Text

07-2003 Draft Outlines
	ML041050302
Person / Time
Site:	Palo Verde
Issue date:	07/21/2003
From:	Gody A; Operations Branch IV
To:	Overbeck G; Arizona Public Service Co
References
	50-528/03-301, 50-529/03-301, 50-530/03-301, ES-301-1 50-528/03-301, 50-529/03-301, 50-530/03-301
	Download: ML041050302 (20)
	v • d • e

PVNGS License Examination Administrative Topics Outline PVNGS Form ES-301-1 Page 1 04/06/2004 Facility: Palo Verde Examination Level: RO Date of Examination: 7/21/03 Operating Test Number: PVNGS RO Administrative Topic (see Note)

Describe activity to be performed:

K/A #

IMP Conduct of Operations Ability to execute procedure steps. (Candidate will be required to complete a power change reactivity balance worksheet for a power ascension)

Scheduled as Admin Task RA1-1. (New)

Can be performed in classroom or simultor.

2.1.19 3.0 Conduct of Operations Ability to use plant computer to obtain and evaluate parametric information on system or component status.

With COLSS Out of Service, the Candidate will be required to use CPC values to determine that the status of ASI/LHR/DNBR/AZTILT is not satisfactory and inform the SRO.

Scheduled as Admin Task RA1-2.

Can be performed in classroom or simultor.

2.1.20 4.3 Equipment Control Perform a Tech Review of a Permit.

Tech Review a Permit and determine three errors.

Schedule as Admin JPM RA2. (New) 40ST-9ZZM1 To be performed in the classroom.

2.2.13 3.6 Radiation Control Verify administrative and radiological entry requirements per the RWP (Candidate will be required to demonstrate the proper method for verifying qualifications and identify the proper REP, task, and dose settings/limits for the particular job assignment.)

Scheduled as Admin JPM RA3. (New)

To be performed in the classroom.

2.3.1 2.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

PVNGS License Examination Control Room/In-Plant Systems Outline PVNGS Form ES301-2 Page 1 Facility: _PVNGS_

Exam Level: _RO_

Date of Examination: _7/21/03__

Operating Test No.: __RO__

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

JPM #

System/JPM Title Type Code*

Safety Function JS1 In order to Emergency Borate, operate HPSI pumps in lieu of Charging pumps (SI030)

S D L A 4.2.024AK3.02 4.2/4.4 2

JS2 Direct Containment Hydrogen Control (HP004)

S D (L) 3.5.028.A4.03 3.1/3.3 5

JS3 Perform Actions for Rapid Turbine Unloading as directed by AOP (New Procedure)

S N 3.4.045A4.02 2.7/2.6 4

(Secondary)

JS4 RC/Operate PZR Press Control System (RC008)

S D A 3.3.010.A4.01 3.7/3.5 3

JS5 Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the Unit Auxiliary Transformer MAN-X02 (NA001)

S D 3.6.062.K1.04 3.7/4.2 6

JS6 Given the need to remove a RU monitor from service, bypass a BOP ESFAS module in accordance with 40OP-9SA01 S N 3.7.016.A4.01 3.9/2.8 7

JS7 Dilute the RCS (CH001)

S M A 3.1.004A4.07 3.9/3.7 1

JS8 Loss of NCW, RCPs are tripped, and Seal Bleedoff Isolated (NC006)

S D A 3.8.008A2.01 3.3/3.6 8

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

JP1 DG/Perform event control action for CR Fire (Time Critical) (PRA Significant) (DG008)

P M A 4.2.068.AA1.10 3.7/3.9 4.2.068.AA1.31 3.9/4.0 6

JP2 Transfer CEAs to the hold bus. (Time Critical)

(SF032)

P D R 3.1.001.A2.14 3.7/3.9 1

JP3 Remote operation of AFA at the Remote S/D Panel (PRA Significant) (AF002)

P D 4.2.068AK3.07 4.0/4.3 4

(Secondary)

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate Path, (C)ontrol Room, (P)lant, (S)imulator, (L)ow Power, (R)CA

PVNGS License Examination Administrative Topics Outline PVNGS Form ES-301-1 Page 1 04/06/2004 Facility: Palo Verde Examination Level: SRO Date: 7/21/03 Operating Test Number: SRO Administrative Topic (see Note)

Describe activity to be performed:

K/A IMP Conduct of Operations Knowledge of conditions and limitations in the facility license. (Candidate will be required to review a completed Safety Function Determination Worksheet and Tracking Sheet and annotate three significant errors)

Scheduled as Admin JPM SA1-1. (AD008)

Can be performed in classroom or simultor.

2.1.12 4.0 Conduct of Operations Ability to use plant computer to obtain and evaluate parametric information on system or component status.

With COLSS Out of Service, the Candidate will be required to use CPC values to determine that the status of ASI/LHR/DNBR/AZTILT is not satisfactory and correlate the T.S. criteria.

Scheduled as Admin JPM SA1-2 Can be performed in classroom or simultor.

2.1.20 4.2 Equipment Control Review Shutdown Margin Surveillance Test; identify three (3) errors and Direct Boration.

Schedule as Admin JPM SA2. (LOCT 99 Audit Exam)

Can be performed in classroom or simultor.

2.2.12 3.4 Radiation Control Knowledge of the process for performing a containment purge. (To be performed in classroom)

Candidate will be asked to review a Gaseous release permit and identify three errors.

Schedule as SRO Admin JPM SA3.

To be performed in the classroom.

2.3.9 3.4 Emergency Plan Ability to take action called for in the Emergency Plan, including acting as Emergency Coordinator. (Candidate will classify event and perform initial Emergency Coordinator duties.)

Scheduled as Admin JPM SA4. (New)

To be performed in Simulator.

2.4.38 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

PVNGS License Examination Control Room/In-Plant Systems Outline PVNGS Form ES301-2 Page 1 Facility: _PVNGS_

Exam Level: _SRO_

Date of Examination: _7/21/03__

Operating Test No.: __SRO__

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

JPM #

System/JPM Title Type Code*

Safety Function JS1 In order to Emergency Borate, operate HPSI pumps in lieu of Charging pumps (SI030)

S D L A 4.2.024AK3.02 4.2/4.4 2

JS2 Direct Containment Hydrogen Control (HP004)

S D (L) 3.5.028.A4.03 3.1/3.3 5

JS3 Perform Actions for Rapid Turbine Unloading as directed by AOP (New Procedure)

S N 3.4.045A4.02 2.7/2.6 4

(Secondary)

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

JP1 DG/Perform event control action for CR Fire (Time Critical) (PRA Significant) (DG008)

P D 4.2.068.AA1.10 3.7/3.9 4.2.068.AA1.31 3.9/4.0 6

JP2 Transfer CEAs to the hold bus. (Time Critical)

(SF032)

P D R 3.1.001.A2.14 3.7/3.9 1

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate Path, (C)ontrol Room, (P)lant, (S)imulator, (L)ow Power, (R)CA

PVNGS NRC License Examination July 18, 2003 PWR Written examination outline PVNGS Form ES-401-2 Page 1 RO K/A Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total K

A A

2 G

Total 1

1 2

3 4

5 3

18 5

2 7

2 3

2 1

1 1

1 9

3 2

5

1.

Emergency &

Abnormal Plant Evolutions Tier Totals 4

4 4

5 6

4 27 8

4 12 1

3 3

2 2

3 2

2 28 3

1 4

2 0

0 0

1 2

0 1

1 1

2 2

10 2

2

2.

Plant Systems Tier Totals 3

3 3

4 4

2 4

3 4

4 4

38 5

1 6

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 2

3 2

3 10 2

2 1

2 7

Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e. the Tier Totals in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding 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 +/-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.

Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution unless they are related 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) 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7.

On the following pages, enter the K/A 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

8.

For Tier 3, enter the K/A 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 K/A statements.

PVNGS NRC License Examination July 18, 2003 PWR Examination outline Emergency and Abnormal Plant evolutions - Tier 1 Group 1 (RO/SRO)

PVNGS Form ES-401-2 Page 2 E/APE #/Name/Safety Function K

1 K

2 K

3 A

1 A

2 G Number K/A Topics Imp.

RO SRO 000007/E02 Reactor Trip - Recovery /1 1

EK2.02 Knowledge of the interrelations between a reactor trip and the following: Breakers, relays and disconnects 2.6 1

000007/E02 Reactor Trip - Recovery /1 1

EA2.1 Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations (43.5) 3.7 1

000008 Pzr Vapor Space Accident /3 1

AA1.06 Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space Accident: Control of PZR level 3.6 1

000009 Small Break LOCA /3 1

EK3.03 Knowledge of the reasons for the following responses as they apply to the small break LOCA:

Reactor trip and safety initiation 4.1 1

000011 Large Break LOCA /3 1

EK2.02 Knowledge of the interrelations between the Large Break LOCA and the following: Pumps 2.6 1

000011 Large Break LOCA /3 1

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation (43.5) 4.4 1

000015/17 RCP Malfunctions /4 1

AA2.08 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high bearing temperature 3.4 1

000022 Loss of Rx Coolant Makeup /2 1

AK1.03 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Pump Makeup: Relationship between charging flow and PZR level 3.0 1

000025 Loss of RHR System /4 1

AA1.03 Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: LPI pumps 3.4 1

000026 Loss of Comp. Cooling Water /8 1

AA2.06 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The length of time after the loss of CCW flow to a component before that component 2.8 1

000027 Pzr Press. Ctrl. Sys. Malf. /3 1

AA2.15 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: Actions to be taken if PZR pressure instrument fails high 3.7 1

000027 Pzr Press. Ctrl. Sys. Malf. /3 1

AA2.11 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: RCS Pressure (43.5) 4.1 1

000029 ATWS /1 1

EA2.02 Ability to determine or interpret the following as they apply to a ATWS: Reactor trip alarm 4.2 1

000029 ATWS /1 1

2.4.1 Knowledge of EOP entry conditions and immediate action steps (43.5) 4.3 1

000038 SG Tube Rupture/3 1

EA1.27 Ability to operate and monitor the following as they apply to a SGTR: Steam dump valve status lights and indicators 3.9 1

000038 SG Tube Rupture/3 1

EA2.02 Ability to determine or interpret the following as they apply to a SGTR: Existence of an S/G tube rupture and its potential consequences (43.5) 4.8 1

000040/E05 Steam Line Rupture /4 1

AA1.04 Ability to operate and / or monitor the following as they apply to the Steam Line Rupture:

Isolation of all steam lines from header 4.3 1

000054 E06 Loss of Feedwater /4 1

EA2.2 Ability to determine and interpret the following as they apply to the (Loss of Feedwater)

Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments (43.5) 4.1 1

000055 Station Blackout /6 1

2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures 4.0 1

000056 /Loss of Off Site Power /6 1

AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Order and time to initiation of power for the load sequencer 3.5 1

000057 Loss of Vital AC Instrument Bus /6 1

2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

3.9 1

000057 Loss of Vital AC Instrument Bus /6 1

AA2.17 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: System and component status, using local or remote controls (43.5) 3.4 1

PVNGS NRC License Examination July 18, 2003 PWR Examination outline Emergency and Abnormal Plant evolutions - Tier 1 Group 1 (RO/SRO)

PVNGS Form ES-401-2 Page 3 E/APE #/Name/Safety Function K

1 K

2 K

3 A

1 A

2 G Number K/A Topics Imp.

RO SRO 000058 Loss of DC Power /6 1

2.1.20 Ability to execute procedure steps.

4.3 1

000062 Loss of Nuclear Service Water /4 1

AK3.03 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water Guidance actions contained in EOP for Loss of nuclear service water 4.0 1

000065 Loss of Instrument Air /8 1

AA2.06 Ability to determine and interpret the following as they apply to the Loss of Instrument Air:

When to trip reactor if instrument air pressure is de-creasing 3.6 1

K/A Category Totals 1

2 3 4 10 5

Group Point Total 18 7

PVNGS NRC License Examination July 18, 2001 PWR Examination outline Emergency and Abnormal Plant evolutions - Tier 1 Group 2 (RO/SRO)

PVNGS Form ES-401-2 Page 4 E/APE #/Name/Safety Function K

1 K

2 K

3 A

1 A

2 G

Number K/A Topics Imp.

RO SRO 000001 Continuous Rod Withdrawal /1 1

AA2.02 Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Position of emergency boration valve (43.5) 4.2 1

000003 Dropped Control Rod /1 1

AA2.01 Ability to determine and interpret the following as they apply to the Dropped Control Rod: Rod position indication to actual rod position (43.5) 3.9 1

000005 Inoperable/Stuck Control Rod /1 1

AA1.01 Ability to operate and / or monitor the following as they apply to the Inoperable /

Stuck Control Rod: CRDS 3.6 1

000024 Emergency Boration /1 000028 /Pzr Level Malfunction /2 1

AK2.02 Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following: Sensors and detectors 2.6 1

000032 Loss of Source Range NI /7 1

2.4.10 Knowledge of annunciator response procedures.

3.0 1

000033 Loss of Intermediate Range NI /7 1

AA2.02 Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Indications of unreliable intermediate-range channel operation (43.5) 3.6 1

000036 /Fuel Handling Accident /8 000037 SG Tube Leak /3 1

2.4.7 Knowledge of event based EOP mitigation strategies (43.5) 3.8 1

000051 Loss of Condenser vacuum /4 1

AA2.02 Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip 3.9 1

000059 Accidental Liquid RadWaste Rel. /9 1

AK3.04 Knowledge of the reasons for the following responses as they apply to the Accidental Liquid Radwaste Release: Actions contained in EOP for accidental liquid radioactive-waste release 3.8 1

000060 Accidental Gaseous Radwaste Rel./9 000061 ARM System Alarms /7 000067 Plant Fire on Site /8 1

AK1.02 Knowledge of the operational implications of the following concepts as they apply to Plant Fire on Site: Fire fighting 3.1 1

000068 Control Room Evac. /8 1

2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications (43.5) 3.6 1

000069 Loss of CTMT Integrity /5 1

AK2.03 Knowledge of the interrelations between the Loss of Containment Integrity and the following: Personnel access hatch and emergency access hatch 2.8 1

000074 Inadequate Core Cooling /4 1

EK1.07 Knowledge of the operational implications of the following concepts as they apply to the Inadequate Core Cooling : Definition of saturated steam 2.8 1

000076 High Reactor Coolant Activity /9 A11 RCS Overcooling/PTS /4 A13 Natural Circulation /4 A16 /Excessive RCS Leakage /2 1

AK1.02 Knowledge of the operational implications of the following concepts as they apply to the (Excess RCS Leakage) Normal, abnormal and emergency operating procedures associated with (Excess RCS Leakage).

3.0 1

E09 /Functional Recovery K/A Category Totals 3

2 1

1 4

3 Group Point Total 9

5

PVNGS NRC License Examination July 2001 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO)

PVNGS Form ES-401-2 Page 5 System #/Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Number K/A Topics Imp.

RO SRO 003 Reactor Coolant Pump 1

K2.01 Knowledge of bus power supplies to the following: RCPS 3.1 1

004 Chemical and Volume Control 1

A3.02 Ability to monitor automatic operation of the CVCS, including: Letdown isolation 3.6 004 Chemical and Volume Control 1

K6.17 Knowledge of the effect of a loss or malfunction on the following CVCS components: Flow paths for emergency boration 4.4 2

005 Residual Heat Removal 1

K2.01 Knowledge of bus power supplies to the following: RHR pumps 3.0 1

005 Residual Heat Removal 1

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR (43.5) 3.1 1

006 Emergency Core Cooling 1

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of flow path 3.9 1

007 Pressurizer Relief/Quench Tank 1

K1.01 Knowledge of the physical connections and/or cause-effect relationships between the PRTS and the following systems:

Containment system 2.9 1

008 Component Cooling Water 1

A1.02 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the CCWS controls including: CCW temperature 2.9 1

010 Pressurizer Pressure Control 1

A4.01 Ability to manually operate and/or monitor in the control room: PZR spray valve 3.7 1

012 Reactor Protection 1

K5.01 Knowledge of the operational implications of the following concepts as the apply to the RPS: DNB 3.3 1

013 ESFAS 1

2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes 3.3 013 ESFAS 1

K6.01 Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors 2.7 2

022 Containment Cooling 1

K3.02 Containment equipment subject to damage by high or low temperature, humidity, and pressure Containment instrumentation 3.0 1

026 Containment Spray 1

A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment temperature 3.6 026 Containment Spray 1

K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems:

ECCS 4.2 2

PVNGS NRC License Examination July 2001 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO)

PVNGS Form ES-401-2 Page 6 System #/Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Number K/A Topics Imp.

RO SRO 039 Main and Reheat Steam 1

A3.02 Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS 3.1 1

056 Condensate 1

A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those mal-functions or operations: Loss of condensate pumps 2.6 1

059 Main Feedwater 1

K3.04 Knowledge of the effect that a loss or malfunction of the MFW will have on the following: RCS 3.6 059 Main Feedwater 1

K4.02 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic turbine/reactor trip runback 3.3 2

061 Auxiliary Feedwater 1

K4.14 Knowledge of AFW design feature(s) and/or interlock(s) which provide for the following: AFW automatic isolation 3.5 1

062 AC Electrical Distribution 1

K2.01 Knowledge of bus power supplies to the following:

Major system loads.

3.3 1

062 AC Electrical Distribution 1

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Causes and significance of grounds (43.5) 2.6 1

063 DC Electrical Distribution 1

A1.01 Ability to predict and/or monitor changes in parameters associated with operating the dc electrical system controls including: Battery capacity as it is affected by discharge rate 2.5 1

063 DC Electrical Distribution 1

2.2.3 (multi-unit) Knowledge of the design, procedural, and operational differences between units. (43.5) 3.3 1

064 Emergency Diesel Generator 1

K4.02 Knowledge of ED/G system design feature(s) and/or inter-lock(s) which provide for the following: Trips for ED/G while operating (normal or emergency) 3.9 1

073 Process Radiation Monitoring 1

K5.03 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits 2.9 1

076 Service Water 1

A4.01 Ability to manually operate and/or monitor in the control room: SWS pumps 2.9 076 Service Water 1

K1.05 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems:

D/G 3.8 2

078 Instrument Air 1

A3.01 Ability to monitor automatic operation of the IAS, including:

Air Pressure 3.1 1

PVNGS NRC License Examination July 2001 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO)

PVNGS Form ES-401-2 Page 7 System #/Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Number K/A Topics Imp.

RO SRO 078 Instrument Air 1

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions (43.5) 2.9 1

103 Containment 1

2.3.11 Ability to control radiation releases 2.7 103 Containment 1

K3.02 Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under normal operations 3.8 2

K/A Category Point totals 3

3 3

3 2

2 3

5 3

2 3

Group Point Total 28 4

PVNGS NRC License Examination July 18, 2001 PWR Examination outline Plant Systems - Tier 2 Group 2 (RO/SRO)

PVNGS Form ES-401-2 Page 8 System #/Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Number K/A Topics Imp.

RO SRO 001 Control Rod Drive 1

K5.02 Knowledge of the following operational implications as they apply to the CRDS: Definitions of differential rod worth and integral rod worth; their applications 2.9 1

002 Reactor Coolant 1

A4.03 Ability to manually operate and/or monitor in the control room: Indications and controls necessary to recognize and correct saturation conditions 4.3 1

011 Pressurizer Level Control 1

2.1.32 Ability to explain and apply all system limits and precautions 3.4 1

014 Rod Position Indication 1

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Dropped rod 4.1 1

015 Nuclear Instrumentation 1

A3.04 Ability to monitor automatic operation of the NIS, including: Maximum disagreement allowed between channels 3.3 1

016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor 1

A4.02 Ability to manually operate and/or monitor in the control room:

Temperature values used to determine RCS/RCP operation during inadequate core cooling (i.e., if applicable, average of five highest values) 3.8 1

027 Containment Iodine Removal 028 H2 Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 1

2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

3.5 1

034 Fuel Handling Equipment 1

A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fuel Handling System operating the controls including: Water level in the Refueling canal 2.9 1

035 Steam Generator 1

A2.06 Ability to (a) predict the impacts of the following mal-functions or operations on the SG; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Small break LOCA 4.6 1

041 Steam Dump/Turbine Bypass Control 1

K4.18 Knowledge of SDS design feature(s) and/or interlock(s) which provide for the following: Turbine trip 3.4 1

045 Main Turbine Generator 055 Condenser Air Removal 068 Liquid Radwaste

PVNGS NRC License Examination July 18, 2001 PWR Examination outline Plant Systems - Tier 2 Group 2 (RO/SRO)

PVNGS Form ES-401-2 Page 9 System #/Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Number K/A Topics Imp.

RO SRO 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 1

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps 2.5 1

079 Station Air 086 Fire Protection 1

K5.03 Knowledge of the operational implication of the following concepts as they apply to the Fire Protection System: Effect of water spray on electrical components 3.1 1

K/A Category Point totals 1 2 1 3 1 2 2 Group Point Total 10 2

PVNGS NRC License Examination July 18, 2003 PWR Examination outline Generic Knowledge and Abilities Outline (Tier 3)

PVNGS Form ES-401-3 Page 10 RO SRO-Only Category K/A #

Topic Imp.

Imp.

2.1.11 Knowledge of less than one hour technical specification action statements for systems 3.0 1

2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation 3.9 1

2.1.1 Knowledge of conduct of operations requirements 3.8 1

2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions 4.3 1

1.

Conduct of Operations Subtotal 2

2 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity 3.7 1

2.2.12 Knowledge of surveillance procedures 3.0 1

2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

3.5 1

2.2.13 Knowledge of tagging and clearance procedures.

3.8 1

2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations.

3.6 1

2.

Equipment Control Subtotal 3

2 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements 2.6 1

2.3.9 Knowledge of the process for performing a containment purge 2.5 1

2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized 3.1 1

3.

Radiation Control Subtotal 2

1 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

2.9 1

2.4.18 Knowledge of the specific bases for EOPs.

2.7 1

2.4.48 Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions 3.5 1

2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures 4.3 1

2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage 3.3 1

4.

Emergency Procedures

/ Plan Subtotal 3

2 Tier 3 Point Total 10 7

Appendix D Scenario Outline Form ES-D-1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9 Facility: PVNGS Scenario No.:

1 Op-Test No:

2003 Examiners:

Operators:

Initial Conditions: IC #16, 50% power, MOC.

Turnover: The following equipment is out of service: HPSI pump A (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ); PW pump A (20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months );

DG A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ). MFP B has been started and is ready to be placed in service to support increasing plant power to 100%.

Event No.

Malf. No.

Event Type*

Event Description 1

N (CO)

Place B MFP in service (CRS to direct and CO to perform) 2 R (ALL) Power increase (CRS to direct and RO/CO to coordinate and perform) 3 TR01:MTNP T11A 100 I (CO)

TLI instrument fails high (CO to diagnose and perform actions and CRS to direct actions and refer to Tech Specs).

4 CV03A C (RO)

CHN-UV-110P Flow control valve fails closed causing a loss of letdown (RO to diagnose and perform actions and CRS to direct recovery) 5 RD02A RD02G C (ALL) CEA drops into core Five minutes later a second CEA drops into core (RO to diagnose and CRS to direct reactor trip) 6 ATWS C (ALL) Reactor Protection system failure to open Reactor Trip Switchgear breakers (PRA Significant)

(Crew to diagnose and take action and CRS to Direct response)

(Critical Task to trip reactor by opening L03 and L10) 7 RV02:SGEP SV554 M

(ALL)

Main steam safety valve on #2 SG fails open (after reactor trip EOP is entered)

(Crew to diagnose and take actions and CRS to diagnose ESD and direct stabilization).

(Critical task to stop feeding and steaming #2 SG)

(Critical Task to control RCS parameters to prevent lifting Pressurizer Safeties)

End point Crew stabilizes heat removal on #1 SG

Appendix D Scenario Outline Form ES-D-1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9 Facility: PVNGS Scenario No.:

2 Op-Test No:

2003 Examiners:

Operators:

Initial Conditions: IC #20, 100% power, MOC.

Turnover: The following equipment is out of service: HPSI pump A (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ); PW pump A (20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months );

DG A has just completed a surveillance test run and is to be shutdown and placed in standby.

Event No.

Malf. No.

Event Type*

Event Description 1

N (CO)

Remove DG A from service (CRS to direct and CO to perform) 2 DG01 C (CO)

DG A trips when control switch is taken to stop (CO to diagnose and perform actions and CRS to refer to Tech Specs) 3 MC01A R (ALL) Condenser vacuum degrades requiring downpower (CO to diagnose and perform actions and CRS to direct stabilization) 4 TR01:CHNL V227 0 I (RO)

VCT level instrument fails low (RO to diagnose and perform actions and CRS to direct recovery) 5 ED03 C

(ALL)

Grid frequency oscillates and results in a Loss of Offsite power (Crew to diagnose and perform actions and CRS to direct actions) 6 RD03A/B C (RO)

Two CEAs fail to fully insert (RO to diagnose and perform actions and CRS to direct boration)

(Critical Task to establish boration to meet safety function requirements prior to completion of the SPTAs) 7 FW21B C

(CO)

Loss of Feedwater (CO to diagnose and perform actions and CRS to direct recovery) 8 FW22 M

(ALL)

Loss of All Feedwater (Crew/CRS to diagnose and CRS to direct transition to FRP) 9 Crew transitions to FRP and cross ties PBB-S04 to PBA-S03 (PRA Significant)

(CO to perform actions and CRS to diagnose and direct actions)

(Critical Task to establish feedwater to a SG)

End point Crew stabilizes plant with AFN feeding at least one SG.

Appendix D Scenario Outline Form ES-D-1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9 Facility: PVNGS Scenario No.:

3 Op-Test No:

2003 Examiners:

Operators:

Initial Conditions: IC #20, 100% power, MOC.

Turnover: The following equipment is out of service: HPSI pump A (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ); PW pump A (20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ); DG A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ). A leak in A low pressure feedwater heater string requires a downpower to 80%.

Event No.

Malf. No.

Event Type*

Event Description 1

R (All)

Downpower to 80% power.

(CRS to direct and RO/CO to coordinate and perform) 2 CV14A I

(RO)

Pressurizer Level Instrument 110X fails low (RO to diagnose and perform actions and CRS to direct and addresses Technical Specifications) 3 TC13 C

(All)

Turbine Trip/ Load Reject/Reactor Power Cutback (Crew to diagnose and perform actions and CRS to direct stabilization) 4 RD11B C

(All)

Control rods continue to insert/Manual Reactor Trip (Crew to diagnose and perform actions and CRS to direct reactor trip) 5 TR01:

SGNPT1024 I

(CO)

Steam bypass control system instrument failure (CO to diagnose and perform actions and CRS to direct stabilization)

(Critical Task to control RCS parameters to prevent lifting Pressurizer Safeties) 6 ED02 M

(All)

Loss of Off-Site Power on Reactor Trip (Crew to diagnose and CRS to direct actions)

(Critical Task to establish feed to S/Gs for level control) 7 EG06B C

(CO)

B DG Fails (PRA Significant)

(CO to diagnose and CRS to direct transition to Blackout)

End point CRS directs powering PBA-S03 with gas turbine generator

Items related to PRA at Palo Verde pertaining to the July 2003 examinations.

Written Category #

System/Event K / A Question Description 037 SG tube leak 2.4.7 EOP mitigation strategies 051 Loss of Condenser Vacuum AA2.02 Rx or Turbine Trip criteria 055 Station Blackout 2.4.4 Entry level conditions 054 Loss of Feedwater EA2.2 Procedure requirements on LOFW 058 Loss of DC Power 2.1.20 Execute procedure steps 056 Loss of Offsite Power AK3.01 Load sequencer operation 061 Auxiliary Feedwater K4.14 AFW Automatic Isolation 064 Emergency Diesel Generator K5.02 EDG Trip signals while operating 062 AC Electrical Distribution K2.01 Major system loads lost 062 AC Electrical Distribution A2.02 Causes & significance of grounds 013 ESFAS 2.4.20 EOP warnings, cautions, & notes 013 ESFAS K6.01 Effect of loss on sensors & detectors 009 Small Break LOCA EK3.03 Rx Trip and safety initiation 011 Large Break LOCA EK2.02 LOCA and pump response Walkthrough Item Number Description JPM JP1 Remote operation of Auxiliary Feedwater Pump JP3 DG operation for CR Fire Scenario/Event Scenario #

Event 1

ATWS 2

LOAF

Sample Plan Methodology General

Description:

Palo Verde uses a Microsoft Access database developed to randomly generate a sample plan in accordance with NUREG 1021 section 401 for the RO and SRO written exam. All selected KAs are greater than or equal to 2.5 importance rating.

The following uses the terminology of Exam Coordinator for the person writing the exam and the terminology program as the Microsoft Access database program. The term KA is a knowledge or ability from the NUREG 1122 and the term EPE/APE is the Emergency Plant Evolution or Abnormal Plant Evolution.

Description of Microsoft Access program query process:

Tables are built to identify the associated systems and EPEs/APEs for each tier and group. Systems and EPE/APEs that do not apply to our facility are excluded form the possible selection (ie; Ice Condenser, Westinghouse and B&W EPE/APEs).

Queries are run to create a pool of possible systems for a given tier-group. The pool of items is automatically numbered sequentially and then a random function picks one of the integers between 1 and the maximum sequential number in the pool. The selected system is appended to another query that retrieves and makes a pool of all the available KAs for that system with KA important ratings greater than or equal to 2.5.

The pool of KAs is again automatically sequentially numbered and then a random function picks one of the KAs from the pool.

The selected KA is appended to the final sample plan table.

The selected system APE/EPE is excluded from future selections until each system has at least one KA selected for the tier group. If a tier-group needs more items than the number of systems available for selection than subsequent selections are made with all the systems in the group.

Any KA appended to the final sample plan table is excluded from the further selection within the tier group.

This process is repeated until there is adequate number of items for each tier-group. The process is done again for the next tier-group.

Included in the pool of available KAs for each system is a placeholder for possible selection of a generic KA for a given system. This enables the program to include a random selection of a generic KAs to be targeted for a system within each tier-group.

Generic KAs for tier 3 are randomly selected from the entire pool of generic KAs that have importance rating greater than or equal to 2.5.

The final table provides a report that shows a matrix of the number of KAs in each tier-group described in ES401-2. It also shows if any column for each tier contains less than the required minimum (2) items for each of K1, K2, K3, K4, K5, K6, A1, A2, A3, A4, G as applicable for the RO Outline.

The subsequent pages of the report list all the selected KAs organized by tier-group listing System-APE/EPE Name, KA#, the KA Text from the 1122 catalog and the Importance Rating in a table format to support the ES401-2 Outline.

How items are removed, replaced, or eliminated:

When an item needs to be replaced to meet the matrix requirements for each tier-group and column, the exam coordinator manually selects the item to be removed and then runs the random selection process to pick a replacement.

KAs are eliminated based on the guidance stated in Attachment 2 of ES-401 and are listed on form ES-401-4.

How the Generic KAs for the selected system and EPEs/APEs within the tier-groups are identified:

The above-described process selects which system and EPE/APE will be tagged with a generic KA to fulfill the matrix. Then the program is ran to randomly select a generic KA from section 2 of NUREG 1122 with KA importance rating > 2.5. The exam coordinator chooses the first generic KA randomly selected that is applicable to the system/APE/EPE.

ML041050302

Text

Description:

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