ML070530105

Wat - Init Exam - 11/2006 - Final Outline

ML070530105
Person / Time
Site:	Waterford
Issue date:	11/23/2006
From:	Operations Branch IV
To:	Entergy Operations
References
Download: ML070530105 (24)

Text

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 Type Describe activity to be performed (see Note) Code*

Conduct of Operations Perform OP-004-015 Attachment 11.1 Manual CEA Subgroup R, N Selection.

Conduct of Operations Perform OP-903-015 Attachment 10.1 Shutdown Margin Calculation R, M Equipment Control Perform OP-903-001 Attachment 11.15 Containment Pressure R, N calculation.

Radiation Control Review RWP.

R,N Emergency Plan Not selected 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 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 Type Describe activity to be performed (see Note) Code*

R, N Review OP-004-015 Attachment 11.1, Manual CEA Subgroup Conduct of Operations Selection.

Conduct of Operations R,N Determine if hours worked exceed guidelines Requirements.

R, N Perform an SRO review of OP-903-001 Attachment 11.15, Equipment Control Containment Pressure calculation.

R, N Review OP-901-131 Attachment 1, Containment Closure Radiation Control checklist.

S,M Determine E-Plan classification and notification requirements Emergency Plan 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 D, P, S 3 Control Room)

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 A, D, S 6 Diesel Generator

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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power / Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator

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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power / Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator

Appendix 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 Malf. Event Type* Event No. No. Description R(RO) Crew performs a brief and commences power escalation toward 1 N/A N(BOP/SRO) 100% power.

SG 2 Channel D low pressure trip setpoint fails high. The crew 2 SG07D2 I(BOP/SRO) 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.

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 3 CV12A2 I(RO/SRO) 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).

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

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

RD11A03 CEAs 3 and 82 stick out on the trip, which causes the RO to 6 C(RO)

RD11A82 emergency borate due to two stuck CEAs.

A LOOP occurs 1 minute after the trip, and EDG B Output breaker ED01A C(BOP) fails to close and cannot be closed. The crew will implement SPTAs ED01B M(ALL) and will be directed to OP-902-003.

ED01C ED01D EG09B 7 After the crew performs Step 7 to Protect Main Condenser, the AB FW05 C(BOP/SRO) EFW Pump trips on overspeed and cannot be restored. The crew will FW07B 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

Appendix 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 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 />.

Event Malf. Event Type* Event No. No. Description CEA 82 drops into the core. The crew should implement OP-901-R(RO) 1 RD02A82 102. To comply with TS 3.1.3.1 the crew implements OP-901-212 for C(BOP/SRO) a rapid power reduction within 15 minutes.

RC23B After the crew satisfies the reactivity manipulation, an RCS leak 2 C(SRO)

(0.01%) develops inside Containment. The crew should enter TS 3.4.5.2.

CV02A Charging Pumps AB and A fail to auto start on lowering Pressurizer 3 I(RO)

CV02C level. The RO should start pumps as directed by the SRO.

SG #1 Steam Flow instrument, FW-IFR-1011, fails low. The crew should enter OP-901-201 and manually control feedwater flow. The 4 MS09A I(BOP/SRO) 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.

RC23B M(ALL) The leak grows to a SB LOCA over a 10 minute period. The crew 5

(0.1%) should manually trip the reactor and manually initiate SIAS and CIAS.

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

RP05B3 CSAS fails to initiate when containment pressure reaches 17.7 psia.

7 RP05C3 I(RO) The RO should recognize this and manually initiate CSAS. Once the RP05D3 RO secures RCPs following CSAS, the scenario may be terminated.

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

Appendix D Scenario Outline Form ES-D-1 Facility: Waterford III Scenario No.: 3 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: IC-10 100%, BOC 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 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 />.

Event Malf. Event Type* Event No. No. Description After the crew takes the shift ENI Channel C Middle Detector fails low energizing Startup Channel 1. The crew should de-energize SU 1 NI01G I(ALL)

Channel 1. The crew should enter TS 3.3.1 & 3.3.3.6 and bypass affected trip bistables.

A loop 1 Thot instrument fails low affecting pressurizer level setpoint.

2 RC21A I(ALL) This event requires implementation of OP-901-110, Pressurizer Level Malfunction Off-Normal procedure.

CCW Pump A bearing seizes and the pump trips. The BOP will start CCW Pump AB to replace A. Since the AB buses are aligned to the 3 CC03A C(BOP/SRO)

B side, this will require entry into TS 3.7.3 and cascading TS per OP-100-014.

The pressure surge on the system causes RCP 1A Lower Seal to fail.

4 RC08A C(RO/SRO) The crew should trip the reactor and secure RCP 1A to comply with OP-901-130.

RP01A The manual reactor trip will fail and the RO will trip the reactor by 5 RP01B I(RO) alternate means.

RP01C 6 EG05 C(BOP) Main Generator Exciter Field Breaker fails to open.

SG01A After the trip a SGTR occurs in SG #1. The crew will enter OP-902-7 M(ALL)

(20%) 007. Once the crew isolates SG #1, the scenario may be terminated.

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

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 K K K K K A A A A G Total A2 G* TOTAL 1 2 3 4 5 6 1 2 3 4

1. 1 3 3 3 3 3 3 18 Emergency & 1 2 2 1 2 1 9 Abnormal Plant Evolutions 2 4 5 5 4 5 4 27 Tier Totals 3 2 3 3 2 2 3 3 2 2 3 28 1

2.

1 0 1 1 1 1 1 1 1 1 1 10 Plant 2 Systems Tier 4 2 4 4 3 3 4 4 3 3 4 38 Totals 1 2 3 4

3. Generic Knowledge and Abilities 1 2 3 4 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 outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final 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 the 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 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 EK1.02 - Knowledge of the operational

1. 00007 (BW/E02 & E10; x 3.4 1 implications of the following concepts as CE/E02) Reactor Trip -

they apply to the reactor trip:

Stabilization - Recovery / 1 Shutdown margin (CFR: 41.10) 2.2.34 - Knowledge of the process for

2. 00008 Pressurizer Vapor x 2.8 1 determining the internal and external effects on Space Accident / 3 core reactivity.

(CFR: 41.1)

EK3.16 - Knowledge of the reasons for the 3.8

3. 000009 Small Break LOCA / 3 x 1 following responses as they apply to the small break LOCA:

Containment temperature, pressure, humidity and level limits (CFR: 41.5)

EK2.02 - Knowledge of the interrelations

4. 000011 Large Break LOCA / 3 x 2.6 1 between a Large Break LOCA and the following:

Pumps (CFR 41.7)

AA2.02 - Ability to determine and interpret the 2.8

5. 000015/17 RCP Malfunctions / 4 x 1 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) 2.1.24 - Ability to obtain and interpret station 2.8

6. 000022 Loss of Rx Coolant x 1 electrical and mechanical drawings.

Makeup / 2 (CFR: 41.3)

AA1.01 - Ability to operate and / or monitor the

7. 000025 Loss of RHR System / 4 x 3.6 1 following as they apply to the Loss of Residual Heat Removal System:

RCS/RHRS cooldown rate (CFR 41.7)

AA1.07 - Ability to operate and / or monitor the

8. 000026 Loss of Component x 2.9 1 following as they apply to the Loss of Component Cooling Water / 8 Cooling Water:

Flow rates to the components and systems that are serviced by the CCWS; interactions among the components (CFR 41.7 )

AK1.01 - Knowledge of the operational

9. 000027 Pressurizer Pressure x 3.1 1 implications of the following concepts as Control System Malfunction / 3 they apply to Pressurizer Pressure Control Malfunctions:

Definition of saturation temperature (CFR 41.14 )

EK2.06 - Knowledge of the interrelations

10. 000029 ATWS / 1 x 2.9 1 between the and the following an ATWS:

Breakers, relays, and disconnects (CFR 41.6 )

EK1.01 - Knowledge of the operational

11. 000038 Steam Gen. Tube x 3.1 1 implications of the following concepts as they Rupture / 3 apply to the SGTR:

Use of steam tables (CFR 41.10)

NUREG-1021, Revision 9 2

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000040 (BW/E05; CE/E05; EK3.3 - Knowledge of the reasons for the

12. x 3.8 1 W/E12) following responses as they apply to Steam Line Rupture - Excessive the (Excess Steam Demand):

Heat Transfer / 4 Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations (CFR: 41.5) 000054 (CE/E06) Loss of Main EK2.1 -Knowledge of the interrelations between

13. x 3.3 1 Feedwater / 4 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) 2.4.12 - Knowledge of general operating crew

14. 000055 Station Blackout / 6 x 3.4 1 responsibilities during emergency operations.

(CFR: 41.10)

AA2.38 - Ability to determine and interpret the

15. 000056 Loss of Off-site Power / x 3.7 1 following as they apply to the Loss of Offsite 6

Power:

Load sequencer status lights (CFR: 41.7)

AK3.01 - Knowledge of the reasons for the

16. 000057 Loss of Vital AC Inst. x 1 following responses as they apply to the Loss of 4.1 Bus / 6 Vital AC Instrument Bus:

Actions contained in EOP for loss of vital ac electrical instrument bus (CFR; 41.10)

AA1.03 - Ability to operate and / or monitor the

17. 000058 Loss of DC Power / 6 x 3.1 1 following as they apply to the Loss of DC Power:

Vital and battery bus components (CFR 41.7)

AA2.06 - Ability to determine and interpret the

18. 000065 Loss of Instrument Air / x 1 following as they apply to the Loss of Instrument 3.6 8

Air:

• When to trip reactor if instrument air pressure is de-creasing (CFR: 41.10) 3 3 3 3 3 3 18 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9 3

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 AK3.04-Knowledge of the reasons for the

19. 000005 Inoperable/Stuck x 3.4 1 following responses as they apply to the Control Rod / 1 Inoperable / Stuck Control Rod:

Tech-Spec limits for inoperable rods.

(CFR 41.2)

AK2.04 - Knowledge of the interrelations

20. 000024 Emergency Boration / 1 x 2.6 1 between the Emergency Boration and the following:

Pumps (CFR 41.8 )

AK1.01 -Knowledge of the operational

21. 000033 Loss of Intermediate x 2.7 1 implications of the following concepts as Range NI / 7 they apply to Loss of Intermediate Range Nuclear Instrumentation:

Effects of voltage changes on performance (CFR 41.2 )

AA1.01 - Ability to operate and / or monitor the

22. 000036 (BW/A08) Fuel x 3.3 1 following as they apply to the Fuel Handling Handling Accident / 8 Incidents:

Reactor building containment purge ventilation system (CFR 41.7)

AA2.02 - Ability to determine and interpret the

23. 000059 Accidental Liquid x 2.9 1 following as they apply to the Accidental Liquid RadWaste Rel. / 9 Radwaste Release:

The permit for liquid radioactive-waste release (CFR: 41.13)

AA2.01 - Ability to determine and interpret the

24. 000069 (W/E14) Loss of CTMT x 3.7 1 following as they apply to the Loss of Integrity / 5 Containment Integrity:

Loss of containment integrity (CFR: 41.9)

EK2.06 - Knowledge of the interrelations

25. 000074 Inadequate Core x 3.5 1 between Inadequate Core Cooling and the Cooling/ 4

• following:

Turbine bypass and atmospheric dump valves (CFR 41.5 )

2.4.10 - Knowledge of annunciator response

26. CE/A16 Excess RCS Leakage / x 3.0 1 procedures.

2 (CFR: 41.10 )

EK3.2 - Knowledge of the reasons for the

27. CE/E09 Functional Recovery x 3.0 1 following responses as they apply to the (Functional Recovery):

Normal, abnormal and emergency operating procedures associated with (Functional Recovery)

(CFR: 41.10) 1 2 2 1 2 1 9 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9 4

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A1.09 - Ability to predict and/or 2.8

28. 003 Reactor Coolant x 1 monitor changes in parameters (to Pump prevent exceeding design limits) associated with operating the RCPS controls including:

Seal flow and D/P (CFR: 41.5)

K6.05 - Knowledge of the effect 2.5

29. 004 Chemical and x 1 of a loss or malfunction on the Volume Control following CVCS components:

Sensors and detectors (CFR: 41.7)

K5.05 - Knowledge of the 2.7

30. 005 Residual Heat x 1 operational implications of the

• Removal following concepts as they apply the RHRS:

Plant response during "solid plant": pressure change due to the relative incompressibility of water (CFR: 41.5)

K1.08 - Knowledge of the 3.6

31. 006 Emergency Core x 1 physical connections and/or cause Cooling effect relationships between the ECCS and the following systems:

CVCS (CFR: 41.6)

A3.05 - Ability to monitor 4.2

32. 006 Emergency Core x 1 automatic operation of the ECCS, Cooling including:

Safety Injection Pump (CFR: 41.7 )

013 Engineered Safety A1.01 - Ability to predict and/or 4.0

33. x 1 Features Actuation monitor changes in parameters (to System (ESFAS) prevent exceeding design limits) associated with operating the ESFAS controls including:

RCS pressure and temperature (CFR: 41.5)

K2.02 - Knowledge of bus power 3.0

34. 008 Component Cooling x 1 supplies to the following: CCW

• Water pump, including emergency backup (CFR: 41.7)

K3.03 - Knowledge of the effect 4.0

35. 010 Pressurizer Pressure x 1 that a loss or malfunction of the Control PZR PCS will have on the following:

ESFAS (CFR: 41.7)

A3.04 - Ability to monitor 2.8

36. 012 Reactor Protection x 1 automatic operation of the RPS,

• including:

Circuit breaker (CFR: 41.6 )

NUREG-1021, Revision 9 5

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K6.09- Knowledge of the effect 3.6

37. 012 Reactor Protection x 1 of a loss or malfunction of the following will have on the RPS:

CEAC (CFR: 41.6) 013 Engineered Safety K3.01 - Knowledge of the effect 4.4

38. x 1 Features Actuation that a loss or malfunction of the System (ESFAS) ESFAS will have on the following:

Fuel (CFR: 41.2)

A2.01 - Ability to (a) predict the

39. 022 Containment Cooling x 2.5 1 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)

A4.04 - Ability to manually

40. 022 Containment Cooling x 3.1 1 operate and/or monitor in the control room:

Valves in the CCS (CFR: 41.7)

K1.02 - Knowledge of the 4.1

41. 026 Containment Spray x 1 physical connections and/or cause effect relationships between the CSS and the following systems:

Cooling water (CFR: 41.8)

K5.01 - Knowledge of the 2.9

42. 039 Main and Reheat x 1 operational implications of the Steam following concepts as they apply to the MRSS:

Definition and causes of steam/

water hammer (CFR: 41.14)

A2.03 - Ability to (a) predict the 2.7

43. 059 Main Feedwater x 1 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)

NUREG-1021, Revision 9 6

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 061 Auxiliary/Emergency K1.03 - Knowledge of the 3.5

44. x 1 Feedwater physical connections and/or cause effect relationships between the AFW and the following systems:

Main steam system (CFR: 41.4)

K4.10 - Knowledge of ac 3.1

45. 062 AC Electrical x 1 distribution system design Distribution feature(s) and/or interlock(s) which provide for the following:

Uninterruptible ac power sources (CFR: 41.7)

K4.04 - Knowledge of DC 2.6

46. 063 DC Electrical x 1 electrical system design feature(s)  ?

Distribution and/ or interlock(s) which provide for the following:

Trips (CFR: 41.7)

A4.01 - Ability to manually 3.6*

47. 005-Residual Heat x 1 operate and/or monitor in the Removal System control room:

Controls and indications for RHR Pump (CFR: 41.8)

K4.02 - Knowledge of ED/G 3.9

48. 064 Emergency Diesel x 1 system design feature(s) and/or Generator interlock( s) which provide for the following:

Trips for ED/G while operating (normal or emergency)

(CFR: 41.7) 073 Process Radiation A2.02 - Ability to (a) predict the 2.7

49. x 1 Monitoring 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) 2.4.48 -Ability to interpret control 4.0

50. 073 Process Radiation x 1 room indications to verify the Monitoring status and operation of system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.12)

NUREG-1021, Revision 9 7

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A1.02 - Ability to predict and/or 2.6

51. 076 Service Water x 1 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)

K2.01 - Knowledge of bus power 2.7

52. 078 Instrument Air x 1 supplies to the following:

Instrument air compressor (CFR: 41.7) 2.1.28- Knowledge of the purpose 3.2

53. 078 Instrument Air x 1 and function of major system components and controls.

(CFR: 41.7)

K3.01 - Knowledge of the effect 3.3

54. 103 Containment x 1 that a loss or malfunction of the

• containment system will have on the following:

Loss of containment integrity under shutdown conditions (CFR: 41.9) 2.1.27 - Knowledge of system 2.8

55. 103 Containment x 1 purpose and or function.

(CFR: 41.7) 3 2 3 3 2 2 3 3 2 2 3 28 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9 8

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K3.02- Knowledge of the effect 3.4

56. 001 Control Rod Drive x 1 that a loss or malfunction of the

• CRDS will have on the following:

RCS (CFR: 41.6)

A4.02 - Ability to manually 4.3

57. 002 Reactor Coolant x 1 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)

A1.04-Ability to predict and/or 3.1

58. 011 Pressurizer Level x 1 monitor changes in parameters Control (to prevent exceeding design limits) associated with operating the PZR LCS controls including:

Tave (CFR: 41.5)

K6.03 - Knowledge of the effect 2.6

59. 015 Nuclear x 1 of a loss or malfunction on the Instrumentation following will have on the NIS:

Component interconnections (CFR: 41.2) 2.1.33 - Ability to recognize 3.4

60. 016 Non-nuclear x 1 indications for system operating Instrumentation parameters which are entry-level conditions for technical specifications.

(CFR: 41.5)

A2.07 - Ability to (a) predict the

61. 014 Rod Position x 2.6 1 impacts of the following Indication 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)

K4.04 -Knowledge of design

62. 033 Spent Fuel Pool x 2.7 1 feature(s) and/or interlock(s)

Cooling which provide for the following:

Maintenance of spent fuel pool radiation (CFR: 41.7)

NUREG-1021, Revision 9 9

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 041 Steam Dump/Turbine A3.02-Ability to monitor

63. x 3.3 1 Bypass Control automatic operation of the SDS, including:

RCS pressure, RCS temperature, and reactor power.

(CFR: 41.5)

K5.04 - Knowledge of the

64. 071 Waste Gas Disposal x 2.5 1 operational implication of the following concepts as they apply to the Waste Gas Disposal System:

Relationship hydrogen/ oxygen concentrations to flammability (CFR: 41.13)

K1.05 - Knowledge of the

65. 072 Area Radiation x 1 physical connections and/or cause 2.8 Monitoring effect relationships between the

• ARM system and the following systems:

MRSS (CFR: 41.11) 1 0 1 1 1 1 1 1 1 1 1 10 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9 10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Waterford 3 Date of Exam: 11/12/2004 Category K/A # Topic RO SRO-Only IR # IR #

1. 66. 2.1.10 Knowledge of conditions and limitations in the facility 2.7 1 license.

Conduct of (CFR: 41.5)

Operations

67. 2.1.25 Ability to obtain and interpret station reference materials 2.8 1 such as graphs, monographs, and tables which contain performance data.

(CFR: 41.10)

68. 2.1.32 Ability to explain and apply all system limits and 3.4 1 precautions.

(CFR: 41.5)

Subtotal 3

2. 69. 2.2.27 Knowledge of the refueling process. 2.6 1 (CFR: 41.13)

Equipment

70. 2.2.22 Knowledge of Limiting Conditions for operations and 3.4 1 Control Safety Limits.

(CFR: 41.8)

Subtotal 2

3. 71. 2.3.2 Knowledge of facility ALARA program. 2.5 1 (CFR: 41.12)

Radiation Control

72. 2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.

(CFR: 41.12)

73. 2.3.11 Ability to control radiation releases. 2.7 1 (CFR: 41.13)

Subtotal 3

4. 74. 2.4.17 Knowledge of EOP terms and definitions. 3.1 1 (CFR: 41.10)

Emergency

75. 2.4.45 Ability to prioritize and interpret the significance of each 3.3 1 Procedures/ Plan annunciator or alarm.

(CFR: 41.7)

Subtotal 2 Tier 3 Point Total 10 NUREG-1021, Revision 9 11

ES-401 PWR SRO 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 K K K K K A A A A G Total A2 G* TOTAL 1 2 3 4 5 6 1 2 3 4

1. 1 3 3 6 Emergency &

Abnormal Plant Evolutions 2 2 2 4 Tier Totals 5 5 10 1 3 2 5

2. K5 Plant 2 2 1 3 Systems Tier Totals 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 2 2 2 1 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 outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final 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 the 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

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 / Group 1 (SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 EA2.1 Ability to determine and interpret the

76. 00007 (BW/E02 & E10; x 3.7 1 following as they apply to CE/E02) Reactor Trip -

the (Reactor Trip Recovery)

Stabilization - Recovery / 1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5) 2.4.1 Knowledge of EOP entry conditions and

77. 000011 Large Break LOCA / 3 x 4.6 1 immediate action steps.

(CFR: 43.5) 2.2.17; Knowledge of the process for managing

78. 000026 Loss of Component x 3.5 1 maintenance activities during power operations.

Cooling Water / 8 (CFR: 43.5) operations risk assessment 000040 (BW/E05; CE/E05; AA2.05 Ability to determine and interpret the

79. x 4.5 1 W/E12) Steam Line Rupture - following as they apply to the Steam Line Excessive Heat Transfer / 4 Rupture: When ESFAS systems may be secured (CFR: 43.5) 000054 (CE/E06) Loss of Main AA2.06; Ability to determine and interpret the

80. x 4.3 1 Feedwater / 4 following as they apply to the Loss of Main Feedwater (MFW): AFW adjustments needed to maintain proper T-ave. and S/G level . .

(CFR: 43.5) 2.4.47, Ability to diagnose and recognize trends

81. 000055 Station Blackout / 6 x 3.7 1 in an accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 43.5) 3 3 6 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 AA2.04 - Ability to determine and interpret the

82. 000001 Continuous Rod x 4.3 1 following as they apply to the Continuous Rod Withdrawal / 1 Withdrawal : Reactor power and its trend (CFR: 43.6) 2.4.11 - Knowledge of abnormal condition

83. 000037 Steam Generator Tube x 3.6 1 procedures.

Leak / 3 (CFR: 43.5)

AA2.02;Ability to determine and interpret the

84. 000051 Loss of Condenser x 4.1 1 following as they apply to the Loss of Condenser Vacuum / 4 Vacuum: Conditions requiring reactor and/or turbine trip (CFR: 43.5) 2.3.1 Knowledge of 10 CFR: 20 and related 3.0

85. 000061 ARM System Alarms / 7 x 1 facility radiation control requirements.

(CFR: 43.4) 2 2 4 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2 / Group 1 (SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 2.1.33 - Ability to recognize

86. 004 Chemical and Volume x 4.0 1 indications for system Control operating parameters which are entry-level conditions for technical specifications.

(CFR: 43.2) 2.3.10 - Ability to perform

87. 007 Pressurizer Relief/ x 3.3 1 procedures to reduce Quench Tank excessive levels of radiation and guard against personnel exposure.

(CFR: 43.4) 013 Engineered Safety A2.06 - Ability to (a) predict the 4.0

88. x 1 Features Actuation impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Inadvertent ESFAS actuation (CFR: 43.2)

A2.03-Ability to (a) predict the 3.4

89. 061 Auxiliary/Emergency x 1 impacts of the following Feedwater malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of dc power (CFR: 43.5)

A2.12 Ability to (a) predict the

90. 062 AC Electrical x 3.6 1 impacts of the following Distribution malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Restoration of power to a system with a fault on it .

(CFR: 43.5) 3 2 5 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2 / Group 2 (SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A2.01 Ability to (a) predict the

91. 034 Fuel Handling x 1 impacts of the following 4.4 Equipment malfunctions or operations on the Fuel Handling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Dropped fuel element (CFR: 43.7) 2.1.34 Ability to maintain

92. 056 Condensate x 1 primary and secondary plant 2.9 chemistry within allowable limits.

((CFR: 43.5)

A2.04-Ability to (a) predict the

93. 086 Fire Protection x 3.3 1 impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure to actuate the FPS when required, resulting in fire damage (CFR: 43.5) 2 1 3 K/A Category Totals: Group Point Total:

NUREG-1021, Revision 9

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Waterford 3 Date of Exam: 11/12/2004 Category K/A # Topic RO SRO-Only IR # IR #

Ability to supervise and assume a management role during

1. 94. 2.1.6 4.3 1 plant transients and upset conditions.

(CFR: 43.5)

Conduct of Ability to evaluate plant performance and make operational Operations 95. 2.1.7 4.4 1 judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 43.5)

Subtotal 2 Knowledge of tagging and clearance procedures.

2. 96. 2.2.13 3.8 1 (CFR: 43.2)

Knowledge of new and spent fuel movement procedures. l Equipment 97. 2.2.28 3.5 1 (CFR: 43.7)

Control Subtotal 2 Knowledge of SRO responsibilities for auxiliary systems

3. 98. 2.3.3 2.9 1 that are outside the control room (e.g., waste disposal and handling systems).

Radiation (CFR: 43.4)

Control Knowledge of the process for performing a containment 3.4

99. 2.3.9 1 purge.

(CFR: 43.4)

Subtotal 2 Knowledge of the emergency plan. 4.0

4. 100. 2.4.29 1 (CFR: 43.5)

Emergency Subtotal 1 Procedures/

Plan Tier 3 Point Total 7 NUREG-1021, Revision 9