ML093520967
| ML093520967 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/15/2009 |
| From: | Tennessee Valley Authority |
| To: | Division of Operating Reactor Licensing |
| References | |
| Download: ML093520967 (24) | |
Text
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT 1
I&C Overview Public Meeting December 15, 2009
Agenda
- Watts Bar Unit 2 Licensing Overview
- Instrumentation and Controls Overview o Safety and Non-Safety Related Systems o Platform Applications at Watts Bar Unit 2 o Platform/Application Licensing o Analysis 2
o Analysis o Questions
- Final Safety Analysis Report (FSAR) o Overview of FSAR Development o Significant Changes Since Watts Bar Unit 1 Licensing o Detailed Discussion of Chapter 7, Instrumentation and Controls o Questions
Watts Bar Nuclear Plant Unit 2 3
Watts Bar Nuclear Plant Unit 2 Licensing Overview
Watts Bar Unit 2 Licensing Overview
- TVA intends to align the licensing and design basis of WBN Units 1 and WBN Unit 2 to the fullest extent practical
- Commission SRM SECY-07-0096 endorsed a license review approach using the current licensing basis for WBN Unit 1 for the review and licensing of WBN Unit 2 4
licensing of WBN Unit 2 Significant changes to licensing approach allowed where backfit rule would be met or as necessary to support dual unit operation
Watts Bar Unit 2 Licensing Overview
- Technical Issues Resolved for Unit 2 as Part of WBN Unit 1 Operating License Review o Original Safety Evaluation Report NUREG-0847 - Watts Bar Units 1 and 2 (June 30, 1982) o Supplemental Safety Evaluation Reports (SSERs) 1-4 (1982-1985),
SSERs 5-20 (1990-1995)
- Generic Letters Bulletins Circulars and TMI Items Resolved for Unit 5
Generic Letters, Bulletins, Circulars and TMI Items Resolved for Unit 2 as Part of WBN Unit 1 Operating License Review
- Corrective Action Programs and Special Programs o Construction deficiencies unique to Watts Bar o Majority resolved for WBN Unit 2 using WBN Unit 1 Precedent o Change to WBN Unit 1 Precedent under Review
- SSER 21 - Baseline for WBN Unit 2 (February 2009)
Watts Bar Unit 2 Licensing Overview
- TVA systematic approach to resolve SER Issues will be via:
- FSAR Amendments submitted as design completes in accordance with Engineering and system waterfall schedule
- Technical Specifications Updates to the templates provided as part of the Operating License Update submitted March 4 2009 6
Operating License Update submitted March 4, 2009
- Additional Correspondence
- Through meetings and/or teleconferences
- Status of outstanding issues will be tracked by periodic updates to TVAs Regulatory Framework Matrix and subsequent NRC SSERs
- Preservation of Licensing Basis using PP-20, Licensing Basis Preservation
Watts Bar Nuclear Plant Unit 2 Instrumentation and Controls Overview 7
Instrumentation and Controls Overview
- Safety Related Systems o Safety Related Actuation Systems 3/4 Solid State Protection System 3/4 Emergency Safety Function Actuation System o Safety Related Control Systems 3/4 Emergency Raw Cooling Water 8
3/4 Emergency Raw Cooling Water 3/4 Component Cooling System 3/4 Auxiliary Feedwater System 3/4 Emergency Gas Treatment Systems 3/4 Post-Accident Monitoring System Temperature Indication o Safety Related Monitoring 3/4 Saturation Monitor 3/4 Reactor Vessel Level Indication System
Instrumentation and Controls Overview
- Non-Safety Related Systems o Non-Safety Related Actuation Systems 3/4 None o Non-Safety Related Control Systems 3/4 Main Feedwater 3/4 Pressurizer Pressure and Level Control 9
3/4 Pressurizer Pressure and Level Control 3/4 Steam Generator Level Control 3/4 Charging and Letdown 3/4 Boric Acid Blender 3/4 Steam Dump 3/4 Secondary Support Systems (Condensate, Heater Drain Tanks, etc.)
o Non-Safety Related Monitoring 3/4 Control Rod Indication (CERPI)
Instrumentation and Controls Overview
- Platform Applications at Watts Bar Unit 2 o Safety Related Actuation Systems 3/4 Eagle 21 3/4 Westinghouse Solid State Protection System 3/4 Sorento - Radiation Monitors (Analog) o Safety Related Control Systems 10 o Safety Related Control Systems 3/4 Foxboro Spec 200 (Analog) o Safety Related Monitoring 3/4 ABB/AC 160 - Common Q Platform (Digital)
Instrumentation and Controls Overview
- Platform Applications at Watts Bar Unit 2 o Non-Safety Related Actuation Systems 3/4 Foxboro I/A o Non-Safety Related Control Systems 3/4 Foxboro I/A 3/4 Westinghouse AEH 11 3/4 Westinghouse AEH o Non-Safety Related Monitoring 3/4 Ronan - Annunciators 3/4 Plant Process Computer 3/4 Bently-Nevada - Vibration Monitoring 3/4 Westinghouse Loose Parts Monitoring
Instrumentation and Controls Overview Safety Related Applications - Actuation Systems Application Platform Type Precedent Deviations Emergency Safety Function Actuation Westinghouse -
Eagle 21 Processor Based WBN 1, SQN,
Diablo Canyon Power Supplies, Board Modifications.
Power Range Nuclear Monitoring Westinghouse (Refurbished)
Analog WBN 1 SRMs /IRMs Thermo Fisher (G
M t i
)
Analog Byron, Catawba, M G i V
l 12 (Gamma-Metrics) 300i McGuire, Vogel Safety System Actuation Logic Westinghouse -
SSPS (Refurbished)
Discrete Logic Various Cont. Purge Isol.
Rad. Mon.
Sorrento (General Atomics)
RM-30AM Analog WBN 1 Transmitters Non-Capillary Rosemount 1154, 1153, 1152 Analog (4-20 mA)
Various Transmitters Capillary Cameron (Barton 764)
Analog (4-20 mA)
WBN 1, Various
Instrumentation and Controls Overview Safety Related Applications - Control Systems Application Platform Type Precedent Deviations Auxiliary Feedwater Foxboro SPEC 200 Analog WBN 1, SQN, Songs, Millstone, Seabrook, Columbia, Calvert Cliffs, Ft. Calhoun, Seabrook, Palo Verde, Turkey Point, Ft. St.
Varain, Yankee Rowe, Clinton, River Bend, Emergency Gas Treat System Misc. Contol (Emergency Raw Cooling Water 13 Grand Gulf, Callaway, Nine Mile, Midland, Oyster Creek, Monticello Peach Bottom, DC Cook, Prairie Island, Conn Yankee, Fitzpatrick, Byron, Surry, Crystal River, Fermi, Perry, etc.
Cooling Water Strainers, Component Cooling Water)
AFW Turbine Speed Control Woodward EGM (Refurbished)
Transmitters Rosemount 1154, 1152 Analog (4-20 mA)
Various
Instrumentation and Controls Overview Safety Related Applications - Monitoring Application Platform Type Precedent Deviations Saturation Monitor and Reactor Vessel Level Indication Common Q (ABB-AC160)
Processor Based Calvert Cliffs, Palo Verde, Calvert Cliffs, Vogle Displays, Processor Module, PC Node Box,
Power Supplies 14 Containment Radiation Monitor Sorrento RM 1000 Processor Based SQN, Duane Arnold Transmitters Capillary (RVLIS)
Cameron (Barton 763)
Analog (4-20 mA)
WBN1, Various
Instrumentation and Controls Overview Non-Safety Related Applications - Control Systems Application Platform Type 2
Feedwater and Steam Generator Level Control Foxboro I/A FCP 270 Version 8.4.1 Processor Based SQN, BFN, Palo Verde, Millstone, North Anna, Surry, Dresden, Quad City, Perry, Turkey Point, St. Lucie, Indian Point, Fort Calhoun, Brunswick, Hope Creek, Hatch, Three Mile Island, Main Yankee Pressurizer Level and Pressure Control Steam Pressure Control Boration Control 15 Charging Control Rod Control Input Condensate Heater Drain Tank Control Misc Ht. Exch. Temp.
and Other Control Turbine Control Westinghouse AEH (Refurbish)
Analog WBN 1, SQN Rod Control Power and Logic Cabinets Westinghouse (Refurbish)
Discrete Logic WBN 1, SQN Transmitters Rosemount 3051, 1152 Digital 3051 Analog 1152 (4-20 mA)
Various
Instrumentation and Controls Overview Non-Safety Related Applications - Monitoring Application Platform Type Precedent Rod Position Indication CERPI Common Q (ABB-AC160)
Processor Based WBN 1, Surry Incore Nuclear Instrumentation Westinghouse WINCISE Processor Based No precedence for entire system.
Process Computer HP RX2660 RTP 8700 Processor Based WBN 1, BFN, SQN Annunciator Ronan X500F Processor Based WBN1 Dos Version 16 X500F Loose Parts Monitoring Westinghouse DMIMS-DX Processor Based Millstone, Crystal River, Diablo Canyon, Wolf Creek, Beaver Valley, Vog Vibration Monitoring Bentley Nevada 3500 Processor Based WBN 1, SQN, BFN Valve Acoustic Monitoring TEC 1414 (Refurbish)
Analog WBN 1, SQN, BFN Radiation Monitors Sorrento RM-1000, RM-80 Processor Based RM-1000 SQN, Duane Arnold RM-80 WBN 1, SQN Transmitters Rosemount 3051, 1152 Digital 3051 Analog 1152 (4-20 mA)
Various
Instrumentation and Controls Overview
- Analysis o Single Point Failure o Segregation Analysis 17
Instrumentation and Controls Overview QUESTIONS 18 QUESTIONS
Watts Bar Nuclear Plant Unit 2 Final Safety Analysis Report 19 y
y p
Final Safety Analysis Report
- Overview of FSAR Development o Basis Amendment 91 - Unit 1&2 FSAR at WBN Unit 1 Licensing o Incorporated Changes - Unit 1 Licensing through UFSAR Amendment 8 o Incorporated Planned Changes Supporting Unit 2 Completion 20 o Chapter 7, Instrumentation and Controls Submittals 3/4 Amendment 95 - November 2009 9 Chapter 7.3 - Engineered Safety Features Actuation Systems 9 Chapter 7.4 - Systems Required for Safe Shutdown 3/4 Amendment 96 - December 14, 2009 9 Chapter 7.1 - Introduction 9 Chapter 7.2 - Reactor Trip System 9 Chapter 7.5 - Instrumentation Systems Important to Safety 9 Chapter 7.6 - All Other Systems Required for Safety 9 Chapter 7.7 - Control Systems
Final Safety Analysis Report
- Significant Changes Since Watts Bar Unit 1 Licensing o Chapter 7.1 - Introduction 3/4 Reactor Coolant System Flow Rate Measurement 3/4 Design Basis Analysis Parameters 3/4 Loose Parts Monitoring o Chapter 7.2 - Reactor Trip System 3/4 Deletion of Neutron Flux Negative Rate Trip 3/4 i
i l
i 21 3/4 Design Basis Analysis Parameters 3/4 Alternate Method for Use of Condenser Steam Dump 3/4 Reactor Coolant System Flow Rate Measurement 3/4 Foxboro I/A o Chapter 7.3 - Engineered Safety Features Actuation System 3/4 Design Basis Analysis Parameters 3/4 Alternate Method for Use of Condenser Steam Dump
Final Safety Analysis Report
- Significant Changes Since Watts Bar Unit 1 Licensing o Chapter 7.5 - Instrumentation Systems Important to Safety 3/4 Plant Process Computer Replacement 3/4 Containment Sump Level Transmitter Replacement 3/4 Safety Injection System Cold Leg Accumulator Level Measurement System 3/4 Common Q/PAMs o Chapter 7.6 - All Other Systems Required for Safety 22 3/4 Plant Process Computer Replacement 3/4 Loose Parts Monitoring System o Chapter 7.7 - Control Systems 3/4 Alternate Means for Monitoring Control or Shutdown Rod Position 3/4 Eliminate Pressurizer Backup Heaters on High Level Signal 3/4 Anticipated Transient without Scram Mitigation System Actuation Circuitry (AMSAC) Replacement 3/4 Foxboro I/A 3/4 WINCISE /Power Distribution Monitoring System (Beacon)
Final Safety Analysis Report
- Detailed Discussion of Chapter 7, Instrumentation and Controls o Line by Line Review of Changes o Basis for Major Changes 3/4 Amendments 3/4 10 CFR 50.59 Evaluations 23
Final Safety Analysis Report QUESTIONS 24