ML030330002
| ML030330002 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/06/2002 |
| From: | Gody A NRC Region 4 |
| To: | Overbeck G Arizona Public Service Co |
| References | |
| 50-528/02-301, 50-529/02-301, 50-530/02-301 50-528/02-301, 50-529/02-301, 50-530/02-301 | |
| Download: ML030330002 (14) | |
Text
PVNGS 2002 INITIAL LIMITED SENIOR REACTOR OPERATOR LICENSE OPERATING EXAMINATION DRAFT OUTLINE EXAM DATE: 11/18/02 FACILITIES:
PVNGS UNITS 1, 2, & 3 OPERATING EXAM A. CATEGORY A - ADMINISTRATIVE TOPICS OUTLINES ES-301 ADMINISTRATIVE TOPICS OUTLINE Form ES-301-1 Facility:
PVNGS Units 1,2,3 Date of Examination: 11/18/02-11/22/02 Examination Level: LSRO Operating Test Number: ____________
Administrative Topic / Subject Description Method of Evaluation:
- 1. ONE Administrative JPM, or
- 2. TWO Administrative Questions A.1 Shift Staffing Requirements JPM 2.1.5(3.4) Ability to locate and use procedures and directives related to shift staffing and activities.
JPM: Evaluate the working hour history for the oncoming refuel crane operator and the oncoming LSRO and determine whether one or both individuals can work a full dayshift of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Station Reference Material Interpretation JPM 2.1.5(3.4) Ability to locate and use procedures and directives related to shift staffing and activities JPM: In planning to recover a foreign object from the spent fuel pool, identify all controls that are required by the Sensitive Issues Manual.
A.2 FME Control JPM 2.2.18 (3.6) Knowledge of the process for managing maintenance activities during shutdown operations.
JPM: Given that work is ongoing in a FME area, determine what actions must be taken for inadvertently losing an item into a FME area in accordance with 30DP-0WM12.
A.3 Radiation Work Permits JPM 2.3.1 (3.0) Knowledge of 10 CFR: 20 and related facility radiation control requirements.
JPM: Given a copy of the refueling RWP, verify radiological entry requirements for the fuel floor RWP A.4 2.4.29 (4.0) Knowledge of the emergency plan.
PVNGS Facility:
PVNGS Units 1,2,3 Date of Examination: 11/18/02-11/22/02 Examination Level: LSRO Operating Test Number: ____________
Administrative Topic / Subject Description Method of Evaluation:
- 1. ONE Administrative JPM, or
- 2. TWO Administrative Questions Emergency Plan JPM JPM: Given a Site Area Emergency has been declared due to degrading plant conditions, identify the correct location for accountability based on given location in the power block.
PVNGS B. CATEGORY B - SYSTEMS EXAMINATION OUTLINES ES-301 INDIVIDUAL WALK-THROUGH TEST OUTLINE Form ES-301-2 Facility:
PVNGS 1,2,3 Date of Examination: 11/18/02-11/22/02 Examination Level: LSRO Operating Test Number: ____________
System / JPM Title Type Code*
Safety Function
- a. Fuel Handling Equipment / Simulate Movement of fuel bundle in the refuel pool-alt path due to fuel bundle hitting adjacent bundle requiring realignment of Fuel Handling Machine.
DASR FHE
- b. Fuel Handling Equipment / Place fuel assembly from the upender into the correct spent fuel pool storage location.
DPR FHE c.
Fuel Handling Equipment / Inspection of new fuel in the new fuel elevator - alt path due to high general area dose rates created by fuel bundle.
DAPR FHE
- d. Aux Systems / Response to loss of air to gate seals (Two questions related to loss of instrument air/loss of spent fuel pool level will be utilized to fulfill this JPM requirement)
NPR AUX
- e. Instrumentation & Control / Take corrective action for high NI count rate IAW 78OP-9FX01 and 72IC-RX03.
MAPR IC g.
B.2 Facility Walk-Through a.
b.
c.
- Type Codes: (D) irect from bank, (M) odified from bank, (N) ew, (A) lternate path, (C ) ontrol room, (S) imulator, (L) ow-Power, (P) lant, (R ) CA Safety Function: FHE: Fuel Handling Equipment, AUX: Auxiliary Systems, IC: Instrumentation and Control; DHR: Decay Heat Removal, RM: Radiation Monitoring
PVNGS C. CATEGORY C - INTEGRATED PLANT (REFUELING EQUIPMENT) EXAMINATION OUTLINE Appendix D SCENARIO OUTLINE Form ES-D-1 Facility: PVNGS 1,2,3 Scenario No. __1__
Examiners:
Op-Test Number: C1 ______
Operators:
Initial Conditions: Core offload is in progress Turnover: A fuel bundle is in transit from the spent fuel pool to the containment Event No.
Malf No.
Event Type*
Event Description 1.
N/A C
Minor leakage from Transfer Carriage Makeup Tank temporarily suspends fuel movement until tank is refilled.
2.
N/A R
A fuel bundle is dropped onto spent fuel pool with significant fuel damage.
( N )ormal,
( R )eactivity,
( I )nstrument, ( C )omponent,
( M )ajor
PVNGS C. CATEGORY C - INTEGRATED PLANT (REFUELING EQUIPMENT) EXAMINATION OUTLINE Appendix D SCENARIO OUTLINE Form ES-D-1 Facility: PVNGS 1,2,3 Scenario No. __2__
Examiners:
Op-Test Number: C2 ______
Operators:
Initial Conditions: Core onload is in progress Turnover: A fuel assembly is in transit from the upender to the core Event No.
Malf No.
Event Type*
Event Description 1.
N/A I
Startup Range Nuclear Monitoring (SRM) Instrument failure requires suspension of core alterations 2.
N/A M
Severe Thunderstorm Warning issued
( N )ormal,
( R )eactivity,
( I )nstrument, ( C )omponent,
( M )ajor
PVNGS RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 1
9/18/02 6
JPM A1-2 changed to state: recover a foreign material from the spent fuel pool vice CEA material from the refuel pool to coincide with the guidance in the Sensitive Issues Manual.
JPM B5 was changed from a Radiation Monitoring category to an I&C category. The original item was considered an Admin JPM and not suitable. The new JPM Take corrective action for high NI count rate better reflects the criteria for this area.
Scenario C-1 was altered such that the fuel bundle is in transit from the spent fuel pool to containment instead of containment to the spent fuel pool. This was necessary to support the original requirements for the JPM.
Scenario C-2 second event was changed from Loss of fuel pool level to Severe Thunderstorm Warning Issued.
Loss of fuel pool level is already taken credit for in the written exam.
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
- 1.
Vendor reference document upgrade
- 2.
Plant modification (include number)
- 3.
Procedure upgrade
- 4.
Internal or External Agency Commitment (indicate item number)
- 5.
Technical Specification Change (indicate amendment number)
- 6.
Other (explain in comments) 2002 INITIAL LIMITED SENIOR REACTOR OPERATOR LICENSE WRITTEN EXAMINATION DRAFT OUTLINE EXAM DATE: 11/18/02
PVNGS FACILITIES:
PVNGS UNITS 1, 2, & 3 A. OUTLINE: (ES-701)
Group (Sample %)
Subject area Number of Questions 1
(15%)
Reactor and fuel characteristics and physical aspects of core construction important to fuel handling or shutdown activities 8
2 (30%)
System equipment and instruments that are important to plant safety and are located near or used during fuel handling activities or during alternate shutdown procedures 15 3
(40%)
Normal, abnormal, emergency operating and administrative procedures related to fuel handling activities 21 4
(15%)
Health physics and radiation protection for fuel handling activities and general employee responsibilities 6
100%
Totals 50
PVNGS B. CONTENT:
Group 1 : 15%
8 Questions Subject Area:
Reactor and fuel characteristics and physical aspects of core construction important to fuel handling or shutdown activities System System Name K/A #
K/A Topic(s)
Imp.
1 42036 Fuel Handling Incidents AK1.03 Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Incidents:
Indications of approaching criticality 4.3 2
6192002 Neutron Life Cycle K1.10 Describe the neutron life cycle using the following terms:
Define SDM 3.6 3
6192002 Neutron Life Cycle K1.11 Describe the neutron life cycle using the following terms:
Define reactivity 3.0 4
32002 RCS K6.14 Knowledge of the effect or a loss or malfunction on the following RCS components:
Core components 2.8 5
6193007 Heat Transfer K1.04 Describe how the presence of gases or steam can affect heat transfer and fluid flow in HXs 3.0 6
31004 CVCS K5.20 Knowledge of the operational implications of the following concepts as they apply to the CVCS:
Reactivity effects of XE, Boration, and Dilution 3.7 7
32002 RCS K3.02 Knowledge of the effect that a loss or malfunction of the RCS will have on the following:
Fuel 4.5 8
2.2 Equipment Control 2.2.32 Knowledge of the effects of alterations on core configuration 3.3
PVNGS Group 2 : 30%
15 Questions Subject Area:
System equipment and instruments that are important to plant safety and are located near or used during fuel handling activities or during alternate shutdown procedures Knowledge and use of radiation monitors, spent fuel pool cooling and residual heat removal (RHR) systems and the Technical Specifications associated with those systems.
Question System System Name K/A #
K/A Topic(s)
Imp 1
42036 Fuel Handling Incidents AK3.02 Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents:
Interlocks associated with fuel handling equipment 3.6 2
5191003 Controllers and Positioners K1.02
+Function and operation of a speed controller 2.7 3
5191005 Motor and Generators K1.02 Potential consequences of overheating insulation or bearings 2.9 4
5191005 Motor and Generators K1.03 Causes of excessive current in motors and generators, such as low voltage, overloading, and mechanical binding 2.8 5
37072 Area Radiation Monitoring K1.03 Knowledge of the physical connections and/or cause-effect relationships between the ARM system and the following systems:
Fuel building isolation 3.7 6
38029 Containment Purge System K4.02 Knowledge of design feature(s) and/or interlock(s) which provide for the following:
Negative pressure in containment 3.1 7
38033 Spent Fuel Pool Cooling System K1.05 Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems:
RWST 2.8 8
38033 Spent Fuel Pool Cooling System K4.01 Knowledge of design feature(s) and/or interlock(s) which provide for the following:
Maintenance of spent fuel level 3.2 9
38033 Spent Fuel Pool Cooling System K4.02 Knowledge of design feature(s) and/or interlock(s) which provide for the following:
Maintenance of spent fuel cleanliness 2.7
PVNGS Group 2 : 30%
15 Questions Subject Area:
System equipment and instruments that are important to plant safety and are located near or used during fuel handling activities or during alternate shutdown procedures Knowledge and use of radiation monitors, spent fuel pool cooling and residual heat removal (RHR) systems and the Technical Specifications associated with those systems.
Question System System Name K/A #
K/A Topic(s)
Imp 10 38033 Spent Fuel Pool Cooling System K4.04 Knowledge of design feature(s) and/or interlock(s) which provide for the following:
Maintenance of spent fuel pool radiation 2.9 11 38034 Fuel Handling Equipment System K1.03 Knowledge of the physical connections and/or cause-effect relationships between the Fuel Handling System and the following systems:
CVCS 2.7 12 38034 Fuel Handling Equipment System K1 05 Knowledge of the physical connections and/or cause-effect relationships between the Fuel Handling System and the following systems:
Shutdown monitor 3.4 13 38034 Fuel Handling Equipment System K1 06 Knowledge of the physical connections and/or cause-effect relationships between the Fuel Handling System and the following systems:
SFPCS 3.0 14 34005 Residual Heat Removal System (RHRS)
K3.07 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following:
Refueling operations 3.6 15 42036 Fuel Handling Incidents AA1.02 Ability to operate and / or monitor the following as they apply to the Fuel Handling Incidents:
ARM System 3.5
PVNGS Group 3 : 40%
21 Questions Subject Area:
Normal, abnormal, emergency operating and administrative procedures related to fuel handling activities, core safety, and accident mitigation, including general facility events.
Control room operators response to events only as it relates to fuel handling activities and the general response expected of employees.
Question System System Name K/A #
K/A Topic(s)
Imp 1
42036 Fuel Handling Incidents AK3.03 Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents:
Guidance contained in EOP for fuel handling incident 4.1 2
32006 Emergency Core Cooling System (ECCS)
K3.02 Knowledge of the effect that a loss or malfunction of the ECCS will have on the following:
Fuel 4.4 3
42069 Loss of Containment Integrity AA2.01 Ability to determine and interpret the following as they apply to the Loss of Containment Integrity:
Loss of containment integrity 4.3 4
32002 Reactor Coolant System (RCS)
K1.12 Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems:
NIS 3.6 5
32006 Emergency Core Cooling System (ECCS)
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems:
RCS 4.3 6
2.2 Equipment Control 2.2.27 Knowledge of the refueling process.
3.5 7
32002 RCS A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Loss of heat sinks 4.6
PVNGS Group 3 : 40%
21 Questions Subject Area:
Normal, abnormal, emergency operating and administrative procedures related to fuel handling activities, core safety, and accident mitigation, including general facility events.
Control room operators response to events only as it relates to fuel handling activities and the general response expected of employees.
Question System System Name K/A #
K/A Topic(s)
Imp 8
2.2 Equipment Control 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.
3.3 9
34005 Residual Heat Removal System (RHRS)
K3.07 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following:
Refueling operations 3.6 10 34076 Service Water System (SWS)
K3.01 Knowledge of the effect that a loss or malfunction of the SWS will have on the following:
Closed cooling water 3.6 11 35022 Containment Cooling System (CCS)
K4.03 Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following:
Automatic containment isolation 4.0
PVNGS Group 3 : 40%
21 Questions Subject Area:
Normal, abnormal, emergency operating and administrative procedures related to fuel handling activities, core safety, and accident mitigation, including general facility events.
Control room operators response to events only as it relates to fuel handling activities and the general response expected of employees.
Question System System Name K/A #
K/A Topic(s)
Imp 12 36062 Electrical Distribution A2.01 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:
Types of loads that, if de-energized, would degrade or hinder plant operation 3.9 13 35103 Containment System A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations Necessary plant conditions for work in containment 3.2 14 37015 Nuclear Instrumentation System A1 07 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the NIS controls including:
Changes in boron concentration 3.4 15 2.1 Conduct of Operations 2.1.3 Knowledge of shift turnover practices.
3.4 16 2.1 Conduct of Operations 2.1.4 Knowledge of shift staffing requirements.
3.4 17 2.1 Conduct of Operations 2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions.
4.3 18 2.2 Equipment Control 2.2.26 Knowledge of refueling administrative requirements.
3.7
PVNGS Group 3 : 40%
21 Questions Subject Area:
Normal, abnormal, emergency operating and administrative procedures related to fuel handling activities, core safety, and accident mitigation, including general facility events.
Control room operators response to events only as it relates to fuel handling activities and the general response expected of employees.
Question System System Name K/A #
K/A Topic(s)
Imp 19 32006 Emergency Core Cooling System (ECCS)
K2.01 Knowledge of bus power supplies to the following:
ECCS Pumps 3.9 20 2.4 Emergency Procedures
/Plan 2.4.25 Knowledge of fire protection procedures.
3.4 21 2.4 Emergency Procedures
/Plan 2.4.37 Knowledge of the lines of authority during an emergency.
3.5
PVNGS Page 15 of 15 Group 4 : 15%
6 Questions Subject Area:
Health physics and radiation protection for fuel handling activities and general emplo responsibilities.
Administrative procedures associated with radiation protection.
Question System System Name K/A #
K/A Topic(s)
Imp 1
42036 Fuel Handling Incidents AK1.01 Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Incidents:
Radiation exposure hazards 4.1 2
2.4 Emergency Procedures /
Plan 2.4.29 Knowledge of the emergency plan.
4.0 3
2.3 Radiation Control 2.3.2 Knowledge of facility ALARA program 2.9 4
37072 Area Radiation Monitoring (ARM) System A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ARM system controls including:
Radiation levels 3.6 5
2.3 Radiation Control 2.3.1 Knowledge of 10 CFR:20 and related facility radiation control requirements.
3.0 6
2.3 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
3.1