Text

2011-08-Draft Outlines
	ML112700860
Person / Time
Site:	Wolf Creek
Issue date:	08/26/2011
From:	; NRC Region 4
To:	;
References
	50-482/11-08
	Download: ML112700860 (47)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Wolf Creek Date of Examination: Aug.- Sept.

2011 Examination Level: RO SRO Operating Test Number:

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

R.A.1.a Refuel/ Reduced Inventory: Perform the time N, R to core uncovery estimation using the OFN EJ-015, LOSS OF RHR COOLING, step 31. Requires use of Conduct of Operations Figures 5 (time to boil) and 6 (time to uncovery).

R.A.1.a 2.1.25 Ability to interpret reference materials, such as graphs, curves tables, etc. (CFR 41.10/43.5/45.12 RO =

3.9 SRO = 4.2)

M, R S.A.1.a Review/Approve/Evaluate the Reactor S.A.1.a Operators completed manual calculation of RTP; STS SE-002, MANUAL CALCULATION OF REACTOR THERMAL POWER. Requires discovery of errors made by Reactor Operator.

2.1.20 Ability to interpret and execute procedure steps.

(CFR 41.10/43.5/45.12 RO = 4.6 SRO = 4.6)

R.A.1.b Determine the shutdown margin using STS N, R RE-004, SHUTDOWN MARGIN DETERINATION, Attachment A, Shutdown Margin Calculation Short form.

Conduct of Operations 2.1.37 Knowledge of procedures, guidelines, or R A.1.b limitations associated with reactivity management (CFR 41.1/43.6/45.6 RO = 4.3 SRO = 4.6)

N, R S.A.1.b Review/Approve/Verify the Reactor Operators S.A.1.b completed manual calculation of the shutdown margin per STS RE-004, SHUTDOWN MARGIN DETERINATION, Attachment A, Shutdown Margin Calculation Short form.

2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management (CFR 41.1/43.6/45.6 RO = 4.3 SRO = 4.6)

DRAFT 1 of 3

R.A.2 Complete STS AL-211, TURB DRIVEN AUX N, R FDWTR SYS FLOW PATH VERIFICATION &

INSERVICE CHEC VALVE TEST, Attachment A Data Equipment Control Sheet.

R.A.2 2.2.12, Knowledge of surveillance procedures (CFR 41.10/45.13 RO = 3.7 SRO = 4.1)

S.A.2 S.A.2 Review/Approve/Evaluate the Reactor N, R Operators completed STS EF-100B, ESW SYSTEM INSERVICE PUMP A & ESW A DISCHARGE CHECK VALVE TEST, Attachment A Data Sheet.

2.2.12, Knowledge of surveillance procedures (CFR 41.10/45.13 RO = 3.7 SRO = 4.1)

S.A.3 The Containment Purge permit that was in N, R progress was stopped. Determine/Authorize the restart for the Containment Purge Permit. (AP 07B-001, Radiation Control Radioactive Releases, see section 6.2.4.6)

S.A.3 2.3.6 Ability to approve release permits (CFR 41.13/43.4/45.9 RO = 2.0 SRO = 3.8) and/or 2.3.11 Ability to control radiation releases (CFR 41.11/43.4/45.10 RO = 3.8 SRO = 4.3)

DRAFT 2 of 3

R.A.4 Determine percentage of Control Room N, R annunciator loss using OFN PK-029, LOSS OF NON-VITAL 125VDC BUS PK01, PK02, PK03, PK04, AND Emergency Procedures/Plan ANNUNCIATORS.

R.A.4 2.4.32 Knowledge of operator response to loss of all annunciators. (CFR 41.10/43.5/45.13 RO = 3.6 SRO

= 4.0)

S.A.4 (In the classroom setting) Determine the E-Plan classification and Protective action recommendations, if S.A.4 D, R any.

2.4.41 Knowledge of the emergency action level thresholds and classifications. (CFR 41.10/43.5/45.11 RO = 2.9 SRO = 4.6) and 2.4.44 Knowledge of emergency plan protective action recommendations. (CFR 41.10/41.12/43.5/45.11 RO =

2.4 SRO = 4.4)

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)

DRAFT 3 of 3

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Wolf Creek Date of Examination: Aug. -Sept.

2011 Examination Level: RO SRO Operating Test Number:

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

Bolded is an Alternate Success Path JPM.

System / JPM Title Type Code* Safety Function

a. S1: 001 - Control Rod Drive System N, S 1 Perform the actions of STS SF-001, CONTROL AND SHUTDOWN ROD OPERABILITY VERIFICATION, for Control Bank A.

001 2.2.12 Knowledge of surveillance procedures. (3.7/4.1)

RO/SRO-I

b. S2: 013 - Engineered Safety Features Actuation M, EN, A, S 2 System (ESFAS)

Perform actions to ensure CRVIS actuation using EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Attachment F, Automatic Signal Verification (step F9, RNO).

PRA: ESFAS is a Risk Significant System at Wolf Creek.

013 A4.01 Ability to manually operate and/or monitor in the control room ESFAS-initiated equipment which fails to actuate. (4.5/4.8)

RO/SRO-I/SRO-U DRAFT 1 of 6

c. S3: 006 - Emergency Core Cooling System (ECCS) D, A, S 3 Perform actions to increase level in an Accumulator using a Safety Injection Pump per procedure SYS EP-200, SAFETY INJECTION ACCUMULATOR OPERATIONS (see sections 6.1, 6.2, 6.3 or 6.4), however, gas voiding is diagnosed due to SIP oscillations and OFN BG-045, GAS BINDING OF CCPS OR SI PUMPS, is entered and performed.

SOER 97-1, Potential Loss of High Pressure Injection and Charging Capability from Gas Intrusion 006 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (2) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: improper discharge pressure. (3.4/3.8) 006 A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (2) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: improper amperage to the pump motor.

(3.4/3.5) 006 A4.01 Ability to manually operate and/or monitor in the control room: pumps. (4.1/3.9)

RO/SRO-I/SRO-U

d. S4: 041 - Steam Dump System and Turbine Bypass M, L, S 4S Control Perform actions to establish a maximum rate cooldown using the ARVs per EMG E-3, STEAM GENERATOR TUBE RUPTURE.

041 A4.06 Ability to manually operate and/or monitor in the control room: Atmospheric relief valve controllers. (2.9/3.1)

RO/SRO-I DRAFT 2 of 6

e. S5: 003 - Reactor Coolant Pumps System M, L, S 4P Perform the actions of ALR 00-070B, RCP VIB/SYS ALERT and OFN BB-005, RCP MALFUNCTIONS, to secure an RCP.

(High frame vibration requires a Controlled Shutdown per Attachment C of OFN BB-005, RCP MALFUNCTIONS).

003 A2.02 Ability to (a) predict the impacts of the following malfunctions of operations on the RCPs; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown in comparison to a normal shutdown of an RCP. (3.7/3.9)

RO/SRO-I/SRO-U

f. S6: 103 - Containment Systems D, S 5 Perform actions to startup the Containment Purge System per SYS GT-120, CONTAINMENT MINI PURGE SYSTEM OPERATIONS, sections 6.1 and 6.2.

103 A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including:

Containment pressure, temperature, and humidity. (3.7/4.1)

RO

g. S7: 015 - Nuclear Instrumentation D, S 7 Perform actions to bypass a failed Power Range nuclear instrumentation channel using OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment R (see step R4).

015 A4.03 Ability to manually operate and/or monitor in the control room: Trip bypasses. (3.8/3.9)

RO/SRO-I DRAFT 3 of 6

h. S8: 008 - Component Cooling Water System (CCW) M, A, S 8 Perform actions of ALR 00-052A, CCW TO RCP FLOW LO, to respond to a loss of a CCW pump.

A4.01 Ability to operate and/or monitor in the control room: CCW indications and controls. (3.3/3.1)

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of a CCW pump. (3.3/3.6)

PRA: Component Cooling Water is a Risk Significant System at Wolf Creek.

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

i. P1: 004 - Chemical and Volume Control System D, A, R, E 1 Perform local actions to borate the Reactor Coolant System. (See OFN BG-009, EMERGENCY BORATION, Attachment A, Establishing Alternate Boration Flowpath.)

004 A2.14 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations. (3.8/3.9)

APE 024 AA1.04 Ability to operate and/or monitor the following as they apply to Emergency Boration: Manual boration valve. (3.6/3.7)

RO/SRO-I/SRO-U DRAFT 4 of 6

j. P2: 061 - Auxiliary/Emergency Feedwater System N 4S Perform actions of STN FC-002, AUX FEEDWATER TURBINE OVERSPEED TEST section 8.1.6.

061 2.1.20 Ability to interpret and execute procedure steps.

(4.4/4.6))

PRA: Auxiliary Feedwater (AL) is a Risk Significant System at Wolf Creek.

RO/SRO-I D, A 6

k. P3: 064 - Emergency Diesel Generators Perform actions of ALR 00-020D, DG NE01 TROUBLE alarm. Local alarm response procedure ALR 501, STANDBY DIESEL ENGINE SYSTEM CONTROL PANEL KJ-121, Attachment A, Fuel Oil Press Low and Attachment C, Fuel Strain Diff Press High, are performed.

064 K1.03 Knowledge of the physical connections and/or cause-effect relationship between the ED/G system and the following systems: Diesel fuel oil supply system.

(3.6/4.0)

PRA: Diesel Fuel Oil (JE) is a Risk Significant System at Wolf Creek.

RO/SRO-I/SRO-U 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 DRAFT 5 of 6

(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)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 DRAFT 6 of 6

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Wolf Creek Date of Exam: Aug - Sept 2011 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 3 0 0 1 1 1 0 NOR 0 0 1 1 1 1 1 SRO-I 1&4 I/C 1256 26 27 8 4 4 2 MAJ 4 4 5 3 2 2 1 SRO-U TS 12 0 0 2 0 2 2 RO RX 3 0 0 1 1 1 0 NOR 0 0 1 1 1 1 1 SRO-I 2&5 I/C 256 1235 236 11 4 4 2 6

SRO-U MAJ 4 4 5 3 2 2 1 TS 0 123 0 3 0 2 2 RO RX 3 0 0 1 1 1 0 NOR 0 0 1 1 1 1 1 SRO-I 3&6 I/C 1 135 2367 8 4 4 2 MAJ 4 4 5 3 2 2 1 SRO-U TS 0 0 23 2 0 2 2 RO 1 RX 3 0 0 1 1 1 0 NOR 0 0 1 1 1 1 1 SRO-I I/C 256 26 27 7 4 4 2 SRO-U MAJ 4 4 5 3 2 2 1 1 TS 0 0 0 0 0 2 2 DRAFT 1 of 5

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Wolf Creek Date of Exam: Aug - Sept 2011 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 2 RX 3 0 0 1 1 1 0 NOR 0 0 1 1 1 1 1 SRO-I I/C 1 135 236 7 4 4 2 SRO-U MAJ 4 4 5 3 2 2 1 TS 0 0 0 0 0 2 2 RO RX 3 1 1 1 0 NOR 0 0 1 1 1 SRO-I I/C 1256 4 4 4 2 SRO-U MAJ 4 1 2 2 1 1 TS 12 2 0 2 2 RO RX 0 0 1 1 0 NOR 0 0 1 1 1 SRO-I I/C 1235 5 4 4 2 6

SRO-U 2 MAJ 4 1 2 2 1 TS 123 3 0 2 2 RO RX 0 0 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2367 4 4 4 2 SRO- MAJ 5 1 2 2 1 U3 TS 23 2 0 2 2 DRAFT 2 of 5

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Wolf Creek Date of Exam: Aug - Sept 2011 Operating Test No.:

A E Scenarios P V 1 2 3 4 Backup 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 4 1 1 1 0 NOR 0 0 1 1 1 SRO-I I/C 1267 4 4 4 2 SRO-U MAJ 38 2 2 2 1 TS 123 3 0 2 2 RO RX 4 4 1 1 1 0 NOR 0 0 0 1 1 1 SRO-I I/C 267 1 4 4 4 2 SRO-U MAJ 38 38 2 2 2 1 TS 0 0 0 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 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 DRAFT 3 of 5

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.

DRAFT 4 of 5

DRAFT 5 of 5 ES-401 PWR Examination Outline Form ES-401-2 Facility: Wolf Creek Printed:

Date of Exam: 08/29/2011 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 2 1 9 0 0 0

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

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

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

1

PWR RO Examination Outline Printed:

Facility: Wolf Creek 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 000007 Reactor Trip - Stabilization - Recovery X EK2.03 - Reactor trip status panel 3.5 1

/1 000008 Pressurizer Vapor Space Accident / 3 X AK2.02 - Sensors and detectors 2.7* 1 000009 Small Break LOCA / 3 X EK2.03 - S/Gs 3.0 1 000011 Large Break LOCA / 3 X EA2.04 - Significance of PZR readings 3.7 1 000015/000017 RCP Malfunctions / 4 X AA2.01 - Cause of RCP failure 3.0 1 000022 Loss of Rx Coolant Makeup / 2 X AK1.02 - Relationship of charging flow 2.7 1 to press. diff. between charging and RCS 000025 Loss of RHR System / 4 X AK3.02 - Isolation of RHR low-pressure 3.3 1 piping prior to pressure increase above specified level 000026 Loss of Component Cooling Water / 8 X 2.4.2 - Knowledge of system set points, 4.5 1 interlocks and automatic actions associated with EOP entry conditions.

000027 Pressurizer Pressure Control System X 2.2.22 - Knowledge of limiting conditions 4.0 1 Malfunction / 3 for operations and safety limits.

000038 Steam Gen. Tube Rupture / 3 X EA1.15 - AFW source level and capacity 3.9 1 (chart) 000040 Steam Line Rupture - Excessive Heat X AK1.03 - RCS shrink and consequent 3.8 1 Transfer / 4 depressurization 000054 Loss of Main Feedwater / 4 X AK1.02 - Effects of feedwater 3.6 1 introduction on dry S/G 000055 Station Blackout / 6 X EA1.01 - In-core thermocouple 3.7 1 temperatures 000062 Loss of Nuclear Svc Water / 4 X 2.1.28 - Knowledge of the purpose and 4.1 1 function of major system components and controls.

000077 Generator Voltage and Electric Grid X AA2.04 - VARs outside the capability 3.6 1 Disturbances / 6 curve W/E04 LOCA Outside Containment / 3 X EA1.2 - Operating behavior 3.6 1 characteristics of the facility W/E05 Loss of Secondary Heat Sink / 4 X EK3.2 - Normal, abnormal and 3.7 1 emergency operating procedures associated with Loss of Secondary Heat Sink 2

PWR RO Examination Outline Printed:

Facility: Wolf Creek 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/E11 Loss of Emergency Coolant Recirc. / 4 X EK3.2 - Normal, abnormal and 3.5 1 emergency operating procedures associated with Loss of Emergency Coolant Recirculation K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 3

PWR RO Examination Outline Printed:

Facility: Wolf Creek 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 000001 Continuous Rod Withdrawal / 1 X AK2.06 - T-ave./ref. deviation meter 3.0* 1 000003 Dropped Control Rod / 1 X AA2.02 - Signal inputs to rod control 2.7 1 system 000005 Inoperable/Stuck Control Rod / 1 X AK3.01 - Boration and emergency 4.0 1 boration in the event of a stuck rod during trip or normal evolutions 000028 Pressurizer Level Malfunction / 2 X AK2.03 - Controllers and positioners 2.6 1 000037 Steam Generator Tube Leak / 3 X AA1.05 - Radiation monitor for auxiliary 3.3 1 building exhaust processes 000051 Loss of Condenser Vacuum / 4 X 2.4.31 - Knowledge of annunciator 4.2 1 alarms, indications, or response procedures.

000061 ARM System Alarms / 7 X AK3.02 - Guidance contained in alarm 3.4 1 response for ARM system 000069 Loss of CTMT Integrity / 5 X AK1.01 - Effect of pressure on leak rate 2.6 1 W/E01 Rediagnosis / 3 X EA2.2 - Adherence to appropriate 3.3 1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 1 2 2 1 2 1 Group Point Total: 9 4

PWR RO Examination Outline Printed:

Facility: Wolf Creek 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 K2.01 - RCPS 3.1 1 003 Reactor Coolant Pump X A4.05 - RCP seal leakage 3.1 1 detection instrumentation 004 Chemical and Volume Control X K3.07 - PZR level and 3.8 1 pressure 005 Residual Heat Removal X K2.03 - RCS pressure 2.7* 1 boundary motor-operated valves 005 Residual Heat Removal X A4.01 - Controls and 3.6* 1 indication for RHR pumps 006 Emergency Core Cooling X K3.01 - RCS 4.1* 1 007 Pressurizer Relief/Quench Tank X 2.1.32 - Ability to explain 3.8 1 and apply system limits and precautions.

007 Pressurizer Relief/Quench Tank X A2.01 - Stuck-open PORV or 3.9 1 code safety 008 Component Cooling Water X K1.02 - Loads cooled by 3.3 1 CCWS 010 Pressurizer Pressure Control X K5.01 - Determination of 3.5 1 condition of fluid in PZR, using steam tables 012 Reactor Protection X K4.08 - Logic matrix testing 2.8* 1 013 Engineered Safety Features X K4.09 - Spurious trip 2.7 1 Actuation protection 022 Containment Cooling X A1.04 - Cooling water flow 3.2 1 022 Containment Cooling X A3.01 - Initiation of 4.1 1 safeguards mode of operation 026 Containment Spray X A2.07 - Loss of Ctmt Spray 3.6 1 pump suction when in recirc.

mode 039 Main and Reheat Steam X K5.08 - Effect of steam 3.6 1 removal on reactivity 059 Main Feedwater X K4.17 - Increased feedwater 2.5* 1 flow following a reactor trip 061 Auxiliary/Emergency Feedwater X K6.01 - Controllers and 2.5 1 positioners 062 AC Electrical Distribution X A1.03 - Effect on 2.5 1 instrumentation and controls of switching power supplies 063 DC Electrical Distribution X K3.02 - Components using 3.5 1 DC control power 063 DC Electrical Distribution X 2.1.31 - Ability to locate 4.6 1 control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

5

PWR RO Examination Outline Printed:

Facility: Wolf Creek 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 tanks 3.2 1 073 Process Radiation Monitoring X 2.1.30 - Ability to locate and 4.4 1 operate components, including local controls.

073 Process Radiation Monitoring X K1.01 - Those systems served 3.6 1 by PRMs 076 Service Water X A1.02 - Reactor and turbine 2.6* 1 building closed cooling water temperatures 078 Instrument Air X A3.01 - Air pressure 3.1 1 078 Instrument Air X K1.04 - Cooling wtr to comp. 2.6 1 103 Containment X A2.04 - Containment 3.5* 1 evacuation (including recognition of the alarm)

K/A Category Totals: 3 2 3 3 2 2 3 3 2 2 3 Group Point Total: 28 6

PWR RO Examination Outline Printed:

Facility: Wolf Creek 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 K4.01 - Filling and draining 2.7 1 the RCS 011 Pressurizer Level Control X K6.04 - Operation of PZR 3.1 1 level controllers 014 Rod Position Indication X A1.04 - Axial and radial 3.5 1 power distribution 015 Nuclear Instrumentation X K3.02 - CRDS 3.3* 1 016 Non-nuclear Instrumentation X K5.01 - Separation of control 2.7* 1 and protection circuits 027 Containment Iodine Removal X K2.01 - Fans 3.1* 1 028 Hydrogen Recombiner and X A2.01 - Hydrogen recombiner 3.4* 1 Purge Control power setting, determined by using plant data book 029 Containment Purge X A4.01 - Containment purge 2.5 1 flow rate 034 Fuel Handling Equipment X 2.2.12 - Knowledge of 3.7 1 surveillance procedures.

035 Steam Generator X A3.01 - S/G water level 4.0 1 control K/A Category Totals: 0 1 1 1 1 1 1 1 1 1 1 Group Point Total: 10 7

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed:

Facility: Wolf Creek Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.18 Ability to make accurate, clear, and concise logs, 3.6 1 records, status boards, and reports.

2.1.36 Knowledge of procedures and limitations involved 3.0 1 in core alterations.

2.1.45 Ability to identify and interpret diverse indications 4.3 1 to validate the response of another indication.

Category Total: 3 Equipment Control 2.2.41 Ability to obtain and interpret station electrical and 3.5 1 mechanical drawings.

2.2.43 Knowledge of the process used to track inoperable 3.0 1 alarms.

Category Total: 2 Radiation Control 2.3.7 Ability to comply with radiation work permit 3.5 1 requirements during normal or abnormal conditions.

2.3.12 Knowledge of radiological safety principles 3.2 1 pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Category Total: 2 Emergency Procedures/Plan 2.4.9 Knowledge of low power /shutdown implications in 3.8 1 accident (e.g. LOCA or loss of RHR) mitigation strategies.

2.4.21 Knowledge of the parameters and logic used to 4.0 1 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.

2.4.47 Ability to diagnose and recognize trends in an 4.2 1 accurate and timely manner utilizing the appropriate control room reference material.

Category Total: 3 Generic Total: 10 8

ES-401 PWR Examination Outline Form ES-401-2 Facility: Wolf Creek Printed:

Date Of Exam: 08/29/2011 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 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: