ML12059A443
| 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: |
| 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 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 2 2 0 9 2 2 4
& N/A N/A Abnormal Tier Plant Totals 5 5 4 5 5 3 27 5 5 10 Evolutions 2.
1 3 2 3 3 I 3 2 2 3 2 2 3 28 3 2 5 l~
Plant 2 I I I I 1 I I I 0 10 1 I 2 0 3 Systems Tier 6 2 8 4 3 4 3 3 4 3 3 3 38 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowledge And Abilities Categories 10 7 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.
PWR RO/SRO Examination Ontline Facility: Indian Pont Unit 2 ES-401 1 E/APE # / Name / Safe tv Function 000007 Reactor Trip - Stabilization x Knowledge of the reasons for the I 4.0 Recovery /1 following responses as they apply to the reactor trip: - Actions contained in EOP for reactor 000008 Pressurizer Vapor Space Accident x Knowledge of the reasons for the I 3.6 I 2
/3 following responses as they apply to the Pressurizer Vapor Space Accident: - Why PORV or code safety exit temperature is below RCS or PZR 000009 Small Break LOCA / 3 Ability to operate and/or monitor the I 4.1 I 3 following as they apply to a small break LOCA: - AFWIMFW 1 Large Break LOCA / 3 x Knowledge ofthe interrelations between 2.6 I 4 the Large Break LOCA and the following:
IS 5/000017 RCP Malfunctions / 4 Conduct of Operations - Ability to 4.4 I 5 evaiuate piant performance and make operational judgments based on operating characteristics, reactor and Knowledge of the operational 2.8 7 Loss of Reactor Coolant Makeup / 2 implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: - Consequences of thermal 1-----:-~-:----11 shock to RCP seals vvvv... .) Loss of RHR System / 4 x Knowledge of the interrelations between 2.6 6 the Loss of Residual Heat Removal System and the following: - Reactor 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 11 1 Form ES-40I-2 Eli\PE # I Name / Safety Function I I(JJJgj K3 I At I A2 I G I Number I KIA Topic lImp. I Q#
000027 Pressurizer Pressure Control Ability to operate and/or monitor the I 4.0 13 System Malfunction / 3 following as they apply to the Pressurizer Pressure Control Malfunctions: - PZR heaters, sprays, and PORVs 000029 A TWS / 1 x Knowledge of the operational 2.8 8 implications of the following concepts as they apply to the ATWS: - definition of negative temperature coefficient as 1------1-1.=apJ:::Jp=lied to large PWR coolant 000038 Steam Gen. Tube Rupture / 3 x 3.9 9 77 10 Conduct of Operations - Ability to 1 - - - - - - 1 1 . _nt.cerpret and execute procedl 000058 Loss of DC Power / 6 Ability to determine and interpret the I 3.5 12 following as they apply to the Loss of DC Power: - DC loads lost; impact on to nnprl'\tp and monitor NUREG 1021 3
PWR RO/8RO Examination Outline Facility: Indian Pont Unit 2 E8-401 1 E/APE # I Name / Safety Function 000065 Loss of Instrument Air 1 8 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
_f-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 E 2 2--I1 AbilitY to determine and interpret the
- -.- I 3.6 I 16 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 of Secondary Heat Sink / 4 I I I I X _I-E-K-l-.1--I1 KnOWledge of the operational
_ implications of the following concepts as I 3.8 I 17 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 I Conduct of Operations - Kn~wledge of I 3.9 I 18 RecIfc. /4 _ system purpose and or functIOn.
Facility: Indian Pont Unit 2 PWR RO/SRO Examination Outline NRC Written Examination Outline J
ES-401 1 Form ES-401-1 E/APE # I Name I Safet Function 1m . _
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 ~lectionof appf'9priate during abnpqual and emergency ooerations NUREG 1021 5
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 2 ES-401 2 EJAPE # / Name J Safetv Function 00000 I Continuous Rod Withdrawal / 1 x Knowledge of the operational 3.6 19 implications of the following concepts as they apply to Continuous Rod Withdrawal: - SUR 000003 firnnnP!il L ..,- '*~trm-.--::'t"--::'*
. ,.~-c
. an-cd:-:i-llt-~rp-;re-t-th=-.e
- .. -c
. . . .-c..-+1-l-:j)-c
. . . +1"""'82-c""",1
~:theyili1~Jyto th~ Dfppped .'.
I<<4~ition indi*on Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following: - Sensors and detectors 000032 Loss of Source Range NI / 7 Ability to operate and/or monitor the 3.i 21 following as they apply to the Loss of Source Range Nuclear Instrumentation:
Manual rest9!lit_i_on_o_f....c __ -"..,-'7C-~-----,--+---I---~c-J
~ergen<::yPr Ability to operate and/or monitor the 22 following as they apply to the Plant Fire on Site: - Fire alarm 000074 Inadequate Core Cooling /4 x Knowledge of the interrelations between 3.6 I 23 the Inadequate Core Cooling and the Ir\Urin..,.* - RCP 000076 High Reactor Coolant Activity / 9 Ability to determine and interpret the 2.8 I 24 following as they apply to the High Reactor Coolant Activity: - Corrective actions required for high fission product activitv in RCS NUREG 1021 6
PWR RO/SRO Examination Outline Facility: Indian Pont 2 ES-401 2 Function W/E03 LOCA Cooldown - Depress. /4 x Knowledge of the reasons for the I 3.4 I 25 following responses as they apply to the LOeA Cooldown and Depressurization: -
Nonnal, abnonnal and emergency operating procedures associated with LOCA Cooldown and ~ ..
WiE09 Natural eire
- 14 85 W/ElO Natural Circ. 14 Ability to detennine and interpret the 26 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 WIE 14 Loss of Containment Integrity / 5 x Knowledge of the operational 3.3 27 impiications of the fonowing concepts as they apply to the High Containment Pressure: - Annunciators and conditions indicating signals, and remedial actions associated with the High Containment Pressure 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 I Ability 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
"'9m"jt fl~"
.~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 IAbili~ to (a)p~~:tt~~jmpacts~n~~
CPQUng
", ':0 ', ;""
!; 1,.J foUowmg
...1.. -
malf~pnspr.~ons;~i?
ri~C' and ('-'):baSOO on tho~*..;;. .
"<<' / u' ,/
to.~~
~onsequen:(,!es of
. ~ Effect tion 3.6Ii~4 007 Pressurizer Relief/Quench Tank I I I I I I I
- IX
- A4.l0 I Ability to manually operate and/or monitor in the control room:
of leaking PORV/code ry I Pressurizer Relief/Quench Tank I I I I I I IX
- I
.AL02 I Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:
uenchtank 2.7 I 35 008 Component Cooling Water IX I
- K4.09 I Knowledge ofCCWS design feature(s)
I and/or interlock(s) which provide tor the following: - The "standby" feature for the I 2.7 I 36 CCW ,
01 0 Pressurizer
- A2.02 I ,
Ability to (a) predict the impacts ofthe I 3.9 I 37 Pressure Control 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 j u valve failures 010 Pre~_izer Pres.~Omtrol
! I I' Ixl'/i...**r sal nmlts.
o12 Reactor Protection r Knowledge of the effect of a loss or malfunction of the following will have on the RPS: - B~Qass-block circuits 012 Reactor Protection I IX I _ K5.01 I Knowledge ofthe operational I 3.3 I 41 implications ofthe following concepts as the RPS: - DNB NUREG 1021 9
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 of the 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:
059 Main Feedwater Ix I Los Malfuncti{)ning steam dum~
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/
Emergency Feedwater 062 AC Electrical Distribution I I I I I IX I
- I
- K6.01 2.4.27 Imalfunction Knowledge of the effect of a loss or of the following will have on the AFW System components:
Controllers and ositioners Emergency Procedures/Plan ~ K.'1owledge of fire in the plant procedure.
I 2.5 I 46 3.4 45 062 AC Electrical Distribution X K3.03 Knowledge of the effect that a loss or malfunction of the A.C. Distribution I 3.7 I 47 System will have on the following: - DC s stem 063 DC Electrical Distribution X K4.02 Knowledge of D.C. Electrical System design feature(s) and/or interlock(s)
I 2.9 I 48 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 of the operational I 2.5 I 51 Monitoring implications of the following concepts as they apply to the PRM System:
Radiation theory, including sources, 076 Service Water _X I . . A3.02 and effects 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 078 Instrument Air IX I Ix K3.02 K4.02 I Knowledge of the effect that a loss or malfunction of the SWS will have on the following: - Secondary closed cooling water I Knovvledge of lAS design feature(s)
I 2.5 I 53
'1 ")
J .... 54 and/or interlock(s) which provide for the following: - Cross-over to other air 103 Containment Ix I
- Kl.08 I systems Knowledge of the 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 following malfunctions or operations on the RCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of I 4.2 I 57 those malfunctions or operations: - Loss of coolant 011 Pressurizer Level IX I
- K6.01 I Knowledge of the effect of a loss or I 2.8 I 58 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 of the 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 of the physical connections 60 Instrumentation 016 Non-nuclear Instrumentation
.X I
- A3.01 I and/or cause-effect relationships between the NIS and the following s~stems: - RPS Ability to monitor automatic operation of I 2.9 I 61 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 of the operational I 2,7 I 56 Generator (MT/G) implications of the following concepts as System they apply to the MT/G System:
Relationship between rod control and RCS boron concentration during T/G load I--------l increases 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 Knowledge of shift or short-term 3.7 66 relief turnover 2.1.20 Ability to interpret and execute 4.6 67 2.1.42 Knowledge of new and spent fuel 2.5 68 movement procedures.
- 1. Conduct of Operations 2.2.2 Ability to manipulate the console 4.6 69 controls as required to operate the facility between shutdown and designated power levels 2.2.39 Knowledge of less than or equal to 3.9 70 one hour Technical Specification
- 2. Equipment action statements for systems Control 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 3.
2.3.15 Knowledge of radiation monitoring 2.9 73 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
~--------------------~~ ----------------------------._r----~--_r----~--~
2 2 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 Record of Rejected KlAs Form ES-401-4
~~~~~~~
Tier I Randomly Selecteed KIA Reason for Rejection Group 0000402439 Emergency Procedure s/Plan - Knowledge of RO Generic KA not applicable to Steam Line R-1/1 Steam Line responsibilities in eme gency plan implementation Rupture Event Rupture 0000542432 Emergency Procedure s/Plan - Knowledge of Generic KA not applicable to Loss of MFW R-1/1 Loss of Min operator response to h ss of all annunciators event Feedwater (MFW)
Knowledge of the reas ons for the following 00WE11K304 responses as they ap~ y to the Loss of Emergency Loss of Coolant Recirculation: - RO or SRO function within This KA is evaluated during the R-1/1 Emergency the control room team as appropriate to the SimulatorlWalkthrough portion of the Exam Coolant assigned position, in such a way that procedures are Recirculation adhered to and the lim tations in the facilities license and amendments are I ot violated 0000262140 Loss of This KA rejected due to inability to write a Conduct of Operations - Knowledge of refueling R-1/1 Component discriminatory question for refueling administrative requirem ents.
Cooling Water administrative requirements for Loss of CCW.
Knowledge of the oper ational implications of the following concepts as 1hey apply to Loss of Offsite This KA was rejected due to overlap with R-1/1 000056K103 Power: - Definition of subcooling: use of steam Question 10.
tables to determine it
0000052449 Emergency Procedures/Plan - Ability to perform Generic KA not applicable to 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.
000037AA101 Ability to operate and/or monitor the following as This KA was rejected because, at IP2 for a 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 006000K509 Knowledge of the operational implications of the 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
This KA is rejected because it is a Generic Knowledge of the operational implications of the Fundamentals concept with limited impact on following concepts as they apply to the CROS: the Control Rod Drive System. The change in R-2/2 001000K520 Effects of RCS temperature on boron reactivity temperature will have an impact on the worth CROS. Unable to write a discriminatory RO level question for this KA. .
--.---~--~~~--~ ---'" .- - --------------
0290002126 ' Conduct of Operations - Knowledge of industrial I Containment safety procedures (such as rotating equipment, Generic KA not applicable to Containment R-2/2 Purge System electrical, high temperature, high pressure, caustic, Purge System (CPS) chlorine, oxygen and hydrogen).
i Ability to predict and/or monitor changes in Unit 2 does not have automatic actions parameters (to prevent exceeding design limits) related to the Area Radiation Monitoring R-2/2 072000A101 associated with operating the ARM system controls System. Unable to write a discriminatory RO including: - Radiation levels level question for this KA.
Generic KA not applicable to written Ability to locate and operate components, 3 2.1.30 examinations. This KA is evaluated during including local controls JPM Evaluation Generic KA not applicable to written Conduct of Operations - Ability to make accurate, 3 2.1.17 examinations. This KA is evaluated during clear and concise verbal reports.
Simulator Evaluation.
0000082206 Pressurizer (PZR) Equipment Control - Knowledge of the process for Generic KA not applicable to Emergency S-1/1 Vapor Space making changes to procedures. Plant Evolutions Accident (Relief Valve stuck open) 3
0000512225 Equipment Control - Knowledge of bases in Loss of Generic KA not applicable to Loss of S-1/2 technical specifications fo rlimitint conditions for Condenser Condenser Vacuum.
operations and safety limits Vacuum 0260002401 Generic KA not applicable to Containment Containment Emergency Procedures/Plan - Knowledge of EOP S-2/1 Spray. There are no Immediate Operator Spray System entry conditions and immediate actions steps Actions for the Containment Spray System.
(CSS) 061000A206 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW System and This KA was rejected because IPEC has no Auxiliary I S-2/1 (b) based on those predictions, use procedures to procedure to address this condition. Unable to Emergency correct, control, or mitigate the consequences of Feedwater (AFW) write a discriminatory SRO level question those malfunctions or operations: - Back leakage of System MFW 0140002113 C' "\11"\ Rod Position Conduct of Operations - Knowledge of facility Generic KA not applicable to Rod Position v-.t:.I.t:.
Indication System requirements for controlling vital/controlled access. Indication System.
(RPIS) 0270002235 Containment Equipment Control - Ability to determine Technical Generic KA unable to write a valid SRO Only S-2/2 Iodine Removal Specification Mode of Operation. question.
System (CIRS)
Conduct of Operations - Knowledge of criteria or Generic KA not applicable to written conditions that require plant-wide announcements, 3 2.1.14 examinations. This KA is evaluated during such as pump starts, reactor trips, mode changes, Simulator Evaluation.
etc.
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 16 i Fair for RO? Revised pressure to 1600 23 Fair for RO? OK 26 iFair for RO? OK 27' Fair for RO? 10K i Done Added bullet items from Joe and I
31 :Add bullets Don't be subtle Irearranged .
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 I Revised question per Joe D.
72' C & D Not Plausible . *Replaced Question 73 Enhance Stem "What action is required.....
1 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
- 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)
I
- 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)
- 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 I Criteria for RO I SRO-II SRO-U
(A)ltemate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank :;;9/:;;8/s4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature - / - / 2:1 (control room system)
(L)ow-Power / Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1(A) 2:2/2:2/2:1 (P)revious 2 exams s 31 s 3/ s 2 (randomly selected)
(R)CA 2:1/2:1/2:1 (S)imulator
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 Type Describe activity to be performed (see Note) Code" Perform an ECP by Hand Conduct of Operations M,R 1940012137 - Conduct of Operations - Knowledge of procedures, guidelines, or limitations associated with reactivity management. RO-4.3 Conduct of Operations NA for ROs Review a Surveillance Test Equipment Control N,R 1940012212 - Equipment Control - Knowledge of surveillance procedures. RO - 3.7 Calculate a Release Permit for Containment Pressure Relief Radiation Control M,R 1940012311 - Radiological Controls - Ability to control radiation releases. RO - 3.8 Perform Initial UNUSUAL EVENT Notifications Emergency Procedures/Plan 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 Type Code* Safety Function
- b. Align Hot Leg Recirculation 23 SIP fails to Start 2
A.M. E (000011 EA1.13 R0-4.1 SRO-4.2)
- c. Depressurize RCS during Natural Circ Cooldovvn and Block A.N.L 3 Low Pressure SI (WE09EA1.1 RO-3.5 SRO-3.5)
- d. Energize 480V bus from Appendix R EDG (00Cl055A 106 N 6 RO- 4.1 SRO-4.5)
- e. Respond to 22 SG "B" Level Channel failure High D 7 (059000A4.08 RO-3.0 SRO-2.9)
- h. Verify Containment Phase A Isolation Manually Close E,A,D 5 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 D 6 SRO-4.2)
- k. Align 24 Waste Gas Decay Tank for Discharge (071000 R,D 9 2.3.11 RO-3.8 SRO-4.1)
@ 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 I Criteria for RO I SRO-II SRO-U
(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank :::9/:::8/:::4 (E)mergency or abnormal in-plant :<:1/:<::1/:<::1 (EN)gineered safety feature / ;::1 (control room system)
(L)ow-Power / Shutdown :<::1/;::1/;::1 (N)ew or (M)odified from bank including 1(A) -=2/-=2/-=1 (P)revious 2 exams s 31 s 3/ ::: 2 (randomly selected)
(R)CA -=1/;::1/:<::1 (S)imulator
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 N/A R (ATC) 1 N (CRS) Power Escalation N (BOP) 2 XMT I(ATC)
SGN008A I(BOP) 23 SG Controlling Steam Flow Transmitter Fails High TS(CRS) 3 MAL C (BOP)
EPS008L C (CRS) MCC-28 will trip on overcurrent.
TS (CRS) 4 MAL-C (ALL)
Loss of offsite power due to Loss of Station Aux Transformer.
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 CVC002 C(ALL) 300 GPM Seal LOCA Crew will take actions for Safety 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.
9 N/A C(ATC) 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 of offsite 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)
TS (CRS) RCS Loop 2:3 T-Hot fails high RCS04:3~A~'-_ _ _+-________________________________~1 2 CVH- R (ATC)
CFW009B N (CRS) 24 MFRV will slowly drift closed due to a broken air line prompting a Rapid Load Shutdown N (BOP) 3 MAL C (ATC)
CRF002AV C (CRS) Control Rod P-6 "ratchets in" during rod motion.
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 1 N/A R (ATC)
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 6 MOC C (CRS)
C (BOP) RHR pumps will not auto start and need to be started manually.
RHR003/4 7 RLY PPL085/09 C (BOP) 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'" Descri ption 1 XMT I (ALL)
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 SWI C (CRS)
PORV 456 loss of control power when attempted to open RCS006B C (BOP)
SWI RCS006C 8 AOV C (CRS) Auxiliary Spray Valve 212 will open but will failed closed resulting 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)