ML12059A443

Final Outlines (Folder 3)

ML12059A443
Person / Time
Site:	Indian Point
Issue date:	08/16/2011
From:	D'Antonio J Operations Branch I
To:	Entergy Nuclear Indian Point 2
Jackson D
Shared Package
ML112350689	List: IR 05000247/2012301 ML112411212 ML120300321 ML12059A360 ML12059A366 ML12059A370 ML12059A434 ML12059A435 ML12059A443 ML12059A447 ML12059A449 ML12072A227 ML12072A249 ML12172A061
References
U01844
Download: ML12059A443 (33)

Text

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

Indian Point Unit 2 Printed: 08/16/2011 Date Of Exam:

02/06/2012

3. Generic Knowledge And RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K41K5 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

I N/A 2

2 N/A 0

9 2

2 4

Abnormal Tier Plant Evolutions Totals 5

5 4

5 5

3 27 5

5 10

2.

1 3

2 3

3 I 3 2

2 3

2 2

3 28 3

2 5

Plant Systems 2

Tier Totals I

4 I

3 I

4 l~

I 3

1 3

I 4

I 3

I 3

0 3

10 38 1 I 6

2 0

2 3

8 1

2 3

4 1

2 3

4 10 7

Abilities Categories 3

2 3

2 2

2 I

2 Note:

1.

Ensure that at least two topics from every applicable KiA 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 KlA 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 :1:1 from that specified in the table based on NRC revisions. The final RO exam must total 75 paints 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 KiA 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 fOf any system or evolution.

5.

Absent a plant-specific priority, only those KiAs 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 KiA categories.

7.* The generic (G) KiAs in Tiers 1 and 2 shall be selected from Section 2 of the KiA 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 KiAs.

8. On the following pages, enter the KiA 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 KiA catalog, and enter the KiA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

NUREG 1021

PWR RO/SRO Examination Ontline Facility: Indian Pont Unit 2 ES-401 E/APE # / Name / Safe tv Function 000007 Reactor Trip - Stabilization Recovery /1 000008 Pressurizer Vapor Space Accident

/3 x

x 000009 Small Break LOCA / 3 1 Large Break LOCA / 3 5/000017 RCP Malfunctions / 4 x

Loss of Reactor Coolant Makeup / 2 vvvv....) Loss of RHR System / 4 x

1 Knowledge ofthe reasons for the following responses as they apply to the reactor trip: - Actions contained in EOP for reactor Knowledge ofthe reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: - Why PORV or code safety exit temperature is below RCS or PZR Ability to operate and/or monitor the following as they apply to a small break LOCA: - AFWIMFW Knowledge ofthe interrelations between the Large Break LOCA and the following:

IS Conduct of Operations - Ability to evaiuate piant performance and make operational judgments based on operating characteristics, reactor and Knowledge ofthe operational implications ofthe following concepts as they apply to Loss ofReactor Coolant Makeup: - Consequences of thermal 1-----:-~-:----11 shock to RCP seals Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following: - Reactor I 4.0 I 3.6 I 2 I 4.1 I 3 2.6 I 4 4.4 I 5 2.8 7

2.6 6

NUREG 1021 2

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline ES-401 Eli\\PE # I Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 11 I I(JJJgj K3 I At I A2 I G I Number I KIA Topic 1

Form ES-40I-2 lImp. I Q#

000027 Pressurizer Pressure Control System Malfunction / 3 Ability to operate and/or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: - PZR heaters, sprays, and PORVs I 4.0 13 000029 A TWS / 1 000038 Steam Gen. Tube Rupture / 3 x

x Knowledge of the operational implications ofthe following concepts as they apply to the ATWS: - definition of negative temperature coefficient as 1------1-1.=apJ:::Jp=lied to large PWR coolant 2.8 3.9 8

9 77 10 Conduct of Operations - Ability to 1------11. _nt.cerpret and execute procedl 000058 Loss of DC Power / 6 Ability to determine and interpret the I 3.5 following as they apply to the Loss ofDC Power: - DC loads lost; impact on to nnprl'\\tp and monitor NUREG 1021 3

12

PWR RO/8RO Examination Outline Facility: Indian Pont Unit 2 E8-401 1

E/APE # I Name / Safety Function 000065 Loss of Instrument Air 18 Ability to operate and/or monitor the 2.6 following as they apply to the Loss of Instrument Air: - Components served by instrument air to minimize drain on 000077 Generator Voltage and Electric X

AK2.01 I Knowledge ofthe interrelations between Grid Disturbances / 6 Generator Voltage and Electrical Grid Disturbances and the following: - Motors W/E04 LOCA Outside Containment / 3

- A-.-

I 3.6 I 16

_f-E-2 2--I1 AbilitY to determine and interpret the following as they apply to the LOCA Outside Containment: - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments W/E05 Inadequate Heat Transfer - Loss

_I-E-K-l-.1--I1 KnOWledge of the operational I 3.8 I 17 I X I I I of Secondary Heat Sink / 4 implications ofthe following concepts as they apply to the Loss of Secondary Heat Sink: - Components, capacity, and function of wl~il Loss of Emergency Coolant I I I I -

2.1.27 IConduct of Operations - Kn~wledge of I 3.9 I 18 RecIfc. /4 system purpose and or functIOn.

NUREG 1021 4

J ES-401 1

Form ES-401-1 E/APE # I Name I Safet Function 1m. _

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline W/El2 SteamLi~:~ppture - E~~!!Sive

~bility ~.* detequh}.eand interpret the Heat Transfer 14: '

foLl()W~1 as th~apply to the U~ol1Fi Depress~tion ofali

.$~ Gene~tors: - Facility co"'

and ~lectionofappf'9priate during abnpqual and emergency ooerations NUREG 1021 5

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 ES-401 EJAPE # / Name JSafetv Function 2

00000 I Continuous Rod Withdrawal / 1 000003 firnnnP!il x

Knowledge of the operational implications of the following concepts as they apply to Continuous Rod 3.6 19 Withdrawal: - SUR L..,-

'*~trm-.--::'t"--::'*

..,.~-c

... an-cd:-:i-llt-~rp-;re-t-th=-.e

• .. -c

.......-c..-+1-l-:j)-c

...... +1"""'8-c2""",1

~:theyili1~Jyto th~ Dfppped.'.

I<<4~ition indi*on 000032 Loss of Source Range NI / 7 Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following: - Sensors and detectors Ability to operate and/or monitor the following as they apply to the Loss of Source Range Nuclear Instrumentation:

3.i 21 Manual rest9!lit_i_on_o_f....c __-"..,-'7C-~-----,--+---I---~c-J

~ergen<::yPr 000074 Inadequate Core Cooling /4 000076 High Reactor Coolant Activity / 9 x

Ability to operate and/or monitor the following as they apply to the Plant Fire on Site: - Fire alarm Knowledge of the interrelations between the Inadequate Core Cooling and the Ir\\Urin..,.* - RCP Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity: - Corrective actions required for high fission product activitv in RCS 3.6 I 2.8 I 22 23 24 NUREG 1021 6

PWR RO/SRO Examination Outline Facility: Indian Pont 2

ES-401 Function W/E03 LOCA Cooldown - Depress. /4 x

WiE09 Natural eire 14 W/ElO Natural Circ. 14 WIE 14 Loss of Containment Integrity / 5 x

2 Knowledge of the reasons for the following responses as they apply to the LOeA Cooldown and Depressurization: -

Nonnal, abnonnal and emergency operating procedures associated with LOCA Cooldown and ~

Ability to detennine and interpret the following as they apply to the Natural Circulation with Steam Void in Vessel with/without RVLIS: - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments Knowledge ofthe operational impiications ofthe fonowing concepts as they apply to the High Containment Pressure: - Annunciators and conditions indicating signals, and remedial actions associated with the High Containment Pressure I 3.4 I 25 85 26 3.3 27 NUREG 1021 7

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 NRC Written Examination Outline 003 Reactor Coolant X

K2.01 Knowledge of bus power supplies to the I 3.1 I 28 Pump following: - RCPS 003 Reactor Coolanl A4.04 IAbility to manually operate and/or

,3.1 29 Pump monitor in the control room: - RCP seal 4ifierential pressure instrumentation 004 Chemical and X I A3.II I Ability to monitor automatic operation of I 3.6 I 30 Volume Control the CVCS, including: - Charging/letdown 004 Chemical and A2.35 I Ability to (a)predictthe impacts I 3.3 I 31 Volume Control following malfunctions or operations on the CVCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Reactor 005 ResiduafHeat I IX I I I I I

• I.ii.OJ Knowledge of bus power supplies to the I 2.7 I 32 Removal following: - RCS pressure boundary valves 005 ResidualHcW.., '>;,t J*"1,', k',', 'I

• f m:!itIW:il

,1';"",:12.2:36*/*'

IEauio~nteontr01"Abilifv,to wlvze r 4.2 I 86 itemoyaJ as degraded Pc

" fl~"

'9m"jt

.~J:l 006 Emergency Core Knowledge of the operational Cooling implications of the following concepts as they apply to the ECCS: - Effects of temperatures on water level indications NUREG 1021 8

PWR RO/SRO Examination Ontline Facility:

Pont 2

()O~EmergenCl{Core CPQUng 1,.J

", ':0 007 Pressurizer IX Relief/Quench Tank I

I I I I

I I

Pressurizer IX

• I Relief/Quench Tank I I I I I I 008 Component IX Cooling Water I

01 0 Pressurizer Pressure Control 010 Pre~_izer Pres.~Omtrol r ! I I' Ixl'/i...**r o12 Reactor Protection 012 Reactor Protection I IX I -

NUREG 1021 9

IAbili~ to (a)p~~:tt~~jmpacts~n~~

foUowmg malf~pnspr.~ons;~i?

...1.. -

ri~C' and ('-'):baSOO on tho~*..;;.

/

u',/

to.~~

~onsequen:(,!es of

. ~ Effect tion I Ability to manually operate and/or 3.6Ii~4 A4.l0 monitor in the control room:

of leaking PORV/code ry I IAbility to predict and/or monitor changes 2.7 I 35

.AL02 in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:

uenchtank IKnowledge ofCCWS design feature(s)

I 2.7 I 36 K4.09 I and/or interlock(s) which provide tor the following: - The "standby" feature for the CCW,

IAbility to (a) predict the impacts ofthe I 3.9 I 37 A2.02 following malfunctions or operations on the PZR PCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Spray valve failures j

u sal nmlts.

Knowledge ofthe effect ofa loss or malfunction of the following will have on the RPS: - B~Qass-block circuits K5.01 I Knowledge ofthe operational I 3.3 I 41 implications ofthe following concepts as the RPS: - DNB

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 Knowledge ofthe physical connections and/or cause-effect relationships between the CCS and the following systems:

SWS/coo 026 Containment 2.4.14 Emergency ProcedureslPlan - Knowledge 3.8 42 Spray of general guidelines for EOP usage.

039 Main and Reheat A2.04 Ability to (a) predict the impacts ofthe 3.4 43 Steam following malfunctions or operations on the MRSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Malfuncti{)ning steam dum~

059 Main Feedwater Ix I Los Knowled!!e ofthe ohvsical connections I 3.1 I 44 NUREG 1021 10

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 061 Auxiliary/

IKnowledge ofthe effect of a loss or I 2.5 I 46 K6.01 IX I Emergency F eedwater I I I I I malfunction of the following will have on

• I the AFW System components:

Controllers and ositioners 062 AC Electrical 2.4.27 Emergency Procedures/Plan ~ K.'1owledge 3.4 45 Distribution of fire in the plant procedure.

062 AC Electrical X

K3.03 Knowledge of the effect that a loss or I 3.7 I 47 Distribution malfunction of the A.C. Distribution System will have on the following: - DC s stem 063 DC Electrical X

K4.02 Knowledge of D.C. Electrical System I 2.9 I 48 Distribution design feature(s) and/or interlock(s) which provide for the following:

Breaker interlocks, permissives, bypasses and cross-ties 064 Emergency Diesel 2.4.34 I Emergency ProcedureslPlan ~ Knowledge I 4.2 I 49 Generator of RO tasks performed outside the main control room during an emergency and the resultant 0 erational effects.

064 Emergency Diesel Ability to predict and/or monitor changes I 3.1 I 50 Generator in parameters (to prevent exceeding design limits) associated with operating the ED/G System controls including:

Maintaining minimum load on ED/G (to reverse 073 Process Radiation Knowledge ofthe operational I 2.5 I 51 Monitoring implications ofthe following concepts as they apply to the PRM System:

Radiation theory, including sources, and effects

_X I 076 Service Water

.. A3.02 I Ability to monitor automatic operation of I 3.7 I 52 the SWS, including: - Emergency heat loads NUREG 1021 11

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 Form ES-401-2 076 Service Water IX I K3.02 I Knowledge ofthe effect that a loss or I 2.5 I 53 malfunction of the SWS will have on the following: - Secondary closed cooling water K4.02 J '1 ")

078 Instrument Air Ix I Knovvledge of lAS design feature(s) 54 and/or interlock(s) which provide for the following: - Cross-over to other air Isystems 103 Containment Ix I Kl.08 Knowledge ofthe phYSical connectlOns I 3.6 I 55 and/or cause-effect relationships between the Containment System and the following systems: - SIS, including action of safety iniection reset NUREG 1021 12

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 Form ES-401-2 002 Reactor Coolant

.. A2.02 I Ability to (a) predict the impacts of the I 4.2 I 57 following malfunctions or operations on the RCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Loss of coolant 011 Pressurizer Level IKnowledge ofthe effect of a loss or I 2.8 I 58 K6.01 IX I Control malfunction of the following will have on the PZR LCS: - Reasons for starting charging pump while increasing letdown flow rate 014 Rod Position X

K3.02 Knowledge ofthe effect that a loss or I 2.5 I 59 Indication System malfunction of the RPIS will have on the (RPIS) following: - Plant computer 015 Nuclear X

Kl.Ol Knowledge ofthe physical connections 60 Instrumentation and/or cause-effect relationships between the NIS and the following s~stems: - RPS 016 Non-nuclear IAbility to monitor automatic operation of I 2.9 I 61 A3.01

.X I Instrumentation the NNIS, including: - Automatic selection ofNNIS inputs to control 017 In-core IX I K4.03 I KnowledQe of ITM Svstem desiQn I 3.1 I 62 Temperature

Monitoring NUREG 1021 13

PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 033 SpeQt fll~l Pool Cooling System (SFPCS)

Ability to manually operate and/or monitor in the control room: - Shift of SIG controls between manual and automatic control, by bumpless transfer 041 Steam Dump x

Ability to predict and/or monitor changes I 3.1 System (SDS)/Turbine in parameters (to prevent exceeding Bypass design limits) associated with operating the SDS controls including: - Steam 045 Main Turbine x

Knowledge ofthe operational I 2,7 I 56 Generator (MT/G) implications ofthe following concepts as System they apply to the MT /G System:

Relationship between rod control and RCS boron concentration during T/G load increases I--------l 075 Circulating Water x

Knowledge of bus power supplies to the I 2.6 I 65 fol1owing: - Emergency/essential SWS NUREG 1021

2.1.3 2.1.20 Knowledge of shift or short-term relief turnover Ability to interpret and execute 3.7 4.6 66 67

• 1. Conduct of Operations 2.1.42 Knowledge ofnew and spent fuel movement procedures.

2.5 68 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels 4.6 69

2. Equipment Control 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems 3.9 70 NUREG 1021 15

Facility Indian Point Unit 2 Date of Exam 7/12/2010 Category KJA #

Topic RO SRO-Only IR Q#

IR Q#

2.3.4 Radiological Controls - Knowledge of 3.2 71 radiation exposure limits under normal and emer enc conditions.

2.3.11 Ability to control radiation releases 3.8 72 2.3.15 Knowledge of radiation monitoring 2.9 73

3.

systems, such as fixed radiation Radiological monitors and alarms, port.able survey Controls instruments, personnel monitoring equipment, etc.

Subtotal 3

1 2.4.45 Ability to prioritize and interpret the 4.1 74 significance of each annunciator or alarm.

2.4.50 Ability to verify system alarm setpoints 4.2 75 and operate controls identified in the alarm res onse manual 2.4.16 Knowled&,ofEOPimple~eJl~tioll;

4. Emergency hie~hy***

Procedures/plan Subtotal 2

2

~--------------------~~

---

._r----~--_r----~--~

Tier 3 Point Totals 10 7

NUREG 1021 16

Description of program used to generate IPEe Unit 2 February 2012 Written Exam KlAs 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 KlAs.

KlAs were suppressed prior to the outline generation process as provided for in the examiner standard, the list of suppressed KlAs is provided as required by the examiners standard.

Inappropriate and inapplicable KlAs were discarded during the outline development process and are included in the record of rejected KlAs. The replacement KlAs were replaced using the random sample function of the NKEG database program.

NUREG 1021 17

ES-401

~~~~~~~

Tier I Group 0000402439 R-1/1 Steam Line Rupture 0000542432 R-1/1 Loss of Min Feedwater (MFW) 00WE11K304 Loss of R-1/1 Emergency Coolant Recirculation 0000262140 Loss of R-1/1 Component Cooling Water R-1/1 000056K103 Record of Rejected KlAs Randomly Selectee d KIA Emergency Procedure s/Plan - Knowledge of RO responsibilities in eme gency plan implementation Emergency Procedure s/Plan - Knowledge of operator response to h ss of all annunciators Knowledge of the reas ons for the following responses as they ap~ y to the Loss of Emergency Coolant Recirculation: - RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the lim tations in the facilities license and amendments are I ot violated Conduct of Operations - Knowledge of refueling administrative requirem ents.

Knowledge of the oper ational implications of the following concepts as 1hey apply to Loss of Offsite Power: - Definition of s ubcooling: use of steam tables to determine it Form ES-401-4 Reason for Rejection Generic KA not applicable to Steam Line Rupture Event Generic KA not applicable to Loss of MFW event This KA is evaluated during the SimulatorlWalkthrough portion of the Exam This KA rejected due to inability to write a discriminatory question for refueling administrative requirements for Loss of CCW.

This KA was rejected due to overlap with Question 10.

Emergency Procedures/Plan - Ability to perform Generic KA not applicable to 0000052449 without reference to procedures those actions that Inoperable/Stuck Control Rod. There are no R-1/2 Inoperable/Stuck require immediate operation of system components procedures with immediate operator actions Control Rod and controls related to this condition.

Ability to operate and/or monitor the following as This KA was rejected because, at IP2 for a 000037AA101 they apply to the Steam Generator Tube Leak: -

Steam Generator Tube Leak, a normal R-1i2 Steam Generator Maximum controlled depressurization rate for cooldown and depressurization is performed Tube Leak affected S/G NOT a maximum rate depressurization.

This KA was rejected because, at IP2 for a Ability to operate and/or monitor the following as Control Room Evacuation, the charging pump R-1/2 000068AA111 they apply to the Control Room Evacuation: -

is aligned to the RWST. Emergency Boration Emergency borate valve controls and indicators is not identified in the procedure 2-AOP-SSO

1.

012000K608 Knowledge of the effect of a loss or malfunction of R-2/1 Reactor Equipment (COLSS) not applicable to IPEC.

the following will have on the RPS: COLSS Protection System I

Knowledge of the operational implications of the 006000K509 following concepts as they apply to the ECCS: -

This KA was rejected due to overlap with R-2/1 Emergency Core Thermodynamics of water and steam, including question 2.

Cooling System subcooled margin, superheat, and saturation Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)

This KA was rejected due to overlap with R-2/1 026000A102 associated with operating the CSS controls question 33.

including: - Containment temperature This KA was rejected because Chemistry 0590002134 Conduct of Operations - Knowledge of primary and Limits are no longer in any operations R-2/1 Main Feedwater secondary plant chemistry limits.

procedure. Unable to write a discriminatory RO level question for this KA.

2

R-2/2 001000K520 R-2/2 0290002126 Containment Purge System (CPS)

R-2/2 072000A101 3

2.1.30 3

2.1.17 S-1/1 0000082206 Pressurizer (PZR)

Vapor Space Accident (Relief Valve stuck open)

Knowledge of the operational implications of the following concepts as they apply to the CROS:

Effects of RCS temperature on boron reactivity worth

--.---~--~~~--~ ---'"

' Conduct of Operations - Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ARM system controls including: - Radiation levels Ability to locate and operate components, including local controls Conduct of Operations - Ability to make accurate, clear and concise verbal reports.

Equipment Control - Knowledge of the process for making changes to procedures.

This KA is rejected because it is a Generic Fundamentals concept with limited impact on the Control Rod Drive System. The change in temperature will have an impact on the CROS. Unable to write a discriminatory RO level question for this KA.

I Generic KA not applicable to Containment Purge System i

Unit 2 does not have automatic actions related to the Area Radiation Monitoring System. Unable to write a discriminatory RO level question for this KA.

Generic KA not applicable to written examinations. This KA is evaluated during JPM Evaluation Generic KA not applicable to written examinations. This KA is evaluated during Simulator Evaluation.

Generic KA not applicable to Emergency Plant Evolutions 3

0000512225 Loss of S-1/2 Condenser Vacuum 0260002401 Containment S-2/1 Spray System (CSS) 061000A206 Auxiliary I S-2/1 Emergency Feedwater (AFW)

System 0140002113 C' "\\11"\\

Rod Position v-.t:.I.t:.

Indication System (RPIS) 0270002235 Containment S-2/2 Iodine Removal System (CIRS) 3 2.1.14 Equipment Control - Knowledge of bases in technical specifications fo rlimitint conditions for operations and safety limits Emergency Procedures/Plan - Knowledge of EOP entry conditions and immediate actions steps Ability to (a) predict the impacts of the following malfunctions or operations on the AFW System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Back leakage of MFW Conduct of Operations - Knowledge of facility requirements for controlling vital/controlled access.

Equipment Control - Ability to determine Technical Specification Mode of Operation.

Conduct of Operations - Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Generic KA not applicable to Loss of Condenser Vacuum.

Generic KA not applicable to Containment Spray. There are no Immediate Operator Actions for the Containment Spray System.

This KA was rejected because IPEC has no procedure to address this condition. Unable to write a discriminatory SRO level question Generic KA not applicable to Rod Position Indication System.

Generic KA unable to write a valid SRO Only question.

Generic KA not applicable to written examinations. This KA is evaluated during Simulator Evaluation.

4

I i

i I

I i

I I

76 C & D Remove NOT

'Done 86 A & B Not plausible

• Done Revised Distractors A & 8 89 Enhance last sentence of Question

• Done Revised last sencence per Joe D.

93 [A &8 Not plausible iWorking 94'Take away number from question use Hilla level

• Done Revised Question 9'KA Mismatch Done Revised question to match KA 12:0K acceptable reverse logic for KA No action required 16iFair for RO?

Revised pressure to 1600 23 Fair for RO?

OK 26iFair for RO?

OK 27' Fair for RO?

10K I

i Done Added bullet items from Joe and 31 :Add bullets Don't be subtle I rearranged 34,8 Not correct for KA Accustic Monitors?

, Done Revised question 36' C seems discardable

. Done 41. Didn't like C

!OK Discussed Over Frequency protections I

42' KA looking for general question Possible reject overlap *OK 50' Didn't like D

. Revised D 58 KA looking for temperature effects on RHX Replaced Question 62 8 &D Not Plausible Make 2800 Done 64' Replace KA

• Replaced KA Replaced Question 67' Replace KA

Replaced KA Replaced Question 70: Enhance Stem What TS actions apply for this situation IRevised question per Joe D.

72' C &D Not Plausible

• Replaced Question 73 1 Enhance Stem "What action is required.....

Done

Administrative Topics Outline Facility:

Indian Point Unit 2 Date of Examination: February 6 2012 Exam ination Level: RO D SRO X Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note)

Code*

Review an ECP by Hand Conduct of Operations M,R 1940012'137 - Conduct of Operations - Knowledge of procedures. guidelines. or limitations associated with reactivity management. SRO-4.6 Determine Isolation Boundaries for CCW Leak Using Plant Print Conduct of Operations N,R 1940012125 - Conduct of Operations - Ability to interpret reference materials such as graphs, curves, tables etc.

SRO-4.2 Review a Surveillance Test Equipment Control N.R 1940012:212 - Equipment Control-Knowledge of surveillance procedures. SRO -- 4.1 Review a Release Permit for Containment Pressure Relief Radiation Control M.R 1940012306 - Radiological Controls - Ability to approve release permits. SRO - 3.8 Classify an Emergency Event Emergency Procedures/Plan M,R 1940012441 - Emergency Procedures/Plan-Knowledge of the emergency action level thresholds and classifications. SRO - 4.6 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 & Critena:

(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 fmm bank (:2: 1)

(P)revious 2 exams (s 1; randomly selected)

ES*301 Control Room/ln*Plant Systems Outline Form ES*301*2 Facility:

Indian Point Unit 2 Date of Examination: Februarv 6 2012 Exam Level: RO 0 SRO-I X SRO-U 0 Operating Test No.:

I Control Room Systems@ (S for RO); (7 for SRO-I); (~~ or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a.

Align CVCS Makeup after Chemistry Sample(004007A4.07 N

1 RO-3.9 SRO 3.7)

b.

Align Hot Leg Recirculation 23 SIP fails to Start A,M, EN 2

(000011 EA1.13 R0-4.1 SRO-4.2)

c.

Depressurize RCS during Natural Circ Cooldown and Block A,N, L 3

Low Pressure SI (WE09EA1.1 RO-3.5 SRO-3.5)

d.

NASROs NA NA

e.

Respond to 22 SG "B" Level Channel failure High D

7 (059000A4.0S RO-3.0 SRO-2.9)

f.

Isolate a faulted SG with CST level < 2.0 feet (000040A 110 A,EN,D 4S RO-4.1, SRO-4.1)

g.

Start 21 RCP during FR-C.1 (WE06EA 1.01 R03.S SRO E.D 4P 3.S)

h.

Verify Containment Phase A Isolation Manually Close EN.A.D 5

Valves (103000A3.01 RO-3.9 SRO-4.2)

! In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Align 23 Charging Pump to 12FD3 (000068AA 1.06 RO-4.1 D.E 6

SRO-4.2)

j.

Lineup Alternate Cooling to SIS and RHR Pumps (005000 D.E.R S

2.4.34 RO-4.2 SRO-4.1)

k.

Align 24 Waste Gas Decay Tank for Discharge (071000 R.D 9

2.3.11 RO-3.S SRO-4.1)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; a" 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 SRO-II SRO-U I

I

(A)ltemate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3

9/

;;8/s4 2

1/2:1/2:1

- / - / 2:1 (control room system) 2:1/2:1/2:1 2:2/2:2/2:1 s 31 s 3/ s 2 (randomly selected) 2:1/2:1/2:1

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

Indian Point Unit 2 Date of Examination: February 6 2012 Examination Level: RO X SRO D Operating Test Number:

Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Type Code" Describe activity to be performed Perform an ECP by Hand M,R 1940012137 - Conduct of Operations - Knowledge of procedures, guidelines, or limitations associated with reactivity management. RO-4.3 NA for ROs N,R Review a Surveillance Test 1940012212 - Equipment Control - Knowledge of surveillance procedures. RO - 3.7 M,R Calculate a Release Permit for Containment Pressure Relief 1940012311 - Radiological Controls - Ability to control radiation releases. RO - 3.8 Perform Initial UNUSUAL EVENT Notifications D,S 1940012439 Emergency Procedures/Plan - Knowledge of the RO's responsibilities in emergency plan implementation. RO - 3.9 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 (2: 1)

(P)revious 2 exams (S 1; randomly selected)

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

Indian Point Unit 2 Date of Examination: February 6 2012 Exam Level: RO X SRO-I D SRO-U D Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title

a.

Align CVCS Makeup after Chemistry Sample (004007A4.07 RO-3.9 SRO 3.7)

b.

Align Hot Leg Recirculation 23 SIP fails to Start (000011 EA1.13 R0-4.1 SRO-4.2)

c.

Depressurize RCS during Natural Circ Cooldovvn and Block Low Pressure SI (WE09EA1.1 RO-3.5 SRO-3.5)

d.

Energize 480V bus from Appendix R EDG (00Cl055A 106 RO-4.1 SRO-4.5)

e.

Respond to 22 SG "B" Level Channel failure High (059000A4.08 RO-3.0 SRO-2.9)

f.

Isolate a faulted SG with CST level < 2.0 feet (OOO040A110 RO-4.1, SRO-4.1)

g.

Start 21 RCP during FR-C.1 (WE06EA1.01 R03.8 SRO 3.8)

h.

Verify Containment Phase A Isolation Manually Close Valves (1 03000A3.01 RO-3.9 SRO-4.2)

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Align 23 Charging Pump to 12FD3 (000068AA 1.06 RO-4.1 SRO-4.2)

j.

Lineup Alternate Cooling to SIS and RHR Pumps (005000 2.4.34 RO-4.2 SRO-4.1 )

k.

Align 24 Waste Gas Decay Tank for Discharge (071000 2.3.11 RO-3.8 SRO-4.1)

Type Code*

Safety Function N

1 A.M. E 2

A.N.L 3

N 6

D 7

A.EN,D 4S E,D 4P E,A,D 5

D 6

D,E,R 8

R,D 9

All RO and SRO-! 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 SRO-II SRO-U I

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3

9/:::8/:::4

<:1/:<::1/:<::1 / ;::1 (control room system)

<::1/;::1/;::1

-=2/-=2/-=1 s 31 s 3/ ::: 2 (randomly selected)

-=1/;::1/:<::1

Facility:

Indian Point 2 Scenario No.:

1 Op-Test No.:_1 Examiners:

Operators:

Initial Conditions:

Reset simulator to IC-115 Load Simulator Schedule-Scenari01 The Plant is at 30% power. 23 EDG is OOS due to a malfunctioning governor.

Turnover:

Return plant to 100% power at 200 MW/hr.

21 EDG, 22 EDG, 138 KVoffsite power supply and 13.8 KV offsite power supply are protected Tech Spec 3.8.1.B surveillance requirement last performed 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago Event Malf. No.

Event Event No.

Type*

Description R (ATC) 1 N/A N (CRS)

Power Escalation N (BOP)

I (ATC) 2 XMT SGN008A I(BOP) 23 SG Controlling Steam Flow Transmitter Fails High TS(CRS)

C (BOP) 3 MAL EPS008L C (CRS)

MCC-28 will trip on overcurrent.

TS (CRS) 4 MAL-Loss of offsite power due to Loss of Station Aux Transformer.

C (ALL)

EPS001 The running charging pump (21) will trip.

5 MAL M{ALL)

Complete loss of off site power resulting in a Reactor Trip SWD003A 6

MAL I

DSG007A M(ALL) 21 EDG will trip and team will enter ECA-O.O.

7 MAL 300 GPM Seal LOCA Crew will take actions for Safety CVC002 C(ALL)

Injection.

8 N/A 22 EDG will be repaired and started. Team must start a C{BOP) service water pump to cool the EDG before it overheats and trips.

C(ATC) 9 N/A Prior to starting a charging pump, RCP Seal Injection must be C(CRS) isolated.

(N)ormal, (R)eactivity, (I}nstrument, (C}omponent, (M}ajor U2 NRC 2012 Scenario 1: Power Escalation from 30%, FT-439B fails high, MCC-28 trips, Loss ofoffsite power, Loss of all EDG to ECA-O.O.

Page 1 of20

Facility:

Indian Point 2 Scenario No.: _2_

Op-Test No.:_1 Examiners: _____________

Operators:

Initial Conditions:

The Plant is in a 100% normal full power lineup.

Turnover:

21 Charging Pump and 21 CCW pump are out of service.

Event I MaH. No. I ~vent Event I.

No.

. Type*

Description 1

XMT I (ALL)

RCS Loop 2:3 T-Hot fails high TS (CRS)

RCS04:3~A~'-___+-________________________________~1 CVH-R (ATC) 2 24 MFRV will slowly drift closed due to a broken air line CFW009B N (CRS) prompting a Rapid Load Shutdown N (BOP)

C (ATC) 3 MAL CRF002AV C (CRS)

Control Rod P-6 "ratchets in" during rod motion.

TS (CRS)

C (ATC) 4 MOT CVC004A C (BOP)

Loss of Letdown due to LCV-459 failing shut. Excess Letdown C (CRS) will be placed in service.

TS (CRS) 5 MAL Steam Break down stream of 21 MSIV & Check Valve in Aux M (ALL)

SGN004A Boiler Feed Pump Building.

6 PLP RHR033 PLP RHR02,2 LOCA outside Containment in Primary Auxiliary Building (PAB)

RLY M (ALL)

Safety Injection fails to Auto Actuate requiring Manual Actuation.

PPL481' RHR valve 746 will fail to auto open requiring Manual Action RLY PPL488 MOV RHR011 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Facility:

Indian Point 2 Scenario No.:

3 Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to IC-117 Load Simulator Schedule Scenario 3 Turnover:

The Plant is at 90% power, 21 EDG is OOS for major PM.

Return plant to 100% power.

Event Malf. No.

Event Event No.

Type*

Description R (ATC) 1 N/A N (CRS)

Power Escalation N (BOP) 2 XMT-PT -419C (2'1 SG C Channel Pressure) fails high causing 21 I (ALL)

SGN037A ADV to fail open requiring manual closure, TS (CRS) 3 MAL-C (ALL) 35 gpm RCS leak, RCSOO2A TS (CRS) 4 MOC C(CRS)

CCWOO3A C (BOP) 23 CCW Pump trips and 21 and 22 CCW Pump fail to auto start MOC TS (CRS)

CCWOO1/2 5

MAL M (ALL)

Large Break RCS LOCA, RCSOO1A C (CRS) 6 MOC RHR pumps will not auto start and need to be started manually.

RHR003/4 C (BOP) 7 RLY C (BOP)

PPL085/09 Failure of Containment Phase A requiring manual initiation.

0 (N)ormal, (R)eactivitv, (I)nstrument, (C)ornponent, (M)aior U2 NRC 2012 Scenario 3: Power Escalation from 90%, SG Pressure Failure causing ADV to open, CCW Pump trip with auto start failure, RCS leakage, LBLOCA with multiple actuation failures.

Page 1 of 19

Facility:

Indian Point 2 Scenario No.: _4_

Op-Test No.:_1 Examiners:

Operators:

Initial Conditions:

Reset simulator to IC-11B. Load Simulator Schedule - Scenario 4 The Plant is in a 100% normal full power lineup. 21 AFW Pump is out of service Turnover:

21 AFW Pump of out of service for scheduled maintenance and is expected back within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

22 and 23 AFW Pumps are protected equipment Maintain 100% Power Malt. No.

Event Event Type'"

Description I (ALL) 1 XMT VCT Level Transmitter LT-112 fails low CVC019A 2

MAL 6 gpm SG Tube Leak 24 SG RCS014D TS (CRS)

R (ATC) 3 NA N (CRS)

Rapid Load Reduction/Shutdown N (BOP)

A MAL M{AI I""enerator Tube Rupture RCS014D 5

BKR C (ATC) 23 EDG output Breaker fails as is DSG004 6

MAL C (BOP)

Safety Injection Pump 21 Fails to Auto Start SIS001 7

AOV RCS003A C (CRS)

SWI PORV 456 loss of control power when attempted to open RCS006B C (BOP)

SWI RCS006C C (CRS)

Auxiliary Spray Valve 212 will open but will failed closed resulting AOV 8

CVC008A C (BOP) in a transition to ECA-3.3 SGTR With Loss of Pressure Control 9

NA C (BOP)

Power is restored to bus 6A C(ATC)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor U2 NRC 2012 Scenario 4: L T-112 failure, SGTL, SGTR, Loss off site power, 23 EDG output BKR fault, Loss of Pressure Control Page 1 of 19