ML103400362

PV-2010-11-Final Outlines

ML103400362
Person / Time
Site:	Palo Verde
Issue date:	11/05/2010
From:	Brian Larson Operations Branch IV
To:	Arizona Public Service Co
References
Download: ML103400362 (26)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ______Palo Verde_____________________ Date of Examination: Nov. 8-12, 2010 Examination Level: RO X SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

Shutdown Margin Calculation Conduct of Operations R, M K/A 2.1.37 RO 4.3 SRO 4.6 A-1 K/A 2.1.20 RO 4.6 SRO 4.6 Complete PDIL entry logs for the Regulating Group and Conduct of Operations R,D Part Strength CEAs A-2 K/A 2.1.18 RO 3.6 SRO 3.8 Perform 40ST-9RC08, Backup RCS leakrate calculation Equipment Control R,N K/A 2.2.12 RO 3.7 SRO 4.1 A-3 R,N Perform RCA Tasks Radiation Control K/A 2.3.13 RO 3.4 SRO 3.8 A-4 Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Rev 2

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ______Palo Verde_____________________ Date of Examination: Nov. 8-12, 2010 Examination Level: RO SRO X Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

Review a Shutdown Margin Calculation, identify errors Conduct of Operations R, M and determine required action(s)

A-5 K/A 2.1.37 RO 4.3 SRO 4.6 Determine if shift manning meets requirements of Tech Conduct of Operations R,N Specs and Station procedures A-6 K/A 2.1.5 RO2.9 SRO 3.9 Determine status of Main Steam Safety valves (LCO)

Equipment Control R,D and any required actions.

A-7 K/A 2.2.22 RO 4.0 SRO 4.7 Determine dose, hold points and permission to exceed R,P Radiation Control those hold points.

A-8 K/A 2.3.4 RO 3.2 SRO 3.7 Classify an event Emergency Procedures/Plan R, N K/A 2.4.41 RO 2.9 SRO 4.6 A-9 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Rev 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _____Palo Verde________________________ Date of Examination: Nov. 8-12, 2010 Exam Level: RO X SRO-I SRO-U Operating Test No.: ______________

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function JS-1 Respond to a Steam Generator Tube Leak (K/A 4.2.037 S,N 4S AA1.13 RO 3.9 SRO 4.0)

JS-2 Perform a Boration of the RCS (K/A 3.1 004 A4.01 RO 3.8 S,A,D 1 SRO 3.9)

JS-3 Implement LOCA instructions and contingencies (K/A 3.2 006 S,L,N,A,EN 2 A3.08 RO 4.2 SRO 4.3)

JS-4 Perform a BDAS Alarm check (K/A 3.7.015.A3.03 RO 3.9 S, D,L 5 SRO 3.9)

JS-5. Implement SGTR instructions and contingencies (K/A 4.2 037 S,D,A,L,P 4P AK3.07 RO 4.2 SRO 4.1)

JS-6. Restore Containment Cooling following inadvertent SIAS (K/A S,D, L 7 3.5.022-A4.01 RO 3.6 SRO 3.6)

JS-7 Perform Diesel Generator Test (K/A 3.6 064 A4.01 RO 4.0 S, N 6 SRO 4.3)

JS-8 Operate the Pressurizer Pressure Control System (K/A S,D,P 3 4.2.027.A1.01 RO 4.0 SRO 3.9)

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

JP-1 Perform Event Control Actions for a Control Room Fire (K/A A,M,E 6 4.2.068.AA1.10 RO 3.7 SRO 3.9)

JP-2 Respond to a Control Room Fire (K/A 4.2 026 AA1.03 RO 3.6 R, N, E 8 SRO 3.6)

JP-3 Perform Actions per 40AO-9ZZ24, Deliberate Acts against N, E, A 4S PVNGS (K/A 3.4 061 A2.05 RO 3.1 SRO 3.4)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U Rev 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _____Palo Verde________________________ Date of Examination: Nov. 8-12, 2010 Exam Level: RO SRO-I X SRO-U Operating Test No.: ______________

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function JS-1 Respond to a Steam Generator Tube Leak (K/A 4.2.037 S,N 4S AA1.13 RO 3.9 SRO 4.0)

JS-2 Perform a Boration of the RCS (K/A 3.1 004 A4.01 RO 3.8 S,A,D 1 SRO 3.9)

JS-3 Implement LOCA instructions and contingencies (K/A 3.2 006 S,L,N,A,EN 2 A3.08 RO 4.2 SRO 4.3)

JS-4 Perform a BDAS Alarm check (K/A 3.7.015.A3.03 RO 3.9 S, D,L 5 SRO 3.9)

JS-5. Implement SGTR instructions and contingencies (K/A 4.2 037 S,D,A,L,P 4P AK3.07 RO 4.2 SRO 4.1)

JS-6. Restore Containment Cooling following inadvertent SIAS (K/A S,D, L 7 3.5.022-A4.01 RO 3.6 SRO 3.6)

JS-7 Perform Diesel Generator Test (K/A 3.6 064 A4.01 RO 4.0 S, N 6 SRO 4.3)

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

JP-1 Perform Event Control Actions for a Control Room Fire (K/A A,M,E 6 4.2.068.AA1.10 RO 3.7 SRO 3.9)

JP-2 Respond to a Control Room Fire (K/A 4.2 026 AA1.03 RO 3.6 R, N, E 8 SRO 3.6)

JP-3 Perform Actions per 40AO-9ZZ24, Deliberate Acts against N, E, A 4S PVNGS (K/A 3.4 061 A2.05 RO 3.1 SRO 3.4)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U Rev 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _____Palo Verde________________________ Date of Examination: Nov. 8-12, 2010 Exam Level: RO SRO-I SRO-U X Operating Test No.: ______________

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function JS-1 Respond to a Steam Generator Tube Leak (K/A 4.2.037 S,N 4S AA1.13 RO 3.9 SRO 4.0)

JS-2 Perform a Boration of the RCS (K/A 3.1 004 A4.01 RO 3.8 S,A,D 1 SRO 3.9)

JS-3 Implement LOCA instructions and contingencies (K/A 3.2 006 S,L,N,A,EN 2 A3.08 RO 4.2 SRO 4.3)

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

JP-1 Perform Event Control Actions for a Control Room Fire (K/A A,M,E 6 4.2.068.AA1.10 RO 3.7 SRO 3.9)

JP-2 Respond to a Control Room Fire (K/A 4.2 026 AA1.03 RO 3.6 R, N, E 8 SRO 3.6)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U Rev 2

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __1 Op-Test No: 2010 Examiners: Operators:

Initial Conditions: IC-101 (2% power, MOC).

Turnover: Unit 1 is at 2% power (250 EFPD) following a Short notice outage of 5 days. Power is being held steady while waiting for the Mode 2 to 1 Mode Change checklist to be completed.

Event Malf. No. Event Type* Event Description No.

1 Imf C Charging Header DP controller fails in the AUTO mode cmCNCV01CHEPDIC240_2 RO/SRO 2 Imf mfSB01C I Core Protection Calculator failure CO/SRO (TS) 3 Imf cmTRCV19RCALT110X_4 I RCA-LT-110X Pressurizer level transmitter fails low.

RO/SRO (TS) 4 Imf mfCPTP04TCNP01A_6 C Turbine Cooling Water pump trip (Standby fails to auto start)

(In setup) Imf CO/SRO cmCPTP04TCNP01B_5 (40AO-9ZZ03, Loss of Cooling Water) 5 Imf mfRP06H1 C Inadvertent CSAS Train B Imf mfRP06H2 CO/RO/SRO (40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations)

(TS) 6 Imf cmCNMS19SGNPIC1010_1 SBCV 1001 fails to 100% open. (Trip Initiator)

Imf MS12A 7 (In setup) Imf C B Train AF valve to SG 1 fails to open.

CMMVFW08AFBUV34_6 CO/SRO 8 Imf mfTH01B M Large Break LOCA ALL (40EP-9EO03) 9 Scenario file noSICI C SIAS fails to initiate CO/SRO CRITCAL TASK - Initiate SI flow when the SIAS setpoint has been exceeded.

10 Imf cmMVRH03SIAUV672_6 C CS A header isolation fails to open (B CS pump stopped due to Inadvertent CSAS earlier)

RO/SRO CRITCAL TASK -Initiate CS flow when the CSAS setpoint has been exceeded.

End The scenario will end when CS and SI is established.

point

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 4 Rev 3

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 8

2. Malfunctions after EOP entry (1-2) 4

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 2 NUREG-1021, Revision 9 2 of 4 Rev 3

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __2 Op-Test No: 2010 Examiners: Operators:

Initial Conditions: IC-102 (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). Stator Cooling Pump A is tagged out for schedule maintenance.

Event Malf. No. Event Type* Event Description No.

1 In setup Imf N Pump the RDT, CH-UV-560 fails to close when securing lineup cmAVCV11CHAUV560_4 RO/SRO (TS) 2 Imf mfNI02A I Control Channel Power Instrument #1 fails low affecting the Reactor Regulating System and the Digital Feedwater Control RO/CO/SRO System (40AO-9ZZ16, RRS Malfunctions) 3 Imf cmTRCV05CHNLT227_4 C VCT level transmitter CHN-LT-227 fails low RO/SRO 4 Imf RD02D R - RO Power Reduction due to slipped CEA N - CO/SRO (40AO-9ZZ11, CEA Malfunctions)

(TS) CRITICAL TASK - Commence a power reduction within 10 minutes.

5 Imf RD02J M Twelve Finger CEA slips (ATWS)

Scenario file atws ALL CRITICAL TASK - Ensure SPTA Reactivity control contingency actions are taken 6 Imf ED02 C On the Trip a Loss of Offsite power occurs ALL 7 (In setup) Imf EG05A C SP A fails to auto start RO/SRO 8 Imf EG17 DG A trips on loss of lube oil 9 (In setup) Imf mfFW22 C Turbine Driven Aux Feedwater pump AFA-P01 trips on overspeed and Motor Driven Aux Feedwater pump AFB-P01 Imf FW21B ALL trips on an 86 lockout (40EP-9EO09 Functional Recovery Procedure)

End Restore feed to at least one SG point CRITICAL TASK - Establish a feed source to at least one Steam Generator

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 4 Rev 5

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 9

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 3 2 of 4 Rev 5

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __3 Op-Test No: 2010 Examiners: Operators:

Initial Conditions: IC-103 (100% power, MOC)

Turnover: Unit 1 is at 100% power (250 EFPD). Stator Cooling Pump A is tagged out for schedule maintenance.

Event Malf. No. Event Type* Event Description No.

1 None N Shift Charging Pumps to 2-3-1.

RO/SRO 2 Imf I RCBPDT125B (SG RCS DP Transmitter) fails low mfCMTRRX09RCBPDT125B_

4 CO/SRO (TS) 3 (In setup) imf C Loss of PBB-S04 - DG breaker fails to auto close mfBKEG03PBBS04B_2 RO/SRO (TS)

(40AO-9ZZ12, Degraded Electrical) 4 Imf mfEG04 C Main Generator AC Regulator failure CO/SRO 5 IMF MC01A R - RO Loss of condenser vacuum N- CO/SRO (40AO-9ZZ07, Loss of Vacuum) 6 IMF mfMS01A M Steam Line Leak (ESD) inside containment (Trip Initiator)

ALL (40EP-9EO06, Excess Steam Demand) 7 Scenario file noMSIS C MSIS fails to automatically initiate CO/SRO CRITICAL TASK - Ensure MSIS is actuated when the MSIS setpoint has been exceeded.

8 (In setup) C HPSI A Trips and the B BOP/ESFAS sequencer fails requiring the RO to start all B train pumps Imf mfSI01A RO/SRO CRITICAL TASK - Ensure SI flow when SIAS setpoint has mfRP07B been exceeded 9 Scenario file noDP1SG C SG DP Lockout fails requiring the CO to manually stop feeding the SG that is faulted inside containment.

CO/SRO CRITICAL TASK - Ensure SG isolated when AFAS DP lockout has been exceeded.

End Scenario ends when crew has caught RCS rebound and a HPSI point pump is running

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 4 Rev 2

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 3

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3 NUREG-1021, Revision 9 2 of 4 Rev 2

ES-401 PWR Examination Outline Form ES-401-2 Facility: Palo Verde 5(9

Date Of Exam: 11/05/2010 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 0 0 0 Emergency 2 1 2 2 N/A 1 2 1 9 0 0 0

& N/A Abnormal Tier Plant Totals 4 5 5 4 5 4 27 0 0 0 Evolutions 1 3 2 3 3 2 2 4 3 2 2 2 28 0 0 0 2.

2 1 1 1 1 1 1 1 1 1 1 0 10 0 0 0 0 Plant Systems Tier 0 0 0 4 3 4 4 3 3 5 4 3 3 2 38 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 10 0 Abilities Categories 3 3 2 2 0 0 0 0 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.

REV 2

PWR RO Examination Outline 5(9

Facility: Palo Verde ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X 2.2.40 - Ability to apply Technical 3.4 1 3 Specifications for a system.

000009 Small Break LOCA / 3 X EK3.10 - Observation of PZR level 3.4 1 000011 Large Break LOCA / 3 X EK2.02 - Pumps 2.6* 1 000015/000017 RCP Malfunctions / 4 X 2.4.11 - Knowledge of abnormal 4.0 1 condition procedures.

000022 Loss of Rx Coolant Makeup / 2 X AA2.02 - Charging pump problems 3.2 1 000025 Loss of RHR System / 4 X AA1.22 - Obtaining of water from 2.9* 1 BWST for LPI system 000027 Pressurizer Pressure Control System X AK2.03 - Controllers and positioners 2.6 1 Malfunction / 3 000029 ATWS / 1 X EA1.11 - Manual opening of the CRDS 3.9* 1 breakers 000038 Steam Gen. Tube Rupture / 3 X EA2.01 - When to isolate one or more 4.1 1 S/Gs 000040 Steam Line Rupture - Excessive X 2.4.46 - Ability to verify that the alarms 4.2 1 Heat Transfer / 4 are consistent with the plant conditions.

000055 Station Blackout / 6 X EK1.02 - Natural circulation cooling 4.1 1 000057 Loss of Vital AC Inst. Bus / 6 X AA1.01 - Manual inverter swapping 3.7* 1 000058 Loss of DC Power / 6 X AA2.01 - That a loss of dc power has 3.7 1 occurred; verification that substitute power sources have come on line 000062 Loss of Nuclear Svc Water / 4 X AK3.03 - Guidance actions contained in 4.0 1 EOP for Loss of nuclear service water 000065 Loss of Instrument Air / 8 X AK3.04 - Cross-over to backup air 3.0 1 supplies CE/E02 Reactor Trip - Stabilization - X EK1.2 - Normal, abnormal and 3.0 1 Recovery / 1 emergency operating procedures associated with Reactor Trip or Safety Injection /Rediagnosis CE/E05 Steam Line Rupture - Excessive X EK1.1 - Components, capacity, and 3.0 1 Heat Transfer / 4 function of emergency systems CE/E06 Loss of Main Feedwater / 4 X EK2.1 - Components, and functions of 3.3 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 REV 2

PWR RO Examination Outline REV 2 Facility: Palo Verde ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000003 Dropped Control Rod / 1 X AA2.01 - Rod position indication to 3.7 1 actual rod position 000024 Emergency Boration / 1 X AK1.02 - Relationship between boron 3.6 1 addition and reactor power 000032 Loss of Source Range NI / 7 X AK2.01 - Power supplies, including 2.7* 1 proper switch positions 000051 Loss of Condenser Vacuum / 4 X AK3.01 - Loss of steam dump 2.8* 1 capability upon loss of condenser vacuum 000061 ARM System Alarms / 7 X AK3.02 - Guidance contained in alarm 3.4 1 response for ARM system 000067 Plant Fire On-site / 9 X AA1.08 - Fire fighting equipment used 3.4 1 on each class of fire 000068 Control Room Evac. / 8 X 2.4.6 - Knowledge of EOP mitigation 3.7 1 strategies.

CE/A13 Natural Circ. / 4 X EA2.1 - Facility conditions and 2.7 1 selection of appropriate procedures during abnormal and emergency operations CE/A16 Excess RCS Leakage / 2 X EK2.1 - Components, and functions of 3.2 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Totals: 1 2 2 1 2 1 Group Point Total: 9 REV 2

PWR RO Examination Outline REV 2 Facility: Palo Verde ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K1.04 - CVCS 2.6* 1 004 Chemical and Volume Control X K3.07 - PZR level and 3.8 1 pressure 005 Residual Heat Removal X K6.03 - RHR heat 2.5 1 exchanger 005 Residual Heat Removal X K2.01 - RHR pumps 3.0 1 006 Emergency Core Cooling X A2.12 - Conditions 4.5 1 requiring actuation of ECCS 006 Emergency Core Cooling X K4.06 - Recirculation of 2.7 1 minimum flow through pumps 007 Pressurizer Relief /Quench X A1.01 -Maintaining quench 2.9 1 Tank tank water level within limits 008 Component Cooling Water X K3.01 - Loads cooled by 3.4 1 CCWS 008 Component Cooling Water X A2.04 - PRMS alarm 3.3 1 010 Pressurizer Pressure Control X A4.02 - PZR heaters 3.6 1 010 Pressurizer Pressure Control X K4.03 - Over pressure 3.8 1 control 012 Reactor Protection X K5.02 - Power density 3.1* 1 013 Engineered Safety Features X K2.01 -ESFAS/safeguards 3.6* 1 Actuation equipment control 013 Engineered Safety Features X A3.02 - Operation of 4.1 1 Actuation actuated equipment 022 Containment Cooling X A1.04 - Cooling water flow 3.2 1 026 Containment Spray X A2.04 - Failure of spray 3.9 1 pump 039 Main and Reheat Steam X K1.02 - Atmospheric relief 3.3 1 dump valves 039 Main and Reheat Steam X 2.4.46 - Ability to verify that 4.2 1 the alarms are consistent with the plant conditions.

059 Main Feedwater X K3.04 - RCS 3.6 1 059 Main Feedwater X A1.03 - Power level 2.7* 1 restrictions for operation of MFW pumps and valves 061 Auxiliary/Emergency X K4.06 - AFW startup 4.0* 1 Feedwater permissives 062 AC Electrical Distribution X A1.01 - Significance of D/G 3.4 1 load limits 063 DC Electrical Distribution X 2.4.34 - Knowledge of RO 4.2 1 tasks performed outside the main control room during an emergency and the resultant operational effects.

REV 2

PWR RO Examination Outline REV 2 Facility: Palo Verde ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 064 Emergency Diesel Generator X K6.08 - Fuel oil storage 3.2 1 tanks 073 Process Radiation Monitoring X K5.03 - Relationship 2.9* 1 between radiation intensity and exposure limits 076 Service Water X A4.01 - SWS pumps 2.9 1 078 Instrument Air X A3.01 - Air pressure 3.1 1 103 Containment X K1.02 - Containment 3.9 1 isolation/containment integrity K/A Category Totals: 3 2 3 3 2 2 4 3 2 2 2 Group Point Total: 28 REV 2

PWR RO Examination Outline REV 2 Facility: Palo Verde ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 002 Reactor Coolant X K6.02 - RCP 3.6 1 015 Nuclear Instrumentation X A4.03 - Trip bypasses 3.8 1 017 In-core Temperature Monitor X K1.01 - Plant computer 3.2* 1 028 Hydrogen Recombiner and X K2.01 -Hydrogen 2.5* 1 Purge Control recombiners 033 Spent Fuel Pool Cooling X A1.01 - Spent fuel pool 2.7 1 water level 035 Steam Generator X A3.01 - S/G water level 4.0 1 control 041 Steam Dump/Turbine Bypass X A2.02 - Steam valve stuck 3.6 1 Control open 055 Condenser Air Removal X K3.01 - Main condenser 2.5 1 071 Waste Gas Disposal X K5.04 - Relationship of 2.5 1 hydrogen/oxygen concentrations to flammability 075 Circulating Water X K4.01 - Heat sink 2.5 1 K/A Category Totals: 1 1 1 1 1 1 1 1 1 1 0 Group Point Total: 10 REV 2

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline 5(9

Facility: Palo Verde Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.15 Knowledge of administrative requirements for 2.7 1 temporary management directives, such as standing orders, night orders, Operations memos, etc.

2.1.25 Ability to interpret reference materials, such as 3.9 1 graphs, curves, tables, etc.

2.1.30 Ability to locate and operate components, 4.4 1 including local controls.

Category Total: 3 Equipment Control 2.2.1 Ability to perform pre-startup procedures for the 4.5 1 facility, including operating those controls associated with plant equipment that could affect reactivity.

2.2.22 Knowledge of limiting conditions for operations 4.0 1 and safety limits.

2.2.39 Knowledge of less than or equal to one hour 3.9 1 Technical Specification action statements for systems.

Category Total: 3 Radiation Control 2.3.5 Ability to use radiation monitoring systems, such 2.9 1 as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

2.3.14 Knowledge of radiation or contamination hazards 3.4 1 that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 2 Emergency Procedures/Plan 2.4.3 Ability to identify post-accident instrumentation. 3.7 1 2.4.37 Knowledge of the lines of authority during 3.0 1 implementation of the emergency plan.

Category Total: 2 Generic Total: 10 REV 2

Rev 2 PVNGS License Examination Record of Rejected K/As Exam Date 11/05/10 PVNGS Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/As RO Exam 1/1 2.1.45 Not on ES-401 4.D.1.b paragraph for acceptable generic T1 or T2 generic KAs. Replaced with 2.1.27.

2/1 2.2.41 Not on ES-401 4.D.1.b paragraph for acceptable generic T1 or T2 generic KAs. Replaced with 2.4.34.

2/1 022 A2.05 Could not write a psychometrically correct question. Replaced with 022 A1.04 1/2 005 AK1.06 Tech Spec Basis is SRO level. Replaced with 003 AA2.01 1/2 036 AK2.01 Fuel Handling at PVNGS is SRO/LSRO Knowledge. Replaced with 032 AK2.01 1/2 2.2.25 Tech Spec Basis is SRO level. Replaced with CE/A EK2.1 1/1 2.1.27 T1 Generic does not relate with the system. Replaced with 2.2.40 2/1 025 K5.02 Ice Condensers not installed at PVNGS. Replaced with 026 A2.04 2/1 012 A4.07 Similar to another question on RO exam. Replaced with 010 A4.02 2/1 2.2.42 Similar to another question on SRO exam. Replaced with 2.4.46 2/1 059 K3.02 Similar to another question on RO exam. Replaced with 061 A4.06 2/1 2.1.19 T1 Generic does not relate with the system. Replaced with 059 A1.03 2/1 063 K3.01 Similar to another question on SRO exam. Replaced with 059 K3.04 2/1 103 A2.05 PVNGS does not have and Emergency CTMT Entry procedure.

Replaced with 103 K1.02 2/2 072 K3.02 Similar to another question on RO exam. Replaced with 055 K3.01 2/2 014 A1.04 RPIS does not relate to PD. Replaced with 033 A1.01 2/2 068 K5.03 No operational implications. Replaced with 071 K5.04 3 2.4.30 Off site notifications is SRO level. Replaced with2.1.25 1/1 2.4.31 SRO Level per NRC Comment. Replaced with 2.4.46

ES-401 PWR Examination Outline Form ES-401-2 Facility: Palo Verde REV 2 Date Of Exam: 11/05/2010 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 N/A 0 0 0 0 2 2 4

& N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 3 Plant Systems Tier 5 3 8 0 0 0 0 0 0 0 0 0 0 0 0 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 2 1 2 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.

REV 2

PWR SRO Examination Outline REV 2 Facility: Palo Verde ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000009 Small Break LOCA / 3 X 2.2.44 - Ability to interpret control 4.4 1 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

000015/000017 RCP Malfunctions / 4 X AA2.10 - When to secure RCPs on loss 3.7 1 of cooling or seal injection 000056 Loss of Off-site Power / 6 X 2.2.44 - Ability to interpret control 4.4 1 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

000058 Loss of DC Power / 6 X 2.1.20 - Ability to interpret and execute 4.6 1 procedure steps.

CE/E02 Reactor Trip - Stabilization - X EA2.1 - Facility conditions and 3.7 1 Recovery / 1 selection of appropriate procedures during abnormal and emergency operations CE/E05 Steam Line Rupture - Excessive X EA2.1 - Facility conditions and 4.0 1 Heat Transfer / 4 selection of appropriate procedures during abnormal and emergency operations K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 REV 2

PWR SRO Examination Outline 5(9

Facility: Palo Verde ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000028 Pressurizer Level Malfunction / 2 X AA2.10 - Whether the automatic mode 3.4 1 for PZR level control is functioning improperly, necessity of shift to manual modes 000037 Steam Generator Tube Leak / 3 X 2.4.30 - Knowledge of events related to 4.1 1 system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

000069 Loss of CTMT Integrity / 5 X 2.4.46 - Ability to verify that the alarms 4.2 1 are consistent with the plant conditions.

000074 Inad. Core Cooling / 4 X EA2.02 - Availability of main or 4.6 1 auxiliary feedwater K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 REV 2

PWR SRO Examination Outline REV 2 Facility: Palo Verde ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 004 Chemical and Volume Control X A2.06 - Inadvertent 4.3 1 boration/dilution 013 Engineered Safety Features X A2.03 - Rapid 4.7 1 Actuation depressurization 039 Main and Reheat Steam X A2.05 - Increasing steam 3.6 1 demand, its relationship to increases in reactor power 059 Main Feedwater X 2.4.4 - Ability to recognize 4.7 1 abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

073 Process Radiation Monitoring X 2.2.40 - Ability to apply 4.7 1 Technical Specifications for a system.

K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 REV 2

PWR SRO Examination Outline REV 2 Facility: Palo Verde ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 002 Reactor Coolant X 2.4.41 - Knowledge of the 4.6 1 emergency action level thresholds and classifications.

002 Reactor Coolant X A2.03 - Loss of forced 4.3 1 circulation 056 Condensate X A2.05 - Condenser tube 2.5* 1 leakage K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 REV 2

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline REV 2 Facility: Palo Verde Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, 3.9 1 such as minimum crew complement, overtime limitations, etc.

2.1.14 Knowledge of criteria or conditions that require 3.1 1 plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Category Total: 2 Equipment Control 2.2.6 Knowledge of the process for making changes to 3.6 1 procedures.

Category Total: 1 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.7 1 normal or emergency conditions.

2.3.11 Ability to control radiation releases. 4.3 1 Category Total: 2 Emergency Procedures/Plan 2.4.6 Knowledge of EOP mitigation strategies. 4.7 1 2.4.8 Knowledge of how abnormal operating 4.5 1 procedures are used in conjunction with EOPs.

Category Total: 2 Generic Total: 7 REV 2

Rev 2 PVNGS License Examination Record of Rejected K/As Exam Date 11/05/10 PVNGS Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/As SRO Exam 1/1 4.2 062 AA2.04 PVNGS Loss of Cooling Water Procedure does not address temperatures, it only addresses flow. Replaced with 4.2 015 AA2.01 2/2 2.4.28 PVNGS does not have a CTMT Iodine Removal system.

Replaced with 2.2.21 1/1 015 AA2.01 AOP does not apply to cause of RCP failure. Replaced with 015 AA2.10 1/1 027 AA2.02 Normal Values of RCS not SRO level. Replaced withCE/E05 EA2.1 1/1 2.2.23 Not in Generic T1 ES 401 list. Replaced with 2.2.44 2/1 005 AA2.01 Stuck or Inop rod actions not SRO level. Replaced with 051 AA2.02 2/1 2.1.6 Not in Generic T2 ES 401 list. Replaced with 2.4.46 1/2 2.3.5 Not in Generic T1 ES 401 list. Replaced with 2.4.30 2/2 2.2.21 Not in Generic T2 ES 401 list. Replaced with 2.4.41 2/2 001 A2.13 Not SRO level. Replaced with 056 A2.05 2/1 2.4.44 Not SRO level. Replaced with 2.2.40 3 2.3.15 Trouble writing SRO level question. Replaced with 2.3.4 Rev 1