ML023570403
| ML023570403 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/04/2002 |
| From: | Gody A Division of Nuclear Materials Safety IV |
| To: | Terry C TXU Electric |
| References | |
| 50-445/02-301, 50-446/02-301 50-445/02-301, 50-446/02-301 | |
| Download: ML023570403 (35) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
CPSES Date of Examination:
11/2002 Examination Level:
RO Operating Test Number:
Administrative Topic/Subject Description Describe method of evaluation:
- 2. TWO Administrative Questions A.1 Conduct of Operations ROA1 (BANK)
-G2.1.20 Ability to execute procedure steps. (3.9/4.0)
--Perform a Quadrant Power Tilt Ratio Calculation Conduct of Operations ROA2 (NEW)
-G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (2.8/3.1)
--Given the plant data, Calculate an RCS Leak Rate A.2 Equipment Control ROA3 (NEW)
-G2.2.13 Knowledge of tagging and clearance procedures. (3.6/3.8)
--Identify errors in faulted tag A.3 Radiation Control ROA4 (NEW)
-G2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (2.9/3.3)
--Interpret a Faulted Survey Map to Determine Entry Requirements.
A.4 Emergency Plan ROA5 (NEW)
-G2.4.39 Knowledge of ROs responsibilities in emergency plan implementation. (3.3/3.1)
--Make the necessary communications for a given accident.
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
CPSES Date of Examination:
11/2002 Examination Level:
SRO Operating Test Number:
Administrative Topic/Subject Description Describe method of evaluation:
- 2. TWO Administrative Questions A.1 Conduct of Operations SROA1(BANK)
-G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (3.9/4.0)
--Perform Shutdown Margin Calculation Conduct of Operations SROA2(BANK)
-G2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data. (2.8/3.1)
--Perform Calorimetric Heat Balance (blow down heat balance)
A.2 Equipment Control SROA3(NEW)
-G2.2.23 Ability to track limiting conditions for operations. (2.6/3.8)
--Given a sequence of events, Determine the end of time of an LCO including any extensions.
A.3 Radiation Control SROA4(NEW)
-G2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (2.9/3.3)
--Interpret a Faulted Survey Map to Determine Entry Requirements.
A.4 Emergency Plan SROA5.1(MODIFIED)
-G2.4.41 Knowledge of EAL thresholds and classifications. (2.3/4.1)
--Following Scenario-1, classify the event and make protective action recommendation.
SROA5.2(MODIFIED)
-G2.4.41 Knowledge of EAL thresholds and classifications. (2.3/4.1)
--Following Scenario-2, classify the event and make protective action recommendation.
SROA5.3(MODIFIED)
-G2.4.41 Knowledge of EAL thresholds and classifications. (2.3/4.1)
--Following Scenario-3, classify the event and make protective action recommendation.
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:
CPSES Date of Examination:
11/2002 Exam Level:
RO/SRO(I)
Operating Test No.:
B.1 Control Room Systems System / JPM Title Type Code*
Safety Function
- a.
JPMS1: Reactor Coolant Pump / Start and Stop a RCP D, S, A, L 4
(Primary)
- b.
JPMS2: CCS / Restore CCS after SI D, S, L 5
- c.
JPMS3: CVCS / Rx M/U Water Malfunction D, S, A 1
- d.
JPMS4: CCW / Shift CCW pumps, CCW pump trip M, S, A 8
e.
JPMS5: NIS / Respond to IR NIS Malfunction D, C, L, A 7
f.
JPMS6: ECCS / Fill SI Accumulators M, C, A 2
- g.
JPMC1: PZR Pressure Control / Place Failed Pressurizer Pressure Channel in Trip Condition D, C 3
B.2 Facility Walk-Through
- a.
JPMP1: Fire Protection / PEO #1 actions to achieve hot shutdown after fire in the control room D, P, L 8
- b.
JPMP2: Main Steam and MFW / Locally Isolate a Ruptured S/G D, P, L 4
(Secondary)
- c.
JPMP3: EDG / Perform a Local Emergency Start of a DG D, P, R 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
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:
CPSES Date of Examination:
11/2002 Exam Level:
SRO Operating Test No.:
B.1 Control Room Systems System / JPM Title Type Code*
Safety Function
- a.
JPMS5: NIS / Respond to IR NIS Malfunction D, C, L, A 7
- b.
JPMS6: ECCS / Fill SI Accumulators M, C, A 2
- c.
- d.
e.
f.
- g.
B.2 Facility Walk-Through
- a.
JPMP1: Fire Protection / PEO #1 actions to achieve hot shutdown after fire in the control room D, P, L 8
- b.
JPMP2: Main Steam and MFW / Locally Isolate a Ruptured S/G D, P, L 4
(Secondary)
- c.
JPMP3: EDG / Perform a Local Emergency Start of a DG D, P, R 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
Appendix D Scenario Outline Form ES-D-1 Facility:
CPSES Scenario No.:
1 Op-Test No.:
11/2002 Examiners:
Howard Bundy Operators:
Mike Murphy Tom Stetka Fred Sanchez Note:
(NEW) SRO Admin A.5-1, Emerg. Class. is to be done in conjunction with this Scenario. (PRELOAD - MET Tower Data -> wind 105)
Time (T) = 0 at end of power increase -> as directed by Chief Examiner Initial Conditions:
Full power steady state; BOL; Equilibrium Xenon; Severe thunderstorm warning and high winds issued and ABN-907, Section 5 completed.
EDG 1-01 is out of service for maintenance (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into LCO).
(IC Info.: EGR06 - DG1 out of service)
Turnover:
The plant has been at 100% power for the last 15 days. A power reduction to 76% is required to perform MSIV testing. The load reduction should be initiated as soon as the shift change is completed.
Event No.
Malf.
No.
Event Type*
Event Description 1
T=0 N (SRO)
R (RO)
Reduce power to 76%
2 T=15 RX05A I (SRO)
I (RO)
Pressurizer level transmitter LT-459 fails low [value=0, ramp over 1 min]
3 T=22 TC05A C (SRO)
C (BOP)
- 1 Main turbine control valve fails closed 4
T=30 ED06G C (ALL)
Loss of 1D3 bus 5
T=33 T=35 RC03D C (RO)
C (SRO)
RCP 4 vibration - initial severity @ 9 mils and ramp severity to 25 mils over 30 min. High vib. alarm on RCP 4 (shaft) alarms at 15 mils & increasing @ approx 0.5 mils/min.
Manual Rx Scram due to high RCP 1-04 vibrations, no SI.
Enter EOP-0.0A and then transition to EOS-0.1A.
6 T=44 ED01 M (ALL)
Lighting strike in switchyard - loss of offsite power. EDG 1-02 starts and loads (E19 triggers automatically when the reactor is tripped) 7 T=50 EG07B C (ALL)
EDG 1-02 trips (overspeed) - loss of all power. Transition to ECA-0.0A and possibly ABN-601.
T=60 EDG 1-02 is restarted after S/G depressurization has started per ECA-0.0A.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility:
CPSES Scenario No.:
2 Op-Test No.:
11/2002 Examiners:
Howard Bundy Operators:
Mike Murphy Tom Stetka Fred Sanchez Note:
(NEW) SRO Admin A.5-2, Emerg. Class. is to be done in conjunction with this Scenario.
Time (T) = 0 at end of power increase -> as directed by Chief Examiner Initial Conditions:
730 - 740 MWE and steady.
(RP01 - Failure of automatic reactor trip; RP13C - Manual reactor trip failure<booth>; TC07C - Automatic main turbine trip failure<booth>.)
Turnover:
The previous shift just completed turbine valve testing and the shift has been directed to return to 100% (8%/hr< rate of increase <10%/hr). Diesel Generator 1 should be returned to service in about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Event No.
Malf.
No.
Event Type*
Event Description 1
T=0 N (SRO)
R (RO)
N (BOP)
Increase reactor power back to 100%
2 T=15 RX04C I (SRO)
I (RO)
S/G 3 Level Transmitter LT-553 fails low (If RO or BOP goes to place bistables in trip, start Event 3) 3 T=30 TP04A C (SRO)
C (RO)
Main Feedwater pump A TPCW blockage [value=100%,
ramp over 5 min]
- 4 T=40 FW03B M (ALL)
Feedwater pump B trips; failure of automatic and manual reactor trip; failure of automatic main turbine trip.
- 5 SG01C M (ALL)
Steam generator tube rupture [value=750 gpm, insert when reactor is tripped]
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
- = insert in conjunction with S/D or trip of A MFP
- = insert when reactor is tripped.
Appendix D Scenario Outline Form ES-D-1 Facility:
CPSES Scenario No.:
3 Op-Test No.:
11/2002 Examiners:
Howard Bundy Operators:
Mike Murphy Tom Stetka Fred Sanchez Note:
(BANK) This scenario is an unused spare from the 2001 CPSES exam Initial Conditions:
20% power and steady.
Turnover:
No equipment is out of service. Train A equipment is in service. FWP repairs have been completed by the previous shift. You have been directed to return to 100% power @8%/hr not to exceed 10%/hr.
Event No.
Malf.
No.
Event Type*
Event Description 1
T=0 N (SRO)
N (BOP)
R (RO)
Increase Reactor power back to 100%
2**
T=15 MS13A I (RO)
I (SRO)
MSL 1 Press Instrument PI-2325 fails high (100%)
3 T=22 FW16 C (RO)
C (BOP)
C (SRO)
Lowering vacuum on main condenser due to loss of vacuum breaker water seal (6% severity) 4 T=32 RX15A C (RO)
C (SRO)
Pzr spray flow control valve failure (PCV-455B) @ 60%
severity. RXR96 is PCV-455B CTRL driver card - remove then delete malfunction 5
T=45 TC06C MS07A MS10A1
@100%
M (ALL)
Main turbine spurious trip and MSIV #1 closes causing SG1 Safety MS-021 to fail open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
- Note - Initiate after Chief Examiner determines power increase is sufficient
Appendix D Scenario Outline Form ES-D-1 Facility:
CPSES Scenario No.:
4 Op-Test No.:
11/2002 Examiners:
Howard Bundy Operators:
Mike Murphy Tom Stetka Fred Sanchez Note:
(NEW)
Initial Conditions:
20% Turbine Load at BOL Turnover:
Plant Startup in Progress following a routine refueling outage. No equipment is out of service.
IPO-003A, Power Operations is complete through step 5.3.9. Starting at step 5.4, Establishing 100% Turbine Load, continue the plant startup in accordance with IPO-003A.
Event No.
Malf. No.
Event Type*
Event Description 1
T=0 R (RO)
N (BOP)
N (SRO)
Increase turbine load in accordance with IPO003A, Power Operations When operator starts dilution, insert malfunction CV16A 2
T=15 CV16A I (RO)
I (SRO)
LT-112 Fails within the auto makeup range 3
T=25 RC03C C (RO)
C (SRO)
RCP 3 shaft high vibration 4
T=35 RC09C2 M (ALL)
Reactor coolant system loop #3 cold leg rupture (double ended shear) 5 T=35 C (ALL)
Rx will not trip in manual or automatic. Go to FRS-0.1A, Response to Nuclear Power Generation/ATWT 6
T=35 SI04B C (RO)
Train B SI Pump failure
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Preload Information T=0:
RP01 Auto Rx trip failure RP15E Rx trip breakers jammed closed
Appendix D Scenario Outline Form ES-D-1 Facility:
CPSES Scenario No.:
5 Op-Test No.:
11/2002 Examiners:
Howard Bundy Operators:
Mike Murphy Tom Stetka Fred Sanchez Note:
(BANK) This Scenario is an unused backup from the 1999 CPSES Exam Initial Conditions:
Full power steady state; BOL; Equilibrium Xenon (I/C Info: EG06, DG1 Out of Service.)
Turnover:
The plant has been at 100% power for the last 15 days. Diesel Generator 1 is out of service for injector replacement; Diesel Generator 1 should be returned to service in about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Shift order directs you to shift CCPs to add oil to CCP1-01.
Event No.
Malf. No.
Event Type*
Event Description 1
T=0 N (RO)
N (SRO)
SWAP Charging Pumps 2
T=10 I (BOP)
I (SRO)
Steam Generator Pressure Transmitter PT-2325 fails high
[Value = 100]
3 T=20 C (BOP)
C (SRO)
R (RO)
Heater drain pump 1-02 trips/auto turbine runback.
Annunciator ALB-9A Window 8.2 4
T=32 M (ALL)
Loss of all off-site power.
Mechanical failure causes spurious trip of diesel generator 2 breaker [Initiate 5 minutes after diesel starts] [Return diesel generator to service 15 minutes after the reactor trip]
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility:
CPSES Scenario No.:
6(SPARE)
Op-Test No.:
11/2002 Examiners:
Howard Bundy Operators:
Mike Murphy Tom Stetka Fred Sanchez Note:
(NEW)
Initial Conditions:
50% Turbine Load at EOL (IC20; MS08B; MSIV 2 fails to close; Need to update operator aid to 25 psig in VCT)
Turnover:
Plant startup in progress following a routine refueling outage. No equipment is out of service.
IPO-003A, Power Operations, is complete through step 5.4.22. Starting at step 5.4.23, Establishing 100% Turbine Load, continue the plant startup in accordance with IPO-003A.
Control Bank D at 170 steps, 517 MWE, 1554 ppm RCS boron Conc., Xenon at equilibrium conditions, Target power change ramp rate of 8%, MAX ramp rate of 10%.
Event No.
Malf. No.
Event Type*
Event Description 1
T=0 R (RO)
N (BOP)
N (SRO)
Increase turbine load in accordance with IPO-003A, Power Operation Note: Examiner must initiate Event 2 2
T=15 CV15 C (SRO)
C (RO)
PCV-131, Letdown Pressure Control Valve fails closed.
3 T=23 IA01A C (ALL)
Instrument air leak - IA Receiver 1-01 relief valve lifting (Severity = 1500 scfm leak) 4 T=30 RP06A I (SRO)
I (RO)
Loop 1 N16 fails high (Start Event 5 prior to RO/BOP placing bistables in trip) 5 T=46 RD01D C (RO)
C (SRO)
Control bank continuous rod withdrawal (Control Bank D) 6 MS02 MS08B M (ALL)
Main steam line leak outside containment downstream of SG 2 MSIV; SG 2 MSIV, HV-2334A, fails to close. (Insert at 1.13 x 10E7 lbm/hour) EXAMINER NOTE: INSERT AFTER TRANSITION TO EOS-0.1A.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
ES-401 - 4 PWR RO TIER GROUP K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
G1 G2 G3 G4 Total 1
1 4
1 2
5 3
1 16 2
2 3
5 2
4 1
17 3
2 1
3 6
4 7
9 8
2 36 2
1 6
2 3
1 2
4 3
1 1
23 2
1 1
2 5
2 1
4 2
1 1
20 3
2 1
2 1
1 1
8 9
2 4
10 3
2 3
9 5
2 2
51 3
1 3
3 2
4 4
3 2
2 4
4 4
13
- 1. Ensure that at least two topics from every K/A are sampled within each tier (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 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 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 priorities. Enter the tier totals for each category in the table above.
Wednesday, May 15, 2002 Page 1 of 12
TIER GROUP Category GROUP_Total TIER_Total 1
1 A1 5
A2 3
G 1
K1 4
K2 1
K3 2
16 1
2 A1 2
A2 4
G 1
K1 2
K2 3
K3 5
17 1
3 A1 2
A2 1
3 Tier Total: 36 2
1 A1 2
A2 4
A3 3
A4 1
G 1
K1 6
K3 2
K4 3
K6 1
23 2
2 A1 1
A2 4
A3 2
A4 1
G 1
K1 1
K2 1
K3 2
K4 5
K5 2
20 2
3 A2 1
K1 2
K2 1
K4 2
K5 1
K6 1
Wednesday, May 15, 2002 Page 2 of 12
ES-401 PWR RO (continued) 8 Tier Total: 51 TIER GROUP Category GROUP_Total TIER_Total 3
1 G1 3
3 3
2 G2 4
4 3
3 G3 2
2 3
4 G4 4
4 Tier Total: 13 Wednesday, May 15, 2002 Page 3 of 12 ES-401 PWR RO (continued)
Check of Tier Totals 1
A1 9
Sat 1
A2 8
Sat 1
G 2
Sat 1
K1 6
Sat 1
K2 4
Sat 1
K3 7
Sat 2
A1 3
Sat 2
A2 9
Sat 2
A3 5
Sat 2
A4 2
Sat 2
G 2
Sat 2
K1 9
Sat 2
K2 2
Sat 2
K3 4
Sat 2
K4 10 Sat 2
K5 3
Sat 2
K6 2
Sat 3
G1 3
Sat 3
G2 4
Sat 3
G3 2
Sat 3
G4 4
Sat Wednesday, May 15, 2002 Page 4 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 ES401-4 OUTLINE Tier 1
Group 1 A1 4.1.074 Inadequate Core Cooling 4.1.074.EA1.26 Ability to operate and monitor the following as they apply to a 3.8 1
Inadequate Core Cooling: Reactor building emergency sump isolation valve control switches and indicators 4.1.074 Inadequate Core Cooling 4.1.074.EA1.24 Ability to operate and monitor the following as they apply to a 3.6 1
Inadequate Core Cooling: Turbine bypass valve hand/automatic controls, indicators, and set points 4.2.005 Inoperable/Stuck Control Rod 4.2.005.AA1.03 Ability to operate and / or monitor the following as they apply to 3.4 1
the Inoperable / Stuck Control Rod: Metroscope 4.2.067 Plant Fire on Site 4.2.067.AA1.05 Ability to operate and / or monitor the following as they apply to 3
1 the Plant Fire on Site: Plant and control room ventilation systems 4.2.068 Control Room Evacuation 4.2.068.AA1.14 Ability to operate and / or monitor the following as they apply to 4.2 1
the Control Room Evacuation: Reactor trip breakers and switches A2 4.2.068 Control Room Evacuation 4.2.068.AA2.10 Ability to determine and interpret the following as they apply to 4.2 1
the Control Room Evacuation: Source range count rate 4.2.076 High Reactor Coolant Activity 4.2.076.AA2.04 Ability to determine and interpret the following as they apply to 2.6 1
the High Reactor Coolant Activity: Process effluent radiation chart recorder 4.2.076 High Reactor Coolant Activity 4.2.076.AA2.03 Ability to determine and interpret the following as they apply to 2.5 1
the High Reactor Coolant Activity: RCS radioactivity level meter G
4.2.027G Generic KA for Pressurizer Pressure Control System Malfunction 3.9 1
(2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions)
K1 4.2.067 Plant Fire on Site 4.2.067.AK1.01 Knowledge of the operational implications of the following 2.9 1
concepts as they apply to Plant Fire on Site: Fire 4.5.E09 Natural Circulation Operations 4.5.E09.EK1.02 Knowledge of the operational implications of the following 3.3 1
concepts as they apply to the (Natural Circulation Operations)
Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).
4.2.069 Loss of Containment Integrity 4.2.069.AK1.01 Knowledge of the operational implications of the following 2.6 1
concepts as they apply to Loss of Containment Integrity: Effect of pressure on leak rate 4.1.055 Station Blackout 4.1.055.EK1.02 Knowledge of the operational implications of the following concepts 4.1 1
as they apply to the Station Blackout : Natural circulation cooling Wednesday, May 15, 2002 Page 5 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 K2 4.2.068 Control Room Evacuation 4.2.068.AK2.03 Knowledge of the interrelations between the Control Room 2.9 1
Evacuation and the following: Controllers and positioners K3 4.2.051 Loss of Condenser Vacuum 4.2.051.AK3.01 Knowledge of the reasons for the following responses as they 2.8 1
apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum 4.5.E07 Saturated Core Cooling 4.5.E07.EK3.01 Knowledge of the reasons for the following responses as they 3.1 1
apply to the (Saturated Core Cooling) 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.
Tier 1
Group 2 A1 4.1.029 Anticipated Transient Without Scram (ATWS) 4.1.029.EA1.03 Ability to operate and monitor the following as they apply to a 3.5 1
ATWS: Charging pump suction valves from VCT operating switch 4.5.E02 SI Termination 4.5.E02.EA1.01 Ability to operate and / or monitor the following as they apply to 4
1 the (SI Termination) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
A2 4.2.061 Area Radiation Monitoring (ARM) System Alarms 4.2.061.AA2.03 Ability to determine and interpret the following as they apply to 3
1 the Area Radiation Monitoring (ARM) System Alarms: Set points for alert and high alarms 4.1.038 Steam Generator Tube Rupture 4.1.038.EA2.11 Ability to determine or interpret the following as they apply to a 3.7 1
SGTR: Local radiation reading on main steam lines 4.1.009 Small Break LOCA 4.1.009.EA2.01 Ability to determine or interpret the following as they apply to a 4.2 1
small break LOCA: Actions to be taken, based on RCS temperature and pressure, saturated and superheated 4.5.E02 SI Termination 4.5.E02.EA2.01 Ability to determine and interpret the following as they apply to 3.3 1
the (SI Termination) Facility conditions and selection of appropriate procedures during abnormal and emergency G
4.1.011G Generic KA for Large Break LOCA (2.4.18 Knowledge of the 2.7 1
specific bases for EOPs)
K1 4.5.E04 LOCA Outside Containment 4.5.E04.EK1.01 Knowledge of the operational implications of the following 3.5 1
concepts as they apply to the (LOCA Outside Containment)
Components, capacity, and function of emergency systems.
4.5.E02 SI Termination 4.5.E02.EK1.02 Knowledge of the operational implications of the following 3.4 1
concepts as they apply to the (SI Termination) Normal, abnormal and emergency operating procedures associated with (SI Termination)
Wednesday, May 15, 2002 Page 6 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 K2 4.2.001 Continuous Rod Withdrawal 4.2.001.AK2.05 Knowledge of the interrelations between the Continuous Rod 2.9 1
Withdrawal and the following: Rod motion lights 4.5.E01 Rediagnosis 4.5.E01.EK2.01 Knowledge of the interrelations between the (Reactor Trip or 3.3 1
Safety Injection/Rediagnosis) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 4.5.E01 Rediagnosis 4.5.E01.EK2.02 Knowledge of the interrelations between the (Reactor Trip or 3.5 1
Safety Injection/Rediagnosis) and the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the K3 4.5.E16 High Containment Radiation 4.5.E16.EK3.01 Knowledge of the reasons for the following responses as they 2.9 1
apply to the (High Containment Radiation) 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.
4.5.E01 Rediagnosis 4.5.E01.EK3.02 Knowledge of the reasons for the following responses as they 3
1 apply to the (Reactor Trip or Safety Injection/Rediagnosis)
Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection/Rediagnosis).
4.5.E03 LOCA Cooldown and Depressurization 4.5.E03.EK3.04 Knowledge of the reasons for the following responses as they 3.5 1
apply to the (LOCA Cooldown and Depressurization) RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
4.5.E05 Loss of Secondary Heat Sink 4.5.E05.EK3.01 Knowledge of the reasons for the following responses as they 3.4 1
apply to the (Loss of Secondary Heat Sink) 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.
4.2.008 Pressurizer Vapor Space Accident 4.2.008.AK3.03 Knowledge of the reasons for the following responses as they 4.1 1
apply to the Pressurizer Vapor Space Accident: Actions contained in EOP for PZR vapor space accident/ LOCA Tier 1
Group 3 A1 4.2.028 Pressurizer Level Control Malfunction 4.2.028.AA1.07 Ability to operate and / or monitor the following as they apply to 3.3 1
the Pressurizer Level Control Malfunctions: Charging pumps maintenance of PZR level (including manual backup) 4.2.065 Loss of Instrument Air 4.2.065.AA1.05 Ability to operate and / or monitor the following as they apply to 3.3 1
the Loss of Instrument Air: RPS A2 4.2.056 Loss of Off-Site Power 4.2.056.AA2.02 Ability to determine and interpret the following as they apply to 3.5 1
the Loss of Offsite Power: ESF load sequencer status lights Wednesday, May 15, 2002 Page 7 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 Tier 2
Group 1 A1 3.5.022 Containment Cooling System 3.5.022.A1.02 Ability to predict and/or monitor changes in parameters (to 3.6 1
prevent exceeding design limits) associated with operating the CCS controls including: Containment pressure 3.7.015 Nuclear Instrumentation System 3.7.015.A1.08 Ability to predict and/or monitor changes in parameters to prevent 3.3 1
exceeding design limits) associated with operating the NIS controls including: Changes in RCS temperature A2 3.2.004 Chemical and Volume Control System 3.2.004.A2.19 Ability to (a) predict the impacts of the following malfunctions or 2.8 1
operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High secondary and primary concentrations of chloride, fluoride, sodium and solids 3.4.059 Main Feedwater System 3.4.059.A2.04 Ability to (a) predict the impacts of the following malfunctions or 2.9 1
operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Feeding a dry S/G 3.7.072 Area Radiation Monitoring System 3.7.072.A2.01 Ability to (a) predict the impacts of the following malfunctions or 2.7 1
operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or 3.5.022 Containment Cooling System 3.5.022.A2.06 Ability to (a) predict the impacts of the following malfunctions or 2.8 1
operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCS pump A3 3.4.061 Auxiliary / Emergency Feedwater System 3.4.061.A3.02 Ability to monitor automatic operation of the AFW, including:
4 1
RCS cooldown during AFW operations 3.2.004 Chemical and Volume Control System 3.2.004.A3.12 Ability to monitor automatic operation of the CVCS, including:
3 1
Interpretation of letdown demineralizer flow-divert valve position indicating lights 3.4.003 Reactor Coolant Pump System 3.4.003.A3.01 Ability to monitor automatic operation of the RCPS, including:
3.3 1
Seal injection flow A4 3.4.059 Main Feedwater System 3.4.059.A4.10 Ability to manually operate and monitor in the control room: ICS 3.9 1
G 3.9.068G Generic KA for Liquid Radwaste System (2.3.4 Knowledge of 2.5 1
radiation exposure limits and contamination control, including permissible levels in excess of those authorized)
K1 3.7.015 Nuclear Instrumentation System 3.7.015.K1.03 Knowledge of the physical connections and/or cause-effect 3.1 1
relationships between the NIS and the following systems: CRDS Wednesday, May 15, 2002 Page 8 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 3.7.015 Nuclear Instrumentation System 3.7.015.K1.08 Knowledge of the physical connections and/or cause-effect 2.6 1
relationships between the NIS and the following systems: RCS (pump start) 3.4.003 Reactor Coolant Pump System 3.4.003.K1.01 Knowledge of the physical connections and/or cause-effect 2.6 1
relationships between the RCPS and the following systems: RCP lube oil 3.4.003 Reactor Coolant Pump System 3.4.003.K1.10 Knowledge of the physical connections and/or cause-effect 3.0 1
relationships between the RCPS and the following systems: RCS 3.5.022 Containment Cooling System 3.5.022.K1.02 Knowledge of the physical connections and/or cause-effect 3.7 1
relationships between the CCS and the following systems:
SEC/remote monitoring systems 3.7.017 In-Core Temperature Monitor System 3.7.017.K1.02 Knowledge of the physical connections and/or cause effect 3.3 1
relationships between the ITM system and the following systems:
RCS K3 3.5.022 Containment Cooling System 3.5.022.K3.02 Containment equipment subject to damage by high or low 3
1 temperature, humidity, and pressure Containment instrumentation readings 3.4.003 Reactor Coolant Pump System 3.4.003.K3.03 Knowledge of the effect that a loss or malfunction of the RCPS 2.8 1
will have on the following: Feedwater and emergency feedwater K4 3.4.061 Auxiliary / Emergency Feedwater System 3.4.061.K4.01 Knowledge of AFW design feature(s) and/or interlock(s) which 3.9 1
provide for the following: Water sources and priority of use 3.2.013 Engineered Safety Features Actuation System 3.2.013.K4.12 Knowledge of ESFAS design feature(s) and/or interlock(s) which 3.7 1
provide for the following Safety injection block 3.5.022 Containment Cooling System 3.5.022.K4.03 Knowledge of CCS design feature(s) and/or interlock(s) which 3.6 1
provide for the following: Automatic containment isolation K6 3.2.013 Engineered Safety Features Actuation System 3.2.013.K6.01 Knowledge of the effect of a loss or malfunction on the following 2.7 1
will have on the ESFAS: Sensors and detectors Tier 2
Group 2 A1 3.7.012 Reactor Protection System 3.7.012.A1.01 Ability to predict and/or monitor Changes in parameters (to 2.9 1
prevent exceeding design limits) associated with operating the RPS controls including: Trip set point adjustment A2 3.8.029 Containment Purge System 3.8.029.A2.01 Ability to (a) predict the impacts of the following mal-functions or 2.9 1
operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Maintenance or other activity taking place inside containment Wednesday, May 15, 2002 Page 9 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 3.6.062 A.C. Electrical Distribution 3.6.062.A2.09 Ability to (a) predict the impacts of the following malfunctions or 2.7 1
operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Consequences of exceeding current limitations 3.7.073 Process Radiation Monitoring System 3.7.073.A2.01 Ability to (a) predict the impacts of the following malfunctions or 2.5 1
operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or 3.2.011 Pressurizer Level Control System 3.2.011.A2.04 Ability to (a) predict the impacts of the following malfunctions or 3.5 1
operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of Loss of one, two or three charging pumps A3 3.4.055 Condenser Air Removal System 3.4.055.A3.03 Ability to monitor automatic operation of the CARS, including:
2.5 1
Automatic diversion of CARS exhaust 3.5.026 Containment Spray System 3.5.026.A3.01 Ability to monitor automatic operation of the CSS, including:
4.3 1
Pump starts and correct MOV positioning A4 3.8.029 Containment Purge System 3.8.029.A4.04 Ability to manually operate and/or monitor in the control room:
3.5 1
Containment evacuation signal G
3.8.079G Generic KA for Station Air System (2.2.22 Knowledge of limiting 3.4 1
conditions for operations and safety limits)
K1 3.7.016 Non-Nuclear Instrumentation System 3.7.016.K1.10 Knowledge of the physical connections and/or cause-effect 3.1 1
relationships between the NNIS and the following systems: CCS K2 3.2.006 Emergency Core Cooling System 3.2.006.K2.02 Knowledge of bus power supplies to the following: Valve 2.5 1
operators for accumulators K3 3.4.035 Steam Generator System 3.4.035.K3.01 Knowledge of the effect that a loss or malfunction of the S/GS 4.4 1
will have on the following: RCS 3.7.016 Non-Nuclear Instrumentation System 3.7.016.K3.08 Knowledge of the effect that a loss or malfunction of the NNIS 3.5 1
will have on the following: PZR PCS K4 3.4.035 Steam Generator System 3.4.035.K4.06 Knowledge of S/GS design feature(s) and/or interlock(s) which 3.1 1
provide for the following: S/G System 3.4.035 Steam Generator System 3.4.035.K4.05 Knowledge of S/GS design feature(s) and/or interlock(s) which 3.7 1
provide for the following: Amount of reserve water in S/G Wednesday, May 15, 2002 Page 10 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 3.7.073 Process Radiation Monitoring System 3.7.073.K4.01 Knowledge of PRM system design feature(s) and/or interlocks 4
1 which provide for the following: Release termination when radiation exceeds set point 3.8.029 Containment Purge System 3.8.029.K4.03 Knowledge of design feature(s) and/or interlock(s) which provide 3.2 1
for the following: Automatic purge isolation 3.8.086 Fire Protection System 3.8.086.K4.01 Knowledge of design feature(s) and/or interlock(s) which provide 3.1 1
for the following: Adequate supply of water for FPS K5 3.8.086 Fire Protection System 3.8.086.K5.03 Knowledge of the operational implication of the following concepts 3.1 1
as they apply to the Fire Protection System: Effect of water spray on electrical components 3.3.010 Pressurizer Pressure Control System 3.3.010.K5.02 Knowledge of the operational implications of the following 2.6 1
concepts as the apply to the PZR PCS: Constant enthalpy expansion through a valve Tier 2
Group 3 A2 3.8.008 Component Cooling Water System 3.8.008.A2.04 Ability to (a) predict the impacts of the following malfunctions or 3.3 1
operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PRMS alarm K1 3.4.076 Service Water System 3.4.076.K1.07 Knowledge of the physical connections and/or cause-effect 2.5 1
relationships between the SWS and the following systems:
Secondary closed cooling water 3.4.045 Main Turbine Generator System 3.4.045.K1.06 Knowledge of the physical connections and/or cause-effect 2.6 1
relationships between the MT/G system and the following systems: RCS, during steam valve test K2 3.4.076 Service Water System 3.4.076.K2.01 Knowledge of bus power supplies to the following: Service water 2.7 1
K4 3.5.007 Pressurizer Relief Tank / Quench Tank System 3.5.007.K4.01 Knowledge of PRTS design feature(s) and/or interlock(s) which 2.6 1
provide for the following: Quench tank cooling 3.4.045 Main Turbine Generator System 3.4.045.K4.47 Knowledge of MT/G system design feature(s) and/or inter-lock(s) 4 1
which provide for the following: Turbine trip upon reactor trip K5 3.5.028 Hydrogen Recombiner and Purge Control System 3.5.028.K5.02 Knowledge of the operational implications of the following 3.4 1
concepts as they apply to the HRPS: Flammable hydrogen K6 3.5.028 Hydrogen Recombiner and Purge Control System 3.5.028.K6.01 Knowledge of the effect of a loss or malfunction on the following 2.6 1
will have on the HRPS: Hydrogen recombiners Wednesday, May 15, 2002 Page 11 of 12
ES-401 PWR RO (continued) CPSES - 11/2002 Tier 3
Group 1 G1 2.1.16 2.1.16 Conduct of Operations: Ability to operate plant phone, paging 2.9 1
system, and two-way radio.
2.1.18 2.1.18 Conduct of Operations: Ability to make accurate, clear and 2.9 1
concise logs, records, status boards, and reports.
2.1.24 2.1.24 Conduct of Operations: Ability to obtain and interpret station 2.8 1
electrical and mechanical drawings.
Tier 3
Group 2 G2 2.2.3 2.2.3 Equipment Control (multi-unit) Knowledge of the design, 3.1 1
procedural, and operational differences between units.
2.2.11 2.2.11 Equipment Control Knowledge of the process for controlling 2.5 1
temporary changes.
2.2.23 2.2.23 Equipment Control Ability to track limiting conditions for 2.6 1
2.2.22 2.2.22 Equipment Control Knowledge of limiting conditions for operations 3.4 1
and safety limits.
Tier 3
Group 3 G3 2.3.2 2.3.2 Radiation Control Knowledge of facility ALARA program.
2.5 1
2.3.4 2.3.4 Radiation Control Knowledge of radiation exposure limits and 2.5 1
contamination control, including permissible levels in excess of those authorized.
Tier 3
Group 4 G4 2.4.39 2.4.39 Emergency Procedures / Plan Knowledge of the RO's 3.3 1
responsibilities in emergency plan implementation.
2.4.46 2.4.46 Emergency Procedures / Plan Ability to verify that the alarms 3.5 1
are consistent with the plant conditions.
2.4.47 2.4.47 Emergency Procedures / Plan Ability to diagnose and recognize 3.4 1
trends in an accurate and timely manner utilizing the appropriate control room reference material.
2.4.25 2.4.25 Emergency Procedures / Plan Knowledge of fire protection 2.9 1
procedures.
Wednesday, May 15, 2002 Page 12 of 12
ES-401 - 3 PWR SRO TIER GROUP K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
G1 G2 G3 G4 Total 1
1 6
4 3
6 4
1 24 2
1 7
2 5
1 16 3
1 2
3 7
4 10 9
11 2
43 2
1 3
2 3
1 2
3 3
1 1
19 2
1 1
2 2
3 1
1 3
1 1
1 17 3
1 1
1 1
4 5
2 4
6 3
2 3
7 4
2 2
40 3
1 6
6 2
4 4
3 2
2 4
5 5
17
- 1. Ensure that at least two topics from every K/A are sampled within each tier (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 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 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 priorities. Enter the tier totals for each category in the table above.
Wednesday, May 15, 2002 Page 1 of 13
TIER GROUP Category GROUP_Total TIER_Total 1
1 A1 6
A2 4
G 1
K1 6
K2 4
K3 3
24 1
2 A1 2
A2 5
G 1
K1 1
K3 7
16 1
3 A1 1
A2 2
3 Tier Total: 43 TIER GROUP Category GROUP_Total TIER_Total 2
1 A1 2
A2 3
A3 3
A4 1
G 1
K1 3
K3 2
K4 3
K6 1
19 2
2 A1 1
A2 3
A3 1
A4 1
G 1
K1 1
K2 1
K3 2
K4 2
K5 3
K6 1
17 2
3 A2 1
K1 1
K2 1
K4 1
4 Wednesday, May 15, 2002 Page 2 of 13 ES-401 PWR SRO (continued)
Tier Total: 40 TIER GROUP Category GROUP_Total TIER_Total 3
1 G1 6
6 3
2 G2 4
4 3
3 G3 2
2 3
4 G4 5
5 Tier Total: 17 Wednesday, May 15, 2002 Page 3 of 13
Check of Tier Totals 1
A1 9
Sat 1
A2 11 Sat 1
G 2
Sat 1
K1 7
Sat 1
K2 4
Sat 1
K3 10 Sat 2
A1 3
Sat 2
A2 7
Sat 2
A3 4
Sat 2
A4 2
Sat 2
G 2
Sat 2
K1 5
Sat 2
K2 2
Sat 2
K3 4
Sat 2
K4 6
Sat 2
K5 3
Sat 2
K6 2
Sat 3
G1 6
Sat 3
G2 4
Sat 3
G3 2
Sat 3
G4 5
Sat Wednesday, May 15, 2002 Page 4 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 ES401-3 OUTLINE Tier 1
Group 1 A1 4.1.029 Anticipated Transient Without Scram (ATWS) 4.1.029.EA1.03 Ability to operate and monitor the following as they apply to a 3.2 1
ATWS: Charging pump suction valves from VCT operating switch 4.1.074 Inadequate Core Cooling 4.1.074.EA1.24 Ability to operate and monitor the following as they apply to a 3.8 1
Inadequate Core Cooling: Turbine bypass valve hand/automatic controls, indicators, and set points 4.2.005 Inoperable/Stuck Control Rod 4.2.005.AA1.03 Ability to operate and / or monitor the following as they apply 3.4 1
to the Inoperable / Stuck Control Rod: Metroscope 4.5.E02 SI Termination 4.5.E02.EA1.01 Ability to operate and / or monitor the following as they apply 3.9 1
to the (SI Termination): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 4.2.068 Control Room Evacuation 4.2.068.AA1.14 Ability to operate and / or monitor the following as they apply 4.4 1
to the Control Room Evacuation: Reactor trip breakers and switches 4.2.067 Plant Fire on Site 4.2.067.AA1.05 Ability to operate and / or monitor the following as they apply 3.1 1
to the Plant Fire on Site: Plant and control room ventilation systems A2 4.2.068 Control Room Evacuation 4.2.068.AA2.10 Ability to determine and interpret the following as they apply 4.4 1
to the Control Room Evacuation: Source range count rate 4.5.E02 SI Termination 4.5.E02.EA2.01 Ability to determine and interpret the following as they apply 4.2 1
to the (SI Termination) Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
4.2.076 High Reactor Coolant Activity 4.2.076.AA2.04 Ability to determine and interpret the following as they apply 3
1 to the High Reactor Coolant Activity: Process effluent radiation chart recorder 4.2.076 High Reactor Coolant Activity 4.2.076.AA2.03 Ability to determine and interpret the following as they apply 3
1 to the High Reactor Coolant Activity: RCS radioactivity G
4.2.027G Generic KA for Pressurizer Pressure Control System 4.1 1
Malfunction (2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions)
K1 4.5.E02 SI Termination 4.5.E02.EK1.02 Knowledge of the operational implications of the following 3.9 1
concepts as they apply to the (SI Termination) Normal, abnormal and emergency operating procedures associated with (SI Termination).
Wednesday, May 15, 2002 Page 5 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 4.2.067 Plant Fire on Site 4.2.067.AK1.01 Knowledge of the operational implications of the following 3.9 1
concepts as they apply to Plant Fire on Site: Fire classifications, by type 4.1.055 Station Blackout 4.1.055.EK1.02 Knowledge of the operational implications of the following 4.4 1
concepts as they apply to the Station Blackout : Natural circulation cooling 4.5.E04 LOCA Outside Containment 4.5.E04.EK1.01 Knowledge of the operational implications of the following 3.9 1
concepts as they apply to the (LOCA Outside Containment)
Components, capacity, and function of emergency systems.
4.5.E09 Natural Circulation Operations 4.5.E09.EK1.02 Knowledge of the operational implications of the following 3.7 1
concepts as they apply to the (Natural Circulation Operations) Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).
4.2.069 Loss of Containment Integrity 4.2.069.AK1.01 Knowledge of the operational implications of the following 3.1 1
concepts as they apply to Loss of Containment Integrity:
Effect of pressure on leak rate K2 4.5.E01 Rediagnosis 4.5.E01.EK2.02 Knowledge of the interrelations between the (Reactor Trip or 3.8 1
Safety Injection/Rediagnosis) and the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
4.5.E01 Rediagnosis 4.5.E01.EK2.01 Knowledge of the interrelations between the (Reactor Trip or 3.5 1
Safety Injection/Rediagnosis) and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
4.2.068 Control Room Evacuation 4.2.068.AK2.03 Knowledge of the interrelations between the Control Room 3.1 1
Evacuation and the following: Controllers and positioners 4.2.001 Continuous Rod Withdrawal 4.2.001.AK2.05 Knowledge of the interrelations between the Continuous Rod 3.1 1
Withdrawal and the following: Rod motion lights K3 4.5.E01 Rediagnosis 4.5.E01.EK3.02 Knowledge of the reasons for the following responses as 3.9 1
they apply to the (Reactor Trip or Safety Injection/Rediagnosis) Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety 4.2.051 Loss of Condenser Vacuum 4.2.051.AK3.01 Knowledge of the reasons for the following responses as 3.1 1
they apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum 4.5.E07 Saturated Core Cooling 4.5.E07.EK3.01 Knowledge of the reasons for the following responses as 3.7 1
they apply to the (Saturated Core Cooling) 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.
Wednesday, May 15, 2002 Page 6 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 Tier 1
Group 2 A1 4.2.065 Loss of Instrument Air 4.2.065.AA1.05 Ability to operate and / or monitor the following as they apply 3.3 1
to the Loss of Instrument Air: RPS 4.1.038 Steam Generator Tube Rupture 4.1.038.EA1.37 Ability to operate and monitor the following as they apply to a 3.4 1
SGTR: Controlling of thermal shock during PZR spray A2 4.2.061 Area Radiation Monitoring (ARM) System Alarms 4.2.061.AA2.03 Ability to determine and interpret the following as they apply 3.3 1
to the Area Radiation Monitoring (ARM) System Alarms:
Set points for alert and high alarms 4.5.E05 Loss of Secondary Heat Sink 4.5.E05.EA2.02 Knowledge of the reasons for the following responses as 4.3 1
they apply to the (Loss of Secondary Heat Sink) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
4.1.038 Steam Generator Tube Rupture 4.1.038.EA2.11 Ability to determine or interpret the following as they apply to 3.9 1
a SGTR: Local radiation reading on main steam lines 4.1.009 Small Break LOCA 4.1.009.EA2.01 Ability to determine or interpret the following as they apply to 4.8 1
a small break LOCA: Actions to be taken, based on RCS temperature and pressure, saturated and superheated 4.2.060 Accidental Gaseous Radwaste Release 4.2.060.EA2.04 Ability to determine and interpret the following as they apply 3.4 1
to the Accidental Gaseous Radwaste: The effects on the power plant of isolating a given radioactive-gas leak G
4.1.011G Generic KA for Large Break LOCA (2.4.18 Knowledge of the 3.6 1
specific bases for EOPs)
K1 4.5.E16 High Containment Radiation 4.5.E16.EK1.03 Knowledge of the operational implications of the following 3.3 1
concepts as they apply to the (High Containment Radiation)
Annunciators and conditions indicating signals, and remedial actions associated with the (High Containment Radiation).
K3 4.5.E11 Loss of Emergency Coolant Recirculation 4.5.E11.EK3.02 Knowledge of the reasons for the following responses as 4
1 they apply to the (Loss of Emergency Coolant Recirculation) Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant 4.5.E16 High Containment Radiation 4.5.E16.EK3.01 Knowledge of the reasons for the following responses as 3.1 1
they apply to the (High Containment Radiation) 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.
Wednesday, May 15, 2002 Page 7 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 4.5.E05 Loss of Secondary Heat Sink 4.5.E05.EK3.01 Knowledge of the reasons for the following responses as 3.8 1
they apply to the (Loss of Secondary Heat Sink) 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.
4.5.E03 LOCA Cooldown and Depressurization 4.5.E03.EK3.04 Knowledge of the reasons for the following responses as 3
1 they apply to the (LOCA Cooldown and Depressurization)
RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
4.2.008 Pressurizer Vapor Space Accident 4.2.008.AK3.03 Knowledge of the reasons for the following responses as 4.6 1
they apply to the Pressurizer Vapor Space Accident: Actions contained in EOP for PZR vapor space accident/ LOCA 4.2.022 Loss of Reactor Coolant Makeup 4.2.022.AK3.03 Knowledge of the reasons for the following responses as 3.3 1
they apply to the Loss of Reactor Coolant Pump Makeup:
Performance of lineup to establish excess letdown after determining need 4.2.032 Loss of Source Range Nuclear Instrumentation 4.2.032.AK3.02 Knowledge of the reasons for the following responses as 4.1 1
they apply to the Loss of Source Range Nuclear Instrumentation: Guidance contained in EOP for loss of source-range nuclear instrumentation Tier 1
Group 3 A1 4.2.028 Pressurizer Level Control Malfunction 4.2.028.AA1.07 Ability to operate and / or monitor the following as they apply 3.3 1
to the Pressurizer Level Control Malfunctions: Charging pumps maintenance of PZR level (including manual backup)
A2 4.2.028 Pressurizer Level Control Malfunction 4.2.028.AA2.14 Ability to determine and interpret the following as they apply 2.8 1
to the Pressurizer Level Control Malfunctions: The effect on indicated PZR levels, given a change in ambient pressure and temperature of reflux boiling 4.2.056 Loss of Off-Site Power 4.2.056.AA2.02 Ability to determine and interpret the following as they apply 3.6 1
to the Loss of Offsite Power: ESF load sequencer status Tier 2
Group 1 A1 3.7.015 Nuclear Instrumentation System 3.7.015.A1.08 Ability to predict and/or monitor changes in parameters to 3.4 1
prevent exceeding design limits) associated with operating the NIS controls including: Changes in RCS temperature 3.5.022 Containment Cooling System 3.5.022.A1.02 Ability to predict and/or monitor changes in parameters (to 3.8 1
prevent exceeding design limits) associated with operating the CCS controls including: Containment pressure Wednesday, May 15, 2002 Page 8 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 A2 3.4.059 Main Feedwater System 3.4.059.A2.04 Ability to (a) predict the impacts of the following malfunctions 3.4 1
or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Feeding a dry S/G 3.2.004 Chemical and Volume Control System 3.2.004.A2.19 Ability to (a) predict the impacts of the following malfunctions 3.5 1
or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High secondary and primary concentrations of chloride, fluoride, sodium and solids 3.5.022 Containment Cooling System 3.5.022.A2.06 Ability to (a) predict the impacts of the following malfunctions 3.2 1
or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCS pump A3 3.4.061 Auxiliary / Emergency Feedwater System 3.4.061.A3.02 Ability to monitor automatic operation of the AFW, including:
4 1
RCS cooldown during AFW operations 3.5.026 Containment Spray System 3.5.026.A3.01 Ability to monitor automatic operation of the CSS, including:
4.5 1
Pump starts and correct MOV positioning 3.2.004 Chemical and Volume Control System 3.2.004.A3.12 Ability to monitor automatic operation of the CVCS, ncluding:
2.7 1
Interpretation of letdown demineralizer flow-divert valve position indicating lights A4 3.4.059 Main Feedwater System 3.4.059.A4.10 Ability to manually operate and monitor in the control room:
3.8 1
G 3.9.068G Generic KA for Liquid Radwaste System (2.3.4 Knowledge of 3.1 1
radiation exposure limits and contamination control, including permissible levels in excess of those authorized)
K1 3.5.022 Containment Cooling System 3.5.022.K1.02 Knowledge of the physical connections and/or cause-effect 3.5 1
relationships between the CCS and the following systems:
SEC/remote monitoring systems 3.7.015 Nuclear Instrumentation System 3.7.015.K1.03 Knowledge of the physical connections and/or cause-effect 3.1 1
relationships between the NIS and the following systems:
3.4.003 Reactor Coolant Pump System 3.4.003.K1.01 Knowledge of the physical connections and/or cause-effect 2.8 1
relationships between the RCPS and the following systems:
RCP lube oil K3 3.4.003 Reactor Coolant Pump System 3.4.003.K3.03 Knowledge of the effect that a loss or malfunction of the RCPS 3.1 1
will have on the following: Feedwater and emergency feedwater Wednesday, May 15, 2002 Page 9 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 3.5.022 Containment Cooling System 3.5.022.K3.02 Containment equipment subject to damage by high or low 3.3 1
temperature, humidity, and pressure Containment instrumentation readings K4 3.2.013 Engineered Safety Features Actuation System 3.2.013.K4.12 Knowledge of ESFAS design feature(s) and/or interlock(s) 3.9 1
which provide for the following Safety injection block 3.5.022 Containment Cooling System 3.5.022.K4.03 Knowledge of CCS design feature(s) and/or interlock(s) which 4
1 provide for the following: Automatic containment isolation 3.4.061 Auxiliary / Emergency Feedwater System 3.4.061.K4.01 Knowledge of AFW design feature(s) and/or interlock(s) which 4.2 1
provide for the following: Water sources and priority of use K6 3.2.013 Engineered Safety Features Actuation System 3.2.013.K6.01 Knowledge of the effect of a loss or malfunction on the 3.1 1
following will have on the ESFAS: Sensors and detectors Tier 2
Group 2 A1 3.7.012 Reactor Protection System 3.7.012.A1.01 Ability to predict and/or monitor Changes in parameters (to 3.4 1
prevent exceeding design limits) associated with operating the RPS controls including: Trip set point adjustment A2 3.8.029 Containment Purge System 3.8.029.A2.01 Ability to (a) predict the impacts of the following mal-3.6 1
functions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Maintenance or other activity taking place inside containment 3.2.011 Pressurizer Level Control System 3.2.011.A2.04 Ability to (a) predict the impacts of the following malfunctions 3.7 1
or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of Loss of one, two or three charging pumps 3.6.062 A.C. Electrical Distribution 3.6.062.A2.09 Ability to (a) predict the impacts of the following malfunctions 3
1 or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequences of exceeding current limitations A3 3.4.055 Condenser Air Removal System 3.4.055.A3.03 Ability to monitor automatic operation of the CARS, including:
2.7 1
Automatic diversion of CARS exhaust A4 3.8.029 Containment Purge System 3.8.029.A4.04 Ability to manually operate and/or monitor in the control 3.6 1
room: Containment evacuation signal Wednesday, May 15, 2002 Page 10 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 G
3.8.079G Generic KA for Station Air System (2.2.22 Knowledge of limiting 4.1 1
Conditions for operations and safety limits)
K1 3.7.016 Non-Nuclear Instrumentation System 3.7.016.K1.10 Knowledge of the physical connections and/or cause-effect 3.1 1
relationships between the NNIS and the following systems:
K2 3.2.006 Emergency Core Cooling System 3.2.006.K2.02 Knowledge of bus power supplies to the following: Valve 2.9 1
operators for accumulators K3 3.4.035 Steam Generator System 3.4.035.K3.01 Knowledge of the effect that a loss or malfunction of the 4.6 1
S/GS will have on the following: RCS 3.7.016 Non-Nuclear Instrumentation System 3.7.016.K3.08 Knowledge of the effect that a loss or malfunction of the 3.7 1
NNIS will have on the following: PZR PCS K4 3.8.086 Fire Protection System 3.8.086.K4.01 Knowledge of design feature(s) and/or interlock(s) which 3.7 1
provide for the following: Adequate supply of water for FPS 3.7.073 Process Radiation Monitoring System 3.7.073.K4.01 Knowledge of PRM system design feature(s) and/or 4.3 1
interlocks which provide for the following: Release termination when radiation exceeds set point K5 3.3.010 Pressurizer Pressure Control System 3.3.010.K5.02 Knowledge of the operational implications of the following 3
1 concepts as the apply to the PZR PCS: Constant enthalpy expansion through a valve 3.5.028 Hydrogen Recombiner and Purge Control System 3.5.028.K5.02 Knowledge of the operational implications of the following 3.9 1
concepts as they apply to the HRPS: Flammable hydrogen concentration 3.8.086 Fire Protection System 3.8.086.K5.03 Knowledge of the operational implication of the following 3.4 1
concepts as they apply to the Fire Protection System:
Effect of water spray on electrical components K6 3.5.028 Hydrogen Recombiner and Purge Control System 3.5.028.K6.01 Knowledge of the effect of a loss or malfunction on the 3.1 1
following will have on the HRPS: Hydrogen recombiners Tier 2
Group 3 A2 3.8.008 Component Cooling Water System 3.8.008.A2.04 Ability to (a) predict the impacts of the following malfunctions 3.5 1
or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PRMS alarm Wednesday, May 15, 2002 Page 11 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 K1 3.4.045 Main Turbine Generator System 3.4.045.K1.06 Knowledge of the physical connections and/or cause-effect 2.6 1
relationships between the MT/G system and the following systems: RCS, during steam valve test K2 3.4.076 Service Water System 3.4.076.K2.01 Knowledge of bus power supplies to the following: Service 2.7 1
K4 3.4.045 Main Turbine Generator System 3.4.045.K4.47 Knowledge of MT/G system design feature(s) and/or 4.3 1
inter-lock(s) which provide for the following: Turbine trip upon reactor trip Tier 3
Group 1 G1 2.1.19 2.1.19 Conduct of Operations: Ability to use plant computer to 3
1 obtain and evaluate parametric information on system or component STATUS 2.1.22 2.1.22 Conduct of Operations: Ability to determine Mode of 3.3 1
2.1.24 2.1.24 Conduct of Operations: Ability to obtain and interpret station 3.1 1
electrical and mechanical drawings.
2.1.18 2.1.18 Conduct of Operations: Ability to make accurate, clear and 3
1 concise logs, records, status boards, and reports.
2.1.6 2.1.6 Conduct of Operations: Ability to supervise and assume a 4.3 1
management role during plant transients and upset 2.1.16 2.1.16 Conduct of Operations: Ability to operate plant phone, paging 2.8 1
system, and two-way radio.
Tier 3
Group 2 G2 2.2.23 2.2.23 Equipment Control Ability to track limiting conditions for 3.8 1
operations.
2.2.3 2.2.3 Equipment Control (multi-unit) Knowledge of the design, 3.3 1
procedural, and operational differences between units.
2.2.22 2.2.22 Equipment Control Knowledge of limiting conditions for 4.1 1
operations and safety limits.
2.2.11 2.2.11 Equipment Control Knowledge of the process for controlling 3.4 1
temporary changes.
Wednesday, May 15, 2002 Page 12 of 13
ES-401 PWR SRO (continued) CPSES - 11/2002 Tier 3
Group 3 G3 2.3.2 2.3.2 Radiation Control Knowledge of facility ALARA program.
2.9 1
2.3.4 2.3.4 Radiation Control Knowledge of radiation exposure limits and 3.1 1
contamination control, including permissible levels in excess of those authorized.
Tier 3
Group 4 G4 2.4.25 2.4.25 Emergency Procedures / Plan Knowledge of fire protection 3.4 1
procedures.
2.4.39 2.4.39 Emergency Procedures / Plan Knowledge of the RO's 3.1 1
responsibilities in emergency plan implementation.
2.4.46 2.4.46 Emergency Procedures / Plan Ability to verify that the 3.6 1
alarms are consistent with the plant conditions.
2.4.43 2.4.43 Emergency Procedures / Plan Knowledge of emergency 3.5 1
communications systems and techniques.
2.4.47 2.4.47 Emergency Procedures / Plan Ability to diagnose and 3.7 1
recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
Wednesday, May 15, 2002 Page 13 of 13