ML070530105

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Wat - Init Exam - 11/2006 - Final Outline
ML070530105
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/23/2006
From:
Operations Branch IV
To:
Entergy Operations
References
Download: ML070530105 (24)
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ES-301, Rev. 9Administrative Topics Outline Form ES-301-1Facility: Waterford 3Date of Examination: 11/13/2006Examination Level: RO SRO Operating Test Number: 1Administrative Topic(see Note)TypeCode*Describe activity to be performedConduct of OperationsR, NPerform OP-004-015 Attachment 11.1 Manual CEA SubgroupSelection.Conduct of OperationsR, MPerform OP-903-015 Attachment 10.1 Shutdown Margin CalculationEquipment ControlR, NPerform OP-903-001 Attachment 11.15 Containment Pressurecalculation.Radiation ControlR,NReview RWP.Emergency PlanNot selectedNOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (£ 3 for ROs;£ 4 for SROs & RO retakes) (N)ew or (M)odified from bank (³ 1) (P)revious 2 exams (£ 1; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility:

Waterford 3 Date of Examination: 11/13/2006 Examination Level: RO SRO Operating Test Number:

1 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R, N Review OP-004-015 Attachment 11.1, Manual CEA Subgroup Selection. Conduct of Operations R,N Determine if hours worked exceed guidelines Requirements. Equipment Control R, N Perform an SRO review of OP-903-001 Attachment 11.15, Containment Pressure calculation. Radiation Control R, N Review OP-901-131 Attachment 1, Containment Closure checklist. Emergency Plan S,M Determine E-Plan classification and notification requirements based on current simulator scenario. NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (N)ew or (M)odified from bank ( 1) (P)revious 2 exams ( 1; randomly selected)

ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford 3 Date of Examination: 11/13/2006 Exam Level: RO SRO-I SRO-U Operating Test No.: 1 Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function a. Recovery Dropped CEA (Continuous CEA Motion) A, D, P, S 1 b. Perform Actions on a Recirculation Actuation (Leak on Suction Line)

A, D, L, P, S 2 c. Perform ATC immediate Operator Actions on CR evacuation (Fire in Control Room)

D, P, S 3 d. Start Reactor Coolant Pump A, L, M, S 4 e. Place Hydrogen Recombiner in service D, C 5 f. Restore Normal Power to a 4.16KV Safety Bus and secure Emergency Diesel Generator A, D, S 6 g. Realign Containment Spray for Automatic initiation following CSAS D, S 7 h. Perform actions in response to CCW system leakage N, S 8 In-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Operate the Atmospheric Dump Valves Locally A, D, E, L 4 j. Perform a SUPS A Startup D 6 k. Place Gas Decay Tank on Decay M, R 9 @ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford 3 Date of Examination: 11/13/2006 Exam Level: RO SRO-I SRO-U Operating Test No.: 1 Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function a. b. Perform Actions on a Recirculation Actuation A, D, L, P, S 2 c. d. e. f. Restore Normal Power to a 4.16KV Safety Bus A, D, S 6 g. h. Perform actions in response to CCW system leakage N, S 8 In-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Operate the Atmospheric Dump Valves Locally A, D, E, L 4 j. k. Place GDT on Decay M, R 9 @ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power

/ Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 A ppendix D Scenario Outline Form ES-D-1 Facility: Waterford III Scenario No.: 1 Op-Test No.: 1 Examiners:

Operators:

Initial Conditions: IC-151 74%, MOC Turnover: EFW Pump A tagged out and is expected to be returned to service by the end of shift. HPSI Pump A is tagged out and is expected to be returned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. MFW Pump B has recently been returned to service following emergent maintenance. Plant is ready to restore power to 100%. Event No. Malf. No. Event Type*

Event Description 1 N/A R(RO) N(BOP/SRO) Crew performs a brief and commences power escalation toward 100% power.

2 SG07D2 I(BOP/SRO) SG 2 Channel D low pressure trip setpoint fails high. The crew should enter TS 3.3.1 and 3.3.2 and take required actions to bypass SG Pressure Low and SG P 1 and 2 (EFAS) in PPS Channel D.

3 CV12A2 I(RO/SRO) After the crew satisfies the reactivity manipulation, the VCT level transmitter fails low causing Charging Pump suction to swap from the VCT to the RWSP. The crew should implement OP-901-113 and secure Charging and Letdown to secure from inadvertent boration. The crew should enter TS 3.1.2.4 due to placing Charging Pump C/S to OFF (may enter 3.0.3 if they take all Pumps to OFF).

4 FW32B C(SRO) MFW Pump B lube oil pipe leak, which causes the crew to commence power reduction. During the power reduction brief the oil leak worsens and trips MFW Pump B.

5 PW02 I(RO/SRO) An automatic reactor power cutback fails to occur, and the crew trips

the reactor.

6 RD11A03 RD11A82 C(RO) CEAs 3 and 82 stick out on the trip, which causes the RO to emergency borate due to two stuck CEAs.

7 ED01A ED01B ED01C ED01D EG09B FW05 FW07B C(BOP) M(ALL) C(BOP/SRO)

A LOOP occurs 1 minute after the trip, and EDG B Output breaker fails to close and cannot be closed. The crew will implement SPTAs and will be directed to OP-902-003.

After the crew performs Step 7 to Protect Main Condenser, the AB EFW Pump trips on overspeed and cannot be restored. The crew will transition to OP-902-008 due to a loss of all feedwater. Once safety function priorities are evaluated, EDG B Output breaker is restored and can be closed. Once closed, the B EFW Pump must be manually started.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor A ppendix D Scenario Outline Form ES-D-1 Facility: Waterford III Scenario No.: 2 Op-Test No.: 1 Examiners:

Operators:

Initial Conditions

IC-30 100%, EOC Turnover: RCP 1A Middle Seal failed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago (RC09A). EFW Pump A is tagged out and is expected to be returned to service by the end of shi ft. HPSI Pump A is tagged out and is expected to be returned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Event No. Malf. No. Event Type*

Event Description 1 RD02A82 R(RO) C(BOP/SRO) CEA 82 drops into the core. The crew should implement OP-901-102. To comply with TS 3.1.3.1 the crew implements OP-901-212 for a rapid power reduction within 15 minutes.

2 RC23B (0.01%) C(SRO) After the crew satisfies the reactivity manipulation, an RCS leak develops inside Containment. The crew should enter TS 3.4.5.2.

3 CV02A CV02C I(RO) Charging Pumps AB and A fail to auto start on lowering Pressurizer level. The RO should start pumps as directed by the SRO.

4 MS09A I(BOP/SRO) SG #1 Steam Flow instrument, FW-IFR-1011, fails low. The crew should enter OP-901-201 and manually control feedwater flow. The Ultrasonic Flowmeter goes bad due to the FW flow transient and the crew should enter TRM 3.3.5. Note: the crew has 1 minute 17 seconds to respond to this failure or the plant will trip on low SG level.

5 RC23B (0.1%) M(ALL) The leak grows to a SB LOCA over a 10 minute period. The crew should manually trip the reactor and manually initiate SIAS and CIAS.

6 SI02B SI16G I(BOP) HPSI Pump B fails to auto start and SI-227B fails to Open. The BOP should manually start HPSI Pump B and open SI-227B. The crew may commence a cooldown with the ADVs.

7 RP05B3 RP05C3 RP05D3 I(RO) CSAS fails to initiate when containm ent pressure reaches 17.7 psia. The RO should recognize this and manually initiate CSAS. Once the RO secures RCPs following CSAS, the scenario may be terminated.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix DScenario OutlineForm ES-D-1Facility: Waterford IIIScenario No.: 3Op-Test No.: 1Examiners: Operators:Initial Conditions: IC-10 100%, BOCTurnover: RCP 1A Middle Seal failed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago (RC09A). EFW Pump A tagged out and is expectedto be returned to service by the end of shift. HPSI Pump A is tagged out and is expected to bereturned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.EventNo.Malf.No.Event Type*EventDescription1NI01GI(ALL)After the crew takes the shift ENI Channel C Middle Detector fails lowenergizing Startup Channel 1. The crew should de-energize SUChannel 1. The crew should enter TS 3.3.1 & 3.3.3.6 and bypassaffected trip bistables.2RC21AI(ALL)A loop 1 Thot instrument fails low affecting pressurizer level setpoint.This event requires implementation of OP-901-110, Pressurizer LevelMalfunction Off-Normal procedure.3CC03AC(BOP/SRO)CCW Pump A bearing seizes and the pump trips. The BOP will startCCW Pump AB to replace A. Since the AB buses are aligned to theB side, this will require entry into TS 3.7.3 and cascading TS per OP-100-014.4RC08AC(RO/SRO)The pressure surge on the system causes RCP 1A Lower Seal to fail.The crew should trip the reactor and secure RCP 1A to comply withOP-901-130.5RP01ARP01BRP01CI(RO)The manual reactor trip will fail and the RO will trip the reactor byalternate means.6EG05C(BOP)Main Generator Exciter Field Breaker fails to open.7SG01A(20%)M(ALL)After the trip a SGTR occurs in SG #1. The crew will enter OP-902-007. Once the crew isolates SG #1, the scenario may be terminated.* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 ES-401 PWR RO Examination Outline Form ES-401-2 Facility: Waterford 3 Date of Exam: 11/10/2006 RO K/A Category Points SRO - Only Points Tier Group K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G
  • Total A2 G* TOTAL 1 3 3 3 3 3 3 3 3 18 2 1 2 2 2 1 2 2 1 9 1. Emergency &

Abnormal Plant Evolutions Tier Totals 4 5 5 5 4 5 5 4 27 1 3 2 3 3 2 2 3 3 2 2 3 28 2 1 0 1 1 1 1 1 1 1 1 1 10 2. Plant Systems Tier Totals 4 2 4 4 3 3 4 4 3 3 4 38 1 2 3 4 1 2 3 4 3. Generic Knowledge and Abilities 3 2 3 2 10 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO Outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling. 2. The point total for each group and tier in the proposed outli ne 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 RO exam must total 75 points and the SRO -only exam must total 25 points. 3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution unless they relate to plant-specific priorities. 4. Systems/evolutions within each group are identified on the associated outline. 5. The shaded areas are not applicable to the category/tier. 6.* The generic (G) 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective. 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for th e applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K" and "A". Use duplicate pages for RO and SRO-only exams. 8. For Tier 3, enter the K/A number, descriptions, importance ratings, and point totals on Form ES-401-3. 9. Refer to ES-401, *-Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

NUREG-1021, Revision 9 2 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO) E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR # 1. 00007 (BW/E02 & E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 x EK1.02 - Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Shutdown margin (CFR: 41.10) 3.4 1 2. 00008 Pressurizer Vapor Space Accident / 3 x 2.2.34 - Knowledge of the process for determining the internal and external effects on core reactivity. (CFR: 41.1) 2.8 1 3. 000009 Small Break LOCA / 3 x EK3.16 - Knowledge of the reasons for the following responses as they apply to the small break LOCA: Containment temperature, pressure, humidity and level limits (CFR: 41.5) 3.8 1 4. 000011 Large Break LOCA / 3 x EK2.02 - Knowledge of the interrelations between a Large Break LOCA and the following: Pumps (CFR 41.7) 2.6 1 5. 000015/17 RCP Malfunctions / 4 x AA2.02 - Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Abnormalities in RCP air vent flow paths and/or oil cooling system (CFR: 41.14) 2.8 1 6. 000022 Loss of Rx Coolant Makeup / 2 x 2.1.24 - Ability to obtain and interpret station electrical and mechanical drawings. (CFR: 41.3) 2.8 1 7. 000025 Loss of RHR System / 4 x AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: RCS/RHRS cooldown rate (CFR 41.7) 3.6 1 8. 000026 Loss of Component Cooling Water / 8 x AA1.07 - Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: Flow rates to the components and systems that are serviced by the CCWS; interactions among the components (CFR 41.7 ) 2.9 1 9. 000027 Pressurizer Pressure Control System Malfunction / 3 x AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions: Definition of saturation temperature (CFR 41.14 ) 3.1 1 10. 000029 ATWS / 1 x EK2.06 - Knowledge of the interrelations between the and the following an ATWS: Breakers, relays, and disconnects (CFR 41.6 ) 2.9 1 11. 000038 Steam Gen. Tube Rupture / 3 x EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the SGTR: Use of steam tables (CFR 41.10) 3.1 1 NUREG-1021, Revision 9 3 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO) E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR # 12. 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 x EK3.3 - Knowledge of the reasons for the following responses as they apply to the (Excess Steam Demand): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations (CFR: 41.5) 3.8 1 13. 000054 (CE/E06) Loss of Main Feedwater / 4 x EK2.1 -Knowledge of the interrelations between the (Loss of Feedwater) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features (CFR: 41.7) 3.3 1 14. 000055 Station Blackout / 6 x 2.4.12 - Knowledge of general operating crew responsibilities during emergency operations.

(CFR: 41.10) 3.4 1 15. 000056 Loss of Off-site Power /

6 x AA2.38 - Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Load sequencer status lights (CFR: 41.7) 3.7 1 16. 000057 Loss of Vital AC Inst. Bus / 6 x AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus (CFR; 41.10) 4.1 1 17. 000058 Loss of DC Power / 6 x AA1.03 - Ability to operate and / or monitor the following as they apply to the Loss of DC Power: Vital and battery bus components (CFR 41.7) 3.1 1 18. 000065 Loss of Instrument Air /

8 x AA2.06 - Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing (CFR: 41.10) 3.6* 1 K/A Category Totals:

3 3 3 3 3 3 Group Point Total:

18 NUREG-1021, Revision 9 4 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO) E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s) IR # 19. 000005 Inoperable/Stuck Control Rod / 1 x AK3.04-Knowledge of the reasons for the following responses as they apply to the Inoperable / Stuck Control Rod: Tech-Spec limits for inoperable rods. (CFR 41.2) 3.4 1 20. 000024 Emergency Boration / 1 x AK2.04 - Knowledge of the interrelations between the Emergency Boration and the following: Pumps (CFR 41.8 ) 2.6 1 21. 000033 Loss of Intermediate Range NI / 7 x AK1.01 -Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: Effects of voltage changes on performance (CFR 41.2 ) 2.7 1 22. 000036 (BW/A08) Fuel Handling Accident / 8 x AA1.01 - Ability to operate and / or monitor the following as they apply to the Fuel Handling Incidents: Reactor building containment purge ventilation system (CFR 41.7) 3.3 1 23. 000059 Accidental Liquid RadWaste Rel. / 9 x AA2.02 - Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: The permit for liquid radioactive-waste release (CFR: 41.13) 2.9 1 24. 000069 (W/E14) Loss of CTMT Integrity / 5 x AA2.01 - Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: Loss of containment integrity (CFR: 41.9) 3.7 1 25. 000074 Inadequate Core Cooling/ 4 x EK2.06 - Knowledge of the interrelations between Inadequate Core Cooling and the following: Turbine bypass and atmospheric dump valves (CFR 41.5 ) 3.5* 1 26. CE/A16 Excess RCS Leakage /

2 x 2.4.10 - Knowledge of annunciator response procedures. (CFR: 41.10 ) 3.0 1 27. CE/E09 Functional Recovery x EK3.2 - Knowledge of the reasons for the following responses as they apply to the (Functional Recovery): Normal, abnormal and emergency operating procedures associated with (Functional Recovery) (CFR: 41.10) 3.0 1 K/A Category Totals:

1 2 2 1 2 1 Group Point Total:

9 NUREG-1021, Revision 9 5 ES-401 PWR Examination Outline Form ES-401-2Plant Systems - Tier 2 / Group 1 (RO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s) IR # 28. 003 Reactor Coolant Pump x A1.09 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including: Seal flow and D/P (CFR: 41.5) 2.8 1 29. 004 Chemical and Volume Control x K6.05 - Knowledge of the effect of a loss or malfunction on the following CVCS components: Sensors and detectors (CFR: 41.7) 2.5 1 30. 005 Residual Heat Removal x K5.05 - Knowledge of the operational implications of the following concepts as they apply the RHRS: Plant response during "solid plant": pressure change due to the relative incompressibility of water (CFR: 41.5) 2.7

  • 1 31. 006 Emergency Core Cooling x K1.08 - Knowledge of the physical connections and/or cause effect relationships between the ECCS and the following systems:

CVCS (CFR: 41.6) 3.6 1 32. 006 Emergency Core Cooling x A3.05 - Ability to monitor automatic operation of the ECCS, including: Safety Injection Pump (CFR: 41.7 ) 4.2 1 33. 013 Engineered Safety Features Actuation System (ESFAS) x A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including: RCS pressure and temperature (CFR: 41.5) 4.0 1 34. 008 Component Cooling

Water x K2.02 - Knowledge of bus power supplies to the following: CCW pump, including emergency backup (CFR: 41.7) 3.0* 1 35. 010 Pressurizer Pressure Control x K3.03 - Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following:

ESFAS (CFR: 41.7) 4.0 1 36. 012 Reactor Protection x A3.04 - Ability to monitor automatic operation of the RPS, including: Circuit breaker (CFR: 41.6 ) 2.8

  • 1 NUREG-1021, Revision 9 6 ES-401 PWR Examination Outline Form ES-401-2Plant Systems - Tier 2 / Group 1 (RO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s) IR # 37. 012 Reactor Protection x K6.09- Knowledge of the effect of a loss or malfunction of the following will have on the RPS:

CEAC (CFR: 41.6) 3.6 1 38. 013 Engineered Safety Features Actuation System (ESFAS) x K3.01 - Knowledge of the effect that a loss or malfunction of the ESFAS will have on the following:

Fuel (CFR: 41.2) 4.4 1 39. 022 Containment Cooling x A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor over-current (CFR: 41.5) 2.5 1 40. 022 Containment Cooling x A4.04 - Ability to manually operate and/or monitor in the control room: Valves in the CCS (CFR: 41.7) 3.1 1 41. 026 Containment Spray x K1.02 - Knowledge of the physical connections and/or cause effect relationships between the CSS and the following systems: Cooling water (CFR: 41.8) 4.1 1 42. 039 Main and Reheat Steam x K5.01 - Knowledge of the operational implications of the following concepts as they apply to the MRSS: Definition and causes of steam/

water hammer (CFR: 41.14) 2.9 1 43. 059 Main Feedwater x A2.03 - Ability to (a) predict the impacts of the following malfunctions 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: Overfeeding event (CFR: 41.5) 2.7 1 NUREG-1021, Revision 9 7 ES-401 PWR Examination Outline Form ES-401-2Plant Systems - Tier 2 / Group 1 (RO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s) IR # 44. 061 Auxiliary/Emergency

Feedwater x K1.03 - Knowledge of the physical connections and/or cause effect relationships between the AFW and the following systems: Main steam system (CFR: 41.4) 3.5 1 45. 062 AC Electrical Distribution x K4.10 - Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: Uninterruptible ac power sources (CFR: 41.7) 3.1 1 46. 063 DC Electrical Distribution x K4.04 - Knowledge of DC electrical system design feature(s) and/ or interlock(s) which provide for the following: Trips (CFR: 41.7) 2.6? 1 47. 005-Residual Heat Removal System x A4.01 - Ability to manually operate and/or monitor in the control room: Controls and indications for RHR Pump (CFR: 41.8) 3.6* 1 48. 064 Emergency Diesel Generator x K4.02 - Knowledge of ED/G system design feature(s) and/or interlock( s) which provide for the following: Trips for ED/G while operating (normal or emergency) (CFR: 41.7) 3.9 1 49. 073 Process Radiation Monitoring x A2.02 - Ability to (a) predict the impacts of the following malfunctions or 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: Detector failure (CFR: 41.11) 2.7 1 50. 073 Process Radiation Monitoring x 2.4.48 -Ability to interpret control room indications to verify the

status and operation of system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.12) 4.0 1 NUREG-1021, Revision 9 8 ES-401 PWR Examination Outline Form ES-401-2Plant Systems - Tier 2 / Group 1 (RO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s) IR # 51. 076 Service Water x A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures (CFR: 41.5) 2.6

  • 1 52. 078 Instrument Air x K2.01 - Knowledge of bus power supplies to the following: Instrument air compressor (CFR: 41.7) 2.7 1 53. 078 Instrument Air x 2.1.28- Knowledge of the purpose and function of major system components and controls. (CFR: 41.7) 3.2 1 54. 103 Containment x K3.01 - Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under shutdown conditions (CFR: 41.9) 3.3* 1 55. 103 Containment x 2.1.27 - Knowledge of system purpose and or function. (CFR: 41.7) 2.8 1 K/A Category Totals:

3 2 3 3 2 2 3 3 2 2 3 Group Point Total:

28 NUREG-1021, Revision 9 9 ES-401 PWR Examination Outline Form ES-401-2Plant Systems - Tier 2 / Group 2 (RO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s) IR # 56. 001 Control Rod Drive x K3.02- Knowledge of the effect that a loss or malfunction of the CRDS will have on the following:

RCS (CFR: 41.6) 3.4

  • 1 57. 002 Reactor Coolant x A4.02 - Ability to manually operate and/or monitor in the control room: Indications necessary to verify natural circulation from appropriate level, flow, and temperature indications and valve positions upon loss of forced circulation (CFR: 41.5) 4.3 1 58. 011 Pressurizer Level Control x A1.04-Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including:

Tave (CFR: 41.5) 3.1 1 59. 015 Nuclear Instrumentation x K6.03 - Knowledge of the effect of a loss or malfunction on the following will have on the NIS:

Component interconnections (CFR: 41.2) 2.6 1 60. 016 Non-nuclear Instrumentation x 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical

specifications. (CFR: 41.5) 3.4 1 61. 014 Rod Position Indication x A2.07 - Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of Reed Switch (CFR: 41.10) 2.6 1 62. 033 Spent Fuel Pool Cooling x K4.04 -Knowledge of design feature(s) and/or interlock(s) which provide for the following: Maintenance of spent fuel pool radiation (CFR: 41.7) 2.7 1 NUREG-1021, Revision 9 10 ES-401 PWR Examination Outline Form ES-401-2Plant Systems - Tier 2 / Group 2 (RO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s) IR # 63. 041 Steam Dump/Turbine Bypass Control x A3.02-Ability to monitor automatic operation of the SDS, including: RCS pressure, RCS temperature, and reactor power. (CFR: 41.5) 3.3 1 64. 071 Waste Gas Disposal x K5.04 - Knowledge of the operational implication of the following concepts as they apply to the Waste Gas Disposal System: Relationship hydrogen/ oxygen concentrations to flammability (CFR: 41.13) 2.5 1 65. 072 Area Radiation Monitoring x K1.05 - Knowledge of the physical connections and/or cause effect relationships between the ARM system and the following systems:

MRSS (CFR: 41.11) 2.8

  • 1 K/A Category Totals:

1 0 1 1 1 1 1 1 1 1 1 Group Point Total:

10 NUREG-1021, Revision 9 11 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3Facility Waterford 3 Date of Exam: 11/12/2004 Category K/A # Topic RO SRO-Only IR # IR # 66. 2.1.10 Knowledge of conditions and limitations in the facility license. (CFR: 41.5) 2.7 1 67. 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data. (CFR: 41.10) 2.8 1 68. 2.1.32 Ability to explain and apply all system limits and precautions. (CFR: 41.5) 3.4 1 1. Conduct of Operations Subtotal 3 69. 2.2.27 Knowledge of the refueling process. (CFR: 41.13) 2.6 1 70. 2.2.22 Knowledge of Limiting Conditions for operations and Safety Limits. (CFR: 41.8) 3.4 1 2. Equipment Control Subtotal 2 71. 2.3.2 Knowledge of facility ALARA program. (CFR: 41.12) 2.5 1 72. 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. (CFR: 41.12) 2.5 1 73. 2.3.11 Ability to control radiation releases. (CFR: 41.13) 2.7 1 3. Radiation Control Subtotal 3 74. 2.4.17 Knowledge of EOP terms and definitions. (CFR: 41.10) 3.1 1 75. 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm. (CFR: 41.7) 3.3 1 4. Emergency Procedures/ Plan Subtotal 2 Tier 3 Point Total 10 NUREG-1021, Revision 9ES-401 PWR SRO Examination Outline Form ES-401-2Facility:Waterford 3Date of Exam: 11/10/2006RO K/A Category PointsSRO - Only PointsTierGroup K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G*Total A2 G*TOTAL 1 3 3 6 2 2 2 4 1.Emergency &Abnormal PlantEvolutionsTier Totals 5 5 10 1 3 2 5 2 K5 2 1 3 2.PlantSystemsTierTotals 5 3 8 1 2 3 4 1 2 3 43. Generic Knowledge and Abilities 2 2 2 1 7Note: 1.Ensure that at least two topics from every K/A category are sampled within each tier of the RO Outline (i.e., the "Tier Totals"in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling.

2.The point total for each group and tier in the proposed outline must match that specified in the table. The final point total foreach group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam musttotal 75 points and the SRO -only exam must total 25 points.

3.Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolutionunless they relate to plant-specific priorities.

4.Systems/evolutions within each group are identified on the associated outline.

5.The shaded areas are not applicable to the category/tier.

6.*The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant tothe applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7.On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for theapplicable license level, and the point totals for each system and category. Enter the group and tier totals for each categoryin the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K" and "A".Use duplicate pages for RO and SRO-only exams.8. For Tier 3, enter the K/A number, descriptions, importance ratings, and point totals on Form ES-401-3.9. Refer to ES-401, *-Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

NUREG-1021, Revision 9 ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier1 / Group 1 (SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)IR #76.00007 (BW/E02 & E10;CE/E02) Reactor Trip -Stabilization - Recovery / 1 xEA2.1 Ability to determine and interpret thefollowing as they apply tothe (Reactor Trip Recovery)Facility conditions and selection of appropriateprocedures during abnormal and emergencyoperations.(CFR: 43.5) 3.7 1 77.000011 Large Break LOCA / 3 x2.4.1 Knowledge of EOP entry conditions andimmediate action steps.(CFR: 43.5) 4.6 1 78.000026 Loss of ComponentCooling Water / 8operations risk assessment x2.2.17; Knowledge of the process for managingmaintenance activities during power operations.(CFR: 43.5) 3.5 1 79.000040 (BW/E05; CE/E05;W/E12) Steam Line Rupture -Excessive Heat Transfer / 4 xAA2.05 Ability to determine and interpret thefollowing as they apply to the Steam LineRupture: When ESFAS systems may besecured(CFR: 43.5) 4.5 1 80.000054 (CE/E06) Loss of MainFeedwater / 4 xAA2.06; Ability to determine and interpret thefollowing as they apply to the Loss of MainFeedwater (MFW): AFW adjustments needed tomaintain proper T-ave. and S/G level . . (CFR: 43.5) 4.3 1 81.000055 Station Blackout / 6 x2.4.47, Ability to diagnose and recognize trendsin an accurate and timely manner utilizing theappropriate control room reference material.(CFR: 43.5) 3.7 1K/A Category Totals: 3 3Group Point Total:

6 NUREG-1021, Revision 9 ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)IR #82.000001 Continuous RodWithdrawal / 1 xAA2.04 - Ability to determine and interpret thefollowing as they apply to the Continuous RodWithdrawal : Reactor power and its trend(CFR: 43.6) 4.3 1 83.000037 Steam Generator TubeLeak / 3 x2.4.11 - Knowledge of abnormal conditionprocedures.(CFR: 43.5) 3.6 1 84.000051 Loss of CondenserVacuum / 4 xAA2.02;Ability to determine and interpret thefollowing as they apply to the Loss of CondenserVacuum: Conditions requiring reactor and/orturbine trip(CFR: 43.5) 4.1 1 85.000061 ARM System Alarms / 7 x2.3.1 Knowledge of 10 CFR: 20 and relatedfacility radiation control requirements.(CFR: 43.4) 3.0 1K/A Category Totals: 2 2Group Point Total:

4 NUREG-1021, Revision 9ES-401 PWR Examination Outline Form ES-401-2Plant systems - Tier 2 / Group 1 (SRO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)IR #86.004 Chemical and VolumeControl x2.1.33 - Ability to recognizeindications for systemoperating parameters whichare entry-level conditionsfor technical specifications.(CFR: 43.2) 4.0 1 87.007 Pressurizer Relief/Quench Tank x2.3.10 - Ability to performprocedures to reduceexcessive levels of radiationand guard against personnelexposure.(CFR: 43.4) 3.3 1 88.013 Engineered SafetyFeatures Actuation xA2.06 - Ability to (a) predict theimpacts of the followingmalfunctions or operationson the ESFAS; and (b) basedAbility on those predictions, useprocedures to correct, control, ormitigate the consequences ofthose malfunctions or operations;Inadvertent ESFAS actuation(CFR: 43.2) 4.0 1 89.061 Auxiliary/EmergencyFeedwater xA2.03-Ability to (a) predict theimpacts of the followingmalfunctions or operationson the AFW; and (b) based onthose predictions, use proceduresto correct, control, or mitigate theconsequences of thosemalfunctions or operations: Lossof dc power(CFR: 43.5) 3.4 1 90.062 AC ElectricalDistribution xA2.12 Ability to (a) predict theimpacts of the followingmalfunctions or operationson the ac distribution system; and(b) based on those predictions,use procedures to correct, control,or mitigate the consequences ofthosemalfunctions or operations:Restoration of power to a systemwith a fault on it .(CFR: 43.5) 3.6 1K/A Category Totals: 3 2Group Point Total:

5 NUREG-1021, Revision 9ES-401 PWR Examination Outline Form ES-401-2Plant systems - Tier 2 / Group 2 (SRO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)IR #91.034 Fuel HandlingEquipment xA2.01 Ability to (a) predict theimpacts of the followingmalfunctions or operations on theFuel Handling System; and (b)based on those predictions, useprocedures to correct, control, ormitigate the consequences ofthose malfunctions or operations:Dropped fuel element(CFR: 43.7) 4.4 1 92.056 Condensate x2.1.34 Ability to maintainprimary and secondary plantchemistry within allowable limits.((CFR: 43.5) 2.9 1 93.086 Fire Protection xA2.04-Ability to (a) predict theimpacts of the followingmalfunctions or operations on theFire Protection System;and (b) based on thosepredictions, use procedures tocorrect, control, or mitigate theconsequences of thosemalfunctions or operations:Failure to actuate the FPS whenrequired, resulting in fire damage(CFR: 43.5) 3.3 1K/A Category Totals: 2 1Group Point Total:

3 NUREG-1021, Revision 9ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3Facility Waterford 3 Date of Exam: 11/12/2004CategoryK/A #Topic ROSRO-Only IR#IR#94.2.1.6Ability to supervise and assume a management role duringplant transients and upset conditions.(CFR: 43.5) 4.3 1 95.2.1.7Ability to evaluate plant performance and make operationaljudgments based on operating characteristics, reactorbehavior, and instrument interpretation.(CFR: 43.5) 4.4 1 1.Conduct ofOperationsSubtotal 2 96.2.2.13Knowledge of tagging and clearance procedures.(CFR: 43.2) 3.8 1 97.2.2.28Knowledge of new and spent fuel movement procedures. l(CFR: 43.7) 3.5 1 2.EquipmentControlSubtotal 2 98.2.3.3Knowledge of SRO responsibilities for auxiliary systemsthat are outside the control room (e.g., waste disposal andhandling systems).(CFR: 43.4) 2.9 1 99.2.3.9Knowledge of the process for performing a containmentpurge.(CFR: 43.4) 3.4 1 3.RadiationControlSubtotal 2 100.2.4.29Knowledge of the emergency plan.(CFR: 43.5) 4.0 1 4.EmergencyProcedures/PlanSubtotal 1Tier 3 Point Total 7

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