Text

Final Outlines (Folder 3)
	ML15335A331
Person / Time
Site:	Crane
Issue date:	09/18/2015
From:	Peter Presby; Operations Branch I
To:	Carreras E; Exelon Generation Co
Shared Package
ML15135A253	List: IR 05000289/2015301; ML15267A771; ML15292A369; ML15292A370; ML15335A327; ML15335A328; ML15335A329; ML15335A330; ML15335A331; ML15335A332; ML15352A064; ML15352A065;
References
	TAC U01913
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JPM A pl Edited Task Standard pS Edited "Delta" symbol on Performance Step 4 p 10 Added clarification to the Standard under Performance Step 18 pl2 Removed page number from Cue Sheet JPM B pl Edited Task Standard pl Removed bullet in Initial Conditions about increased Letdown flowrates p3 Changed Event 2 items to Event 1 to reflect how the JPM was validated (Steps 2 and 3) p3 Edited MAP malfunction under Step 1 plO Removed bullet in Initial Conditions about increased Letdown flowrates plO Removed page number from Cue Sheet JPM C pl Edited second bullet of the Initial Conditions for clarity p3 Added malfunction to Exam Setup (Step 1.C) p6 Removed unnecessary capitalization in Standard under Performance Step 7 p7 Added Examiner Note directly following Performance Step 11 p7 Enhanced Booth Cue directly following Performance Step 12 p7 Removed unnecessary capitalization in Standard under Performance Steps 11 and 12 p13 Edited second bullet of the Initial Conditions for clarity p13 Removed page number from Cue Sheet JPM D pl Edited Task Standard p9 Removed Performance Step 12 pll Removed page number from Cue Sheet Removed pag JPM E p3 Changed "Trainer" to "Simulator" pll Removed page number from Cue Sheet JPM F p2 Edited Task Standard p2 Changed Time Critical from "Yes" to "No" p3 Changed a Simulator Override to a Remote Function (fourth bullet from the bottom) p4 Edited Coding nomenclature for bullets #2 and 3 pl6 Changed Time Critical from "Yes" to "No" pl6 Removed page number from Cue Sheet JPM G pl Enhanced fifth and last bullets under Initial Conditions p2 Edited third bullet under Required Materials p9 Enhanced Evaluator Note just prior to Performance Step 16

pl9 Enhanced fifth and last bullets under Initial Conditions pl9 Removed page number from Cue Sheet JPM H pl Edited Task Standard p2 Removed Steps 4 and 5 under Simulator Setup due to being repeated in Steps 7 and 8 p4 Changed Font issues on Performanc Step 2 plO Removed page number from Cue Sheet JPM I p3 Added Evaluator Note prior to Performance Step 1 p6 Removed page number from Cue Sheet JPM J p3 Added Evaluator Cue just after Performance Step 1 p4 Edited second Evaluator Cue after Performance Step 3 for accuracy pS Edited Terminating Cue p7 Removed page number from Cue Sheet JPM K Pl Added last procedure under General References p4 Added Evaluator Note at top of page p9 Removed page number from Cue Sheet JPM RO Al-1 pl Edited Task Standard pl Edited Bullets #3 and 7 under Initial Conditions p7 Edited Bullets #3 and 7 under Initial Conditions p7 Removed page number from Cue Sheet p8 Removed page number from Cue Sheet p8 Changed shaded blocks for clarity JPM RO Al-2 pl Edited Task Standard pl Removed last bullet under Initial Conditions pl2 Removed page number from Cue Sheet JPM RO A2 pl Edited last 2 bullets under the first Time stamp of the Initial Conditions p7 Edited second position in Table p9 Edited last 2 bullets under the first Time stamp of the Initial Conditions p9 Removed page number from Cue Sheet

JPM RO A4 pl Edited Task Standard p7 Added Evaluator Cue just prior to Performance Step 10 p10 Removed page number from Cue Sheet JPM SRO Al-1 pl Edited next-to-last bullet under Initial Conditions p9 Edited next-to-last bullet under Initial Conditions p9 Removed page number from Cue Sheet plO Removed page number from Cue Sheet pll Removed page number from Cue Sheet JPM SRO Al-2 pl Edited second bullet under Initial Conditions pl Edited Task Standard p2 Edited Initiating Cue p9 Edited Evaluator Note prior to Performance Step 19 p12 Edited Initiating Cue p12 Edited second bullet under Initial Conditions p12 Removed page number from Cue Sheet p13 Removed page number from Cue Sheet JPM SRO A2 pl Edited last 2 bullets under the first Time stamp of the Initial Conditions pS Edited Standard under Performance Step 3 pg Edited second position in Table pll Edited last 2 bullets under the first Time stamp of the Initial Conditions p11 Removed page number from Cue Sheet JPM SRO A3 pl Edited Task Standard pl Edited Initial Conditions p2 Edited Initiating Cue p3 Edited Performance Step 2 pS Edited performance Step 6 p6 Edited first and third sections under Table 2 p8 Removed page number from Cue Sheet Scenario 1

pl Added more to initial conditions

pl Removed first Critical Task pl Changed URO to ARO for Event 4 p3 Verified no overlap with regards to MU-V-17 plO Removed first Critical Task p13 Added feed limits for EFW with and without RCP's pl6 Clarified remote function pl7 Clarified information to match simulator setup pl8 Clarified information to match simulator setup pl9 Changed 30 day timeclock to 7 day p20 Edited indications available p21 Edited indications available p22 Added AOP-001, Fire, actions due to invalid alarms that require attention p22 Edited to make either ventilation train possible p24 Added note to continue with scenario p26 Note added about OP-TM-641-404 p27 Edited indications available p27 Edited booth cue p28 Removed unnecessary step from top of page p30 Edited first line for crew p33 Edited indications available p35 Edited Booth cue p48 Changed EAL Scenario 2

pl Edited events 3 and 5 description p3 Edited criteria to move on from event 2 pS Edited tech specs for event 3 pS Edited crew actions for event 3 pl7 Clarified information to match simulator setup pl8 Clarified information to match simulator setup p20/21 Clarified note about key p26 Edited crew action p28 Addressed tech spec call p28/29 Added action for MU-V-3 p28 Added to last step listed on page p29 Edited RNO step numbers Sceanrio 3

pl Added to initial conditions pl Edited Event #5 line p7 Edited MS-V-SB plS Fixed symbol top half of page pl8 Clarified information to match simulator setup pl9 Edited first Examiner Note

p21 Edited information about no HPI flow once MUP is secured p29 Edited examiner note p35 Added reratio steps p36 Edited second booth cue p37 Edited last step on page p38 Edited last step on page P42 Added routing note based on procedures Scenario 5

pl Rearranged events 3 and 4 pl Added description to event 6 pl Changed IC number plS Clarified information to match simulator setup pl7 Added cue about rx eng.

p23 Removed last step p34 Typo in second step fixed p42 Changed URO to ARO in first step

ES-401 PWR Examination Outline Form ES-401-2 Facility: Three Mile Island Date of Exam: 09/28/2015 RO KIA Category Points SRO-Only Points Tier Group K

K K

K A

A A

A G

1 2

3 4

5 6

1 2

3 4

Total A2 G*

Total

1.

Emergency 1

3 3

18 3

3 6

& Abnormal 2

1 2

1 N/A 2

2 N/A 1

9 2

2 4

Plant Evolutions Tier Totals 4

5 4

5 5

4 27 5

5 10 1

3 2

3 3

3 2

2 3

2 28 3

2 5

2.

Plant 2

1 1

0 10 0

2 1

3 Systems Tier Totals 4

3 4

4 4

3 3

4 3

4 2

38 5

3 8

3. Generic Knowledge and Abilities 1

2 3

4 1

2 3

4 Categories 2

3 2

3 10 2

2 1

2 7

Note:

1.

Ensure that at least two topics from every applicabl'e K/A category are sampled within each tier of the RO and SRO outlines (i.e. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category.)

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 K/A statements.

4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/As 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 K/A categories.

7.*

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A 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 K/As.

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 K/A catalog, and enter the K/A numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G*

Generic K/As ES-401, Page 21 of 33

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

EK1.2 - Knowledge of the operational implications of the following concepts as 000007 (BW/E02&E10; CE/E02) Reactor x

they apply to the (Post-Trip Stabilization):

3.5 Trip - Stabilization - Recovery I 1 Normal, abnormal and emergency operating procedures associated with (Post-Trip Stabilization)

AK2.03 - Knowledge of the interrelations 000008 Pressurizer Vapor Space x

between the Pressurizer Vapor Space 2.5 Accident I 3 Accident and the following: Controllers and positioners EA2.04 - Ability to determine or interpret 000009 Small Break LOCA I 3 x

the following as they apply to a small 3.8 break LOCA: PZR level EK2.02 - Knowledge of the interrelations 000011 Large Break LOCA I 3 x

between the and the following Large 2.6 Break LOCA: Pumps AA 1.02 - Ability to operate and I or monitor the following as they apply to the 000015/17 RCP Malfunctions I 4 x

Reactor Coolant Pump Malfunctions (Loss 2.8 of RC Flow): RCP oil reservoir level and alarm indicators 2.2.39 - Knowledge of less than or equal 000022 Loss of Rx Coolant Makeup I 2 x

to one hour Technical Specification action 3.9 statements for systems.

AK3.02 - Knowledge of the reasons for the following responses as they apply to the 000025 Loss of RHR System I 4 x

Loss of Residual Heat Removal System:

3.3 Isolation of RHR low-pressure piping prior to pressure increase above specified level AK3.02 - Knowledge of the reasons for the following responses as they apply to the 000026 Loss of Component Cooling x

Loss of Component Cooling Water: The 3.6 Water I 8 automatic actions (alignments) within the CCWS resulting from the actuation of the ES FAS 000027 Pressurizer Pressure Control x

2.4.18 - Knowledge of the specific bases 3.3 System Malfunction I 3 for EOPs.

EK1.01 - Knowledge of the operational implications of the following concepts as 000029 A TWS I 1 x

they apply to the ATWS: Reactor 2.8 nucleonics and thermo-hydraulics behavior 000040 (BW/E05; CE/E05; W/E12)

AK1.06 - Knowledge of the operational Steam Line Rupture - Excessive Heat x

implications of the following concepts as 3.7 Transfer I 4 they apply to Steam Line Rupture: High energy steam line break considerations AA 1.01 - Ability to operate and I or 000054 (CE/E06) Loss of Main monitor the following as they apply to the Feedwater I 4 x

Loss of Main Feedwater (MFW): AFW 4.5 controls, including the use of alternate AFW sources x

2.2.42 - Ability to recognize system 000055 Station Blackout I 6 parameters that are entry-level conditions 3.9 for Technical Specifications.

AA2.07 - Ability to determine and interpret the following as they apply to the Loss of 000057 Loss of Vital AC Inst. Bus I 6 x

Vital AC Instrument Bus: Valve indicator 3.3 of charging pump suction valve from RWST ES-401, Page 22 of 33

ES-401 2

Form ES-401-2 AK3.01 - Knowledge of the reasons for the 000058 Loss of DC Power I 6 x

following responses as they apply to the 3.4 Loss of DC Power: Use of de control power by D/Gs AA2.02 - Ability to determine and interpret 000062 Loss of Nuclear Svc Water I 4 x

the following as they apply to the Loss of 2.9 Nuclear Service Water: The cause of possible SWS loss EK2.1 - Knowledge of the interrelations between the (Inadequate Heat Transfer)

BW/E04; W/E05 Inadequate Heat and the following: Components, and Transfer - Loss of Secondary Heat Sink I 4 x

functions of control and safety systems, 3.8 including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

AA 1.04 - Ability to operate and/or monitor 000077 Generator Voltage and Electric x

the following as they apply to Generator 4.1 Grid Disturbances I 6 Voltage and Electric Grid Disturbances:

Reactor controls 000009 Small Break LOCA I 3 x

2.4.41 - Knowledge of the emergency 4.6 action level thresholds and classifications.

EA2.01 - Ability to determine or interpret the following as they apply to a Large 000011 Large Break LOCA I 3 x

Break LOCA: Actions to be taken, based 4.7 on RCS temperature and pressure -

saturated and superheated AA2.09 - Ability to determine and interpret the following as they apply to the Reactor 000015/17 RCP Malfunctions I 4 x

Coolant Pump Malfunctions (Loss of RC

3.5 Flow)

When to secure RCPs on high stator temperatures 2.4.30 - Knowledge of events related to system operation/status that must be 000057 Loss of Vital AC Inst. Bus I 6 x

reported to internal organizations or 4.1 external agencies, such as the State, the NRC, or the transmission system operator.

000058 Loss of DC Power I 6 x

2.4.11 - Knowledge of abnormal condition 4.2 procedures.

EA2.1 - Ability to determine and interpret the following as they apply to the (Vital 000007 (BW/E02&E10; CE/E02) Reactor x

System Status Verification): Facility 4.0 Trip - Stabilization - Recovery I 1 conditions and selection of appropriate procedures during abnormal and emergencv operations.

KIA Category Totals:

3 3

3/

Group Point Total:

18/6 3

3 ES-401, Page 22 of 33

ES-401 3

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

AK2.01 - Knowledge of the interrelations 000005 Inoperable/Stuck Control Rod I 1 x

between the Inoperable I Stuck Control 2.5 Rod and the following: Controllers and positioners AA 1.19 - Ability to operate and I or monitor the following as they apply to 000024 Emergency Boration I 1 x

Emergency Boration: Makeup control 3.2 system selector switch for eves isolation valve AA2.03 - Ability to determine and interpret 000033 Loss of Intermediate Range NI I 7 x

the following as they apply to the Loss of 2.8 Intermediate Range Nuclear Instrumentation: Indication of blown fuse AK1.1 - Knowledge of the operational 000036 (BW/A08) Fuel Handling Accident I implications of the following concepts as 8

x they apply to the (Refueling Canal Level

3.7 Decrease)

Components, capacity, and function of emeroencv svstems.

AK3.01 - Knowledge of the reasons for the following responses as they apply to the 000051 Loss of Condenser Vacuum I 4 x

Loss of Condenser Vacuum: Loss of 2.8 steam dump capability upon loss of condenser vacuum AK2.03 - Knowledge of the interrelations 000069 (W/E14) Loss of CTMT Integrity I 5 x

between the Loss of Containment Integrity 2.8 and the following: Personnel access hatch and ememencv access hatch 2.1.25 - Ability to interpret reference BW/A01 Plant Runback I 1 x

materials, such as graphs, curves, tables, 3.9 etc.

AA2.2 - Ability to determine and interpret the following as they apply to the BW/A05 Emergency Diesel Actuation I 6 x

(Emergency Diesel Actuation): Adherence 3.5 to appropriate procedures and operation within the limitations in the facility*s license and amendments.

EA 1.2 - Ability to operate and I or monitor BW/E13&E14 EOP Rules and Enclosures x

the following as they apply to the (EOP

2.8 Enclosures)

Operating behavior characteristics of the facility.

000024 Emergency Boration I 1 x

2.4.6 - Knowledge of EOP mitigation 4.7 strateoies.

AA2.02 - Ability to determine and interpret 000036 (BW/A08) Fuel Handling Accident I x

the following as they apply to the Fuel 4.1 8

Handling Incidents: Occurrence of a fuel handlina incident AA2.1 - Ability to determine and interpret the following as they apply to the (NNl-X):

BW/A02&A03 Loss of NNl-X/Y I 7 x

Facility conditions and selection of 4.0 appropriate procedures during abnormal and emerqencv operations BW/E08; W/E03 LOCA Cooldown -

x 2.4.18 - Knowledge of the specific bases 4.0 Depress. I 4 for EOPs.

KIA Category Point Totals:

1 2

21 1/

Group Point Total:

9/4 2

2 ES-401, Page 23 of 33

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO I SRO)

System #I Name K

K K

K A

A A

A G

KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 K5.02 - Knowledge of the operational 003 Reactor Coolant Pump x

implications of the following concepts 2.8 as they apply to the RCPS: Effects of RCP coastdown on RCS parameters K6.14 - Knowledge of the effect of a 003 Reactor Coolant Pump x

loss or malfunction on the following will 2.6 have on the RCPS: Starting requirements K4.10 - Knowledge of CVCS design 004 Chemical and Volume feature(s) and/or interlock(s) which Control x

provide for the following: Minimum 3.2 temperature requirements on borated systems (prevent crystallization)

A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based 005 Residual Heat Removal x

on those predictions, use procedures to 2.9 correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction A4.04 - Ability to manually operate 005 Residual Heat Removal x

and/or monitor in the control room:

3.1 Controls and indication for closed cooling water pumps K 1.13 - Knowledge of the physical 006 Emergency Core Cooling x

connections and/or cause-effect 3.3 relationships between the ECCS and the following svstems: CSS K5.02 - Knowledge of the operational 007 Pressurizer Relief/Quench x

implications of the following concepts 3.1 Tank as they apply to PRTS: Method of formina a steam bubble in the PZR K1.04 - Knowledge of the physical connections and/or cause-effect 008 Component Cooling Water x

relationships between the CCWS and 3.3 the following systems: RCS, in order to determine source(s) of RCS leakage into the CCWS A4.10 - Ability to manually operate 008 Component Cooling Water x

and/or monitor in the control room:

3.1 Conditions that require the operation of two CCW coolers 010 Pressurizer Pressure K3.02 - Knowledge of the effect that a Control x

loss or malfunction of the PZR PCS will 4.0 have on the following: RPS K6.11 - Knowledge of the effect of a 012 Reactor Protection x

loss or malfunction of the 2.9 following will have on the RPS: Trip setpoint calculators 013 Engineered Safety Features K2.01 - Knowledge of bus power Actuation x

supplies to the following:

3.6 ESFAS/safeauards equipment control A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based 022 Containment Cooling x

on those predictions, use procedures to 2.5 correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor over-current A4.05 - Ability to manually operate 022 Containment Cooling x

and/or monitor in the control room:

3.8 Containment readings of temperature, pressure, and humidity system ES-401, Page 24 of 33

ES-401 4

Form ES-401-2 K4.06 - Knowledge of CSS design 026 Containment Spray x

feature(s) and/or interlock(s) which 2.8 provide for the following: Iodine scavenqinq via the CSS K4.07 - Knowledge of MRSS design 039 Main and Reheat Steam x

feature(s) and/or interlock(s) which 3.4 provide for the following: Reactor buildinq isolation A3.02 - Ability to monitor automatic 039 Main and Reheat Steam x

operation of the MRSS, including:

3.1 Isolation of the MRSS 2.2.44 - Ability to interpret control room indications to verify the status and 059 Main Feedwater x

operation of a system, and understand 4.2 how operator actions and directives affect plant and system conditions.

K5.01 - Knowledge of the operational 061 Auxiliary/Emergency implications of the following concepts x

as the apply to the AFW: Relationship 3.6 Feedwater between AFW flow and RCS heat transfer A2.08 - Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b} based 061 Auxiliary/Emergency on those predictions, use procedures to x

correct, control, or mitigate the 2.7 Feedwater consequences of those malfunctions or operations: Flow rates expected from various combinations of AFW pump discharoe valves K1.02 - Knowledge of the physical connections and/or causeeffect 062 AC Electrical Distribution x

relationships between the ac 4.1 distribution system and the following systems: ED/G K3.01 - Knowledge of the effect that a 062 AC Electrical Distribution x

loss or malfunction of the ac distribution 3.5 system will have on the following:

Major svstem loads A 1.01 - Ability to predict and/or monitor changes in parameters associated with 063 DC Electrical Distribution x

operating the DC electrical system 2.5 controls including: Battery capacity as it is affected by discharqe rate A 1.01 - Ability to predict and/or monitor changes in parameters (to prevent 064 Emergency Diesel x

exceeding design limits) associated 3.0 Generator with operating the ED/G system controls including: ED/G lube oil temperature and pressure K3.01 - Knowledge of the effect that a 073 Process Radiation x

loss or malfunction of the PRM system 3.6 Monitoring will have on the following: Radioactive effluent releases K2.08 - Knowledge of bus power 076 Service Water x

supplies to the following: ESF-actuated 3.1 MO Vs A3.01 - Ability to monitor automatic 078 Instrument Air x

operation of the IAS, including: Air 3.1 pressure 2.2.37 - Ability to detenmine operability 103 Containment x

and/or availability of safety related 3.6 equipment.

ES-401, Page 24 of 33

ES-401 4

Form ES-401-2 A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 010 Pressurizer Pressure x

based on those predictions, use 4.2 Control procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures A2.01 - Ability to (a) predict the impacts of the following malfunctions or 013 Engineered Safety Features operations on the ESFAS; and (b) x based Ability on those predictions, use 4.8 Actuation procedures to correct, control, or mitigate the consequences of those malfunctions or operations: LOCA 2.4.20 - Knowledge of the operational 063 DC Electrical Distribution x

implications of EOP warnings, cautions, 4.3 and notes.

A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and 073 Process Radiation x

(b) based on those predictions, use 2.9 Monitoring procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Calibration drift 076 Service Water x

2.4.1 - Knowledge of EOP entry 4.8 conditions and immediate action steps.

3 2

K/A Category Point Totals:

3 2

3 3

3 2

2 I

2 3

I Group Point Total:

28/5 3

2 ES-401, Page 24 of 33

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO I SRO)

System #I Name K

K K

K A

A A

A G

KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 K3.01 - Knowledge of the effect that a 001 Control Rod Drive x

loss or malfunction of the CRDS will 2.9 have on the followina: eves 011 Pressurizer Level Control x

K2.02 - Knowledge of bus power 3.1 supplies to the following: PZR heaters A4.04 - Ability to manually operate 029 Containment Purge x

and/or monitor in the control room:

3.5 Containment evacuation sianal K6.02 - Knowledge of the effect of a loss or malfunction on the following 034 Fuel Handling Equipment x

will have on the Fuel Handling

2.6 System

Radiation monitoring svstems K5.01 - Knowledge of operational implications of the following concepts 035 Steam Generator x

as the apply to the S/GS: Effect of 3.4 secondary parameters, pressure, and temoerature on reactivitv A 1.02 - Ability to predict and/or 041 Steam Dump/Turbine Bypass monitor changes in parameters (to x

prevent exceeding design limits) 3.1 Control associated with operating the SDS controls includina: Steam pressure K4.01 - Knowledge of design feature(s) and/or interlock(s) which 068 Liquid Radwaste x

provide for the following: Safety and 3.4 environmental precautions for handling hot, acidic, and radioactive liquids A3.03 - Ability to monitor automatic operation of the Waste Gas Disposal 071 Waste Gas Disposal x

System including: Radiation 3.6 monitoring system alarm and actuating sianals K1.01 - Knowledge of the physical connections and/or causeeffect 075 Circulating Water x

relationships between the circulating 2.5 water system and the following svstems: SWS A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection 086 Fire Protection x

System; and (b) based on those 3.0 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Low FPS header oressure A2.15 - Ability to (a) predict the impacts of the following malfunction or operations on the CRDS-and (b) 001 Control Rod Drive x

based on those predictions, use 4.2 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Quadrant power tilt ES-401, Page 25 of 33

ES-401 5

Form ES-401-2 A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) 016 Non-nuclear Instrumentation x

based on those predictions, use 3.1 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure 2.4.45 - Ability to prioritize and 035 Steam Generator x

interpret the significance of each 4.3 annunciator or alarm.

0 KIA Category Point Totals:

1 1

1 y,

1 1

I Group Point Total:

10/3 1

ES-401, Page 25 of 33

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

Form ES-401-3 Facility: Three Mile Island Date of Exam: 09/28/2015 Category KIA#

Topic RO SRO-Only IR IR 2.1.19 Ability to use plant computers to evaluate system or 3

component status.

2.1.25 Ability to interpret reference materials, such as 3

qraphs, curves, tables, etc.

Ability to use procedures related to shift staffing,

1.

2.1.5 such as minimum crew complement, overtime 3

Conduct limitations, etc.

of Operations 2.1.35 Knowledge of the fuel-handling responsibilities of 3

SROs.

2.1.

Subtotal 2

2 2.2.13 Knowledge of tagging and clearance procedures.

4 2.2.38 Knowledge of conditions and limitations in the 3

facility license.

2.2.42 Ability to recognize system parameters that are 3

entry-level conditions for Technical Specifications.

2.

Knowledge of pre-and post-maintenance Equipment 2.2.21 operability requirements.

4 Control Knowledge of the bases in Technical Specifications 2.2.25 for limiting conditions for operations and safety 4

limits.

2.2.

3 2

Subtotal Knowledge of radiological safety procedures pertaining to licensed operator duties, such as 2.3.13 response to radiation monitor alarms, containment 3

entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Knowledge of radiation monitoring systems, such as

3.

2.3.15 fixed radiation monitors and alarms, portable survey 2

Radiation instruments, personnel monitorinq equipment, etc.

Control 2.3.6 Ability to approve release permits.

3 2.3.

2.3.

Subtotal 2

1

4.

Ability to recognize abnormal indications for system Emergency 2.4.4 operating parameters that are entry-level conditions 4

Procedures I for emergency and abnormal operatinq procedures.

ES-401, Page 26 of 33

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

Form ES-401-3 Plan Knowledge of the organization of the operating 2.4.5 procedures network for normal, abnormal, and 3

emergency evolutions.

Ability to diagnose and recognize trends in an 2.4.47 accurate and timely manner utilizing the appropriate 4

control room reference material.

2.4.18 Knowledge of the specific bases for EOPs.

4 2.4.25 Knowledge of fire protection procedures.

3 2.4.

Subtotal 3

2 Tier 3 Point Total 10 7

ES-401, Page 26 of 33

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA 1 I 1 054 I AA1.03 The subject KIA is not relevant at the subject facility.

Replaced with 054 I AA1.01 2 I 1 008 I A4.11 The subject KIA is not relevant at the subject facility.

Replaced with 008 I A4.10 2 I 1 059 I K3.03 Topic overlaps with the Audit Written Exam.

Replaced with 062 I K3.01 2/1 103 I A1.01 Topic overlaps with the Audit Written Exam.

Replaced with 003 I K5.02 2 I 1 078 I 2.2.44 Generic KIA oversampled. 078 I 2.2.44 overlaps with 059 I 2.2.44.

Replaced with 022 I A4.05 2 I 1 013 I 2.1.27 Original KIA is LOO 1.

Replaced with 103 I 2.2.37 212 014 I 2.1.27 Original KIA is LOO 1.

Replaced with 086 I A2.02 212 015 I K1.04 The subject KIA is not relevant at the subject facility.

Replaced with 075 I K1.01 3 I 1 2.1.30 The subject KIA is not generic enough for Tier level at the subject facility.

Replaced with 2.1.25 3/3 2.3.11 Topic overlaps with the Audit Written Exam.

Replaced with 2.3.13 1 I 1 009 I 2.4.45 Generic KIA oversampled. 009 I 2.4.45 overlaps with 035 I 2.4.45.

SRO Replaced with 009 I 2.4.41 1 I 1 E05 I 2.2.36 The subject KIA is not relevant to the topic at the subject facility.

SRO Replaced with 057 I 2.4.30 1 I 2 051 I 2.4.1 Original KIA is RO LOK.

SRO Replaced with E08 I 2.4.18 1 I 2 060 I 2.4.47 Topic oversampled. 060 I 2.4.47 overlaps with RO Generic KIA 2.4.47.

SRO Replaced with 024 I 2.4.6 2 I 1 006 I A2.04 Original KIA is RO LOK.

SRO Replaced with 010 I A2.03 212 075 I A2.03 Topic overlaps with the Audit Written Exam I NRG Operational.

SRO Replaced with 001 I A2.15 3/2 2.2.1 Original KIA is RO LOK.

SRO Replaced with 2.2.21 3/3 2.3.15 Topic oversampled. 2.3.15 overlaps with RO Generic KIA 2.3.15.

SRO Replaced with 2.3.6 ES-401, Page 44 of 50

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Three Mile Island Date of Examination: 09/28/2015 Examination Level: RO [8J SRO D Operating Test Number: 2015-301 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Verify Watchstanding Requirements -Work-Hour Rules Conduct of Operations M/R 2.1.5 (2.9): Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime limitations, etc.

Given a Dropped Rod at Power, Calculate SOM Conduct of Operations M/R 2.1.25 (3.9): Ability to interpret station reference materials such as graphs, curves, tables, etc.

Given Intermediate Closed Cooling Water System Electrical and Mechanical Print Drawings, Identify the Equipmen! Control N/R Status of Associated Containment Isolation Valves 2.2.41 (3.5): Ability to obtain and interpret station electrical and mechanical drawings.

Radiation Control Category Not Selected for RO Applicants.

Perform State and Local Event Notification Emergency Plan M/S 2.4.43 (3.2): Knowledge of Emergency Communications Systems and Techniques.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~ 3 for ROs; ~ 4 for SROs & RO retakes)

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

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

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Three Mile Island Date of Examination: 09/28/2015 Examination Level: ROD SRO 1:8:1 Operating Test Number: 2015-301 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Maintain Minimum Shift Staffing - Control Overtime Conduct of Operations M/R 2.1.5 (3.9): Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime limitations, eto.

Given a Dropped Rod at Power, Review Submitted SDM Conduct of Operations M/R for Approval 2.1.25 ( 4.2): Ability to interpret station reference materials such as graphs, curves, tables, etc.

Given Intermediate Closed Cooling Water System Electrical and Mechanical Print Drawings, Identify the Status of Associated Containment Isolation Valves with Equipment Control N/R Tech Spec LCO 2.2.41 (3.9): Ability to obtain and interpret station electrical and mechanical drawings.

Review RB Entry Survey Log 2.3.13 (3.8): Knowledge of radiological safety procedures Radiation Control M/R pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aliqninq filters, etc.

Determine the Emergency Action Level (EAL) and Make a Protective Action Recommendation (PAR) IAW the Facility Emergency Plan M/S Emergency Plan 2.4.44 (4.4): 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 (which would require all five items).

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (.::: 1)

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

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Three Mile Island Date of Examination: 09/28/2015 Exam Level: RO ~ SRO-I D SRO-U D Operating Test No.: 2015-301 Control Room Systems: *8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Respond to an Inoperable/Stuck Control Rod (005) AA 1.01 M/S 1

b. Respond to a Loss of Pressurizer Level Control with Failures (011)

D/A/S 2

A2.03

c. Restore Seal Injection with a Loss of ICCW (003) K6.02 P/S/A 4P

d. Respond to an OTSG Overfeed (035) A2.04 N/A/S 4S

e. Initiate RB Spray (026) A2.03 D/L/S/A/EN 5

f. Lower CFT Level and Pressure from the Control Room (006) A4.02 N/S 3

g. Startup Reactor Protection System Channel (012) A4.02 D/S 7

h. Respond to Loss of SCCW (026) AA 1.05 D/A/S 8

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

i. Initiate Emergency Boration IAW EOP-020 (004) G2.1.30 D/E/L/R 1

j. Respond to a Loss of Instrument Air (078) A3.01 D/E 8

k. EFW from Fire Service using FS-P-15 (061) A2.04 D/E/L 4S All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank s9/ s8 I s 4 (E)mergency or abnormal in-plant 2: 1 I

> 1 I 2: 1 (EN)gineered safety feature 2: 1 I 2: 1 I 2: 1 (control room system)

(L)ow-Power I Shutdown 2: 1 I 2: 1 I 2: 1 (N)ew or (M)odified from bank including 1 (A) 2: 2 I >2 I > 1 (P)revious 2 exams s 3/ s3 I s 2 (randomly selected)

(R)CA 2: 1 I 2: 1 I 2: 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Three Mile Island Date of Examination: 09/28/2015 Exam Level: ROD SRO-I~ SRO-U D Operating Test No.: 2015-301 Control Room Systems: *8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Respond to an Inoperable/Stuck Control Rod (005) AA1.01 M/S 1

b. Respond to a Loss of Pressurizer Level Control with Failures (011)

D/A/S 2

A2.03

c. Restore Seal Injection with a Loss of ICCW (003) K6.02 P/S/A 4P

d. Respond to an OTSG Overfeed (035) A2.04 N/A/S 4S

e. Initiate RB Spray (026) A2.03 D/L/S/A/EN 5

f. Lower CFT Level and Pressure from the Control Room (006) A4.02 N/S 3

g.

h. Respond to Loss of SCCW (026) AA 1.05 D/A/S 8

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

i. Initiate Emergency Boration IAW EOP-020 (004) G2.1.30 D/E/L/R 1

j. Respond to a Loss of Instrument Air (078) A3.01 D/E 8

k. EFW from Fire Service using FS-P-15 (061) A2.04 D/E/L 4S All RO and SRO-I control room (and in-plant) systems must be different and seNe different safety functions; all five SRO-U systems must seNe different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank s9/ s8 I <4 (E)mergency or abnormal in-plant

?. 1 I

?. 1 I ?. 1 (EN)gineered safety feature

?. 1 I

?. 1 I ?. 1 (control room system)

(L)ow-Power I Shutdown

?. 1 I

~1 I ?. 1 (N)ew or (M)odified from bank including 1 (A)

?. 2 I

?. 2 I ?. 1 (P)revious 2 exams s3 I s3 I s 2 (randomly selected)

(R)CA

?. 1 I

> 1 I ?. 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Three Mile Island Date of Examination: 09/28/2015 Exam Level: RO D SRO-I D SRO-U IZI Operating Test No.: 2015-301 Control Room Systems: *8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a.

b.

c.

d. Respond to an OTSG Overfeed (035) A2.04 N/A/S 4S

e. Initiate RB Spray (026} A2.03 D/US/A/EN 5

f. Lower CFT Level and Pressure from the Control Room (006) A4.02 N/S 3

g.

h.

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

i. Initiate Emergency Boration IAW EOP-020 (004) G2.1.30 D/E/UR 1

j. Respond to a Loss of Instrument Air (078) A3.01 D/E 8

k.

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions mav overlap those tested in the control room.

Type Codes Criteria for RO I SRO-I I SRO-U (A}lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank s_9/ s8 I s 4 (E)mergency or abnormal in-plant 2: 1 I 2: 1 I 2: 1 (EN)gineered safety feature 2: 1 I 2: 1 I 2: 1 (control room system)

(L}ow-Power I Shutdown 2: 1 I 2: 1 I 2: 1 (N)ew or (M)odified from bank including 1 (A) 2:2 I 2:_2 I 2: 1 (P)revious 2 exams s 3/

s_3 I s 2 (randomly selected)

(R)CA 2: 1 I 2: 1 I 2: 1 (S)imulator ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-1 Facility:

Three Mile Island Scenario No.:

1 Op Test No.:

2015-301 Examiners:

Operators:

Initial Conditions:

(Temporary IC-175) 85% Power, MOL, reduced from 100% 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago, due to PJM instructions.

BS-P-1A is OOS for maintenance, expected to return to service in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Crane work is occurring on the West side of the Plant to stage new piping Turnover:

Maintain 85% Power Operations Critical Tasks:

Shutdown Reactor -ATWS (CT-24)

Restore Feed to a Dry OTSG (CT-26)

Event No.

Malt. No.

Event Type*

Event Description 1

RM0323 TSCRS Reactor Building Hi Range Radiation Monitor, RM-G-23, Failure 2

ZAIRC1LIC CCRS MU-V-17 Fails Closed in Auto, entry into OP-TM-211-472 CURO (URO: Controls Pressurizer Level with MU-V-17 in Manual) 3 ED09D TSCRS Loss of D Inverter, Loss ofVBD, entry into OP-TM-AOP-018 CARO (ARO: Place Rad Monitors Interlock switches to Defeat, Restore Control Building Ventilation) 4 02A5S81 CCRS Low Makeup Tank Pressure, entry into OP-TM-MAP-D0303 CARO (ARO: Raise Makeup Tank pressure) 5 IC23 ICRS SG/RX Demand Station fails to 0 Volts, Entry into OP-TM-AOP-070 IURO IARO (URO/ARO: ICS station to Manual, Stabilize Power) 6 MU29 CCRS RCS leak through the Letdown Line, entry into OP-TM-AOP-050 RURO CARO (URO: Lowers power in Manual ARO: Isolate the Letdown Line) 7 FW15B MCRS "B" Main Feed Pump trips, "A" Main Feed Pump Runs to 0 rpm, RD28 MURO ATWS, Lack of Primary to Secondary Heat Transfer.

RD32 MARO 8

FW19 CCRS EFW Control Valves fail to operate, EF-V-52A-D Closed CARO (ARO: Establish PSHT via Condensate Booster Pump flow) 9 (if MU358 CCRS MU-P-1A/C will not start, MU-P-18 trips.

required)

CURO (URO: Establish PORV control for Heat Transfer)

. (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility:

Three Mile Island Scenario No.:

2 Op Test No.:

2015-301 Examiners:

Operators:

Initial Conditions:

(Temporary IC-176) 100% Power, MOL BS-P-1A is OOS for maintenance, expected to return to service in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Crane work is occurring on the West side of the Plant to stage new piping Turnover:

Maintain 100% Power Operations Critical Tasks:

Electrical Power Alignment (CT-8)

Turbine Trip (CT-18)

Protect against RCP Seal LOCA (CT-*)

Event No.

Malt. No.

Event Type*

Event Description 1

Nl27A ICRS Pressurizer Pressure Instrument Fails High, entry into OP-TM-IURO MAP-G0106, OP-TM-MAP-G0107 IARO (URO: Blocks PORV, closes Spray Valve, Pressurizer Heater Control in Manual, ARO: "A" RPS to Manual Bypass) 2 IC12 CCRS Total RCS Flow IN Fails to Zero Volts, entry into OP-TM-AOP-070 CURO and 1102-4.

CARO (URO/ARO: ICS station to Manual, Stabilize Power) 3 03A3S09 TSCRS Loss of 1E 4KV Bus, Entry into OP-TM-AOP-014 CURO ZDl1SAE (URO: Manual control of Makeup valves) 2(1) 4 TU01D NCRS High Vibrations on Main Turbine, entry into OP-TM-MAP-K0201 RURO and 1102-4 NARO (URO/ARO: Power reduction with ICS in Manual) 5 EG04A I CRS Loss of Stator Coolant Pumps, Main Turbine fails to automatically EG04B I URO trip (URO: Trip Reactor) 6 HVB-1-1 TSCRS Fire in EG-Y-1 B Room, entry into OP-TM-AOP-001 HVB-2-1 CARO A-1-4 (ARO: Secure EG-Y-18) 7 ED01 MCRS Loss of Offsite Power, entry into OP-TM-AOP-020.

MURO MARO 8

EG01A CCRS "A" EDG fails to start, SBO start required. (URO)

CURO (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility:

Three Mile Island Scenario No.:

3 Op Test No.:

2015-301 Examiners:

Operators:

Initial Conditions:

(Temporary IC-177) 85% Power, MOL, reduced from 100% 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago, due to PJM instructions.

BS-P-1 A is OOS for maintenance, expected to return to service in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Crane work is occurring on the West side of the Plant to stage new piping Turnover:

Maintain 85% Reactor Power Critical Tasks:

Control HPI (CT-5)

Establish FW Flow and Feed SG(s) (CT-10)

Natural Circulation RCS Flow (CT-12)

Event No.

Malt. No.

Event Type*

Event Description 1

DHR32 TSCRS BWST level lowers, entry into OP-TM-MAP-E0304 2

03A4S01 TSCRS Inadvertent ES Actuation, "B" Train (TS), entry into OP-TM-AOP-IURO 046 ZDIPB1R (URO: Defeats signal, ARO: Opens MU-V-2A/B)

CBON IARO 3

RCOSB ICRS Tc Instrument Fails High, SASS Fails to Actuate, entry into OP-TM-IC51 IURO AOP-070 IARO (URO: Manual control of Control Rods, ARO: Manual control of Feedwater) 4 MU19A N CRS RC-P-1A #1 Seal Leak, leak at 6.5 gpm, Entry into OP-TM-AOP-RURO 040 NARO (URO/ARO: Power reduction in manual) 5 MU19A CCRS RC-P-1A #'1 Seal Failure, leak at 10 gpm, Entry into OP-TM-AOP-CURO 040 CARO (URO: Secure RC-P-1A, ARO: Reratio MFW) 6 MS19A C CRS lsolable Steam Leak in Turbine Bldg, entry into OP-TM-AOP-051.

CARO (ARO: Isolate Steam Leak) 7 TH06 MCRS RCS LOCA, entry into OP-TM-AOP-050, OP-TM-EOP-001.

MURO MARO 8

CC06A CCRS NSCCW Rupture in RC-P-1A Motor Air Cooler, Loss of NSCCW, CURO entry into OP-TM-AOP-031 (URO: Trip RCP's) 9 ICR02 CCRS HSPS fails to feed OTSG's to 50%

ICR04 CARO (ARO: Feed OTSG's to >50% in manual)

(N)ormal, (R)eactivity,

( l)nstrument, (C)omponent, (M)ajor JPM A pl Edited Task Standard pS Edited "Delta" symbol on Performance Step 4 p 10 Added clarification to the Standard under Performance Step 18 pl2 Removed page number from Cue Sheet JPM B pl Edited Task Standard pl Removed bullet in Initial Conditions about increased Letdown flowrates p3 Changed Event 2 items to Event 1 to reflect how the JPM was validated (Steps 2 and 3) p3 Edited MAP malfunction under Step 1 plO Removed bullet in Initial Conditions about increased Letdown flowrates plO Removed page number from Cue Sheet JPM C pl Edited second bullet of the Initial Conditions for clarity p3 Added malfunction to Exam Setup (Step 1.C) p6 Removed unnecessary capitalization in Standard under Performance Step 7 p7 Added Examiner Note directly following Performance Step 11 p7 Enhanced Booth Cue directly following Performance Step 12 p7 Removed unnecessary capitalization in Standard under Performance Steps 11 and 12 p13 Edited second bullet of the Initial Conditions for clarity p13 Removed page number from Cue Sheet JPM D pl Edited Task Standard p9 Removed Performance Step 12 pll Removed page number from Cue Sheet Removed pag JPM E p3 Changed "Trainer" to "Simulator" pll Removed page number from Cue Sheet JPM F p2 Edited Task Standard p2 Changed Time Critical from "Yes" to "No" p3 Changed a Simulator Override to a Remote Function (fourth bullet from the bottom) p4 Edited Coding nomenclature for bullets #2 and 3 pl6 Changed Time Critical from "Yes" to "No" pl6 Removed page number from Cue Sheet JPM G pl Enhanced fifth and last bullets under Initial Conditions p2 Edited third bullet under Required Materials p9 Enhanced Evaluator Note just prior to Performance Step 16