ML070530063

Init Exam - 11/2006 - Draft Outlines

ML070530063
Person / Time
Site:	Waterford
Issue date:	11/10/2006
From:	NRC Region 4
To:	Entergy Operations
References
50-285/06-301
Download: ML070530063 (31)

Text

ES-401 Record of Rejected K/As Form ES-401-4 Waterford 3 11/10/2006 Tier / Group Randomly Selected K/A Reason for Rejection 1/2 RO 003/AK3.03 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Turbine automatic runback with reactor in order to balance power output.

Rejected due to KA not applicable to Waterford 3 and similarities with Operating Test.

Replaced with 005/AK3.04 2/2 RO 028/K2.01 Knowledge of bus power supplies to the following:

Hydrogen Recombiners.

Rejected due to over sampling of power supply K/As. A3 was not originally selected for Tier 2 gr oup 2, No A3 K/As existed for 028.

Replaced with 041/A3.02 1/1 SRO 054/AA2.02 Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Differentiation between loss of all MFW and trip of one MFW pump. Rejected due to similarity with Operational Exam.

Replaced with AA2.06 2/1 SRO 061/A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the

consequences of those malfuncti ons or operations: Startup of MFW pump during AFW operation. Rejected due to Low Operational value for discriminatory SRO

level question.

Replaced with A2.03 NUREG-1021, Revision 9

Facility: RO / SRO 07/11/2006 Waterford 3 Printed: IMPORTANCE Suppressed K/As Basis 025 Ice Condenser System Knowledge of the physical connections and/or cause-effect relationships between the Ice Condenser System and the following systems:

K1 K1.01 Containment ventilation 2.7*/2.7*K1.02 Refrigerant systems 2.7*/2.7*K1.03 Containment sump system 3.2*/3.0*K2.01 Containment ventilation fans and dampers 2.2*/2.7*K2.02 Refrigerant systems 2.0*/2.5*K2.03 Isolation valves 2.0*/2.2*K3.01 Containment 3.8*/3.8*K4.01 Glycol expansion tank levels and ice condenser system containment isolation valves 2.2*/2.5*K4.02 System control 2.8*/3.0*K5.01 Relationships between pressure and temperature 3.0*/3.4*K5.02 Heat transfer 2.6*/2.8*K5.03 Gas laws 2.4*/2.8*K6.01 Upper and lower doors of the ice condenser 3.4*/3.6*A1.01 Temperature chart recorders 3.0*/3.0*A1.02 Glycol expansion tank level 2.5*/2.2*A1.03 Glycol flow to ice condenser air handling units 2.5*/2.5*A2.01 Trip of glycol circulation pumps 2.2*/2.7*A2.02 High/low floor cooling temperature 2.7*/2.5*A2.03 Opening of ice condenser doors 3.0*/3.2*A2.04 Containment isolation 3.0*/3.2*A2.05 Abnormal glycol expansion tank level 2.5*/2.7*A2.06 Decreasing ice condenser temperature 2.5*/2.7*A3.01 Refrigerant system 3.0*/3.0*A3.02 Isolation valves 3.4*/3.4*A4.01 Ice condenser isolation valves 3.0*/2.7*A4.02 Containment vent fans 2.7*/2.5*A4.03 Glycol circulation pumps 2.2*/2.2*2.1.1 Knowledge of conduct of operations requirements.

3.7/3.8 2.1.10 Knowledge of conditions and limitations in the facility license.

2.7/3.9 2.1.11 Knowledge of less than one hour technical specification action statements for systems.

3.0/3.8 2.1.12 Ability to apply technical specifications for a system.

2.9/4.0 2.1.13 Knowledge of facility requirements for controlling vital / controlled access.

2.0/2.9 2.1.14 Knowledge of system status criteria which require the notification of plant personnel.

2.5/3.3 2.1.15 Ability to manage short-term information such as night and standing orders.

2.3/3.0 2.1.16 Ability to operate plant phone, paging system, and two-way radio.

2.9/2.8 2.1.17 Ability to make accurate, clear and concise verbal reports.

3.5/3.6 2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports.

2.9/3.0 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status.

3.0/3.0 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

3.0/4.0 1 Facility: RO / SRO 07/11/2006 Waterford 3 Printed: IMPORTANCE Suppressed K/As Basis 025 Ice Condenser System Conduct of Operations 2.1 2.1.20 Ability to execute procedure steps.

4.3/4.2 2.1.21 Ability to obtain and verify controlled procedure copy.

3.1/3.2 2.1.22 Ability to determine Mode of Operation.

2.8/3.3 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

3.9/4.0 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

2.8/3.1 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

2.8/3.1 2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.2/2.6 2.1.27 Knowledge of system purpose and or function.

2.8/2.9 2.1.28 Knowledge of the purpose and function of major system components and controls.

3.2/3.3 2.1.29 Knowledge of how to conduct and verify valve lineups.

3.4/3.3 2.1.3 Knowledge of shift turnover practices.

3.0/3.4 2.1.30 Ability to locate and operate components, including local controls.

3.9/3.4 2.1.31 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

4.2/3.9 2.1.32 Ability to explain and apply all system limits and precautions.

3.4/3.8 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

3.4/4.0 2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.

2.3/2.9 2.1.4 Knowledge of shift staffing requirements.

2.3/3.4 2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities.

2.3/3.4 2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions.

2.1/4.3 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

3.7/4.4 2.1.8 Ability to coordinate personnel activities outside the control room.

3.8/3.6 2.1.9 Ability to direct personnel activities inside the control room.

2.5/4.0 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

3.7/3.6 2.2.10 Knowledge of the process for determining if the margin of safety, as defined in the basis of any technical specification is reduced by a proposed change, test or experiment.

1.9/3.3 2.2.11 Knowledge of the process for controlling temporary changes.

2.5/3.4*2.2.12 Knowledge of surveillance procedures.

3.0/3.4 2.2.13 Knowledge of tagging and clearance procedures.

3.6/3.8 2.2.14 Knowledge of the process for making configuration changes.

2.1/3.0 2.2.15 Ability to identify and utilize as-built design and configuration change documentation to ascertain expected current plant configuration and operate the plant.

2.2/2.9 2.2.16 Knowledge of the process for making of field changes.

1.9/2.6*2.2.17 Knowledge of the process for managing maintenance activities during power operations.

2.3/3.5 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations.

2.3/3.6 2.2.19 Knowledge of maintenance work order requirements.

2.1/3.1 2 Facility: RO / SRO 07/11/2006 Waterford 3 Printed: IMPORTANCE Suppressed K/As Basis 025 Ice Condenser System Equipment Control 2.2 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

4.0/3.5 2.2.20 Knowledge of the process for managing troubleshooting activities.

2.2/3.3 2.2.21 Knowledge of pre- and post-maintenance operability requirements.

2.3/3.5 2.2.22 Knowledge of limiting conditions for operations and safety limits.

3.4/4.1 2.2.23 Ability to track limiting conditions for operations.

2.6/3.8 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

2.6/3.8 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

2.5/3.7 2.2.26 Knowledge of refueling administrative requirements.

2.5/3.7 2.2.27 Knowledge of the refueling process.

2.6/3.5 2.2.28 Knowledge of new and spent fuel movement procedures.

2.6/3.5 2.2.29 Knowledge of SRO fuel handling responsibilities.

1.6/3.8 2.2.3 (multi-unit) Knowledge of the design, procedural, and operational differences between units.3.1/3.3 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

3.5/3.3 2.2.31 Knowledge of procedures and limitations involved in initial core loading.

2.2/2.9*2.2.32 Knowledge of the effects of alterations on core configuration.

2.3/3.3 2.2.33 Knowledge of control rod programming.

2.5/2.9 2.2.34 Knowledge of the process for determining the internal and external effects on core reactivity.

2.8/3.2*2.2.4 (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

2.8/3.0*2.2.5 Knowledge of the process for making changes in the facility as described in the safety analysis report.

1.6/2.7 2.2.6 Knowledge of the process for making changes in procedures as described in the safety analysis report.

2.3/3.3 2.2.7 Knowledge of the process for conducting tests or experiments not described in the safety analysis report.

2.0/3.2 2.2.8 Knowledge of the process for determining if the proposed change, test, or experiment involves an unreviewed safety question.

1.8/3.3 2.2.9 Knowledge of the process for determining if the proposed change, test or experiment increases the probability of occurrence or consequences of an accident during the change, test or experiment.

2.0/3.3 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

2.6/3.0 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

2.9/3.3 2.3.11 Ability to control radiation releases.

2.7/3.2 2.3.2 Knowledge of facility ALARA program.

2.5/2.9 2.3.3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control room (e.g., waste disposal and handling systems).

1.8/2.9 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

2.5/3.1 3 Facility: RO / SRO 07/11/2006 Waterford 3 Printed: IMPORTANCE Suppressed K/As Basis 025 Ice Condenser System Radiological Controls 2.3 2.3.5 Knowledge of use and function of personnel monitoring equipment.

2.3/2.5 2.3.6 Knowledge of the requirements for reviewing and approving release permits.

2.1/3.1 2.3.7 Knowledge of the process for preparing a radiation work permit.

2.0/3.3 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.

2.3/3.2 2.3.9 Knowledge of the process for performing a containment purge.

2.5/3.4 2.4.1 Knowledge of EOP entry conditions and immediate action steps.

4.3/4.6 2.4.10 Knowledge of annunciator response procedures.

3.0/3.1 2.4.11 Knowledge of abnormal condition procedures.

3.4/3.6 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.

3.4/3.9 2.4.13 Knowledge of crew roles and responsibilities during EOP flowchart use.

3.3/3.9 2.4.14 Knowledge of general guidelines for EOP flowchart use.

3.0/3.9 2.4.15 Knowledge of communications procedures associated with EOP implementation.

3.0/3.5 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures.

3.0/4.0 2.4.17 Knowledge of EOP terms and definitions.

3.1/3.8 2.4.18 Knowledge of the specific bases for EOPs.

2.7/3.6 2.4.19 Knowledge of EOP layout, symbols, and icons.

2.7/3.7 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. Note: The issue of setpoints and automatic safety features is not specifically covered in the systems sections.

3.9/4.1 2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes.

3.3/4.0 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions including: 1. Reactivity control; 2. Core cooling and heat removal; 3. Reactor coolant system integrity; 4. Containment conditions; 5. Radioactivity release control.

3.7/4.3 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

3.0/4.0 2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

2.8/3.8 2.4.24 Knowledge of loss of cooling water procedures.

3.3/3.7 2.4.25 Knowledge of fire protection procedures.

2.9/3.4 2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

2.9/3.3 2.4.27 Knowledge of fire in the plant procedure.

3.0/3.5 2.4.28 Knowledge of procedures relating to emergency response to sabotage.

2.3/3.3 2.4.29 Knowledge of the emergency plan.

2.6/4.0 2.4.3 Ability to identify post-accident instrumentation.

3.5/3.8 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.

2.2/3.6 2.4.31 Knowledge of annunciators alarms and indications, and use of the response instructions.

3.3/3.4 2.4.32 Knowledge of operator response to loss of all annunciators.

3.3/3.5 2.4.33 Knowledge of the process used track inoperable alarms.

2.4/2.8 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications.

3.8/3.6 4 Facility: RO / SRO 07/11/2006 Waterford 3 Printed: IMPORTANCE Suppressed K/As Basis 025 Ice Condenser System Emergency Procedures/Plan 2.4 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications.

3.3/3.5 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.

2.0/2.8 2.4.37 Knowledge of the lines of authority during an emergency.

2.0/3.5 2.4.38 Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator.

2.2/4.0 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.

3.3/3.1 2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

4.0/4.3 2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation.

2.3/4.0 2.4.41 Knowledge of the emergency action level thresholds and classifications.

2.3/4.1 2.4.42 Knowledge of emergency response facilities.

2.3/3.7 2.4.43 Knowledge of emergency communications systems and techniques.

2.8/3.5 2.4.44 Knowledge of emergency plan protective action recommendations.

2.1/4.0 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

3.3/3.6 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

3.5/3.6 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

3.4/3.7 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.

3.5/3.8 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

4.0/4.0 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

2.9/3.6 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

3.3/3.3 2.4.6 Knowledge symptom based EOP mitigation strategies.

3.1/4.0 2.4.7 Knowledge of event based EOP mitigation strategies.

3.1/3.8 2.4.8 Knowledge of how the event-based emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs.

3.0/3.7 2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

3.3/3.9 5 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. Reset CSAS Actuation D, S 7 h. 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 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 of Dropped Rod A, D, P, S 1 b. Perform Actions on a Recirculation Actuation A, D, L, P, S 2 c. ATC immediate Operator Actions on CR evacuation A, 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 A, D, S 6 g. Reset CSAS Actuation D, S 7 h. Restoration From Control Room Isolation D, 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 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 E S-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 Perform OP-004-015 Attachment 11.1 Manual CEA Subgroup Selection. Conduct of Operations R, N Evaluate Proposed Work Schedule Against Established Overtime Guidelines Equipment Control R, N Perform OP-903-001 Attachment 11.15 Containment Pressure calculation. Radiation Control R,N Determine Stay Times to Operate Equipment in a High Dose Field. 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)

A ppendix 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 No. Malf. No. Event Type*

Event Description 1 NI01G I(ALL) After the crew takes the shift ENI Channel C Middle Detector fails low energizing Startup Channel 1. The crew should de-energize SU Channel 1. The crew should enter TS 3.3.1 & 3.3.3.6 and bypass affected trip bistables.

2 RC21A I(ALL) A loop 1 T hot instrument fails low affecting pressurizer level setpoint. This event requires implementation of OP-901-110, Pressurizer Level Malfunction Off-Norma l procedure.

3 CC03A C(BOP/SRO) 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 B side, this will require entry into TS 3.7.3 and cascading TS per OP-100-014. 4 RC08A C(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 with OP-901-130.

5 RP01A RP01B RP01C I(RO) The manual reactor trip will fail and the RO will trip the reactor by alternate means.

6 FW07B I(BOP) EFW Pump B will fail to auto start, requiring the BOP to manually start the pump.

7 SG01A (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 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 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 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 containment 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 A ppendix D Scenario Outline Form ES-D-1 Facility: Waterford III Scenario No.: 1 Op-Test No.: 1 Examiners:

Operators:

Initial Conditions: IC-19 70%, 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 C(BOP) M(ALL) 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.

8 FW05 C(BOP/SRO) 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 may be used to

feed SGs. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 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 K1 K 2 K3 K4 K5 K6 A1 A2 A3 A4 G

• Total A2 G* TOTAL 1 3 3 6 2 2 2 4 1. Emergency

& Abnormal Plant Evolutions Tier Totals 5 5 10 1 3 2 5 2 K5 1 1 1 3 2. Plant Systems Tier Totals 5 3 8 1 2 3 4 1 2 3 4 3. Generic Knowledge and Abilities 2 2 2 1 7 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO Outline (i.e., t he "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 specifi ed 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-401-2Emergency 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 x EA2.1 Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery) Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR: 43.5) 3.7 1 77. 000011 Large Break LOCA / 3 x 2.4.1 Knowledge of EOP entry conditions and immediate action steps. (CFR: 43.5) 4.6 1 78. 000026 Loss of Component Cooling Water / 8 operations risk assessment x 2.2.17; Knowledge of the process for managing maintenance 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 x AA2.05 Ability to determine and interpret the following as they apply to the Steam Line Rupture: When ESFAS systems may be secured (CFR: 43.5) 4.5 1 80. 000054 (CE/E06) Loss of Main Feedwater / 4 x AA2.06; Ability to determine and interpret the 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) 4.3 1 81. 000055 Station Blackout / 6 x 2.2.25; Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. (CFR: 43.2) 3.7 1 K/A Category Totals:

3 3 Group Point Total:

6 NUREG-1021, Revision 9 ES-401 PWR Examination Outline Form 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 Rod Withdrawal / 1 x AA2.04 - Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal : Reactor power and its trend (CFR: 43.6) 4.3 1 83. 000037 Steam Generator Tube Leak / 3 x 2.1.34 - Ability to maintain primary and secondary plant chemistry within allowable limits. (CFR: 43.2) 2.9 1 84. 000051 Loss of Condenser Vacuum / 4 x AA2.02;Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip (CFR: 43.5) 4.1 1 85. 000061 ARM System Alarms / 7 x 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. (CFR: 43.4) 3.0 1 K/A Category Totals:

2 2 Group Point Total:

4 NUREG-1021, Revision 9 ES-401 PWR Examination Outline Form ES-401-2 Plant 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 Volume Control x 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. (CFR: 43.2) 4.0 1 87. 007 Pressurizer Relief/ Quench Tank x 2.3.10 - Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (CFR: 43.4) 3.3 1 88. 013 Engineered Safety Features Actuation x A2.04 - Ability to (a) predict the 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; Loss of instrument bus (CFR: 43.2) 4.2 1 89. 061 Auxiliary/Emergency Feedwater x A2.03-Ability to (a) predict the impacts of the following 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) 3.4 1 90. 062 AC Electrical Distribution x A2.12 Ability to (a) predict the impacts of the following 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) 3.6 1 K/A Category Totals:

3 2 Group Point Total:

5 NUREG-1021, Revision 9 ES-401 PWR Examination Outline Form ES-401-2 Plant 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 Handling Equipment x K5.02- Knowledge of the operational implication of the following concepts as they apply to the Fuel Handling System: Limiting of load (CFR: 43.7) 2.6 1 92. 056 Condensate x 2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits. ((CFR: 43.5) 2.9 1 93. 086 Fire Protection x A2.04-Ability to (a) predict the 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) 1 K/A Category Totals:

1 1 1 Group Point Total:

3 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 # 94. 2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions. (CFR: 43.5) 4.3 1 95. 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 43.5) 4.4 1 1. Conduct of Operations Subtotal 2 96. 2.2.13 Knowledge of tagging and clearance procedures. (CFR: 43.2) 3.8 1 97. 2.2.28 Knowledge of new and spent fuel movement procedures. l (CFR: 43.7) 3.5 1 2. Equipment Control Subtotal 2 98. 2.3.3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control room (e.g., waste disposal and handling systems). (CFR: 43.4) 2.9 1 99. 2.3.6 Knowledge of the requirements for reviewing and approving release permits. (CFR: 43.4) 3.1 1 3. Radiation Control Subtotal 2 100.2.4.29 Knowledge of the emergency plan. (CFR: 43.5) 4.0 1 4. Emergency Procedures/

Plan Subtotal 1 Tier 3 Point Total 7

NUREG-1021, Revision 91ES-401 PWR RO Examination Outline Form ES-401-2Facility:Waterford 3Date of Exam: 11/10/2006RO K/A Category PointsSRO - Only PointsTierGroupK1K2K3K4K5K6A1A2A3A4G*TotalA2G*TOTAL1333333331821 222 122191.Emergency &Abnormal PlantEvolutionsTier Totals4 555 45542713233223322328210111111111102.PlantSystemsTierTotals4244334433438123412343. Generic Knowledge and Abilities323210Note: 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 92ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR #1.00007 (BW/E02 & E10;CE/E02) Reactor Trip -Stabilization - Recovery / 1xEK1.02 - Knowledge of the operationalimplications of the following concepts asthey apply to the reactor trip:Shutdown margin(CFR: 41.10)3.4 12.00008 Pressurizer VaporSpace Accident / 3x2.2.34 - Knowledge of the process fordetermining the internal and external effects oncore reactivity.(CFR: 41.1)2.8 13.000009 Small Break LOCA / 3 xEK3.16 - Knowledge of the reasons for thefollowing responses as the apply to thesmall break LOCA:Containment temperature, pressure, humidity andlevel limits(CFR: 41.5)3.814.000011 Large Break LOCA / 3 xEK2.02 - Knowledge of the interrelationsbetween a Large Break LOCA and the following:Pumps(CFR 41.7)2.6 15.000015/17 RCP Malfunctions / 4xAA2.02 - Ability to determine and interpret thefollowing as they apply to the Reactor CoolantPump Malfunctions (Loss of RC Flow):Abnormalities in RCP air vent flow paths and/oroil cooling system(CFR: 41.14)2.816.000022 Loss of Rx CoolantMakeup / 2x2.1.24 - Ability to obtain and interpret stationelectrical and mechanical drawings.(CFR: 41.3)2.817.000025 Loss of RHR System / 4 xAA1.01 - Ability to operate and / or monitor thefollowing as they apply to the Loss of ResidualHeat Removal System:RCS/RHRS cooldown rate(CFR 41.7)3.6 18.000026 Loss of ComponentCooling Water / 8 xAA1.07 - Ability to operate and / or monitor thefollowing as they apply to the Loss of ComponentCooling Water:Flow rates to the components and systems thatare serviced by the CCWS; interactions amongthe components(CFR 41.7 )2.9 19.000027 Pressurizer PressureControl System Malfunction / 3xAK1.01 - Knowledge of the operationalimplications of the following concepts asthey apply to Pressurizer Pressure ControlMalfunctions:Definition of saturation temperature(CFR 41.14 )3.1 110.000029 ATWS / 1 xEK2.06 - Knowledge of the interrelationsbetween the and the following an ATWS:Breakers, relays, and disconnects(CFR 41.6 )2.9 111.000038 Steam Gen. TubeRupture / 3xEK1.01 - Knowledge of the operationalimplications of the following concepts asthey apply to the SGTR:Use of steam tables (CFR 41.10)3.1 1 NUREG-1021, Revision 93ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR #12.000040 (BW/E05; CE/E05;W/E12)Steam Line Rupture - ExcessiveHeat Transfer / 4 xEK3.3 - Knowledge of the reasons for thefollowing responses as they apply tothe (Excess Steam Demand):Manipulation of controls required to obtaindesired operating results during abnormal, andemergency situations(CFR: 41.5)3.8 113.000054 (CE/E06) Loss of MainFeedwater / 4 xEK2.1 -Knowledge of the interrelations betweenthe (Loss of Feedwater) andthe following:Components, and functions of control and safetysystems, including instrumentation, signals,interlocks, failure modes, and automatic andmanual features(CFR: 41.7)3.3 114.000055 Station Blackout / 6x2.4.20- Knowledge of operational implications ofEOP warnings, cautions, and notes. (CFR: 41.10)3.3 115.000056 Loss of Off-site Power /6xAA2.38 - Ability to determine and interpret thefollowing as they apply to the Loss of OffsitePower:Load sequencer status lights(CFR: 41.7)3.7 116.000057 Loss of Vital AC Inst.Bus / 6 xAK3.01 - Knowledge of the reasons for thefollowing responses as they apply to the Loss ofVital AC Instrument Bus:Actions contained in EOP for loss of vital acelectrical instrument bus(CFR; 41.10)4.1117.000058 Loss of DC Power / 6 xAA1.03 - Ability to operate and / or monitor thefollowing as they apply to the Loss of DC Power:Vital and battery bus components(CFR 41.7)3.1 118.000065 Loss of Instrument Air /8xAA2.06 - Ability to determine and interpret thefollowing as they apply to the Loss of InstrumentAir:When to trip reactor if instrument air pressure isde-creasing(CFR: 41.10)3.6*1K/A Category Totals:3 3 3 333Group Point Total:18 NUREG-1021, Revision 94ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR #19.000005 Inoperable/StuckControl Rod / 1 xAK3.04-Knowledge of the reasons for thefollowing responses as they apply to theInoperable / Stuck Control Rod:Tech-Spec limits for inoperable rods.(CFR 41.2)3.4 120.000024 Emergency Boration / 1 xAK2.04 - Knowledge of the interrelationsbetween the Emergency Boration and thefollowing:Pumps(CFR 41.8 )2.6 121.000033 Loss of IntermediateRange NI / 7xAK1.01 -Knowledge of the operationalimplications of the following concepts asthey apply to Loss of Intermediate Range NuclearInstrumentation:Effects of voltage changes on performance(CFR 41.2 )2.7 122.000036 (BW/A08) FuelHandling Accident / 8 xAA1.01 - Ability to operate and / or monitor thefollowing as they apply to the Fuel HandlingIncidents:Reactor building containment purge ventilationsystem(CFR 41.13 )3.3 123.000059 Accidental LiquidRadWaste Rel. / 9xAA2.02 - Ability to determine and interpret thefollowing as they apply to the Accidental LiquidRadwaste Release:The permit for liquid radioactive-waste release(CFR: 41.13)2.9 124.000069 (W/E14) Loss of CTMTIntegrity / 5xAA2.01 - Ability to determine and interpret thefollowing as they apply to the Loss ofContainment Integrity:Loss of containment integrity(CFR: 41.9)3.7 125.000074 Inadequate CoreCooling/ 4 xEK2.06 - Knowledge of the interrelationsbetween Inadequate Core Cooling and thefollowing:Turbine bypass and atmospheric dump valves(CFR 41.5 )3.5*126.CE/A16 Excess RCS Leakage /2x2.4.10 - Knowledge of annunciator responseprocedures.(CFR: 41.10 )3.0 127.CE/E09 Functional Recovery xEK3.2 - Knowledge of the reasons for thefollowing responses as they apply to the(Functional Recovery): Normal, abnormal and emergency operatingprocedures associated with (Functional Recovery)(CFR: 41.10)3.0 1K/A Category Totals:1 2 2 121Group Point Total:9 NUREG-1021, Revision 95ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2 / Group 1 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR #28.003 Reactor CoolantPump xA1.09 - Ability to predict and/ormonitor changes in parameters (toprevent exceeding design limits)associated with operating theRCPS controls including:Seal flow and D/P(CFR: 41.5)2.8129.004 Chemical andVolume Control xK6.05 - Knowledge of the effectof a loss or malfunction on thefollowing CVCS components:Sensors and detectors (CFR: 41.7)2.5130.005 Residual HeatRemoval xK5.05 - Knowledge of theoperational implications of thefollowing concepts as theyapply the RHRS:Plant response during "solidplant": pressure change due to therelative incompressibility of water(CFR: 41.5)2.7*131.006 Emergency CoreCoolingxK1.08 - Knowledge of thephysical connections and/or causeeffect relationships between theECCS and the following systems:CVCS(CFR: 41.6)3.6132.006 Emergency CoreCooling xA3.05 - Ability to monitorautomatic operation of the ECCS,including:Safety Injection Pump(CFR: 41.7 )4.2133.007 Pressurizer Relief/Quench Tank xA1.01 - Ability to predict and/ormonitor changes in parameters (toprevent exceeding design limits)associated with operating thePRTS controls including:Maintaining quench tank waterlevel within limits(CFR: 41.5)2.9134.008 Component CoolingWater xK2.02 - Knowledge of bus powersupplies to the following: CCWpump, including emergencybackup(CFR: 41.7)3.0*135.010 Pressurizer PressureControl xK3.03 - Knowledge of the effectthat a loss or malfunction of thePZR PCS will have on thefollowing:ESFAS(CFR: 41.7)4.0136.012 Reactor Protection xA3.04 - Ability to monitorautomatic operation of the RPS,including:Circuit breaker(CFR: 41.6 )2.8*1 NUREG-1021, Revision 96ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2 / Group 1 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR #37.012 Reactor Protection xK6.09- Knowledge of the effectof a loss or malfunction of thefollowing will have on the RPS:CEAC(CFR: 41.6)3.6138.013 Engineered SafetyFeatures Actuation xK3.01 - Knowledge of the effectthat a loss or malfunction of theESFAS will have on thefollowing:Fuel(CFR: 41.2)4.4139.022 Containment CoolingxA2.01 - Ability to (a) predict theimpacts of the followingmalfunctions or operationson the CCS; and (b) based onthose predictions, use proceduresto correct,control, or mitigate theconsequences of thosemalfunctions or operations:Fan motor over-current(CFR: 41.5)2.5 140.022 Containment Cooling xA4.04 - Ability to manuallyoperate and/or monitor in thecontrol room:Valves in the CCS(CFR: 41.7)3.1 141.026 Containment SprayxK1.02 - Knowledge of thephysical connections and/or causeeffect relationships between theCSS and the following systems:Cooling water(CFR: 41.8)4.1142.039 Main and ReheatSteam xK5.01 - Knowledge of theoperational implications of thefollowing concepts as they applyto the MRSS:Definition and causes of steam/water hammer(CFR: 41.14)2.9143.059 Main FeedwaterxA2.03 - Ability to (a) predict theimpacts of the followingmalfunctions or operationson the MFW; and (b) based onthose predictions, use proceduresto correct, control, or mitigate theconsequences of thosemalfunctions or operations:Overfeeding event(CFR: 41.5)2.71 NUREG-1021, Revision 97ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2 / Group 1 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR #44.061 Auxiliary/EmergencyFeedwaterxK1.03 - Knowledge of thephysical connections and/or causeeffect relationships between theAFW and the following systems:Main steam system(CFR: 41.4)3.5145.062 AC ElectricalDistribution xK4.10 - Knowledge of acdistribution system designfeature(s) and/or interlock(s)which provide for the following:Uninterruptible ac power sources(CFR: 41.7)3.1146.063 DC ElectricalDistribution xK4.04 - Knowledge of DCelectrical system design feature(s)and/ or interlock(s) which providefor the following:Trips(CFR: 41.7)2.6?147.063 DC ElectricalDistribution xA4.03 - Ability to manuallyoperate and/or monitor in thecontrol room:Battery discharge rate(CFR: 41.8)3.0*148.064 Emergency DieselGenerator xK4.02 - Knowledge of ED/Gsystem design feature(s) and/orinterlock( s) which provide for thefollowing:Trips for ED/G while operating(normal or emergency)(CFR: 41.7)3.9149.073 Process RadiationMonitoringxA2.02 - Ability to (a) predict theimpacts of the followingmalfunctions or operations on thePRM system; and(b) based on those predictions,use procedures to correct,control, or mitigate theconsequences of thosemalfunctions or operations:Detector failure(CFR: 41.11)2.7150.073 Process RadiationMonitoringx2.4.48 -Ability to interpret controlroom indications to verify thestatus andoperation of system, andunderstand how operator actionsand directivesaffect plant and systemconditions.(CFR: 43.12)4.01 NUREG-1021, Revision 98ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2 / Group 1 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR #51.076 Service Water xA1.02 - Ability to predict and/ormonitor changes in parameters(to prevent exceeding designlimits) associated withoperating the SWS controlsincluding:Reactor and turbine buildingclosed cooling water temperatures(CFR: 41.5)2.6*152.078 Instrument Air xK2.01 - Knowledge of bus powersupplies to the following:Instrument air compressor(CFR: 41.7)2.7153.078 Instrument Airx2.1.28- Knowledge of the purposeand function of major systemcomponents and controls.(CFR: 41.7)3.2154.103 Containment xK3.01 - Knowledge of the effectthat a loss or malfunction of thecontainment system will have onthe following:Loss of containment integrityunder shutdown conditions(CFR: 41.9)3.3*155.103 Containmentx2.1.29 - Knowledge of how toconduct and verify valve lineups.(CFR: 41.9)3.41K/A Category Totals:3 2 3 3 2 2 33 2 23Group Point Total: 28 NUREG-1021, Revision 99ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2 / Group 2 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR #56.001 Control Rod Drive xK3.02- Knowledge of the effectthat a loss or malfunction of theCRDS will have on the following:RCS(CFR: 41.6)3.4*157.002 Reactor Coolant xA4.03 - Ability to manuallyoperate and/or monitor in thecontrol room:Indications necessary to verifynatural circulation fromappropriate level, flow, andtemperature indications and valvepositions upon loss of forcedcirculation(CFR: 41.5)4.3158.011 Pressurizer LevelControl xA1.04-Ability to predict and/ormonitor changes in parameters(to prevent exceeding designlimits) associated withoperating the PZR LCS controlsincluding:Tave(CFR: 41.5)3.1159.015 NuclearInstrumentation xK6.03 - Knowledge of the effectof a loss or malfunction on thefollowing will have on the NIS:Component interconnections(CFR: 41.2)2.6160.016 Non-nuclearInstrumentationx2.1.33 - Ability to recognizeindications for system operatingparameters which are entry-levelconditions for technicalspecifications.(CFR: 41.5)3.4161.029 Containment PurgexA2.04 - Ability to (a) predict theimpacts of the followingmalfunctions or operations on theContainment Purge System; and(b) based on those predictions,use procedures to correct, control,or mitigatethe consequences of thosemalfunctions or operations:Health physics sampling ofcontainment atmosphere(CFR: 41.9)2.5 162.033 Spent Fuel PoolCoolingHVF xK4.04 -Knowledge of designfeature(s) and/or interlock(s)which provide for the following:Maintenance of spent fuel poolradiation(CFR: 41.7)2.7 1 NUREG-1021, Revision 910ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2 / Group 2 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR #63.041 Steam Dump/TurbineBypass Control xA3.02-Ability to monitorautomatic operation of the SDS,including:RCS pressure, RCS temperature,and reactor power.(CFR: 41.5)3.3 164.071 Waste Gas Disposal xK5.04 - Knowledge of theoperational implication of thefollowing concepts as theyapply to the Waste Gas DisposalSystem:Relationship hydrogen/ oxygenconcentrations to flammability(CFR: 41.13)2.5 165.072 Area RadiationMonitoringxK1.05 - Knowledge of thephysical connections and/or causeeffect relationships between theARM system and the followingsystems:MRSS(CFR: 41.11)2.8*1K/A Category Totals:1 0 1 1 1 1 11 1 11Group Point Total:10 NUREG-1021, Revision 911ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3Facility Waterford 3Date of Exam: 11/12/2004CategoryK/A #TopicROSRO-OnlyIR#IR#66.2.1.10 Knowledge of conditions and limitations in the facilitylicense.(CFR: 41.5)2.7167.2.1.25Ability to obtain and interpret station reference materialssuch as graphs, monographs, and tables which containperformance data.(CFR: 41.10)2.8168.2.1.32Ability to explain and apply all system limits andprecautions.(CFR: 41.5)3.411.Conduct ofOperationsSubtotal369.2.2.27Knowledge of the refueling process.(CFR: 41.13)2.6170.2.2.34Knowledge of the process for determining the internaland external effects on core reactivity.(CFR: 41.1)2.812.EquipmentControlSubtotal271.2.3.2Knowledge of facility ALARA program.(CFR: 41.12)2.5172.2.3.4Knowledge of radiation exposure limits andcontamination control, including permissible levels inexcess of those authorized.(CFR: 41.12)2.5173.2.3.11Ability to control radiation releases.(CFR: 41.13)2.713.Radiation ControlSubtotal374.2.4.17 Knowledge of EOP terms and definitions.(CFR: 41.10)3.1175.2.4.45Ability to prioritize and interpret the significance of eachannunciator or alarm.(CFR: 43.7)3.314.EmergencyProcedures/ PlanSubtotal2Tier 3 Point Total10 Written Outline K/A Selection Methodology The following were used to generate the writ ten examination outlin es for the RO and SRO subjects: Westinghouse Owners Group, PWR K/A DATABASE PROGRAM, JUNE 2005 VERSION 2.2.3, CE Plant Version, De veloped by WD Associates for the Westinghouse Owners Group (WOG), PA-OSC-0059 All K/As for the Ice Condenser system were suppressed. This system is not part of Waterford 3's design. The program filters a ll K/As < 2.5 for the applicable exam level. No other K/As were suppressed. This resulted in some K/As being replaced using a rand om number generator.

Waterford III used the following methodology for manually selecting replacement Knowledge/Ability (K/A) statements:

1. Selected Knowledge/Ab ility/Generic groups (K1-6, A1-4) should only be changed: If no other K/A statements exist fo r the associated subject in the selected Knowledge/Abil ity/Generic group with a rating of > 2.5, If no other K/A statements exist for the associated subject within the Knowledge/Ability/Generic group which are appropriate to be tested on the written examination, To prevent low coverage of Knowledge/Ability/Generic groups. To prevent over-sampling between written and operating tests. 2. Using a random number gener ator select a K/

A statement (for example K1.01, or 2.1.1) for each of the applicable K/A statements to be replaced. The K/A statement must have an impor tance rating of > 2.5 an d must be appropriate to be tested on the wri tten examination.

3. K/A statements maybe replaced to ensure representative sampling of 10CFR55 requirements.