Text

DC-2009-02-Draft Outlines
	ML090790307
Person / Time
Site:	Diablo Canyon
Issue date:	02/06/2009
From:	Brian Larson; Operations Branch IV
To:	;
References
	Download: ML090790307 (26)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Diablo Canyon Facility: _______________________________ 02/09/09 Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________L061C Administrative Topic Type Describe activity to be performed (see Note) Code*

Determination of SFP Heat Load Removal Parameters (LJACO-01R)

Conduct of Operations D, R G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation. (4.4)

Review Outage Safety Checklist (NRC ADM02SRO - L031)

Conduct of Operations D, R G2.1.40 - Knowledge of refueling administrative requirements. (3.9)

Verify AFD is within Tech Spec Limits (LJAEC - 11S)

Equipment Control D, R G2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (4.6)

Review Liquid Radwaste Discharge checklist N, R G2.3.6 - Ability to approve release permits. (3.8)

Radiation Control Offsite Dose Assessment and classification - FHB Accident (LJC-166)

D, R l Emergency Procedures/Plan G2.4.41 - Knowledge of the emergency action level thresholds and classifications. (4.6)

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

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (# 3 for ROs; # 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ($ 1)

(P)revious 2 exams (# 1; randomly selected)

ES-301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Diablo Canyon Facility: _____________________________ 02/09/09 Date of Examination: ______________

Exam Level: RO SRO-I SRO-U L061C 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

a. S1 - 004/Isolate VCT Rupture (LJC-005) M,A,E,S 02

b. S2 - 010/Respond to PT-456 failed high (LJC-143) D,S 03

c. S3 - 005/Isolate LOCA outside containment (LJC-118) D,A,E,S 04p

d. S4 - 103/Manually isolate CVI components N,A,E,S 05

e. S5 - 008/Loss of CCW to one RCP (L031 NRC test) D,A,E,S 08

f. S6 - 041/RCS cooldown for SGTR (LJC-090) D,A,E,S 04s

g. S7 - 073/Verify RM-44A OPERABLE N,S 07 h.

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

i. P1 - 062/Transfer pressurizer heater group 12 to backup (LJP-029) D,L,E 06

j. P2 - 004/Align CCP suction to RWST (LJP-207, modified for Unit 2) M,E,L,R 02

k. P3 - 012/De-energize SSPS to block SI (LJP-09S) D,L 07

@ 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 l (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank #9/#8/#4 (E)mergency or abnormal in-plant $1/$1/$1 (EN)gineered safety feature - / - / $1 (control room system) l (L)ow-Power / Shutdown $1/$1/$1 (N)ew or (M)odified from bank including 1(A) $2/$2/$1 (P)revious 2 exams # 3 / # 3 / # 2 (randomly selected)

(R)CA $1/$1/$1 (S)imulator ES-301, Page 23 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Date of Exam: Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

M C S A B S A B S A B S A B L U A T R T O R T O R T O R T O M(*)

N Y O C P O C P O C P O C P R I U T P E

RO RX 2 1 1 1 0 NOR 3 1 1 1 1 SRO-I I/C 3,4, 5 1-3,6 3,4,7,8 11 4 4 2 SRO-U MAJ 7 4 6 3 2 2 1 TS 3,4 2 0 2 2 RO RX 2 1 1 1 0 NOR 1 3 2 1 1 1 SRO-I I/C 3,4,5 1,2,5 1,3-5 10 4 4 2 SRO-U MAJ 7 4 6 3 2 2 1 TS 3,4 2 0 2 2 RO RX 2 1 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 3,4,5 1,2,3 1,3,5 9 4 4 2 SRO-U MAJ 7 4 6 3 2 2 1 TS 1,3 2 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 1 Op-Test No.: L061C-1 Examiners: Operators:

Initial Conditions: 100% Reactor power, BOL, Boron at 1182 ppm CFCU 1-2 cleared.

Turnover: High Swell warning is expected in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ODM has decided to ramp both units to 25% power at 3 MW/min. OP O-28 actions are complete. OP L-4 preparations are done, at step 6.3.3.m. Turn Pzr Backup heaters on and commence ramp.

Event Malf. No. Event Event Description and Time Line No. Type*

1 N Turn Pzr Backup Heaters ON.

2 R Ramp unit to 25% power.

3 Xmt rcs15 I Loop 1 narrow range Tcold fails high and causes rods to step in. (TS 3.3.1.E & X and 3.3.2.M) 4 Pmp ven C CFCU 11 overcurrent trip. (TS 3.6.6.C )

5 Cnv mfw6 C FCV-540 FW reg valve to S/G 14 fails open 6 mal tur1 C No Automatic turbine trip, must trip manually. (CT) 7 mal rcs3a M Small break LOCA (4) 3 minutes after turbine trip. Will require RCP Trip criteria.(CT) 8 Mal eps C 4KV Bus G differential trip on Safety Injection.

9 pmp cvc1 C Charging pump 11 doesnt auto start. (CT)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 1.doc Rev. 0

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 2 Op-Test No.: L061C-2 Examiners: Operators:

Initial Conditions: 75% Reactor power, MOL, Boron at 848 ppm ASW pp 12 cleared.

Turnover:

Event Malf. No. Event Event Description and Time Line No. Type*

1 Vlv pzr5 C PCV-456 Pzr PORV fails open, must isolate using block valve. (TS 3.4.11 )

(CT) 2 Mal R - CO Ramp unit to 50% power due to FWP 11 high vibration.

mfw2a C - BO 3 Xmt mfw37 I LT-459 Pzr level channel fails to 10% (TS 3.3.1.M, 3.3.3.F, 3.3.4)

N - CO Restores letdown flow.

N -BOP 4 Mal rcs4c M S/G 13 tube leak ramps to 400 gpm (CT) 5 Pmp asw1 C ASW pp 11 trips on overcurrent on reactor trip, requires x-tie with U-2. (CT) 6 Cnv mss C PCV-21 fails open after RCS cooldown complete. Transition to ECA 3.1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 2.doc Rev. 0

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 3 Op-Test No.: L061C-3 Examiners: Operators:

Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover: PRA Status: Yellow. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. RHR pp 11 is cleared for seal repair. U-2 at 100% power.

Event Malf. No. Event Event Description and Time Line No. Type*

1 mal cvc8 C RCP seal injection filter plugs up, reducing charging flow to seals.

2 R TOC requests ramp to 900 MW at 25 MW/min 3 xmt rcs93 I NI-44 fails high, requires rods to manual. ( TS 3.3.1.D, E, S, T) 4 mal eps4c C 4KV bus F diff trip (TS 3.0.3 due to loss of both RHR pumps )

5 mal mfw2a C Both MFW pumps trip spuriously.

mal mfw2b 6 mal ppl5a M Reactor trip breakers wont open from the control room. ATWS. (CT) mal ppl5b 7 ovr C 52-hd-13 fdr for bus 13d fails to open, so 1 MG set stays in service. Crew must xv5i245o insert rods and go to FR S.1. (CT) 8 vlv afw7 C TDAFW pp 11 fcv-95 won't open automatically, crew must open at VB3. (CT)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 3.doc Rev. 0

ES-401 PWR Examination Outline Form ES-401-2 Facility: Diablo Canyon Power Plant Printed: 11/12/2008 Date Of Exam: 02/06/2009 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 1 1 2 9 0 0 0

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

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

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

11/12/2008 9:31:49 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant 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 AK1.02 - Change in leak rate with 3.1 1 3 change in pressure 000009 Small Break LOCA / 3 X EA2.12 - Charging pump ammeter 2.8 1 000011 Large Break LOCA / 3 X EA1.03 - Securing of RCPs 4.0 1 000022 Loss of Rx Coolant Makeup / 2 X AK1.03 - Relationship between 3.0 1 charging flow and PZR level 000025 Loss of RHR System / 4 X AA2.07 - Pump cavitation 3.4 1 000027 Pressurizer Pressure Control System X AK2.03 - Controllers and positioners 2.6 1 Malfunction / 3 000029 ATWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1 disconnects 000038 Steam Gen. Tube Rupture / 3 X EK1.01 - Use of steam tables 3.1 1 000040 Steam Line Rupture - Excessive X AK2.02 - Sensors and detectors 2.6* 1 Heat Transfer / 4 000054 Loss of Main Feedwater / 4 X AA1.01 - AFW controls, including the 4.5 1 use of alternate AFW sources 000055 Station Blackout / 6 X 2.1.31 - Ability to locate control room 4.6 1 switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

000056 Loss of Off-site Power / 6 X AA2.19 - T-cold and T-hot indicators 4.0 1 (wide range) 000057 Loss of Vital AC Inst. Bus / 6 X 2.4.20 - Knowledge of operational 3.8 1 implications of EOP warnings, cautions, and notes.

000058 Loss of DC Power / 6 X AA1.02 - Static inverter dc input 3.1* 1 breaker, frequency meter, ac output breaker, and ground fault detector 000062 Loss of Nuclear Svc Water / 4 X AK3.02 - The automatic actions 3.6 1 (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air / 8 X 2.4.47 - Ability to diagnose and 4.2 1 recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

W/E04 LOCA Outside Containment / 3 X EK3.4 - RO or SRO function within the 3.6 1 control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated 11/12/2008 9:38:08 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant 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 W/E05 Inadequate Heat Transfer - Loss of X EK3.2 - Normal, abnormal and 3.7 1 Secondary Heat Sink / 4 emergency operating procedures associated with Loss of Secondary Heat Sink K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 11/12/2008 9:38:08 am 2

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant 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 000032 Loss of Source Range NI / 7 X AK3.01 - Startup termination on 3.2 1 source-range loss 000033 Loss of Intermediate Range NI / 7 X AA2.01 - Equivalency between 3.0 1 source-range, intermediate-range, and power-range channel readings 000036 Fuel Handling Accident / 8 X AK1.02 - SDM 3.4 1 000059 Accidental Liquid RadWaste Rel. / X 2.2.22 - Knowledge of limiting 4.0 1 9 conditions for operations and safety limits.

000060 Accidental Gaseous Radwaste Rel. / X 2.4.50 - Ability to verify system alarm 4.2 1 9 setpoints and operate controls identified in the alarm response manual.

000074 Inad. Core Cooling / 4 X EK3.04 - Tripping RCPs 3.9 1 W/E08 RCS Overcooling - PTS / 4 X EK2.2 - Facility's heat removal systems, 3.6 1 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 W/E13 Steam Generator Over-pressure / 4 X EA1.1 - Components, and functions of 3.1 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E14 Loss of CTMT Integrity / 5 X EK2.2 - Facility's heat removal systems, 3.4 1 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 K/A Category Totals: 1 2 2 1 1 2 Group Point Total: 9 11/12/2008 9:38:15 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant 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 K1.08 - Containment 2.7* 1 isolation 004 Chemical and Volume Control X A3.03 - Ion exchange 2.9 1 bypass 004 Chemical and Volume Control X K5.11 - Thermal stress, 3.6 1 brittle fracture, pressurized thermal shock 005 Residual Heat Removal X K5.02 - Need for adequate 3.4 1 subcooling 006 Emergency Core Cooling X 2.1.30 - Ability to locate and 4.4 1 operate components, including local controls.

006 Emergency Core Cooling X K6.13 - Pumps 2.8 1 007 Pressurizer Relief/Quench X K4.01 - Quench tank 2.6 1 Tank cooling 008 Component Cooling Water X A2.02 - High/low surge tank 3.2 1 level 008 Component Cooling Water X K2.02 - CCW pump, 3.0* 1 including emergency backup 010 Pressurizer Pressure Control X A4.01 - PZR spray valve 3.7 1 010 Pressurizer Pressure Control X K6.03 - PZR sprays and 3.2 1 heaters 012 Reactor Protection X A2.03 - Incorrect channel 3.4 1 bypassing 013 Engineered Safety Features X 2.4.31 - Knowledge of 4.2 1 Actuation annunciator alarms, indications, or response procedures.

013 Engineered Safety Features X K1.10 - CPS 2.8* 1 Actuation 022 Containment Cooling X A4.01 - CCS fans 3.6 1 022 Containment Cooling X A2.01 - Fan motor 2.5 1 over-current 026 Containment Spray X K2.01 - Containment spray 3.4* 1 pumps 039 Main and Reheat Steam X A3.02 - Isolation of the 3.1 1 MRSS 059 Main Feedwater X A4.03 - Feedwater control 2.9* 1 during power increase and decrease 059 Main Feedwater X K3.04 - RCS 3.6 1 061 Auxiliary/Emergency X K1.11 - AFW turbine 2.7 1 Feedwater exhaust/drains 062 AC Electrical Distribution X K3.03 - DC system 3.7 1 063 DC Electrical Distribution X A1.01 - Battery capacity as 2.5 1 it is affected by discharge rate 11/12/2008 9:38:24 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant 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 K3.01 - Systems controlled 3.8* 1 by automatic loader 073 Process Radiation Monitoring X K5.01 - Radiation theory, 2.5 1 including sources, types, units, and effects 076 Service Water X 2.4.4 - Ability to recognize 4.5 1 abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

078 Instrument Air X K4.03 - Securing of SAS 3.1* 1 upon loss of cooling water 103 Containment X K4.01 - Vacuum breaker 3.0* 1 protection K/A Category Totals: 3 2 3 3 3 2 1 3 2 3 3 Group Point Total: 28 11/12/2008 9:38:24 am 2

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant 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 001 Control Rod Drive X K2.01 - One-line diagram of 3.5 1 power supply to M/G sets 011 Pressurizer Level Control X A4.02 - Movement of the 3.4 1 pressure control valve, using manual controller 014 Rod Position Indication X 2.1.32 - Ability to explain 3.8 1 and apply system limits and precautions.

028 Hydrogen Recombiner and X K5.03 - Sources of hydrogen 2.9 1 Purge Control within containment 033 Spent Fuel Pool Cooling X K3.02 - Area and ventilation 2.8 1 radiation monitoring systems 034 Fuel Handling Equipment X K6.02 - Radiation 2.6 1 monitoring systems 035 Steam Generator X A3.01 - S/G water level 4.0 1 control 071 Waste Gas Disposal X A1.06 - Ventilation system 2.5 1 075 Circulating Water X K4.01 - Heat sink 2.5 1 079 Station Air X K1.01 - IAS 3.0 1 K/A Category Totals: 1 1 1 1 1 1 1 0 1 1 1 Group Point Total: 10 11/12/2008 9:38:31 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such 3.4 1 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.39 Knowledge of conservative decision making 3.6 1 practices.

Category Total: 2 Equipment Control 2.2.2 Ability to manipulate the console controls as 4.6 1 required to operate the facility between shutdown and designated power levels.

2.2.6 Knowledge of the process for making changes to 3.0 1 procedures.

2.2.13 Knowledge of tagging and clearance procedures. 4.1 1 Category Total: 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.

2.3.13 Knowledge of radiological safety procedures 3.4 1 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

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: 3 Emergency Procedures/Plan 2.4.26 Knowledge of facility protection requirements, 3.1 1 including fire brigade and portable fire fighting equipment usage.

2.4.32 Knowledge of operator response to loss of all 3.6 1 annunciators.

Category Total: 2 Generic Total: 10 11/12/2008 9:38:38 am 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Diablo Canyon Power Plant Printed: 11/12/2008 Date Of Exam: 02/06/2009 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 0 0 0 0 2 2 4

& N/A 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 1 1 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: