ML030140355

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August 2002 - Final Outline
ML030140355
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 09/18/2002
From: Gody A
Operations Branch IV
To: Anderson C
Entergy Operations
References
50-313/02-302, ES-401 50-313/02-302
Download: ML030140355 (41)
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Text

ES-401 Record of Rejected K/As - RO Exam Form ES-401-10 (R8, S1)

Tier / Group Randomly Selected K/A Reason for Rejection 1/1 051 AK2.02 Changed to AK3.01 due to low importance of initial choice, AK2.02.

1/1 055 EK3.01 Changed to EK2.07 to maintain even K&A distribution due to change in KA category in 051, Loss of Condenser Vacuum.

1/1 057 K1 Changed KA category to K3 due to lack of KA's in K1 category.

1/1 074 EK3.03 Changed to EK1.1.01 to maintain even K&A distribution due to change in KA category in 057, Loss of Vital AC Elect. Inst. Bus.

2/1 004 A3.16 Rejected since this is not applicable to ANO-1, Unit does not have emergency borate valves.

2/1 059 K5.02 Rejected since this is not applicable to ANO-1, Unit does not suffer from shrink and swell. After further consideration the entire category was rejected due to low KA's.

2/2 062 A1.01 Changed to K2.01 to maintain even K&A distribution due to change in KA category in 086, Fire Protection.

2/2 086 K2 Changed KA category to K6 due to lack of KA's in K2 category.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO Unit 1 Date of Examination: 8-19-02 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Ability to perform specific system and integrated plant Conduct of procedures during all modes of plant operation.

Operations 2.1.23 NEW ADMIN JPM (A1JPM-RO-RCS2)

Knowledge of shift turnover practices.

2.1.3 NEW CLOSED REFERENCE QUESTION Ability to execute procedure steps.

2.1.20 NEW OPEN REFERENCE QUESTION A.2 Knowledge of surveillance procedures.

Equipment Control ADMIN JPM (A1JPM-RO-SURV2) 2.2.12 A.3 Ability to control radiation releases.

Radiation Control ADMIN JPM (A1JPM-RO-RAD1) 2.3.11 A.4 Knowledge of emergency communications systems and Emergency techniques.

Procedures/Plan 2.4.43 NEW ADMIN JPM (A1JPM-RO-COMM2)

June 2000 21 of 26 NUREG-1021, Revision 8

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: _ANO UNIT 1__________________ Date of Examination: __08/19/02____

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ___1___

B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. ANO-1-JPM-R0-CRD03 D/S/A 1 Transfer Group 4 to Aux Power Supply
b. ANO-1-JPM-RO-EOP10 D/S/L 2 Perform actions required to correct ICC
c. ANO-1-JPM-R0-MFW04 N/S/A 4 Place second MFP in service (Secondary)
d. AN0-1-JPM-RO-AOP29 N/S/L 4 Perform actions for a loss of DHR (Primary)
e. ANO-1-JPM-R0-QT001 D/S 5 Transfer Quench Tank Contents to a CWRT
f. ANO-1-JPM-RO-EOP09 D/S/A/L 6 Energize Bus A2 from Bus A4 during Degraded Power
g. ANO-1-JPM-RO-ICW01 D/S 8 Shift ICW Pumps B.2 Facility Walk-Through
a. ANO-1-JPM-R0-CRD04 D 1 De-energize one CRD because of High Temperature
b. ANO-1-JPM-R0-AOP07 D/R 2 Remote Shutdown WCO Duties, 1203.009 Section 1D
c. ANO-1-JPM-R0-ED019 D/A/L 6 Synchronize and power Y02 from Y01
  • 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 NUREG-1021, Revision 8 22 of 26

ANO Unit One PWR RO Examination Outline Facility: ANO, Unit One Date of Exam: Aug. 16, 2002 Exam Level: RO K/A Category Points Point Tier Group Temp Std.

K K K K K K A A A A G Total Average Total Dev.

1 2 3 4 5 6 1 2 3 4 *

1. 1 2 2 4 3 2 3 16 16 Emergency & 2 4 2 3 3 2 3 17 17 Abnormal 3 0 0 0 1 1 1 3 3 Plant Tier Evolutions Totals 6 4 7 7 5 7 36 36 6.00 1.26
2. 1 1 2 2 3 2 2 2 2 3 2 2 23 23 Plant 2 2 1 2 2 3 2 1 2 2 1 2 20 20 Systems 3 1 1 1 0 0 1 1 1 0 1 1 8 8 Tier Totals 4 4 5 5 5 5 4 5 5 4 5 51 51 4.64 0.50
3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 5 3 3 2 13 13 K/A/G/ Totals 10 8 12 5 5 5 11 10 5 4 25 100 100 9.09 6.01 33 of 46 NUREG-1021, Revision 8, Supplement 1

PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID 000005 Inoperable/Stuck Control Rod / 1 1 2.4.11 Knowledge of abnormal condition procedures. 3.4 1 171 000015/17 RCP Malfunctions / 4 0 B/W EK2.2 Knowledge of the interrelations between the (Natural Circulation Cooldown) and the following:

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 1 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. 4.0 1 363 AA2.01 Ability to determine and interpret the following as they apply to the Emergency Boration: Whether boron 000024 Emergency Boration / 1 1 flow and/or MOVs are malfunctioning, from plant conditions. 3.8 1 417 AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Component 000026 Loss of Component Cooling Water / 8 1 Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS. 3.6 1 95 AA1.01 Ability to operate and/or monitor the following as 000027 Pressurizer Pressure Control System Malfunction / 3 1 they apply to the Pressurizer Pressure Control Malfunctions: PZR heaters, sprays, and PORV's. 4.0 1 344 B/W EK3.3 Knowledge of the reasons for the following 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive responses as they apply to the (Excessive Heat Heat Transfer / 4 1

Transfer): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations. 4.2 1 285 CE/A11; W/E08 RCS Overcooling - PTS / 4 Not applicable. 0 AK3.01 Knowledge of the reasons for the following 000051 Loss of Condenser Vacuum / 4 1 responses as they apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum. 2.8 1 229 EK2.07 Knowledge of the interrelations between the Station Blackout and the following: Breakers, relays, and 000055 Station Blackout / 6 1 disconnects.

  • Justification for K/A <2.5 Importance: Knowledge of the link between breakers and a Station Blackout is paramount to restoration of power to the unit. *2.2 1 174

PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID AK 3.01 Knowledge of the reasons for the following 000057 Loss of Vital AC Elec. Inst. Bus / 6 1 responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus. 4.1 1 414 000062 Loss of Nuclear Service Water / 4 1 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. 3.9 1 418 000067 Plant Fire On-site / 9 1 2.4.27 Knowledge of fire in the plant procedure. 3.0 1 14 B/W A06 AA1.1 Ability to operate and / or monitor the following as they apply to the (Shutdown Outside Control 000068 (BW/A06) Control Room Evac. / 8 1 Room ): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. 4.3 1 15 AA1.01 Ability to operate and / or monitor the following as they apply to the Loss of Containment Integrity:

000069 (W/E14) Loss of CTMT Integrity / 5 1 Isolation valves, dampers, and electropneumatic devices. 3.5 1 419 EK1.01 Knowledge of the operational implications of the 000074 (W/E06&E07) Inad. Core Cooling / 4 1 following concepts as they apply to the Inadequate Core Cooling: Methods of calculating subcooling margin. 4.3 1 420 B/W EA2.1 Ability to determine and interpret the BW/E03 Inadequate Subcooling Margin / 4 1 following as they apply to the Inadequate Subcooling Margin): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. 3.0 1 421 000076 High Reactor Coolant Activity / 9 0 B/W A02 AK1.3 Knowledge of the operational implications of the following concepts as they apply to BW/A02&A03 Loss of NNI-X/Y / 7 1 the (Loss of NNI-X): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of NNI-X). 3.8 1 20 K/A Category Totals: 2 2 4 3 2 3 Group Point Total = 16 16

PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID AA1.02 Ability to operate and/or monitor the following as 000001 Continuous Rod Withdrawal / 1 1 they apply to the Continuous Rod Withdrawal: Rod in-out-hold switch. 3.6 1 422 000003 Dropped Control Rod / 1 0 B/W E02 EK2.2 Knowledge of the interrelations between 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery the (Vital System Status Verification) and the following:

/1 1 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. 4.2 1 415 BW/A01 Plant Runback / 1 0 B/W AK2.1 Knowledge of the interrelations between the (Turbine Trip) and the following: Components, and BW/A04 Turbine Trip / 4 1 functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. 3.5 1 423 AK1.01 Knowledge of the operational implications of the 000008 Pressurizer Vapor Space Accident / 3 1 following concepts as they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves. 3.2 1 RO 27 EK3.21 Knowledge of the reasons for the following 000009 Small Break LOCA / 3 1 responses as they apply to the small break LOCA:

Actions contained in EOP for small break LOCA/leak. 4.2 1 372 2.4.6 Knowledge symptom based EOP mitigation 000011 Large Break LOCA / 3 1 strategies. 3.1 1 337 W/E04 LOCA Outside Containment / 3 Not applicable. 0 BW/E08; W/E03 LOCA Cooldown/Depress. / 4 0 W/E11 Loss of Emergency Coolant Recirc. / 4 Not applicable. 0 W/E01 & E02 Rediagnosis & SI Termination / 3 Not applicable. 0 000022 Loss of Reactor Coolant Makeup / 2 0 AK1.01 Knowledge of the operational implications of the following concepts as they apply to a Loss of Residual 000025 Loss of RHR System / 4 1 Heat Removal System: Loss of RHRS during all modes of operation. 3.9 1 164 EK3.12 Knowledge of the reasons for the following 000029 Anticipated Transient w/o Scram / 1 1 responses as they apply to the ATWS: Actions contained in EOP for ATWS. 4.4 1 35

PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID AK3.01 Knowledge of the reasons for the following 000032 Loss of Source Range NI / 7 1 responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss. 3.2 1 184 AK1.01 Knowledge of the operational implications of the 000033 Loss of Intermediate Range NI / 7 1 following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: Effects of voltage changes on performance. 2.7 1 RO 425 AA2.11 Ability to determine and interpret the following as 000037 Steam Generator Tube Leak / 3 1 they apply to the Steam Generator Tube Leak: When to isolate one or more S/Gs. 3.8 1 426 2.4.48 Ability to interpret control room indications to verify the status and operation of system, and 000038 Steam Generator Tube Rupture / 3 1 understand how operator actions and directives affect plant and system conditions. 3.5 1 364 AA1.04 Ability to operate and / or monitor the following 000054 (CE/E06) Loss of Main Feedwater / 4 1 as they apply to the Loss of Main Feedwater (MFW): HPI, under total feedwater loss conditions. 4.4 1 365 B/W EA2.1 Ability to determine and interpret the BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat following as they apply to the (Inadequate Heat Sink / 4 1

Transfer): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. 3.2 1 186 AK1.01 Knowledge of the operational implications of the 000058 Loss of DC Power / 6 1 following concepts as they apply to Loss of DC Power:

Battery charger equipment and instrumentation. 2.8 1 187 AA1.01 Ability to operate and / or monitor the following 000059 Accidental Liquid RadWaste Rel. / 9 1 as they apply to the Accidental Liquid Radwaste Release: Radioactive liquid monitor. 3.5 1 167 000060 Accidental Gaseous Radwaste Rel. / 9 1 2.3.11 Ability to control radiation releases.

(Replaced by Plant Specific Priority in T2G3) 2.7 1 424 000061 ARM System Alarms / 7 0 W/E16 High Containment Radiation / 9 Not applicable. 0 CE/E09 Functional Recovery Not applicable. 0 K/A Category Totals: 4 2 3 3 2 3 Group Point Total = 17 17

PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group3 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID 000028 Pressurizer Level Malfunction / 2 0 000036 (BW/A08) Fuel Handling Accident / 8 0 AA1.10 Ability to operate and/or monitor the following as 000056 Loss of Off-site Power / 6 1 they apply to the Loss of Offsite Power:

Auxiliary/emergency feedwater pump (motor driven). 4.3 1 427 AA2.05 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to 000065 Loss of Instrument Air / 8 1 commence plant shutdown if instrument air pressure is decreasing. 3.4 1 RO 428 BW/E13&E14 EOP Rules and Enclosures 0 BW/A05 Emergency Diesel Actuation / 6 0 BW/A07 Flooding / 8 1 2.4.11 Knowledge of abnormal condition procedures.

(Replaced by Plant Specific Priority in T2G3) 3.4 1 137 CE/A16 Excess RCS Leakage / 2 Not applicable. 0 W/E13 Steam Generator Over-pressure / 4 Not applicable. 0 W/E15 Containment Flooding / 5 Not applicable. 0 K/A Category Totals: 0 0 0 1 1 1 Group Point Total = 3 3

PWR RO Examination Outline Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 2.4 K2.06 Knowledge of bus power supplies to the following:

Circuit breakers.

  • Justification for <2.5 Importance: Knowledge of power supplies to the CRDMs is essential in understanding the 001 Control Rod Drive 1 1 implications of malfunctions of these components upon a system that directly affects core reactivity.

3.4 A2.06 Ability to (a) predict the impacts of the following malfunction or operations on the CRDS, and (b) based on those predictions, use procedures to correct, control, or 429 mitigate the consequences of those malfunctions or operations: Effects of transient xenon on reactivity. 2 52 3.1 K2.01 Knowledge of bus power supplies to the following:

RCPs. 2 003 Reactor Coolant Pump 1 1 3.4 A1.05 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including: RCS flow. 2 264 3.8 K3.05 Knowledge of the effect that a loss or malfunction of 189 the CVCS will have on the following: PZR LCS.

004 Chemical and Volume Control 1 1 A3.11 Ability to monitor automatic operation of the CVCS, 3.6 including: Charging/letdown. 2 RO 191 K4.10 Knowledge of ESFAS design feature(s) and/or 013 Engineered Safety Features Actuation 1 interlock(s) which provide for the following: Safeguards equipment control reset. 3.3 1 430 3.5 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on 015 Nuclear Instrumentation 1 1 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Power supply loss or erratic operation.

3.9 431 A3.03 Ability to monitor automatic operation of the NIS, including: Verification of proper functioning/operability. 2 58 K3.01 Knowledge of the effect that a loss or malfunction of 017 In-core Temperature Monitor 1 the ITM system will have on the following: Natural circulation indications. 3.5 1 RO 194

PWR RO Examination Outline Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 3.6 RO A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating 022 Containment Cooling 1 1 the CCS controls including: Containment pressure.

2.4.48 Ability to interpret control room indications to verify the 3.5 433 status and operation of system, and understand how operator actions and directives affect plant and system conditions. 2 416 025 Ice Condenser Not applicable. 0 2.6 K1.03 Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: MFW.

K6.10 Knowledge of the effect of a loss or malfunction of the 056 Condensate 1 1 following will have on the Condensate System components:

Pumps. 434

  • Justification for <2.5 Importance: Knowledge of the effect
  • 1.6 of malfunctions in secondary systems is important to plant safety since secondary transients may cause primary transients. 2 RO 261 3.4 A3.07 Ability to monitor automatic operation of the MFW, including: ICS. 63 059 Main Feedwater 1 1 K4.02 Knowledge of MFW design feature(s) and/or 3.3 interlock(s) which provide for the following: Automatic turbine trip/reactor trip runback. 2 RO 255 K5.01 Knowledge of the operational implications of the 061 Auxiliary/Emergency Feedwater 1 following concepts as they apply to the AFW: Relationship between AFW flow and RCS heat transfer. 3.6 1 435 A4.03 Ability to manually operate and/or monitor in the control 3.9 room: Stoppage of release if limits exceeded.

222 (Replaced by Plant Specific Priority in T2G3) 068 Liquid Radwaste 1 1 2.1.32 Ability to explain and apply all system limits and precautions. 3.4 2 RO 436

PWR RO Examination Outline Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 2.5 RO K5.04 Knowledge of the operational implications of the following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.

071 Waste Gas Disposal 1 1 *2.3 K6.10 Knowledge of the effect of a loss or malfunction of the following will have on the Waste Gas Disposal System 437 components: Surge and decay tanks.

  • Justification for <2.5 Importance: The surge and decay tanks are the primary storage components in the WGS and knowledge of their loss or malfunction is vital to the understanding of system operation. 2 439 3.3 RO K4.01 Knowledge of ARM design feature(s) and/or interlock(s) which provide for the following: Containment ventilation isolation.

072 Area Radiation Monitoring 1 1 299 (Replaced by Plant Specific Priority in T2G3) 3.0 A4.01 Ability to manually operate and/or monitor in the control room: Alarm and interlock setpoint checks and adjustments. 2 379 K/A Category Totals: 1 2 2 3 2 2 2 2 3 2 2 Group Point Total = 23 23 23

PWR RO Examination Outline Plant Systems - Tier2/Group2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 2.1.28 Knowledge of the purpose and function of major 002 Reactor Coolant 1 system components and controls. 3.2 1 440 K5.02 Knowledge of the operational implications of the 006 Emergency Core Cooling 1 following concepts as they apply to ECCS: Relationship between accumulator volume and pressure. 2.8 1 197 K5.01 Knowledge of the operational implications of the 010 Pressurizer Pressure Control 1 following concepts as they apply to the PZR PCS:

Determination of condition of fluid in PZR, using steam tables. 3.5 1 441 K4.01 Knowledge of PZR LCS design feature(s) and/or 011 Pressurizer Level Control 1 interlock(s) which provide for the following: Operation of the PZR heater cutout at low level. 3.3 1 RO 73 K1.01 Knowledge of the physical connections and/or cause-012 Reactor Protection effect relationships between the RPS and the following 1 systems: 120V vital/instrument power system. 3.4 1 85 A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating 014 Rod Position Indication 1 the RPIS controls including: Control rod position indication on control room panels. 3.2 1 442 A3.01 Ability to monitor automatic operation of the NNIS, 016 Non-nuclear Instrumentation 1 including: Automatic selection of NNIS inputs to control systems. 2.9 1 77 K4.06 Knowledge of CSS design feature(s) and/or 026 Containment Spray 1 interlock(s) which provide for the following: Iodine scavenging via the CSS. 2.8 1 RO 444 K1.04 Knowledge of the physical connections and/or cause-029 Containment Purge 1 effect relationships between the Containment Purge System and the following systems: Purge system. 3.0 1 RO 311 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling 033 Spent Fuel Pool Cooling 1 System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level. 3.1 1 200 A2.05 Ability to (a) predict the impacts of the following 035 Steam Generator 1 malfunctions or operations on the S/GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Unbalanced flows to the S/Gs. 3.2 1 443 2.2.2 Ability to manipulate the console controls as required to 039 Main and Reheat Steam 1 operate the facility between shutdown and designated power levels. 4.0 1 445

PWR RO Examination Outline Plant Systems - Tier2/Group2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID K6.02 Knowledge of the effect of a loss or malfunction of the following will have on the CARS components: Vacuum pumps.

055 Condenser Air Removal 1

  • Justification for <2.5 Importance: The knowledge of the operation of the CARS is important to the ability to maintain a secondary heat sink in the condenser. *1.6 1 RO 446 K2.01 Knowledge of bus power supplies to the following:

062 AC Electrical Distribution 1 Major system loads. 3.3 1 140 063 DC Electrical Distribution 1 K3.01 Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: ED/G. 3.7 1 224 A3.04 Ability to monitor automatic operation of the ED/G 064 Emergency Diesel Generator 1 system, including: Number of starts available with an air compressor. 3.1 1 447 K5.03 Knowledge of the operational implications of the 073 Process Radiation Monitoring 1 following concepts as they apply to the PRM system:

Relationship between radiation intensity and exposure limits. 2.9 1 448 K3.02 Knowledge of the effect that a loss or malfunction of the circulating water system will have on the following: Main condenser.

075 Circulating Water 1

  • Justification for <2.5 Importance: The knowledge of the effects of the CWS on the secondary heat sink is important to overal plant operation. *2.1 1 RO 205 A4.01 Ability to manually operate and/or monitor in the control 079 Station Air 1 room: Cross-tie valves with IAS. 2.7 1 102 K6.04 Knowledge of the effect of a loss or malfunction of the 086 Fire Protection 1 following will have on the Fire Protection System: Fire, smoke, and heat detectors. 2.6 1 151 K/A Category Totals: 2 1 2 2 3 2 1 2 2 1 2 Group Point Total = 20 20 20

PWR RO Examination Outline Plant Systems - Tier2/Group3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 005 Residual Heat Removal 1 2.4.10 Knowledge of annunciator response procedures. 3.0 1 449 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on 007 Pressurizer Relief/Quench Tank 1 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Stuck open PORV or code safety.

3.9 1 208 008 Component Cooling Water 0 027 Containment Iodine Removal Not applicable. 0 K3.01 Knowledge of the effect that a loss or malfunction of 028 Hydrogen Recombiner and Purge Control 1 the HRPS will have on the following: Hydrogen concentration in containment. 3.3 1 210 K1.04 Knowledge of the physical connections and/or cause-034 Fuel Handling Equipment 1 effect relationships between the Fuel Handling System and the following systems: NIS. 2.6 1 RO 450 K6.03 Knowledge of the effect of a loss or malfunction on the 041 Steam Dump/Turbine Bypass Control 1 following will have on the SDS: Controller and positioners, including ICS, S/G, CRDS. 2.7 1 108 045 Main Turbine Generator 0 A4.02 Ability to manually operate and/or monitor in the control 076 Service Water 1 room: SWS valves. 2.6 1 RO 46 K2.01 Knowledge of bus power supplies to the following:

078 Instrument Air 1 Instrument air compressor. 2.7 1 RO 170 A3.01 Ability to monitor automatic operation of the 103 Containment 1 containment system, including: Containment isolation. 3.9 1 104 0

K/A Category Totals: 1 1 1 0 0 1 1 1 0 1 1 Group Point Total = 8 8

PWR RO Examination Outline Plant Systems - Tier2/Group3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 005 Residual Heat Removal 1 2.4.10 Knowledge of annunciator response procedures. 3.0 1 449 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on 007 Pressurizer Relief/Quench Tank 1 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Stuck open PORV or code safety.

3.9 1 208 008 Component Cooling Water 0 027 Containment Iodine Removal Not applicable. 0 K3.01 Knowledge of the effect that a loss or malfunction of 028 Hydrogen Recombiner and Purge Control 1 the HRPS will have on the following: Hydrogen concentration in containment. 3.3 1 210 K1.04 Knowledge of the physical connections and/or cause-034 Fuel Handling Equipment 1 effect relationships between the Fuel Handling System and the following systems: NIS. 2.6 1 RO 450 K6.03 Knowledge of the effect of a loss or malfunction on the 041 Steam Dump/Turbine Bypass Control 1 following will have on the SDS: Controller and positioners, including ICS, S/G, CRDS. 2.7 1 108 045 Main Turbine Generator 0 A4.02 Ability to manually operate and/or monitor in the control 076 Service Water 1 room: SWS valves. 2.6 1 RO 46 K2.01 Knowledge of bus power supplies to the following:

078 Instrument Air 1 Instrument air compressor. 2.7 1 RO 170 A3.01 Ability to monitor automatic operation of the 103 Containment 1 containment system, including: Containment isolation. 3.9 1 104 0

K/A Category Totals: 1 1 1 0 0 1 1 1 0 1 1 Group Point Total = 8 8

PWR RO Examination Outline Plant Systems - Tier2/Group3 Plant-Specific Priorities System/Topic Recommended Replacement for Reason Points This item relates to ICS and has more importance to 045 K1.12 Knowledge of the physical connections and/or cause-overall plant operation at ANO than the Accidental effect relationships between the MT/G System and the following 060 2.3.11 Gaseous Radwaste Release topic.

systems: Load control system in "following mode."

(T1G2) *Justification for <2.5 KA: The knowledge of the effects of the ICS on the secondary heat sink is important to KA Importance Value = 2.1 overall plant operation. 1 059 K1.07 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems:

B/W A07 2.4.11 ICS. This item relates to ICS and has more importance to (T1G3) overall plant operation at ANO than the Flooding KA Importance Value = 3.2 procedure topic. 1 016 K4.03 Knowledge of NNIS design feature(s) and/or interlock(s)

This item relates to ICS and has more importance to which provide for the following: Input to control systems. 068 A4.03 overall plant operation at ANO than the Liquid (T2G1)

Radwaste topic it replaces, the Liquid Radwaste topic KA Importance Value = 2.8 is still tested with another KA. 1 015 K3.04 Knowledge of the effect that a loss or malfunction of the This item relates to ICS and has more importance to NIS will have on the following: ICS. 072 K4.01 overall plant operation at ANO than the Area Rad (T2G1) Monitor topic it replaces, the Area Rad Monitor topic is KA Importance Value = 3.4 still tested with another KA. 1 Plant-Specific Priority Total: (limit 10) 4

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: ANO Unit One Date of Exam: 2/11/01 Exam Level: RO QID Category K/A # Topic Imp. Points 2.1 .1 Knowledge of conduct of operations requirements. 3.7 1 244 Knowledge of less than one hour technical specification action 2.1 .11 statements for systems. 3.0 1 113 2.1.21 Ability to obtain and verify controlled procedure copy. 3.1 1 RO 389 Conduct of 2.1.29 Knowledge of how to conduct and verify valve lineups. 3.4 1 RO 245 Operations Ability to recognize indications for system operating parameters which 2.1.33 are entry-level conditions for technical specifications. 3.4 1 161 2.1.

Total 5 Ability to perform pre-startup procedures for the facility, including 2.2.1 operating those controls associated with plant equipment that could affect reactivity. 3.7 1 RO 232 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 247 Equipment 2.2.12 Knowledge of surveillance procedures. 3.0 1 RO 233 Control 2.2.

2.2.

2.2.

Total 3 Knowledge of 10 CFR: 20 and related facility radiation control 2.3.1 requirements. 2.6 1 121 Knowledge of radiation exposure limits and contamination control, 2.3.4 including permissible levels in excess of those authorized.

2.5 1 122 Radiation Ability to perform procedures to reduce excessive levels of radiation 2.3.10 Control and guard against personnel exposure. 2.9 1 234 2.3.

2.3.

2.3.

Total 3 2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.3 1 RO 126 Knowledge of local auxiliary operator tasks during emergency 2.4.35 Emergency operations including system geography and system implications. 3.3 1 RO 451 Procedures 2.4.

/ 2.4.

Plan 2.4.

2.4.

Total 2 Tier 3 Point Total (RO) 13 13 NUREG 1021, Revision 8, Supplement 1 40 of 46

ES-401 Record of Rejected K/As - RO Exam Form ES-401-10 (R8, S1)

Tier / Group Randomly Selected K/A Reason for Rejection 1/1 015/017 AK2.05 Changed to AK2.08 due to low importance of initial choice, AK2.05.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO Unit 1 Date of Examination: 08/19/02 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions Conduct of Knowledge of shift staffing requirements.

A.1 Operations 2.1.4 NEW ADMIN JPM (A1JPM-SRO-QUAL1)

Ability to perform specific system and integrated plant Conduct of procedures during all modes of plant operation.

Operations 2.1.23 ADMIN JPM (A1JPM-SRO-PROC1)

A.2 Knowledge of the process for managing maintenance activities Equipment during power operations.

Control 2.2.17 NEW ADMIN JPM (A1JPM-SRO-MNTC1)

A.3 2.3.1 Knowledge of 10CFR 20 and related facility radiation Radiation control requirements.

Control OPEN REFERENCE QUESTION 2.3.2 Knowledge of facility ALARA program.

OPEN REFERENCE QUESTION A.4 Ability to take actions called for in the emergency plan, including Emergency (if required) supporting or acting as emergency coordinator.

Procedures/Plan 2.4.38 NEW ADMIN JPM (A1JPM-SRO-EAL7) 21 of 26 NUREG-1021, Revision 8

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: _ANO UNIT 1__________________ Date of Examination: __08/19/02____

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: 1 B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. ANO-1-JPM-R0-CRD03 D/S/A 1 Transfer Group 4 to Aux Power Supply
b. AN0-1-JPM-RO-AOP29 N/S/L 4 Perform actions for a loss of DHR (Primary)
c. ANO-1-JPM-R0-MFW04 N/S/A 4 Place second MFP in service (Secondary)

B.2 Facility Walk-Through

a. ANO-1-JPM-R0-AOP07 D/R 2 Remote Shutdown WCO Duties, 1203.009 Section 1D
b. ANO-1-JPM-R0-ED019 D/A/L 6 Synchronize and power Y02 from Y01
  • 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 NUREG-1021, Revision 8 22 of 26

ANO Unit One PWR SRO Examination Outline Facility: ANO, Unit One Date of Exam: Aug. 16, 2002 Exam Level: SRO K/A Category Points Point Tier Group Total K K K K K K A A A A G SRO 1 2 3 4 5 6 1 2 3 4

  • Only
1. 1 3 3 6 4 3 5 24 5 24 Emergency & 2 3 2 3 3 3 2 16 4 16 Abnormal 3 0 1 0 1 0 1 3 1 3 Plant Tier Evolutions Totals 6 6 9 8 6 8 43
2. 1 1 2 2 1 1 1 2 3 3 2 1 19 2 19 Plant 2 1 1 2 1 3 1 0 2 3 1 2 17 2 17 Systems 3 0 0 0 0 0 1 0 2 0 0 1 4 1 4 Tier Totals 2 3 4 2 4 3 2 7 6 3 4 40
3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 6 4 3 4 17 10 17 NUREG-1021, Revision 8, Supplement 1 26 of 46 K/A/G/ Totals 8 9 13 2 4 3 10 13 6 3 29 100 25 SRO Only Total

PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID AA1.02 Ability to operate and/or monitor the following as 000001 Continuous Rod Withdrawal / 1 1 they apply to the Continuous Rod Withdrawal: Rod in-out-hold switch. 3.4 1 2.1.12 Ability to apply Technical Specifications for a 000003 Dropped Control Rod / 1 1 system. 3.6 1 SRO 467 000005 Inoperable/Stuck Control Rod / 1 1 2.4.11 Knowledge of abnormal condition procedures. 3.6 1 2.4.6 Knowledge symptom based EOP mitigation 000011 Large Break LOCA / 3 1 strategies. 4.0 1 W/E04 LOCA Outside Containment / 3 Not applicable. 0 W/E02 & E02 Rediagnosis & SI Termination / 3 Not applicable. 0 AK2.08 Knowledge of the interrelations between the 000015/17 RCP Malfunctions / 4 1 Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: CCWS. 2.6 1 SRO 452 B/W EK1.2 Knowledge of the operational implications of 4.0 SRO the following concepts as they apply to the (Natural Circulation Cooldown): Normal, abnormal and emergency operating procedures associated with (Natural Circulation Cooldown).

B/W EK2.2 Knowledge of the interrelations between the BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 1 1 (Natural Circulation Cooldown) and the following:

4.0 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.

2 278 AA2.01 Ability to determine and interpret the following as they apply to the Emergency Boration: Whether boron 000024 Emergency Boration / 1 1 flow and/or MOVs are malfunctioning, from plant conditions. 4.1 1 AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Component 000026 Loss of Component Cooling Water / 8 1 Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS. 3.9 1 EK3.12 Knowledge of the reasons for the following 000029 Anticipated Transient w/o Scram / 1 1 responses as they apply to the ATWS: Actions contained in EOP for ATWS. 4.7 1

PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID B/W EK3.3 Knowledge of the reasons for the following 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive responses as they apply to the (Excessive Heat Heat Transfer / 4 1

Transfer): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations. 3.8 1 CE/A11; W/E08 RCS Overcooling - PTS / 4 Not applicable. 0 AK3.01 Knowledge of the reasons for the following 000051 Loss of Condenser Vacuum / 4 1 responses as they apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum. 3.1 1 EK2.07 Knowledge of the interrelations between the Station Blackout and the following: Breakers, relays, and 000055 Station Blackout / 6 1 disconnects.

  • Justification for K/A <2.5 Importance: Knowledge of the link between breakers and a Station Blackout is paramount to restoration of power to the unit. *2.4 1 AK 3.01 Knowledge of the reasons for the following 000057 Loss of Vital AC Elec. Inst. Bus / 6 1 responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus. 4.4 1 AA1.01 Ability to operate and / or monitor the following 000059 Accidental Liquid RadWaste Rel. / 9 1 as they apply to the Accidental Liquid Radwaste Release: Radioactive-liquid monitor. 3.5 1 000062 Loss of Nuclear Service Water / 4 1 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.0 1 000067 Plant Fire On-site / 9 1 2.4.27 Knowledge of fire in the plant procedure. 3.5 1 B/W A06 AA1.1 Ability to operate and / or monitor the following as they apply to the (Shutdown Outside Control Room ): Components, and functions of control and 000068 (BW/A06) Control Room Evac. / 8 1 safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. 4.2 1

PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID AA1.01 Ability to operate and / or monitor the following as they apply to the Loss of Containment Integrity:

000069 (W/E14) Loss of CTMT Integrity / 5 1 Isolation valves, dampers, and electropneumatic devices. 3.7 1 EK1.01 Knowledge of the operational implications of the 000074 (W/E06&E07) Inad. Core Cooling / 4 1 following concepts as they apply to the Inadequate Core Cooling: Methods of calculating subcooling margin. 4.7 1 B/W EK3.1 Knowledge of the reasons for the following 3.8 SRO responses as they apply to the (Inadequate Subcooling Margin): 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.

BW/E03 Inadequate Subcooling Margin / 4 1 1 B/W EA2.1 Ability to determine and interpret the following as they apply to the Inadequate Subcooling Margin): Facility conditions and selection of appropriate 4.0 procedures during abnormal and emergency operations.

2 368 AA2.02 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:

000076 High Reactor Coolant Activity / 9 1 Corrective actions required for high fission product activity in RCS. 3.4 1 SRO 342 B/W A02 AK1.3 Knowledge of the operational implications of the following concepts as they apply to BW/A02&A03 Loss of NNI-X/Y / 7 1 the (Loss of NNI-X): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of NNI-X). 3.8 1 K/A Category Totals: 3 3 6 4 3 5 Group Point Total = 24 24 24

PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID B/W E02 EK2.2 Knowledge of the interrelations between 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery the (Vital System Status Verification) and the following:

/1 1 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. 4.2 1 AK3.2 Knowledge of the reasons for the following BW/A01 Plant Runback / 1 1 responses as they apply to the (Plant Runback): Normal, abnormal and emergency operating procedures associated with (Plant Runback). 3.6 1 SRO 62 B/W AK2.1 Knowledge of the interrelations between the (Turbine Trip) and the following: Components, and BW/A04 Turbine Trip / 4 1 functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. 3.3 1 000008 Pressurizer Vapor Space Accident / 3 0 EK3.21 Knowledge of the reasons for the following 000009 Small Break LOCA / 3 1 responses as they apply to the small break LOCA:

Actions contained in EOP for small break LOCA/leak. 4.5 1 EK1.2 Knowledge of the operational implications of the BW/E08; W/E03 LOCA Cooldown - Depress. / 4 1 following concepts as they apply to the (LOCA Cooldown): Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown). 3.8 1 SRO 182 W/E11 Loss of Emergency Coolant Recirc. / 4 Not applicable. 0 AA1.01 Ability to operate and / or monitor the following 000022 Loss of Reactor Coolant Makeup / 2 1 as they apply to the Loss of Reactor Coolant Pump Makeup: CVCS letdown and charging. 3.3 1 SRO 32 AK1.01 Knowledge of the operational implications of the following concepts as they apply to a Loss of Residual 000025 Loss of RHR System / 4 1 Heat Removal System: Loss of RHRS during all modes of operation. 4.3 1 AA1.01 Ability to operate and/or monitor the following as 000027 Pressurizer Pressure Control System Malfunction / 3 1 they apply to the Pressurizer Pressure Control Malfunctions: PZR heaters, sprays, and PORV's. 3.9 1

PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID AK3.01 Knowledge of the reasons for the following 000032 Loss of Source Range NI / 7 1 responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss. 3.6 1 000033 Loss of Intermediate Range NI / 7 0

AA2.11 Ability to determine and interpret the following as 000037 Steam Generator Tube Leak / 3 1 they apply to the Steam Generator Tube Leak: When to isolate one or more S/Gs. 3.8 1 2.4.48 Ability to interpret control room indications to verify the status and operation of system, and 000038 Steam Generator Tube Rupture / 3 1 understand how operator actions and directives affect plant and system conditions. 3.8 1 AA1.04 Ability to operate and / or monitor the following 000054 (CE/E06) Loss of Main Feedwater / 4 1 as they apply to the Loss of Main Feedwater (MFW): HPI, under total feedwater loss conditions. 4.5 1 B/W EA2.1 Ability to determine and interpret the following as they apply to the (Inadequate Heat BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 1 Transfer): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. 4.4 1 AK1.01 Knowledge of the operational implications of the 000058 Loss of DC Power / 6 1 following concepts as they apply to Loss of DC Power:

Battery charger equipment and instrumentation. 3.1 1 000060 Accidental Gaseous Radwaste Rel. / 9 1 2.3.11 Ability to control radiation releases.

(Replaced by Plant Specific Priority in T2G3) 3.2 1 AA2.05 Ability to determine and interpret the following as 000061 ARM System Alarms / 7 1 they apply to the Area Radiation Monitoring (ARM) System Alarms: Need for area evacuation; check against existing limits. 4.2 1 SRO 367 W/E16 High Containment Radiation / 9 Not applicable. 0 000065 Loss of Instrument Air / 8 0 CE/E09 Functional Recovery Not applicable. 0 K/A Category Totals: 3 2 3 3 3 2 Group Point Total = 16 16 16

PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier1/Group3 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points QID 000028 Pressurizer Level Malfunction / 2 0 B/W AK2.1 Knowledge of the interrelations between the (Refueling Canal Level Decrease) and the following:

000036 (BW/A08) Fuel Handling Accident / 8 1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. 3.8 1 SRO 347 AA1.10 Ability to operate and/or monitor the following as 000056 Loss of Off-site Power / 6 1 they apply to the Loss of Offsite Power:

Auxiliary/emergency feedwater pump (motor driven). 4.3 1 BW/E13&E14 EOP Rules and Enclosures 0 BW/A05 Emergency Diesel Actuation / 6 0 BW/A07 Flooding / 8 1 2.4.11 Knowledge of abnormal condition procedures.

(Replaced by Plant Specific Priority in T2G3) 3.6 1 CE/A16 Excess RCS Leakage / 2 Not applicable. 0 W/E13 Steam Generator Over-pressure / 4 Not applicable. 0 W/E15 Containment Flooding / 5 Not applicable. 0 K/A Category Totals: 0 1 0 1 0 1 Group Point Total = 3 3 SRO 3 Only

PWR SRO Examination Outline Plant Systems - Tier2/Group1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 2.8 K2.06 Knowledge of bus power supplies to the following:

Circuit breakers.

A2.06 Ability to (a) predict the impacts of the following 3.7 001 Control Rod Drive 1 1 malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effects of transient xenon on reactivity.

2 3.1 K2.01 Knowledge of bus power supplies to the following:

RCPs.

003 Reactor Coolant Pump 1 1 A1.05 Ability to predict and/or monitor changes in parameters 3.5 (to prevent exceeding design limits) associated with operating the RCPS controls including: RCS flow.

2 4.2 K3.05 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: PZR LCS.

004 Chemical and Volume Control 1 1 A3.02 Ability to monitor automatic operation of the CVCS, 3.6 including: Letdown isolation.

2 SRO 432 K4.10 Knowledge of ESFAS design feature(s) and/or 013 Engineered Safety Features Actuation 1 interlock(s) which provide for the following:Safeguards equipment control reset. 3.7 1 A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating 014 Rod Position Indication 1 the RPIS controls including: Control rod position indication on control room panels. 3.6 1 3.9 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or 015 Nuclear Instrumentation 1 1 operations: Power supply loss or erratic operation.

3.9 A3.03 Ability to monitor automatic operation of the NIS, including: Verification of proper functioning/operability.

2 017 In-core Temperature Monitor 0

PWR SRO Examination Outline Plant Systems - Tier2/Group1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 2.4.48 Ability to interpret control room indications to verify the status and operation of system, and 022 Containment Cooling 1 understand how operator actions and directives affect plant and system conditions. 3.8 1 025 Ice Condenser Not applicable. 0 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on 026 Containment Spray 1 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of spray pump.

4.2 1 SRO 454 K1.03 Knowledge of the physical connections and/or cause-056 Condensate 1 effect relationships between the Condensate System and the following systems: MFW. 2.6 1 A3.07 Ability to monitor automatic operation of the MFW, 059 Main Feedwater 1 including: ICS. 3.5 1 K5.01 Knowledge of the operational implications of the 061 Auxiliary/Emergency Feedwater 1 following concepts as they apply to the AFW: Relationship between AFW flow and RCS heat transfer.

3.9 1 K3.01 Knowledge of the effect that a loss or malfunction of 063 DC Electrical Distribution 1 the DC electrical system will have on the following: ED/G.

4.1 1 A4.03 Ability to manually operate and/or monitor in the control 068 Liquid Radwaste 1 room: Stoppage of release if limits exceeded.

(Replaced by Plant Specific Priority in T2G3) 3.8 1 K6.10 Knowledge of the effect of a loss or malfunction of the 071 Waste Gas Disposal 1 following will have on the Waste Gas Disposal System components: Surge and decay tanks. 2.5 1 072 Area Radiation Monitoring 1 A4.01 Ability to manually operate and/or monitor in the control room: Alarm and interlock setpoint checks and adjustments. 3.3 1 K/A Category Totals: 1 2 2 1 1 1 2 3 3 2 1 Group Point Total = 19 19 19

PWR SRO Examination Outline Plant Systems - Tier2/Group2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 002 Reactor Coolant 1 2.1.28 Knowledge of the purpose and function of major system components and controls. 3.3 1 K5.02 Knowledge of the operational implications of the 006 Emergency Core Cooling 1 following concepts as they apply to ECCS: Relationship between accumulator volume and pressure.

2.9 1 K5.01 Knowledge of the operational implications of the following concepts as they apply to the PZR PCS:

010 Pressurizer Pressure Control 1 Determination of condition of fluid in PZR, using steam tables. 4.0 1 K4.03 Knowledge of PZR LCS design feature(s) and/or 011 Pressurizer Level Control 1 interlock(s) which provide for the following: Density compensation of PZR level. 2.9 1 SRO 169 K1.01 Knowledge of the physical connections and/or cause-012 Reactor Protection 1 effect relationships between the RPS and the following systems: 120V vital/instrument power system. 3.1 1 A3.01 Ability to monitor automatic operation of the NNIS, 016 Non-nuclear Instrumentation 1 including: Automatic selection of NNIS inputs to control systems. 2.9 1 027 Containment Iodine Removal Not applicable. 0 K3.01 Knowledge of the effect that a loss or malfunction of 028 Hydrogen Recombiner and Purge Control 1 the HRPS will have on the following: Hydrogen concentration in containment. 4.0 1 029 Containment Purge 0 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures 033 Spent Fuel Pool Cooling 1 to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level.

3.5 1 K4.03 Knowledge of design feature(s) and/or interlock(s) 034 Fuel Handling Equipment 1 which provide for the following: Overload protection.

3.3 1 SRO 455

PWR SRO Examination Outline Plant Systems - Tier2/Group2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the S/GS; and (b) based on 035 Steam Generator 1 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Unbalanced flows to the S/Gs.

3.4 1 2.2.2 Ability to manipulate the console controls as required to 039 Main and Reheat Steam 1 operate the facility between shutdown and designated power levels. 3.5 1 055 Condenser Air Removal 0 K2.01 Knowledge of bus power supplies to the following:

062 AC Electrical Distribution 1 Major system loads. 3.4 1 A3.04 Ability to monitor automatic operation of the ED/G 064 Emergency Diesel Generator 1 system, including: Number of starts available with an air compressor. 3.5 1 K5.03 Knowledge of the operational implications of the 073 Process Radiation Monitoring 1 following concepts as they apply to the PRM system:

Relationship between radiation intensity and exposure limits. 3.1 1 075 Circulating Water 0 A4.01 Ability to manually operate and/or monitor in the control 079 Station Air 1 room: Cross-tie valves with IAS. 2.7 1 K6.04 Knowledge of the effect of a loss or malfunction of the 086 Fire Protection 1 following will have on the Fire Protection System: Fire, smoke, and heat detectors. 2.9 1 A3.01 Ability to monitor automatic operation of the 103 Containment 1 containment system, including: Containment isolation. 4.2 1 K/A Category Totals: 1 1 2 1 3 1 0 2 3 1 2 Group Point Total = 17 17 17

PWR SRO Examination Outline Plant Systems - Tier2/Group3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic Imp. Points QID 005 Residual Heat Removal 1 2.4.10 Knowledge of annunciator response procedures. 3.1 1 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on 007 Pressurizer Relief/Quench Tank 1 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Stuck open PORV or code safety.

4.2 1 A2.04 Ability to (a) predict the impacts of the following malfunction or operations on the CCWS, and (b) based on 008 Component Cooling Water 1 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PRMS alarm. 3.2 1 SRO 466 K6.03 Knowledge of the effect of a loss or malfunction on the 041 Steam Dump/Turbine Bypass Control 1 following will have on the SDS: Controller and positioners, including ICS, S/G, CRDS. 2.9 1 045 Main Turbine Generator 0 076 Service Water 0 078 Instrument Air 0 K/A Category Totals: 0 0 0 0 0 1 0 2 0 0 1 Group Point Total = 4 4 SRO only Plant-Specific Priorities 4 System/Topic Recommended Replacement for Reason Points This item relates to ICS and has more importance to 045 K1.12 Knowledge of the physical connections and/or cause-overall plant operation at ANO than the Accidental effect relationships between the MT/G System and the following 060 2.3.11 Gaseous Radwaste Release topic.

systems: Load control system in "following mode."

(T1G2) *Justification for <2.5 KA: The knowledge of the effects of the ICS on the secondary heat sink is important to KA Importance Value = 2.1 overall plant operation. 1 059 K1.07 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems:

B/W A07 2.4.11 ICS. This item relates to ICS and has more importance to (T1G3) overall plant operation at ANO than the Flooding KA Importance Value = 3.2 procedure topic. 1

PWR SRO Examination Outline Plant Systems - Tier2/Group3 016 K4.03 Knowledge of NNIS design feature(s) and/or interlock(s) which provide for the following: Input to control systems. 068 A4.03 This item relates to ICS and has more importance to (T2G1) overall plant operation at ANO than the Liquid KA Importance Value = 2.9 Radwaste topic it replaces, the Liquid Radwaste topic is still tested with another KA. 1 Plant-Specific Priority Total: (limit 10) 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Based on NUREG 1021 Rev. 8 Form ES-401-5 QID Facility: ANO, Unit One Date of Exam: 8/16/02 Exam Level: SRO Category K/A # Topic Imp. Points 2.1.1 Knowledge of conduct of operations requirements. 3.8 1 2.1.4 Knowledge of shift staffing requirements. 3.4 1 SRO 407 2.1.11 Knowledge of less than one hour technical specification action statements for systems.

3.8 1 Conduct of Operations 2.1.12 Ability to apply technical specifications for a system. 4.0 1 SRO 457 2.1.22 Ability to determine Mode of Operation. 3.3 1 SRO 458 Ability to recognize indications for system operating parameters which are entry-level conditions for 2.1.33 technical specifications. 4.0 1 Total 6 Knowledge of the process for making changes in procedures as described in the safety analysis 2.2.6 report. 3.3 1 SRO 459 2.2.11 Knowledge of the process for controlling temporary changes. 3.4 1 SRO 117 2.2.13 Knowledge of tagging and clearance procedures. 3.8 1 Equipment Knowledge of SRO fuel handling responsibilities. 3.8 Control 2.2.29 1 SRO 354 2.2.

2.2.

Total 4 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. 3.0 1 Knowledge of radiation exposure limits and contamination control, including permissible levels in 2.3.4 excess of those authorized. 3.1 1 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel Radiation 2.3.10 exposure. 3.3 1 Control 2.3.

2.3.

2.3.

Total 3 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures.

4.0 1 SRO 331 Knowledge of which events related to system operations/status should be reported to outside 2.4.30 agencies. 3.6 1 SRO 411 Emergency Procedures/ 2.4.33 Knowledge of the process used to track inoperable alarms. 2.8 1 SRO 460 Plan 2.4.41 Knowledge of the emergency action level thresholds and classifications.

4.1 1 SRO 129 2.4.

2.4.

Total 4 Tier 3 Point Total (SRO) 17 17 SRO Only topics

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 1 Op-Test No.: 2002-1 Page of Examiners: Operators:

Initial Conditions:

  • ~70% Power from 40% power after repair to A Main Feedwater Pump
  • # 1 EDG is out of service for online maintenance. Day 1 of an expected 2 day outage.
  • ICS runbacks are disabled due to a design discrepancy in the STAR module.

Turnover:

  • Power escalation to 100%. ~70% Power from 40% power after repair to A Main Feedwater Pump.
  • # 1 EDG is out of service for online maintenance. Day 1 of an expected 2 day outage.
  • Severe thunderstorm warnings for Pope, Johnson, and Yell counties for next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Event Malf. No. Event Event No. Type* Description 1 N/A N Place the Heater Drain Pumps (P8A & P8B) in service 2 IMF MS131 .06 R1:00 C Main Steam leak inside the containment building. (OTSG Operating Range Level tap) 3 N/A R Power escalation to 100% at ~30%/Hr.

4 IMF TR568 100 R3:00 I A OTSG Operating Range Level Transmitter fails High.

5 IMF FW074 C A Main Feedwater Pump trips (R) 6 ICM CV1008_a .10 C Pressurizer Spray valve fails to seat and leaks by.

IOR -DO HS1008_R FALSE 7 MMF MS131 .2 M Main Steam Line rupture inside containment.

8 IMF RD369 C 2 control rods stick in the fully withdrawn position and will not drop into the core.

IMF RD377

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

Appendix D Scenario Outline Form ES D1 Facility: ANO-1 Scenario No.: 2 Op-Test No.: 2002-1 Page of Examiners: Operators:

Initial Conditions:

  • 100% power, equilibrium xenon.
  • #1 EDG is out of service for online maintenance. Day 1 of an expected 2 day outage.

Turnover:

  • 100% power, equilibrium xenon.
  • #1 EDG is out of service for online maintenance. Day 1 of an expected 2 day outage.
  • Severe thunderstorm warnings for Pope, Johnson, and Yell counties for next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Event Malf. No. Event Event No. Type* Description 1 IMF NI240 I Nuclear Instrumentation (NI5) drifts high 2 N/A N Chemistry reports that routine RCS sampling backup sample reveals 55 ppmb difference between RCS and pressurizer boron concentrations. Equalize boron.

3 IOR -AI TIC4026_S 1 C ACW control valve for turbine lube oil coolers fails closed due to input failure 4 CAE file R The Mablevale substation experiences storm damage causing the breakers in the switchyard supplying that line to open. The caemable dispatcher requests an emergency power reduction to ~600 MWe to maintain system integrity.

5 IOR -DI ICC0009_L C The ULD toggle switch will not lower demand.

FALSE 6 IMF ED183 M Loss of offsite power occurs. Reactor trip.

IMF DG176 C #2 EDG fails to autostart and the pushbutton on C10 fails to start the EDG.

IOR -DI CSI-DG2_S STATION BLACKOUT 7 IMF FW611 C EFIC/EFW fill rate control failure.

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

Appendix D Scenario Outline Form ES D1 Facility: ANO-1 Scenario No.: 3 Op-Test No.: 2002-1 Page of Examiners: Operators:

Initial Conditions:

  • 100% power, equilibrium xenon.
  • #1 EDG is out of service for online maintenance. Day 1 of an expected 2 day outage.
  • RPS is failed and will not automatically actuate when setpoint is reached.
  • The Reactor Trip pushbutton on C03 will not work when depressed Turnover:
  • ~97% power from power escalation. Holding for performance of NI calibration adjustment to align NIs with Heat Balance power. Then continue to ~100% power operations.
  • #1 EDG is out of service for online maintenance. Day 1 of an expected 2 day outage.

Event Malf. No. Event Event No. Type* Description 1 N/A N Place ICS in MANUAL for performance of NI calibration.

Then return ICS to AUTO when calibration completed.

2 IMF TR051 0 R3:00 I Selected Pressurizer Level transmitter fails low.

D0 3 IMF CV018 C D RCP first stage seal failure 4 N/A R Power reduction to secure D RCP 5 IMF RX599 C B main feed pump fails to respond to ICS demand signal 6 IMF CV022 D RCP 2 nd stage seal failure IMF CV026 D RCP 3 rd stage seal failure IMF RC005 . M LOCA into the Containment Building 7 IMF CV095 C ES HPI pump trips on high bearing temperature requiring HPI to be supplied from the operating Makeup Pump. (P36B or C)

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

Appendix D Scenario Outline Form ES D1 Facility: ANO-1 Scenario No.: 4 Op-Test No.: 2002-1 Page of Examiners: Operators:

Initial Conditions:

  • 100% power, equilibrium xenon.
  • #1 EDG is out of service for online maintenance. Day 2 of an expected 2 day outage.
  • RPS is failed and will not actuate automatically when setpoint is reached.

Turnover:

  • 100% power, equilibrium xenon.
  • #1 EDG is out of service for online maintenance. Day 2 of an expected 2 day outage.
  • #1 EDG is running at ~2750 Kw for operability test following maintenance on the governor.

Event Malf. No. Event Event No. Type* Description 1 IMF TR556 I B main feed flow transmitter drifts low slowly 2 IOR -DI CS3- N Secure the #1 EDG as per the surveillance test for completion DG1_W02 TRUE of the operability test. As load is reduced by the operator, the C governor fails and continues to reduce load without a command.

3 IMF MC088 3000 C Main Condenser vacuum leak R4:00 R

4 IMF RC002 .5 R20:00 M Tube rupture in the B OTSG R

5 RMF EDB0125 FALSE C Switchyard breaker B0125 (feed for SU #1 transformer) opens rendering SU#1 transformer unavailable.

6 IMF TC245 C Main Turbine trips >43% power. Requires manual Reactor trip.

7 IOR -DI 152-111/CS_T C SU#2 feeder breaker to A1 bus trips on Rx. Trip. Loss of A1 TRUE and A3 buses

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