ML17292A560
| ML17292A560 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/01/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9610280152 | |
| Download: ML17292A560 (19) | |
Text
CATEG RY 2 REGULATE INFORMATION DISTRIBUTIONOESTEM (RIDE)
'ACCESSION NBR:9610280152 DOC.DATE: 96/05/01 NOTARIZED:
NO DOCKET
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FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 "AUTH.NAME AUTHOR ~AFFI LIAT ION
, Region 4 (Post 820201)
RECIP.NAME RECIPIENT AFFILIATION J-s=~,
Document Control Branch (Document Control Desk)
SUBJECT:
Forwards NRC Approved Operator Licensing Exam (facility outline 6 initial exam submittal) for tests administered on 960325-28.
DISTRIBUTION CODE:
A070D COPIES RECEIVED:LTR;'NCL SIZE:
TITLE: Written and Operating Exam NOTES:
INTERNAL:
RECIPIENT ID CODE/NAME ENTER COPIES LTTR ENCL RECIPIENT ID CODE/NAME NRR/DRCH/HOLB COPIES LTTR ENCL 1
E EXTERNAL: NRC PDR D
0 E
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR Y
ENCL 3
sl
/ '
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 COUNT MATRIX Summarizing Counts by K/A Group for BWR - Senior Reactor Operator Plant Wide Generics Kl K2 K3 K4 K5 K6 Al A2 A3 A4 SG Total 12 Plant Systems I Plant Systems II Plant Systems III 3
1 0
1 1
3 4
1 1
3 0
0 1
0 1
2 1
2 0
1 2
0 0
0 23 13 Emergency/Abn I Emergency/Abn II 2
6 2
3 2
4 3
2 26 17 Totals 9
ll 9
8 1
7 11 15 Model Total 95 96i0280i52 96050i PDR ADQCK 05000397 V
0 I
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 PLANT-WIDEGENERIC RESPONSIBILITIES BWR - Senior Reactor Operator Target: 17%
- Actual:
17%
Topic RO/SRO Rating 1.
294001K102 2.
294001K103 3.
294001K107 4.
294001K108 5.
29400 1K114 6.
294001 K116 7.
29400lA 103 8.
294001A108 9.
294001 A111 10.
294001A113 11.
294001A115 12.
294001 A116 Knowledge of tagging and clearance procedures.
Knowledge of 10 CFR 20 and related facility radiation control requirements.
Knowledge of safety procedures related to electrical equipment.
Knowledge of safety procedures related to high pressure.
Knowledge of safety procedures related to confined spaces.
Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
Abilityto locate and use procedures and directives related to shift staffing and
~
activities.
Abilityto obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.
Abilityto direct personnel activities inside the control room.
Abilityto locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
Abilityto use plant computer to obtain and evaluate parametric information on system or component status.
Abilityto take actions called for in the Facility Emergency Plan, including (if required) supporting or acting as the Emergency Coordinator.
3.9/4.5 3.3/3.8 3.3/3.6 3.1/3.8 3.2/3.4 3.5/3.8 2.7/3.7 3.1/3.7 3.3/4.3 4.5/4.3 3.2/3.4 2.9/4.7
- NOTE: It is intended that 17 of 100 questions be written utilizing the above 12 selected KAs.
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 PLANT SYSTEMS - GROUP I BWR - Senior Reactor Operator Target: 23%
Actual: 23%
1.
201005 A402 2.
203000K401 Topic (Systems - Group I)
Abilityto manually operate and/or monitor in the control room: Rod display module (lights and push buttons).
(Rod Control and Information System)
Design feature(s) and/or interlocks which provide for Automatic system initiationlinjection (RHR/LPCI: Inj. mode)
RO/SRO Rating 3.7/3.7 4.2/4.2 3.
209001K602 Effect that a loss or malfunction of the Emergency generators willhave on the 3.8/3.9 LPCS system. (LPCS) 4.
209002 K407 HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) design feature(s) and/or interlocks which provide for the override ofreactor water level interlock.
(HPCS) 3.5/3.7 5.
211000K105 Physical connections and/or cause-effect relationships bctwecn SLC system and 3.4/3.6 RWCU. (SLC) 6.
212000 K302 7.
212000A308 Effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on Primary containment isolation systemlnuclear steam supply shut-off.
(RPS)
Monitor automatic operations of the REACTOR PROTECTION SYSTEM including Recirculation pump trip. (RPS) 3.7/3.9 3.7/3.7 8.
215005 K301 9.
216000K302 10.
216000K506 Knowledge of the effect that a loss or malfunction of the APRM/LPRM system 4.0/4.0 will have on RPS. (APRM/LPRM)
Knowledge of the effect that a loss or malfunction of the NUCLEAR BOILER 4.0/4.3 Instrumentation willhave on PC/$/NSSSS. (NBI)
Operational implications of rapid vessel depressurization effects on vessel level 3.4/3.6 indications as it applies to NUCLEAR BOILER INSTRUMENTATION.(NBI) 11.
217000A215 12.
218000 K201 13.
218000A301 14.
223002 G008 15.
223002A102 16.
239002K108 Predict the impacts of the following on RCIC and based on those predictions, use procedures to correct, control, or mitigate the consequences of a steam line break. (RCIC)
Electrical power supplies to the ADS logic. (ADS)
Abilityto monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including: ADS valve operation. (ADS)
Knowledge of annunciators alarms and indications, and use of the response instructions. (NSSSS)
Predict and/or monitor changes in parameters associated with operating the PRIMARYCONTAINMENTISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including valve closures.
(NSSSS)
Physical connections and/or cause-effect relationships between RELIEF/SAFETY VALVES and the Automatic depressurization system.
(Relief/safety valves) 3.8/3.8 3.1/3.3 4.2/4.3 3.7/3.6 3.7/3.7 4.0/4.1
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 17.
241000K102 18.
241000K612 19.
259002K602 20.
261000A213 Topic (Systems - Group I)
Physical connections and/or cause-effect relationships between REACTOR/TURBINE PRESSURE REGULATINGSYSTEM and reactor pressure.
(DEH)
Effect that a loss or malfunction of the Controllgovernor valves will have on the REACTOR/TURBINE PRESSURE REGULATINGSYSTEM.
(DEH)
Effect that a loss or malfunction of A.C. power will have on the REACTOR WATER LEVELCONTROL SYSTEM. (FWLC)
Predict the impacts of high secondary containment ventilation exhaust radiation on the STANDBY GAS TREATMENTSYSTEM; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations.
(SGT)
RO/SRO Rating 3.9/4.1 3.3/3.4 3.3/3.4 3.4/3.7 21.
26200+1 406 22.
262001K602 Effect that a loss or malfunction of Ogsite popover willhave on the A.C.
ELECTRICALDISTRIBUTION. (AC) 3.6/3.9 A.C. ELECTRICALDISTRIBUTIONdesign feature(s) and/or interlocks which 3.6/3.9 provide for redundant power sources to vital buses. (AC) 23.
264000K402 EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for Emergency generator trips (emergency/LOCA).
(DG) 4.0/4.2
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 PLANT SYSTEMS - GROUP II BWR - Senior Reactor Operator Target: 13%
Actual:
13%
1.
201001A210 2.
20 1002 A202 3.
201004K403 4.
201006A405 5.
202001K411 Topic (Systems - Group II)
Predict the impacts of low HCU accumulator pressure/high level on the CONTROL ROD DRIVE HYDRAULICSYSTEM and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. (CRDH)
Predict the impacts of a rod drift alarm on the REACTOR MANUAL CONTROL SYSTEM and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. (RMCS)
ROD SEQUENCE CONTROL SYSTEM design feature(s) and/or interlocks which provide for withdraw rod blocks. (RSCS)
Manually operate and/or monitor in the control room: rod insert error indication. (RWM)
RECIRCULATION System design feature(s) and/or interlocks which provide for limitation ofrecirculation pumps flow mismatch. (RRC)
RO/SRO Rating 3.5/3.6 3.2/3.3 3.3/3.4 3.2/3.2 3.1/3.5 6.
204000A301 Monitor automatic operations of the REACTOR WATER CLEANUP SYSTEM 3.3/3.3 including: system pressure downstream ofthe pressure regulating valve.
(RWCU) 7.
205000K403 8.
215003 A105 9.
219000A414 10.
245000A305 11.
259001K602 12.
262002K301 13.
271000K102 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which provide for the following: low reactor water level. (RHR-SDC)
Predict and/or monitor changes in parameters associated with operating the INTERMEDIATERANGE MONITOR (IRM) SYSTEM controls including:
SCRAM and rod block trip setpoints. (IRM)
Manually operate and/or monitor in the control room: the overrides for suppression pool cooling valve logic.
Monitor automatic operations of the MAINTURBINE GENERATOR AND AUXILIARYSYSTEMS including: control valve operation. (MT Gen & Aux)
Effect that a loss or malfunction of the Condensate system willhave on the REACTOR FEEDWATER SYSTEM. (RFW)
Effect that a loss or malfunction of the UNINTERRUPTABLEPOWER SUPPLY (A.C./D.C.) willhave on water level control. (UPS)
Physical connections and/or cause-effect relationships between OFFGAS SYSTEM and the Process radiation monitoring system. (OG) 3.8/3.8 3.9/3.9 3.7/3.5 3.0/3.1 3.3/3.4 3.1/3.3 3.1/3.3
N
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 PLANT SYSTEMS - GROUP III BWR - Senior Reactor Operator Target: 4%
Actual: 4%
Topic (Systems - Group III) 1.
201003K402 CONTROL ROD AND DRIVE MECHANISMdesign feature(s) and/or interlocks which provide for the following: detection ofan uncoupled rod.
(CRDM)
RO/SRO
)Rating 3.8/3.9 2.
233000K102 3.
239001K201 4.
256000A206 Physical connections and/or cause-effect relationships between FUEL POOL COOLING AND CLEAN-UP and the Residual heat removal system. (FPC)
Electrical power supplies to the Main steam isolation valve solenoids. (MS)
Predict thc impacts of low hottvell level on the REACTOR CONDENSATE SYSTEM; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. (COND)
Al 2.9/3.0 3.2/3.3 3.2/3.2
l
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 EMERGENCY & ABNORMALPLANT EVOLUTIONS - GROUP I BWR - Senior Reactor Operator Target: 26%
Actual: 26%
K/A 1.
295003 K203 2.
295003A202 3.
295003G010 4.
29500 6A206 5.
295006 G002 6.
295007K304 Topic (Emerg. &Abn. - Group I)
Interrelations between PARTIALOR COMPLETE LOSS OF A.C. POWER and the A.C. electrical distribution system.
(Partial or complete loss of A.C. Power)
Determine and/or interpret the following as they apply to PARTIALOR COMPLETE LOSS OF A.C. POWER: Reactor power, pressure, and level.
(Partial or Complete Loss of A.C. Power)
Abilityto perform without reference to procedures those actions that require immediate operation of system components or controls. (Partial or Complete Loss of A.C. Power)
Determine and/or interpret the following as they apply to SCRAM: cause of."
reactor SCR4M. (SCRAM)
Knowledge of which events related to system operation/status should be reported to outside agencies.
(SCRAM)
Reasons for the following responses as they apply to HIGH REACTOR PRESSURE: Safety/relief valve operation.
(High Reactor Pressure)
RO/SRO Rating 3.7/3.9 4.2/4.3 3.9/4.1 3.5/3.8 3.0/4.5 4.0/4.1 7.
295009K201 Knowledge of the interrelations between LOW REACTOR WATER LEVEL 3.9/4.0 and the following: Reactor water level indication.
(Low Reactor Water Level) 8.
295010A201 9.
295013K302 10.
295014K205 11.
295016K201 12.
295017 K206 13.
295023 G010 14.
295024K304 15.
295024A111 Determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Leak rates.
(High Drywell Pressure)
Reasons for the following responses as they apply to HIGH SUPPRESSION POOL TEMPERATURE: Limiting heat additions. (High Suppression Pool Temp)
Interrelations between INADVERTENTREACTIVITYADDITIONand the following: Neutron monitoring system. (Inadvertent Reactivity Addition)
Interrelations between CONTROL ROOM ABANDONMENTand the following: Remote shutdown'anel.
(Control Room Abandonment)
Interrelations between HIGH OFF-SITE RELEASE RATE and the following:
Site emergency plan.
(High Off-Site Release Rate)
Abilityto perform without reference to procedures those actions that require immediate operation of system components or controls. (Refueling Accidents)
Reasons for the following responses as they apply to HIGH DRYWELL PRESSURE: Emergency depressurization.
(High Drywell Pressure)
Operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: Drpvell spray.
(High Drywell Pressure) 3.4/3.8 3.6/3.8 4.0/4.1 4.4/4.5 3.4/4.6 3.8/3.9 3.7/4.1 4.2/4.2
0
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR4122, Rev. 5 16.
295025K103 17.
295025K204 18.
295025G012 19.
295026G008 20.
295030A106 Topic (Emcrg. & Abn. - Group I)
Operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE: Safety/relief valve tailpipe temperatttre/pressure relationships. (High Reactor Pressure)
Interrelations between HIGH REACTOR PRESSURE and the following:
ARl/RPT/ATIVS. (High Reactor Pressure)
Abilityto utilize symptom based procedures.
(High Reactor Pressure)
Abilityto recognize indications for system operating parameters which are entry-level conditions for technical specifications. (Suppression Pool High Water Temperature)
Operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Condensate storage and transfer (make-up to the suppression pool).
(Low Suppression Pool Water Level)
RO/SRO Rating 3.6/3.8 3.9/4.1 3.9/4.5 3.6/4.5 3.4/3.4 21.
295030G011 Abilityto recognize abnormal indications for system operating parameters which 4.3/4.5 are entry-level conditions for emergency and abnormal operating procedures.
(Low Suppression Pool Water Level) 22.
295031K103 23.
295031A204 24.
295031G012 25.
295037K303 26.
295038G011 Operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL: Water level effects on reactor power.
(Reactor Low Water Level)
Determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling.
(Reactor Low Water Level)
Abilityto utilize symptom based procedures.
(Reactor Low Water Level)
Reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Lowering reactor water level.
(SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown)
Abilityto recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
(High Off-Site Release Rate) 3.7/4.1 4.6/4.8 3.9/4.5 4.1/4.5 4.2/4.5
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR4122, Rev. 5 EMERGENCY & ABNORMALPLANT EVOLUTIONS - GROUP II BWR - Senior Reactor Operator Target: 17%
Actual:
17%
l.
295001A201 2.
295002G010 3.
295004 A202 4.
29500SA 102 5.
295008 K202 Topic (Emerg. & Abn. - Group II)
Determine and/or interpret the following as they apply to PARTIALOR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:Powerlflow map. (Partial or Complete Loss of Forced Core Flow Circulation)
Abilityto perform without reference to procedures those actions that require immediate operation of system components or controls.
(Loss of Main Condenser Vacuum)
Determine and/or interpret the following as they apply to PARTIALOR COMPLETE LOSS OF D.C. POWER: Extent ofpartial or complete loss of D.C. power.
(Partial or Complete Loss of D.C. Power)
Operate and/or monitor the following as they apply to MAINTURBINE GENERATOR TRIP: RPS.
(Main Turbine Generator Trip)
Interrelations between HIGH REACTOR WATER LEVELand the following:
Reactor feedwarer system.
(High Reactor Water Level)
RO/SRO Rating 3.5/3.8 3.8/3.7 3.5/3.9 3.6/3.6 3.6/3.8 6.
2950 12G011 Abilityto recognize abnormal indications for system operating parameters which 4.1/4.4 are entry-level conditions for emergency and abnormal operating procedures.
(High Drywell Temperature) 7.
295018K101 8.
295019 G010 Operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on componenf/system operations.
(Partial or Complete Loss of Component Cooling Water)
Abilityto perform without reference to procedures those actions that require immediate operation of system components or controls.
(Partial or Complete Loss of Instrument Air) 3.5/3.6 3.7/3.4 9.
295020K201 Interrelations between INADVERTENTCONTAINMENTISOLATION and the 3.6/3.7 following: Main steam system.
(Inadvertent Containment Isolation) 10.
295021K103 11.
295022G010 12.
295P28K301 13.
295029G012 14.
295032G011 Operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING: Adequate core cooling.
(Loss of Shutdown Cooling)
Abilityto perform without reference to procedures those actions that require immediate operation of system components or controls.
(Loss of CRD Pumps)
Reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE: Emergency depressurizarion.
(High Drywell Temperature)
Abilityto utilize symptom based procedures.
(High Suppression Pool Water Level)
Abilityto recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
(High Secondary Containment Area Temperature) 3.9/3.9 3.7/3.5 3.6/3.9 3.6/4.4 4.1/4.2
Facility: WNP2 Knowledge and AbilityRecord Form Exam date: March 25, 1996 ref: NUREG/BR-0122, Rev. 5 K/A Topic (Emerg. & Abn. - Group II)
RO/SRO Rating 15.
295034K206 Interrelations between SECONDARY CONTAINMENTVENTILATIONHIGH 3.9/4.2 RADIATIONand the following: PCISINSSSS.
(Secondary Containment Ventilation High Radiation) 16.
295035A 101 17.
29503 6A102 Operate and/or monitor the following as they apply to SECONDARY CONTAINMENTHIGH DIFFERENTIALPRESSURE: Secondary containment ventilation system.
(Secondary Containment High Differential Pressure)
Operate and/or monitor the following as they apply to SECONDARY CONTAINMENTHIGH SUMP/AREA WATER LEVEL: Affected systems so as to isolate damaged portions.
(Secondary Containment High Sump/Area Water Level) 3.6/3.6 3.5/3.6 10