Text

Initial Exam - 02/2005 - Draft Written Outlines and Rejected Ka'S
	ML050890254
Person / Time
Site:	Diablo Canyon
Issue date:	10/19/2004
From:	; - No Known Affiliation
To:	; Office of Nuclear Reactor Regulation
References
	50-275/05-301, 50-323/05-301, ES-401, ES-401-4 50-275/05-301, 50-323/05-301
	Download: ML050890254 (28)
	v • d • e

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected WA RO APE 057 G2.4.10 Deleted in accordance with guidance in ES-40 1, Attachment TlGl 2, WA Elimination Guidelines RO At DCPP, there is no tie between Service Water (Aux 076 K3.05 T2G1 Saltwater) and secondary plant cooling.

SRO Deleted in accordance with guidance in ES-401, Attachment EPE 01 1 G2.4.36 TlGl 2, WA Elimination Guidelines SRO Deleted in accordance with guidance in ES-40 1, Attachment APE 022 G2.2.18 TlGl 2. WA Elimination Guidelines SRO At DCPP there is no tie from Vital AC to Turbine Load APE 057 AA2.10 TlGl Limiter SRO Deleted in accordance with guidance in ES-401, Attachment WE13 G2.2.7 T1G2 2. WA Elimination Guidelines SRO APE 061 AA2.05 Not testable at the SRO level T1G2 Resampled, KA (Primary Coil Voltage Measurement) does RO 014 A4.03 not amlv to utilitv. Randomlv selected A4.04 as redacement.

ES-401 PWR Examination Outline Form ES-401-2 Facilitv: DCPP Printed: 12/02/2004 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 (Le., the 'Tier Totals" in each WAcategory 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 +fromI 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 "K" and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3,enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2,for guidance regarding the elimination of inappropriate WA statements.

1

PWR RO Examination Outline Printed: 12/02/2004 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 i

Form ES-401-2

, &/APE# /Name / Safety Function K1

- mp. Points 000007 Reactor Trip - Stabilization - EK2.03 - Reactor trip status panel 3.5 1 Recovery / 1 I 000008 Pressurizer Vapor Space Accident I AA2.20 - The effect of an open PORV 3.4 1 on code safety, based on observation of 13 plant parameters 0000 11 Large Break LOCA I 3 X 4.1 1 cooling, including reflux boiling 000015/000017 RCP Malfunctions I 4 1AA 1.10 - RCP ammeter and trip alarm 2.7 1 000022 Loss of Rx Coolant Makeup 1 2 2.1.25 - Ability to obtain and interpret 2.8 1 station reference materials such as graphs, monographs, and tables which contain performance data.

000026 Loss of Component Cooling Water / AA2.04 - The normal values and upper 2.5 1 limits for the temperatures of the components cooled by CCW I 000029 ATWS I 1 IEA 1.O1 - Charging pumps 3.4* 1 000038 Steam Gen. Tube Rupture / 3 EA2.06 - Shutdown margins and 3.8 1 required boron concentrations

' 900054 Loss of Main Feedwater /4 IAA 1.02 - Manual startup of electric and steam-driven AFW pumps 4.4 1 000055 Station Blackout 1 6 EK3 .O1 - Length of time for which 2.7 1 battery capacity is designed 000056 Loss of Off-site Power 1 6 AK1.O1 - Principle of cooling by natural 3.7 1 convection 000057 Loss of Vital AC Inst. Bus / 6 X 2.1.32 - Ability to explain and apply all 3.4 1 system limits and precautions.

000058 Loss of DC Power 1 6 AK3.02 - Actions contained in EOP for 4.0 1 loss of dc power I

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

3.4 1 WE04 LOCA Outside Containment / 3 EK2.1 - Components, and functions of 3.5 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E05 Inadequate Heat Transfer - Loss of EK3.1 - Facility operating 3.4 1 Secondary Heat Sink 1 4 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

PWR RO Examination Outline Printed: 12/02/2004 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2

~~

JAPE # / Name / Safety Function KA Topic Imp. Points W E 1 1 Loss of Emergency Coolant Recirc. / EK2.2 - Facility's heat removal systems, 3.9 1 4 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 EK1.2 - Normal, abnormal and 3.5 1 Heat Transfer / 4 emergency operating procedures associated with Uncontrolled Depressurization of all Steam Generators K/A Category Totals: Group Point Total: 18 2

PWR RO Examination Outline Printed: 12/02/2004 Facility: DCPP ES - 401 -

Emergency and Abnormal Plant Evolutions Tier 1 I Group 2 Form ES-401-2

.JAPE # I Name I Safety Function K1 K2 G I KATopic IImp. 1 Points 000001 Continuous Rod Withdrawal I 1 X IAK2.05 - Rod motion lights I 2.9* I 1 000003 Dropped Control Rod I 1 X IAK1.2 1 - Delta flux (I) I 2.7 I 1 000033 Loss of Intermediate Range NI I 7 000036 Fuel Handling Accident / 8 X AK1.O1 - Effects of voltage changes on performance AK3.02 - Interlocks associated with fuel I I2*7 2.9 1 handling equipment 000060 Accidental Gaseous Radwaste Rel. I AA1.02 - Ventilation system 2.9 1 9

00006 1 ARM System Alarms I 7 AA2.04 - Whether an alarm channel is 3.1 1 functioning properly W/EOl Rediagnosis / 3 EK3.3 - Manipulation of controls 3.5 1 required to obtain desired operating results during abnormal, and emergency situations WE03 LOCA Cooldown - Depress. 1 4 to perform specific 3.9 1 system and integrated plant procedures during all modes of plant operation.

W E 16 High Containment Radiation I 9 X 2.4.19 - Knowledge of EOP layout, 2.7 1 symbols, and icons.

KIA Category Totals: 2 1 2 Group Point Total: 9 1

PWR RO Examination Outline Printed: 12/02/2004 Facility: DCPP Form ES-401-2 I I KA Topic Imp. Points K4.07 - Minimizing RCS 3.2 1 leakage (mechanical seals)

JS2.01 - Boric acid makeup 2.9 1 DUmDS A4.17 - Deborating demineralizer K6.03 - RHR heat I 2.7 2.5 II 1 exchanger K1.02 - ESFAS 2.4.32 - Knowledge of 3.3 operator response to loss of I all annunciators. -

A2.03 - Overpressurization 3.6 1 of the PZR -

K3.03 - RCP 4.1 1 2.2.13 -Knowledge of 3.6 1 tagging and clearance I procedures.

K6.02 - PZR 3.2 1 K5.01- DNB 3.3* 1 K5.01 - Definitions of safety 2.8 1 train and ESF channel A 1.02 - Containment 3.6 1 Dressure 2.4.34 - Knowledge of RO 3.8 tasks performed outside the main control room during emergency operations including system geography and system implications.

K4.0 1 - Source of water for 4.2 CSS, including recirculation Dhase after LOCA

~

Al.05 - RCS T-ave I 3.2* I 1 A4.03 - MFW pump turbines 1 K3.04 - RCS I 2.8*

3.6 II 1 K5.05 - Feed line voiding and water hammer K2.0 1 - Major system loads I 2.7 3.3 1

1 A2.01 - Grounds 2.5 1 A3.10 - Function of ED/G 2.8 1 I megawatt load controller I

A3.03 - Indicating lights, meters, and recorders 3*4 I 1

PWR RO Examination Outline Printed: 12/02/2004 Facility: DCPP FS - 401 Plant Systems Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K4 K5 K6 k1 A2 A3 KA Topic Imp. Point 073 Process Radiation Monitoring K1.O1 - Those systems 3.6 1 served by PRMs 073 Process Radiation Monitoring A4.02 - Radiation 3.7 1 monitoring system control Dane1 076 Service Water K3.05 - RHR components, 3.0* 1 1 I controls, sensors, indicators, and alarms, including rad monitors 078 Instrument Air X K4.01 -ManuaVautomatic 32.J7" transfers of control I 103 Containment I I X A2.03 - Phase A and B isolation K/A Category Totals:

212 3 3 2 2 3 2 Group Point Total: 28 2

PWR RO Examination Outline Printed: 12/02/2004 Facility: DCPP Form ES-401-2 KA Topic Imp. Points K6.13 - Location and operation of RPIS position prior to startup K3.01- RCS 3.4* 1 K2.01 - Hydrogen 2.5* 1 recombiners Al.03 - Containment 3.0* 1 pressure, temperature, and humidity 2.4.12 - Knowledge of 3.4 1 general operating crew responsibilities during emergency operations.

A2.02 - Steam valve stuck 3.6 1 open K4.01 - Safety and 3.4 1 environmental precautions for handling hot, acidic, and radioactive liquids K5.02 - Radiation intensity 2.5 1 changes with source distance K1.08 - Emergency/essential 3.2* 1 sws Group Point Total: 10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 12/02/2004 Facilitv: DCPP Form ES-401-3 Generic Category -

KA KA ToDic ImD. Points I I I I Conduct of Operations 2.1.10 Knowledge of conditions and limitations in the 2.7 1 facility license.

1 2.1.2 1 I Ability to obtain and verify controlled procedure cow.

2.1.29 Knowledge of how to conduct and verify valve 3.4 1 lineups.

Equipment Control 2.2.28 Knowledge of new and spent fuel movement 2.6 1 procedures.

2.2.33 Knowledge of control rod programming. 2.5 1 Radiation Control I 2.3.1 1 Knowledge of 10 CFR: 20 and related facility radiation control reauirements.

1 2.6 1 I 2.3.2 I Knowledge of facility ALARA program. I 2.5 I 2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.

Category Total: 3 Emergency Proceduresh'lan 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

Category Total: 2 Generic Total: 10 1

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ES-401 PWR Examination Outline Form ES-401-2 Facilitv: DCPP Printed: 12/02/2004 Date Of Exam: 02/07/2005 I I I RO K/A 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 *Ifrom 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 "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 ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

1

PWR SRO Examination Outline Printed: 12/02/2004 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function I K1 KA Topic Imp. Points 000011 Large Break LOCA 1 3 2.2.25 - Knowledge of bases in 3.7 1 technical specifications for limiting conditions for operations and safety limits.

000022 Loss of Rx Coolant Makeup I 2 2.1.33 - Ability to recognize indications 4.0 1 for system operating parameters which are entry-level conditions for technical specifications.

000025 Loss of RHR System I 4 AA2.02 - Leakage of reactor coolant 3.8 1 fiom RHR into closed cooling water system or into reactor building atmosphere 000026 Loss of Component Cooling Water / I AA2.06 - The length of time after the 3.1* 1 8 loss of CCW flow to a component before that component may be damaged 000054 Loss of Main Feedwater / 4 AA2.01 - Occurrence of reactor andor 4.4 turbine trip 000057 Loss of Vital AC Inst. Bus I 6 AA2.14 - That substitute power sources 3.6 have come on line on a loss of initial ac K/A Category Totals: 0 Group Point Total: 6 1

PWR SRO Examination Outline Printed: 12/02/2004 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 EIAPE # I Name I Safety Function K1 K2 K3 A1 A2 G KATopic Imp. Points 000061 ARM System Alarms / 7 X AA2.05 - Need for area evacuation; check against existing limits WE02 SI Termination / 3 X EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations WE09 Natural Circ. / 4 X EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations WE13 Steam Generator Over-pressure / 4 should be reported to outside agencies.

KIA Category Totals: 0 0 0 0 3 Group Point Total:

1

PWR SRO Examination Outline Printed: 12/02/2004 Facility: DCPP Plant Systems - Tier 2 / Group 1 Form ES-401-2 ES - 401 Sys/Evol # / Name K1 A2 A3 A4 G KATopic Imp.

003 Reactor Coolant Pump X A2.05 - Effects of VCT 2.8 pressure on RCP seal leakoff flows I

005 Residual Heat Removal X 2.4.45 - Ability to prioritize 3.6 and interpret the significance of each annunciator or alarm.

010 Pressurizer Pressure Control I X A2.03 - PORV failures 4.2 022 Containment Cooling X A2.04 - Loss of service 3.2 water 076 Service Water X 2.2.22 - Knowledge of 4.1 limiting conditions for

- operations and safety limits.

WA Category Totals: 0 3 0 0 2 Group Point Total:

PWR SRO Examination Outline Printed: 12/02/2004 Facility: DCPP Sys/Evol# I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points 01 1 Pressurizer Level Control X A2.05 - Loss of PZR heaters 3.7 1 014 Rod Position Indication X 2.4.10 - Knowledge of 3.1 1 annunciator response procedures.

034 Fuel Handling Equipment X A2.01 - Dropped fuel 4.4 1 element WACategory Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 12/02/2004 Facilitv: DCPP Form ES-401-3 Conduct of Operations 2.1.10 Knowledge of conditions and limitations in the 3.9 1 facility license.

2.1.22 Ability to determine Mode of Operation. 3.3 1 Category Total: 2 Equipment Control 2.2.27 Knowledge of the refueling process. 3.5 1 Category Total: 1 I I I I I Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. 3*1 2.3.8 Knowledge of the process for performing a 3.2 1 planned gaseous radioactive release.

Emergency ProceduresL'lan 2.4.41 Knowledge of the emergency action level thresholds and classifications.

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

ML050890254

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