ML082540140
| ML082540140 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/16/2008 |
| From: | Florida Power & Light Co |
| To: | Plant Licensing Branch III |
| Cushing, J S, NRR/DORL/LPLIII-1,415-1424 | |
| References | |
| Download: ML082540140 (24) | |
Text
FPL POINT BEACH NUCLEAR PLANT MEETING WITH NRC ON EPU September 8, 2008 FPL
Agenda
- Introduction
- EPU Overview
° Matrix 1 - Materials and Chemical Engineering
- Matrix 2 - Mechanical and Civil Engineering
- Matrix 3 - Electrical Engineering
- Matrix 4 - Instrumentation and Controls
- Matrix 5 - Plant Systems Matrix 6 - Containment Review Considerations Matrix 7 - Habitability, Filtration, and Ventilation
- Matrix 8 - Reactor Systems Break
" Matrix 9 - Source Terms and Radiological Consequences Analyses
- Matrix 10- Health Physics
" Matrix 11 - Human Performance
- Matrix 12 - Power Ascension and Testing Plan
- Matrix 13 - Risk Evaluation
- Closing Discussion 2
I Introduction Point Beach Attendees
- Steve Hale (FPL) - Engineering Director, Power Uprates
- Jim Peschel (FPL) - Licensing Director
- Liz Abbott (FPL) - Project Director
- Ivy Netzel (FPL)- Licensing Lead, Point Beach EPU
- Norm Hanley (Shaw Stone & Webster) - Engineering Director
- Dave Dominicus (Westinghouse)
- Pat Vaughn (Westinghouse)
- Uriel Bachrach (Westinghouse)
- Andrew Bowman (Westinghouse)
Extended Power Uprate Team
- Core Team in home office with over 200 man-years of nuclear experience
- Uprate implementation experience
- Proven regulatory track record
- Active participant in the development of INPO uprate guidance
- Dedicated engineering team on-site
- Direct interface with System Engineers for system evaluations
- Experienced Shaw Stone and Webster.and Westinghouse Teams
- Have implemented over 40 successful uprates
- Members with specific involvement with Ginna EPU 3
I Introduction Actions to ensure a quality submittal
- Review by senior, experienced engineers in Juno
- Benchmarking against other successful EPU LARs (specifically Ginna)
- Senior level internal calculation review by Westinghouse
- Technical challenge boards
- Review and incorporation of previous RAIs and industry OE as applicable
- Multi-party sequester week reviews
- Technical Challenge Boards
- Integrated LAR review by senior team including independent industry experts
- Senior level FPL corporate review FPL
EPU Overview 17% increase in core power level (modeled after Ginna EPU)
-AST S- EPU Common submittals
- Point Beach has single Technical Specifications and UFSAR
- No significant environmental impacts
- Project organization and implementation plan modeled after successful uprate a Seabrook Aggressive approach to addressing operating experience (INPO, etc.)
- Maintaining or improving margins is a goal for the project
- Extensive review of licensing basis in preparation of the LAR per RS-001 Addressing events even though not in current licensing basis
- Steam Generator overfill analysis FPL
EPU Overview Thermal Design Parameters Current Extended Power Uprate Case 1 Case 2 Case 3 Case 4 1546 1806 1806 1806 1806 NSSS Power, MWt 5275 6162 6162 6162 6162 101 Btuhr 1540 1800 1800 1800 1800 Reactor Power. MWt 5255 6142 6142 6142 6142 106 Btu/hr 89,000 89,000 89,000 89,000 89,000 Thermal Design Flow, loop gpm 67.4 '69.3 69.3 67.6 67.6 Reactor 106 ltb/hr 2250 2250 2250 2250 2250 Reactor Coolant Pressure, psia 6.5 6.5 (8b 6.5 (ab 6.5 (ac 6.5 (ac 0/o Core Bypass, Notes:
- a. Corebypass flowaccountsforthimbleplugsremoved.
Reactor Coolant Temperature, IF "
- b. Ifthnimleplugsareinstalled, thecorebypass flowis4.5%,coreoutlet temperature andcore is595.91F, average Core Outlet 607.2 597.3 ( s97.3 (
K) 615.3 -- 615.3 -
temperatureis561.0,F.
Vessel Outlet 603.5 592.9 592.9 611.1 611.1 c Ifthtdmte plugsareinstalled, thecorebypass flowis 4.5%,coreoutlet temperatureis613.911',
andcoreaverage 0
temperatureis580.3F.
Core Average 577.2 561.8 (b) 561.8 () 581.0 () 581.0 () d. Ifa Nghsteampressure ismorelimting foranalysispurposes,a greater steampressre of8W0 psia,steam 1
574.0 558.0 558.0 577.0 577.0 andsteam flowof8.13x 0 lb/t shotld beassumed.
temperture of518.211', Thisistoenvelope thepossibility that Vessel Average theplantcoud operatewithbetter thanellpected steamgenerator perfornane.
Vessel/Core Inlet 544.5 523.1 523.1 542.9 542.9 eP Steamflowisaffectedbythetwodifferent teedwater temperturas.
544.2 522.9 522.9 542.7 542.7 Steam Generator Outlet Steam Generator .*, :"- ,
Steam Outlet Temperature, OF 518.2 490.8 486.3 511.6 d 507.3 800 626 601 755 (d 727 psia Steam Outlet Pressure, 7.39/8.12 Steam Outlet Flow, 106 lb/hr 6.75 7.36/8.08 (1) 7.36/8.08 (e) Wd.) 7.39/8.11 (e total Feed Temperature, °F 438.1 390.0/458.0 390.0/458.0 390.0/458.0 390.0/458.0 0.10 0.25 0.25 0.25 0.25 max.
Steam Outlet Moisture, 0/b
°/o 0 0 10 0 10
,Tube Plugging Level, 547 547 547 547 547
-F Zero Load Temperature, Hydraulic Design Parameters Mechanical Design Flow, gpmn per 101,200 101,200 loop Minimum Measured Flow, gpm total i82,400U 6 S I PL
EPU Overview
- LAR Submittal-1 1/1/08
- NRC approval of LAR-1/1/10
- Modifications, Unit 1
- Fall 2008.
- Spring 2010, EPU implementation Modifications, Unit 2
- Fall 2009
- Spring 201 1, EPU implementation 7
Matrix 1 Materials and Chemical Engineering Reactor Vessel Material Surveillance Program Analysis updated to address higher fluences Pressure-Temperature Limits and Upper Shelf Analysis updated to address higher fluences Energy Pressurized Thermal Shock Analysis updated to address higher fluences Reactor Internal and Core Support Materials Analysis updated to address higher fluences, temperatures, and fatigue Reactor Coolant Pressure Boundary Materials Analysis updated to address EPU conditions Leak-Before-Break Analysis updated to address higher temperatures Protective Coating Systems (Paints) - Organic Materials Acceptable for EPU Conditions Effect of Power Uprate on Flow Accelerated Corrosion Additional base line inspections, program updated to address changes in flow, pressure, temperature and steam quality Steam Generator Tube Inservice Inspection New RG 1.121 analysis for EPU Steam Generator Blowdown System No changes Chemical and Volume Control System - Including Boron No changes Recovery Reactor Water Cleanup System (BWR) NA 8
Matrix 2 Mechanical and Civil Engineering Pipe Rupture Locations and Associated Dynamic Effects No changes in pipe rupture locations-Dynamic effects being evaluated for EPU conditions with no modifications expected. New break (ASME) criteria being utilized.
Revised Environmental P/T as a result of HELB Pressure-Retaining Components and Component Supports Evaluated for EPU conditions-Modifications required Steam Generator Moisture Separator Changes Several BOP Component Replacements (i.e., FW heaters, FW and CN Pumps, HD Valves)
Pipe Support Modifications for MS and FW Piping Reactor Pressure Vessel Internals and Core Supports Evaluated for EPU conditions-No modifications required Safety-Related Valves and Pumps Evaluated for EPU conditions-Modifications required Addition of Fast Acting FW Isolation Valves Higher capacity AFW Pumps Installed Main Steam Safety Valve Setpoint Change Pressurizer Safety Valve Setpoint tolerence Change Main FW Reg. Valve Trim & Actuator Changes Seismic and Dynamic Qualification of Mechanical and Electrical Evaluated for EPU conditions-No modifications required Equipment 9
Matrix 3 Electrical Engineering Environmental Qualification of Electrical Equipment EQ equipment evaluation for the changes in normal operating and post accident radiation, pressure and temperature effects-No hardware changes expected, documentation packages to be updated to reflect the revised environmental conditions Offsite Power System Grid stability has already been evaluated by the transmission system operator to address the impact of the EPU and transmission system modifications have been proposed to improve system reliability-FPL will provide a copy of the grid stability study to NRC AC Onsite Power System Replacing Main Transformers Modifying Isolated Phase Bus Duct cooling system Effect of EPU on system evaluated utilizing ETAP model-Implementing installation of main generator output breakers and relay setting changes DC Onsite Power System EPU has minimal impact on the DC Onsite Power System-No modifications required Station Blackout Plant response to Station Blackout post EPU is acceptable-No modifications required 10 FPL
Matrix 4 Instrumentation and Controls-Implementing revised setpoint methodology for Reactor Protection System, Emergency Safety Features Systems, and other Emergency Operating Procedure setpoints consistent with NRC expectations and commitments Reactor Trip System Some changes in setpoints Engineered Safety Features Systems Some changes in setpoints Safety Shutdown Systems Some changes in setpoints Control Systems Some changes in setpoints Diverse I&C Systems NA
I Matrix 5 Plant Systems Flood Protection No modifications required Equipment and Floor Drainage System No modifications required Circulating Water System No modifications required Internally Generated Missiles (Outside Containment) No modifications required Internally Generated Missiles (inside Containment) No modifications required Turbine Generator Replacing high pressure turbine steam path (rotating and fixed turbine blades)
Upgrading high pressure turbine control valves Replacing main generator rotors Rewinding main generator stators Updating turbine missile analysis for EPU conditions Protection against Postulated Piping Failures in Fluid Systems Outside Analyses being reconstituted-No new break locations identified, but some changes in Containment pressure/temperature conditions as a result of breaks post EPU. No hardware changes required, but EQ documentation packages will be updated for the revised conditions (See Matrix 3)
Fire Protection Program No modifications required as a result of EPU Pressurizer Relief Tank No modifications required Fission Product Control Systems and Structures No modifications required Main Condenser Evacuation System No modifications required Turbine Gland Sealing System No modifications required Main Steam Isolation Valve Leakage Control System N/A Spent Fuel Pool Area Ventilation System No modifications required Auxiliary and Radwaste Area Ventilation System No modifications required Turbine Area Ventilation System No modifications required 12 FPL
Matrix 5 (cont.)
Plant Systems ESF Ventilation System No modifications required Spent Fuel Pool Cooling and Cleanup System Analysis updated to reflect revised decay heat loads-No modifications required Station Service Water System Analysis updated to reflect revised decay heat loads-No modifications required Reactor Auxiliary Cooling Water Systems Analysis updated to reflect revised decay heat loads-No modifications required Ultimate Heat Sink Analysis updated to reflect revised decay heat loads-No modifications required Auxiliary Feedwater System EPU working with AFW project team to perform a holistic review of system design. EPU analyses based on new 250 GPM motor driven pumps power by 4160 V bus Main Steam Supply System Upgrades to MSIVs Main Condenser No modifications required Turbine Bypass System No modifications required Condensate and Feedwater System Installing fast acting feedwater isolation valves Replacing Condensate Pumps and Motors Replacing Feedwater Heaters Replacing Feedwater Pumps and Motors Replacing selected heater drain piping and valves Gaseous Waste Management Systems No modifications required Liquid Waste Management Systems No modifications required Solid Waste Management Systems No modifications required Emergency Diesel Engine Fuel Oil Storage and Transfer System Analysis updated for EPU, no modifications required Light Load Handling System (Related to Refueling) No modifications required 13 FPL
Matrix 6 Containment Review Considerations Dry Containments Containment response evaluated for EPU conditions Ice Condenser Containments N/A Pressure-Suppression Type BWR Containments N/A Subcompartment Analysis Subcompartment Analysis evaluated for EPU conditions Mass and Energy Release for Postulated LOCA New mass and energy releases developed for EPU conditions Mass and Energy Release for Postulated Secondary New mass and energy releases developed for EPU System Pipe Ruptures conditions Combustible Gas Control in Containment No modifications required Containment Heat Removal Analysis updated to reflect revised EPU heat loads-No modifications required Secondary Containment Functional Design N/A Minimum, Containment Pressure Analysis for ECCS Analysis updated for EPU utilizing GOTHIC Performance Capability Studies (methodology change)-No modifications required 14 FPL
Matrix 7 Habitability, Filtration, and Ventilation Control Room Habitability System Modifications for AST ESF Atmosphere Cleanup System NA Control Room Area Ventilation System Modifications for AST Spent Fuel Pool Area Ventilation System No modifications required Auxiliary and Radwaste Area Ventilation System No modifications required Turbine Area Ventilation System No modifications required ESF Ventilation System No modifications required 15 FPL
Matrix 8 Reactor Systems Fuel System Design No significant fuel design changes (increased axial blanket length). Analyzed and updated for EPU conditions Nuclear Design Analyzed and updated for EPU conditions Thermal and Hydraulic Design Analyzed and updated for EPU conditions Functional Design of Control Rod Drive System Analyzed and updated for EPU conditions, no modifications required Overpressure Protection during Power Operation MSSV Setpoint changes, analyzed for EPU conditions, no modifications required Overpressure Protection during Low Temperature Operation Analyzed for EPU conditions, no modifications required Reactor Core Isolation Cooling System (BWR) N/A Residual Heat Removal System Analyzed for EPU conditions, no modifications required Emergency Core Cooling System Analyzed for EPU conditions, no modifications required. Modifications are required for AST and addressed in AST LAR Standby Liquid Control System (BWR) N/A Decrease in Feedwater Temperature, Increase in Feedwater Flow, Analyzed for EPU conditions, no modifications required Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve Decrease in Feedwater Temperature, Increase in Feedwater Flow, Analyzed for EPU conditions, no modifications required Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve 16 FPL
ýZ
I Matrix 8 (cont.)
Reactor Systems Steam System Piping Failures Inside and Outside Containment Updating HELB licensing basis to GL 87-11. Analyzed for EPU conditions, no modifications required Loss of External Load, Turbine Trip, Loss of Condenser Vacuum, and Analyzed for EPU conditions, no modifications required Steam Pressure Regulator Failure (Closed)
Loss of Non-emergency AC Power to Station Analyzed for EPU conditions, no modifications required, two AFW pumps required Auxiliaries for certain scenarios Loss of Normal Feedwater Flow Analyzed for EPU conditions, no modifications required, two AFW pumps required for certain scenarios Feedwater System Pipe Breaks Inside and Outside Containment Analyzed for EPU conditions, no modifications required Loss of Forced Reactor Coolant Flow including Trip of Pump Motor and Analyzed for EPU conditions, no modifications required Flow Controller Malfunctions Reactor Coolant Pump Rotor Seizure and Analyzed for EPU conditions, no modifications required Reactor Coolant Pump Shaft Break Uncontrolled Control Rod Assembly Withdrawal from a Sub-critical or Low Analyzed for EPU conditions, no modifications required Power Condition Uncontrolled Control Rod Assembly Withdrawal at Power Analyzed for EPU conditions, no modifications required 17 FPL
Matrix 8 (cont.)
Reactor Systems Control Rod Misoperation (System Malfunction or Operator Error) Analyzed for EPU conditions, no modifications required Startup of an Inactive Loop or Recirculation Loop at an Incorrect Temperature, and Flow NA Controller Malfunction Causing an Increase in BWR Core Flow Rate Chemical and Volume Control System Malfunction that Results in a Decrease in Boron Analyzed for EPU conditions, no modifications required Concentration in the Reactor Coolant Spectrum of Rod Ejection Accidents Analyzed for EPU conditions, no modifications required Spectrum of Rod Drop Accidents Analyzed for EPU conditions, no modifications required Inadvertent Operation of ECCS and Chemical and Volume Control System Malfunction Analyzed for EPU conditions, no modifications required that increases Reactor Coolant Inventory Inadvertent Opening of a Pressurizer Pressure Relief Valve or a BWR Pressure Relief Not in current Point Beach licensing basis. However, evaluated for EPU Valve conditions, no modifications required Steam Generator Tube Rupture Radiological analysis addressed in AST. Steam generator overfill not in current Point Beach licensing basis. However, analyzed for EPU conditions and planned AFW modifications Loss of Coolant Accidents Resulting from Spectrum of Postulated Piping Breaks within the Analyzed for EPU conditions, no modifications required Reactor Coolant Pressure Boundary Anticipated Transients Without Scram Analyzed for EPU conditions, no modifications required New Fuel Storage Analyzed for EPU conditions, no modifications required Spent Fuel Storage Analyzed for EPU conditions, no modifications required 18 FPL
Matrix 9 Source Terms and Radiological Consequences Analyses Source Terms for Input into Radwaste Management Systems Analyses Revised based on AST analysis Radiological Consequence Analyses Using Alternative Source Terms See AST Radiological Consequences of Main Steamline Failures Outside Containment for a PWR See AST Radiological Consequences of Reactor Coolant Pump Rotor Seizure and Reactor Coolant See AST Pump Shaft Break Radiological Consequences of a Control Rod Ejection Accident See AST Radiological Consequences of a Control Rod Drop Accident NA for PWRs utilizing AST Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant Outside NA for PWRs utilizing AST Containment Radiological Consequences of Steam Generator Tube Failure See AST Radiological Consequences of Main Steamline Failure Outside Containment for a BWR NA Radiological Consequences of a Design Basis Loss of Coolant Accident including Containment See AST Leakage Contribution Radiological Consequences of a Design Basis Loss of Coolant Accident Leakage from ESF See AST Components Outside Containment Radiological Consequences of a Design Basis Loss of Coolant Accident Leakage from Main N/A Steam Isolation Valves (BWR)
Radiological Consequences of Fuel Handling Accidents See AST Radiological Consequences of Spent Fuel Cask Drop Accidents NA for PWRs utilizing AST 19 FPL
Matrix 10 Health Physics Radiation Sources Addressed in EPU LAR based on AST LAR Radiation Protection Design Features Addressed for EPU conditions Operational Radiation Protection Program Addressed for EPU conditions 20 F-PL
Matrix 11 Human Performance Reactor Operating Training Impact on reactor operating training identified Training for Non-Licensed Plant Staff Impact on training for Non-Licensed Plant Staff identified Operating and Emergency Operating Procedures Impact on Operations Department Procedures identified Human Factors Engineering Impact on Human Factors addressed 21 FPL
Matrix 12 Power Ascension and Testing Plan Power Ascension and Testing Testing plan described Plan on performing pre- and post- EPU testing Specific vibration testing plan being developed 22 FPL
Matrix 13 Risk Evaluation Y
Risk Evaluation Probabilistic Safety Assessment revised to address impact of the EPU EPU has minimal impact on PSA CDF Several modifications will be implemented that will reduce the existing CDF by an order of magnitude and address fire protection issues with AFW 23 FPL
Closing Discussion 24 FPL