ML17353A580
| ML17353A580 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/29/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17353A579 | List: |
| References | |
| PROC-960229, NUDOCS 9603110467 | |
| Download: ML17353A580 (58) | |
Text
WORD:NRCMATLS.16 9603i10467 96030i PDR ADDCK 05000250 V
- Delma, This material willbe going to:
- 1. NRC in Atlanta Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W., Suite 2900 Atlanta. GA 30323-0199 Attn:
George Hopper License Examiner
- 2. NRC Contractor:
Sonalysts 215 Parkway North Waterford, CT 06385 Attn:
Tim Guilfoil (203) 442-4355 X451 Fax (203) 447-8883 / 442-5696
- 3. Our Contractor:
'arry Veeder Note: This willbe a partial set.
How much or how little after I'e talked to the contractor.
- 4. Last set of four for our (Training &Students) use.
WORD:NRCMATLS.16
A I L I Complete Listing ofMaterial Provided for Exam Preparation Upgrade Procedure Index Basis Document Index L
P ED Administrative Procedures General Operating Procedures Operating Procedures (4 Books)
Off-Normal Operating Procedures (2 Books)
Annunciator Response Procedures Fuel Handling Procedures Emergency Operating Procedures (2 Books)
EOP Basis Documents (4 Books)
Emergency Plan Implementing Procedures Surveillance Procedures Y TEMD RIPTI N -3 Books PLAN System Description Lesson Plans (5 Books)
Emergency Operating Procedure Lesson Plans (5 Books)
Off-Normal Operating Procedure Lesson Plans (3 Books)
Administrative Procedure Lesson Plans (2 Books)
Emergency Plan Implementing Procedure Lesson Plans Technical Specifications Lesson Plans E~XAMEA Systems Exam Bank (2 Books)
Emergency Operating Procedure Exam Bank Off-Normal Procedure Exam Bank Administrative Procedure Exam Bank Emergency Plan Implementing Procedure Exam Bank Technical Specifications Exam Bank EEEHNA 2 '2-22 E
THER PLANTREFEREN E/TRAININ MATERIALS Job Performance Measures (3 Books)
Technical Specifications with Position Statements Plant Curve Book
" Simulator Information Plant Drawings / Logics & Control Diagrams WORD:NRCMATLS.16
ADMINISTRATIVEPROCEDURES ProcedA Date Title 0-ADM-031 0-ADM-051 0-ADM-102 0-ADM-103 0-ADM-115 0-ADM-200 0-ADM-201 0-ADM-202 0-ADM-203 0-ADM-204 0-ADM-205 0-ADM-207 0-ADM-208 0-ADM-211 0-ADM-212
'-ADM-213 0-ADM-214 0-ADM-503 0-ADM-536 0-ADM-555 0-ADM-600 0-ADM-701 07/06/95 01/25/96 09/26/95C 07/11/95 08/03/95 02/08/96 07/11/95 06/01/95 01/28/93 03/24/94 10/27/95 10/26/93 01/06/94 08/23/95 12/21/95 08/01/95 02/14/95 03/15/94 04/14/94 03/28/95 12/06/94C 01/03/96 Independent Verification Outage Risk Assessment and Control On The Spot Changes to Procedures Temporary Procedures Notification of Plant Events Conduct of Operations Operations Procedure Usage Shift Relief and Turnover Shift Operating Practices Operations Narrative Logbooks Administrative Control of Valves, Locks, and Switches Operations Instructions in the Event of a Situation Not Addressed by Procedure Secondary Plant Chemistry Control and Limits Emergency and Off-Normal Operating Procedure Usage In-Plant Equipment Clearance Orders Technical Specification Related Equipment Out-of-Service Logbook Administrative Control of Defeated Annunciators Control and Use ofTemporary System Alterations Technical Specification Position Statements Reactivity Management Radiation Protection Manual Control of Plant Work Activities WORD:NRCMhYLS.16
GENERAL OPERATING PROCEDURF<D ProcedA 3-6OP-103 3-GOP-301 3-GOP-305 3-GOP-503 Date 10/03/95 01/05/96 10/03/95 12/01/95 Title Power Operation to Hot Standby Hot Standby to Power Operation Hot Standby to Cold Shutdown Cold Shutdown to Hot Standby WORD:NRCMATLS.16
OPERATING PROCEDUM8 ProcedA'ate Title Book 1 Book 2 Book 3 Book 4 O-OP-003.1 O-OP-003.2 O-OP-003.3.
O-OP-003.4 3-OP-005 3-OP-005.1 3-OP-006 3-OP-007 3-OP-008 3-OP-013 3-OP-019 3-OP-023 0-OP-025 3-OP-028 3-OP-028.1 3-OP-030 3-OP-041.1 3-OP-041.2 3-OP-041.3 3-OP-041.4 3-OP-041.7 3-OP-041.8 3-OP-041.9 0-OP-046 3-OP-047 3-OP-050 O-OP-051.2 0-OP-053 3-OP-062 3-OP-064 0-OP-066
'3-OP-067 3-OP-068 3-OP-072 3-OP-073 3-OP-074 O-OP-074.1 3-OP-075 3-OP-087 3-OP-089 3-OP-094 04/19/94 12/17/92 02/02/96 07/28/95, 12/07/95C 07/28/95 02/14/96 03/09/93 07/25/95 01/11/96 02/18/96 01/31/96 08/25/95 03/31/92 06/06/95 01/10/96 10/06/95 12/12/95 04/29/94 05/18/95C 10/23/95 ll/09/95 06/06/95 07/13/95 01/02/96 02/06/96 04/18/95 10/03/95 04/08/94 07/13/95 05/11/95 09/27/94 04/05/94 10/11/95 02/22/96 09/25/95 07/11/95 04/29/94 06/29/95 05/25/95 10/03/95 125 V Vital DC System 125 V AuxiliaryDC System 120 V Vital Instrument AC System Auxiliary 120 V AC System 4160 VoltBuses A, B and D 4160 VoltBus C 480 Volt Switchgear System 480 VoltMotor Control Centers Turbine Plant Cooling Water Instrument AirSystem Intake Cooling Water System Emergency Diesel Generator Control Room Ventilation System Control Rod Drive M-G Set Operation RPI Power Supply System Component Cooling Water System Reactor Coolant Pump Pressurizer Operation Pressurizer Relief Tank Overpressure Mitigating System Draining the Reactor Coolant System Filling and Venting the RCS Reduced Inventory Operations CVCS - Boron Concentration Control CVCS - Charging and Letdown Residual Heat Removal System Post Accident Containment Vent System Containment Purge System Safety Injection Safety Injection Accumulators Area Radiation Monitoring System Process Radiation Monitoring System Containment Spray System Main Steam System Condensate System Steam Generator Feedwater Pump Standby S/G Feedwater System Auxiliary'Feedwater System Turbine Lube Oil System Main Turbine Containment Post Accident Monitoring Systems WORD:NRCMATLS.16
E OFF-NORMALOPERATING PROCEDUIUB
\\
Procedà Book 1 Date Title 3-ONOP-003.4
. 3-ONOP-003.5 3-ONOP-003.6 3-ONOP-003.7 3-ONOP-003.8 3-ONOP-003.9 3-ONOP-004 3-ONOP-004. 1 3-ONOP-004.2 3-ONOP-004.3 3-ONOP-004.4 3-ONOP-004.5 3-ONOP-008 3-ONOP-011 0-ONOP-013 3-ONOP-014 O-ONOP-016.7 3-ONOP-019 3-ONOP-023.2 3-ONOP-028 3-ONOP-028.1 3-ONOP-028.2 3-ONOP-028.3 3-ONOP-030 3-ONOP-033.1 3-ONOP-033.2 3-ONOP-033.3 3-ONOP-041.1 06/16/94 10/21/92 06/29/95 07/25/95 07/25/95 07/25/95
~ 09/28/95 09/28/95 09/28/95 09/28/95 06/29/95 09/28/95 11/08/95 02/23/96 09/28/95 06/06/95 03/03/94 02/18/96 06/07/94 06/06/95 03/10/94 03/10/94 09/27/94 11/27/95 09/26/95 06/24/93 12/08/92 09/19/95 Loss of DC Bus 3D01 'and 3D01A (3A)
Loss of DC Bus 3D23 and 3D23A (3B)
Loss of 120 V Vital Inst Panel 3P06 Loss of 120 V Vital Inst Panel 3P07 Loss of 120 V Vital Inst Panel 3P08 Loss of 120 V VitalInst Panel 3P09 Loss of Offsite Power System Restoration Following Loss of Offsite Power Loss of 3A 4KV Bus Loss of 3B 4KV Bus Loss of 3C 4KV Bus Loss of 3D 4KV Bus Turbine Plant Cooling Water Malfunction Screen Wash System / Intake Malfunction Loss of Instrument Air Main Condenser Loss of-Vacuum E
Screen Wash Emergency Makeup to the Fire Protection System Intake Cooling Water Malfunction Emergency Diesel Generator Failure Reactor Control System Malfunction RCC Misalignment RCC Position Indication Malfunction Dropped RCC Compo'nent Cooling Water Malfunction Spent Fuel Pit (SFP) Cooling System Malfunction Refueling Cavity Seal Failure Accidents Involving New or Spent Fuel Reactor Coolant Pump Off-Normal WORD:NRCMATLS.16
OFF-NORMALOPERATING PROCEDUM8 (continued)
Procedà Date Title Book 2 3-ONOP-041.3 3-ONOP-041.4 3-ONOP-041.5 3-ONOP-041.6 3-ONOP-041.7 3-ONOP-041.8, 3-ONOP-046.1 O-ONOP-046.3 3-ONOP-046.4 3-ONOP-047.1 3-ONOP-049.1 3-ONOP-050 3-ONOP-053 3-ONOP-059.4 3-ONOP-059.5 3-ONOP-059.6 3-ONOP-059.7 3-ONOP-059.8 3-ONOP-059.9 0-ONOP-066 3-ONOP-067
. 3-ONOP-071.1 3-ONOP-075 3-ONOP-089 3-ONOP-092.1 3-ONOP-092.2 3-ONOP-092.3 3-ONOP-092.4 3-ONOP-100 0-ONOP-105 10/30/95 04/05/94 10/14/93 02/09/93C1 09/28/95 09/28/95 01/11/96 04/06/93 01/11/96 03/08/95 10/04/95 10/05/95 05/11/93 07/13/95 12/29/93 10/14/93 07/13/95 05/05/94 12/07/95 05/11/95 08/08/95 08/25/94 07/11/95 03/10/94 08/03/94 04/21/95 06/15/93 06/15/93C 06/06/95 07/13/95 Excessive Reactor Coolant System Leakage Excessive Reactor Coolant Systein Activity Pressurizer Pressure Control Malfunction Pressurizer Level Control Malfunction Shutdown'LOCA [Mode 3 (less than 1000psig) or Mode 4]
Shutdown LOCA [Mode 5 or 6]
Emergency Boration Loss of Boration Flowpath(s)
Malfunction of Boron Concentration Control System Loss of Charging Flow in Modes 1 Through 4 Deviation or Failure of Safety Related or Reactor Protection Channels Loss ofRHR Loss of Containment Integrity Excessive AxialFlux Difference Source Range Nuclear Instrumentation Malfunction Backup NIS (Gamma Metrics) Malfunction Intermediate Range Nuclear Instrumentation Malfunction Power Range Nuclear Instrumentation Malfunction Excessive Quadrant Power TiltRatio High Area Radiation Monitoring System Alarm Radioactive Effluent Release Secondary Chemistry Deviation from Limits AuxiliaryFeedwater System Malfunction Turbine Runback Main Transformer Malfunction AuxiliaryTransformer Malfunction Startup Transformer Malfunction C Bus Transformer Malfunction Fast Load Reduction Control Room Evacuation WORD:NRCMhTLS.16
ANNUNCIATORRESPONSE PROCEDURE Proced.¹'ate Title 3-ARP-097.CR 09/26/95 Control Room Annunciator Response WORD:NRCMATLS.16
FUEL HANDLINGPROCEDUEUH Proced.¹ Date Title 0-ADM-035 OP-16200 3-OP-038.1 3-OP-038.5 3-OP-038.9 3-OP-038.23 06/23/92 10/18/94~
09/10/95 11/09/95, 11/15/95 06/25/92 Limitations and Precautions for Handling Fuel Assemblies Manipulator Crane - Operating Instructions Preparation for Refueling Activities Spent Fuel Pit Bridge Crane Operation Refueling Activities Checkoff List Fuel Transfer System - Normal Operation WORD:NRCMATLS.16
UNIT3 EMI<WGENCYOPERATING PROCEDURI~A Procedà Date Title Book 1 3-EOP-E-0 3-EOP-ES-0.0 3-EOP-ES-0.1 3-EOP-ES-0.2 3-EOP-ES-0.3 3-EOP-ES-0.4 3-EOP-E-1 3-EOP-ES-F 1
3-EOP-ES-1.2 3-EOP-ES-1.3 3-EOP-ES-1.4 3-EOP-E-2 3-EOP-E-3 3-EOP-ES-3.1 3-EOP-ES-3.2 3-EOP-ES-3.3 Book 2 09/28/95 03/30/95 09/28/95 09/28/95 09/28/95 09/28/95 06/30/95 09/28/95 09/28/95 09/28/95 09/28/95 03/30/95 09/28/95 03/30/95 03/30/95
. 03/30/95 Reactor Trip or Safety Injection Rediagnosis Reactor Trip Response Natural Circulation Cooldown Natural Circulation Cooldown With Steam Void In Vessel (With RVLMS)
Natural Circulation Cooldown With Steam Void In Vessel (Without RVLMS)
Loss of Reactor or Secondary Coolant SI Termination Post LOCA Cooldown and Depressurization Transfer to Cold Leg Recirculation Transfer to Hot Leg Recirculation Faulted Steam Generator Isolation Steam Generator Tube Rupture Post-SGTR Cooldown Using Backfill Post-SGTR Cooldown Using Blowdown Post-SGTR Cooldown Using Steam Dump 3-EOP-ECA-0.0 3-EOP-ECA-0.1 3-EOP-ECA-0.2 3-EOP-ECA-1.1
.3-EOP-ECA-1.2 3-EOP-ECA-2.1 3-EOP-ECA-3.1 3-EOP-ECA-3.2 3-EOP-ECA-3.3 3-EOP-F-0 3-EOP-FR-S.1 3-EOP-FR-S.2 3-EOP-FR-C.1 3-EOP-FR-C.2 3-EOP-FR-C.3 3-EOP-FR-H.1 3-EOP-FR-H.2 08/17/95 09/28/95 09/28/95 09/28/95 03/30/95 09/28/95 09/28/95 09/28/95C 09/28/95 03/30/95 03/30/95 03/30/95 09/28/95 09/28/95 03/30/95 06/29/95 03/30/95 Loss of AllAC Power Loss of AllAC Power Recovery Without SI Required Loss of AllAC Power Recovery With SI Required Loss of Emergency Coolant Recirculation LOCA Outside Containment Uncontrolled Depressurization of AllSteam Generators SGTR With Loss of Reactor Coolant - Subcooled Recovery Required SGTR With Loss of Reactor Coolant - Saturated Recovery Desired SGTR Without Pressurizer Pressure Control Critical Safety Function Status Trees Response to Nuclear Power Generation/ATWS Response to Loss of Core Shutdown Response to Inadequate Core Cooling Response to Degraded Core Cooling Response to Saturated Core Cooling Response to Loss of Secondary Heat Sink Response to Steam Generator Overpressure WORD:NRCMhTLS.16
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'P'>;'~?%R UNIT3 EMERGENCY OPERATING PROCEDUMH (continued)
Proced.¹ Book 2 (continued)
Date Title 3-EOP-FR-H.3 3-EOP-FR-H.4 3-EOP-FR-H.5 3-EOP-FR-P. 1 3-EOP-FR-P.2 3-EOP-FR-Z.1 3-EOP-FR-Z.2.
3-EOP-FR-Z.3 3-EOP-FR-I.1 3-EOP-FR-I.2 3-EOP-FR-I.3 03/30/95 03/30/95 03/30/95 09/28/95 03/30/95 09/28/95 03/30/95 03/30/95
.03/30/95 03/30/95 09/28/95 Response to Steam Generator High Level Response to Loss ofNormal Steam Release Capabilities Response to Steam Generator Low Level Response to Imminent Pressurized Thermal Shock Condition Response to Anticipated Pressurized Thermal Shock Condition Response to High Containment Pressure Response to Containment Flooding Response to High Containment Radiation Level Response to High Pressurizer Level Response to Low Pressurizer Level Response to Voids in Reactor Vessel WORD:NRCMATLS.16
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>c m)..; +pe<'m; 'P:,i'<~~: i UNIT3 EMERGENCY OPERATING PROCEDUM8 BASIS DOCUMENTS Proced.t Date Title Book 1 3-BD-EOP-E-0 3-BD-EOP-ES-O.O 3-BD-EOP-ES-0. 1 3-BD-EOP-ES-0.2 3-BD-EOP-ES-0.3 3-BD-EOP-ES-0.4 3-BD-EOP-E-1 3-BD-EOP-ES-1.1 3-BD-EOP-ES-1.2 3-BD-EOP-ES-1.3 Book 2 10/11/95 08/01/91 09/28/95 09/28/95 09/28/95 09/28/95 06/30/95 09/28/95 09/28/95 09/28/95 Reactor Trip or Safety Injection Rediagnosis Reactor Trip Response Natural Circulation Cooldown Natural Circulation Cooldown With Steam Void in Vessel With RVLMS (QSPDS)
Natural Circulation Cooldown With Steam Void in Vessel (Without RVLMS)
Loss of Reactor or Secondary Coolant SI Termination Post LOCA Cooldown and Depressurization Transfer to Cold Leg Recirculation 3-BD-EOP-ES-1.4 3-BD-EOP-E-2 3-BD-EOP-E-3 3-BD-EOP-ES-3. 1 3-BD-EOP-ES-3.2 3-BD-EOP-ES-3.3 3-BD-EOP-ECA-0.0 3-BD-EOP-ECA-0.1 3-BD-EOP-ECA-0.2 3-BD-EOP-ECA-1.1 09/28/95 03/30/95 09/28/95 12/09/92 12/09/92 12/09/92 06/29/95 09/28/95 09/28/95 09/28/95 Transfer to Hot Leg Recirculation Faulted Steam Generator Isolation Steam Generator Tube Rupture
. Post-SGTR Cooldown Using Backfill Post-SGTR Cooldown Using Blowdown Post-SGTR Cooldown Using Steam Dump Loss of AllAC Power Loss of AllAC Power Recovery Without SI Required Loss ofAllAC Power Recovery With SI Required Loss of Emergency Coolant Recirculation WORD:NRCMATLS.16
0
UNIT3 EMHtGENCY OPERATING PROCEDURES BASIS DOCUMENTS (continued)
Proced.¹ Date Title Book 3 3-BD-EOP-ECA-1.2 3-BD-EOP-ECA-2. 1 3-BD-EOP-ECA-3.1 3-BD-EOP-ECA-3.2 3-BD-EOP-ECA-3.3 3-BD-EOP-F-0 3-BD-EOP-FR-S. 1 3-BD-EOP-FR-S.2 3-BD-EOP-FR-C. 1 3-BD-EOP-FR-C.2 Book 4 08/01/91 09/28/95 09/28/95 09/28/95 09/28/95 03/09/93 12/11/92 12/22/92 09/28/95 09/28/95 LOCA Outside Containment Uncontrolled Depressurization ofAllSteam Generators SGTR With Loss of Reactor Coolant - Subcooled Recovery Desired SGTR With Loss of Reactor Coolant - Saturated Recovery Desired SGTR Without Pressurizer Pressure Control Critical Safety Function Status Trees Response to Nuclear Power Generation/ATWS Response to Loss of Core Shutdown Response to Inadequate Core Cooling Response to Degraded Core Cooling 3-BD-EOP-FR-C.3 3-BD-EOP-FR-H. 1 3-BD-EOP-FR-H.2 3-BD-EOP-FR-H,3 3-BD-EOP-FR-H.4 3-BD-EOP-FR-H.5 3-BD-EOP-FR-P.1 3-BD-EOP-FR-P.2 3-BD-EOP-FR-Z.1 3-BD-EOP-FR-Z.2 3-BD-EOP-FR-Z,3 3-BD-EOP-FR-I.1 3-BD-EOP-FR-I.2 3-BD-EOP-FR-I.3 08/01/91 06/29/95 08/01/91 08/01/91 08/01/91 OKL01/91 09/28/95 08/01/91 09/28/95 08/01/91 08/01/91 08/01/91 08/01/91 09/28/95 Response to Saturated Core Cooling Response to Loss of Secondary Heat Sink Response to Steam Generator Overpressure Response to Steam Generator High Level Response to Loss ofNormal Steam Release Capabilities, Response to Steam Generator Low Level Response to Imminent Pressurized Thermal Shock Condition Response to Anticipated Pressurized Thermal Shock Condition Response to High Containment Pressure Response to Containment Flooding
Response
to High Containment Radiation Level Response to High Pressurizer Level Response to Low Pressurizer Level
. Response to Voids in Reactor Vessel
'ORD:NRCMATLS.I6
EMERGENCY PLANIMPLEMENTINGPROCEDUIU~A Proced.¹ Date Title EPIP-20101 EPIP-20104 EPIP-20106 EPIP-20107 EPIP-20110 EPIP-20111 EPIP-20126 12/29/94 06/30/94 01/24/95 10/06/94C 10/17/91C 12/15/94 01/24/95 Duties of Emergency Coordinator Emergency Response Organization Notification/Staff Augmentation
'atural Emergencies Fire/Explosion Emergencies Criteria For, and Conduct of Owner Controlled Area Evacuation Re-entry Off-Site Dose Calculations WORD:NRCMATLS.16
SURVEILLANCEPROCEDURE ProcedA'ate Title 3-OSP-023.1 O-OSP-023.3 O-OSP-025.1 3-OSP-041.1 3-OSP-041.7 3-OSP-041.16 3-OSP-059.1 3-OSP-059.2 3-OSP-059.5 3-OSP-059.6 3-OSP-059.10 3-OSP-075.1 07/25/95C 01/05/96 03/14/95 02/02/96 02/02/96 08/25/94 06/16/94 06/15/95 01/05/96 03/16/93 11/10/94 09/24/93 Diesel Generator Operability Test Equipment Operability Verification with an Emergency Diesel Generator Inoperable Control Room Emergency Ventilation System Operability Test Reactor Coolant System Leak Rate Calculation Reactor Coolant System Heatup and Cooldown Temperature Verification Minimum Temperature for Criticality Verification Source Range Nuclear Instrumentation Analog Channel Operational Test Intermediate Range Nuclear Instrumentation Analog Channel Operational Test Power Range Nuclear Instrumentation Shift Checks and Daily Calibrations High Flux at Shutdown Determination of Quadrant Power TiltRatio AuxiliaryFeedwater Train 1 Operability Verification WORD:NRCMATLS.16
SYSTEM DESCRIj.'TIONS SDk'ate Title Book 1 3
4 5
03/30/95 03/30/95 06/08/94 7
8 9
11 13 21 02/08/95 10/26/94 10/17/95 01/22/96 08/07/95 12/05/95 6
02/26/96 Incore Instrumentation Excore Nuclear Instrumentation Full Length Rod Control Rod Position Indication Reactor Coolant Reactor Coolant Pumps Pressurizer and Relief Steam Generator Chemical &Volume Control Emergency Core Cooling Book 2 25 26 28 29 40
, 41 44 63 68 104 105 111 112 117 123 127 130 132 137 140 144 153 155 165 170 10/05/95 02/16/96 07/28/95 04/25/94 10/30/95 08/05/94 02/08/95 01/11/96 02/14/96 07/10/95 07/11/95 08/28/95 08/02/95 12/22/94 02/26/96 03/30/95 09/14/95 04/12/95 01/03/96 01/08/96 10/02/95 03/07/95 12/12/95 01/18/96 10/05/94 Containment Spray Containment Building Containment Post Accident Evaluation Containment Ventilation and Heat Removal Component Cooling Water Fuel Pool Cooling, Purification and Ventilation Fuel Handling Reactor Protection and Safeguards Actuation Radiation Monitoring and Protection Main and Extraction Steam Steam Dump Feedwater Heater Vents and Drains Condensate and Feedwater AuxiliaryFeedwater Condenser and Circulating Water Main Turbine Control Turbine, Turbine Oil, and Gland Seal Turbine Plant Cooling Water Emerg Diesel Generator and Auxiliaries Main Power Distribution 120 VAC & 125 VDC Distribution Fire Prot, Alternate S/D &Safe S/D Plant Air Intake Cooling Water Emergency Load Sequencer WORD:NRCMATLS.16
SYSTEM DESCRIPTION LESSON PACKAGES SDP'ate LP Num.
Title Book 1 7
8 9
04/13/95 12/06/94 01/25/95 3
10/07/94 4
05/25/95 5
06/08/94 6
06/08/94 6900103 6900104 6900105 6900106 6900107 6900108 6900109 Incore Instrumentation Excore Nuclear Instrumentation Full Length Rod Control Rod Position Indication, Reactor Coolant System Reactor Coolant Pumps Pressurizer and Relief System Book 2 Book 3 Book 4 Book 5 11 13 21 25 26 28 29 40 41 44 63 68 104 105 111 112 117 123 127 130 132 137 140 144 153 155 165 170 01/23/96 08/07/95 09/30/94 01/03/96 08/17/95 06/22/95 09/30/94 01/22/96 06/12/95 06/06/94 01/10/96 11/29/94 09/09/94 07/11/95 05/01/95 07/12/95 03/29/95 05/05/95 01/31/95 09/11/95 04/06/95 09/11/95 02/21/96 02/21/96 03/07/95 09/30/95 01/26/96 02/21/96 6900111 6900113 6900121 6900125 6900126 6900128 6900129 6900140 6900141 6900144 6900163 6900168 6900117 6900118 6900120 6900122 6900123 6900131 6900132 6900133 6900134 6900136 6900138 6900139 6900143 6900145 6900154 6900157 Steam Generator Chemical & Volume Control System Emergency Core Cooling System Containment Spray Containment Building Containment Post Accident Evaluation Containment Vent. and Heat Removal Component Cooling Water Spent Fuel Pool Cooling, Purif. and Vent.
Fuel Handling System Reactor Prot. and Safeguards Actuation Radiation Monitoring and Protection Main and Extraction Steam System Steam Dump System Feedwater Heater Vents and Drains Condensate and Feedwater System AuxiliaryFeedwater System Condenser and Circulating Water Main Turbine Control Turbine, Oil, and Gland Seal Turbine Plant Cooling Water System Emerg Diesel Gen And Auxiliaries Main Power Distribution 120 VAC & 125 VDC Distribution Fire Prot, AltShutdown, Safe Shutdown Instrument AirSystem Intake Cooling Water System Bus Stripping &Load Sequencer WORD:NRCMATLS.16
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UNIT3 EM<AGENCYOPERATING PROCEDURXS LESSON PACKAGES Procedà Date LP Num.
Title 3-EOP-E-0 3-EOP-ES-0.0 3-EOP-ES-0.1 3-EOP-ES-0.2 3-EOP-ES-0.3 10/12/95 6900321 04/21/92 6900322 10/11/95 6900323 10/23/95 6900324 10/17/95 6900325 3-EOP-E-1 09/26/93 6900327 3-EOP-ES-0.4 10/19/95 6900326 Reactor Trip or Safety Injection Rediagnosis Reactor Trip Response Natural Circulation Cooldown Natural Circulation Cooldown With Steam Void In Vessel With RVLMS (QSPDS)
Natural Circulation Cooldown With Steam Void In Vessel (Without RVLMS)
Loss of Reactor or Secondary Coolant Book 2 Book 3 3-EOP-ES-1.1 3-EOP-ES-1.2 3-EOP-ES-1.3 3-EOP-ES-1.4 3-EOP-E-2 3-EOP-E-3 3-EOP-ES-3.
1 3-EOP-ES-3.2 3-EOP-ES-3.3 3-EOP-ECA-0.0 3-EOP-ECA-0. 1 10/24/95 10/24/95
'10/24/95 10/12/93 11/06/91 10/25/95 10/19/93 10/13/93 10/13/93 09/21/94 05/30/95
'-EOP-ECA-0.2 11/01/95 3-EOP-ECA-1.1 09/24/93
.3-EOP-ECA-1.2 04/29/92 3-EOP-ECA-2.1 10/12/93 6900328 6900329 6900330 6900331 6900334 6900339 6900340 6900341 6900342 6900348 6900349 6900350 6900332 6900333 6900335 SI Termination Post LOCA Cooldown and Depressurization Transfer to Cold Leg Recirculation Transfer to Hot Leg Recirculation Faulted Steam Generator Isolation-Steam Generator Tube Rupture Post-SGTR Cooldown Using Backfill Post-SGTR Cooldown Using Blowdown Post-SGTR Cooldown Using Steam Dump Loss of AllAC Power Loss of AllAC Power Recovery Without SI Required Loss of AllAC Power Recovery With SI Required.
Loss of Emergency Coolant Recirculation LOCA Outside Containment Uncontrolled Depressurization of AllSteam Generators Book 4 3-EOP-ECA-3;1 10/13/93 6900343 3-EOP-ECA-3.3 02/28/96 3-EOP-F-0 05/03/94 3-FR-S.1-2 09/26/93 6900345 6900353 6900346 3-FR-C.1-3 10/26/95 6900347 3-EOP-ECA-3.2 02/28/96 6900344 SGTR With Loss of Reactor Coolant -Subcooled Recovery Desired
=
SGTR With Loss ofReactor Coolant -Saturated Recovery Desired SGTR Without Pressurizer Pressure Control Critical Safety Function Status Trees Response to Nuclear Generation/ATWS-Loss of Core Shutdown Core Cooling Book 5 3-FR-H. 1-5 3-FR-P.1-2 3-FR-Z.1-3 3-FR-I.1-3 WORD:NRCMhTLS.16 10/26/95 10/30/95 10/11/93 10/31/95 6900337 6900336 6900338 6900351 Heat Sink Integrity Abnormalities Responses to High/Low PRZ Levels and Voids in the Reactor Vessel
}
OFF-NORMALOPERATING PROCEDURE LESSON PACKAGES Procedà Date LP Num.
Title Book 1 ONOP-003.X ONOP-004 ONOP-004. 1 ONOP-004.X ONOP-008 ONOP-011 ONOP-019 ONOP-028.X ONOP-030 ONOP-041.1 Book 2 12/15/94 06/20/95 06/20/95 06/20/95 08/17/93 04/20/95 04/28/93 12/06/94 06/07/95 04/18/94 6900260 6900255 6900256 6900263 6900217 7100152 7100154 6900207 6900229 6900205 Loss of 120V Vital Instrument Panel Loss of Offsite Power System Restoration following Loss of Offsite Power Loss of <<A, <<B, <<C, or *D4KV Bus ONOPs Turbine Plant Cooling Water Malfunction Screen Wash System / Intake Malfunction Intake Cooling Water System ONOP Training Rod Control System Malfunctions Component Cooling Water Malfunctions Reactor Coolant Pump Off-Normal ONOP-041.3 ONOP-041.4 ONOP-041.5 ONOP-041.6 ONOP-041.7 ONOP-041.8 ONOP-046.1 ONOP-046.3 ONOP-047.1 ONOP-049.1 ONOP-050 ONOP-059.X ONOP-066 ONOP-067 ONOP-075 Book 3 10/11/94 10/07/93 06/14/93 11/01/93 12/11/95 11/22/94 08/19/93 10/07/93 09/25/95 12/15/94 11/22/95 01/08/89 11/05/91 01/10/96 09/16/93 6900212 6900228 6900204 6900254 6900265 6900266 6900232 6900233 6900234 6900243 6900210 6900206 6900246 6900242 6900202 Excessive RCS Leakage Excessive RCS Activity Pressurizer Pressure Control Malfunction Pressurizer Level Control Malfunction Shutdown LOCA (Mode 3 (1000 psig or Mode 4)
Shutdown LOCA ( Mode 5 or 6)
Emergency Boration Loss of Boration Flowpaths Loss of Charging Flow in Modes 1-4 Deviation or Failure of Safety Related or Reactor Protection Channels Loss of Residual Heat Removal Nuclear Instrumentation Malfunctions High Area Radiation Monitoring System Alarm Radioactive Effluent Release AuxiliaryFeedwater System Malfunction ONOP-089 ONOP-100 ONOP-105 04/18/95 09/13/93 12/05/94 6900248 6900239 6900252 Turbine Runback Fast'Load Reduction Control Room Evacuation WORD:NRCMATLS.16
ADMINISTRATIVEPROCEDURE LESSON PACKAGES ProcedA'ate LP Num.
Title Book 1 ADM-031 ADM-051 ADM-102/103 ADM-115 ADM-200 ADM-201 ADM-202 ADM-203 ADM-204 ADM-205 ADM-207 ADM-208 ADM-211 ADM-212 Book 2 09/21/93 07/24/95 02/28/96 12/22/94 04/25/94 04/26/94 01/03/95 04/26/94 07/26/94 01/26/96 05/24/94 6900012 6900032 6900010 6900006 6900025 6900003 6900022 6900024 6900023 6900005 6900011.
10/12/94 6900208 06/29/95 6900320 01/05/95 6900008 Independent Verification Outage Risk Assessment and Control Instructions/Procedures and Drawings Notification of Plant Events Conduct of Operations Operations Procedure Usage Shift Relief and Turnover Shift Operating Practices Operations Narrative Logbooks Control of Switches, Valves &Locks Ops Instru'ctions in the Event of a Situation Not Addressed By Procedure Secondary Chemistry Requirements &Deviation From Limits EOP Introduction and EOP/ONOP User's Guide In-Plant Equipment Clearance Orders ADM-213 ADM-503 ADM-536 ADM-555 ADM-600 ADM-701 04/08/94 01/03/95 12/02/94 04/26/95 12/08/94 01/03/95 6900037 6900029 6900503 6900043 6900020
'900007 Tech Spec Related Equipment OOS Logbook Control &Use of Temporary System Alterations Tech Spec Position Statements Reactivity Management Health Physics Manual PWO Preparation WORD:NRCMATLS.16
EMIMtGENCYPLANIMPLEMENTINGPROCEDURES LESSON PLANS LP Num.
Date Title
- 3200001, 3200002 3200003 3200004 3200008 3200012 3200013 05/09/95 02/28/96 10/10/95 07/11/95 03/10/95 02/28/96 05/09/95 Emergency Plan Overview Notifications/Communications Emergency Classification Radiological Assessment/Protective Action Recommendations Management Control of Emergencies and Recovery Technical Support Center Operations Support Center WORD:NRCMhTLS.16
TECHNICALSPECIFICATIONS LESSON PLANS LP Num.
Date Title 6900517 6900518 6900519 6900520 6900521 6900522 6900523 6900524 6900525 6900526 6900527 6900528 6900529 6900531 03/15/93 09/15/95 01/25/95 02/06/95 03/30/95 10/29/94 09/15/95 10/14/94 10/24/94 04/01/94 08/04/95 01/08/96 06/05/95 12/10/93 Introduction &Summary Sect 1.0/2.0 Definitions, Safety Limits and Limited Safety System Settings Sect 5.0/6.0 Design Features and Administrative Controls Sect 3/4.0 Applicability Sect 3/4.1 Reactivity Control Systems Sect 3/4.2 Power Distribution Limits Sect 3/4.3 Instrumentation Sect 3/4.4 Reactor Coolant System Sect 3/4.5 Emergency Core Cooling Sect 3/4.6 Containment System Sect 3/4.7 Plant Systems Sect 3/4.8 Electrical Power Systems Sect 3/4.9 Refueling Operations Sect 3/4.11 Radioactive Effluence WORD:NRCMATLS.16
SYSTEMS EXAMBANKQUESTIONS SDP LP Num.
File Title 3
4 5
6 7
8 9
11 13 21 25 26 28 29 40 41 63 68 104 105 6900103 6900104 6900105 6900106 6900107 6900108 6900109 6900111 6900113 6900121 6900125 6900126 6900128 6900129 6900140 6900141 6900144 6900163 6900168 6900117 6900118 SYS01 SYS01 SYS01 SYS01 SYS01 SYS01 SYS01 SYS02 SYS02 SYS02 SYS02 SYS02 SYS02 SYS02 SYS03 SYS03 SYS03 SYS03 SYS03 SYS03 SYS03 Incore Instrumentation Excore Nuclear Instrumentation Full Length Rod Control Rod Position Indication Reactor Coolant System Reactor Coolant Pumps Pressurizer and Relief System Steam Generator Chemical &Volume Control System Emergency Core Cooling System Containment Spray Containment Building Containment Post Accident Evaluation Containment Ventilation and Heat Removal System Component Cooling Water Fuel Pool Cooling, Purification and Ventilation Fuel Handling System Reactor Protection and Safeguards Actuation System Radiation Monitoring and Protection Main and Extraction Steam System Steam Dump System 112 117 6900120 6900122 6900123 123 6900131 127 6900132 130
. 6900133 132 137 140 144 153 155 6900134 6900136 6900138 6900139 6900143 6900145 165 6900154 170 6900157 SYS03 SYS03 SYS04 SYS04 SYS04 SYS04 SYS04 SYS04 SYS04 SYS05 SYS05 SYS05 SYS05 SYS05 Feedwater Heater Vents and Drain Condensate and Feedwater System AuxiliaryFeedwater System Condenser and Circulating Water Main Turbine Control Turbine, Oil, and Gland Seal Turbine Plant Cooling Water System Emergency Diesel Generator and Auxiliaries Main Power Distribution 120 VAC& 125 VDC Distribution Fire Prot, Fire Water &ASD Panel Plant AirSystems.
Intake Cooling Water System Emergency Load Sequencer/Bus Stripping WORD:NRCMhTLS.16
TECHNICALSPECIFICATION EXAMBANKQUESTIONS LP Num.
File Technical Specification Section / Title 6900517 6900518 6900519 6900520 6900521 6900522 6900523 6900524 6900525 6900526 6900527 6900528 6900529 6900531 TECHSPEC TECHSPEC TECHSPEG TECHSPEC TECHSPEC TECHSPEC TECHSPEC TECHSPEC TECHSPEC TECHSPEC TECHSPEC TECHSPEC TECHSPEC TECHSPEC Introduction &Summary Sect 1.0/2.0 Definitions, Safety Limits and Limited Safety System Settings Sect 5.0/6.0 Design Features and Administrative Controls Sect 3/4.0 Applicability Sect 3/4.1 Reactivity Control Systems Sect 3/4.2 Power Distribution Limits Sect 3/4.3 Instrumentation Sect 3/4.4 Reactor Coolant System Sect 3/4.5 Emergency Core Cooling Sect 3/4.6 Containment System Sect 3/4.7 Plant Systems Sect 3/4.8 Electrical Power Systems Sect 3/4.9 Refueling Operations Sect 3/4.11 Radioactive Effluence WORD:NRCMATLS.16
UNIT3 EMERGENCY OPERATING PROCEDURES EXAMBANK Proced.t Date Title 3-EOP-E-0 3-EOP-ES-O.O 3-EOP-ES-0.1 3-EOP-ES-0.2 3-EOP-ES-0.3 6900321 6900322 6900323 6900324 6900325 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB1 3-EOP-ES-0.4 6900326 EOP EB1 3-EOP-E-1 3-EOP-ES-1.1 3-EOP-ES-1.2 3-EOP-ES-1.3 3-EOP-ES-1.4 3-EOP-E-2 3-EOP-E-3 3-EOP-ES-3.1 3-EOP-ES-3.2 3-EOP-ES-3.3 3-EOP-ECA-0.0 3-EOP-ECA-0. 1 3-EOP-ECA-0.2 3-EOP-ECA-1. 1 3-EOP-ECA-1.2 3-EOP-ECA-2.1 3-EOP-ECA-3.1 6900327 6900328 6900329 6900330 6900331 6900334 6900339 6900340 6900341 6900342 6900348 6900349 6900350 6900332 6900333 6900335 6900343 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB1 EOP EB2 EOP EB2 EOP EB2 EOP EB2 EOP EB2 EOP EB2 EOP EB2 3-EOP-ECA-3.3 3-EOP-F-0 3-FR-S.1,2 3-FR-C.1-3 3-FR-H.1-5 3-FR-P.1,2 3-FR-Z.1-3 3-FR-I.1-3 6900345 6900353 6900346 6900347 6900337 6900336 6900338 6900351 EOP EB2 EOP EB2 EOP EB2 EOP EB2 EOP EB2 EOP EB2 EOP EB2 EOP EB2 3-EOP-ECA-3.2 6900344 EOP EB2 Reactor Trip or Safety Injection Rediagnosis Reactor Trip Response Natural Circulation Cooldown Natural Circulation Cooldown With Steam Void In Vessel With RVLMS (QSPDS)
Natural Circulation Cooldown With Steam Void In Vessel (Without RVLMS)
Loss of Reactor or Secondary Coolant SI Termination Post LOCA Cooldown and Depressurization Transfer to Cold Leg Recirculation Transfer to Hot Leg Recirculation Faulted Steam Generator Isolation Steam Generator Tube Rupture Post-SGTR Cooldown Using.Backfill Post-SGTR Cooldown Using Blowdown Post-SGTR Cooldown Using Steam Dump Loss of AllAC Power Loss of AllAC Power Recovery Without SI Required Loss of AllAC Power Recovery With SI Required Loss of Emergency Coolant Recirculation LOCA Outside Containment Uncontrolled Depressurization of AllSteam Generators SGTR With Loss of Reactor Coolant - Subcooled
. Recovery Required SGTR With Loss of Reactor Coolant - Saturated Recovery Desired SGTR Without Pressurizer Pressure Control Critical Safety Function Status Trees Response to Nuclear Generation/ATWS Response to Inadequate Core Cooling Response to Loss of Secondary Heat Sink Response to Imminent Pressurized Thermal Shock Condition Response to High Containment Challenges Response to RCS Integrity Challenges WORD:NRCMATLS.16
OFF NORMALOPERATING PROCEDURE EXAMBANK Procedà Date Title ONOP-003.X ONOP-004 ONOP-004.1 ONOP-004.X ONOP-008 ONOP-011 ONOP-019 ONOP-028.X ONOP-030 ONOP-041.1 ONOP-041.3 ONOP-041.4 ONOP-041.5 ONOP-041.6 ONOP-041.7 ONOP-041.8 ONOP-046.1 ONOP-046.3 ONOP-047.1 ONOP-049.1 ONOP-050 ONOP-059.X ONOP-066 ONOP-067 ONOP-075 ONOP-089 ONOP-100 ONOP-105 6900260 6900255 6900256 6900263 6900217 7100152 7100154 6900207 6900229 6900205 6900212 6900228 6900204 6900254 6900265 6900266 6900232 6900233 6900234 6900243 6900210 6900206 6900246 6900242 6900202 6900248 6900239 6900252 ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB
'NOP EB
, ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP. EB ONOP EB ONOP EB ONOP EB ONOP EB ONOP EB
'ONOP EB ONOP EB ONOP EB Loss of Vital AC ONOP's Loss of Offsite Power System Restoration following Loss of Offsite Power Loss of ~A, ~B, ~C, or ~D 4KV Bus ONOPs Turbine Plant Cooling Water Malfunction Screen Wash System / Intake Malfunction Intake Cooling Water Malfunctions Rod Control System Malfunctions Loss of Component Cooling Water Reactor Coolant Pump Malfunction Excessive RCS Leakage Excessive RCS Activity Pressurizer Pressure Control Malfunction Pressurizer Level Control Malfunction Shutdown LOCA (Mode 3 < 1000 psig or Mode 4)
Shutdown LOCA ( Mode 5 or 6)
Emergency Boration Loss ofBoration Flowpaths Loss of Charging Flow in Modes 1-4 Deviation or Failure of Safety Related or Reactor'rotection Channels Loss of Residual Heat Removal Nuclear Instrumentation Malfunctions High Area Radiation Monitoring Alarms Radioactive Effluent Release AuxiliaryFeedwater System Malfunction Turbine Runback Fast Load Reduction Control Room Evacuation WORD:NRCMATLS.16
~ ~
ADMIN EXAMBANK ProcedA Date Title ADM-031 ADM-051 ADM-102/103 ADM-115 ADM-200 ADM-201 ADM-202 ADM-203 ADM-204 ADM-205 ADM-207 ADM-208 ADM-211 ADM-212 ADM-213 ADM-503 ADM-536 ADM-600 ADM-701 6900012 6900032 6900010 6900006 6900025 6900003 6900022 6900024 6900023 6900005 6900011 6900208 6900320 6900008 6900037 6900029 6900503 6900020 6900007 ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB ADM EB Independent Verification Outage Risk Assessment and Control Instruction/Procedure Change Control Notification of Plant Events Conduct of Operations Operations Procedure Usage Shift Relief and Turnover Shift Operating Practices Operations Narrative Logbooks Control of Switches, Valves &Locks Situations Not Addressed By Procedure Secondary Chemistry Requirements EOP Introduction and EOP/ONOP User',s Guide In-Plant Equipment Clearance Orders Tech Spec Related Equipment OOS Temporary System Alterations Tech Spec Position Statements Health Physics Manual Plant Work Orders WORD:NRCMATLS.16
EMERGENCY PLANIMPLEMENTINGPROCEDURES-EXAMBANK LPP Title 3200001 3200002 3200003 3200004 3200008 3200012 3200013 EPIP EB EPIP EB EPIP EB EPIP EB EPIP EB EPIP EB EPIP EB Emergency Plan Overview Notifications/Communications Emergency Classification
. Radiological Assessment/Protective Action Recommendations Management Control of Emergencies and Recovery Technical Support Center Operations Support Center WORD:NRCMhTLS.16
SIMULATOREVALUATIONSCENARIO GUIDES Date Title Book 1 SES-001 SES-012 SES-013 SES-016 SES-022 SES-023 SES-027 SES-033 SES-035 SES-035.1 SES-036 SES-038 SES-038.1 SES-042 SES-043 SES-045 SES-045.1 SES-049 Book 2 02/26/96 01/03/96 01/03/96 01/08/96 02/26/96 01/08/96 01/09/96 02/26/96 01/04/96 Ol/09/96 01/04/96 02/26/96 03/09/95 03/21/95 01/04/96 02/26/96 02/26/96 02/26/96 Reactor Startup Loss of Feedwater/ATWS RCP Seal Pkg Failure / Loss of Emergency Coolant Recirculation Loss of AllFeedwater/ATWS Plant Startup/Steam Break I.C./ATWS Loss ofTurbine Load/ATWS Loss of Coolant Accident (Mode 4)
Pzr Stm Space LOCA with ECCS and Turbine Trip Failures Small Break Loss of Coolant Accident Plant Startup Power/Small Break LOCA Small Break LOCA/ATWS Unit Shutdown/RCP Seal Failure Loss of Charging/RCP Seal Failure Steam Generator Tube Rupture e
SGTR/Loss of Offsite Power Faulted-Ruptured S/G with Sequencer Failure Faulted-Ruptured S/G / Inadvertent Dilution RCP Seal Failure / SGTR 1
SES-054 SES-055 SES-055.2 SES-055.3 SES-057 SES-057.1 SES-065 SES-065.1 SES-065.3 SES-065.4 SES-065.5 SES-065.6 SES-070.1 02/26/96 01/04/96 12/20/95 12/20/95 02/26/96 02/26/96 11/01/95 02/26/96 10/18/95 11/01/95 11/02/95 06/02/95 03/09/95 Steam Break Outside Containment Steam Break Inside Containment Steam Break I.C./ATWS/Loss of 3A 4KV Bus Ruptured-Faulted S/G I.C.
Depressurization of AllSteam Generators AllS/G's Depress Outside of CNMT/SI Termination Loss ofAllAC and RHR in Mode 5 Loss ofAllAC Power Loss of CCW / Loss of Offsite Power/3A EDG Failure Loss of Offsite Power/RHR in Mode 4 Loss ofAllAC Power/Loss of AllFeedwater Large Break LOCA/Loss of OffsitePower Loss of 3P06/Loss of AllCharging/LOCA WORD:NRCMATLS.16
Distribution Sheet Priority: Normal From: Elaine Walker Distri55.txt ill<>>
Action Recipients:
NRR/DLPM/LPD2-2 K Jabbour Copies:
1 Not Found Not Found Internal Recipients:
RGN 2 FILE 01 NRR/D M/OLHP CQJJ.-.F. CEQT ACRS Not Found Not Found Not Found Not Found External Recipients:
Total Copies:
Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003679744
Subject:
Forwards NRC Forms 396 and 398 for listed employee re renewal of operating license.
Body:
Docket: 05000250, Notes: N/A Docket: 05000251, Notes: N/A Page 1
)
s t
JAN 2 4 2000 L-2000-018 10 CFR 55.57 10 CFR 2.790 Luis A. Reyes Regional Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.
W., Suite 23T85
- Atlanta, GA 30303
Dear Mr. Reyes:
Re: Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 w
The following Florida Power S Light Company (FPL) employee is applying for renewal of his operating license:
NAME ICEN E
~OK~ET Milton A. Newton
~
SOP-20632-1 55-20342 Attached are NRC Forms 396 and 398 for the above listed FPL employee.
By copy of this letter we are providing the original and two copies of this package to Mr. Harold Christensen, as instructed by your staff.
This letter contains personal information, the disclosure of which would clearly constitute unwarranted invasion of personal privacy.
Pursuant to 10 CFR 2.790(a)(6),
we request this letter be withheld from public disclosure.
V ry ruly yours, R. J.
Hovey Vice Presiden Turkey Point Plant OIH Attachments cc: Harold Christensen, Chief, Operations
- Branch, Region II, USNRC (original and 2 copies)
Document Control Desk, Washington D.C.
(w/o attachments)
Senior Resident Inspector, USNRC, Tu'rkey Point Plant (w/o attachments) 0094 jg 7Q'p an FPL Group company h
g(~@3
Priority: Normal From:
Andy Hoy Action Recipients:
Internal Recipients:
RGN2 FILE 01 NRR jgg/(ggg FILE CEN CRS External Recipients:
NOAC Distri94.txt Distribution Sheet ig./s~ <f Copies:
Paper Copy Paper Copy Paper Copy Paper Copy Paper Copy Total Copies:
Item:
ADAMS Document Library:
ML ADAMS"HQNTAD01 ID: 003678354
Subject:
License Restriction Change.
Change to license SOP-2382-8 for TL Wogan requested.
Body:
ADAMS DISTRIBUTION NOTIFICATION.
Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS.
The Document may also be viewed by searching f or Accession Number ML003678354.
Delete PDR from Distribution If IE42 Operator Licensing Examination Reports Page 1
I
't 4
J+
Mr. Luis A. Reyes Regional Administrator, Region II-U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85 Atlanta, Georgia 30323 L-99-281 10 CFR 55.23 DEH(f190
Dear Mr. Reyes:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 L'
The following Florida Power and Light Company (FPL) employee is requesting a
change in his operating license to add a restriction.
NAME Thomas L. Wogan
~IZCENSE SOP-2382-8 OCKET 55-4290 Attached is the NRC Form 396, "Certification of Medical Examination by Facility Licensee,"
and supporting medical documentation for the above listed employee.
This letter and its attachments contain personal information, the disclosure of which would clearly constitute unwarranted invasion of personal privacy.
Pursuant to 10 CFR 2.790 (a)(6),
we request that this letter be withheld from public disclosure.
Very truly yours, R.
. Hovey Vice President Turkey Point Plant OIH Attachments cc:
Harold Christensen, Chief, Operator Licensing and Human Performance
- Branch, Region II, USNRC Document Control Desk, Washington D.C.
(w/o attachments)
Senior Resident Inspector, USNRC, Turkey Point Plant (w/o attachments) an FPL Group company
Distribution Sheet Distri85.txt Priority: Normal From: Elaine Walker Action Recipients:
NRR/DLPM/LPD2-2 KJabbour
'nternal Recipients:
RGN 2 FILE 01 NRR/DlPM/OLHP E CENTER ACRS External Recipients:
Copies:
1 Not Found Not Found 1
Not Found 1
Not Found Not Found 1,
Not Found, Total Copies:
item: ADAMSDocument Library: ML ADAMS"HQNTAD01 ID: 003674931
Subject:
Turkey Point Units 3 and 4 License Restriction Change Body:
PDR ADOCK05000250 V
Docket: 05000250, Notes: N/A Docket: 05000251, Notes: N/A Page 1
5)
'h
L-2000-003 10 CFR 55.23 10 CFR 2.790 Mr. Luis A. Reyes Regional Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta 'Federal Center
,61 Forsyth St.,
SW, Suite 23T85 Atlanta, Georgia 30323
Dear Mr. Reyes:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 i
n 1
The following Florida Power and Light Company (FPL) employee is requesting a
change in his operating license to add a restriction.
NAME George M. Murphy
~IICENEE SOP-20403-2
~K~ET 55-20073 Attached is the NRC Form 396, "Certification of Medical Examination by Facility Licensee,"
and supporting medical documentation for the above listed employee.
This letter and its attachments contain personal information, the disclosure of which would clearly constitute unwarranted invasion of personal privacy.
Pursuant to 10 CFR 2.790 (a)(6),
we request that this letter be withheld from public disclosure.
R.
. Hovey Vice President Turkey Point Plant OIH Attachments CC:
Harold Christensen, Chief, Operator Licensing and Human Performance
- Branch, Region II, USNRC Document Control Desk, Washington D.C.
(w/o attachments)
Senior Resident Inspector, USNRC, Turkey Point Plant (w/o attachments) an FPL Group company
~.Pp<<
k (r~Ar
Ca
Distri66. txt Distribution Sheet Priority: Normal From:
Esperanza Lomosbog Action Recipients:
NRR/DLPM/LPD2-2 K Jabbour Copies:
1 1
Not Found Not Found Internal Recipients:
RGN 2.FILE 01 NRR HP ILE CENTER CRS Not Found Not Found Not Found Not Found Total Copies:
Item:
ADAMS Document Library:
ML ADAMS"HQNTAD01 ID: 993500288
Subject:
Letter forwarding NRC Form 396 and supporting medical documentation fo r M. J.
Matuszewski, license SOP-20402-2.
The employee is requesting a
license change restriction.
Enclosures are withheld, per 10CFR2.790(a
) (6)
~
Body:
PDR ADOCK 05000250 V
Docket:
- 05000250, Notes:
N/A Docket:
- 05000251, Notes:
N/A Page 1
Dkc o v >999 L-99-261 10 CFR 55.23 10 CFR 2.790 Mr. Luis A. Reyes Regional Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85 Atlanta, Georgia 30323
Dear Mr. Reyes:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 The following Florida Power and Light Company (FPL) employee is requesting a
change in his operating license to add a restriction.
um~E Michael J. Matuszewski SOP-20402-2 55-20735 Attached is the NRC Form 396, "Certification of Medical Examination by Facility Licensee,"
and supporting medical documentation for the above listed employee.
This letter and its attachments contain personal information, the disclosure of which would clearly constitute unwarranted invasion of personal. privacy.
Pursuant to 10 CFR 2.790 (a)(6),
we request that this letter be withheld from public disclosure.
Very truly yours, R. J.
Hovey Vice President Turkey Point Plant OIH Attachments CC:
Harold Christensen, Chief, Operator Licensing and Human Performance
- Branch, Region II, USNRC Document Control Desk, Washington D.C.
(w/o attachments)
Senior Resident Inspector, USNRC, Turkey Point, Plant (w/o attachments) qg~gOOZ88 an FPL Croup company
Distri67.txt Distribution Sheet Priority: Normal From:
Esperanza Lomosbog Action Recipients:
NRR/DLPM/LPD2-2 K Jabbour Copies:
1 1
Not Found Not Found Internal Recipients:
RGN 2
. FILE 01 NRR/DIPM/OLHP CENTER Not Found Not Found Not Found Not Found Total Copies:
Item:
ADAMS Document Library:
ML ADAMS"HQNTAD01 ID: 993500294
Subject:
Letter informing of license relinquishment for F.
AD Burke, license OP -21194, effective 991130.
Body:
PDR ADOCK 05000250 V
Docket:
- 05000250, Notes:
N/A Docket:
- 05000251, Notes:
N/A Page 1
PPt DEC 07 1999 L-99-262 10 CFR 50.74 10 CFR 2.790 Luis A. Reyes Regional Administrator, Region II U. S.'Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85 Atlanta, Georgia 30323
Dear Mr. Reyes:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 The following Florida Power 6 Light Company employee is relinquishing her license:
E E
F. A. Burke OP-21194 55-22169 November 30, 1999 This letter contains personal information, the disclosure of which would clearly constitute unwarranted invasion of personal privacy.
Pursuant to 10 CFR 2.790 (a)(6),
we request that this letter be withheld from public disclosure.
Very truly yours, R. J.
Hovey Vice President Turkey Point Plant OIH cc:
Harold Christensen, Chief, Operator Licensing and Human Performance
~ Senior Resident Inspector, USNRC, Turkey Point Plant on FPL Group company gq 35oG 29g gz.c.
PDR.
QO~