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*

1.

1 3

3 3

3 3

3 18 3

3 Emergency 2

2 2

2 1

2 0

9 2

2 N/A N/A Abnormal Tier Plant Evolutions Totals 5 5

5 4

5 3 27 5

5

2.

1 3

2 3

3 3

2 3

3 2

3 2

28 3

2 Plant 2

1 1

1 1

1 1

1 1

1 1

0 10 0 I 2 1

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;; 1UL1 I

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 Grol!I!_ 1 Form ES-401-2 EIAPE #I Name I Safe!y Function 000007 Reactor Trip - Stabilization - Recovery I 1 000007Reactor Trip

  • Stabilization - Recovery./

I 000008 Pressurizer Vapor Space Accident I 3 000009 Slll;all }3rea.k LOCA I 3 000011 Large Break LOCA I 3 0000151000017 RCP Malfunctions I 4 000022 Loss ofRx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water I 8 000038 Steam Gen. Tube Rupture I 3 000040 Steam Line Rupture - Excessive Heat Transfer /4 NUREG 1021 I

I I

I KllK2 I K3 I At I A2 I G I Number I KIA Topic I Imp. I Q#

X X

X AAl.l2 X

AK3.04 I X I I

-AK2.05 I

I X I

-AK3.02 I

I I

1:' A,..., 1 C 2

Knowledge of the operational implications of the following concepts as they apply to the reactor trip:- Reasons for closing the main turbine I 3.7 governor valve and the main turbine stop valve after a reactor 4.3 3.8 4.1 U..,;J......_) u.pp*)....................1.'-"""'-""""-'1. '-V'VUA *.t.II...._ !,..I.J.J.&p

2.8 Malfunctions

-Reactor coolant loop flow meters Knowledge of the reasons for the following resoonses as they apply to the Loss of Reactor 3.2 eu : - lsolatin letdown Knowledge of the interrelations between the I Loss of Residual Heat Removal System and the I 2.6

- Reactor building sum~

Knowledge of the reasons for the following responses as they apply to the Loss of I Component Cooling Water:- The automatic I 3.6 actions (alignments) within the CCWS resulting from the actuation ofthe ESFAS I Ability to determine and interpret the following as they apply to a SGTR: - Pressure at which to I 4.2 maintain RCS durin SIG cooldown Knowledge of the operational implications of the following concepts as they apply to Steam Line I 4.1 uences of PTS 76 2

3 I

4 5

I 6

I 7

I 9

I 10

Facility: Indian Pont Unit 2 ES-401 EIAPE #I Name I Safety Function 000054 Loss of Main Feedwater I 4 000055 Station Blackout I 6 00005,5 Station Black9\\lt I 6 000056 Loss of Off-site Power /p 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 ofN\\JClear 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 Emergency and Abnormal Plant Evolutions-Tier 1/ 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 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 Ability to operate and/or monitor the following as they apply to the Loss of Offsite Power: -

PORV 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 Eower bv ED/Gs Apility to Q.etermine and interpret as they apply w the Loss ofNuclear Service-Water:

Ability to determine and interpret the following as they apply to the Loss oflnstrument Air: -

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 primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the of the I !!I!I!-1_ Q#

3.5 14 3.9 12 79 I 3.3 I 13 I

3 I

8 I 3.4 I ll I 3.6 I 80 I 2.8 I 15 I 3.8 I 16

Facility: Indian Pont Unit 2 ES-401 EIAPE #I Name I Safe!Y_ Function WIE05 Ina(leqUfi!e Heat Transfer-Loss of.

S~Qndary HeatJSinkl 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 Evolutions - Tier 1 I Group 1 Form ES-401-2

] Kl I J.au] K3 TAl I AT] G I Number I KIA Topic I Imp. I Q#

X 4

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

as tll~Y. apply t9tlle Lo$S of Seconctm-Y Heat Sink:~.J?acility coJld,itions and selection of l 4..4 aooronriate proce4Ure~ duriJ!i ~bnortllll1 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 3.7 3.4 81 17 18

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 X

following concepts as they apply to Dropped 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 I 3.6 I 21 Control Rod: - Tech-Spec limits for rod 000005 Inoperable/Stuck Control Rod I 1 X

mismatch Ability to determine and interpret the following as they apply to the Loss oflntermediate Range Nuclear Instrumentation:- Equivalency between I 3.0 I 22 000033 Loss oflntermediate Range NI I 7 source-range, intermediate-range, and power-channel readings Knowledge of the operational implications of the following concepts as they apply to Fuel I 3.5 I 23 Handling Incidents: - Radiation exposure 000036 Fuel Handling Accident I 8 X

hazards Equipment Control - Ability to determine operability and/or availability of safe~ related

. 00003 7 Steant G~eratQr Wbe ~I 3

ent.

Knowledge of the interrelations between the 000060 Accidental Gaseous Radwaste Rei. I 9 X

Accidental Gaseous Radwaste Release and the 2.7 24 000068 Control Room Evac. I 8 tbe 4.8 83

!llSll;:fltlj.

Ability to determine and interpret the following as they apply to the Loss of Containment I 3 9 I 25 Integrity: - Verification of automatic and manual 000069 Loss of CTMT Integrity I 5 means of Ability to operate and/or monitor the following as they apply to an Inadequate Core Cooling: -

I 4.1 I 26 000074 Inad. Core Cooling I 4 X

RCS temEerature and Eressure indicators

  • Ability to determine and interpret tbe following as tbey apply to tbe Sl Termination: -: A9J:ieren(;e appropriate procedures and operation witbiq *..* *.I 4.0 **J ~4 WIE02 *SI Termination I 3
  • tbe limitations in the facility's license and NUREG 1021 5

Facility: Indian Pont Unit 2 ES-401 E/APE #I Name I Safety Function W /E03 LOCA Cool down - Depress. I 4 Wlf;JO Natur~ Circ. I 4 W/ElO Natural Circ. I 4 NUREG 1021 PWR RO/SRO Examination Outline NRC Written Examination Outline Emergency and Abnormal Plant EvQll!tions-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 I Imp. I Q#

6 EK2.02

~

'~<

EA2.01 K3.02 Knowledge of the interrelations between the LOCA Cooldown and Depressurization and the following: - Facility's heat removal systems, including primary coolant, emergency coolant, I 3.7 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

.3$ they. applyto the. N~

Circul~tiori ~ith

steamVoid in V~~ wi~wit~RV11S:-.

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 with/without RVLIS:- Normal, abnormal and I 3.2 emergency operating procedures associated with Natural Circulation with Steam Void in Vessel with/without RVLIS 27

~~

19

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 003 Reactor Coolant Pump I X 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 I 28 the followin s stems: - RCP seal 004 Chemical and Volume Knowledge ofthe effect of a loss or malfunction 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 followjng m!llfunctions or operations on the 005 ResiQ,ual H~

',1

-n

',.. l

'-"'-' I I - 111"~2.01 I IUIR.Sand (b)based on tl1ose predictions, use

  • Removal pr()(;edw:es to correct, control* or tpitig_llte the I 2 9 I 86

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

  • 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 -

I III'IIAL07 I parameters (to prevent exceeding design limits) associated with operating the ECCS controls I 3.3 I 31 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

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 formin a steam bubble in the PZR 008 Component Cooling Knowledge of the effect that a loss or Water malfunction of the CCWS will have on the I 3.4 1 34 g - Loads cooled b~ CCWS Ability to (a) predict the imp~s ofthe 008 C01nponent CooJing I I I J I I I.>

.A2.02

. f following malfunctions or o~i()ns on tbe Water

~.. \\

  • .. _ (;CWS 11t1d (b) based on tho&!' llftldictio~ use I 3.5 I 87 proc~es to, 9orrect,. control; *or mitiga~. tlt~-

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 Knowledge of the effect that a loss or K3.04 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 operate components, including local controls.

I 4.4 I 36 013 Engineered Safety Knowledge of bus power supplies to the Features Actuation X

K2.01 following: - ESF AS/safeguards equipment I 3.6 I 38 control 022 Containment Cooling I I

I I

I I

I -

I

-'"')A'"')"'l I Emergency Procedures/Plan-Knowledge of the bases for prioritizing emergency procedure I 3.4 I 39 ttation during emergenc~ o~eratior 022 Containment Cooling I I

I I

I I

I v

I A'Jf\\1 I Ability to monitor automatic operation of the CCS, including: - Initiation of safeguards mode I 4.1 I 40 of o~eration 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 039 Main and Reheat Ability to predict and/or m Steam X

Al.06 parameters (to prevent exceeomg oes1gn umusJ 3.0 I 42 associated with operating the MRSS controls includin : - Main steam ressure 059 Main Feedwater Knowledge of the effect that a loss or 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) 061 Auxiliary /Emergency I

I I lx I I

I I II K4.02 I and/or interlock(s) which provide for the Feedwater following: - AFW automatic start upon loss of I 4.5 I 45 MFW pump, S/G level, blackout, or safety on 061 Auxiliary/Emergency I

I I

I lx I I

  • I II K5.01 1

Knowledge of the operational implications of the Feed water following concepts as they apply to the AFW I 3 6 I 51 System: - Relationship between AFW flow and RCS heat transfer NUREG 1021 8

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 062 AC Electrical I

I I

I I

I I

  • I Ill A2.04 Distribution I

I I

I 062 AC Electrical I

I I

  • lx
  • A4.07 Distribution 062 AC Electrical DiStribution I

I I

t I

l I -

I

---2.2.36 063 DC Electrical I

lx I I

I I

I -

I K2.0l Distribution 064 Emergency Diesel Generator X

K4.ll 073 Process Radiation Monitoring X

Kl.Ol 076 Service Water 076 Service_ Water 078 Instrument Air X

l 03 Containment NUREG 1021 9

Ability to (a) predict the impacts of the following malfunctions or operations on the I A.C. Distribution System and (b) based on those predictions, use procedures to correct, control, or I 3.4 mitigate the consequences of those malfunctions or operations: - Effect on plant of de-energizing a bus I Abili the control room: - Svnchromzm!! and 1 VJ. ~Q.II~.Jo~l~~n... '-i a~t.~~'V..IU~~;t~ ~:>U\\.<J:~~ ":"~~~"'v~

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:

safe uard Knowled~

CaUSe-effe_,t I ClllllUH:>llip:> UCl V¥<0<011 111<0 r 1'\\..lVl

~.

~*

Procequres/Plan - Knowledge of nnernt:ing procedures are.I.JSed in Knowledge ofiAS design feature(s) and/or interlock(s) which provide for the following:-

Cross-over to other air Ability to manually operate the control room: - ESF I 3.1

! 4.2 I 2.9 I 3.5 I 3.6 3.5 4.5.

3.2 2.7 I 46 I 48 I'

88 I 47 I 49 I 50 52 89 53 54

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 l 03 Containment 103 Containment X

NUREG 1021 10 Abi,Jity to (a) predict th9 iJtlpacts following malt\\mctions or opeTPtions on lbe CogtaiJunent System and (b) biised on tlJ9se predictionS, use proeedures to ~t, control, or mitip1:e the consequences of those Dlali~mctions

~.8.* I 90

'/

3.7 I 55

Facility: Indian Pont Unit 2 001 Control Rod Drive 002 Reactor Coolant 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-Nuclear Instrumentation System (NNIS 017 In-core Temperature Monitor 029 Containment Purge System (CPS) 034 Fuel Handling

.~'}uipment..

035 Steam Generator System (S/GS)

NUREG 1021 I

I I

IX I I

I I

X IX I

X I

I I

I I

PWR RO/SRO Examination Outline I.. I K2.03 Knowledge of bus power supplies to the I following:- One-line diagram of power supplies I 2.7 56 to 57 K5.02 following concepts as they apply to the RPIS: -

58 RPIS inde endent of demand osition Knowledge ofNIS design feature(s) and/or K4.03 I interlock(s) which provide for the following:-

Reading of source range/intermediate I 3.9 I 59 range outside control room Knowledge of the effect that a loss or K3.09 malfunction of the NNIS will have on the I 3.5 I 61 followin : - ESF AS f'n.llnu.r1nn-rn"lllf' ** nrot-i I -

I A2.02 I ~J~*~m ~u~ \\VJ v~~~~ vu mv~~ p*~~*~uvu~, w~~

~

I 3.6 I 60 X

3.4 62 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 2.5 64 mrot room: - Ma or com onems Knowledge of the physical connections and/or 086 Fire Protection lx I I

I I

I I.. I K1.03 1 cause-effect relationships between the Fire I 3.4 I 65 Protection System and the following systems: -

AFW 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 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

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.

I 4.2.

94

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

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.

      • Equipment Cofitrol-Knowledge of the i:Y.;;?< ::;':*" <.
2. Equipment process for managing maintenance activities Control durin~ P?wer operations, suchas~isk..

2.2.11.

.3;~::

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

coordination with :tbe operator.

EqUipment Control - Knowledge of the i:*

process for managing maintenance activities i~*j:

2.2.18 during shutdown operations:, such as risk 97

    • . 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 Facility I Indian Point Unit 3 I Date of Exam Category

3.

Radiological Controls

4. Emergency Procedures/plan Tier 3 Point Totals NUREG 1021 KIA#

2.3.5 2.3.12 2.3.4 Subtotal 2.4.35 Topic Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

Radiological Controls - Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Radiological Controls - ~owledge of radiation exposure limits tinder normatand emergency conditions.

Emergency Procedures/Plan - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects..

Knowledge of events related to system operation/status that must be reported to 2.4.30 internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

.~.Em~rg~(:Y Procedure.s!Pian-Knowledg. e of.

2.4.32.* ~

Emergency Procedures/Plan to.

2.4:46 1

verifY ~at the alaptU are consistent witht plant conditions.

Subtotal Form ES-401-3 RO SRO-Only IR Q#

IR Q#

2.9 71 3.2 72 3.7 98 2

1 3.8 73 2.7 74 4.0

.* ~

2 2

10 7

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 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 A lWS: - 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 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 R 1/1 Pressurizer Conduct of Operations - Ability to locate and Rejected because this KA is best evaluated 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 Rejected K/As Form ES-401-4 IPEC Unit 2 has defeated automatic rod 0000012132 withdrawal and manual uncontrolled rod R 1/2 Ability to explain and apply all system limits and withdrawal requires a reactor trip. Due to Continuous Rod precautions.

equipment configuration unable to write a Withdrawal discriminatory RO question that does not overlap with an existing JPM 0060002114 Conduct of Operations - Knowledge of criteria or 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 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.

Knowledge of the operational implications of the R 2/1 073000K502 following concepts as they apply to the PRM System:- Radiation intensity changes with source distance Knowledge of the operational implications of the R 2/2 014000K501 following concepts as they apply to the RPIS: -

Reasons for differences between RPIS and step counter

ES-401 Record of Rejected Kl As Form ES-401-4 033000K302 Knowledge of the effect that a loss or malfunction of Rejected because at IPEC a loss of cooling R2/2 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 R2/2 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.

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

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.

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 079000A201 malfunctions or operations on the SAS and (b) 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 Ability to (a) predict the impacts of the following 014000A204 malfunctions or operations on the RPIS and (b) s 2/2 Rod Position based on those predictions, use procedures to Per discussion with Lead Examiner, unable to Indication correct, control, or mitigate the consequences of write a discriminatory SRO question.

those malfunctions or operations: - Misaligned rod

ES-401 Record of Rejected Kl As Form ES-401-4 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-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

  • 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 (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 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)

Review Reactor Vessel Venting Time Per FR-1.3, Conduct of Operations M,R (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 I

Criteria for RO I SR0-1/ SRO-U

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 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 12-3

>91::>81::>4
11"=11"=1

- I -

I ;::1 (control room system)

11;
:11;::1
21;
:21;::1
3 I
:; 3 I::; 2 (randomly selected)

"=11;::11"=1

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 1

2 3

4 5

6 7

8 9

N/A R (ATC)

N (CRS)

Power Escalation N (BOP)

MOT-C(BOP) 23 SW Pump trips.

SWS008A TS(CRS)

XMT-I (ATC)

SGN034A I (CRS)

PT-404 Steam Header Pressure fails high causing MBFPs to be placed in manual.

MAL-C (ALL)

EPS0070 TS(CRS) 480V Bus 6A fault.

MAL-M(ALL)

Small Break LOCA RCS006A BKR-PPL003/4 M(ALL)

ATWS MOC-C(CRS)

AFW001 21 AFW Pump failure C(BOP)

RLY-PPL487/48 C(CRS)

Automatic Safety Injection failure 8

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 No.

1 2

3 4

5 6

7 8

9 Malf. No.

Event Event Type*

Description N/A R (ATC)

N (CRS)

Power Reduction N (BOP)

MOT-C (ALL) 21 Condensate Pump trip. TS for AFD.

CFW001B TS(CRS)

BST-C(BOP)

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

MAL-C (ALL)

EPS007B TS(CRS) 480V Bus 3A fault.

CNH-C(ATC)

PCS007D C(CRS) 22 FRV fails in auto.

CVH-M(ALL) 22 FRV fails in manual.

CFW005A MOC-AFW002 M(ALL)

Failure of 22 and 23 AFW to start which along with other CVH-conditions leads to loss of heat sink.

ATS017B AOV-C(ALL)

MSS036AI Failure of Turbine Stop/Control Valve pair.

CVH-MSS0308 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 No.

1 2

3 4

5 6

7 8

9 10 Malf. No.

Event Event Type*

Description N/A R (ATC)

N (CRS)

Power Ascension N (BOP)

MOT-C (ATC)

CVC003B C(CRS) 21 Charging Pump trip TS(CRS)

MOC-C (BOP)

CCW003A C (CRS) 23 CCW pump trip with failure of other CCW pumps to TS(CRS) autostart XMT-TS(CRS)

Control Rod 08 IRPI fails low.

CRF012A XMT-C (ALL)

PT-408A fails high causing 21 MFW Pump to go to minimum CFW036A speed.

MAL-M(ALL) 21 MFW Pump trips.

ATS005A MAL-RCS014D M(ALL) 24 SGTR.

AOV-C(ALL)

Failure of air to containment making PORVs required for CAS009A depressurization.

AOV-C(ALL)

RCS002A PORV will not close causing team to transition to ECA-3.1 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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