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TMI - Retake - Final Outlines (Folder 3)
	ML101270306
Person / Time
Site:	Crane
Issue date:	02/26/2009
From:	; Exxon Nuclear Co
To:	D'Antonio J; Operations Branch I
	Hansell S
Shared Package
ML092470034	List: ML100960287; ML101270294; ML101270306; ML101270314; ML101540234; ML102320233; TMI-10-002, Retake - Draft - Outlines (Facility Letter Dated 1/8/10) Folder 2);
References
	U01820
	Download: ML101270306 (12)
	v • d • e

ES-401 Written Examination Outline Form ES-401-2 Facility: TMI Date of Exam:

4/12/2010 Points Tier Group K

K K

G G*

2 3

1.

1 3

3 3

3 18 Emergency 2

2 2

9 Plant Evaluations Tier 4

5 4

5 27 Totals 3

3 3

28

2.

2 10 Plant Systems 4

2 4

38 2

3 4

i 3. Generic Knowledge & Abilities 10 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 (Le., 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 that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate KIA statements.

4.

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

5.

Absent a plant specific priority, only those KAs having an importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the FlO 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) KlAs 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 KIA's

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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, I Rs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to Total 3

8 7

ES-401 2

Form ES-401-2 TMI Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

[= EAPE#/Name Safety Function KIA Topic(s)

AK1.03 - Knowledge of the operational implications of the following concepts as they apply to 015 / 17 / Reactor Coolant Pump the Reactor Coolant Pump 3.0 39 Malfunctions / 4 Malfunctions (Loss of RC Flow):

The basis for operating at a reduced power level when one RCP is out of service EK1.04 Knowledge of the operational implications of the following concepts as they apply to 007/ Reactor Trip /1 3.6 40 the reactor trip: Decrease in reactor power following reactor trip (prompt and AK1.03 - Knowledge of the operational implications of the 022 / Loss of Reactor Coolant following concepts as they apply to 3.0 41 Makeup / 2 Loss of Reactor Coolant Pump Makeup: Relationship between flow and PZR level EK2.03 - Knowledge of the interrelations between the small 009 / Small Break LOCA 13 i 3.0 42 break LOCA and the following:

EK2.1 - Knowledge of the interrelations between the (Excessive Heat Transfer) and the following: Components, and EOS I Steam Line Rupture functions of control and safety 3.8 43 Excessive Heat Transfer 14 systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

AK2.01 - Knowledge of the 008/ Pressurizer Vapor Space interrelations between the 2.7 44 Accident/3 Pressurizer Vapor Space Accident and the

Valves AK3.05 Knowledge of the reasons for the following responses as they 054/ Loss of Main Feedwater / 4 apply to the Loss of Main 4.6 45 Feedwater (MFW): HPI/PORV 056/ Loss of Off-site Power / 6 4.4 46 011 / Large Break LOCA / 3 3.9 47 038/ Steam Generator Tube 3.6 48 Rupture / 3 2

ES-401 2

Form ES-401-2 TMI Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AA 1.02 - Ability to operate and / or monitor the following as they apply 065/ Loss of Instrument Air /8 to the Loss of Instrument Air:

2.6 49 Components served by instrument 027 / Pressurizer Pressure Control 3.1 System Malfunction / 3 029 / Anticipated Transient Without 4.4 Scram (A TWS) /1 AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Residual Heat 025 / Loss of Residual Heat Removal System: Leakage of 3.4 52 Removal System / 4 reactor coolant from RHR into closed cooling water system or into reactor buildi EA2.01 - Ability to determine or interpret the following as they apply 055 / Station Blackout /6 to a Station Blackout: Existing 3.4 53 valve positioning on a loss of 2.4.45 - Emergency Procedures /

057 / Loss of Vital AC Electrical Plan: Ability to prioritize and 4.1 54 Instrument Bus /6 interpret the significance of each annunciator or 2.1.19 - Conduct of Operations:

E04/lnadequate Heat Transfer-Ability to use plant computers to 3.9 55 Loss of Secondary Heat Sink /4 evaluate system or component status.

2.1.31 - Conduct of Operations:

Ability to locate control room 026 / Loss of Component Cooling switches, controls, and indications, 4.6 56 Water / 8 and to determine that they correctly KIA CategoryTotals 3

3 3

3

ES-401 3

Form ES-401-2 TMI Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 AK1.01 Knowledge of the operational implications of the 024 / Emergency Soration /1 X

following concepts as they apply to Emergency Soration: Relationship between boron addition and in T-ave AK2.2 Knowledge of the interrelations between the (Loss of NNI-Y) and the following: Facility's heat removal systems, including iA03 / Loss NNI-X/Y /7 X

primary coolant, emergency 3.3 58 coolant, the decay heat removal systems, and relations between the proper operation of these systems to faci EK3.4 - Knowledge of the reasons for the following responses as they apply to the (EOP Enclosures)

RO or SRO function within the E14/ EOP Rules and Enclosures /5 X

control room team as appropriate to the assigned position, in such a 3.5 59 way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

AA1.04 - Ability to operate and / or i005 /lnoperable/Stuck Control Rod /

1 monitor the following as they apply to the Inoperable / Stuck Control 3.9 60 Rod: Reactor and turbine EA2.1 - Ability to determine and interpret the following as they apply E08 / LOCA Cooldown - Depress. I i4 to the (LOCA Cooldown) Facility conditions and selection of appropriate procedures during 2.8 61 abnormal and emergency rations.

2.1.31 - Conduct Operations:

076 / High Reactor Coolant Activity /

9 Ability to locate control room switches, controls, and indications, 4.6 and to determine that they correctly.

62 2.1.28 Conduct of Operations:

A07 I Flooding / 8 Knowledge of the purpose and function of major system 4.1 63 and controls.

AK2.03 - Knowledge ofthe 028/ Pressurizer Level Control Malfunction / 2 X

interrelations between the Pressurizer Level Control Malfunctions and the following:

2.6 64 Controllers and positioners 4

ES-401 3

Form ES-401-2 TMI Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 060 I Accidental Gaseous RadWaste Release / 9 KIA Category Totals 2

AA2.01 - Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste: A radiation-level alarm, as to whether the cause was due to a gradual (in time) signal increase 3.1 or due to a sudden increase (a "spike"), including the use of strip-chart recorders, meter and alarm Group Point Total:

65 9

5

ES-401 4

Form ES-401-2 TMI Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s) 006 Emergency Core Cooling 026 Containment Spray 062 AC Electrical Distribution X

X X

K1.10 - Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems: Safety tank K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: Cooling water K2.01 - Knowledge of bus power supplies to the 005 Residual Heat Removal X

022 Containment Coolill9 X

K3.01 - Knowledge of the effect that a loss or malfunction of the CCS will have on the following:

Containment equipment subject to damage by high or low temperature, humidity, and 078 Instrument Air 063 DC Electrical Distribution 003 Reactor Coolant Pump X

X X

K4.02 - Knowledge of lAS design feature(s) and/or interlock(s) which provide for the following: Cross-over to other air K4.01 - Knowledge of dc electrical system design feature(s) and/or interlock(s) which provide for the following:

Manual/automatic transfers of control K4.07 - Knowledge of RCPS design feature(s) and/or interlock(s) which provide for the following: Minimizing RCS 004 Chemical and Volume Control 007 Pressurizer Relief/Quench Tank 4.1 3.0 2.9 3.2 2.7 3.2 2.6 3.1 2

3 4

5 6

7 8

9 10 6

ES-401 4

Form ES-401-2 TMI Written Examination Outline Plant Systems - Tier 2 Group 1 KIA Topic(s)

K6.03 - Knowledge of the effect of a loss or malfunction 0'\\ 0 Pressurizer Pressure x

of the following will have on Control the PZR PCS: PZR sprays and heaters K6.02 Knowledge of the 061 Auxiliary/Emergency effect of a loss or malfunction x

Feedwater of the following will have on theAFW A1.01 - Ability to predict and/or monitor changes in parameters (to prevent 073 Process Radiation exceeding design limits)

Monitoring associated with operating the PRM system controls

Radiation levels A 1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 076 Service Water associated with operating the SWS controls including:

Reactor and turbine building closed cooling water A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use 059 Main Feedwater procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in MFW suction or A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based 013 Engineered Safety Ability on those predictions, Features Actuation use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; 064 Emergency Diesel Generator 012 Reactor Protection 7

3.2 2.6 3.2 13 2.6 14 3.1 15 4.4 16 3.7 17 3.6 18

ES-401 4

Form ES-401-2 TMI Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name 008 Component Cooling Water 103 Containment 039 Main and Reheat Steam 012 Reactor Protection 064 Emergency Diesel Generator 005 Residual Heat Removal X

003 Reactor Coolant Pump 013 Engineered Safety Features Actuation X

004 Chemical and Volume Control 061 Auxiliary/Emergency Feedwater KJA Category Totals 3

3 KJA Topic(s)

A4.04 - Ability to manually operate and/or monitor in the control room: Startup of a CCW pump when the system is shut down.

A4.06 - Ability to manually operate and/or monitor in the control room: Operation of the containment personnel airlock door 2.4.4 - Emergency Procedures I Plan: Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating A3.04 - Ability to monitor automatic operation of the RCS flow K2.01 - Knowledge of bus power supplies to the following: ESFAS/safeguards control K6.05 - Knowledge ofthe effect of a loss or malfunction X

on the following CVCS components: Sensors and detectors K5.02 - Knowledge of the operational implications of the following concepts as the apply to the AFW: Decay heat and 2.7 4.5 3.7 22 3.9 23 2.9 24 2.5 27 3.2 28 8

ES-401 5

Form ES-401-2 TMI Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KJA Topic(s)

Imp. I Q# I K2.01 - Knowledge of bus power supplies to the 015 Nuclear Instrumentation x

following: NIS channels, 3.3 29 components, and interconnections K1.06 - Knowledge of the physical connections and/or 045 Main Turbine Generator x

cause-effect relationships between the MT/G system and 2.6 30 the following systems: RCS, K5.04 - Knowledge of the operational implication of the following concepts as they 068 Liquid Radwaste x

apply to the Liquid Radwaste 3.2 31 System: Biological hazards of radiation and the resulting goal of ALAR A A 1.02 - Ability to predict and/or monitor changes in 04i Steam DumpfTurbine Bypass Control x

parameters (to prevent exceeding design limits) associated with operating the 3.1 32 SDS controls including: Steam K3.02 - Knowledge of the 016 Non-Nuclear Instrumentation x

effect that a loss or malfunction of the NNIS will have on the following: PZR 3.4 33 LCS A3.02 - Ability to monitor 001 Control Rod Drive automatic operation of the 3.7 34 CRDS includi Rod hei A4.04 - Ability to manually 029 Containment Purge operate and/or monitor in the control room: Containment 3.5 35 evacuation si nal A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Cooling System; and (b) based on 033 Spent Fuel Cooling those predictions, use procedures to correct, control, 3.1 36 or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level 2.4.50 - Emergency 072 Area Radiation Monitoring Procedures / Plan: Ability to verify system alarm setpoints and operate controls identified 4.2 37 in the alarm manual.

9

ES-401 5

Form ES-401-2 TMI Written Examination Outline Plant Systems - Tier 2 Group 2 C

System #/Name KIA Topic(s)

K6.03 - Knowledge of the effect of a loss or malfunction 035 Steam Generator x

2.6 38 on the following will have on the level detector

't<JA Category Totals o

Group Point Total:

10 10

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

Form ES-401-3 Facility:

ML101270306

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