ML12332A097

Final Outlines (Folder 3)

ML12332A097
Person / Time
Site:	Ginna
Issue date:	10/18/2012
From:	Peter Presby Operations Branch I
To:	Geckle M Constellation Energy Nuclear Group
Jackson D
Shared Package
ML12137A368	List: IR 05000244/2012301 ML12143A262 ML12272A026 ML12291A019 ML12332A097 ML12332A107 ML12332A110 ML12339A253 ML12339A257 ML12356A332 ML12356A346 ML12356A352 ML12356A369 ML12356A376
References
TAC U01857
Download: ML12332A097 (33)

Text

{{#Wiki_filter:ES-401 PWR Examination Outline Form ES-401-2 II Robert E Ginna Date of Exam: October 18, 2012 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

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

Abnormal 2 1 1 2 N/A 2 2 N/A 1 9 2 2 4 Plant

                                                                                                                              ~

Evolutions Tier Totals 4 4 5 5 5 4 27 5 10 1 3 2 3 4 2 2 2 3 2 2 3 5 2. Plant Systems 2 1 1 0 1 2 1 1 2 0 0 1 10 o I 1 3 Tier Totals 4 3 3 5 4 3 3 5 2 2 4 38 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 4 7 Categories 2 3 3 2 1 2 2 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 KIA 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 KIA statements.

4. Select topics from as many systems and evolutions (IS 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 KlAs 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) K/As 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 KlAs.

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.

ES-401 1 RO Form ES-401*2 ES-401 E/APE # I Name I Safety Function

                                   - mationo,",oo and             .               1 (ROI SRO)

KiA Topic(s) Form ES-401-2 IR G # 1 000007 (BWIE02&E10; CE/E02) Reactor X EK1.02 - Shutdown Margin 3.4 2 Trip - Stabilization - Recovery 11 Knowledge of the operational implications of the following concepts as they apply to the reactor trip: 000009 Small Break LOCA I 3 X EK2.03 - S/Gs 3.0 8 Knowledge of the interrelations between the small break LOCA and the followina: 000011 Large Break LOCA I 3 X EK3.13 - Hot-leg injection/recirculation 3.8 12 Knowledge of the reasons for the following responses as the apply to the Large Break LOCA: 000015/17 RCP Malfunctions I 4 X AA11.08 S/G LCS 3.0 16 Ability to operate and I or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): 000022 Loss of Rx Coolant Makeup I 2 X AA1.06 CVCS charging pump 2.9 18 ammeters and running indicators Ability to operate and I or monitor the following as they apply to the Loss of Reactor Coolant Makeup: 000025 Loss of RHR System I 4 2.4.4~ Knotf}ledge of the emeFgency 2a action level thFesholds and classifications. X 2.4.11 - Knowledge of abnormal 4.0 22 condition procedures 000026 Loss of Component Cooling X AK3.04 - Effect on the CCW flow 3.5 28 Water 18 header of a loss of CCW Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: 000027 Pressurizer Pressure Control X AK2.03 - Controllers and positioners 2.6 32 System Malfunction I 3 Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: 000038 Steam Gen. Tube Rupture I 3 X EK1.01 Use of steam tables 3.1 38 Knowledge of the operational implications of the following concepts as they apply to the SGTR:

000040 (BW/E05; CE/E05; W/E12) X AK2.02 Sensors and detectors 2.6 42 Steam Line Rupture - Excessive Heat Transfer 14 Knowledge of the interrelations between the Steam Line Rupture and the following: 000054 (CE/E06) Loss of Main X AA1.03 AFW auxiliaries, including oil 3.5 48 Feedwater 14 cooling water supply Ability to operate and I or monitor the following as they apply to the loss of Main Feedwater (MFW): 000056 Loss of Off-site Power 16 :a.:a.44 Ability te iAte~p~t GeRt~1 ~eem 52 iRciiGalieRs te ..'eFity the staws aRci epe~tieR ef a system, aRci YRcie~taRci tlew epe~tel' aGtieRs aRci cii~Gti¥es aff.eGt

                                                      ...1",... "'......         * *

• X 2.4.9 Knowledge of low power/shutdown 4.2 52 implications in accident (e.g., lOCA or loss of residual heat removal) mitigation strategies.

000057 Loss of Vital AC Inst. Bus I 6 X AK3.01 Actions contained in EOP for loss 4.1 56 of vital ac electrical instrument bus Knowledge of the reasons for the following responses as they apply to the loss of Vital AC Instrument Bus: 000062 Loss of Nuclear Svc Water I 4 X 2.4.11 Knowledge of abnormal condition 4.0 58 procedures. W/E04 LOCA Outside Containment I 3 X EA2.1 - Facility conditions and selection of 3.4 62 appropriate procedures during abnormal and emergency operations. Ability to determine and interpret the following as they apply to the (lOCA Outside Containment) W/E11 Loss of Emergency Coolant X EA2.2 - Adherence to appropriate 3.4 68 Recirc./4 procedures and operation within the limitations in the facility license and amendments Ability to determine and interpret the following as they apply to the (loss of Emergency Coolant Recirculationl BW/E04; W/E05 Inadequate Heat X EK1.1 Components, capacity, and function 3.8 72 Transfer - Loss of Secondary Heat Sink I 4 of emergency systems. Knowledge of the operational implications of the following concepts as they apply to the floss of Secondary Heat Sink) 000077 Generator Voltage and Electric X AA2.06 - Generator frequency limitations 3.4 75 Grid Disturbances 16 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: KIA Category Totals: 3~pointTotal: 18

ES-401 2RO Form ES-401*2 ES-401 PWR Examination Outline Form lant Evolutions - Tier 1/Gr 0) E/APE # / Name / Safety Function I~I~I K~G 312 KIA Topic{s) IR # 000003 Dropped Control Rod I 1 X AK2.05 - Control rod drive power 2.5 10 supplies and logic circuits Knowledge of the interrelations between the Dropped Control Rod and the following: 000005 Inoperable/Stuck Control Rod 11 X AA2.03 - Required actions if more 3.5 20 than one rod is stuck or inoperable Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod: 000036 (BW/A08) Fuel Handling Accident 1 8 X AK3.03 - Guidance contained in EOP 3.7 30 for fuel handling incident Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: 000037 Steam Generator Tube Leak 13 2.2.38 KRe'Nledge ef seRditieRs

                                                                                          .  +,",,,,,j:. . .  ;~    "

as X 2.1.28 - Knowledge of the purpose 3.6 36 and function of major system components and controls 000059 Aeei(,jentalli~lji(,j RaElWaste ReI. ! 9 AK2.02 Radieastive gas meRiteF6 40 KRe'Nledge ef the iRteFrelatieFis bet\t.'eeFi the AssideFital biql:lid D ...... .+.... .... +10 4',,11. 000068 (BW/A06) Control Room Evac. / 8 X AK3.09 Transfer the following to 3.9 40 local control: Charging pumps, charging header flow control valve, PRZR heaters, and boric acid transfer pum~s W/E01 & E02 Rediagnosis & SI Termination 1 3 X EA2.1 - Facility conditions and 3.2 50 selection of appropriate procedures during abnormal and emergency operations Ability to determine and interpret the following as they apply to the (Reactor Trip or Safety Injection Rediagnosis) W/E15 Containment Flooding 15 X EA1.2 - Operating behavior 2.7 60 characteristics of the facility Ability to operate and I or monitor the following as they apply to the (Containment Flooding) W/E16 High Containment Radiation 19 X EA1.1 - Com ponents, and functions 3.1 70 of control and safety systems. including instrumentation. signals, interlocks, failure modes, and automatic and manual features Ability to operate and I or monitor the following as they apply to the (High Containment Radiation)

BWIE09; CE/A13; W/E09&E10 Natural eire. 14 x EK1.3 - Annunciators and 3.3 73 conditions indicating signals, and remedial actions associated with the Natural Circulation with Steam Void in Vessel withlwithout RVLlS Knowledge of the operational implications of the following concepts as they apply to the Natural Circulation Operations als:

ES-401 3RO Form ES-401-2 Form ES-401-2 ES-401

                                         ~ot S .tem.

PWR Examination Outline T., 21GrnuD 1 (RO I SRO) System # / Name K K K KKAAAA G KIA Topic(s) IR # 1 2 3 561234 003 Reactor Coolant Pump X KS.14 Starting requirements 2.6 1 Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: 004 Chemical and Volume X K1.07- NIS 2.6 3 Control Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: 005 Residual Heat Removal X K4.03 - RHR heat exchanger 2.9 5 bypass flow control Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following: 006 Emergency Core Cooling X A2.04 - Improper discharge 3.4 7 pressure Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: QQ7 I2res&\lFi~eF Relief,IQl;leAsR :U.23 Abili~' te pe~Fm 44

+aAA                                                                   epeGifiG system and integFated plant pFeGedWFeS dWAng all
                                                                                .11

• 026 Containment Spray X 2.1.27 Knowledge of system 3.9 11 purpose and/or function 007 Pressurizer Relief/Quench M.03 Menitcning "!wenGh tank U ta Tank tempeFatwFe Ability te prediGt andteF meniteF Ghanges in paFameteF6 (t9 pre'Jent eXGeeding design limite) ass9GiateEi '.....<ith 9peFating the DDT~ * .lIl ....
• 064 Emergency Diesel Generator X A1.03 - Operating voltages, 13 currents, and temperatures Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G controls including:

008 Component Cooling Water A1.03 CCW PFeSSUFe ~ Ability t9 pFediGt aRd.!9F m9Rit9F GhaRges iR paFameteFB (t9 pFe¥eRt eXGeediRg desigR limits) ass9Giated ......ith 9peFatiRg the

                                              "Ale!           ;"~I .. ~; .....

• X K4.01 - Automatic start of 3.1 15 standby pump Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:

008 Component Cooling Water 2.2.44 Ability t9 iRteFpFet 33 G9RtF91 FG9m iRdiGati9Rs t9 ¥eFify the status aRd 9peFati9R 9f a system, aRd uRdeFBtaRd h9....' 9peFat9F aGti9Rs aRd diFeGti¥es affeGt plaRt aRd system G9Rditi9Rs: X 2.4.21 - Knowledge of the 4.2 33 parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, RCS integrity, containment conditions, radioactivity release control, etc. 010 Pressurizer Pressure Control X K2.02 - Controller for PZR spray 2.5 17 valve Knowledge of bus power supplies to the following: 012 Reactor Protection X K6.02 - Redundant channels 2.9 21 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: 013 Engineered Safety Features X A2.04 - Loss of Instrument bus 3.6 23 Actuation , Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; 013 Engineered Safety Features X K5.02 - Safety System logic and 2.9 25 Actuation reliability Knowledge of the operational implications of the following concepts as they apply to the ESFAS: 022 Containment Cooling X K4.01 - Cooling of containment 2.5 27 penetrations Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following:

022 Containment Cooling 2,2.44 ABility:te iRteFP~t M GeRtFel Feem iRdiGatieRs te ..'eFify the statl:lS aRd apeFatiaR af a system, aRd I:IRdeFSlaRd heo.... epeFateF aGti9R& aRd di~Gti>.<es affeGt plaRt aRd system G9RditiaRs: 2.4.4~ KRa>JJledge af the 31 emeFgeRGY aGtiaR le..'el th~sheld& aRd Glas&ifiGatiaRS X 2.4.31 - Knowledge of 4.2 31 annunciator alarms, indications, or response procedures: 026 Containment Spray X K3.01-CCS 3.9 35 Knowledge of the effect that a loss or malfunction of the CSS will have on the following: 039 Main and Reheat Steam X K3.06-SDS 2.8 37 Knowledge of the effect that a loss or malfunction of the MRSS (Main and Reheat Steam Sys) will have on the followi'!9: 059 Main Feedwater X K4.17 -Increased feedwater flow 2.5 41 following a reactor trip Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: 061 Auxiliary/Emergency X K5.03 - Pump head effects when 2.6 43 Feedwater control valve is shut Knowledge of the operational implications of the following concepts as the apply to the AFW: 062 AC Electrical Distribution X K1.04 - Off-site power sources 3.7 45 Knowledge of the physical connections and/or cause effect relationships between the ac distribution system and the following systems: 063 DC Electrical Distribution X A3.01 - Meters, annunciators, 2.7 47 dials, recorders, and indicating lights Ability to monitor automatic operation of the DC electrical system, including: 063 DC Electrical Distribution X A1.01 - Battery capacity as it is 2.5 51 affected by discharge rate Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: 064 Emergency Diesel Generator X K2.02 - Fuel oil pumps 2.8 53 Knowledge of bus power supplies to the following:

073 Process Radiation X A2.02 - Detector failure 2.7 55 Monitoring Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: I 076 Service Water X K1.17-PRMS 57 Knowledge of the physical connections and/or cause- effect relationships between the SWS and the following systems: 078 Instrument Air X A3.01 - Air pressure 3.1 61 Ability to monitor automatic operation of the lAS, including: Q78 Instrument Air A4.01 Pressyre gayges &3 Ability ta maRl,lally aperate aAdial' maAital' iA iRe 6aAtmlmam: 012 X A4.01 - Manual Trip button 4.5 63 Ability to manually operate and/or monitor in the control room: 103 Containment X K3.03 - Loss of containment 3.7 65 integrity under refueling operations Knowledge of the effect that a loss or malfunction of the containment system will have on the following: 103 Containment X A4.03 - ESF slave relays 2.7 67 Ability to manually operate and/or monitor in the control room: 3 2 3 4 2 3 Group Point Total: 28

ES-401 5RO Form ES-401*2

-~

1 PWR Examination Outline

                                  ~UP2(ROfSRO)

F System # I Name K K G KIA Topic(s) IR # 1 234561 A2.14 - Urgent failure alarm, 001 Control Rod Drive X including rOd-out-of-sequence and 3.7 6 motion-inhibit alarms Ability to (a) predict the impacts of the following malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: 011 Pressurizer Level Control X K6.05 - Function of PZR level 3.1 9 gauges as post-accident monitors Knowledge of the effect of a loss or malfunction on the following will have on the PZR LCS: 014 Rod Position Indication X K1.01-CRDS 3.2 19 Knowledge of the physical connections and/or cause effect relationships between the RPIS and the following systems: 015 Nuclear Instrumentation X K2.01 - NIS channels, components, 3.3 29 and interconnections Knowledge of bus power supplies to the following: 033 Spent Fuel Pool Cooling 2.2.38 KR9..,,-'ledge of G9RditioR6

                                                                              . ,,.~ ". .m ,"

X 2.2.22 - Knowledge of limiting 3.6 conditions for operations and safety limits 045 Main Turbine Generator X A1.06 - Expected response of 3.3 46 secondary plant parameters following T/G trip Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including:

071 IJ>Jaste Gas Disposal K5.04 RelatieAstlip ef 49 tlydmgenlexygen GenGentratieAs te flammability Knowledge ef tt:\e eperatienal impliGatien ef tt:\e telle~""ing GeAGepts as tt:\ey apply te ttle IAI. -""',..... ...

• 016 Non-Nuclear Instrumentation X K5.01 - Separation of control and 2.7 49 protection circuits Knowledge of the operational implication of the following concepts as they apply to the NNIS 072 Ar:ea RadiatieR MeRiteriRg A3.0~ Ctlanges iFt ..' entilatien 68 alignment Ability te meniteF autemaliG eperatieR ef the ARM system, 002 RCS KS.1 & Reason teF tt:\e autematiG 68 featUF8S ef ttle ~eedwateF CentFeI system aUFing tetal less ef Fea&teF Geelant fle'I.'

X K5.08 Why PZR level should be 3.4 59 kept within the programmed band Knowledge 079 StatioR ,A,ir A4.01 CFeSS tie '.<8I..<8s with I,&,S r; 029 Containment Purge System X A2.01 Maintenance or other activity 2.9 69 (CPS) taking place inside CNMT Ability to (a) predict the impacts of the following malfunction or operations on the CPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: 086 Fire Protection X K4.02 - Maintenance of fire header 3.0 74 pressure Knowledge of design feature(s) and/or interlock(s) which provide for the following: KiA Category Point Totals: ~Gl:tl:ilit: 2 1 Group Point Total: 10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) - RO Form ES-401-3 II ility: Date of Exam: Category KIA # Topic RO SRO-Only i IR # IR # 2+.41- Ability t9 make aSGurate, slear, and G9nGise J,.9 4

                                .MIo._

1. Conduct 2.1.32 Ability to explain and apply system limits and 3.8 4 precautions of Operations 2.1.20 Ability to interpret and execute procedure steps. 4.6 14 Subtotal 2 2.2.14 Knowledge of the process for c(lntrolling 3.9 24 equipment configuration or status.

                   ~        Kn9wledge         9f the preGess   f9r managing   U       2i 2.

Equipment

                            ..,    .L   .L   ...; _ _  **

• Control 2.2.42 Ability to recognize system parameters that are 3.9 26 entry level conditions for Tech Specs i 2.2.38 Knowledge of conditions and limitations in the 3.6 34 facility license.

Subtotal 3 ' ',,:

                   ~        Ability t9 G9mply with radiati9n ~"19rk permit    a.a     44 re'luiremel'1ts during R9rmal 9r abn9rmal s9nditi9ns.

3. 2.3.12 Knowledge of radiological safetl' principles 3.2 44 Radiation pertaining to licensed operator duties, such as Control containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc. 2.3.11 Ability to control radiation releases. 3.8 54 2.3.13 Knowledge of radiological safety procedures 3.4 64 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Subtotal 3 2.4.13 Knowledge of crew roles and responsibilities 4.0 66 during EOP usage. 4. Emergency 2.4.23 Knowledge ofthe bases for prioritizing 3.4 71 emergency procedure implementation during Procedures I emergency operations. Plan , ,i< Subtotal 2 ',' i Tier 3 Point Total 10

ES-401 1 SRO Form ES-401*2 ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1/Grouo 1 (RO 1 SRO) E/APE # 1 Name I Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000008 Pressurizer Vapor Space M2,~O WigR pF8SSYFe injeGti9n +1 Accident 1 3 l/allo'es and G9ntroileFS Ability t9 deteFmine and inteFpret tRe fGII9wing as tRey apply t9 tRe D ___.....I__ * \/"' ....... ~ ............. A * .... x AA~~.28 - Safety parameter display 3.9 system indications 000029 A TWS I 1 x 2.1.20

• Ability to interpret and execute 4.6 procedure steps.

000040 (BW/E05; CE/E05; W1E12) X EA2.2 - Adherence to appropriate 3.9 87 Steam Line Rupture - Excessive Heat Transfer 14 procedures and operation within the limitations in the facility*s license and amendments. Ability to determine and interpret the following as they apply to the (Uncontrolled Depressurization of all Steam Generators) 000055 Station Blackout I 6 X 2.1.25 - Ability to interpret reference 4.2 93 materials, such as graphs, curves, tables, etc. 000058 Loss of DC Power I 6 X 2.4.20 - Knowledge of the operational 4.3 97 implications of EOP warnings, cautions, and notes. 000065 Loss of Instrument Air I 8 X AA2.07 - Whether backup nitrogen 3.2 100 supply is controlling valve position Ability to determine and interpret the following as they apply to the Loss of Instrument Air: KIA Category Totals: 3 3 Group Point Total: 10/0 II

ES-401 2SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emeraency and Abnormal Plant Evolutions - Tier 1IGrou-,,- 2JHO 1 SRO) E/APE # 1 Name 1 Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000068 (8W/A06) Control Room Evac. 1 8 X 2.4.6 - Knowledge of EOP 80 mitjgation strategies. 000069 (W/E14) Loss of CTMT Integrity 1 5 X EA2.1 - Facility conditions and 3.8 85 selection of appropriate procedures during abnormal and emergency operations Ability to determine and interpret the following as they apply to (Loss of CTMT Integrity) 000074 (W/E06&E07) Inad. Core Cooling 1 4 X EA2.2 - Adherence to 3.9 90 appropriate procedures and operation within the limitations in the facilities license and amendments Ability to determine and interpret the following as they apply to (Inadequate Core Cooling) 000076 High Reactor Coolant Activity 1 9 X 2.2.25 - Knowledge of the bases 4.2 95 in Technical Specifications for limiting conditions for operations and safe!}, limits. KIA Cateaorv Point Totals: 2 2 Group Point Total: 9/4

ES-401 3SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group 1 (RO 1 SRO) System # 1 Name K K K K I( K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump A2.04 Effects of fluctuation 16 of )tCl= pfessufe on RCP seal injection flow Ability to {a} pfedict the impacts of the follotlJing malfunctions Of opefations on the RCPS; and {b} based on those pl'8dictions, use pfocedufes to cOffect, control, Of mitigate the consequences of those

                                                                          .I~.*                 .

x A2.01 - Problems with RCP 3.9 76 seals, especially rates of seal leak-off 004 Chemical and Volume X 2.1.23 - Ability to perform 4.4 81 Control specific system and integrated plant procedures during all modes of plant operation. 062 AC Electrical Distribution X A2.08 - Consequences of 3.0 86 exceeding voltage limitations Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or o~erations: 064 Emergency Diesel Generator X 2.4.9 - Knowledge of low 4.2 91 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. 073 Process Radiation X A2.03 - Calibration drift 2.9 96 Monitoring Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: KIA Category Point Totals: 3 2 Group Point Total: 281 5

ES-401 4SRO Form ES-401*2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 21Group 2 (RO 1 SRO) System # 1 Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 002 Reactor Coolant X A2.02 - Loss of coolant 4.4 78 pressure 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 those malfunctions or operations: 029 Containment Purge X A2.04 - Health physics 3.2 88 sampling of containment atmosphere Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: 056 Condensate X 2.1.32 - Ability to explain and 4.0 98 apply system limits and precautions. KIA Category Point Totals: 2 1 Group Point Total: 101 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

• SRO Form ES-401*3 Facility: Date of Exam:

Category KIA # Topic RO SRO-Onlv IR # IR # 2.1.39 Knowledge of conservative decision making 4.3 79 1. Conduct practices. of Operations Subtotal 1 I.,.,,, Knowledge of the process for making design or 3.2 82 operating changes to the facility.

2. 2.2.17 Knowledge of the process for managing 3.8 84 Equipment maintenance activities during power operations, Control such as risk assessments, work prioritization, and coordination with the transmission system operator.

Subtotal 2 2.3.4 Knowledge of radiation exposure limits under 3.7 89 normal or emergency conditions. 3. Radiation 2.3.6 Ability to approve release permits. 3.8 92 Control Subtotal 2 2.4.18 Knowledge of the specific bases for EOPs. 4.0 94 4. Emergency 2.4.29 Knowledge of the emergency plan. 4.4 99 Procedures I Plan Subtotal 2 I I 10 7

ES-401 Record of Rejected KlAs Form ES-401-4 Tier 1 Randomly Reason for Rejection Group Selected KIA T11 G1 056 2.2.44 Per 07106/12 Ginna Outline Comments, questionable duplication of Generic KIA 2.2.44. Replaced with randomly selected 2.4.9 (052) T1/G2 037 2.2.38 Per 07106/12 Ginna Outline Comments, questionable duplication of Generic KIA 2.2.38. Replaced with randomly selected 2.1.28 (036) T2/G1 007 2.2.44 Per 07106/12 Ginna Outline Comments, questionable duplication of Generic KIA 2.2.44. Replaced with randomly selected 026 2. '1.27 (011) T21 G1 008 2.2.44 Per 07106/12 Ginna Outline Comments, questionable duplication of Generic KIA 2.2.44. Replaced with randomly selected 2.4.21 (033) T21 G1 022 2.2.44 Per 07106/12 Ginna Outline Comments, questionable duplication of Generic KIA 2.2.44. Replaced with randomly selected 2.4.41 (031) T2/G2 033 2.2.38 Per 07106/12 Ginna Outline Comments, questionable duplication of Generic KIA 2.2.38. Replaced with randomly selected 2.2.22 (039) T2/G2 079 A4.01 Per 07/24 telecClm with Chief Examiner. He agrees that there could be too much system overlap between this Service Air system KIA and the two 078 Instrument Air KlAs selected in T2IG 1. He authorized the random replacement of system 079 and its previously selected KIA. Replaced with randomly selected 029 A2.01 (069) T3/G2 2.2.20 Per 7/26 telecom with Chief Examiner. Our troubleshooting procedure has no involvement with the ROs. Reselection authorized: randomly selected 2.2.42 (026) T2/G2 072 A3.01 Ginna RMS Area monitors have no automatic operation associated with them. Replaced with 002 K5.16 (059). This replacement resulted in 0 which was too similar to 041, replaced KIA with 002.K5.08 (059) T1/G2 059AK2.02 Ginna only has one AB gas process monitor. Credible scenario might be possible, but plausible distractors were too difficult. Reelaced with 068 AK3.09 {040} T3/G1 2.1.17 Per ES-401-9 CI::>mment, authorized random KIA replacement. Replaced with 2.1.32. (04) T2/G1 0072.1.23 Per ES-401-9 Comment, PRT at Ginna is a very simple system. Authorized random KIA replacement. Replaced with 0262.1.27. (01 'I)

Tier 1 Randomly Reason for Rejection Group Selected KIA T1/G1 0252.4.41 Per ES-401-9 Comment, authorized random KIA re~lacement. Not an RO task. Replaced with 2.4.11. (022) T2/G1 0222.4.41 Per ES-401-9 Comment, authorized random KIA replacement. EALs not an RO task. Replaced with 2.4.31. (031) T2/G2 071 K5.04 Per ES-401-9 Comment, authorized random KIA replacement. Unable to write discriminating O. Replaced with 016 K5.01(049) T2/G1 07SA4.01 Per ES-401-9 Comment, authorized random KIA replacement

                      - too similar to 061. Replaced with 012 A4.01 (063)

T2/G1 003A2.04 Discussed with Chief Examiner per telecom 9/11. Too challenging to write higher cognitive 0 to this KIA. Authorized random replacement with 003. A2.01 (076) T1/G1 OOS AA2.10 Discussed with Chief Examiner per telecom 9/11. Too challenging to write higher cognitive 0 to this KIA. Authorized random replacement with OOS. AA2.2S (077) T2/G1 OOS A1.03 Discussed with Chief Examiner per telecom 9/13. Too challenging to write higher cognitive 0 to this KIA. Authorized random replacement with OOS. K4.01 (015) T3/G3 2.3.7 Too challenging to write a question to this KIA which is not GET knowledge. Replacement KIA authorized by Chief Examiner 10/01l12. Replaced with 2.3.12. (044) T2/G1 007 A1.03 Discussed with Chief Examiner - too difficult to write a design limit question on Ginna's simple PRT design. Authorized replacement 10/01. Replaced with 064 A1.03 (013)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Robert E. Ginna Date of Examination: October 1, 2012 Examination Level: RO X SRO D Operating Test Number: 2012-N-1 Administrative Topic Type Describe activity to be performed (see Note) Code* S,N Perform OPG-REACTIVITY-CALC Conduct of Operations KIA 2.1.37 (4.3/4.6) Knowledge of procedures, guidelines, or limitations associated with reactivity management. R,D Determine maximum allowable Rx Vessel Head Venting time Conduct of Operations KIA 2.1.25 (3.9 I 4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. R,N Perform 11M plot per 0-1.2.1 I Equipment Control KIA 2.2.1 (4.5 14.4) Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. Utilize site survey map and the Radiation Control R,N Manual to determine stay time for local valve operation in the RCA. Radiation Control KIA 2.3.4 (3.2/3.7) Knowledge of radiation exposure limits under normal or emergency conditions. Emergency Procedures/Plan NIA 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 Administrative Topics Outline Form ES-301*1 Facility: Robert E. Ginna Date of Examination: October 1,2012 Examination Level: RO 0 SRO X Operating Test Number: 2012-N-1 Administrative Topic Type Describe activity to be performed (see Note) Code* Perform IV of OPG-REACTIVITY-CALC Conduct of Operations S,N KIA 2.1.37 (4.3/4.6) Knowledge of procedures, guidelines, or limitations associated with reactivity management. Determine the Allowable Hours An Operator Can Work (JR119.001 ) Conduct of Operations R,M KIA 2.1.5 (2.9* /3.9) Ability to use procedures related to shift staffing, such as minimum crew com~lement, overtime limitations, etc. R,N Evaluate 1/M Plot per 0-1.2.1 and 0-1.2 Equipment Control KIA 2.2.1 (4.5/4.4) Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. R,N Determine Worker Availability Based on Radiation Exposure Limits Radiation Control KIA 2.3.4 (3.2/3.7) Knowledge of radiation exposure limits under normal or emergency conditions. R,M Determine PAR and complete EPIP 1-5, Att.3a Emergency Procedures/Plan KIA 2.4.44 (2.4 14.4) Knowledge of Emergency Plan protective action recommendations. 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)irnulator, or Class(R)oom (D)irect from bank (~~ 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: Robert E. Ginna Date of Examination: October 1, 2012 Exam Level: RO X SRO-I D SRO-U Operating Test No.: 2012-N-1 I Control Room Systems<m (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System 1 .IPM Title Type Code'" Safety Function A. 004 Chemical and Volume Control System S,N,A 1 Borate for one rod not fully inserted per ES-0.1 step 4, and ER CVCS.1 004 A4.07 (3.9/3.7): Ability to manually operate and/or monitor in the control room: Boration/dilution B. 006 Emergency Core Cooling System S, N 3 Secure SIPs as part of Termination of Bleed and Feed, per FR H.1, Response To Loss Of Secondary Heat Sink 006 A2.02 (3.9/4.3): Ability to (a) predict the impact of the following operations on the RCS; and (b) based on those predictions, use procedures to control the consequences of those operations: Loss of flow path. C. 005 Heat Removal- Primary System, RHR Sysb~m S,D 4P Align RHR and SI Systems For High Head Recirculation 002 A2.04 (4.3/4.6): Ability to (a) predict the impa,:ts 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 those malfunctions or operations: Loss of heat sinks. D. 045 Heat Removal- Secondary System, Main Turbine S,D,A 4S Generator Synchronize Generator On-Line (Improper Load Pickup) 045 A2.17 (2.7*/2.9*): Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Malfunction of electrohydraulic control. E. 015 Nuclear Instrumentation System S,L, N 7 Perform STP-0-6.1 on Source Range N-31 015 A4.02 (3.9/3.9): Ability to manually operate and/or monitor in the control room: NIS indicators.

F. 064 Electrical S,P 6 Shutdown the "An Emergency Diesel Generator (2008 NRC ILT) 064 A4.06 {3.9/3.9}: Manual start, loading, and stopping of the ED/G. G. 012 Reactor Protection System S,EN,N 7 Respond to a Spurious CVI While at Full Power 012 A2.01 (3.1/3.6): Ability to (a) predict the impacts of the following malfunctions or operation on the RPS; .and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation. H. 008 Plant Service Systems S,A,N 8 Respond to rapidly lowering CCW Surge Tank level 008 A2.02 (3.2/3.5): Ability to (a) predict the impacts of the following malfunctions or operation on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low surge tank level. In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) I. 006 Emergency Core Cooling System R,N 2 Makeup to "An SI Accumulator Using the SI Accumulator Makeup Pump 006 A1.13 (3.5/3.7): Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration). J. 071 Waste Gas Disposal System (2010 NRC ILT) R,P,A 9 Release 'A' Gas Decay Tank 071 A4.27 (3.0* /2.7*): Ability to manually operate and/or monitor in the control room: Opening and closing of the decay tank discharge control valve. K. 103 Containment System E,EN,D 5 Perform Attachment Cl/CVI (Intermediate Bldg Cold Side) 103 A2.03 {3.5* / 3.8*}: Ability to (a) predict the impacts of the following malfunctions or operation on the containment system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A and B isolation.

@ All RO and SRO-I 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 (A)lternate path 4-6 14-6/2-3 (C)ontrol room (D)irect from bank :s9/:s8/:S4 (E)mergency or abnormal in-plant 2::1/2::1/2::1 (EN)gineered safety feature 1 2::1 (control room system)

(L)ow-Power 1 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 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Robert E. Ginna Date of Examination: October 1! 2012 Exam Level: RO 0 SRO-I X SRO-U 0 Operating Test No.: 2012-N-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System 1 JPM Title Type Code* Safety Function A. 004 Chemical and Volume Control System S, N,A 1 Borate for one rod not fully inserted per ES-0.1 step 4, and ER CVCS.1 004 A4.07 (3.9/3.7): Ability to manually operate and/or monitor in the control room: Boration/dilution B. 006 Emergency Core Cooling System S,N 3 Secure SIPs as part of Termination of Bleed and Feed, per FR H.1, Response To Loss Of Secondary Heat Sink 006 A2.02 (3.9/4.3): Ability to (a) predict the impact of the following operations on the RCS; and (b) based on those predictions, use procedures to control the consequences of those operations: Loss of flow path. C. 005 Heat Removal -- Primary System, RHR System S,D 4P Align RHR and SI Systems For High Head Recirculation 002 A2.04 (4.3/4.6): 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 mitjgate the consequences of those malfunctions or operations: Loss of heat sinks. D. 045 Heat Removal -- Secondary System, Main Turbine S, D,A 4S Generator Synchronize Generator On-Line (Improper Load Pickup) 045 A2.17 (2.7*/2.9*): Ability to (a) predict the impacts of the following malfunctions or operation on the MTIG system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Malfunction of electrohydraulic control. E. 015 Nuclear Instrumentation System S, L, N 7 Perform STP-O-6.1 on Source Range N-31 015 A4.02 (3.9/3.9): Ability to manually operate and/or monitor in the control room: NIS indicators.

F. 064 Electrical S, P 6 Shutdown the "An Emergency Diesel Generator (2008 NRC ILT) 064 A4.06 (3.9/3.9): Manual start, loading, and stopping of the ED/G. H. 008 Plant Service Systems S,A, N 8 Respond to rapidly lowering CCW Surge Tank level 008 A2.02 (3.2/3.5): Ability to (a) predict the impacts of the following malfunctions or operation on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low surge tank level. In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) I. 006 Emergency Core Cooling System R,N 2 Makeup to "An SI Accumulator Using the SI Accumulator Makeup Pump 006 A 1.13 (3.5/3.7): Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration). J. 071 Waste Gas Disposal System (2010 NRC ILT) R, P,A 9 Release 'A' Gas Decay Tank 071 A4.27 (3.0* / 2.7*): Ability to manually operate and/or monitor in the control room: Opening and closing of the decay tank discharge control valve. K. 103 Containment System E,EN,D 5 Perform Attachment CI/CVI (Intermediate Bldg Cold Side) 103 A2.03 (3.5* / 3.8*): Ability to (a) predict the impacts of the following malfunctions or operation on the containment system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A and B isolation. @ All RO and SRO-I 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 1 SRO-II SRO-U (A)lternate path 4-6 14-6 1 2-3 (C}ontrol room (D)irect from bank S9/S8/s4 (E}mergency or abnormal in-plant ~1/~1/~1

{EN}gineered safety feature 1 ~1 (control room (L)ow-Power I Shutdown system) {N)ew or (M)odified from bank including 1(A) ~1/~1/~1 {P)revious 2 exams ~2/~2/~1 (R)CA s 31 s 31 s; 2 (randomly (S)imulator selected)

                                                      ~1/~1/~1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Robert E. Ginna Date of Examination: October 1, 2012 Exam Level: RO D SRO-I D SRO-U X Operating Test No.: 2012-N-1 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 A. 004 Chemical and Volume Control System S, N,A 1 Borate for one rod not fully inserted per ES-0.1 step 4, and ER CVCS.1 004 A4.07 (3.9/3.7): Ability to manually operate and/or monitor in the control room: Boration/dilution E. 015 Nuclear Instrumentation System S, L, N 7 Perform STP-O-6.1 on Source Hange N-31 015 A4.02 (3.9/3.9): Ability to manually operate and/or monitor in the control room: NIS indicators. G. 012 Reactor Protection System S,EN,N 7 Respond to a Spurious CVI While at Full Power 012 A2.01 (3.1/3.6): Ability to (a) predict the impacts of the following malfunctions or operation on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) J. 071 Waste Gas Disposal System (2010 NRC ILT) R, P, A 9 Release 'A' Gas Decay Tank 071 A4.27 (3.0'" 12.7"'): Ability to manually operate andlor monitor in the control room: Opening and closing of the decay tank discharge control valve. K. 103 Containment System E,EN,D 5 Perform Attachment CI/CVI (Intermediate Bldg Cold Side) 103 A2.03 (3.5* 13.8*): Ability to (a) predict the impacts of the following malfunctions or operation on the containment system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A and B isolation.

 @           All RO and SRO-I 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 (A)lternate path 4-6 1 4-6 12-3 (C)ontrol room (D)irect from bank s9/s8/S4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - / - I ~1 (control room system)

. (L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams s 31 s 31 s 2 (randomly selected) (R)CA ~1/~1/~1 (S)imulator

2012 Ginna ILT Operating Exam Review/Walkthrough Comments & Resolution '-~~ JPM Page Comment Resolution Sim JPM 'B' 1 Prep week version had one PORV failure to open, which had Reverted back to initial condition with both PORVs open (Secure SI pumps the potential for confusing candidate as to the initial condition as part of entry point within the procedure terminating RCS 12 Original version allowed a success path "option" to E-1 entry Removed success path option for E-l entry and added more feed and bleed) detail to Examiner Note

    --~

Sim JPM 'D' 3 Original malfunction severity had no consequence beyond Changed MALF TUR18 from 25MW severity to OMW severity to (Synchronize procedural violation. provide consequence for inaction (reverse power trip in ~1 Generator On-Line min) with improper load pickup)

 --~

Sim JPM 'H' 2 Original version had MALF CLGOS severity set to 100GPM Changed leakrate severity ramp/insertion times to allow (Respond to consistent evaluation of operator response rapidly lowering CCW surge tank level) In-Plant JPM 'I' f----~ 1 Change Method of Test to "Simulated" and "Plant" Modified (Makeup to 'A' SI r- ~-~ 2 Ensure Initiating Cue information aligns with Cue Sheet Modified Cue Sheet, then copied to p2 Accumulator using 10 Delete page reference at top of page. Delete 5th bullet in Initial Changes made as requested. SI Accumulator Conditions (duplicate information). Delete all peripheral Makeup Pump) directions on CUE sheet to minimize the amount of information the candidate has to read. In-Plant JPM 'J' 1 Change Method of Test to "Simulated" and "Plant" Modified (Release the"A" 2 Typo under Instructor Actions: "and" should be "are". Ensure Mark up procedure. Gas Decay Tank) student H/O is marked up per this note. 4 Delete first "CUE" in Step 4 - already provided this material to Deleted.

                    !----~

examinee in Step I, no need for further mention. r---~ 8 Change "As examinee ..." to "IF examinee ..." Changed. 10 Add clarification to CUE when to report that R-14 indicates Added clarifications. 2x105 cpm. Also, clarification added if asked "Is R-14 in alarm?" 13 Delete page reference at top of page. Clarified first bullet for Changes made as requested. Initiating Cue. Delete all peripheral directions on CUE sheet to

  ~-~    ~--                   ~ -~

minimize the amount of information the candidate has to read. ~-

                                                                                                               --   -~    ~-~   ~-~   -~    ~-~  ~-~ .............-

I In-Plant JPM 'K' 1

                                       ~~ange     Method of Test to "Simulated" and "Plant"              Modified (Perform                   3           List possible locations/methods whereby the candidate may         Methods added (FCMS or copy from Control Room)

Attachment CIjCVI locate a copy of the attachment. Add NOTE that applicant must Added NOTE. for Valves in the demonstrate eSOMS information himself. Intermediate 4,5 Changed CUEs for eSOMS locations to NOTEs per previous Changed eSOMs CUES as described. Building Clean ~I'l.:lnge requiring applicant to determine information himself. f--- ------- Side) 7 Delete page reference at top of page. Clarify first bullet in All changes made as requested. Initiating Cue and remove other bulleted information. Delete all peripheral directions on CUE sheet to minimize the amount of information the candidate has to read. nd Admin RA-l 2 Remove 2 bullet from Initiating Cue to agree with candidate Removed. (Perform OPG- Cue Sheet. REACTIVITY-CALC) 4 Add Examiner NOTE to reflect how the PCNDR spreadsheet Added new EXAMINER NOTE. program is initialized ("Enable Macros") 11 Delete page reference at top of page. Remove 2 nd bullet {{Do Changes made as requested. Not Print" directions from Initiating Cue. Delete all peripheral directions on CUE sheet to minimize the amount of information ~----- the candidate has to read. nd Admin RA-2 7 Delete page reference at top of page. Remove 2 bullet, Changes made as requested. (Determine guidance for rounding off values, from Initiating Cue. Delete all Maximum peripheral directions on CUE sheet to minimize the amount of Allowable RV information the candidate has to read. Head Venting KEY Add acceptable answer margins contained within the JPM to Acceptable margins added to answer key. Time) ------- the answer key. Admin RA-3 2 Add new section to document "Questions" Added. (Perform l/M Plot 10 Delete page reference at top of page. Delete all peripheral Changes made as requested. per 0-1.2.1) directions on CUE sheet to minimize the amount of information the candidate has to read. Admin RA-4 1 Replace valve with a significant manual valve without divulging Replaced valve and modified survey map accordingly. Added (Determine stay its location on the survey map. Make the candidate find the "procedures cart" to list of required materials. Modified Initial time for local appropriate procedure (allow access to procedures cart). Conditions on this page and on p6. valve operation in Modify Initial Conditions to reflect changed conditions. the RCA)

Admin RA-4 2 Do not provide A-I procedure to candidate, but make available Changes made as requested. (Cont'd) on procedures cart. Change wording on Initiating Cue to reflect new valve, modified conditions. ------ 3 Modify Step 1 to reflect candidate needs to locate appropriate Steps 1 and 2 modified. r----~~-~ procedure on cart. Modify Step 2 to reflect new valve/location.

                             ~~~~-~

4 Modify calculations to reflect changed dose rates for the year. All calculations revised. Determine limiting dose and calculate new stay time. 6 Modify Initial Conditions and Initiating Cue to reflect new Changes made as requested. values limitations. Delete page reference at top of page. Delete all peripheral directions on CUE sheet beyond technical info. 7 Add Current Exposure data sheet to the JPM package itself. Data sheet added to JPM file. Admin SA-l 4 Add Examiner NOTE to reflect how the PCNDR spreadsheet Added new EXAMINER NOTE. (Verify OPG- program is initialized ("Enable Macros") REACTIVITY-CALC) 11 Delete page reference at top of page. Delete all peripheral Changes made as requested. directions on CUE sheet to minimize the amount of information the candidate has to read. Admin SA-2 8 Delete page reference at top of page. Delete all peripheral Changes made as requested. (Determine The directions on CUE sheet to minimize the amount of information Allowable Hours the candidate has to read. An Operator Can Work) r~~-~~ Admin SA-3 12 Delete page reference at top of page. Delete all peripheral Changes made as requested. (Evaluate 1/M Plot directions on CUE sheet to minimize the amount of information per 0-1.2.1and 0 the candidate has to read. 1.2) ----- Admin SA-4 1 Replace valve with a significant manual valve without divulging Replaced valve and modified survey map accordingly. Added (Determine its location on the survey map. Make the candidate find the "procedures cart" to list of required materials. Modified Initial Worker appropriate procedure (allow access to procedures cart). Conditions on this page and on p6. Availability Based Modify Initial Conditions to reflect changed conditions. on Radiation 2 Do not provide A-I procedure to candidate, but make available Changes made as requested. Exposure Limits) on procedures cart. Change wording on Initiating Cue to reflect new valve, modified conditions, more information required of SRO candidate.

Admin SA-4 3 Modify Step 1 to reflect candidate needs to locate appropriate Steps 1 and 2 modified. (Cont'd) procedure on cart. Modify Step 2 to reflect new valve/location and change in dose rate value (same as N-RA-4).

• 4 Modify calculations to reflect changed dose rates for the year. All calculations revised.

Determine limiting dose and calculate new stay time to nearest limit. S Add new step to identify which dose limit will be exceeded. Added new step 6 Modify step to reflect revised dose limit, new approvals. Modified. 8 Modify Initial Conditions and Initiating Cue to reflect new Changes made as requested. values and new required information. Delete page reference at top of page. Delete all peripheral directions on CUE sheet beyond technical info. 9 Add Worker Exposure data sheet to the JPM package itself. Data sheet added to JPM file. Admin SA-S 1 Add steps to complete EPIP-l.5, Att.3a information in addition New information added. (Determine PAR to determining PAR recommendation. and complete EPIP 6,7 Added new performance steps to evaluate new requirement New steps added. 1-5, Attachment above. 3a) 10 Added new information to Initial Conditions and Initiating Cue Initial Conditions and Initiating Cue modified. to enable Att.3a to be completed. KEY Post-Exam Administration. Utility determined that the original Provided revised Answer Key to "Evacuate" answer key to "Shelter" was incorrect.}}