ML023570392

CP - Init Exam - 11/2002 - Final Outline

ML023570392
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, NUREG-1021 50-445/02-301, 50-446/02-301
Download: ML023570392 (34)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Revision 2 Facility: CPSES Date of Examination: 11/2002 Examination Level: RO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Conduct of ROA1 (BANK)

Operations -G2.1.20 Ability to execute procedure steps. (3.9/4.0)

--Perform a Quadrant Power Tilt Ratio Calculation Conduct of ROA2 (NEW)

Operations -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 ROA3 (NEW)

Control -G2.2.13 Knowledge of tagging and clearance procedures. (3.6/3.8)

--Identify errors in faulted tag A.3 Radiation ROA4 (NEW)

Control -G2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (2.9/3.3)

--Interpret a Survey Map and Answer 2 Questions about it.

A.4 Emergency ROA5.1 (NEW)

Plan -G2.4.39 Knowledge of ROs responsibilities in emergency plan implementation. (3.3/3.1)

-Question from the general training plan ROA5.2 (NEW)

-G2.4.39 Knowledge of ROs responsibilities in emergency plan implementation. (3.3/3.1)

-Question from the general training plan

ES-301 Administrative Topics Outline Form ES-301-1 Revision 2 Facility: CPSES Date of Examination: 11/2002 Examination Level: SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Conduct of SROA1(BANK)

Operations -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 SROA2(NEW)

Operations -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)

-Review a Faulted Calorimetric Calculation A.2 Equipment SROA3(NEW)

Control -G2.2.13 Knowledge of tagging and clearance procedures. (3.6/3.8)

--Identify errors in faulted tag A.3 Radiation SROA4(NEW)

Control -G2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (2.9/3.3)

--Interpret a Survey Map and Answer 2 Questions about it.

A.4 Emergency SROA5.1(MODIFIED)

Plan -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.

Revision 2 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 Safety Code* 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 D, C 3 Pressurizer Pressure Channel in Trip Condition B.2 Facility Walk-Through

a. JPMP1: Fire Protection / PEO #1 actions to achieve hot D, P, L, R 8 shutdown after fire in the control room

b. JPMP2: Main Steam and MFW / Locally Isolate a D, P, L 4 Ruptured S/G (Secondary)

c. JPMP3: EDG / Perform a Local Emergency Start of a D, P, R 6 DG

• 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

Revision 2 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(U) Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Safety Code* 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 D, P, L, R 8 shutdown after fire in the control room

b. JPMP2: Main Steam and MFW / Locally Isolate a D, P, L 4 Ruptured S/G (Secondary)

c. JPMP3: EDG / Perform a Local Emergency Start of a D, P, R 6 DG

• 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

Revision 2 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 McKernon Fred Sanchez Note: (NEW) SRO Admin A.5-1, Emerg. Class. with this Scenario (SAE).

Initial Conditions: Full power steady state; BOL; Equilibrium Xenon; 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.: IC-15, EGR06 - DG1 out of service with sw. in pull out)

(PRELOAD - MET Tower Data -> wind from 180)

Turnover: The plant has been at 100% power for the last 15 days. Severe thunderstorm warning and high winds issued and ABN-907, Sec. 5 completed. Maintenance has been trouble shooting problems with the 1-01 HTR Drain Pump, and requests the pump be secured within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Management has directed a power reduction to 70% at 15%/hour to support securing the 1-01 HTR Drain Pump. EDG 1-01 is out of service for maint., and OPT-215 was completed 1 hr ago.

Event Malf. No. Event Event No. Type* Description 1 N (SRO) Reduce power to 70%

T=0 R (RO)

N (BOP) 2 (Cue) RX05A I (SRO) Pressurizer level transmitter LT-459 fails low [value=0, ramp over 1 min]

T=12 I (RO) (NOTE: initiate Event 2 on Chief Examiners cue) 3 TC05A C (SRO) #1 Main turbine control valve fails closed T=22 C (BOP) (NOTE: initiate Event 3 prior to completion of actions for Event 2) 4 ED06G C (ALL) Loss of 1D3 bus T=32 5 (Cue) RC03D C (RO) RCP 4 vibration - initial severity @ 9 mils and ramp severity to 25 mils over T=40 C (SRO) 6 min. High vib. alarm on RCP 4 (shaft) alarms at 15 mils & increasing @

approx 3 mils/min.

(NOTE: must provide cue for vibration monitor readings - increasing at 3 mils/min - when applicant goes to look)

T=44 Manual Rx Scram due to high RCP 1-04 vibrations, no SI. Enter EOP-0.0A and then transition to EOS-0.1A.

6 ED01 M (ALL) Lighting strike in switchyard - loss of offsite power. EDG 1-02 starts and T=49 loads (NOTE: E6 to be initiated 5 minutes after RX Trip)

(NOTE to Simulator Operator: Call RO and report lighting strike in switchyard and high winds with wind speed of 105 mph (sustained))

7 EG07B C (ALL) EDG 1-02 trips (overspeed) - loss of all power. Transition to ECA-0.0A T=E6+3 and possibly ABN-601.

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

Revision 2 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 McKernon Fred Sanchez Note: (NEW) SRO Admin A.5-2, Emerg. Class. with this Scenario (SAE).

Initial Conditions: 75% power and steady; BOL.

(IC-14; RP01 - Failure of automatic RX trip; RP13C - Manual RX trip failure <both>; TC07C - Automatic main turbine trip failure <both>; Fault 1B4 to prevent manual RX trip by de-energizing the bus)

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 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. OPT-215 was completed on DG-1 1 hr ago.

Event Malf. Event Event No. No. Type* Description 1 N (SRO) Increase reactor power back to 100%

T=0 R (RO)

N (BOP) 2 (Cue) RX04C I (SRO) S/G 3 Level Transmitter LT-553 fails low T=10 I (RO)

(If RO or BOP goes to place bistables in trip, start E3) 3 TP04A C (SRO) Main Feedwater pump A TPCW blockage [value=100%,

T=19 C (RO) ramp over 5 min]

• • 4 FW03B C (ALL) Feedwater pump B trips; failure of automatic and manual T=27 RP01 M (ALL) reactor trip; failure of automatic main turbine trip.

• • • 5 SG01C M (ALL) S/G#4 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.

Revision 2 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 McKernon Fred Sanchez Note: (BANK) This scenario is an unused spare from the 2001 CPSES exam Initial Conditions: 30% power and steady. (IC-11)

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. Start at IPO-003A step 5.4.10 and SOP-308A step 5.1.20 for the power increase.

Event Malf. Event Event No. No. Type* Description 1 N (SRO) Increase Reactor power back to 100%

T=0 N (BOP)

R (RO) 2 (Cue) MS13A I (RO) MSL 1 Press Instrument PI-2325 fails high (100%)

T=13 I (BOP)

I (SRO) 3 RX08A I (RO) PZR press transmitter PT-455 fails at 2300# (ramps over 45 T=16 I (SRO) seconds) 4 RX15A C (RO) PZR spray flow control valve failure (PCV-455B) @ 70%

T=16 C (SRO) severity. Failure occurs at the instant that the RO takes pressure control to manual. (Removing faulty card - PCV-455B CTRL (RXR96) - allows spray valve to go back to closed) 5 FW16 C (RO) Lowering vacuum on main condenser due to loss of vacuum T=22 C (BOP) breaker water seal (5% severity)

C (SRO) 6 TC06C M (ALL) Main turbine spurious trip and MSIV #1 closes causing SG1 T=35 MS07A M (ALL)

Safety MS-021 to fail open MS10A1

@100%

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

ES-401 - 4.r2 PWR RO CPSES - 11/2002 TIER GROUP K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G G1 G2 G3 G4 Total 1

1 3 1 2 5 3 1 15 2 2 3 5 2 5 1 18 3 2 2 4 5 4 7 9 10 2 37 2

1 6 2 3 1 2 4 3 1 1 23 2 1 1 2 6 1 1 3 2 1 1 19 3 2 1 2 1 1 1 8 9 2 4 11 2 2 3 8 5 2 2 50 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. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

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.

Thursday, October 31, 2002 Page 1 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 TIER GROUP Category GROUP_Total TIER_Total 1 1 A1 5 A2 3 G 1 K1 3 K2 1 K3 2 15 1 2 A1 2 A2 5 G 1 K1 2 K2 3 K3 5 18 1 3 A1 2 A2 2 4

Tier Total: 37 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 3 A3 2 A4 1 G 1 K1 1 K2 1 K3 2 K4 6 K5 1 19 2 3 A2 1 K1 2 K2 1 K4 2 K5 1 K6 1 Thursday, October 31, 2002 Page 2 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 8

Tier Total: 50 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 Thursday, October 31, 2002 Page 3 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 Check of Tier Totals 1 A1 9 Sat 1 A2 10 Sat 1 G 2 Sat 1 K1 5 Sat 1 K2 4 Sat 1 K3 7 Sat 2 A1 3 Sat 2 A2 8 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 11 Sat 2 K5 2 Sat 2 K6 2 Sat 3 G1 3 Sat 3 G2 4 Sat 3 G3 2 Sat 3 G4 4 Sat Thursday, October 31, 2002 Page 4 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 ES401-4 OUTLINE Tier 1 Group 1 A1 RO#1 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 setpoints RO#2 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 RO#3 4.2.005 Inoperable/Stuck Control Rod 4.2.005.AA1.05 Ability to operate and / or monitor the following as they apply to 3.4 1 the Inoperable / Stuck Control Rod: RPI RO#4 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 RO#5 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 RO#6 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 RO#7 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 RO#8 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 G

RO#9 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 RO#10 4.1.055 Station Blackout 4.1.055.EK1.02 Knowledge of the operational implications of the following 4.1 1 concepts as they apply to the Station Blackout : Natural RO#11 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 RO#13 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).

K2 RO#14 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 Thursday, October 31, 2002 Page 5 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 K3 RO#15 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 RO#16 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 RO#17 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 RO#18 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 RO#19 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 RO#20 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 RO#21 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: Setpoints for alert and high alarms RO#61 4.2.022 Loss of Reactor Coolant Makeup 4.2.022.AA2.03 Ability to determine and interpret the following as they apply to 3.6 1 the Loss of Reactor Coolant Pump Makeup: Failures of flow control valve or controller RO#22 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 G

RO#23 4.1.011G Generic KA for Large Break LOCA : 2.4.18 Knowledge of the 2.7 1 specific bases for EOPs.

K1 RO#24 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)

RO#25 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.

Thursday, October 31, 2002 Page 6 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 K2 RO#26 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.

RO#27 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 RO#28 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 K3 RO#29 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.

RO#30 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.

RO#31 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).

RO#32 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 RO#33 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 as a witnin 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.

Tier 1 Group 3 A1 RO#34 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 RO#35 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)

A2 RO#36 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 Thursday, October 31, 2002 Page 7 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 RO#12 4.2.028 Pressurizer Level Control Malfunction 4.2.028.AA2.01 Ability to determine and interpret the following as they apply to 3.4 1 the Pressurizer Level Control Malfunctions: PZR level indicators and alarms Tier 2 Group 1 A1 RO#37 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 RO#38 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 A2 RO#39 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 operationson 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 RO#40 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 RO#41 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 RO#42 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 A3 RO#43 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 RO#44 3.2.004 Chemical and Volume Control System 3.2.004.A3.12 Ability to monitor automatic operation of the CVCS, ncluding: 3 1 Interpretation of letdown demineralizer flow-divert valve position indicating lights RO#45 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 RO#46 3.4.059 Main Feedwater System 3.4.059.A4.11 Ability to manually operate and monitor in the control room: 3.1 1 Recovery from automatic feedwater isolation G

RO#47 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.

Thursday, October 31, 2002 Page 8 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 K1 RO#48 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 RO#49 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 RO#50 3.1.001 Control Rod Drive System 3.1.001.K1.05 Knowledge of the physical connections and/or cause-effect 4.5 1 relationships between the CRDS and the following systems: NIS and RPS RO#51 3.7.015 Nuclear Instrumentation System 3.7.015.K1.01 Knowledge of the physical connections and/or cause-effect 4.1 1 relationships between the NIS and the following systems:RPS RO#52 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 RO#53 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 K3 RO#54 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 RO#55 3.4.061 Auxiliary / Emergency Feedwater System 3.4.061.K3.02 Knowledge of the effect that a loss or malfunction of the AFW 4.2 1 will have on the following: S/G K4 RO#56 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 RO#57 3.2.013 Engineered Safety Features Actuation System 3.2.013.K4.12 Knowledge of ESFAS design feature(s) and/or intelock(s) which 3.7 1 provide for the following Safety injection block RO#58 3.1.001 Control Rod Drive System 3.1.001.K4.23 Knowledge of CRDS design feature(s) and/or interlock(s) which 3.4 1 provide for the following: Rod motion inhibit K6 RO#59 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 RO#60 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 setpoint adjustment A2 RO#62 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 Thursday, October 31, 2002 Page 9 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 RO#63 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 RO#64 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 RO#65 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 RO#66 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 A4 RO#67 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

RO#68 3.7.012G Generic KA for Reactor Protection System : 2.2.22 Knowledge of 3.4 1 limiting conditions for operations and safety limits.

K1 RO#69 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 RO#70 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 RO#71 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 RO#72 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 RO#73 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 RO#74 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 Thursday, October 31, 2002 Page 10 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 RO#75 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 setpoint RO#76 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 RO#77 3.4.035 Steam Generator System 3.4.035.K4.05 Knowledge of S/GS design feature(s) and/or interlock(s) which 2.9 1 provide for the following: Amount of reserve water in S/G RO#78 3.8.086 Fire Protection System 3.8.086.K4.03 Knowledge of design feature(s) and/or interlock(s) which provide 3.1 1 for the following: Detection and location of fires K5 RO#79 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 RO#80 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 RO#81 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 RO#82 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 K2 RO#83 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 RO#84 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 RO#85 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 F2. 1 provide for the following: Quench tank cooling K5 RO#86 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 RO#87 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 Thursday, October 31, 2002 Page 11 of 12

ES-401.r2 PWR RO (continued) CPSES - 11/2002 Tier 3 Group 1 G1 RO#88 2.1.16 2.1.16 Conduct of Operations: Ability to operate plant phone, paging 2.9 1 system, and two-way radio.

RO#89 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.

RO#90 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 RO#91 2.2.3 2.2.3 Equipment Control (multi-unit) Knowledge of the design, 3.1 1 procedural, and operational differences between units.

RO#92 2.2.22 2.2.22 Equipment Control Knowledge of limiting conditions for operations 3.4 1 and safety limits.

RO#93 2.2.23 2.2.23 Equipment Control Ability to track limiting conditions for 2.6 1 RO#94 2.2.11 2.2.11 Equipment Control Knowledge of the process for controlling 2.5 1 temporary changes.

Tier 3 Group 3 G3 RO#95 2.3.2 2.3.2 Radiation Control Knowledge of facility ALARA program. 2.5 1 RO#96 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 RO#97 2.4.39 2.4.39 Emergency Procedures / Plan Knowledge of the RO's 3.3 1 responsibilities in emergency plan implementation.

RO#98 2.4.46 2.4.46 Emergency Procedures / Plan Ability to verify that the alarms 3.5 1 are consistent with the plant conditions.

RO#99 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.

RO#100 2.4.25 2.4.25 Emergency Procedures / Plan Knowledge of fire protection 2.9 1 procedures.

Thursday, October 31, 2002 Page 12 of 12

ES-401 Record of Rejected K/As-RO Form ES-401-10 Tier/Group Randomly Selected K/A Reason for Rejection 1/1 4.2.005.AA1.03 Not applicable to CPSES 2/1 3.4.059.A4.10 Not applicable to CPSES 2/1 3.5.022.K1.02 Too many K/As from this system 2/1 3.5.022.K4.03 Too many K/As from this system 2/1 3.4.003.K3.03 Too many K/As from this system 2/2 3.8.079.G.2.2.22 Not applicable to CPSES 2/2 3.8.086.K5.03 Unable to generate question, and none in banks either 1/1 4.2.069.AK1.01 Unable to find/generate adequate RO quesiton 2/1 3.7.015.K1.08 Not applicable to CPSES 1/2 4.2.060.AA2.04 Unable to generate question, and none in banks either 1/2 4.2.022.AK3.03 Not applicable to CPSES 2/2 3.8.029.A2.01 Unable to find/generate adequate RO question

ES-401 - 3.r2 PWR SRO CPSES - 11/2002 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 6 2 6 1 16 3 1 2 3 7 4 9 9 12 2 43 2

1 3 2 3 1 2 3 3 1 1 19 2 1 1 2 3 2 1 1 3 1 1 1 17 3 1 1 1 1 4 5 2 4 7 2 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. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

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.

Thursday, October 31, 2002 Page 1 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 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 6 G 1 K1 1 K3 6 16 1 3 A1 1 A2 2 3

Tier Total: 43 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 3 K5 2 K6 1 17 2 3 A2 1 K1 1 K2 1 K4 1 4

Thursday, October 31, 2002 Page 2 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 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 Thursday, October 31, 2002 Page 3 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 Check of Tier Totals 1 A1 9 Sat 1 A2 12 Sat 1 G 2 Sat 1 K1 7 Sat 1 K2 4 Sat 1 K3 9 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 7 Sat 2 K5 2 Sat 2 K6 2 Sat 3 G1 6 Sat 3 G2 4 Sat 3 G3 2 Sat 3 G4 5 Sat Thursday, October 31, 2002 Page 4 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 ES401-3 OUTLINE Tier 1 Group 1 A1 RO/SRO#17 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 RO/SRO#1 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 setpoints RO/SRO#4 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 RO/SRO#5 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 RO/SRO#3 4.2.005 Inoperable/Stuck Control Rod 4.2.005.AA1.05 Ability to operate and / or monitor the following as they apply 3.4 1 to the Inoperable / Stuck Control Rod: RPI RO/SRO#18 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 A2 RO/SRO#7 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 RO/SRO#6 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 RO/SRO#8 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 SRO ONLY#19 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.

G RO/SRO#9 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 K1 RO/SRO#11 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 Thursday, October 31, 2002 Page 5 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 RO/SRO#10 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 SRO ONLY#73 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 RO/SRO#24 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).

RO/SRO#25 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.

RO/SRO#13 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).

K2 RO/SRO#28 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 SRO ONLY#14 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 RO/SRO#26 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.

RO/SRO#27 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.

K3 RO/SRO#15 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 RO/SRO#31 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 RO/SRO#16 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.

Thursday, October 31, 2002 Page 6 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 Tier 1 Group 2 Imp.

A1 RO/SRO#34 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 SRO ONLY#2 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 RO/SRO#20 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 RO/SRO#22 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 RO/SRO#21 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:

Setpoints for alert and high alarms SRO ONLY#41 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.

RO/SRO#61 4.2.022 Loss of Reactor Coolant Makeup 4.2.022.AA2.03 Ability to determine and interpret the following as they apply to 3.6 1 the Loss of Reactor Coolant Pump Makeup: Failures of flow control valve or controller SRO ONLY#45 4.2.060 Accidental Gaseous Radwaste Release 4.2.060.AA2.02 Ability to determine and interpret the following as they apply 4.0 1 to the Accidental Gaseous Radwaste: The possible location of a radioactive-gas leak, with the assistance of PEO, HP, and CHEM pers.

G RO/SRO#23 4.1.011G Generic KA for Large Break LOCA : 2.4.18 Knowledge of the 3.6 1 specific bases for EOPs.

K1 SRO ONLY#49 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 RO/SRO#32 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 SRO ONLY#53 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 Thursday, October 31, 2002 Page 7 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 SRO ONLY#63 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 RO/SRO#33 4.5.E03 LOCA Cooldown and Depressurization 4.5.E03.EK3.04 Knowledge of the reasons for the following responses as 3.9 1 they apply to the (LOCA Cooldown and Depressurization)

RO or SRO function as a witnin 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.

RO/SRO#29 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.

RO/SRO#30 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.

Tier 1 Group 3 Imp.

A1 RO/SRO#35 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 RO/SRO#12 4.2.028 Pressurizer Level Control Malfunction 4.2.028.AA2.01 Ability to determine and interpret the following as they apply to 3.4 1 the Pressurizer Level Control Malfunctions: PZR level indicators and alarms RO/SRO#36 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 Imp.

A1 SRO ONLY#38 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 RO/SRO#37 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 A2 Thursday, October 31, 2002 Page 8 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 RO/SRO#40 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 RO/SRO#39 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 operationson 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 RO/SRO#42 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 A3 RO/SRO#65 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 RO/SRO#44 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 RO/SRO#43 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 A4 RO/SRO#46 3.4.059 Main Feedwater System 3.4.059.A4.11 Ability to manually operate and monitor in the control room: 3.3 1 Recovery from automatic feedwater isolation G

RO/SRO#47 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 RO/SRO#50 3.1.001 Control Rod Drive System 3.1.001.K1.05 Knowledge of the physical connections and/or cause-effect 4.4 1 relationships between the CRDS and the following systems:

NIS and RPS RO/SRO#52 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 RO/SRO#48 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:

K3 Thursday, October 31, 2002 Page 9 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 RO/SRO#54 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 RO/SRO#55 3.4.061 Auxiliary / Emergency Feedwater System 3.4.061.K3.02 Knowledge of the effect that a loss or malfunction of the 4.4 1 AFW will have on the following: S/G K4 RO/SRO#58 3.1.001 Control Rod Drive System 3.1.001.K4.23 Knowledge of CRDS design feature(s) and/or interlock(s) 3.8 1 which provide for the following: Rod motion inhibit RO/SRO#57 3.2.013 Engineered Safety Features Actuation System 3.2.013.K4.12 Knowledge of ESFAS design feature(s) and/or intelock(s) 3.9 1 which provide for the following Safety injection block SRO ONLY#56 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 RO/SRO#59 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 Imp.

A1 RO/SRO#60 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 setpoint adjustment A2 SRO ONLY#51 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 RO/SRO#62 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 RO/SRO#64 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 A3 RO/SRO#66 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 Thursday, October 31, 2002 Page 10 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 RO/SRO#67 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 G

SRO ONLY#68 3.7.012G Generic KA for Reactor Protection System : 2.2.22 4.1 1 Knowledge of limiting conditions for operations and safety K1 RO/SRO#69 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 RO/SRO#70 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 RO/SRO#72 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 RO/SRO#71 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 K4 RO/SRO#76 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 RO/SRO#75 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 setpoint RO/SRO#78 3.8.086 Fire Protection System 3.8.086.K4.03 Knowledge of design feature(s) and/or interlock(s) which 3.7 1 provide for the following: Detection and location of fires K5 RO/SRO#79 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 RO/SRO#86 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 K6 RO/SRO#87 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 Imp.

A2 Thursday, October 31, 2002 Page 11 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 RO/SRO#80 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 K1 RO/SRO#81 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 RO/SRO#83 3.4.076 Service Water System 3.4.076.K2.01 Knowledge of bus power supplies to the following: Service 2.7 1 K4 SRO ONLY#84 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 Imp.

G1 SRO ONLY#74 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 RO/SRO#88 2.1.16 2.1.16 Conduct of Operations: Ability to operate plant phone, paging 2.8 1 system, and two-way radio.

RO/SRO#89 2.1.18 2.1.18 Conduct of Operations: Ability to make accurate, clear and 3 1 concise logs, records, status boards, and reports.

SRO ONLY#77 2.1.22 2.1.22 Conduct of Operations: Ability to determine Mode of 3.3 1 RO/SRO#90 2.1.24 2.1.24 Conduct of Operations: Ability to obtain and interpret station 3.1 1 electrical and mechanical drawings.

SRO ONLY#82 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 Tier 3 Group 2 Imp.

G2 SRO ONLY#94 2.2.11 2.2.11 Equipment Control Knowledge of the process for controlling 3.4 1 temporary changes.

SRO ONLY#92 2.2.22 2.2.22 Equipment Control Knowledge of limiting conditions for 4.1 1 operations and safety limits.

Thursday, October 31, 2002 Page 12 of 13

ES-401.r2 PWR SRO (continued) CPSES - 11/2002 SRO ONLY#93 2.2.23 2.2.23 Equipment Control Ability to track limiting conditions for 3.8 1 operations.

RO/SRO#91 2.2.3 2.2.3 Equipment Control (multi-unit) Knowledge of the design, 3.3 1 procedural, and operational differences between units.

Tier 3 Group 3 Imp.

G3 SRO ONLY#95 2.3.2 2.3.2 Radiation Control Knowledge of facility ALARA program. 2.9 1 SRO ONLY#96 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 Imp.

G4 RO/SRO#99 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.

RO/SRO#97 2.4.39 2.4.39 Emergency Procedures / Plan Knowledge of the RO's 3.1 1 responsibilities in emergency plan implementation.

SRO ONLY#85 2.4.43 2.4.43 Emergency Procedures / Plan Knowledge of emergency 3.5 1 communications systems and techniques.

SRO ONLY#100 2.4.25 2.4.25 Emergency Procedures / Plan Knowledge of fire protection 3.4 1 procedures.

SRO ONLY#98 2.4.46 2.4.46 Emergency Procedures / Plan Ability to verify that the 3.6 1 alarms are consistent with the plant conditions.

Thursday, October 31, 2002 Page 13 of 13

ES-401 Record of Rejected K/As-SRO Form ES-401-10 Tier/Group Randomly Selected K/A Reason for Rejection 1/1 4.2.005.AA1.03 Not applicable to CPSES 2/1 3.4.059.A4.10 Not applicable to CPSES 2/1 3.5.022.K1.02 Too many K/As from this system 2/1 3.5.022.K4.03 Too many K/As from this system 2/1 3.4.003.K3.03 Too many K/As from this system 2/2 3.8.079.G.2.2.22 Not applicable to CPSES 2/2 3.8.086.K5.03 Unable to generate question, and none in banks either 1/3 4.2.028.AA2.14 Unable to generate question, and none in banks either