ML020440613
| ML020440613 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/07/2002 |
| From: | Gody A NRC Region 4 |
| To: | Maynard O Wolf Creek |
| References | |
| 50-482/01301 | |
| Download: ML020440613 (36) | |
Text
Administrative Topics Outline Facility:
WCGS Date of Examination:
12/10/2001 Examination Level (circle one): &
SRO Operating Test Number:
1 Administrative Describe method of evaluation:
Topic/Subject
Integrated Plant Given the plant data, Calculate an RCS Leak Rate.
Procedures Changed due to new C.O. process released.
(RO Admin A-2)
(CFR 41.10/43.5/45.12, RO 4.3) 2.1.20 Execute Given the Data and procedure, Calculate QPTR.
Procedure Steps (Previously used as an SRO Admin. JPM)
(RO Admin A-3.1)
(CFR 43.2/45.2, RO 3.4)
A.2 2.2.22 LCO's and Safety Question (Open Reference): Given a combination of Power, RCS Limits Pressure and Tavg, determine if a Safety Limit has been violated.
2.2.25 (RO Admin A-3.2)
(CFR 43.2, RO 2.5)
Bases for LCO's Band Safet Limts Question (Open Reference): T.S. LCO Bases. During Surveillance and Safety Limits Testing it is determined that the motor on BG HV-8357A is shorted and the valve will not open. How does this affect the Operability of "A" CCP.
(RO Admin A-4)
(CFR 41.12/43.4/45.9/45.10 RO 2.5)
A.3 2.3.2 ALARA Program While performing the in plant RCA JPM provide a Survey Map and have the applicant determine the allowed stay time and protective clothing requirements for a task.
(RO Admin A-5)
(CFR 41.10/43.5/45.13, RO 3.0)
A.4 2.4.32, The Control Room Supervisor suspects a loss of annunciators. The Knowledge of operator response Shift Manger request you to determine if Annunciator's are affected and to a loss of all what % has been lost.
annunciator Rev 02 11/2001
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Robert-Acres WCGS Exam Author
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"Howard Bundy NRC Chief Examiner DATE Form ES-301-1 (R8, S1)
ES-301 DATE
Administrative Topics Outline Facility:
WGCS Date of Examination:
12/10/2001 Examination Level (circle one):
RO Operating Test Number:
1 Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions (SRO Admin A.1)
(CFR 45.2/45.6, SRO 4.0)
A.1 2.1.23 Integrated Plant Given the plant data, Calculate an RCS Leak Rate.
Procedures (SRO Admin A.2)
(CFR 41.10/43.5/45.12, SRO 3.1) 2.1.25 Obtain and 9 days into a Refueling Outage, Mode 6 with RCS level 3.5 feet below Interpret Station the flange. "A" RHR pump tripped on overcurrent. Attempts to place "B" Reference Train RHR in service have been unsuccessful. Determine the Time to Material Boiling and Time to Core Uncovery. (Modified from an RO Admin. JPM)
(SRO Admin A.3)
(CFR 43.2/45.13, SRO 3.8)
A.2 2.2.23 Ability to track Given a sequence of events, Determine the end time of an LCO LCO's.
including any extensions.
(SRO Admin A.4)
CFR 41.12/43.4/45.9/45.10, SRO 2.9)
A.3 2.3.2 ALARA While performing the in plant RCA JPM provide a Survey Map and have the applicant determine the allowed stay time and protective clothing requirements for a task.
A.4 2.4.41 (SRO Admin A.5)
(CFR 43.5/45.11, SRO 4.1)
Classify an Event Following a Dynamic Scenario, make the E-plan Classification and Protective Action Recommendation.
Rev 02 11/2001 S2/
If-30-D A-
"howard Bundy NRC Chief Examiner
'('I Robert Acre'e r
WCGS Exam Author
/ /ý-?7- 0 ES-301 Form ES-301-1 (R8, $1)
DATE DATE
Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 (R8, 51)
Facility:
WCGS Date of Examination:
12/10/2001 Exam Level (circle one): RO / SRO(I)
Operating Test No.:
1 B.1 Control Room Systems System / JPM Title Type Safety Code*
Function
- a. LRW Release Control Room NAS SF9 C-0158A (S-1)
- b. Swap CCW supply to the Service Loop DS SF8 C-048 (S-2)
- c. Start H2 Analyzers Post LOCA DSL SF5 C-079 (S-3)
- d. Increase ECCS Accumulator Pressure DSL SF3 C-029 (S-4)
- e. Shift Charging Pumps DAS SF2 (Used on Previous Exam)
C-026 (S-5)
B.2 Facility Walk-Through
- a. Isolate ESW Drains (OFN SG-003)
N SF4 T-157 (P-i)
- b. Swap Vital Instrument Bus to the SOLA Xfmr.
D SF6 T-116 (P-2)
- c. Perform Actions for Local Emergency Borate DAR SF1 T-133A (P-3)
- 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 E:am Author Chief Examiner Date ES-301 ZA'_'
// t-zT-7-l Date
Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 (R8, S)
Facility:
WCGS Date of Examination:
12/10/2001 Exam Level (circle one): SRO(U)
Operating Test No.:
1 B.1 Control Room Systems System / JPM Title Type Safety Code*
Function
- a. LRW Release Control Room NAS SF9 C-0158A (S-1)
- b.
- c. Start H2 Analyzers Post LOCA DSL SF5 C-079 (S-3)
- d.
- e.
- f.
- g.
B.2 Facility Walk-Through
- a. Isolate ESW Drains (OFN SG-003)
N SF4 T-157 (P-1)
- b. Swap Vital Instrument Bus to the SOLA Xfmr.
D SF6 T-116 (P-2)
- c. Perform Actions for Local Emergency Borate DAR SF1 T-133A (P-3)
- 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 1/f-2*7-0o Exhm Author Date Chief Examiner Date ES-301
/ IL-SC-C)t WWýý Examn Author Date
- Chief Examiner Date
Appendix D Scenario Outline Form ES-D-1 (RB, SI)
Facility:
WCGS Examiners:
Scenario No.:
1 Op-Test No.:
1 Operators:
See Examiner/Operator assignment sheet. This Scenario will be seen by multiple crews.
Initial Conditions: 100% Power, MOL, "A" CCW pump OOS for PM's.
Turnover: Continue plant operations, make preps to return "A" CCW pump to service.
System Ops reports Grid Stability problems. Weekday Nightshift.
Event Malf.
Event Event No.
No.
Type*
Description 1
mPCS I (All)
AB PT-505 (T-Ref) fails low, Rods begin Inserting, BOP T+1.0 02A verifies no Turbine Runback in progress.
2 mMSS I -BOP AB PT-545 fails low, affects Steam Flow Channel AB FT T+14.0 01 D2 I-CRS 543. BOP take manual Control of "D" SG FRV.
3 mEPS R-RO La Cygne Line in the switchyard opens, System Ops request T+25.0 03A N-BOP expedite load reduction due to Grid problems. Load N-CRS reduction commences to less than 968 Mwe per OFN AF-15.
Using OFN MA-038.
4 mMSS C-All Steam Leak commences in Turbine Building large enough to T+34.0 11 affect downpower.
5 mMSS M-All CRS should direct a Reactor Trip, Upon the trip the leak T+40.0 11 becomes a MSLB. MSIV's will not close.
6 C-RO SI fails to actuate in Automatic. Manual Available. RO/CRS T+43.0 C-CRS must recognize that an SI will be required or the setpoint has already been reached and SI did not actuate.
Uncontrolled de-pressurization of all SG's will require entry into EMG C-21. Scenario terminates after crew establishes 30K Aux Feedwater flow to each SG or at Lead Examiner discretion.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor RbWert Acree WCGS Exam Author Howard Bundy NRC Chief Examiner DATE f
8 Form ES-D-1 (R8, S1)
Appendix D Scenario Outline f
w w
DATE
Appendix D Scenario Outline Form ES-D-1 (R8, SI)
Facility:
WCGS Examiners:
Scenario No.:
2 Op-Test No.:
1 Operators:
See Examiner/Operator assignment sheet. This Scenario will be seen by multiple crews.
Initial Conditions: The core age is Middle of Life (MOL). The plant has been operating at or near 100% Dower for the last 42 days. The "B" train Emergencv Diesel Generator (EDG) and Centrifuqal Charging Pump(CCP) are out of service (OOS) for preventative maintenance. The "D" SG atmospheric relief valve is isolated due to seat leakage. "B" MFP has abnormal vibration.
Turnover: Normal Shift Activities, Weekday Night Shift Event Malf.
Event Event No.
No.
Type*
Description 1
N(SRO)
Downpower maneuver to remove the MFP from service.
T+1.0 R(RO)
VCT divert valve LCV1 12A-control failure T+7.0 01 C(RO)
If the operator has begun to borate it will take 6 minutes to reach the low level alarm(first indication). If boration has not commenced an auto makeup will be his first indication within 1-2 minutes.
3 mNIS-I(SRO)
Power Range NI-41 fails high T+1 7.
Steam Generator "C" level controller fails in automatic causing the T+30 03C l(BOP) feed reg. valve to begin closing. Manual is available.
5 mRCS-M(SRO)
RCS loop A 300 gpm leak T+38 06A M(RO)
The reactor will not trip in manual or automatic. EMG FR-S1 is T+38.5 08A&B C(RO) used to make the reactor subcritical.
Loss of CCW to the RCPs T+58 D (8) 1 C(RO)
P19046 C (8) 0
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
/141ý
/
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Robert Acree WCGS Exam Author
/ (1-o-(
"flowa-rd Bundy NRC Chief Examiner Form ES-D-1 (R8, $1)
Appendix D Scenario Outline DATE DATE
Appendix D Scenario Outline Form ES-D-1 (R8, SI)
Scenario No.:
3 Op-Test No.:
1 Operators:
See Examiner/Operator assignment sheet. This Scenario will be seen by multiple crews.
Initial Conditions:
Reduction from 100% power in progqress. Currently at 48% Power. "B" Main Feed Pump Taggcqed out for maintenance on control valve linkagqe. Severe Thunderstorm Watch in effect for Coffev County.
Turnover:
Continue power OFN AF-025 is in effect reduction to 33% (400MWe) to remove all heater strings.
Event Malf.
Event Event No.
No.
Type*
Description 1
R-RO Continue Power reduction to 33% at 1/2 % per minute.
T+0 N-BOP N-CRS 2
mRCS I-RO Loop 1 Thot fails high causing a rod insertion.
T+7 Oil I-CRS 3
mFWM I-BOP "B" SG Level AE LT-529 fails high.
T+17 0283 I-CRS 4
mEPSO M-All Sequential Loss of Offsite Power, Reactor Trips due to low T+23 1A and RCS flow. NB01 "A" Emergency Bus has a bus Lock Out.
1 B 5
mWAT C-RO "B" ESW pump fails to start. RO/CRS must get "B" ESW T+23 03A C-CRS pump started prior to the EDG overheating causing entry into EMG C-0.
6 mMSS C-BOP "A" SG ARV fails open.
T+33 07E C-CRS (R)eactivity, Revision 1,j1 1/27/2001 (I)nstrument,
///
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(C)omponent, (M)ajor Robjrt)A'r~e WCGS Exam Author Howard Bundy NRC Chief Examiner Facility:
WCGS Examiners:
I I
I I I
-w Jw
- . w Scenario Outline Form ES-D-1 (R8, $1)
Appendix D
- (N)ormal, DATE DATE
Appendix D Scenario Outline Form ES-D-1 (R8, SI)
Scenario No.:
4(Spare)
Op-Test No.:
1 Operators:
Initial Conditions: The plant is at MOL. Unit startup is in progress after a 7 day outage to resolve a voltage requlator problem. Reactor power is at E Amps, Rod control in manual, Startup Feedpump in service, GEN 00-003 is complete through step 6.24.
Turnover: All systems normal, resume startup at step 6.25 of Gen 00-003.
Event Malf.
Event Event Description No.
No.
Type*
1 N (SRO)
Increase reactor power to 1%
PZR pressure channel BB PT-457 fails high T+1 1 01B I (RO) 3 mFW C (SRO)
"B" SG Level Channel AE LT-529 Fails Low T+25 M02B C(BOP) 3 4
mPRS C (SRO)
PORV BB PCV-455A excessive seat leakage. Block valve BB T+35 10A C (RO)
HV-8000A is isolated.
5 mMSS M (SRO)
S/G "B" faulted inside containment T+47 03B M (RO)
MSIV's Fail to close in Automatic T+48 02E-H C (BOP) 7 mPCS C (SRO)
Failure of containment isolation phase A T+53 10A &
C (RO) 10B Terminate after stabilization of RCS after Steam Generator blowdown.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Revision 1/ 1/27/2001 Robert Acr'e WCGS Exam Author
//-
"H-Coward bundy NRC Chief Examiner Facility:
Examiners:
WCGS Scenario Outline Form ES-D-1 (R8, S1)
Appendix D DATE DATE
Record of Reiected K/As Tier Group Randomly Selected K/A Reason for Rejection 1/1 040 AK3.03 Both Exams. WCNOC does not use non-return valves. Changed to AK3.02.
1/2 007 EA2.03 SRO Exam, Not tied to 55.43 SRO topic. 007 Reactor Trip does not have any 55.43 ties. Randomly selected 038 SGTR, EA2.06 1/2 037 AA1.06 Both Exams, WCNOC does not have Steam Line Rad Monitors that would detect a tube leak. Randomly selected KA 037 AA2.12 to replace 2/1 013 K1.03 Both Exams. Replaced to balance exam. Containment Cooling system is tested under KA 011 EA2.06. Changed to K1.05 for CTMT Spray System.
2/1 026 2.1.34 SRO Exam. KA not applicable to CTMT Spray system. Changed to 2.1.33 2/2 086 K5.03 Both Exams. Automatic Electrical System responses to Fire Protection System at WCNOC have been deleted. Changed to K5.04 1/2 001 AA2.02 RO Exam. N/A to WCNOC for Continuous Rod Withdrawal accident. Changed to AA2.03.
2/1 017 A3.01 Typographical Error occurred on original outline. Should be K3.01 vice A3.01.
t
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T 1-t I
1 1
I I
I I.
ES-401 I
i i
i
ES-401 Facility:
WCGS PWR RO Examination Outline Form ES-401-4 Exam Date: 12/07/2001 I-K/A Category Points Tier Group KI K2 K3 K4 K5 K6 Al 1
3 3
3
- 1.
Emergency 2
4 4
3 Abnormal Plant 3
1 1
0 Evolutions I
Totals 8
8 6
Tier
- 2.
Plant Systems 1
2 2
1 2
3 2
2 0
6 2
A2 3
A3 A4 G
1 1
6 2
2 3
0 2
2 Point Total 16 17 3
36 23 2
1 2
3 2
2 1
2 1
3 2
1 20 3
1 0
1 1
1 1
0 1
1 1
0 8
Tier Totals 4
4 5
5 6
4 4
5 6
5 3
51 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 3
3 4
3 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each teir (i.e., the "Tier Totals" in each K/A category shall not be less than two).
- 2. Actual point totals must match those specified in the table.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate 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 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.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorites. Enter the tier totals for each category in the table above.
1 Exam Level: RO Printed: 12/13/2001 4
2 1
PWR RO Examination Outline Facility:
WCGS ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 1 E/APE #
E/APE Name / Safety Function K1. K2 K3 Al A2 G KA Topic Imp.
Points 005 Inoperable/Stuck Control Rod / 1 X
AK1.04 - Definitions of axial imbalance, neutron error, 3.0*
1 power demand, actual power tracking mode, ICS tracking 2.5 1
005 Inoperable/Stuck Control Rod / 1 X
AK2.02 - Breakers, relays, disconnects, and control 2.5 room switches 015 Reactor Coolant Pump (RCP) Malfunctions / 4 X
AK2. 10 - RCP indicators and controls 2.8*
1 017 Reactor Coolant Pump (RCP) Malfunctions (Loss of X
AA1.03 - Reactor trip alarms, switches, and indicators 3.7*
1 RC Flow) / 4 027 Pressurizer Pressure Control (PZR PCS) Malfunction X
AK 1.01 - Definition of saturation temperature 3.1
/3 040 Steam Line Rupture / 4 X
AK3.02 - ESFAS initiation 4.4 1
057 Loss of Vital AC Electrical Instrument Bus / 6 X
AA1.04 - RWST and VCT valves 3.5 1
068 Control Room Evacuation / 8 X
AK2.07 - ED/G 3.3 1
069 Loss of Containment Integrity / 5 X
AA17.03 - Fluid systems penetrating containment 2.8 1
I Printed:
12/13/2001 l*nrm I*_A(IIA
PWR RO Examination Outline Facility:
12/13/2001 Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 1 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 074 Inadequate Core Cooling / 4 X
EA2.08 - The effect of turbine bypass valve operation 3.8 1
on RCS temperature and pressure 074 Inadequate Core Cooling / 4 X 2.4.21 - Knowledge of the parameters and logic used to 3.7 1
assess the status of safety functions including: 1.
Reactivity control; 2. Core cooling and heat removal;
- 3. Reactor coolant system integrity; 4. Containment conditions; 5. Radioactivity release control.
076 High Reactor Coolant Activity / 9 X
AA2.01 - Location or process point that is causing an 2.7 1
alarm E07 Saturated Core Cooling / 4 X
EK3.1 - Facility operating characteristics during 3.1 1
transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics E08 Pressurized Thermal Shock / 4 X
EK1.1 - Components, capacity, and function of 3.5 1
emergency systems E09 Natural Circulation Operations /4 X
EK3.1 - Facility operating characteristics during 3.3 1
transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics E 0 Natural Circulation with Steam Void in Vessel X
EA 1.1 - Components, and functions of control and 3.8 with/without RVLIS / 4 safety systems, including instrumentation, signals, interlocks, tailure modes, and automatic anU manual features K/A Category Totals:
3 3
3 4
2 1
Group Point Total:
16 2
l*nrm l*_dfl!
_A
PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1I /Granun2 Printed:
12/13/2001 lpm VC
- AAIA E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 001 Continuous Rod Withdrawal / 1 X
AK2.08 - Individual rod display lights and indications 3.1 1
001 Continuous Rod Withdrawal / 1 X
AA2.03 - Proper actions to be taken if automatic safety 4.5 1
functions have not taken place 003 Dropped Control Rod / 1 X
AK 1.10 - Definitions of core quadrant power tilt 2.6 1
008 Pressurizer (PZR) Vapor Space Accident (Relief X
AK1.02 - Change in leak rate with change in pressure 3.1 Valve Stuck Open) / 3 008 Pressurizer (PZR) Vapor Space Accident (Relief X
AK2.02 - Sensors and detectors 2.7*
1 Valve Stuck Open) /3 009 Small Break LOCA /3 X
EA2.10 -Airbome activity 3.1 1
022 Loss of Reactor Coolant Makeup / 2 X
AA 1.02 - CVCS charging low flow alarm, sensor, and 3.0 1
indicator 025 Loss of Residual Heat Removal System (RHRS) / 4 X
AK2.03 - Service water or closed cooling water pumps 2.7 1
029 Anticipated Transient Without Scram (ATWS) / 1 X
EK1.02 - Definition of reactivity 2.6 1
033 Loss of Intermediate Range Nuclear Instrumentation /
X AK3.02 - Guidance contained in EOP for loss of 3.6 1
7 intermediate-range instrumentation 1
WCGS Facility:
ES - 401
PWR RO Examination Outline Facility:
WCGS ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 2 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 037 Steam Generator (S/G) Tube Leak / 3 X
AA2.12 - Flow rate of leak 3.3 1
054 Loss of Main Feedwater (MFW) / 4 X
AK1.02 - Effects of feedwater introduction on dry S/G 3.6 1
054 Loss of Main Feedwater (MFW) / 4 X
AK3.01 - Reactor and/or turbine trip, manual and 4.1 1
automatic 058 Loss of DC Power / 6 X 2.2.25 - Knowledge of bases in technical specifications 2.5 1
for limiting conditions for operations and safety limits.
E02 SI Termination / 3 X
EA1.2 - Operating behavior characteristics of the 3.6 1
facility E05 Loss of Secondary Heat Sink / 4 X
EK2.1 - Components, and functions of control and 3.7 1
safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features El1 Loss of Emergency Coolant Recirculation / 4 X
EK3.1 - Facility operating characteristics during 3.3 transient conditions, including coolant chemistry and the effects of temperature, pressure, anf reactivity changes and operating limitations and reasons for these operating characteristics K/A Category Totals:
4 4
3 2
3 1
Group Point Total:
17 2
I..
Printed:
12/13/2001 17arm I*.AII1-A
PWR RO Examination Outline Facility:
WCGS ES - 401 Emergencv and Abnormal Plant Evolutions - Tier 1I /Groun 3 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 028 Pressurizer (PZR) Level Control Malfunction / 2 X
AK2.03 - Controllers and positioners 2.6 1
056 Loss of Offsite Power / 6 X
AKi1.01 - Principle of cooling by natural convection 3.7 1
065 Loss of Instrument Air / 8 X
AA2.07 - Whether backup nitrogen supply is controlling 2.8*
valve position K/A Category Totals:
1 1
0 0
1 0
Group Point Total:
3 I
Printed:
12/13/2001 l*arm I*_AfllA
PWR RO Examination Outline Plant Svstems - Tier 2 / Group I Printed:
12/13/2001
< *! fl AU
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Sys/Ev#
System/Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 001 Control Rod Drive System / 1 X
A3.06 - RCS temperature and pressure 3.9 1
003 Reactor Coolant Pump System X
K2.02 - CCW pumps 2.5*
1 (RCPS) / 4 003 Reactor Coolant Pump System X
K5.03 - Effects of RCP shutdown on T-ave.,
3.1 1
(RCPS) / 4 including the reason for the unreliability of T-ave. in the shutdown loop 004 Chemical and Volume Control System X
K4.15 - Interlocks associated with operation of 3.0*
1 (CVCS) / 1 orifice isolation valves 004 Chemical and Volume Control System X
A4.09 - PZR spray and heater controls 3.5 1
(CVCS) / 1 013 Engineered Safety Features Actuation X
A2.01 - LOCA 4.6 1
System (ESFAS) / 2 013 Engineered Safety Features Actuation X
K1.05 - CSS 4.1 1
System (ESFAS) / 2 015 Nuclear Instrumentation System / 7 X
K6.03 - Component interconnections 2.6 1
015 Nuclear Instrumentation System / 7 X 2.2.23 - Ability to track limiting conditions for 2.6 1
operations.
017 In-Core Temperature Monitor (ITM)
X K5.01 - Temperature at which cladding and fuel 3.1 1
System / 7 melt 017 In-Core Temperature Monitor (ITM)
X
]R3.01 - Natural circulation indications 3.5*
1 System / 7 1=
F 1
WCGS Facility:
ES - 401
PWR RO Examination Outline au IUilIII I2.3I,~UI,.
Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 022 Containment Cooling System (CCS) /
X A 1.03 - Containment humidity 3.1 1
5 056 Condensate System / 4 X
A2.04 - Loss of condensate pumps 2.6 1
059 Main Feedwater (MFW) System / 4 X
K4.16 - Automatic trips for MFW pumps 3.1*
1 059 Main Feedwater (MFW) System / 4 X
A3.02 - Programmed levels of the S/G 2.9 1
061 Auxiliary / Emergency Feedwater X
K5.03 - Pump head effects when control valve 2.6 1
(AFW) System / 4 is shut 061 Auxiliary / Emergency Feedwater X
K2.02 - AFW electric driven pumps 3.7*
1 (AFW) System / 4 068 Liquid Radwaste System (LRS) / 9 X
K1.07 - Sources of liquid wastes for LRS 2.7 1
068 Liquid Radwaste System (LRS) / 9 X
K6. 10 - Radiation monitors 2.5 1
071 Waste Gas Disposal System (WGDS)
X A2.09 - Stuck-open relief valve 3.0*
1
/9 071 Waste Gas Disposal System (WGDS)
X 2.1.27 - Knowledge of system purpose and or 2.8 1
/9 function.
072 Area Radiation Monitoring (ARM)
X A1.01 - Radiation levels 3.4 1
Plant
/AI 7
1____
System / 71 1
Printed:
12/13/2001 2
L WCGS Facility:
ES - 401
_6 ------------- e-
PWR RO Examination Outline Facility:
WCGS K/A Category Totals:
2 2
1 2
3 2
2 3
2 2
2 Group Point Total:
23 3
Printed:
12/13/2001
Facility:
WCGS ES - 401 PWR RO Examination Outline Plant Stm
- Tipr "2 / Crnnn Printed:
12/13/2001 Sys/Ev #
System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 002 Reactor Coolant System (RCS) / 2 X
K3.02 - Fuel 4.2 1
006 Emergency Core Cooling System-X K5.10 - Theory of thermal stress 2.5 1
(ECCS) / 2 006 Emergency Core Cooling System X
A1.09 - Pump amperage, including start, normal 2.8 1
(ECCS) / 2 and locked 010 Pressurizer Pressure Control System X
K4.01 - Spray valve warm-up 2.7 1
(PZR PCS) / 3 012 Reactor Protection System / 7 X
K2.01 - RPS channels, components, and 3.3 1
interconnections 012 Reactor Protection System / 7 X
A3.02 - Bistables 3.6 1
026 Containment Spray System (CSS) / 5 X
K3.02 - Recirculation spray system 4.2*
1 026 Containment Spray System (CSS) / 5 X 2.1.2 - Knowledge of operator responsibilities 3.0 1
during all modes of plant operation.
029 Containment Purge System (CPS)/ 8 X
K4.03 - Automatic purge isolation 3.2*
1 035 Steam Generator System (S/GS) /4 X
A4.06 - S/G isolation on steam leak or tube 4.5 rupture/leak 035 Steam Generator System (S/GS) / 4 X
K6.02 - Secondary PORV 3.1 I
I
PWR RO Examination Outline Plant vte
- Tipr 2 I inun Printed:
12/13/2001
. r.*.I P*
tA1=l]
Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 039 Main and Reheat Steam System X
K3.04 - MFW pumps 2.5*
1 (MRSS) / 4 055 Condenser Air Removal System X
K1.06 - PRM system 2.6 1
(CARS) / 4 062 A.C. Electrical Distribution System / 6 X
K2.01 - Major system loads 3.3 1
063 D.C. Electrical Distribution System / 6 X
A3.01 - Meters, annunciators, dials, recorders, 2.7 1
and indicating lights 063 D.C. Electrical Distribution System / 6 X
A4.03 - Battery discharge rate 3.0*
1 064 Emergency Diesel Generator (ED/G)
X Al1.01 - ED/G lube oil temperature and pressure 3.0 1
System / 6 079 Station Air System (SAS) / 8 X
A2.01 - Cross-connection with IAS 2.9 1
086 Fire Protection System (FPS) / 8 X
A3.03 - Actuation of fire detectors 2.9 1
086 Fire Protection System (FPS) / 8 X
K5.04 - Hazards to personnel as a result of fire 2.9 1
1 type and methods of protection K/A Category Totals:
1 2
3 2
2 1
2 1
3 2
1 Group Point Total:
WCGS Facility:
ES - 401 20 2
Facility:
WCGS ES - 401 K/A Category Totals:
1 0
1 1
1 PWR RO Examination Outline Plant Svti"-Trr2IGnu 1
0 1
1 1
0 Printed:
12/13/2001 Group Point Total:
8 1
_____________1 U
II
-It l
Sys/Ev#
System/ Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 007 Pressurizer Relief Tank/Quench Tank X
K3.01 - Containment 3.3 1
System (PRTS) / 5 008 Component Cooling Water System X
A3.08 - Automatic actions associated with the 3.6*
1 (CCWS) / 8 CCWS that occur as a result of a safety injection signal 028 Hydrogen Recombiner and Purge X
K6.01 - Hydrogen recombiners 2.6 1
Control System (HRPS) / 5 034 Fuel Handling Equipment System X
A4.01 - Radiation levels 3.3 1
(FHES) / 8 041 Steam Dump System (SDS) and X
A2.03 - Loss of lAS 2.8 1
Turbine Bypass Control / 4 045 Main Turbine Generator (MT/G)
X K5.23 - Relationship between rod control and 2.7 1
System / 4 RCS boron concentration during T/G load increases 076 Service Water System (SWS) / 4 X
K4.01 - Conditions initiating automatic closure 2.5*
1 of closed cooling water auxiliary building header supply and return valves 103 Containment System / 5 X
KI.02 - Containment isolation/containment 3.9 1
F__ _
integrity I
I
- m 1[* Afsl A
Generic Knowledge and Abilities Outline (Tier 3)
Printed:
12/13/2001 PWR RO Examination Outline Facility:
WCGS Generic Category KA KA Topic Form ES-401-5 Imp.
Points Conduct of Operations 2.1.19 2.1.23 2.1.30 Ability to use plant computer to obtain and evaluate parametric information on system or component status.
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Ability to locate and operate components, including local controls.
.1 1 ____________________________________________________
Category Total:
3 Equipment Control 2.2.2 22.13 2.2.33 Ability to manipulate the console controls as required to operate shutdown and designated power levels.
Knowledge of tagging and clearance procedures.
Knowledge of control rod programming.
.1 ____
1 __________________________________________
Category Total:
3 Radiation Control 2.3.2 Knowledge of facility ALARA program.
2.5 1
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible 2.5 1
levels in excess of those authorized.
2.3.9 Knowledge of the process for performing a containment purge.
2.5 1
2.3.11 Ability to control radiation releases.
2.7 1
Category Total:
4 Emergency Procedures/Plan 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP 3.9 1
entry conditions. Note: The issue of setpoints and automatic safety features is not specifically covered in the systems sections.
2.4.10 Knowledge of annunciator response procedures.
3.0 1
2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during 2.8 1
emergency operations..
Category Total:
Generic Total:
13 I
3 I
PWR SRO Examination Outline Facility:
WCGS Form ES-401-3 Exam Date: 12/07/2001 Exam Level: SRO K/A Category Points Tier Group K1 K2 g2 I
VA IZ I
Al 1
4 4
3
- 1.
2 3
3 3
Emergency 3
1 1
0 Abnormal Plant Tier Evolutions Totals 8
8 6
- 2.
Plant Systems 1
2 2
2 1
0 6
2 1
2 2
AA 6
4 0
G 2
2 1
10 2
5 1
2 Point Total 24 16 3
43 1
19 2
1 1
2 2
2 1
2 1
2 1
2 17 3
0 0
1 0
1 0
0 1
1 0
0 4
Tier Totals 3
3 5
4 4
3 4
4 4
3 3
40 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 4
4 4
5 17 Note: 1. Ensure that at least two topics from every K/A category are sampled within each teir (i.e., the "Tier Totals" in each K/A category shall not be less than two).
- 2. Actual point totals must match those specified in the table.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate 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 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.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorites. Enter the tier totals for each category in the table above.
1 ES-401 Printed: 12/13/2001 K3*.
PWR SRO Examination Outline Facility:
WCGS Emerencv and Abnormal Plant 1vnIuitinn
- Tir 1 I tZ.nm
1
... o
- r
-.., up ror Afl--,* -.
E/APE #
E/APE Name / Safety Function Ki K2 K3 Al A2 G KA Topic Imp.
Points 001 Continuous Rod Withdrawal / 1 X
AK2.08 - Individual rod display lights and indications 3.0 1
003 Dropped Control Rod / 1 X
AK 1.10 - Definitions of core quadrant power tilt 2.9 1
005 Inoperable/Stuck Control Rod / I X
AK1.04 - Definitions of axial imbalance, neutron error, 3.4*
1 power demand, actual power tracking mode, ICS tracking 005 Inoperable/Stuck Control Rod / 1 X
AK2.02 - Breakers, relays, disconnects, and control 2.6 1
room switches 011 Large Break LOCA / 3 X
EA2.06 - That fan is in slow speed and dampers are in 4.0*
1 accident mode during LOCA 015 Reactor Coolant Pump (RCP) Malfunctions /4 X
AK2. 10 - RCP indicators and controls 2.8 1
017 Reactor Coolant Pump (RCP) Malfunctions (Loss of X
AAl1.03 - Reactor trip alarms, switches, and indicators 3.8 1
RC Flow) / 4 026 Loss of Component Cooling Water (CCW) / 8 X 2.2.21 - Knowledge of pre-and post-maintenance 3.5 1
operability requirements.
029 Anticipated Transient Without Scram (ATWS) / 1 X
EK1.02 - Definition of reactivity 2.8 1
040 Steam Line Rupture / 4 X
AK3.02 - ESFAS initiation 4.4 1
I ES - 401 Printed:
12/13/2001
PWR SRO Examination Outline Facility:
WCGS ES - 401 Emereencv and Abnormal Plant Evolutions - Tier 1 / Grnnn 1 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 055 Loss of Offsite and Onsite Power (Station Blackout) /
X EA2.03 - Actions necessary to restore power 4.7 1
6 057 Loss of Vital AC Electrical Instrument Bus / 6 X
AA1.04 - RWST and VCT valves 3.6 1
057 Loss of Vital AC Electrical Instrument Bus / 6 X
AA2.05 - S/G pressure and level meters 3.8 1
068 Control Room Evacuation / 8 X
AK2.07 - ED/G 3.4 1
069 Loss of Containment Integrity / 5 X
AA2.02 - Verification of automatic and manual means 4.4 of restoring integrity 069 Loss of Containment Integrity/ 5 X
AA1.03 - Fluid systems penetrating containment 3.0 1
E02 SI Termination / 3 X
EA1.2 - Operating behavior characteristics of the 3.8 1
facility E04 LOCA Outside Containment / 3 X
EA2.1 - Facility conditions and selection of appropriate 4.3 1
procedures during abnormal and emergency operations E06 Degraded Core Cooling / 4 X
EA2.1 - Facility conditions and selection of appropriate 4.2 1
I procedures during abnormal and emergency operations 2
Printed:
12/13/2001 l*rm I* *_AIN I _It
PWR SRO Examination Outline Printed:
12/13/2001 ES - 401 E/APE #
E07 E08 Pressurized Thermal Shock / 7 X
E09 Natural Circulation Operations / 4 Natural Circulation with Steam Void in Vessel with/without RVLIS / 4 High Containment Pressure / 5
.12.4.10
-Knowledge of annunciator response procedures.
EK1. 1 - Components, capacity, a-nd fu-nction
-of emergency systems EK3.1 - Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics EA 1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE Name / Safety Function K
K 3 Al A2 G KA Topic Saturated Core Cooling / 4 X
EK3.1 - Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics K/A Category Totals:
4 4
3 5
6 2
Group Point Total:
24 3
Form ES-401-3 m
Points 3.7 1
3.8 1
El0 E14 Facility:
WCGS 3.6 11 3.6 11 3.1 11 f
PWR SRO Examination Outline Facility:
WCGS ES - 401 Emertfencv and Abnormal Plant Evln~utinn* - Tipr 1 I (*.rnuan E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 008 Pressurizer (PZR) Vapor Space Accident (Relief X
AKI.02 - Change in leak rate with change in pressure 3.7 1
Valve Stuck Open) / 3 008 Pressurizer (PZR) Vapor Space Accident (Relief X
AK2.02 - Sensors and detectors 2.7 1
Valve Stuck Open) / 3 009 Small Break LOCA / 3 X
EA2.10 - Airborne activity 3.7 1
022 Loss of Reactor Coolant Makeup / 2 X
AAI.02 - CVCS charging low flow alarm, sensor, and 2.9 1
indicator 025 Loss of Residual Heat Removal System (RHRS) / 4 X
AK2.03 - Service water or closed cooling water pumps 2.7 1
027 Pressurizer Pressure Control (PZR PCS) Malfunction X
AK 1.01 - Definition of saturation temperature 3.4 1
/3 033 Loss of Intermediate Range Nuclear Instrumentation /
X AK3.02 - Guidance contained in EOP for loss of 3.9 1
7 intermediate-range instrumentation 037 Steam Generator (S/G) Tube Leak / 3 X
AA2.12 - Flow rate of leak 4.1 1
038 Steam Generator Tube Rupture (SGTR) / 3 X
EA2.06 - Shutdown margins and required boron 4.4 1
concentrations I
I..
Printed:
12/13/2001 Un*
II*
Aft1 2
PWR SRO Examination Outline Facility:
WCGS ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 2 E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 054 Loss of Main Feedwater (MFW) / 4 X
AK1.02 - Effects of feedwater introduction on dry S/G 4.2 1
054 Loss of Main Feedwater (MFW) / 4 X
AK3.01 - Reactor and/or turbine trip, manual and 4.4 automatic 058 Loss of DC Power / 6 X 2.2.25 - Knowledge of bases in technical specifications 3.7 for limiting conditions for operations and safety limits.
060 Accidental Gaseous Radwaste Release / 9 X
AA2.04 - The effects on the power plant of isolating a 3.4*
given radioactive-gas leak E03 LOCA Cooldown and Depressurization / 4 X 2.4.21 - Knowledge of the parameters and logic used to 4.3 assess the status of safety functions including: 1.
Reactivity control; 2. Core cooling and heat removal;
- 3. Reactor coolant system integrity; 4. Containment conditions; 5. Radioactivity release control.
E05 Loss of Secondary Heat Sink /4 X
EK2.1 - Components, and functions of control and 3.9 safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Eli Loss of Emergency Coolant Recirculation / 4 X
EK3.1 - Facility operating characteristics during 3.9 F 9 Ls E
r c
oaRtransient conditions, including coolant chemistry and the ettects ot temperature, pressure, ana reactivity changes and operating limitations and reasons for these operating characteristics K/A Category Totals:
3 3
3 1
4 2
Group Point Total:
16 2
Printed:
12/13/2001 l*nrm l*,q_,t fll _'*
PWR SRO Examination Outline Facility:
WCGS Printed:
12/13/2001 Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 3 K/A Category Totals:
1 1
0 0
0 1
Group Point Total:
3 I
ES - 401 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 028 Pressurizer (PZR) Level Control Malfunction / 2 X
AK2.03 - Controllers and positioners 2.9 1
056 Loss of Offsite Power / 6 X
AK1.01 - Principle of cooling by natural convection 4.2 1
El3 Steam Generator Overpressure / 4 X 2.4.6 - Knowledge symptom based EOP mitigation 4.0 1
Form ES-401-3 strategies.I I
Form ES-4fll-:
PWR SRO Examination Outline plan*
_ T*a "Pr / 9-1 Facility:
-Y ro*,
,, uorm IE -4U1-j Sys/Ev #
System / Evolution Name K11 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 003 Reactor Coolant Pump System X
K2.02 - CCW pumps 2.6*
1 (RCPS) / 4 003 Reactor Coolant Pump System X
K5.03 - Effects of RCP shutdown on T-ave.,
3.5 1
(RCPS) / 4 including the reason for the unreliability of T-ave. in the shutdown loop 004 Chemical and Volume Control System X
K4.15 - Interlocks associated with operation of 3.4 1
(CVCS) / 1 orifice isolation valves 013 Engineered Safety Features Actuation X
K1.05 - CSS 4.4 1
System (ESFAS) / 2 015 Nuclear Instrumentation System / 7 X
K6.03 - Component interconnections 3.0 1
017 In-Core Temperature Monitor (ITM)
X K3.01 - Natural circulation indications 3.7*
1 System / 7 022 Containment Cooling System (CCS) /
X A 1.03 - Containment humidity 3.4 1
5 026 Containment Spray System (CSS) / 5 X
K3.02 - Recirculation spray system 4.3 1
026 Containment Spray System (CSS) / 5 X 2.1.33 - Ability to recognize indications for 4.0 1
system operating parameters which are entry-level conditions for technical specifications.
056 Condensate System / 4 X
A2.04 - Loss of condensate pumps 2.8*
1 1
Printed:
12/13/2001
Facility:
WCGS ES - 401 PWR SRO Examination Outline Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 059 Main Feedwater (MFW) System / 4 X
K4.16 - Automatic trips for MFW pumps 3.2*
1 061 Auxiliary / Emergency Feedwater X
K2.02 - AFW electric driven pumps 3.7 1
(AFW) System / 4 063 D.C. Electrical Distribution System / 6 X
A3.01 - Meters, annunciators, dials, recorders, 3.1 1
and indicating lights 063 D.C. Electrical Distribution System / 6 X
A4.03 - Battery discharge rate 3.1 068 Liquid Radwaste System (LRS) / 9 X
K1.07 - Sources of liquid wastes for LRS 2.9 1
068 Liquid Radwaste System (LRS) / 9 X
K6. 10 - Radiation monitors 2.9 1
071 Waste Gas Disposal System (WGDS)
X
-A2.09
- Stuck-open relief valve 3.5*
1
/9 072 Area Radiation Monitoring (ARM)
X A1.01 - Radiation levels 3.6 1
System / 7 072 Area Radiation Monitoring (ARM)
X A4.02 - Major components 2.5 Plant Systems 7-ATie 2
/ajorcomponWnts 2.5
_____System
/ 71 1
1 1
1 Printed:
12/13/2001 K/A Category Totals:
2 2
2 2
1 2
2 2
1 2
1 Group Point Total:
19 2
1*"
Facility:
WCGS ES - 401 PWR SRO Examination Outline Plant Q ef~me - Tip. I / 1--*
1 Printed:
12/13/2001
-J
"'* -V F*rulll E*-f*U1-a Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 002 Reactor Coolant System (RCS) / 2 X 2.4.10 - Knowledge of annunciator response 3.1 1
procedures.
002 Reactor Coolant System (RCS) / 2 X
K3.02 - Fuel 4.5 1
006 Emergency Core Cooling System X
K5.10 - Theory of thermal stress 2.9*
1 (ECCS) / 2 006 Emergency Core Cooling System X
A 1.09 - Pump amperage, including start, normal 3.2 1
(ECCS) / 2 and locked 010 Pressurizer Pressure Control System X
-K4.01
- Spray valve warm-up 2.9 1
(PZR PCS) / 3 012 Reactor Protection System / 7 X
K2.01 - RPS channels, components, and 3.7 1
interconnections 012 Reactor Protection System / 7 X
A3.02 - Bistables 3.6 1
028 Hydrogen Recombiner and Purge X
K6.01 - Hydrogen recombiners 3.1 1
Control System (HRPS) / 5 029 Containment Purge System (CPS) / 8 X
1K4.03 - Automatic purge isolation 3.5 1
035 Steam Generator System (S/GS) / 4 X
A4.06 - S/G isolation on steam leak or tube 4.6 1
rupture/leak 039 Main and Reheat Steam System X
K3.04 - MFW pumps 2.6*
1 (MRSS) / 4 1
Facility:
WCGS ES - 401 PWR SRO Examination Outline Plant Q efame - Trier I /'r~~
9 P....
P fuirorm E--qu1-3 Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 055 Condenser Air Removal System X
K1.06 - PRM system 2.6 1
(CARS) / 4 064 Emergency Diesel Generator (ED/G)
X A1.01 - ED/G lube oil temperature and pressure 3.1 1
System / 6 073 Process Radiation Monitoring (PRM)
X 2.4.4 - Ability to recognize abnormal 4.3 1
System / 7 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
079 Station Air System (SAS) / 8 X
A2.01 - Cross-connection with IAS 3.2 1
086 Fire Protection System (FPS) / 8 X
A3.03 - Actuation of fire detectors 3.3 1
086 Fire Protection System (FPS) / 8 X
K5.04 - Hazards to personnel as a result of fire 3.5*
1 1 1 1 1 type and methods of protection Printed:
12/13/2001 K/A Category Totals:
1 1
2 2
2 1
2 1
2 1
2 Group Point Total:
17 2
I
Facility:
WCGS ES - 401 PWR SRO Examination Outline Plant Q*citftme - Ti.r
/I
-*--n Printed:
12/13/2001 H
V I
urtorl U13a-fuI Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 007 Pressurizer Relief Tank/Quench Tank X
K3.01 - Containment 3.6 1
System (PRTS) / 5 008 Component Cooling Water System X
A3.08 - Automatic actions associated with the 3.7*
1 (CCWS) / 8 CCWS that occur as a result of a safety injection signal 041 Steam Dump System (SDS) and X
A2.03 - Loss of IAS 3.1 1
Turbine Bypass Control / 4 045 Main Turbine Generator (MT/G)
K5.23 - Relationship between rod control and 2.8 1
System / 4 1RCS boron concentration during T/G load ncreases K/A Category Totals:
0 0
1 0
1 0
0 1
1 0
0 Group Point Total:
4 I
Facility:
WCGS Generic Category Generic Knowledge and Abilities Outline (Tier 3)
Printed:
12/13/2001 PWR SRO Examination Outline Form ES-401-5 KA KA Topic Conduct of Operations 2.1.11 Knowledge of less than one hour technical specification action statements for systems.
3.8 1
2.1.20 Ability to execute procedure steps.
4.2 1
2.1.22 Ability to determine Mode of Operation.
3.3 1
2.1.30 Ability to locate and operate components, including local controls.
3.4 1
1 1
Category Total:
4 Equipment Control 2.2.13 Knowledge of tagging and clearance procedures.
3.8 1
2.2.19 Knowledge of maintenance work order requirements.
3.1 1
2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and 3.7 1
safety limits.
2.2.33 Knowledge of control rod programming.
2.9 1.
Category Total:
4 Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.
3.0 1
2.3.2 Knowledge of facility ALARA program.
2.9 1
2.3.3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control room 2.9 1
(e.g., waste disposal and handling systems).
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 1
personnel exposure.
Category Total:
4 1
Imp.
Points
Generic Knowledge and Abilities Outline (Tier 3)
Printed:
12/13/2001 PWR SRO Examination Outline Form ES-401-5 Facility:
WCGS Generic Category KA KA Topic Imp.
Points Category Total:
5 Generic Total:
17 2
Emergency Procedures/Plan 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP 4.1 1
entry conditions. Note: The issue of setpoints and automatic safety features is not specifically covered in the systems sections.
2.4.10 Knowledge of annunciator response procedures.
3.1 1
2.4.11 Knowledge of abnormal condition procedures.
3.6 1
2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support 4.0 1
procedures.
2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during 3.8 1
emergency operations.