ML092440256
| ML092440256 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/25/2009 |
| From: | Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation |
| Orf, T J, NRR/DORL/301-415-2788 | |
| References | |
| Download: ML092440256 (63) | |
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Agenda
- Introduction
- Purpose
- EPU Overview and Schedule
- EPU Parameters
- Unique Features
- Plant Modifications
- Proposed Technical Specification Changes
- RS-OO 1 Matrix Review
- Closing Discussion 2
I=PL
Introduction
- St. Lucie Team Attendees
- Liz Abbott (FPL) - Licensing Director, Power Uprates
- Jack Hoffman (FPL) - Licensing Manager, S1. Lucie EPU
- Eric Katzman (FPL) - Licensing Manager, S1. Lucie Plant
- Jay Kabadi (FPL) - Manager, S1. Lucie Fuels
- Chris Wasik (FPL) - Licensing Supervisor, S1. Lucie EPU
- Jeff Brown (FPL) - I&C Supervisor, S1. Lucie EPU
- Steve Cornell (FPL) - Mechanical Supervisor, S1. Lucie EPU
- Dave Brown (FPL) - Operations Supervisor, S1. Lucie EPU
- Ken Garner (Westinghouse) - EPU Project Manager
- Dale Graves (Shaw) - EPU Project Manager 3
r=PL
Purpose
- Provide Staff with a comprehensive overview of the proposed St. Lucie Unit 1 Extended Power Uprate
- Encourage active dialog between FPL and Staff to gain most benefit from the meeting
- Agree on communication plan going forward F=PL
Uprate Team Experience
- Extended Power Uprate Team
- Dedicated engineering team on-site
- Senior, experienced S1. Lucie design engineers in key positions
- Direct interface with site and fleet engineers for technical and licensing evaluations
- Home office support with extensive nuclear experience
- Specific experience with Uprate LARs
- Uprate implementation experience
- Active participant in the development of NEI uprate guidance
- Experienced Shaw and Westinghouse Teams
- Have implemented over 40 successful uprates
- Members with specific involvement with several up 5
I=PL.
LAR Process
- Benchmarking against other successful uprate LARs (specifically Ginna, Comanche Peak and Millstone)
- Integrated LAR review by senior team including independent industry experts 6
I=PL
UDrate Team - Key Players
- NSSS system & component analyses
- Areva
- Fuel design and safety analyses
- NSSS component analyses (reactor head and pressurizer)
- Shaw
- Balance of Plant (BOP) analyses
- B&W Canada
- Replacement steam generator analyses
- Dose analysis
- Siemens
- Turbine generator evaluations 7
I=PL
EPU Schedule
- LAR Submittal - November 2009
- NRC approval of LAR - January 2011
- Modifications
- Spring 201 0
- Limited scope - performed under 10 CFR 50.59
- NRC approval not required
- No changes in plant operating conditions
- Fall 2011, EPU implementation 8
F=PL.
St. Lucie EPU Specifics
- Second uprate for St. Lucie
- 5.5% stretch power uprate implemented in November 1981
- Core thermal power increase from 2700 MWt to 3020 MWt
- 10% EPU (2700 MWt to 2970 MWt)
- 1.70/0 MUR (2970 MWt to 3020 MWt)
- Safety analysis values
- 3030 MWt (0.30/0 measurement uncertainty)
- 3050 MWt total NSSS power (includes 20 MWt for Rep heat) 9 I=PL
Uprate Paramerers Parameter Value Comments I I I Current value is 365,000 gpm. Minimum Thermal Design Flow measured flow is 390,000 gpm (includes 375,000 (Total, gpm) flow measurement uncertainty of 15,000 gpm)
RCS Tcold (OF) 551 Current value is 549°F SG Tube Plugging (%) °to 10°A> (Avg)
Tube plugging asymmetry of +/- 20/0 between the two steam generators SG Pressure (psia) 856 Best estimate predictions for HP turbine (at Outlet Nozzle) design Steam Generator Based on initial startup testing and EPU 0.1 0/0 Moisture Carryover, (0A>> RSG analysis 10 I=PL
Uprate Parameters
- Four parameter cases developed to establish design parameters
- Case 1: T cold =535°F at 00/0 SGTP
- Case 2: Tcold =535°F at 100/0 SGTP
- Case 3: Tcold =551°F at 0% SGTP
- Case 4: T cold =551°F at 100/0 SGTP 11 I=PL
prate Parameters I
NSSS PCWG Parameters for PSL1 EPU EPU I I Thermal Design Parameters Current (8) I Case 1 I Case 2 I Case 3 I Case 4 NSSS Power (% current) 100 112 112 112 112 MWt - 3050(5) 3050(5) 3050(5) 3050(5) 6 10 Btu/hr - 10,407 10,407 10,407 10,407 Reactor Power MWt 2700 3030(4) 3030(4) 3030(4) 3030(4) 6 10 Btu/hr 9,215 10,339 10,339 10,339 10,339 Thermal Design Flow, loop gpm 185,000 187 ,500(2) 187,500(2) 187 ,500(2) I 187 ,500(2)
Reactor 10 6 1b/hr I 139.3 I 143.8 I 143.8 I 140.8 I 140.8 R~actor Coolant Pressure'l pSla 2250 I 2250 I 2250 I 2250 I 2250 Core Bypass, 0/0 I 3.7 I 4.2(9) I 4.2(9) I 4.2(9) I 4.2(9)
Reactor Coolant Temperature, of Core Outlet - 593.3 593.3 608.2 608.2 Vessel Outlet 594 591 591 606 606 Core Average - 565.2 565.2 580.8 580.8 Vessel Average 571.3 563 563 578.5 578.5 Vessel/Core Inlet 548.5 535 535 551 551 Steam Generator 548.5 534.6 534.6 I 550.6 I 550.6 Outlet 12 FPL.
Uprate Parameters NSSS PCWG Parameters for PSL1 EPU EPU Thermal Design Parameters Current (8) Case 1 Case 2 Case 3 Case4 NSSS Power (% current) 100 112 112 112 112 MWt - 3050(5) 3050(5) 3050(5) 3050(5) 6 10 Btu/hr - 10,407 10,407 10,407 10,407 Steam Generator Steam Outlet 529.1 513.9 510.9 530.6(6) 527.7 Temperature, of Steam Outlet 770(1) 750(1) 890(1,6) 868(1) 878 Pressure, psia Steam Outlet Flow, 106 11.8 12.78/13.36 12.78/13.35 12.84/13.42(6) 12.83/13.40 Ib/hr total Feed Temperature, of 432.4 409.0/441.0 409.0/441.0 409.0/441.0 409.0/441.0 Steam Outlet Moisture, 0.1 0.1 0.1 .0.1 0.1 0/0 max.
Design Fouling Factor, hr. sq. ft. of/Btu 0.00005 0.00005 0.00005 0.00005 0.00005 Tube Plugging Level 10(7) 10(7)
(%) 0 0 0 Notes:
- 1) 13 psi steam generator internal pressure drop incorporated.
- 2) Thermal design flow of 187,500 gpmlhot leg (each steam generator contains one hot leg and two cold legs).
- 3) Minimum measured flow based on a 15,000 gpm flow measurement uncertainty,
- 4) Upper limit on core thermal power.
- 5) Rep net heat input of 20 MWt included in NSSS power.
- 6) If a high steam pressure is more limiting for analysis purposes, a greater steam pressure of 908 psia, steam temperature of 533.1°F, and steam flow of 13.43 x 106 Ib/hr should be assumed. This is to envelop the possibility that the plant could operate with better than expected steam generator performance.
- 7) SGTP of up to 10% average tube plugging with a maximum asymmetry of +1- 2% of the actual average value between steam generators
- 8) and a maximum Current peakobtained parameters tube plugging level of4.4-1, from Tables up to 4.4*2, 12%. 4.4-3, 4.4-4, 5.1-1 and 5.3-1 of the UFSAR. ""i,,:t!;!iiiiii;;i iii!; ;Illiii¥ii!li!ii!:i!lili~
- 9) EPU analysis conservatively increased bypass assumption to 4.2%.
13 F=PL.
EPU Unique Features
- Packaging theMUR with the EPU submittal
- Separate section to address MUR specifics
- Requires a Technical Specification Bases change for St. Lucie Unit 2
- Unit 2 Condensate Storage Tank (CST) TS Bases include a water requirement for Unit 1
- Marked-up Unit 2 TS Bases page will be included in LAR
- No linked submittals 14
. F=PL
'PU Margin Improvements
- Considered analytical and operating margin improvements during EPU scoping phase
- Utilized insights from the plant margin management program
- Analytical margin improvement examples:
- 480V Electrical Bus Voltage Margin Improvement
- Increased RCS flow
- Reduced Linear Heat Rate limit from 15.0 to 14.7 kW/ft
- Reduced Total Integrated Peaking Factor from 1.70 to 1.65
- Operating margin improvement examples:
- Turbine cooling water HX replacement
- Steam bypass control system capacity increase
- Continuous containment purge system upgrade 15 FPL
Application of 10CFR50.59
- 10 CFR 50.59 will be applied to determine when prior NRC review is required
- Preliminary review indicates implementation of plant modifications will not require prior NRC review
- NRC review required for use of:
- Leading Edge Flow Meter (LEFM) installation
- Continuous containment purge system modification
- Safety Injection Tank (SIT) design pressure increase 16 F=PL
Plant Modifications
- Fuel
- EPU will transition to the Areva Advanced CE 14 HIP (High Thermal Performance) fuel design
- Differences with current design include:
- M5' fuel rod cladding and end caps
- Increase in initial helium backfill pressure
- MONOBLOC guide tubes
- M5' exemption to be included in LAR I=PL
Plant Modifications
- Hot Leg Injection Flow Increase
- Continuous Containment Purge System Modification
- Increase Safety Injection Tank Design Pressure
- Setpoints and Scaling
Plant Modifications
- Balance of Plant
- Leading Edge Flow Meter - Measurement Uncertainty Recapture
- Main Feedwater Pump Replacement
- Steam Generator Flow Control Valve Replacement
- High Pressure Feedwater Heater No.5 Replacement
- Heater Drain Pump Rotating Element Replacement
- Heater Drain Valve Replacements
- Moisture Separator Reheater Replacement 19 I=PL
Plant Modifications
- Balance of Plant
- Condenser Upgrades
- Main Steam Isolation Valve Actuator Upgrade
- Steam Bypass Control System Capacity Increase
- Turbine Cooling Water Heat Exchanger Replacement
- Iso-phase Bus Duct Cooling Upgrade
- Main Transformer Cooler Upgrade (1A & 1B)
- 480V Electrical Bus Voltage Margin Improvement
- Setpoints and Scaling F=PL
Plant Modifications
- Turbine Generator
- High Pressure Turbine Steam Path Upgrade
- Low Pressure Turbine Steam Path Upgrade
- DEH Computer Replacement
- Main Generator Upgrade
- Generator Hydrogen Seal Oil Pressure Increase
- Main Generator Hydrogen Cooler Replacement
- Exciter Cooler Replacement 21 I=PL
Plant Modifications
- Replace switchyard disconnect switches
- Replace Midway Substation disconnect switches
- Install spacers between existing Midway conductors 22 I=PL
Proposed Tech Spec Changes
- Section 1.0 Definitions
- Delete definition of "E Average Disintegration Energy"
- Add definition for "Dose Equivalent Xe-133"
- Revise definition for RTP from 2700 to 3020 MWt
- Section 2.0 Safety Limits
- Figure 2.1-1 Rx Core Thermal Margin Safety Limit Four RCPs Operating
- Increase Vessel Flow from 365,000 to 375,000 gpm 23 F=PL
Proposed Tech Spec Changes
- Section 3/4.1 Reactivity Control Systems
- 3.1.1.1 & 3.1.1.2 Shutdown Margin - Change boron concentration from > 1720 to > 1900 ppm
- 3.1.2.2 - Revise boron injection flowpaths to credit RWT only in Mode 3 < 1750 psi and Mode 4
- 3.1.2.7 & 3.1.2.8 Borated Water Sources - Change boron concentration from;::: 1720 to ~ 1900 ppm
- Revise Figure 3.1-1 Min BAMT Volume vs. Stored BAMT Concentration 24 I=PL
Proposed Tech Spec Changes
- Section 3/4.2 Power Distribution Limits
- 3.2.5 DNB Parameters - Change Table 3.2-1 DNB Margin Limits (TSTF-487)
- For Cold Leg Temperature, Pressurizer Pressure and Reactor Coolant Flow Rate, delete numerical limits and reference COLR for values
- Revise Reactor Coolant Flow Rate minimum value and also reference COLR 25 F=PL
Proposed Tech Spec Changes
- Section 3/4.4 Reactor Coolant System
- 3.4.8 Specific Activity - Replace 1DOlE limit with Dose Equivalent Xe-133 limit (TSTF-490)
- 3.4.9 Pressure Temperature Limits - Update P-T Limit Curves for extended period of operation
- 3.4.13 Power Operated Relief Valves - Increase LTOP enable temperature for heatup 26 I=PL
Proposed Tech Spec Changes
- Section 3/4.5 Emergency Core Cooling Systems
- 3.5.1 Safety Injection Tanks
- Change boron concentration from > 1720 to > 1900 ppm
- Change nitrogen cover gas pressure range to from 200 - 250 psig to 230 - 280 psig
- 3.5.2 ECCS Subsystems - Add new LCO for One OPERABLE Charging Pump per ECCS subsystem
- 3.5.4 Refueling Water Tank - Change boron concentration from ~ 1720 to > 1900 ppm 27 I=PL
Proposed Tech Spec Changes
- Section 3/4.6 Containment Systems
- 3.6.1.4 Internal Pressure - Change max pressure from 2.4 psig to 0.5 psig
- 3.6.1.7 Containment Purge System - add new specification similar to Unit 2 to allow for containment purge at power 28 I=PL
Proposed Tech Spec Changes
- Section 3/4.7 Plant Systems
- 3.7.1.3 Condensate Storage Tank - Change CST Minimum Volume from 116,000 to 153,400 gallons
- Current value does not include unusable volume or uncertainties
- EPU value does include unusable volume and uncertainties
- Table 4.7-1, Steam Line Safety Valves - Increase Positive As-Found Tolerance from +1 % to +3%
29 I=PL
Proposed Tech Spec Changes
- Section 3/4.8 Electrical Power Systems
- 3.8.1.1 A. C. Sources - Change EDG frequency criteria from +/- 20/0 to + 1%
- Section 3/4.9 Refueling Operations
- 3.9.1 Boron Concentration - Change boron concentration from > 1720 to > 1900 ppm
- 3.9.11 Spent Fuel Storage Pool - Change boron concentration from > 1720 to > 1900 ppm 30 I=PL
Proposed Tech Spec Changes
- Section 3/4.1 0 Special Test Exceptions
- 3.1 0.1 Shutdown Margin - Change boron concentration from > 1720 to > 1900 ppm
- Section 3/4.11 Radioactive Effluents
- 3.11.2.6 Gas Storage Tanks
- Change 100/E to DOSE EQUIVALENT XE-133
- Reduce noble gas curie limit 31 I=PL
Proposed Tech Spec Changes
- Section 5.0 Design Features
- 5.3.1 Fuel Assemblies - revise paragraph to include M5 cladding material
- 5.6.1 Fuel Storage - Criticality
- 5.6.1.c.1 - Change fuel enrichment from 4.5 to 4.6 weight percent
- 5.6.1.d - Change fuel enrichment from 4.5 weight percent to 4.6 weight percent maximum initial planar average U-235
- Add fuel storage configurations for EPU fuel I=PL
Prop ed Tech Spec Changes
- Section 6.0 Administrative Controls
- 6.8.4.h Containment Leakage Rate Testing Program increase Pa consistent with EPU containment analysis
- 6.9.11 Core Operating Limits Report (COLR) - update references specific to EPU
Other Changes
- COLR changes
- Reduced Linear Heat Rate (LHR) limit from 15.0 to 14.7 kW/ft
- Revised Axial Shape Index (ASI) limits for LHR
- Reduced Total Integrated Peaking Factor (FrT) from 1.70 to 1.65
- Increased refueling boron concentration from
>1720 to >1900 ppm
- Relocate limits of DNB parameters to COLR
- Revise List of Approved Methodologies
- MUR/LEFM
- Add the actions to be taken when the LEFM is degraded or out of-service to the Licensee-Controlled Technical Specification Requirements of UFSAR Section 13.8 34 I=PL
Conformance with RS-001
- Application will follow RS-001 template
- St. Lucie Unit 1 not licensed to the Standard Review Plan
- Licensed prior to the GOes and the SRP
- Designed/constructed based on proposed GOCs published in 1967
- CP issued in 1970; GDCs issued in 1971
- AEC concluded plant meets the intent of the GOCs F=PL
RS-001 Matrix 1 Materials and Chemical Engineering
- RV Material Surveillance Program
- Analysis performed to address EPU fluences - no changes
- P-T Limits & Upper-Shelf Energy
- Limits revised to address EPU fluences, increasing EFPY for extended period of operation
- Pressurized Thermal Shock
- Analysis performed to address EPU fluences - criteria met
- Reactor Internal & Core Support Materials
- Evaluation performed to address the impact of EPU conditions on aging effects - no modifications required
- RCPS Materials
- Assessment performed to address EPU temperature increases - no impact
- Leak-Before-Break
- Current analysis acceptable for EPU conditions
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36 FPL
RS-001 atrix 1 Materials and Chemical Engineering
- Protective Coating Systems (Paints)
- Evaluation performed to address EPU conditions - no changes
- Flow-Accelerated Corrosion
- Program updated to address changes in flow, pressure, temperature and steam quality
- SG Tube Inservice Inspection
- Evaluation performed to addressEPU conditions - no changes
- SG Slowdown System
- Evaluation performed to address EPU conditions - no changes
- Chemical & Volume Control System
- Evaluation performed to address EPU conditions
- Modified BAM Tank requirements 37 I=PL
RS-001 Matrix 2 Mechanical and Civil Engineering
- Pipe Rupture Locations & Associated Dynamic Effects
- Evaluation performed to address EPU conditions - no changes
- Pressure-Retaining Components & Supports
- NSSS Components
- Evaluations performed to address EPU conditions
- Includes piping, supports, reactor vessel, CRDMs, reactor coolant pumps, steam generators and pressurizer
- No changes
- BOP Components
- Evaluations performed to address EPU conditions
- Several BOP component replacements required
- Piping acceptable, some support modifications 38 I=PL
RS-001 Matrix 2 Mechanical and Civil Engineering
- RPV Internals & Core Supports
- Evaluation performed to address EPU conditions - no modifications required
- Safety-Related Valves & Pumps
- Evaluations performed to address EPU conditions - no modifications required
- Seismic & Dynamic Qualification
- Evaluation performed to address EPU conditions - no modifications required
- NSSS Design Transients
- Evaluation performed to address EPU conditions - minor changes to selected transients 39 I=PL
RS-OO Matrix 3 Electrical Engineering
- Environmental Qualification of Electrical Equipment
- EO equipment evaluated for changes in normal and accident conditions
- No equipment replacement required
- Offsite Power System
- Grid stability has been evaluated at EPU conditions
- Contingencies selected conform to SRP 8.2-111.1.f
- Results indicate thermal, voltage and stability performance not degraded by EPU
- AC Onsite Power System
- Evaluation performed to address EPU conditions using ETAP model
- Modifications being implemented to improve margin
- DC Onsite Power System
- Evaluation performed to address EPU conditions - no modifications required
- Station Blackout
- Evaluation performed to address EPU conditions Increasing time for Alternative AC power from 25 min 40 I=PL.
RS-001 Matrix 4 Instrumentation and Controls
- RP, Safety Features Actuation, 8t Control Systems
- Evaluations performed to address EPU conditions
- No changes to RPS or ESFAS setpoints
- Some control system changes required
- Plant Operability
- Detailed transient modeling performed
- Some control system changes required
- Pressurizer Component Sizing
- Evaluation performed to address EPU conditions - no changes required I=PL
RS-001 Matrix 4 Instrumentation and Controls
- MUR/LEFM
- Content and format of MUR LR section consistent with RIS 2002-03
- References/links to related EPU LR sections provided where appropriate
- MUR based on Cameron (Caldon) LEFM CheckPlus System and Cameron Topical Reports ER-80P and ER-157P
- Flow elements have been calibrated at Alden Labs using plant specific piping models 42 I=PL
5-001 atrix 5 Plant Systems
- Flood Protection
- Evaluation performed to address EPU conditions no modifications required
- Missile Protection (Internally Generated & Turbine Generator)
- Evaluations performed to address EPU conditions
- No changes to internal missiles
- Updated turbine missile analysis to address EPU conditions and modified HP and LP turbine steam paths
- Pipe Failures
- Evaluation performed to address EPU conditions no modifications required 43 I=PL
5-001 Matrix 5 Plant Systems
- Fire Protection
- Evaluation performed to address EPU conditions - no modifications required
- Pressurizer Relief Tank
- Evaluation performed to address EPU conditions - no modifications required
- Fission Product Control
- Fission Product Control Systems & Structures
- Evaluation performed to address EPU conditions - no modifications required
- Main Condenser Evacuation System
- Evaluation performed to address EPU conditions - no modifications required
- Turbine Gland Sealing System
- Evaluation performed for EPU conditions 44 I=PL
RS-001 Matrix 5 Plant Systems
- Component Cooling & Decay Heat Removal
- Evaluations performed for increased EPU heat loads on the following systems:
- Spent Fuel Pool Cooling & Cleanup System
- Full core off-load and partial core off-load cases analyzed
- Acceptance criteria met
- Station Service Water System (ICW)
- No modifications required
- Reactor Auxiliary Cooling Water Systems (CCW)
- No modifications required
- No modifications required
- Auxiliary Feedwater System
- No modifications required 45 I=PL
RS-001 Matrix 5 Plant Systems
- Balance-af-Plant Systems
- Evaluations performed and modifications required for the following systems: .
- Main Steam - MSIV actuator upgrade
- Main Condenser - tube staking
- Turbine Bypass - steam bypass capacity increase
- Condensate & Feedwater
- LEFM installation
- FW pump & HD pumps upgrades
- High pressure FW heater
- Valve upgrades (FW control and heater drain)
- Waste Management Systems
- Evaluations performed to address EPU conditions for the following systems - no modifications required:
- Gaseous Waste Management System
- Liquid Waste Management System
- Solid Waste Management System 46 I=PL.
RS-001 Matrix 5 Plant Systems
- Additional Considerations
- EDG Engine Fuel Oil Storage & Transfer System
- Evaluations performed to address EPU conditions - no modifications required
- Light Load Handling System (Related to Refueling)
- Evaluations performed to address EPU conditions - no modifications required 47 I=PL
RS-001 Matrix 6 Containment Review
- Primary Containment Functional Design
- Containment response evaluated to address EPU conditions
- Containment design pressure and temperature limits are met
- Subcompartment Analyses
- Containment response evaluated to address EPU conditions - no changes
- Mass & Energy Release
- EPU releases calculated for LOCA and secondary system pipe ruptures
- Combustible Gas Control in Containment
- Evaluation performed to address EPU conditions - no modifications required I=PL
RS-001 Matrix 6 Containment Review
- Containment Heat Removal
- Analyses performed to address EPU heat loads, no modifications required
- Pressure Analysis for ECCS Performance
- Minimum pressure analysis performed at EPU conditions and 10 CFR 50.46 acceptance criteria met I=PL.
RS-001 Matrix 7 Habitability, Filtration and Ventilation
- Evaluations performed to address EPU conditions for the following systems - no modifications required:
- Control Room Habitability System
- ESF Atmosphere Cleanup
- Spent Fuel Pool Area Ventilation System
- Auxiliary, Radwaste & Turbine Areas Ventilation Systems
- Containment Ventilation Systems
- Modification to the continuous containment purge system to allow for online containment purge 50 I=PL
RS-001 Matrix 8 Reactor Systems
- Fuel System Design
- Areva Advanced CE14 HTP fuel design
- Fuel analyzed at EPU conditions and acceptance criteria met
- Nuclear Design*
- Analyzed at EPU conditions and fuel design limits not exceeded
- Thermal & Hydraulic Design
- Analyzed at EPU conditions and acceptance criteria met I=PL
RS-001 Matrix 8 Reactor Systems
- Emergency Systems
- Functional Design of CR Drive System
- Evaluation performed to address EPU conditions -no modifications required
- Overpressure Protection During Power Operation
- Analyses performed to address EPU conditions - no modifications required
- Overpressure Protection During Low Temperature Operation
- Evaluation performed to address EPU conditions
- Modify LTOP enable temperature for heatup
- Residual Heat Removal System
- Evaluation performed to address EPU conditions - no modifications required 52 I=PL
RS-001 Matrix 8 Reactor Systems
- Non LOCA Analysis Codes
- S-RELAP5 code utilized for transient analysis
- RODEX2 code utilized to model fuel rod
- XCOBRA-IIIC code used to calculate fuel assembly flow and enthalpy
- All Codes approved for use on St. Lucie Unit 1 I=PL
RS-001 Matrix 8 Reactor Systems
- Non LOCA Analyses
- All events analyzed/evaluated at EPU conditions and specific acceptance criteria met
- Increase in Heat Removal by the Secondary System
Inadvertent Opening of SG Relief or Safety Valve
- Steam System Piping Failures Inside & Outside Containment
- Decrease in Heat Removal by the Secondary System
- Loss of External Load
- Loss of AC Power to the Station Auxiliaries
- Loss of Normal Feedwater Flow
- Feedwater System Pipe Breaks
- Loss of Forced Reactor Coolant Flow 54 FPL
RS-001 Matrix 8 Reactor Systems
- Non LOCA Analyses (continued)
- RCP Rotor Seizure
- Uncontrolled CR Assembly Withdrawal from Subcritical or Low Power Startup Condition
- Uncontrolled CR Assembly Withdrawal at Power
- Control Rod Misoperation
- CVCS Malfunction
- Spectrum of Rod Ejection Accidents
- Inadvertent Opening of Pressurizer PRV
- SG Tube Rupture
- Anticipated Transients Without Scrams 55 I=PL
RS-001 Matrix 8 Reactor Systems
- Small Break Loss of Coolant Accident (LOCA)
- Performed using Areva Appendix K model
- Credited increased SIT pressure
- All acceptance criteria met
- Large Break Loss of Coolant Accident (LOCA)
- Performed using Areva realistic LBLOCA methodology
- All acceptance criteria met
- Post-LOCA Long-term Cooling
- Performed using Westinghouse post-LOCA LTC model
- Consistent with methodology used for Waterford to address Staff concerns
- Minimum hot leg injection flow increased from 190 gpm to 250 gpm 56 I=PL
5-001 Matrix 8 Reactor Systems
- Fuel Storage
- New Fuel Storage
- Analyzed at 4.6 weight percent enrichment {planar averagS?}
- All acceptance criteria met
- Spent Fuel Storage
- Analyzed at 4.6 weight percent enrichment {planar averagS?}
- All acceptance criteria met
- Analyses available
- Additional Reactor Systems
- Loss of Residual Heat Removal at Midloop
- Evaluated for higher EPU decay heat load
- Developed new time to boil curves
- Natural Circulation Cooldown
- Analyzed at EPU conditions
- All acceptance criteria met 57 I=PL
RS-001 Matrix 9 Source Term and Radiological Consequences
- Source Terms for Radwaste Systems Analyses
- Source term revised for EPU conditions
- Radiological Consequences Analyses Using Alternate Source Terms
- AST previously approved for St. Lucie 1
- Events analyzed for EPU using same methodology
- Waste Gas Decay Tank Rupture
- Analysis performed for EPU conditions
- Dose limits consistent with BTP 11-5 58 I=PL
RS-001 Matrix 10 Health Physics
- Occupational & Public Radiation Doses
- Doses determined at EPU conditions
- Results acceptable, no modifications required 59 I=PL
RS-001 Matrix 11 Human Performance
- Programs, procedures, training and plant design features related to operator performance evaluated to address EPU conditions
- Evaluation responds to NRC questions regarding changes to:
- Emergency & Abnormal Operating Procedures
- Operator Actions Sensitive to Power Uprate
- Control Room Controls, Displays and Alarms
- Safety Parameter Display System
- Operator Training Program and Simulator 60 r=PL
RS-001 Matrix 12 Power Ascension and Testing Plan
- Approach to EPU Power Level & Test Plan
- Test plan includes:
- Augmented start-up testing from hot zero power to current 100%
power level
- Incremental power ascension from current 1000/0 power level to EPU conditions
- Post modification testing
- Additional testing (e.9., vibration monitoring)
- Compared EPU testing plan to original start-up testing Numerous transients evaluated using CENTS model Consistent with SRP 14.2.1, Generic Guidelines for EPU Testing Programs 61 I=PL
RS-001 Matrix 13 Risk Evaluation
- Risk Evaluation of EPU
- PRA models updated for EPU conditions
- Additional hardware modifications and human actions being evaluated to reduce EPU effects 62 I=PL