rejected because this KA is best evaluated R3 2.4.13 EOP usage during Simulator exam. Unable to write a discriminatory RO Question.

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.

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 Ability to (a) predict the impacts of the following 014000A204 malfunctions or operations on the RPIS and (b)

Per discussion with Lead Examiner, unable to s 2/2 Rod Position based on those predictions, use procedures to write a discriminatory SRO question.

correct, control, or mitigate the consequences of Indication those malfunctions or operations: - Misaligned rod

ES-401 Record of Rejected Kl As Form ES-401-4 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-401 Record of Rejected K/As Form ES-401-4 When the outline was submitted, only one KA was selected for the RO Tier 2 (Plant Systems) Generic column. This is the result of a problem with the NKEG WOG NRC KA Exam Generator.

The error was identified by Dave Silk.

The Exam Generator did not select another generic KA after several attempts. After a discussion with Dave Silk, we randomly selected a new Plant systems KA for a System that was already represented twice (013 Engineered Safety Features Actuation).

ES-301 Administrative Topics Outline Form ES-301-1 Facility: IPEC Unit 2 Date of Examination: Feb 10. 2014 Examination Level: RO Administrative Topic

  • SRO D 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)

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; s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (<:: 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)

Review 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 (S 3 for ROs; s 4 for SROs & RO retakes)

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

(P)revious 2 exams (S 1; 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

  • 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 (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. 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 (039000A4.07 N,E 8 R0-2.8 SR0-2.9)
j. Release a small gas decay tank (071000A4.05 R0-2.6 D,R 9 SR0-2.6)
k. Perform the Required Actions to Replace 21 Feedwater 0, E 4S Regulating Bypass Valve Air Lines for Local Operation during Loss of Secondary Heat Sink (OOWE05A 101 RO-4.1 SRO- 4.0)

@ 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/ SRO-U I

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 J PM 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 (000011 A 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 (039000A4.07 N, E 8 R0-2.8 SR0-2.9)
j. Release a small gas decay tank (071 OOOA4.05 R0-2.6 D,R 9 SR0-2.6)
k. Perform the Required Actions to Replace 21 Feedwater D,E 4S Regulating Bypass Valve Air Lines for Local Operation during Loss of Secondary Heat Sink (OOWE05A101 RO-4.1 SRO- 4.0)

@ 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/ SRO-U I

(A)Iternate path 4-6 I 4-6 12-3 (C)ontrol room (D)irect from bank  ::>91::>81::>4 (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 (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. NA SRO-U
e. NA SRO-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. NA SRO-U
h. NA SRO-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 (039000A4.07 N,E 8 R0-2.8 SR0-2.9)
j. Release a small gas decay tank (071 OOOA4.05 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 :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 :s; 3 I :s; 3 I :s; 2 (randomly selected)

(R)CA <.:11<.:11<.: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)

EPS0070 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 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 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 BST- 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 FRV fails in auto.

C(CRS) 6 CVH- 22 FRV fails in manual.

M(ALL)

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.

ATS017B 8 AOV-MSS036AI 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 Page 1 of 18

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)

CCW003A C (CRS) 23 CCW pump trip with failure of other CCW pumps to autostart TS(CRS) 4 XMT- TS(CRS) Control Rod 08 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 10 MOC-C(BOP) 21 and 22 Containment Recirc Fans fail to autostart.

CNM008/9

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor U2 NRC 2014 Scenario 3 Page 1 of 18
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