ML042080222

2004 Final Outline

ML042080222
Person / Time
Site:	Wolf Creek
Issue date:	05/13/2004
From:	Gody A Operations Branch IV
To:	Muench R Wolf Creek
References
50-482/04-301, ES-301, ES-301-1 50-482/04-301
Download: ML042080222 (18)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Wolf Creek Date of Examination: 05/10/2004 Examination Level: RO Operating Test Number: 1 Revision 03 Administrative Topic (see Note)

Describe activity to be performed:

Conduct of Operations 2.1.33 RO A1.a (BANK)

Conduct of Operations: Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

Perform Surveillance Test for AFD Conduct of Operations 2.1.7 RO A1.b (NEW)

Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Given Data, complete a 1/M plot and determine estimated critical rod position (Alternate Success Path)

Equipment Control 2.2.12 RO A2 (NEW)

Equipment Control: Knowledge of surveillance procedures.

Given Data, Complete the Surveillance Test Data sheet identifying and documenting any out of spec readings.

Radiation Control 2.3.1 RO A3 (MODIFIED BANK)

Radiation Control: Knowledge of 10 CFR: 20 and related facility radiation control requirements Given a Clearance Order for venting/draining a contaminated system in the RCA, Determine the RWP, limits and time allowed to complete the job.

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Wolf Creek Date of Examination: 5/10/2004 Examination Level: SRO Operating Test Number: 1 Revision 03 Administrative Topic (see Note)

Describe activity to be performed:

Conduct of Operations 2.1.33 SRO A1.a (Bank)

Conduct of Operations: Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

Review Surveillance Test for AFD and based on results determine any required actions. (Alternate Success Path)

Conduct of Operations 2.1.20 SRO A1.b (NEW)

Conduct of Operations: Ability to execute procedure steps.

Given initial plant conditions of a SG tube leak, determine from the OFN the required actions.

Equipment Control 2.2.23 SRO A2 (2001 Exam Bank)

Equipment Control: Ability to track limiting conditions for operations.

Given a sequence of events, Determine the end time of an LCO including any extensions.

Radiation Control 2.3.6 SRO A3 (NEW)

Radiation Control: Knowledge of the requirements for reviewing and approving release permits.

Given a Release Permit, Review for Technical Accuracy.

Emergency Plan 2.4.41 SRO A4 (Modified Bank)

Emergency Procedures / Plan: Knowledge of the emergency action level thresholds and classifications.

After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.

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

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 NOTE: The following are to be run concurrent:

S1/S2 S3/S4 S5/S6 Facility: Wolf Creek Date of Examination: 5/10/2004 Exam Level: RO / SRO(I)

Operating Test No.: 1 Revision 03 Control Room Systems (8 for RO; 7 for SROI; 2 or 3 for SROU)

System / JPM Title Type Code*

Safety Function

a. (S1) Emergency Borate using EMG FR-S1 (101-S)

DAS 1

b. (S2) Fill an ECCS Accumulator (202-S)

DS 2

c. (S3) Isolate Source of Containment Flooding, EMG FR-Z2 (501-S)

MS 5

d. (S4) Feed S/Gs with TDAWP (401-S)

DSL 4

e. (S5) Swap CCW Trains (801-S)

(2001 Exam)

DSL 8

f. (S6) Rx Start Up, 10-8 amps to Point of Adding Heat (701-S)

NASL 7

g. (S7) OFN BB-31 S/D LOCA, Isolate RHR Leak (301-S)

(RO Only)

NS 3

h. (C1) EMG C-0, Loss of All AC, Align Alternate Power to Safeguards Bus using the OFN (601-C)

NAC 6

In-Plant Systems (3 for RO; 3 for SROI; 3 or 2 for SROU)

i. (P1) Locally Unisolate BIT (302-P)

MR 3

j. (P2) Align 120 vac Vital Bus to SOLA Xfmr (602-P)

(2001 Exam)

DAP 6

k. (P3) EMG C-0, Loss of All AC, Isolate RCP Seal Leak Off (202-P)

NR 2

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

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Wolf Creek Date of Examination: 5/10/2004 Exam Level: SRO(U)

Operating Test No.: 1 Revision 03 Control Room Systems (8 for RO; 7 for SROI; 2 or 3 for SROU)

System / JPM Title Type Code*

Safety Function

c. (S3) Isolate Source of Containment Flooding, EMG FR-Z2 (501-S)

MS 5

d. (S4) Feed S/Gs with TDAWP (401-S)

DSL 4

f. (S6) Rx Start Up, 10-8 amps to Point of Adding Heat (701-S)

NASL 7

In-Plant Systems (3 for RO; 3 for SROI; 3 or 2 for SROU)

j. (P2) Align 120 VAC Vital Bus to SOLA Xfmr (602-P)

(2001 Exam)

DAP 6

k. (P3) EMG C-0, Loss of All AC, Isolate RCP Seal Leak Off (202-P)

NR 2

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (P)lant NOTE: The following simulator JPMs are to be done concurrent:

S3 and S4

WCNOC License Examination May 7, 2004 PWR Written Examination Outline Revision 02 Form ES-401-2 Confidential Page 1 RO K/A Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total K

A A

2 G

Total 1

2 5

3 2

3 3

18 4

3 7

2 1

1 2

1 3

1 9

2 3

5

1.

Emergency &

Abnormal Plant Evolutions Tier Totals 3

6 5

3 6

4 27 6

6 12 1

2 2

4 2

2 2

2 2

4 3

3 28 3

1 4

2 2

1 2

1 2

1 1

10 2

2

2.

Plant Systems Tier Totals 4

2 5

2 4

3 4

2 4

4 4

38 3

3 6

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 2

2 2

4 10 2

2 2

1 7

Note:

1.

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

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution unless they are related to plant specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Emergency and Abnormal Plant evolutions - Tier 1 Group 1 (RO/SRO)

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

1 K

2 K

3 A

1 A

2 G Number K/A Topics Imp.

RO #

SRO #

000007 Reactor Trip -

Stabilization - Recovery / 1 R

41007 EK301 Knowledge of the reasons for the following as the apply to a reactor trip:

Actions contained in EOP for reactor trip 4.0 XXX 000007 Reactor Trip -

Stabilization - Recovery / 1 S

41007 2445 Emergency Procedures / Plan: Ability to prioritize and interpret the significance of each annunciator or alarm.

3.6 XXX 000008 Pressurizer Vapor Space Accident / 3 R

42008 AK101 Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves 3.2 XXX 000009 Small Break LOCA /3 R

41009 EA239 Ability to determine or interpret the following as they apply to a small break LOCA: Adequate core cooling 4.3 XXX 000009 Small Break LOCA /3 S

41009 EA223 Ability to determine or interpret the following as they apply to a small break LOCA: RCP operating parameters and limits. 10 CFR 43.5 3.3 XXX 000011 Large Break LOCA /3 R

41011 EK202 Knowledge of the interrelations between the and the following Large Break LOCA: Pumps 2.6 XXX 000015/17 RCP Malfunctions /4 R

42015 AK210 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP indicators and controls 3.3 XXX 000022 Loss of Rx Coolant Makeup /2 R

42022 2435 Emergency Procedures / Plan: Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications.

2.9 XXX 000025 Loss of RHR System /4 R

42025 AA204 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Location and isolability of leaks 3.3 XXX 000026 Loss of Comp. Cooling Water /8 R

42026 AA203 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition 2.6 XXX 000027 Pzr Press. Ctrl. Sys. Malf.

/3 R

42027 AK203 Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners.

2.6 XXX 000029 ATWS /1 R

41029 222 Equipment Control: Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

4.0 XXX 000029 ATWS /1 S

41029 EA209 Ability to determine or interpret the following as they apply to a ATWS:

Occurrence of a main turbine/reactor trip. 10 CFR 43.5 4.4 XXX 000038 SG Tube Rupture/3 S

41038 EA216 Ability to determine or interpret the following as they apply to a SGTR:

Actions to be taken if S/G goes solid and water enters steam line. 10 CFR 43.5 4.6 XXX 000040 W/E12 Steam Line Rupture /4 000054 Loss of Feedwater /4 R

42054 2125 Conduct of Operations: Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

2.8 XXX

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Emergency and Abnormal Plant evolutions - Tier 1 Group 1 (RO/SRO)

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

1 K

2 K

3 A

1 A

2 G Number K/A Topics Imp.

RO #

SRO #

000055 Station Blackout /6 000056 /Loss of Off Site Power /6 R

42056 AK103 Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: Definition of subcooling: use of steam tables to determine it 3.1 XXX 000056 /Loss of Off Site Power /6 S

42056 2132 Conduct of Operations: Ability to explain and apply all system limits and precautions. 10 CFR 43.2 3.8 XXX 000057 Loss of Vital AC Instrument Bus /6 R

42057 AA102 Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual control of PZR level 3.8 XXX 000057 Loss of Vital AC Instrument Bus /6 S

42057 AA218 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: The indicator, valve, breaker, or damper position which will occur on a loss of power. 10 CFR 43.5 3.1 XXX 000058 Loss of DC Power /6 R

42058 AK301 Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Use of dc control power by D/Gs 3.4 XXX 000062 Loss of Nuclear Service Water /4 R

42062 AK302 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 3.6 XXX 000065 Loss of Instrument Air /8 W/E04 LOCA Outside Containment /3 R

45E04 EA12 Ability to operate and / or monitor the following as they apply to the (LOCA Outside Containment): Operating behavior characteristics of the facility.

3.6 XXX W/E04 LOCA Outside Containment /3 S

45E04 2410 Emergency Procedures / Plan: Knowledge of annunciator response procedures. 10 CFR 43.5 3.1 XXX W/E11 Loss of Emergency Coolant Recirc. / 4 R

45E11 EK22 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: 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.

3.9 XXX W/E05 Inadequate Heat Transfer-Loss of Secondary Heat Sink / 4 R

45E05 EK21 Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

3.7 XXX K/A Category Totals RO

/

SRO 2 5 3 2 3

/

4 3

/

3 Group Point Total 18 7

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Emergency and Abnormal Plant evolutions - Tier 1 Group 2 (RO/SRO)

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

1 K

2 K

3 A

1 A

2 G Number K/A Topics Imp.

RO#

SRO #

000001 Continuous Rod Withdrawal /1 R

42001 AA203 Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Proper actions to be taken if automatic safety functions have not taken place 4.5 XXX 000003 Dropped Control Rod /1 000005 Inoperable/Stuck Control Rod /1 000024 Emergency Boration /1 R

42024 2422 Emergency Procedures / Plan: Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

3.0 XXX 000024 Emergency Boration /1 S

42024 AA205 Ability to determine and interpret the following as they apply to the Emergency Boration: Amount of boron to add to achieve required SDM. 10 CFR 43.5 3.9 XXX 000028 /Pzr Level Malfunction /2 S

42028 AA212 Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Cause for PZR level deviation alarm: controller mal-function or other instrumentation malfunction.

10 CFR 43.5 3.5 XXX 000032 Loss of Source Range NI

/7 000033 Loss of Intermediate Range NI /7 000036 /Fuel Handling Accident /8 R

42036 AA102 Ability to operate and / or monitor the following as they apply to the Fuel Handling Incidents: ARM system 3.1 XXX 000037 SG Tube Leak /3 R

42037 AK303 Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: Comparison of makeup flow and letdown flow for various modes of operation 3.1 XXX 000051 Loss of Condenser vacuum

/4 R

42051 AA202 Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip 3.9 XXX 000051 Loss of Condenser vacuum

/4 S

42051 2132 Conduct of Operations: Ability to explain and apply all system limits and precautions.

3.8 XXX 000059 Accidental Liquid RadWaste Rel. /9 000060 Accidental Gaseous Radwaste Rel./9 R

42060 AK104 Knowledge of the operational implications of the following concepts as they apply to Accidental Gaseous Radwaste Release: Calculation of offsite doses due to a release from the power plant 2.5 XXX 000061 ARM System Alarms /7

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Emergency and Abnormal Plant evolutions - Tier 1 Group 2 (RO/SRO)

Form ES-401-2 Confidential Page 5 E/APE #/Name/Safety Function K

1 K

2 K

3 A

1 A

2 G Number K/A Topics Imp.

RO #

SRO #

000067 Plant Fire on Site /8 R

42067 AA213 Ability to determine and interpret the following as they apply to the Plant Fire on Site: Need for emergency plant shutdown 3.3 XXX 000068 Control Room Evac. /8 000069 W/E14 Loss of CTMT Integrity /5 000074 W/E06&E07Inadequate Core Cooling /4 000076 High Reactor Coolant Activity /9 R

42076 AK305 Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity: Corrective actions as a result of high fission-product radioactivity level in the RCS 2.9 XXX 000076 High Reactor Coolant Activity /9 S

42076 249 Emergency Procedures / Plan: Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies. 10 CFR 43.5 3.9 XXX W/EO1 & E02 Rediagnosis & SI Termination / 3 R

45E02 EK22 Knowledge of the interrelations between the (SI Termination) and the following: 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.

3.5 XXX W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 S 45W/E15 234 Radiation Control: Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. 10 CFR 43.4 3.1 XXX W/E16 High Containment Radiation / 9 K/A Category Totals RO

/

SRO 1 1 2 1 3

/

2 1

/

3 Group Point Total 9

5

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO)

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

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Number K/A Topics Imp.

RO#

SRO#

003 Reactor Coolant Pump R

34003 A101 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including: RCP vibration 2.9 XXX 003 Reactor Coolant Pump S

34003 A203 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems. 10 CFR 43.5 3.1 XXX 004 Chemical and Volume Control R

31004 2128 Conduct of Operations: Knowledge of the purpose and function of major system components and controls.

3.2 XXX 004 Chemical and Volume Control S

32004 A209 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: High primary and/or secondary activity. 10 CFR 43.5 3.9 XXX 005 Residual Heat Removal R

34005 K306 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: CSS 3.1 XXX 006 Emergency Core Cooling R

33006 K201 Knowledge of bus power supplies to the following: ECCS pumps 3.6 XXX 006 Emergency Core Cooling R

33006 A402 Ability to manually operate and/or monitor in the control room: Valves 4.0 XXX 007 Pressurizer Relief/Quench Tank R

35007 A203 Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Overpressurization of the PZR 3.6 XXX 008 Component Cooling Water R

38008 A303 Ability to monitor automatic operation of the CCWS, including: All flow rate indications and the ability to evaluate the performance of this closed-cycle cooling system.

3.0 XXX

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO)

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

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Number K/A Topics Imp.

RO#

SRO#

010 Pressurizer Pressure Control R

33010 K303 Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: ESFAS 4.0 XXX 012 Reactor Protection R

37012 K501 Knowledge of the operational implications of the following concepts as the apply to the RPS: DNB 3.3 XXX 012 Reactor Protection R

37012 K601 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Bistables and bistable test equipment 2.8 XXX 013 ESFAS R

32013 K406 Knowledge of ESFAS design feature(s) and/or intelock(s) which provide for the following: Recirculation actuation system reset 4.0 XXX 013 ESFAS S

32013 A206 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent ESFAS Actuation.

4.5 XXX 022 Containment Cooling R

35022 A301 Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation 4.1 XXX 022 Containment Cooling R

35022 A401 Ability to manually operate and/or monitor in the control room: CCS fans 3.6 XXX 026 Containment Spray R

35026 A203 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of ESF 4.1 XXX 039 Main and Reheat Steam R

34039 217 Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

3.7 XXX 056 Condensate R

34056 K103 Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: MFW.

2.6 XXX 059 Main Feedwater R

34059 A107 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including: Feed Pump speed. (ICS is N/A for Wolf Creek.)

2.5 XXX 059 Main Feedwater R

34059 A306 Ability to monitor automatic operation of the MFW, including: Feedwater isolation 3.2 XXX

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO)

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

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Number K/A Topics Imp.

RO#

SRO#

061 Auxiliary Feedwater R

34061 K501 Knowledge of the operational implications of the following concepts as the apply to the AFW: Relationship between AFW flow and RCS heat transfer 3.6 XXX 062 AC Electrical Distribution R

36062 K301 Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: Major system loads 3.5 XXX 063 DC Electrical Distribution R

36063 K402 Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following:

Breaker interlocks, permissives, bypasses and cross-ties.

2.9 XXX 064 Emergency Diesel Generator R

36064 K105 Knowledge of the physical connections and/or cause-effect relationships between the ED/G system and the following systems: Starting air system 3.4 XXX 064 Emergency Diesel Generator R

36064 K608 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Fuel oil storage tanks 3.2 XXX 073 Process Radiation Monitoring R

37073 239 Radiation Control: Knowledge of the process for performing a containment purge.

2.5 XXX 073 Process Radiation Monitoring S

37073 236 Radiation Control: Knowledge of the requirements for reviewing and approving release permits. 10 CFR 43.4 3.1 XXX 076 Service Water R

34076 K201 Knowledge of bus power supplies to the following:

Service Water 2.7 XXX 076 Service Water R

34076 K301 Knowledge of the effect that a loss or malfunction of the SWS will have on the following: Closed cooling water 3.4 XXX 078 Instrument Air R

38078 A401 Ability to manually operate and/or monitor in the control room: Pressure gauges 3.1 XXX 103 Containment R

35103 A301 Ability to monitor automatic operation of the containment system, including: Containment isolation 3.9 XXX K/A Category Point totals RO

/

SRO 2

2 4

2 2

2 2

2

/

3 4

3 3

/

1 Group Point Total 28 4

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 2 (RO/SRO)

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

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Number K/A Topics Imp.

RO#

SRO#

001 Control Rod Drive R

31001 A104 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CRDS controls including: PZR level and pressures 3.7 XXX 002 Reactor Coolant R

32002 A104 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including: Subcooling Margin 3.9 XXX 011 Pressurizer Level Control R

32011 K301 Knowledge of the effect that a loss or malfunction of the PZR LCS will have on the following: CVCS 3.2 XXX 014 Rod Position Indication R

31014 A402 Ability to manually operate and/or monitor in the control room:

Control rod mode-select switch 3.4 XXX 015 Nuclear Instrumentation 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 H2 Recombiner and Purge Control R

35028 K502 Knowledge of the operational implications of the following concepts as they apply to the HRPS: Flammable hydrogen concentration 3.4 XXX 028 H2 Recombiner and Purge Control S

35028 239 Radiation Control: Knowledge of the process for performing a containment purge. 10 CFR 43.4 3.5 XXX 029 Containment Purge R

35029 2132 Conduct of Operations: Ability to explain and apply all system limits and precautions.

3.4 XXX 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator R

34035 K602 Knowledge of the effect of a loss or malfunction on the following will have on the S/GS: Secondary PORV 3.1 XXX 041 Steam Dump/Turbine Bypass Control R

34041 K505 Knowledge of the operational implications of the following concepts as the apply to the SDS: Basis for RCS design pressure limits 2.6 XXX 045 Main Turbine Generator 055 Condenser Air Removal S

34055 2225 Equipment Control: Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

2.5 XXX 068 Liquid Radwaste R

39068 K107 Knowledge of the physical connections and/or cause effect relationships between the Liquid Radwaste System and the following systems: Sources of liquid wastes for LRS 2.7 XXX 071 Waste Gas Disposal

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 2 (RO/SRO)

Form ES-401-2 Confidential Page 10 System #/Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Number K/A Topics Imp.

RO#

SRO#

072 Area Radiation Monitoring 075 Circulating Water R

38075 K102 Knowledge of the physical connections and/or cause-effect relationships between the circulating water system and the following systems: Liquid radwaste discharge 2.9 XXX 079 Station Air 086 Fire Protection K/A Category Point totals RO

/

SRO 2 2 1 2 - - 1 1

/

2 Group Point Total 10 2

WCNOC NRC License Examination May 7, 2004 PWR Examination outline Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Confidential Page 11 RO SRO-Only Category K/A #

Topic Imp.

Imp.

2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

3.0 XXX 2.1.12 Ability to apply technical specifications for a system. 10 CFR 43.5 4.0 XXX 2.1.14 Knowledge of system status criteria which require the notification of plant personnel. 10 CFR 43.5 3.3 XXX 2.1.20 Ability to execute procedure steps.

4.3 XXX

1.

Conduct of Operations Subtotal 2

2 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity 3.7 XXX 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations. 10 CFR 43.5 3.6 XXX 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits 2.5 XXX 2.2.33 Knowledge of control rod programming. 10 CFR 43.6 2.9 XXX

2.

Equipment Control Subtotal 2

2 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. 10 CFR 43.4 3.0 XXX 2.3.2 Knowledge of facility ALARA program.

2.5 XXX 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release. 10 CFR 43.4 3.2 XXX 2.3.11 Ability to control radiation releases.

2.7 XXX

3.

Radiation Control Subtotal 2

2 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

2.9 XXX 2.4.6 Knowledge of sympton based EOP mitigation strategies.

3.1 XXX 2.4.9 Knowledge of low power / shutdown implications in accident (e.g.

LOCA or loss of RHR) mitigation strategies.

3.3 XXX 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies. 10 CFR 43.5 3.6 XXX 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications.

3.8 XXX

4.

Emergency Procedures

/ Plan Subtotal 4

1 Tier 3 Point Total 10 7

Appendix D Scenario Outline Form ES-D-1 Facility: Wolf Creek_ Scenario No.: One (NEW)

Op-Test No.: One Revision 03 Examiners:

Operators:

Initial Conditions:

100% Power, MOL A MDAFWP is OOS for bearing replacement.

__________________S Safety Injection Pump is OOS for Oil Change______________

Severe Thunderstorm Watch for Coffey County.

Turnover: Maintain current plant conditions.

Event No.

Malf.

No.

Event Type*

Event Description 1

T+1 mMSS 13 I (BOP)

Steam Header Pressure Channel fails low. (Affects both MFPs) 2 T+11 mPRS 03A C (RO)

Pzr Spray Valve fails full open in Automatic.

3 T+18 mEPS 06B C (ALL)

Vital 4160volt NB02 bus lockout 4

T+38 N/A N (BOP)

R (RO)

Tech Spec Required Shutdown due to loss of two AFW pumps.

5 T+48 mFWM 20 M (ALL)

Main Feed Line break in Turbine Building 6

T+54 mAFW 02B C (BOP)

TDAFW pump fails. Entry to FR-H1.

7 T+60 IOR P0105 5B C (RO)

A CCP fails to Auto Start on Safety Injection.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility: Wolf Creek_ Scenario No.: 2 (MODIFIED) Op-Test No.: One Revision 03 Examiners:

Operators:

Initial Conditions:

100% Power, MOL NCP is OOS for bearing replacement.

Turnover: Maintain current plant conditions.

Event No.

Malf.

No.

Event Type*

Event Description 1

T+1 mPRS 01C I (RO)

PZR Pressure Channel Fails High 2

T+17 mMSS 07C C (BOP)

C S/G ARV fails open in auto, manual available.

3 T+26 mFWM 03B C (BOP)

B S/G MFRV fails closed in auto, manual available.

4 T+34 mNIS 03C I (RO)

Nuclear Instrumentation Channel NI-43 fails high.

5 T+45 mRCS 06A M (ALL)

SSE/OBE escalates to Loss of Offsite Power, LBLOCA.

6 T+49 mDGS 02A/B C (RO)

Both EDGs fail to Auto Start.

7 T+70 rBN881 2A C (RO)

A Train RWST suction to RHR fails to align during EMG ES-12, Transfer to Cold Leg Recirc

Appendix D Scenario Outline Form ES-D-1 Facility: Wolf Creek Scenario No.: 3 B/U (NEW)

Op-Test No.: One Revision 03 Examiners:

Operators:

Initial Conditions: 30% increasing power, Ready to Enter Gen 00-004 Turnover: Prepare to continue power increase to 100%

Event No.

Malf.

No.

Event Type*

Event Description 1

T+1 mFWM 02C4 I (BOP)

C S/G Controlling Level Channel fails high.

2 T+11 mCVC 13C C (RO)

Normal Charging Pump Trips 3

T+19 mCVC 06A C

(ALL)

Excessive Seal Leak Off A RCP.

4 T+45 mRCS 02A M

(ALL)

S/G Tube Rupture develops on A S/G requiring Rx Trip/SI.

5 T+48 p19019 B &

p19028 B

C (RO)

Both ESW pumps fail to auto start on Safety Injection.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor