ML042080222
| 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 Describe activity to be performed:
(see Note)
(BANK)
Conduct of Operations Conduct of Operations: Ability to recognize indications for system 2.1.33 operating parameters which are entry-level conditions for technical specifications.
RO A1.a Perform Surveillance Test for AFD (NEW)
Conduct of Operations Conduct of Operations: Ability to evaluate plant performance and make 2.1.7 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
RO A1.b Given Data, complete a 1/M plot and determine estimated critical rod position (Alternate Success Path)
(NEW)
Equipment Control 2.2.12 Equipment Control: Knowledge of surveillance procedures.
RO A2 Given Data, Complete the Surveillance Test Data sheet identifying and documenting any out of spec readings.
(MODIFIED BANK)
Radiation Control Radiation Control: Knowledge of 10 CFR: 20 and related facility 2.3.1 radiation control requirements RO A3 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 Describe activity to be performed:
(see Note)
(Bank)
Conduct of Operations Conduct of Operations: Ability to recognize indications for system 2.1.33 operating parameters which are entry-level conditions for technical specifications.
SRO A1.a Review Surveillance Test for AFD and based on results determine any required actions. (Alternate Success Path)
(NEW)
Conduct of Operations 2.1.20 Conduct of Operations: Ability to execute procedure steps.
SRO A1.b Given initial plant conditions of a SG tube leak, determine from the OFN the required actions.
Equipment Control (2001 Exam Bank) 2.2.23 Equipment Control: Ability to track limiting conditions for operations.
Given a sequence of events, Determine the end time of an SRO A2 LCO including any extensions.
(NEW)
Radiation Control 2.3.6 Radiation Control: Knowledge of the requirements for reviewing and approving release permits.
SRO A3 Given a Release Permit, Review for Technical Accuracy.
(Modified Bank)
Emergency Plan Emergency Procedures / Plan: Knowledge of the emergency action 2.4.41 level thresholds and classifications.
SRO A4 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 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)
Safety System / JPM Title Type Code*
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) 8 (2001 Exam) DSL
- f. (S6) Rx Start Up, 10-8 amps to Point of Adding Heat 7 NASL (701-S)
(RO Only) NS 3
- h. (C1) EMG C-0 , Loss of All AC, Align Alternate 6 Power to Safeguards Bus using the OFN (601-C) NAC 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)
DAP 6 (2001 Exam)
- 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 are to be run concurrent:
S1/S2 S3/S4 S5/S6
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 5 FR-Z2 (501-S) MS
- 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
- 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 Tier Group RO K/A Category Points SRO-Only Points K K K K K K A A A A G Total K A A G Total 1 2 3 4 5 6 1 2 3 4
- 2 *
- 1. 1 2 5 3 2 3 3 18 4 3 7 Emergency &
Abnormal Plant 2 1 1 2 1 3 1 9 2 3 5 Evolutions Tier 3 6 5 3 6 4 27 6 6 12 Totals 1 2 2 4 2 2 2 2 2 4 3 3 28 3 1 4 2.
Plant Systems 2 2 - 1 - 2 1 2 - - 1 1 10 - 2 2 Tier 4 2 5 2 4 3 4 2 4 4 4 38 3 3 6 Totals
- 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 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.
Confidential Page 1
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 K K K A A E/APE #/Name/Safety Function G Number K/A Topics Imp. RO # SRO #
1 2 3 1 2 000007 Reactor Trip - 41007 Knowledge of the reasons for the following as the apply to a reactor trip:
R 4.0 XXX Stabilization - Recovery / 1 EK301 Actions contained in EOP for reactor trip 000007 Reactor Trip - 41007 Emergency Procedures / Plan: Ability to prioritize and interpret the S 3.6 XXX Stabilization - Recovery / 1 2445 significance of each annunciator or alarm.
Knowledge of the operational implications of the following concepts as they 000008 Pressurizer Vapor Space 42008 R apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow 3.2 XXX Accident / 3 AK101 characteristics of open or leaking valves 41009 Ability to determine or interpret the following as they apply to a small break 000009 Small Break LOCA /3 R 4.3 XXX EA239 LOCA: Adequate core cooling 41009 Ability to determine or interpret the following as they apply to a small break 000009 Small Break LOCA /3 S 3.3 XXX EA223 LOCA: RCP operating parameters and limits. 10 CFR 43.5 41011 Knowledge of the interrelations between the and the following Large Break 000011 Large Break LOCA /3 R 2.6 XXX EK202 LOCA: Pumps Knowledge of the interrelations between the Reactor Coolant Pump 42015 000015/17 RCP Malfunctions /4 R Malfunctions (Loss of RC Flow) and the following: RCP indicators and 3.3 XXX AK210 controls Emergency Procedures / Plan: Knowledge of local auxiliary operator tasks 000022 Loss of Rx Coolant 42022 R during emergency operations including system geography and system 2.9 XXX Makeup /2 2435 implications.
42025 Ability to determine and interpret the following as they apply to the Loss of 000025 Loss of RHR System /4 R 3.3 XXX AA204 Residual Heat Removal System: Location and isolability of leaks Ability to determine and interpret the following as they apply to the Loss of 000026 Loss of Comp. Cooling 42026 R Component Cooling Water: The valve lineups necessary to restart the CCWS 2.6 XXX Water /8 AA203 while bypassing the portion of the system causing the abnormal condition 000027 Pzr Press. Ctrl. Sys. Malf. 42027 Knowledge of the interrelations between the Pressurizer Pressure Control R 2.6 XXX
/3 AK203 Malfunctions and the following: Controllers and positioners.
41029 Equipment Control: Ability to manipulate the console controls as required to 000029 ATWS /1 R 4.0 XXX 222 operate the facility between shutdown and designated power levels.
41029 Ability to determine or interpret the following as they apply to a ATWS:
000029 ATWS /1 S 4.4 XXX EA209 Occurrence of a main turbine/reactor trip. 10 CFR 43.5 41038 Ability to determine or interpret the following as they apply to a SGTR:
000038 SG Tube Rupture/3 S 4.6 XXX EA216 Actions to be taken if S/G goes solid and water enters steam line. 10 CFR 43.5 000040 W/E12 Steam Line Rupture /4 Conduct of Operations: Ability to obtain and interpret station reference 42054 000054 Loss of Feedwater /4 R materials such as graphs, monographs, and tables which contain performance 2.8 XXX 2125 data.
Confidential Page 2
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 E/APE #/Name/Safety Function K K K A A G Number K/A Topics Imp. RO # SRO #
1 2 3 1 2 000055 Station Blackout /6 Knowledge of the operational implications of the following concepts as they 42056 000056 /Loss of Off Site Power /6 R apply to Loss of Offsite Power: Definition of subcooling: use of steam tables 3.1 XXX AK103 to determine it 42056 Conduct of Operations: Ability to explain and apply all system limits and 000056 /Loss of Off Site Power /6 S 3.8 XXX 2132 precautions. 10 CFR 43.2 000057 Loss of Vital AC 42057 Ability to operate and / or monitor the following as they apply to the Loss of R 3.8 XXX Instrument Bus /6 AA102 Vital AC Instrument Bus: Manual control of PZR level Ability to determine and interpret the following as they apply to the Loss of 000057 Loss of Vital AC 42057 S Vital AC Instrument Bus: The indicator, valve, breaker, or damper position 3.1 XXX Instrument Bus /6 AA218 which will occur on a loss of power. 10 CFR 43.5 42058 Knowledge of the reasons for the following responses as they apply to the Loss 000058 Loss of DC Power /6 R 3.4 XXX AK301 of DC Power: Use of dc control power by D/Gs Knowledge of the reasons for the following responses as they apply to the Loss 000062 Loss of Nuclear Service 42062 R of Nuclear Service Water: The automatic actions (alignments) within the 3.6 XXX Water /4 AK302 nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air /8 W/E04 LOCA Outside 45E04 Ability to operate and / or monitor the following as they apply to the (LOCA R 3.6 XXX Containment /3 EA12 Outside Containment): Operating behavior characteristics of the facility.
W/E04 LOCA Outside 45E04 Emergency Procedures / Plan: Knowledge of annunciator response S 3.1 XXX Containment /3 2410 procedures. 10 CFR 43.5 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: Facility's heat removal systems, including W/E11 Loss of Emergency 45E11 R primary coolant, emergency coolant, the decay heat removal systems, and 3.9 XXX Coolant Recirc. / 4 EK22 relations between the proper operation of these systems to t he operation of the facility.
Knowledge of the interrelations between the (Loss of Secondary Heat Sink)
W/E05 Inadequate Heat Transfer- 45E05 and the following: Components, and functions of control and safety systems, R 3.7 XXX Loss of Secondary Heat Sink / 4 EK21 including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
K/A Category Totals 3 3 RO 2 5 3 2 / / Group Point Total 18 7
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4 3 SRO Confidential Page 3
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 K K K A A E/APE #/Name/Safety Function G Number K/A Topics Imp. RO# SRO #
1 2 3 1 2 Ability to determine and interpret the following as they apply to the 000001 Continuous Rod 42001 R Continuous Rod Withdrawal: Proper actions to be taken if automatic 4.5 XXX Withdrawal /1 AA203 safety functions have not taken place 000003 Dropped Control Rod /1 000005 Inoperable/Stuck Control Rod /1 42024 Emergency Procedures / Plan: Knowledge of the bases for prioritizing 000024 Emergency Boration /1 R 3.0 XXX 2422 safety functions during abnormal/emergency operations.
Ability to determine and interpret the following as they apply to the 42024 000024 Emergency Boration /1 S Emergency Boration: Amount of boron to add to achieve required 3.9 XXX AA205 SDM. 10 CFR 43.5 Ability to determine and interpret the following as they apply to the 42028 Pressurizer Level Control Malfunctions: Cause for PZR level deviation 000028 /Pzr Level Malfunction /2 S 3.5 XXX AA212 alarm: controller mal- function or other instrumentation malfunction.
10 CFR 43.5 000032 Loss of Source Range NI
/7 000033 Loss of Intermediate Range NI /7 42036 Ability to operate and / or monitor the following as they apply to the 000036 /Fuel Handling Accident /8 R 3.1 XXX AA102 Fuel Handling Incidents: ARM system Knowledge of the reasons for the following responses as they apply to 42037 000037 SG Tube Leak /3 R the Steam Generator Tube Leak: Comparison of makeup flow and 3.1 XXX AK303 letdown flow for various modes of operation Ability to determine and interpret the following as they apply to the 000051 Loss of Condenser vacuum 42051 R Loss of Condenser Vacuum: Conditions requiring reactor and/or 3.9 XXX
/4 AA202 turbine trip 000051 Loss of Condenser vacuum 42051 Conduct of Operations: Ability to explain and apply all system limits S 3.8 XXX
/4 2132 and precautions.
000059 Accidental Liquid RadWaste Rel. /9 Knowledge of the operational implications of the following concepts as 000060 Accidental Gaseous 42060 R they apply to Accidental Gaseous Radwaste Release: Calculation of 2.5 XXX Radwaste Rel./9 AK104 offsite doses due to a release from the power plant 000061 ARM System Alarms /7 Confidential Page 4
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 K K K A A E/APE #/Name/Safety Function G Number K/A Topics Imp. RO # SRO #
1 2 3 1 2 42067 Ability to determine and interpret the following as they apply to the 000067 Plant Fire on Site /8 R 3.3 XXX AA213 Plant Fire on Site: Need for emergency plant shutdown 000068 Control Room Evac. /8 000069 W/E14 Loss of CTMT Integrity /5 000074 W/E06&E07Inadequate Core Cooling /4 Knowledge of the reasons for the following responses as they apply to 000076 High Reactor Coolant 42076 R the High Reactor Coolant Activity: Corrective actions as a result of 2.9 XXX Activity /9 AK305 high fission-product radioactivity level in the RCS Emergency Procedures / Plan: Knowledge of low power / shutdown 000076 High Reactor Coolant 42076 S implications in accident (e.g. LOCA or loss of RHR) mitigation 3.9 XXX Activity /9 249 strategies. 10 CFR 43.5 Knowledge of the interrelations between the (SI Termination) and the following: Facility's heat removal systems, including primary coolant, W/EO1 & E02 Rediagnosis & SI 45E02 R emergency coolant, the decay heat removal systems, and relations 3.5 XXX Termination / 3 EK22 between the proper operation of these systems to the operation of the facility.
W/E13 Steam Generator Over-pressure / 4 Radiation Control: Knowledge of radiation exposure limits and 45W/E15 W/E15 Containment Flooding / 5 S contamination control, including permissible levels in excess of those 3.1 XXX 234 authorized. 10 CFR 43.4 W/E16 High Containment Radiation / 9 K/A Category Totals 3 1 RO 1 1 2 1 / / Group Point Total 9 5
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2 3 SRO Confidential Page 5
WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO) Form ES-401-2 K K K K K K A A A A System #/Name G Number K/A Topics Imp. RO# SRO#
1 2 3 4 5 6 1 2 3 4 Ability to predict and/or monitor changes in parameters (to 34003 003 Reactor Coolant Pump R prevent exceeding design limits) associated with operating 2.9 XXX A101 the RCPS controls including: RCP vibration 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 34003 003 Reactor Coolant Pump S mitigate the consequences of those malfunctions or 3.1 XXX A203 operations: Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems. 10 CFR 43.5 004 Chemical and Volume 31004 Conduct of Operations: Knowledge of the purpose and R 3.2 XXX Control 2128 function of major system components and controls.
Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on 004 Chemical and Volume 32004 those predictions, use procedures to correct, control, or S 3.9 XXX Control A209 mitigate the consequences of those malfunctions or operations: High primary and/or secondary activity. 10 CFR 43.5 005 Residual Heat 34005 Knowledge of the effect that a loss or malfunction of the R 3.1 XXX Removal K306 RHRS will have on the following: CSS 006 Emergency Core 33006 Knowledge of bus powe r supplies to the following: ECCS R 3.6 XXX Cooling K201 pumps 006 Emergency Core 33006 Ability to manually operate and/or monitor in the control R 4.0 XXX Cooling A402 room: Valves Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on 007 Pressurizer 35007 R those predictions, use procedures to correct, control, or 3.6 XXX Relief/Quench Tank A203 mitigate the consequences of those malfunctions or operations: Overpressurization of the PZR Ability to monitor automatic operation of the CCWS, 008 Component Cooling 38008 including: All flow rate indications and the ability to R 3.0 XXX Water A303 evaluate the performance of this closed-cycle cooling system.
Confidential Page 6
WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO) Form ES-401-2 K K K K K K A A A A System #/Name G Number K/A Topics Imp. RO# SRO#
1 2 3 4 5 6 1 2 3 4 010 Pressurizer Pressure 33010 Knowledge of the effect that a loss or malfunction of the R 4.0 XXX Control K303 PZR PCS will have on the following: ESFAS 37012 Knowledge of the operational implications of the 012 Reactor Protection R 3.3 XXX K501 following concepts as the apply to the RPS: DNB Knowledge of the effect of a loss or malfunction of the 37012 012 Reactor Protection R following will have on the RPS: Bistables and bistable test 2.8 XXX K601 equipment Knowledge of ESFAS design feature(s) and/or intelock(s) 32013 013 ESFAS R which provide for the following: Recirculation actuation 4.0 XXX K406 system reset Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based 32013 013 ESFAS S on those predictions, use procedures to correct, control, or 4.5 XXX A206 mitigate the consequences of those malfunctions or operations: Inadvertent ESFAS Actuation.
35022 Ability to monitor automatic operation of the CCS, 022 Containment Cooling R 4.1 XXX A301 including: Initiation of safeguards mode of operation 35022 Ability to manually operate and/or monitor in the control 022 Containment Cooling R 3.6 XXX A401 room: CCS fans Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on 35026 026 Containment Spray R those predictions, use procedures to correct, control, or 4.1 XXX A203 mitigate the consequences of those malfunctions or operations: Failure of ESF Conduct of Operations: Ability to evaluate plant 039 Main and Reheat 34039 performance and make operational judgments based on R 3.7 XXX Steam 217 operating characteristics, reactor behavior, and instrument interpretation.
Knowledge of the physical connections and/or cause-effect 34056 056 Condensate R relationships between the Condensate System and the 2.6 XXX K103 following systems: MFW.
Ability to predict and/or monitor changes in parameters (to 34059 prevent exceeding design limits) associated with operating 059 Main Feedwater R 2.5 XXX A107 the MFW controls including: Feed Pump speed. (ICS is N/A for Wolf Creek.)
34059 Ability to monitor automatic operation of the MFW, 059 Main Feedwater R 3.2 XXX A306 including: Feedwater isolation Confidential Page 7
WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 1 (RO/SRO) Form ES-401-2 K K K K K K A A A A System #/Name G Number K/A Topics Imp. RO# SRO#
1 2 3 4 5 6 1 2 3 4 Knowledge of the operational implications of the 34061 061 Auxiliary Feedwater R following concepts as the apply to the AFW: Relationship 3.6 XXX K501 between AFW flow and RCS heat transfer Knowledge of the effect that a loss or malfunction of the 062 AC Electrical 36062 R ac distribution system will have on the following: Major 3.5 XXX Distribution K301 system loads Knowledge of DC electrical system design feature(s) 063 DC Electrical 36063 R and/or interlock(s) which provide for the following: 2.9 XXX Distribution K402 Breaker interlocks, permissives, bypasses and cross-ties.
Knowledge of the physical connections and/or cause-effect 064 Emergency Diesel 36064 R relationships between the ED/G system and the following 3.4 XXX Generator K105 systems: Starting air system Knowledge of the effect of a loss or malfunction of the 064 Emergency Diesel 36064 R following will have on the ED/G system: Fuel oil storage 3.2 XXX Generator K608 tanks 073 Process Radiation 37073 Radiation Control: Knowledge of the process for R 2.5 XXX Monitoring 239 performing a containment purge.
073 Process Radiation 37073 Radiation Control: Knowledge of the requirements for S 3.1 XXX Monitoring 236 reviewing and approving release permits. 10 CFR 43.4 34076 Knowledge of bus power supplies to the following:
076 Service Water R 2.7 XXX K201 Service Water 34076 Knowledge of the effect that a loss or malfunction of the 076 Service Water R 3.4 XXX K301 SWS will have on the following: Closed cooling water 38078 Ability to manually operate and/or monitor in the control 078 Instrument Air R 3.1 XXX A401 room: Pressure gauges 35103 Ability to monitor automatic operation of the containment 103 Containment R 3.9 XXX A301 system, including: Containment isolation K/A Category Point totals 2 3 RO 2 2 4 2 2 2 2 / 4 3 / Group Point Total 28 4
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3 1 SRO Confidential Page 8
WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 2 (RO/SRO) Form ES-401-2 K K K K K K A A A A System #/Name G Number K/A Topics Imp. RO# SRO#
1 2 3 4 5 6 1 2 3 4 Ability to predict and/or monitor changes in parameters (to prevent 31001 001 Control Rod Drive R exceeding design limits) associated with operating the CRDS 3.7 XXX A104 controls including: PZR level and pressures Ability to predict and/or monitor changes in parameters (to prevent 32002 002 Reactor Coolant R exceeding design limits) associated with operating the RCS controls 3.9 XXX A104 including: Subcooling Margin 32011 Knowledge of the effect that a loss or malfunction of the PZR LCS 011 Pressurizer Level Control R 3.2 XXX K301 will have on the following: CVCS 31014 Ability to manually operate and/or monitor in the control room:
014 Rod Position Indication R 3.4 XXX A402 Control rod mode-select switch 015 Nuclear Instrumentation 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 H2 Recombiner and Purge 35028 Knowledge of the operational implications of the following concepts R 3.4 XXX Control K502 as they apply to the HRPS: Flammable hydrogen concentration 028 H2 Recombiner and Purge 35028 Radiation Control: Knowledge of the process for performing a S 3.5 XXX Control 239 containment purge. 10 CFR 43.4 35029 Conduct of Operations: Ability to explain and apply all system 029 Containment Purge R 3.4 XXX 2132 limits and precautions.
033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 34035 Knowledge of the effect of a loss or malfunction on the following 035 Steam Generator R 3.1 XXX K602 will have on the S/GS: Secondary PORV 041 Steam Dump/Turbine 34041 Knowledge of the operational implications of the following concepts R 2.6 XXX Bypass Control K505 as the apply to the SDS: Basis for RCS design pressure limits 045 Main Turbine Generator 34055 Equipment Control: Knowledge of bases in technical specifications 055 Condenser Air Removal S 2.5 XXX 2225 for limiting conditions for operations and safety limits.
Knowledge of the physical connections and/or cause effect 39068 068 Liquid Radwaste R relationships between the Liquid Radwaste System and the following 2.7 XXX K107 systems: Sources of liquid wastes for LRS 071 Waste Gas Disposal Confidential Page 9
WCNOC NRC License Examination May 7, 2004 PWR Examination outline Plant Systems - Tier 2 Group 2 (RO/SRO) Form ES-401-2 K K K K K K A A A A System #/Name G Number K/A Topics Imp. RO# SRO#
1 2 3 4 5 6 1 2 3 4 072 Area Radiation Monitoring Knowledge of the physical connections and/or cause-effect 38075 075 Circulating Water R relationships between the circulating water system and the following 2.9 XXX K102 systems: Liquid radwaste discharge 079 Station Air 086 Fire Protection K/A Category Point totals 1 RO 2 2 1 2 - - 1 / Group Point Total 10 2
/ 2 SRO Confidential Page 10
WCNOC NRC License Examination May 7, 2004 PWR Examination outline Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Category K/A # Topic RO SRO-Only Imp. # Imp. #
Knowledge of operator responsibilities during all modes of plant 2.1.2 3.0 XXX operation.
2.1.12 Ability to apply technical specifications for a system. 10 CFR 43.5 4.0 XXX 1.
Knowledge of system status criteria which require the notification Conduct of 2.1.14 3.3 XXX of plant personnel. 10 CFR 43.5 Operations 2.1.20 Ability to execute procedure steps. 4.3 XXX Subtotal 2 2 Ability to perform pre-startup procedures for the facility, including 2.2.1 operating those controls associated with plant equipment that could 3.7 XXX affect reactivity Knowledge of the process for managing maintenance activities
- 2. 2.2.18 3.6 XXX during shutdown operations. 10 CFR 43.5 Equipment Knowledge of bases in technical specifications for limiting Control 2.2.25 2.5 XXX conditions for operations and safety limits 2.2.33 Knowledge of control rod programming. 10 CFR 43.6 2.9 XXX Subtotal 2 2 Knowledge of 10 CFR: 20 and related facility radiation control 2.3.1 3.0 XXX requirements. 10 CFR 43.4 2.3.2 Knowledge of facility ALARA program. 2.5 XXX
- 3. Knowledge of the process for performing a planned gaseous Radiation 2.3.8 3.2 XXX radioactive release. 10 CFR 43.4 Control 2.3.11 Ability to control radiation releases. 2.7 XXX Subtotal 2 2 Knowledge of the organization of the operating procedures network 2.4.5 2.9 XXX for normal, abnormal, and emergency evolutions.
2.4.6 Knowledge of sympton based EOP mitigation strategies. 3.1 XXX Knowledge of low power / shutdown implications in accident (e.g.
2.4.9 3.3 XXX
Emergency Knowledge of which events related to system operations/status 2.4.30 3.6 XXX Procedures should be reported to outside agencies. 10 CFR 43.5
/ Plan Knowledge of RO tasks performed outside the main control room 2.4.34 during emergency operations including system geography and 3.8 XXX system implications.
Subtotal 4 1 Tier 3 Point Total 10 7 Confidential Page 11
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 Malf. Event Event No. No. Type* Description 1 mMSS Steam Header Pressure Channel fails low. (Affects both T+1 13 I (BOP) MFPs) 2 mPRS C (RO) Pzr Spray Valve fails full open in Automatic.
T+11 03A 3 mEPS C (ALL) Vital 4160volt NB02 bus lockout T+18 06B 4 N (BOP) Tech Spec Required Shutdown due to loss of two AFW N/A T+38 R (RO) pumps.
5 mFWM M (ALL) Main Feed Line break in Turbine Building T+48 20 6 mAFW C (BOP) TDAFW pump fails. Entry to FR-H1.
T+54 02B 7 IOR P0105 C (RO) A CCP fails to Auto Start on Safety Injection.
T+60 5B
- (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 Malf. Event Event No. No. Type* Description 1 mPRS T+1 01C I (RO) PZR Pressure Channel Fails High 2 mMSS C (BOP) C S/G ARV fails open in auto, manual available.
T+17 07C 3 mFWM T+26 03B C (BOP) B S/G MFRV fails closed in auto, manual available.
4 mNIS T+34 03C I (RO) Nuclear Instrumentation Channel NI-43 fails high.
5 mRCS T+45 06A M (ALL) SSE/OBE escalates to Loss of Offsite Power, LBLOCA.
6 mDGS T+49 02A/B C (RO) Both EDGs fail to Auto Start.
7 rBN881 C (RO) A Train RWST suction to RHR fails to align during EMG T+70 2A ES-12, Transfer to Cold Leg Recirc
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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 Malf. Event Event No. No. Type* Description 1 mFWM I (BOP) C S/G Controlling Level Channel fails high.
T+1 02C4 2 mCVC 13C C (RO) Normal Charging Pump Trips T+11 3 mCVC C 06A (ALL) Excessive Seal Leak Off A RCP.
T+19 4 mRCS M 02A (ALL) S/G Tube Rupture develops on A S/G requiring Rx Trip/SI.
T+45 p19019 5 B& C (RO) Both ESW pumps fail to auto start on Safety Injection.
T+48 p19028 B
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor