ML050890250

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Init Exam - 02/2005 - Final Outlines
ML050890250
Person / Time
Site: Diablo Canyon  
(DPR-080, DPR-082)
Issue date: 01/21/2005
From:
- No Known Affiliation
To:
Office of Nuclear Reactor Regulation
References
50-275/05-301, 50-323/05-301, ES-401, ES-401-2 50-275/05-301, 50-323/05-301
Download: ML050890250 (27)


Text

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ES-401 PWR Examination Outline Form ES-401-2 Facilitv:

DCPP Printed: 01 /21/2005 Date Of Exam:

02/07/2005 I

I RO wA Category Point!

I SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the 'Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.
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 +I 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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline
5. The shaded areas are not applicable to the category /tier.

6.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA 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 columns labeled "Kf and "A".

Use duplicate pages for RO and SRO-only exams.

8. Far Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

ES-401-3.

1

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PWR RO Examination Outline Printed: 01/21/2005 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 Facility:

DCPP ES - 401

' TJAPE # / Name I Safety Function I K1 KA Topic EK2.03 - Reactor trip status panel

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I 000007 Reactor Trip - Stabilization -

I Recovery / 1 I 000008 Pressurizer Vapor Space Accident / I AA2.20 - The effect of an open PORV on code safety, based on observation of plant parameters EK1.O1 - Natural circulation and cooling, including reflux boiling 13 0000 1 1 Large Break LOCA I 3 X

00001 5/000017 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 000026 Loss of Component Cooling Water I AA 1.10 - RCP ammeter and trip alarm 2.7 I

2.1.25 - Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

2.8 1

AA2.04 - The normal values and upper limits for the temperatures of the components cooled by CCW 2.5 1

)000029 ATWS I 1 EA1.O1 - Charging pumps 3.4*

1 3.8 -

4.4 1 -

1 EA2.06 - Shutdown margins and required boron concentrations AA1.02 - Manual startup of electric and steam-driven AFW pumps 000038 Steam Gen. Tube Rupture 13 2.7 -

3.7 1 -

1 EK3.01 - Length of time for which battery capacity is designed AK1.O 1 - Principle of cooling by natura convection 10055 Station Blackout / 6 3.4 -

4.0 1 -

1 2.1.32 - Ability to explain and apply all system limits and precautions.

AK3.02 - Actions contained in EOP for loss of dc power 000065 Loss of Instrument Air I 8 WE04 LOCA Outside Containment / 3 I 3.4 -

3.5 3.4 1 -

1 1

2.1.32 - Ability to explain and apply all system limits and precautions.

EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK3.1 - Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics 1

Facility:

DCPP ES - 401 41 PWR RO Examination Outline Printed: 0 1 /2 1/2005 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 A2 3

3

' "/APE # / Name / Safety Function G

WE1 1 Loss of Emergency Coolant Recirc. /

4 KATopic EK2.2 - Facility's 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 WE12 - Steam Line Rupture - Excessive Heat Transfer / 4 mp.

3.9 3.5 K/A Category Totals:

Points 1

1 K1 -

X 3

EK1.2 - Normal, abnormal and emergency operating procedures associated with Uncontrolled Depressurization of all Steam Generators 31 Group Point Total:

18 2

PWR RO Examination Outline Facility:

DCPP 000033 Loss of Intermediate Range NI I 7 Printed: 01/21/2005 X

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 KIA Category Totals:

2 000001 Continuous Rod Withdrawal I 1 I

I X 000003 Dropped Control Rod I 1 000036 Fuel Handling Accident I 8 000060 Accidental Gaseous Radwaste Rel. /

9 000061 ARM System Alarms 17 I

WE0 1 Rediagnosis I 3 WE03 LOCA Cooldown - Depress. 14 W E 16 High Containment Radiation / 9 KA Topic AK2.05 - Rod motion lights AK1.21 - Delta flux (I)

AK1.01 - Effects of voltage changes on performance AK3.02 - Interlocks associated with fuel handling equipment AA1.02 - Ventilation system AA2.04 - Whether an alarm channel is functioning properly EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

2.4.19 - Knowledge of EOP layout, symbols, and icons.

Group Point Total:

9 1

PWR RO Examination Outline Facility:

DCPP ES - 401 I

Cys/Evol # / Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 006 Emergency Core Cooling 007 Pressurizer RelieUQuench Tank 008 Component Cooling Water 008 Component Cooling Water 010 Pressurizer Pressure Control 0 12 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 022 Containment Cooling 026 Containment Spray 039 Main and Reheat Steam 039 Main and Reheat Steam 059 Main Feedwater 06 1 AuxiliaryBmergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 064 Emergency Diesel Generator 073 Process Radiation Monitoring Printed: 01/21/2005 Form ES-401-2 Imp. Points Plant Systems - Tier 2 / Group 1 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic X

K4.07 - Minimizing RCS 3.2 1

leakage (mechanical seals)

X K2.01 - Boric acid makeup 2.9 1

Pumps X

A4.17 - Deborating 2.7 1

demineralizer X

K6.03 - RHR heat 2.5 1

exchanger X

K1.02 - ESFAS 4.3 1

X K6.03 - Safety Injection 3.6 1

X A2.03 - Overpressurization 3.6 1

X K3.03 - RCP 4.1 1

X 2.2.13 - Knowledge of 3.6 1

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Pumps of the PZR tagging and clearance procedures.

X K6.02 - PZR 3.2 1

X K5.01 - DNB 3.3*

1 X

K5.01 - Definitions of safety 2.8 1

X A 1.02 - Containment 3.6 1

X 2.4.34 - Knowledge of RO 3.8 1

train and ESF channel pressure tasks performed outside the main control room during emergency operations including system geography and system implications.

CSS, including recirculation phase after LOCA X

Al.05 - RCS T-ave 3.2*

1 X

A4.03 - MFW pump 2.8*

1 turbines K3.04 - RCS 3.6 1

X K5.05 - Feed line voiding 2.7 1

and water hammer X

K4.01 - Source of water for 4.2 1

X X

K2.01 - Major system loads 3.3 1

X K3.01 - ED/G 3.7*

1 X

A3.10 - Function of ED/G 2.8 1

X A3.03 - Indicating lights, 3.4 1

megawatt load controller

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meters, and recorders

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x K1.O1 - Those systems 3.6 1

1

Facility:

DCPP ES - 401 K2 PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 K3 K4 X

X 2

4 3

Printed: 01/21/2005 Form ES-401-2 3ys/Evol# / Name I

073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment K/A Category Totals:

K1 -

2 I

I A4.02 - Radiation monitoring system control panel K3.05 - RHR components, 3.0*

1 controls, sensors, indicators, and alarms, including rad monitors K4.01 - ManuaVautomatic 2.7 1

transfers of control A2.03 - Phase A and B 3.5*

1 isolation Group Point Total:

28 2

ES - 401 I Cys/Evol # / Name 00 1 Control Rod Drive 014 Rod Position Indication 016 Non-nuclear Instrumentation 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 034 Fuel Handling Equipment 041 Steam Dump/Turbine Bypass Control 068 Liquid Radwaste 072 Area Radiation Monitoring I 075 Circulating Water WACategoryTotals:

1 Form ES-401-2 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points Plant Systems - Tier 2 / Group 2 X

K6.13 - Location and 3.6 1

X A4.04 - Re-zeroing of rod 2.7 1

X K3.01-RCS 3.4*

1 X

K2.01 - Hydrogen 2.5*

1 X

A1.03 - Containment 3.0*

1 operation of RPIS position prior to startup recombiners pressure, temperature, and humidity general operating crew responsibilities during emergency operations.

X A2.02 - Steam valve stuck 3.6 1

open environmental precautions for handling hot, acidic, and radioactive liquids changes with source distance sws X 2.4.12 - Knowledge of 3.4 1

X K4.01 - Safety and 3.4 1

X K5.02 - Radiation intensity 2.5 1

X K1.08 - Emergency/essential 3.2*

1 1

1 1

1 1

1 1

1 0

1 1

Group Point Total:

10

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Facility:

DCPP 2.2.28 2.2.33 Generic CatePorv Knowledge of new and spent fuel movement 2.6 1

Knowledge of control rod programming.

2.5 1

procedures.

KA 2.3.4 KA Topic Knowledge of radiation exposure limits and 2.5 1

contamination control, including permissible levels in excess of those authorized.

Conduct of Operations 2.4.12 2.1.10 Knowledge of general operating crew responsibilities during emergency operations.

2.1.21 2.4.45 2.1.29 Ability to prioritize and interpret the significance 3.3 1

of each annunciator or alarm.

Printed: 01/21/2005 Form ES-401-3

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Knowledge of conditions and limitations in the facility license.

Ability to obtain and verify controlled procedure COPY.

Knowledge of how to conduct and verify valve lineups.

I Category Total:

Imp.

2.7 3.1 3.4 Points 1

1 1

3 Equipment Control Radiation Control Emergency ProceduresRlan Category Total:

2 4

2.3.1 Knowledge of 10 CFR: 20 and related facility I 2.6 I 1 I I radiation control requirements.

I I

I 2.3.2 Knowledge of facility ALARA program.

I 2*5 I I

I I

I I

I I

I I

Generic Total:

10 1

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ES-401 PWR Examination Outline

~~

Form ES-401-2 Facilitv:

DCPP Date Of Exam:

02/07/2005 Printed: 01 /21/2005 I

I I

RO wA Category Point!

I SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the 'Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.
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 +I 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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category /tier.

6.* The generic (G) WAS in Tiers I and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA 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 columns labeled "K" and "A".

Use duplicate pages for RO and SROanly exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

ES-401-3.

1

PWR SRO Examination Outline Facility:

DCPP Printed: 0112112005 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2

' VJAPE # I Name I Safety Function K1 KA Topic

[mp.

Points 0000 1 1 Large Break LOCA I 3 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

3.7 4.0 3.8 000022 Loss of Rx Coolant Makeup 12 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

000025 Loss of RHR System 14 AA2.02 - Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere 000026 Loss of Component Cooling Water I 8

AA2.06 - The length of time after the loss of CCW flow to a component before that component may be damagec 3.1*

000054 Loss of Main Feedwater 1 4 AA2.01 - Occurrence of reactor and/or turbine trip 4.4 3.6 AA2.14 - That substitute power sources have come on line on a loss of initial ac 000057 Loss of Vital AC Inst. Bus 16 0 -

KIA Category Totals:

Group Point Total:

6 1

Facility:

DCPP ES - 401 K3 PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 A1 0

0

' v,/APE # / Name / Safety Function 42 X

X X

u00061 ARM System Alarms / 7 WE02 SI Termination / 3 G

X 3

1 I I WE09 Natural Circ. 1 4 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations W E 13 Steam Generator Over-pressure / 4 4.2 1

EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 3.8 1

Printed: 01/21/2005 Form ES-401-2 2.4.30 - Knowledge of which events related to system operations/status should be reported to outside agencies.

KA Topic 3.6 I

AA2.05 - Need for area check against existing limits Group Point Total:

4 1

Facility:

DCPP A3 ES - 401

' Yys/Evol # / Name K1 A4 0

0 003 Reactor Coolant Pump 005 Residual Heat Removal 0 10 Pressurizer Pressure Control 3.6 I

I 022 Containment cooling 1

076 Service Water K/A Category Totals:

0 PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Printed: 01/21/2005 Form ES-401-2 KA Topic A2.05 - Effects of VCT pressure on RCP seal leakoff flows 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

A2.03 - PORV failures A2.04 - Loss of service water 2.2.22 - Knowledge of limiting conditions for operations and safety limits.

Imp. I Points 2.8 I 4.2 I 1 Group Point Total:

5 1

PWR SRO Examination Outline Facility:

DCPP

' Cys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic 01 1 Pressurizer Level Control 0 14 Rod Position Indication X

A2.05 - Loss of PZR heaters annunciator response procedures.

element X 2.4.10 - Knowledge of 034 Fuel Handling Equipment X

A2.0 1 - Dropped fuel Printed: 01/21/2005 Imp. Points 3.7 1

3.1 1

4.4 1

K/A Category Totals: I O 1 O 1 O 1 O 1 O 1 O I O 1 21 O 1 O I 1 1 3

1 Group Point Total:

1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Conduct of Operations 2.1.10 2.1.22 Printed: 0 1/2 1/2005 Knowledge of conditions and limitations in the 3.9 1

Ability to determine Mode of Operation.

3.3 1

facility license.

Form ES401-3 Facilitv:

DCPP Radiation Control 2.3.4 2.3.8 Equipment Control 2.2.27 2.4.45 I 3.5 I I

Knowledge of the refueling process.

Ability to prioritize and interpret the significance 3.6 1

of each annunciator or alarm.

I Category Total:

1 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Knowledge of the process for performing a planned gaseous radioactive release.

Category Total:

2 Emergency Proceduresfflan 1 2.4.41 1 Knowledge of the emergency action level thresholds and classifications.

1 4.1 1

1 Generic Total:

7 1

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