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, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 Facility: _______________________________

Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan l

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)

Diablo Canyon 02/09/09

L061C Determination of SFP Heat Load Removal Parameters (LJACO-01R)

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

D, R Review Outage Safety Checklist (NRC ADM02SRO - L031)

G2.1.40 - Knowledge of refueling administrative requirements. (3.9)

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

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

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

N, R Offsite Dose Assessment and classification - FHB Accident (LJC-166)

G2.4.41 - Knowledge of the emergency action level thresholds and classifications. (4.6)

D, R

ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _____________________________

Date of Examination: ______________

Exam Level: RO 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 a.

b.

c.

d.

e.

f.

g.

h.

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

j.

k.

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 l

Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature l

(L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3

9 / # 8 / # 4

$ 1 / $ 1 / $ 1

- / - / $1 (control room system) l

$ 1 / $ 1 / $ 1

$ 2 / $ 2 / $ 1

3 / # 3 / # 2 (randomly selected)

$ 1 / $ 1 / $ 1 Diablo Canyon 02/09/09

L061C S1 - 004/Isolate VCT Rupture (LJC-005)

M,A,E,S 02 S2 - 010/Respond to PT-456 failed high (LJC-143)

D,S 03 S3 - 005/Isolate LOCA outside containment (LJC-118)

D,A,E,S 04p S4 - 103/Manually isolate CVI components N,A,E,S 05 S5 - 008/Loss of CCW to one RCP (L031 NRC test)

D,A,E,S 08 S6 - 041/RCS cooldown for SGTR (LJC-090)

D,A,E,S 04s S7 - 073/Verify RM-44A OPERABLE N,S 07 P1 - 062/Transfer pressurizer heater group 12 to backup (LJP-029)

D,L,E 06 P2 - 004/Align CCP suction to RWST (LJP-207, modified for Unit 2)

M,E,L,R 02 P3 - 012/De-energize SSPS to block SI (LJP-09S)

D,L 07

ES-301 Transient and Event Checklist Form ES-301-5 Facility:

Date of Exam:

Operating Test No.:

Scenarios 1

2 3

4 CREW POSITION CREW POSITION CREW POSITION CREW POSITION M

I N

I M

U M(*)

A P

P L

I C

A N

T E

V E

N T

T Y

P E

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

T O

T A

L R

I U

RX 2

1 1

1 0 NOR 3

1 1

1 1 I/C 3,4, 5 1-3,6 3,4,7,8 11 4

4 2 MAJ 7

4 6

3 2

2 1 RO SRO-I SRO-U TS 3,4 2

0 2 2 RX 2

1 1

1 0 NOR 1

3 2

1 1 1 I/C 3,4,5 1,2,5 1,3-5 10 4

4 2 MAJ 7

4 6

3 2

2 1 RO SRO-I SRO-U TS 3,4 2

0 2 2 RX 2

1 1

1 0 NOR 1

1 1

1 1 I/C 3,4,5 1,2,3 1,3,5 9

4 4 2 MAJ 7

4 6

3 2

2 1 RO SRO-I SRO-U TS 1,3 2

0 2 2 RX 1

1 0 NOR 1

1 1 I/C 4

4 2 MAJ 2

2 1 RO SRO-I SRO-U 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 No.

Malf. No.

Event Type*

Event Description and Time Line 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 No.

Malf. No.

Event Type*

Event Description and Time Line 1

Vlv pzr5 C

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

(CT) 2 Mal mfw2a R - CO C - BO Ramp unit to 50% power due to FWP 11 high vibration.

3 Xmt mfw37 I

N - CO N -BOP LT-459 Pzr level channel fails to 10% (TS 3.3.1.M, 3.3.3.F, 3.3.4)

Restores letdown flow.

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

L061C Scenario 3.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 No.

Malf. No.

Event Type*

Event Description and Time Line 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 mal mfw2b C

Both MFW pumps trip spuriously.

6 mal ppl5a mal ppl5b M

Reactor trip breakers wont open from the control room. ATWS. (CT) 7 ovr xv5i245o C

52-hd-13 fdr for bus 13d fails to open, so 1 MG set stays in service. Crew must 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

11/12/2008 Printed:

ES-401 Facility:

Diablo Canyon Power Plant PWR Examination Outline Form ES-401-2 3

3 3

3 1

2 2

1 1

2 4

5 5

4 4

5 3

2 3

3 3

2 1

3 2

3 3

1 1

1 0

1 1

1 4

3 4

4 4

3 2

3 3

4 4

2 3

3 2

RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*

1.

Emergency Abnormal Plant Evolutions 1

1 2

2 Tier Totals Tier Totals 2.

Plant Systems 1

2 3

4

3. Generic Knowledge And Abilities Categories 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.

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.

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.

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.

Note:

Date Of Exam:

02/06/2009 28 18 9

27 10 38 10 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).

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.

SRO-Only Points A2 G*

0 0

0 1

2 3

4 0

0 0

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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

N/A N/A Total 0

0 1

11/12/2008 9:31:49 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 AK1.02 - Change in leak rate with change in pressure 3.1 1

X 000008 Pressurizer Vapor Space Accident /

3 EA2.12 - Charging pump ammeter 2.8 1

X 000009 Small Break LOCA / 3 EA1.03 - Securing of RCPs 4.0 1

X 000011 Large Break LOCA / 3 AK1.03 - Relationship between charging flow and PZR level 3.0 1

X 000022 Loss of Rx Coolant Makeup / 2 AA2.07 - Pump cavitation 3.4 1

X 000025 Loss of RHR System / 4 AK2.03 - Controllers and positioners 2.6 1

X 000027 Pressurizer Pressure Control System Malfunction / 3 EK2.06 - Breakers, relays, and disconnects 2.9*

1 X

000029 ATWS / 1 EK1.01 - Use of steam tables 3.1 1

X 000038 Steam Gen. Tube Rupture / 3 AK2.02 - Sensors and detectors 2.6*

1 X

000040 Steam Line Rupture - Excessive Heat Transfer / 4 AA1.01 - AFW controls, including the use of alternate AFW sources 4.5 1

X 000054 Loss of Main Feedwater / 4 2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

4.6 1

X 000055 Station Blackout / 6 AA2.19 - T-cold and T-hot indicators (wide range) 4.0 1

X 000056 Loss of Off-site Power / 6 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.

3.8 1

X 000057 Loss of Vital AC Inst. Bus / 6 AA1.02 - Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector 3.1*

1 X

000058 Loss of DC Power / 6 AK3.02 - The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 3.6 1

X 000062 Loss of Nuclear Svc Water / 4 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 1

X 000065 Loss of Instrument Air / 8 EK3.4 - RO or SRO function within the 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 3.6 1

X W/E04 LOCA Outside Containment / 3 1

11/12/2008 9:38:08 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK3.2 - Normal, abnormal and emergency operating procedures associated with Loss of Secondary Heat Sink 3.7 1

X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 18 3

3 3

3 K/A Category Totals:

Group Point Total:

2 11/12/2008 9:38:08 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AK3.01 - Startup termination on source-range loss 3.2 1

X 000032 Loss of Source Range NI / 7 AA2.01 - Equivalency between source-range, intermediate-range, and power-range channel readings 3.0 1

X 000033 Loss of Intermediate Range NI / 7 AK1.02 - SDM 3.4 1

X 000036 Fuel Handling Accident / 8 2.2.22 - Knowledge of limiting conditions for operations and safety limits.

4.0 1

X 000059 Accidental Liquid RadWaste Rel. /

9 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

4.2 1

X 000060 Accidental Gaseous Radwaste Rel. /

9 EK3.04 - Tripping RCPs 3.9 1

X 000074 Inad. Core Cooling / 4 EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 3.6 1

X W/E08 RCS Overcooling - PTS / 4 EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.1 1

X W/E13 Steam Generator Over-pressure / 4 EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 3.4 1

X W/E14 Loss of CTMT Integrity / 5 9

1 2

2 1

1 2

K/A Category Totals:

Group Point Total:

1 11/12/2008 9:38:15 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Diablo Canyon Power Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K1.08 - Containment isolation 2.7*

1 X

003 Reactor Coolant Pump A3.03 - Ion exchange bypass 2.9 1

X 004 Chemical and Volume Control K5.11 - Thermal stress, brittle fracture, pressurized thermal shock 3.6 1

X 004 Chemical and Volume Control K5.02 - Need for adequate subcooling 3.4 1

X 005 Residual Heat Removal 2.1.30 - Ability to locate and operate components, including local controls.

4.4 1

X 006 Emergency Core Cooling K6.13 - Pumps 2.8 1

X 006 Emergency Core Cooling K4.01 - Quench tank cooling 2.6 1

X 007 Pressurizer Relief/Quench Tank A2.02 - High/low surge tank level 3.2 1

X 008 Component Cooling Water K2.02 - CCW pump, including emergency backup 3.0*

1 X

008 Component Cooling Water A4.01 - PZR spray valve 3.7 1

X 010 Pressurizer Pressure Control K6.03 - PZR sprays and heaters 3.2 1

X 010 Pressurizer Pressure Control A2.03 - Incorrect channel bypassing 3.4 1

X 012 Reactor Protection 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

4.2 1

X 013 Engineered Safety Features Actuation K1.10 - CPS 2.8*

1 X

013 Engineered Safety Features Actuation A4.01 - CCS fans 3.6 1

X 022 Containment Cooling A2.01 - Fan motor over-current 2.5 1

X 022 Containment Cooling K2.01 - Containment spray pumps 3.4*

1 X

026 Containment Spray A3.02 - Isolation of the MRSS 3.1 1

X 039 Main and Reheat Steam A4.03 - Feedwater control during power increase and decrease 2.9*

1 X

059 Main Feedwater K3.04 - RCS 3.6 1

X 059 Main Feedwater K1.11 - AFW turbine exhaust/drains 2.7 1

X 061 Auxiliary/Emergency Feedwater K3.03 - DC system 3.7 1

X 062 AC Electrical Distribution A1.01 - Battery capacity as it is affected by discharge rate 2.5 1

X 063 DC Electrical Distribution 1

11/12/2008 9:38:24 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Diablo Canyon Power Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K3.01 - Systems controlled by automatic loader 3.8*

1 X

064 Emergency Diesel Generator K5.01 - Radiation theory, including sources, types, units, and effects 2.5 1

X 073 Process Radiation Monitoring 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.5 1

X 076 Service Water K4.03 - Securing of SAS upon loss of cooling water 3.1*

1 X

078 Instrument Air K4.01 - Vacuum breaker protection 3.0*

1 X

103 Containment 28 3

2 3

1 3

3 K/A Category Totals:

3 3

2 2

3 Group Point Total:

2 11/12/2008 9:38:24 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Diablo Canyon Power Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 K2.01 - One-line diagram of power supply to M/G sets 3.5 1

X 001 Control Rod Drive A4.02 - Movement of the pressure control valve, using manual controller 3.4 1

X 011 Pressurizer Level Control 2.1.32 - Ability to explain and apply system limits and precautions.

3.8 1

X 014 Rod Position Indication K5.03 - Sources of hydrogen within containment 2.9 1

X 028 Hydrogen Recombiner and Purge Control K3.02 - Area and ventilation radiation monitoring systems 2.8 1

X 033 Spent Fuel Pool Cooling K6.02 - Radiation monitoring systems 2.6 1

X 034 Fuel Handling Equipment A3.01 - S/G water level control 4.0 1

X 035 Steam Generator A1.06 - Ventilation system 2.5 1

X 071 Waste Gas Disposal K4.01 - Heat sink 2.5 1

X 075 Circulating Water K1.01 - IAS 3.0 1

X 079 Station Air 10 1

1 1

1 0

1 K/A Category Totals:

1 1

1 Group Point Total:

1 11/12/2008 9:38:31 am

Facility:

Diablo Canyon Power Plant Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 11/12/2008 Printed:

PWR RO Examination Outline 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

3.4 1

Conduct of Operations 2.1.39 Knowledge of conservative decision making practices.

3.6 1

2 Category Total:

2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

4.6 1

Equipment Control 2.2.6 Knowledge of the process for making changes to procedures.

3.0 1

2.2.13 Knowledge of tagging and clearance procedures.

4.1 1

3 Category Total:

2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

3.2 1

Radiation Control 2.3.13 Knowledge of radiological safety procedures 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.

3.4 1

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

3.4 1

3 Category Total:

2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.

3.1 1

Emergency Procedures/Plan 2.4.32 Knowledge of operator response to loss of all annunciators.

3.6 1

2 Category Total:

10 Generic Total:

1 11/12/2008 9:38:38 am

11/12/2008 Printed:

ES-401 Facility:

Diablo Canyon Power Plant PWR Examination Outline Form ES-401-2 0

0 0

RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*

1.

Emergency Abnormal Plant Evolutions 1

1 2

2 Tier Totals Tier Totals 2.

Plant Systems 1

2 3

4

3. Generic Knowledge And Abilities Categories 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.

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.

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.

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.

Note:

Date Of Exam:

02/06/2009 0

0 0

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).

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.

SRO-Only Points A2 G*

3 3

2 2

5 5

3 2

1 1

3 2

1 2

2 1

2 3

4 10 4

6 5

3 8

7 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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

N/A N/A Total 1

5 1

11/12/2008 9:45:28 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 EA2.06 - Occurrence of a reactor trip 4.5 1

X 000007 Reactor Trip - Stabilization -

Recovery / 1 2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

4.2 1

X 000026 Loss of Component Cooling Water /

8 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.7 1

X 000055 Station Blackout / 6 2.4.6 - Knowledge of EOP mitigation strategies.

4.7 1

X 000056 Loss of Off-site Power / 6 AA2.10 - Generator overheating and the required actions 3.8 1

X 000077 Generator Voltage and Electric Grid Disturbances / 6 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 4.2 1

X W/E11 Loss of Emergency Coolant Recirc. /

4 6

0 0

3 3

K/A Category Totals:

Group Point Total:

1 11/12/2008 9:44:58 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 2.4.11 - Knowledge of abnormal condition procedures.

4.2 1

X 000024 Emergency Boration / 1 2.2.38 - Knowledge of conditions and limitations in the facility license.

4.5 1

X 000076 High Reactor Coolant Activity / 9 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.9 1

X W/E01 Rediagnosis / 3 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.9 1

X W/E07 Inad. Core Cooling / 4 4

0 0

2 2

K/A Category Totals:

Group Point Total:

1 11/12/2008 9:45:04 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Diablo Canyon Power Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.01 - Problems with RCP seals, especially rates of seal leak-off 3.9 1

X 003 Reactor Coolant Pump A2.02 - Abnormal pressure in the PRT 3.2 1

X 007 Pressurizer Relief/Quench Tank 2.2.38 - Knowledge of conditions and limitations in the facility license.

4.5 1

X 012 Reactor Protection 2.2.38 - Knowledge of conditions and limitations in the facility license.

4.5 1

X 059 Main Feedwater A2.03 - Loss of dc power 3.4 1

X 061 Auxiliary/Emergency Feedwater 5

0 0

3 2

K/A Category Totals:

0 0

0 Group Point Total:

1 11/12/2008 9:45:10 am

11/12/2008 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Diablo Canyon Power Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A1.01 - Load limits 3.2 1

X 034 Fuel Handling Equipment A2.02 - Steam valve stuck open 3.9 1

X 041 Steam Dump/Turbine Bypass Control 2.4.11 - Knowledge of abnormal condition procedures.

4.2 1

X 055 Condenser Air Removal 3

0 0

0 1

1 1

K/A Category Totals:

0 0

0 Group Point Total:

1 11/12/2008 9:45:16 am

Facility:

Diablo Canyon Power Plant Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 11/12/2008 Printed:

PWR SRO Examination Outline 2.1.13 Knowledge of facility requirements for controlling vital / controlled access.

3.2 1

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

3.1 1

2 Category Total:

2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.

4.3 1

Equipment Control 1

Category Total:

2.3.11 Ability to control radiation releases.

4.3 1

Radiation Control 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3.1 1

2 Category Total:

2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

4.6 1

Emergency Procedures/Plan 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 1

2 Category Total:

7 Generic Total:

1 11/12/2008 9:45:23 am

ES-401, Page 27 of 33 ES-401 Record of Rejected K/As Form ES-401-4 l

Tier /

Group Randomly Selected K/A Reason for Rejection RO-T2/G1 061 K2.03 KA is knowledge of the power supply to AFW diesel driven pump.

This is not applicable at DCPP Replaced with 061 K1.11 interrelationship between AFW/Turbine exh/drains, IR 2.7 RO-T2/G1 076 A1.02 KA is to predict and monitor changes in reactor and turbine building closed cooling water temperatures.

At DCPP, Service Water is ASW which is not supplied to either building. It only supplies cooling to CCW.

Replaced with 008 K2.02-Power to pumps, including emergency B/U IR 3.0*

SRO -

W/E12 G2.4.1 KA tests knowledge of EOP entry conditions and immediate actions. There are no T1/G1 immediate actions in the Steam Line Rupture (E-2) EOP.

Replaced with APE 056 2.4.6 - EOP mitigation strategies IR 4.7 SRO APE 005 G2.4.20 knowledge of eop warning, notes, cautions, for stuck rod, T1/G2 not testable at SRO level. replaced with APE 076 G2.2.38 RO T1G1 APE 017G2.2.38 This is a Tech Spec KA, for RCPs there are no Tech Specs (ie <1hr) that are RO knowledge. Replaced with EPE055.G2.1.31 RO T1G2 APE 003AK1.17 theory KA that is not site specific and category 1. Replaced with E14.EK2.2

ML090790307

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