ML15084A076

2015-03 - Draft Outline Submittal

ML15084A076
Person / Time
Site:	Comanche Peak
Issue date:	03/23/2015
From:	Vincent Gaddy Operations Branch IV
To:	Luminant Generation Co
laura hurley
References
Download: ML15084A076 (12)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Comanche Peak RO Retake Date of Exam:

02/09/2015 Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

Emergency &

Abnormal Plant Evolutions 1

3 3

3 N/A 3

3 N/A 3

18 6

2 1

2 1

2 2

1 9

4 Tier Totals 4

5 4

5 5

4 27 10

2.

Plant Systems 1

3 2

3 2

3 3

2 2

3 2

3 28 5

2 1

1 1

1 1

1 1

1 1

1 10 3

Tier Totals 3

3 4

3 4

4 3

3 4

3 4

38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 2

3 2

Note:

1.

Ensure that at least two topics from every applicable K/A 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 K/A 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 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 K/A 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, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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 / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 X

EK1.03 - Knowledge of the operational implications of the following concepts as they apply to the reactor trip:

Reasons for closing the main turbine governor valve and the main turbine stop valve after a reactor trip (CFR 41.8

/ 41.10 / 45.3).

3.7 1 (1) 000008 Pressurizer Vapor Space Accident / 3 X

AK2.02 - Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following:

Sensors and detectors (CFR 41.7 / 45.7) 2.7 1

000009 Small Break LOCA / 3 000011 Large Break LOCA / 3 X

2.1.27 - Knowledge of system purpose and/or function (CFR: 41.7).

3.9 1

000015/17 RCP Malfunctions / 4 X

AK3.03-Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Sequence of events for manually tripping reactor and RCP as a result of an RCP malfunction (CFR 41.5,41.10 / 45.6 / 45.13) 3.7 1

000022 Loss of Rx Coolant Makeup / 2 X

AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: Consequences of thermal shock to RCP seals (CFR 41.8 / 41.10 / 45.3) 2.8 1

000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water / 8 X

AA1.07 - Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: Flow rates to the components and systems that are serviced by the CCWS; interactions among the components (CFR 41.7 / 45.5 / 45.6) 2.7 1

000027 Pressurizer Pressure Control System Malfunction / 3 X

AK3.03 - Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction, (CFR 41.5,41.10 / 45.6 / 45.13) 3.7 1

000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 X

EA1.18 - Ability to operate and monitor the following as they apply to a SGTR: S/G blowdown valve indicators (CFR 41.7 / 45.5 / 45.6) 4.0 1

000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer / 4 X

W/E12, EK2.2 - Knowledge of the interrelations between the (Uncontrolled Depressurization of all Steam Generators) and the following: Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. (CFR: 41.7 / 45.7) 3.6 1

000054 (CE/E06) Loss of Main Feedwater / 4 X

AA2.08 - Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

Steam flow-feed trend recorder (CFR: 43.5 / 45.13) 2.9 1 (10) 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 X

2.2.38 - Knowledge of conditions and limitations in the facility license. (CFR: 41.7 / 41.10 / 43.1 / 45.13) 3.6 1

000057 Loss of Vital AC Inst. Bus / 6 X

AA2.16 - Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:

Normal and abnormal PZR level for various modes of plant operation (CFR: 43.5 / 45.13) 3.0 1

000058 Loss of DC Power / 6 X

2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR:

41.5 / 43.5 / 45.12 / 45.13) 4.4 1

000062 Loss of Nuclear Svc Water / 4 X

AK3.04 - Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: Effect on the nuclear service water discharge flow header of a loss of CCW (CFR 41.4, 41.8 / 45.7 )

3.5 1

000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 X

EK2.1 - Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features (CFR: 41.7 /

45.7).

3.5 1

W/E11 Loss of Emergency Coolant Recirc. / 4 X

EA1.1 - Ability to operate and / or monitor the following as they apply to the (Loss of Emergency Coolant Recirculation) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR: 41.7 / 45.5 / 45.6) 3.9 1

BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X

EK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (Loss of Secondary Heat Sink): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink) (CFR: 41.8 / 41.10, 45.3).

3.9 1

000077 Generator Voltage and Electric Grid Disturbances / 6 X

AA2.06 - Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Generator frequency limitations (CFR:

41.5 and 43.5 / 45.5, 45.7, and 45.8) 3.4 1 (18)

K/A Category Totals:

3 3

3 3

3 3

Group Point Total:

18/6

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 / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 X

AK2.05 - Knowledge of the interrelations between the Dropped Control Rod and the following: Control rod drive power supplies and logic circuits. (CFR 41.7 / 45.7) 2.5 1 (19) 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 X

AK3.02 - Knowledge of the reasons for the following responses as they apply to Emergency Boration: Actions contained in EOP for emergency boration (CFR 41.5, 41.10 / 45.6 /

45.13) 4.2 1

000028 Pressurizer Level Malfunction / 2 X

AA2.03 - Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Charging subsystem flow indicator and controller (CFR: 43.5 / 45.13) 2.8 1

000032 Loss of Source Range NI / 7 X

AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of Source Range Nuclear Instrumentation: Manual restoration of power (CFR 41.7 / 45.5 / 45.6) 3.1 1

000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 X

AK2.01 - Knowledge of the interrelations between the Accidental Liquid Radwaste Release and the following: Radioactive-liquid monitors (CFR 41.7 / 45.7) 2.7 1

000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 X

E07, EA2.2 - Ability to determine and interpret the following as they apply to the (Saturated Core Cooling): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments. (CFR:

43.5 / 45.13) 3.3 1

000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 X

2.4.6 - Knowledge of EOP mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 3.7 1

W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4

BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X

EA1.3 - Ability to operate and / or monitor the following as they apply to the (LOCA Cooldown and Depressurization): Desired operating results during abnormal and emergency situations.

(CFR: 41.7 / 45.5 / 45.6) 3.7 1

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X

E10, EK1.2 - Knowledge of the operational implications of the following concepts as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Normal, abnormal and emergency operating procedures associated with (Natural Circulation with Steam Void in Vessel with/without RVLIS). (CFR: 41.8

/ 41.10 / 45.3) 3.2 1 (27)

BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals:

1 2

1 2

2 1

Group Point Total:

9/4

ES-401 4

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 003 Reactor Coolant Pump X

K4.04 - Knowledge of RCPs design feature(s) and/or interlock(s) which provide for the following: Adequate cooling of RCP motor and seals (CFR: 41.7) 2.8 1 (28) 004 Chemical and Volume Control X

K5.08 - Knowledge of the operational implications of the following concepts as they apply to the CVCS: Estimation of subcritical multiplication factor (K-eff) by means other than the 6-factor formula:

relationship of count rate changes to reactivity changes (CFR: 41.5/45.7).

2.6 1

005 Residual Heat Removal X

X K5.01 - Knowledge of the operational implications of the following concepts as they apply the RHRS: Nil ductility transition temperature (brittle fracture) (CFR: 41.5 /

45.7).

A1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including: Closed cooling water flow rate and temperature (CFR: 41.5 /

45.5) 2.9 2.5 1

1 006 Emergency Core Cooling X

K1.08 - Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems: CVCS (CFR: 41.2 to 41.9 / 45.7 to 45.8).

3.6 1

007 Pressurizer Relief/Quench Tank X

X K4.01 - Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the following: Quench tank cooling (CFR: 41.7).

A4.09 - Ability to manually operate and/or monitor in the control room: Relationships between PZR level and changing levels of the PRT and bleed holdup tank (CFR: 41.7 /

45.5 to 45.8).

2.6 2.5 1

1 008 Component Cooling Water X

X K3.01 - Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: Loads cooled by CCWS 2.1.32-Ability to explain and apply system limits and precautions.l (CFR: 41.10 / 43.2 /

45.12) 3.4 3.8 1

1 010 Pressurizer Pressure Control X

X K3.01 - Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: RCS (CFR: 41.7 / 45.6).

A4.02 - Ability to manually operate and/or monitor in the control room: PZR heaters (CFR: 41.7 / 45.5 to 45.8) 3.8 3.6 1

1

012 Reactor Protection X

K6.01 - Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Bistables and bistable test equipment (CFR: 41.7 / 45/7).

2.8 1

013 Engineered Safety Features Actuation X

X K6.01 - Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors (CFR:

41.7 / 45.5 to 45.8).

A2.03 - 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: Rapid depressurization (CFR: 41.5 / 43.5 / 45.3 /

45.13).

2.7 4.4 1 (40) 1 022 Containment Cooling X

K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems:

SEC/remote monitoring systems (CFR: 41.2 to 41.9 / 45.7 to 45.8).

3.7 1

025 Ice Condenser Not applicable to plant design.

026 Containment Spray X

A3.01 - Ability to monitor automatic operation of the CSS, including: Pump starts and correct MOV positioning (CFR: 41.7 /

45.5).

4.3 1

039 Main and Reheat Steam X

K5.05 - Knowledge of the operational implications of the following concepts as the apply to the MRSS: Bases for RCS cooldown limits (CFR: 441.5 / 45.7).

2.7 1

059 Main Feedwater X

A3.02 - Ability to monitor automatic operation of the MFW, including:

Programmed levels of the S/G (CFR: 41.7 /

45.5).

2.9 1

061 Auxiliary/Emergency Feedwater X

K6.02 - Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Pumps (CFR: 41.7 /

45.7).

2.6 1

062 AC Electrical Distribution X

K2.01 - Knowledge of bus power supplies to the following: Major system loads (CFR:

41.7).

3.3 1

063 DC Electrical Distribution X

K2.01 - Knowledge of bus power supplies to the following: Major DC loads (CFR: 41.7) 2.9 1

064 Emergency Diesel Generator X

X A2.15 - Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Water buildup in cylinders (CFR: 41.5 / 43.5 / 45.3

/ 45.13).

A3.05 - Ability to monitor automatic operation of the ED/G system, including:

Operation of the governor control of frequency and voltage control in parallel operation (CFR: 41.7 / 45.5).

2.6 2.8 1

1 (50) 073 Process Radiation Monitoring X

2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

(CFR: 41.7 / 41.10 / 43.2 / 45.13) 3.9 1

076 Service Water X

K3.01 - Knowledge of the effect that a loss or malfunction of the SWS will have on the following: Closed cooling water (CFR: 41.7

/ 45.6).

3.4 1

078 Instrument Air X

2.1.14 - Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. l (CFR: 41.10 / 43.5 / 45.12) 3.1 1

103 Containment X

X K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: Containment isolation/containment integrity (CFR: 41.2 to 41.9 / 45.7 to 45.8).

A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including:

Containment pressure, temperature, and humidity (CFR: 41.5 / 45.5).

3.9 3.7 1

1 (55)

K/A Category Point Totals:

3 2

3 2

3 3

2 2

3 2

3 Group Point Total:

28/5

ES-401 5

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 001 Control Rod Drive X

K5.59 - Knowledge of the following operational implications as they apply to the CRDS: Reasons for overlap of control rod banks for withdrawal and insertion (CFR:

41.5/45.7).

2.7 1 (56) 002 Reactor Coolant 011 Pressurizer Level Control X

K2.02 - Knowledge of bus power supplies to the following: PZR heaters (CFR: 41.7).

3.1 1

014 Rod Position Indication X

K3.02 - Knowledge of the effect that a loss or malfunction of the RPIS will have on the following: Plant computer (CFR: 41.7 / 45.6).

2.5 1

015 Nuclear Instrumentation X

2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations (CFR: 41.10 / 43.2 / 45.13).

3.1 1

016 Non-nuclear Instrumentation 017 In-core Temperature Monitor X

A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Core damage (CFR:

41.5 / 43.5 / 45.3 / 45.5).

3.6 1

027 Containment Iodine Removal X

A4.01 - Ability to manually operate and/or monitor in the control room: CIRS controls (CFR: 41.7 / 45.5 to 45.8).

3.3 1

028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling X

K4.04 - Knowledge of design feature(s) and/or interlock(s) which provide for the following:

Maintenance of spent fuel pool radiation (CFR:

41.7).

2.7 1

034 Fuel Handling Equipment 035 Steam Generator X

A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Waste Gas Disposal System operating the controls including: SG Pressure (CFR: 41.5 / 45.5).

3.5 1

041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator X

A3.11 - Ability to monitor automatic operation of the MT/G system, including: Generator trip (CFR: 41/7 / 45.5) 2.6 1

055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal

072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection X

K6.04 - Knowledge of the effect of a loss or malfunction of the following will have on the Fire Protection System: Fire, smoke, and heat detectors (CFR: 41.7 / 45.7).

2.6 1 (65)

K/A Category Point Totals:

1 1

1 1

1 1

1 1

1 1

Group Point Total:

10/3

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

Form ES-401-3 Facility: Comanche Peak RO Retake Exam Date of Exam: TBD/2014 Category K/A #

Topic RO SRO-Only IR IR

1.

Conduct of Operations 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (CFR: 41.10 / 45.12 / 45.13) 3.6 1 (66) 2.1.30 Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7) 4.4 1

2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. (CFR: 41.10 / 45.12) 4.6 1

Subtotal

2.

Equipment Control 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. (CFR: 41.5 / 41.10 / 43.5

/ 43.6 / 45.1) 4.5 1

2.2.40 Ability to apply Technical Specifications for a system. (CFR:

41.10 / 43.2 / 43.5 / 45.3) 3.4 1 (70)

Subtotal

3.

Radiation Control 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11 / 41.12 /

43.4 / 45.9) 2.9 1

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR: 41.12 / 45.10) 3.5 1

2.3.13 Knowledge of radiological safety procedures 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. (CFR: 41.12 / 43.4 / 45.9 / 45.10) 3.4 1

Subtotal

4.

Emergency Procedures /

Plan 2.4.18 Knowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 /

45.13) 3.3 1

2.4.46 Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 1 (75)

Subtotal Tier 3 Point Total 10 7

ES401 RecordofRejectedK/As FormES4014 Tier/Group Randomly SelectedK/A ReasonforRejection 1/1 027 AK3.03 Question 7 Pressurizer Pressure Control Malfunction: Could not write a discriminating question based on the content of the original K/A. Replaced K/A 027 AK3.01 with 027 AK3.03 1/2 003 AK2.05 Question 19 Dropped Control Rod: Could not write a discriminating question using Metroscope. Replaced K/A 003 AK2.03 with 003 AK2.05 1/2 059 AK2.01 Question 23 Accidental Liquid RadWaste Rel: Liquid Waste not monitored by Gas monitors at Comanche Peak. Replaced K/A 059 AK2.02 with 059 AK2.01 1/2 W/E15 G 2.4.6 Question 25 Containment Flooding: Could not write question that specifically mentions safety related equipment to be secured during containment flooding. Replaced K/A W/E15 G 2.2.37 with W/E15 G 2.4.6 2/1 006 K1.08 Question 32 Emergency Core Cooling: Safety injection tank heating system is not used at Comanche Peak. Replaced K/A 006 K1.10 with 006 K1.08 2/1 008 G 2.1.32 Question 36 Component Cooling Water: No safety limits associated with the CCW system at Comanche Peak. Replaced K/A 008 G 2.2.22 with 008 G 2.1.32 2/1 073 G 2.2.39 Question 51 Process Radiation Monitoring: PRM instrumentation is essentially the same between units. Replaced K/A 073 G 2.2.4 with 073 G 2.2.39 2/1 078 G 2.1.14 Question 53 Instrument Air: Could not write a discriminating question on this KA without it being a direct lookup. Replaced K/A 078 G 2.1.20 with 078 G 2.1.14 2/1 103 K1.02 Question 54 Containment: Shield Building Ventilation System not applicable at Comanche Peak. Replaced K/A 103 K1.03 with 103 K1.02 2/2 035 A1.02 Question 63 Waste Gas Disposal: Could not write question on how ventilation system impacted Gas system design parameters.

Replaced Waste Gas Disposal (071) with Steam Generator (035) and replaced K/A 071 A1.06 with 035 A1.02 2/2 045 A3.11 Question 64 Area Radiation Monitoring: Area radiation monitor not linked to automatic ventilation alignment. Replaced Area Radiation Monitoring (072) with Main Turbine Generator (045) and replaced K/A 072 A3.01 with 045 A3.11