ML070530063

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Init Exam - 11/2006 - Draft Outlines
ML070530063
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/10/2006
From:
NRC Region 4
To:
Entergy Operations
References
50-285/06-301
Download: ML070530063 (31)
v • d • e


Text

ES-401 Record of Rejected K/As Form ES-401-4 Waterford 3 11/10/2006 Tier / Randomly Group 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 group 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 malfunctions 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

Suppressed K/As Printed: 07/11/2006 Facility: Waterford 3 IMPORTANCE Basis RO / SRO 025 Ice Condenser System K1 Knowledge of the physical connections and/or cause-effect relationships between the Ice Condenser System and the following systems:

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 3.0/3.0 component status.

2.1.2 Knowledge of operator responsibilities during all modes of plant operation. 3.0/4.0 1

Suppressed K/As Printed: 07/11/2006 Facility: Waterford 3 IMPORTANCE Basis RO / SRO 025 Ice Condenser System 2.1 Conduct of Operations 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 3.9/4.0 plant operation.

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, 2.8/3.1 and tables which contain performance data.

2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment, electrical, high 2.2/2.6 temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

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 4.2/3.9 they are correctly reflecting the desired plant lineup.

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 3.4/4.0 conditions for technical specifications.

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 2.1/4.3 conditions.

2.1.7 Ability to evaluate plant performance and make operational judgments based on 3.7/4.4 operating characteristics, reactor behavior, and instrument interpretation.

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 3.7/3.6 controls associated with plant equipment that could affect reactivity.

2.2.10 Knowledge of the process for determining if the margin of safety, as defined in the basis 1.9/3.3 of any technical specification is reduced by a proposed change, test or experiment.

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 2.2/2.9 ascertain expected current plant configuration and operate the plant.

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 2.3/3.6 operations.

2.2.19 Knowledge of maintenance work order requirements. 2.1/3.1 2

Suppressed K/As Printed: 07/11/2006 Facility: Waterford 3 IMPORTANCE Basis RO / SRO 025 Ice Condenser System 2.2 Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between 4.0/3.5 shutdown and designated power levels.

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 2.5/3.7 safety limits.

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 3.1/3.3 units.

2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from 3.5/3.3 fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

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 2.8/3.2*

reactivity.

2.2.4 (multi-unit) Ability to explain the variations in control board layouts, systems, 2.8/3.0*

instrumentation and procedural actions between units at a facility.

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

2.2.6 Knowledge of the process for making changes in procedures as described in the safety 2.3/3.3 analysis report.

2.2.7 Knowledge of the process for conducting tests or experiments not described in the safety 2.0/3.2 analysis report.

2.2.8 Knowledge of the process for determining if the proposed change, test, or experiment 1.8/3.3 involves an unreviewed safety question.

2.2.9 Knowledge of the process for determining if the proposed change, test or experiment 2.0/3.3 increases the probability of occurrence or consequences of an accident during the change, test or experiment.

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 2.9/3.3 personnel exposure.

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 1.8/2.9 room (e.g., waste disposal and handling systems).

2.3.4 Knowledge of radiation exposure limits and contamination control, including 2.5/3.1 permissible levels in excess of those authorized.

3

Suppressed K/As Printed: 07/11/2006 Facility: Waterford 3 IMPORTANCE Basis RO / SRO 025 Ice Condenser System 2.3 Radiological Controls 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 3.0/4.0 procedures.

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 3.9/4.1 entry conditions. Note: The issue of setpoints and automatic safety features is not specifically covered in the systems sections.

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 3.7/4.3 including: 1. Reactivity control; 2. Core cooling and heat removal; 3. Reactor coolant system integrity; 4. Containment conditions; 5. Radioactivity release control.

2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency 3.0/4.0 operations.

2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during 2.8/3.8 emergency operations.

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 2.9/3.3 fighting equipment usage.

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 2.2/3.6 outside agencies.

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 3.8/3.6 operations including system geography and system implications.

4

Suppressed K/As Printed: 07/11/2006 Facility: Waterford 3 IMPORTANCE Basis RO / SRO 025 Ice Condenser System 2.4 Emergency Procedures/Plan 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including 3.3/3.5 system geography and system implications.

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) 2.2/4.0 supporting or acting as emergency coordinator.

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 4.0/4.3 entry-level conditions for emergency and abnormal operating procedures.

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 3.4/3.7 appropriate control room reference material.

2.4.48 Ability to interpret control room indications to verify the status and operation of system, 3.5/3.8 and understand how operator actions and directives affect plant and system conditions.

2.4.49 Ability to perform without reference to procedures those actions that require immediate 4.0/4.0 operation of system components and controls.

2.4.5 Knowledge of the organization of the operating procedures network for normal, 2.9/3.6 abnormal, and emergency evolutions.

2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm 3.3/3.3 response manual.

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 3.0/3.7 in conjunction with the symptom-based EOPs.

2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of 3.3/3.9 RHR) mitigation strategies.

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 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 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 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 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 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 Evaluate Proposed Work Schedule Against Established Overtime R, N Guidelines Equipment Control Perform OP-903-001 Attachment 11.15 Containment Pressure R, N calculation.

Radiation Control Determine Stay Times to Operate Equipment in a High Dose Field.

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)

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

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

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.: 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 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.

ED01A A LOOP occurs 1 minute after the trip, and EDG B Output breaker ED01B fails to close and cannot be closed. The crew will implement SPTAs C(BOP) 7 ED01C and will be directed to OP-902-003.

M(ALL)

ED01D EG09B 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 8 FW05 C(BOP/SRO) 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

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 K3 K4 K5 K6 A1 A2 A3 A4 G Total A2 G* TOTAL 2

1. 1 3 3 6 Emergency

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

2. K5 Plant 2 1 1 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) 2.2.25; Knowledge of bases in technical

81. 000055 Station Blackout / 6 x 3.7 1 specifications for limiting conditions for operations and safety limits.

(CFR: 43.2) 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) 2.1.34 - Ability to maintain primary and
83. 000037 Steam Generator Tube x 2.9 1 secondary plant chemistry within allowable Leak / 3 limits.

(CFR: 43.2)

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 A2.04 - Ability to (a) predict the 4.2

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; Loss of instrument bus (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 K5.02- Knowledge of the

91. 034 Fuel Handling x 1 operational implication of the 2.6 Equipment following concepts as they apply to the Fuel Handling System:

Limiting of load (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 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) 1 1 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 requirements for reviewing and 3.1

99. 2.3.6 1 approving release permits.

(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

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 the 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 Rupture / 3 they 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) 2.4.20- Knowledge of operational implications of

14. 000055 Station Blackout / 6 x 3.3 1 EOP warnings, cautions, and notes.

(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 41.13 )

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 )

A1.01 - Ability to predict and/or 2.9

33. 007 Pressurizer Relief/ x 1 monitor changes in parameters (to Quench Tank prevent exceeding design limits) associated with operating the PRTS controls including:

Maintaining quench tank water level within limits (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 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)

A4.03 - Ability to manually 3.0

47. 063 DC Electrical x 1 operate and/or monitor in the
  • Distribution control room:

Battery discharge rate (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: 43.12)

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) 2.1.29 - Knowledge of how to 3.4

55. 103 Containment x 1 conduct and verify valve lineups.

(CFR: 41.9) 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)

A4.03 - 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)

A2.04 - Ability to (a) predict the

61. 029 Containment Purge x 2.5 1 impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Health physics sampling of containment atmosphere (CFR: 41.9)

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:

HVF 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 2.8 1

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

(CFR: 41.10)

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 2.8 1

70. 2.2.34 Knowledge of the process for determining the internal Control and external effects on core reactivity.

(CFR: 41.1)

Subtotal 2

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

Radiation Control 2.5 1

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

(CFR: 41.12)

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 3.3 1

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

(CFR: 43.7)

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

Written Outline K/A Selection Methodology The following were used to generate the written examination outlines for the RO and SRO subjects:

Westinghouse Owners Group, PWR K/A DATABASE PROGRAM, JUNE 2005 VERSION 2.2.3, CE Plant Version, Developed 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 all 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 random number generator.

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

1. Selected Knowledge/Ability/Generic groups (K1-6, A1-4) should only be changed:

If no other K/A statements exist for the associated subject in the selected Knowledge/Ability/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 generator 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 importance rating of > 2.5 and must be appropriate to be tested on the written examination.
3. K/A statements maybe replaced to ensure representative sampling of 10CFR55 requirements.
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