ML022340608
| ML022340608 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 08/08/2002 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022340608 (14) | |
Text
Committed to Nuclear Excellence KNPP/NRC Meeting Covering:
Licensing Submittals for Fuel Transition and Power Uprates (MUR and Stretch)
August 8, 2002 Rockville, MD ENCLOSURE 2
Committed to Nuclear Excellence Participants KNPP Participants
- Jerry Riste - Licensing Manager
- Harv Hanneman - Power Uprate Project Manager
- John Holly - Analytical Lead for AST, Fuel Transition, and Power Uprate
- Lynne Gunderson - Power Uprate Licensing Lead
- Ted Maloney - Licensing Engineer
- NRC Participants Excelln Committed to Nuclear Agenda
"* Purpose
"* Overview
"* Submittals Associated with Power Uprate
- Alternate Source Term (AST) Submittal Status
- Core Operating Limits Report (COLR) Status
- Fuel Transition Status
- Gothic 7.0 Containment Analysis Methodology
- Measurement Uncertainty Recapture (MUR) Uprate
- Stretch Uprate
- License Amendment Schedules/Interdependencies
- Summary/Vrap-Up
Commrtted toNuclear Excellence Purpose Update the NRC Staff on recent and planned submittals that support power uprates including:
- AST, COLR, and Fuel Transition (already submitted)
- Gothic 7.0, MUR, and Stretch (proposed submittals)
- Discuss individual submittal contents and proposed schedule
- Discuss the integrated analyses, schedule, and interdependencies
- Obtain NRC feedback 4
Commifted ro Nuclear xcellence Overview
"* Transition to Westinghouse Fuel (April 2003)
"* Ta*,e increase (April 2003)
"*KNPP originally designed for higher power
"* A 7.4% Power Uprate in two steps
- Measurement Uncertainty Recapture Uprate (1.4%)
"*Submittal December 2002
"*Implementation May 2003
- Stretch Power Uprate (additional 6%)
"*Submittal February 2003
"*Implementation December 2003
"* Submittals/analyses interdependencies
Conmmffed fto c *cl nc Overview Gothic 7.0 Stretch 09/02 03/03 02/03 12/03 MUR 12/02 04/03 Fuel Transition 7102 02103 KNPP Submittal Interdependencies Co-ffrredroNuclearExcellence AST Submittal Overview of submittal
- Original submittal sent 03/19/02
- Selective Implementation
- RAI Responses
- Approval needed by 12/02
- Links to other submittals/schedule:
- Fuel transition radiological analyses based on AST
- MUR uprate will use the same AST analyses
- AST analyses will be evaluatedlreperformed for Stretch 7
Committed to NuclearExWIDEl)
COLR Submittal Overview of submittal
- LAR 185 submitted 07/26/02
- Standard COLR format
- Approval needed by 02/03 Links to other submittals/schedule:
- Fuel transition assumed COLR was approved
- COLR to be used for Cycle 26
- MUR and Stretch LARs will also assume COLR Committed to Nuclear E eItt n Fuel Transition Submittal Overview of Submittal
- LAR 187 submitted 07/26/02
- Fuel transition from FRA-ANP to Westinghouse 422V+
- Reload Transition Safety Report (RTSR)
- Fuel Analysis (100.6% of 1772 MvWt with Tav,, band of 556.3°F - 573.0°F).
- LOCA and non-LOCA accident analyses performed at 7.4% uprate (100.6% of 1772 MWt with T., band)
Committed to Nuclear ExcellenteD Fuel Transition Submittal Overview of Submittal
- Radiological accident analyses use AST (102% of 1650 MWt)
- Technical Specification and COLR changes
- Actual Cycle 26 Reload Safety Evaluation and COLR need to be completed prior to 2003 Refueling Outage
- Approval needed by 02/03 I0 NMC--"
Committed to Nuclear Excoelence Fuel Transition Submittal Links to other submittals
- Requires approval of AST and COLR
- Provides the LOCA and non-LOCA accident analyses for MUR and Stretch Uprates
- The LAR 187 LOCA and non-LCOA accident analyses will be referenced in the MUR and Stretch Uprate submittals II
Commotted to Nuclear Exce once" Gothic 7.0 Submittal Overview of Proposed Submittal
- Gothic 6.0 containment evaluation model approved for KNPP DBA's, LOCA, and MSLB
- Gothic 7.0 with MDLM required for power uprate containment analysis
- Submittal planned for 09/02
- Approval needed by 03/03 Links to other submittals/schedule:
- Required for stretch uprate containment analysis only 12 Canm-rradro Nuclear Exee e Gothic 7.0 Submittal Technical Discussion Points
- Mist Diffusion Layer Model (MDLM) used for heat and mass transfer
- MDLM validated against 8 data sets from 5 different test facilities
- KNPP containment analysis DBA's are covered by the validation database
- Conservative factor applied to MDLM based on 95/95 statistics
Commtaed to Nuclear facedenCe Gothic 7.0 Submittal Technical Discussion Points
- Code version upgrade has minimal impact on results
- MDLM has a small impact on LOCA results and reduces MSLB peak pressure by 2 psi
- MDLM conceptual model similar to that used in AP600 containment model 14 Commtted to Nuclear Excellence Proposed MUR Uprate Submittal
- Submittal to consider RIS 2002-03, MUR power uprate guidance AMAG Crossflow Ultrasonic Flow Measuring Device (UFMD):
- Clamp on system (no spool piece)
- Electronics Unit takes/receives data and calculates correction tactors for venturi-measured FW flow and FW temperature.
- Input to the PPCS for RTO calculation
- Supports a power measurement uncertainty ot +/-0 6% allowing a 1 4% increase in licensed RTP from 1650 MWt to 1673 MWt
Ejc IIIn Committed to Nuclear Proposed MUR Uprate Submittal Technically supported by CENPD-397-P-A, which was approved March 20, 2000, and is referenced in the following approved MUR uprates:
- Salem SER 05/25/01
- Hope Creek SER 07/30/01 16 Committed roNuclear xce Ince Proposed MUR Uprate Submittal Accident and Transient Analyses
- Non-LOCA transients will reference Fuel Transition submittal (100.6% of 1772 MWt)
- LOCA will reference Fuel Transition submittal (100.6% of 1772 MWt)
- Radiological analyses will reference AST submittal (102% of 1650 MWt)
- Containment Integrity analysis will reference RSG (50.59) (102% of 1650 MWt) 17
eDceSlec_
Committed to Nuclear Proposed MUR Uprate Submittal Component Integrity and Design
- New analyses supporting the 7.4% uprate and will bound the MUR Electrical Equipment Design
- Evaluated for 7.4% uprate and will bound the MUR
- Grid loading and stability studies performed by ATC for 7.4% uprate and will bound the MUR
- No electrical equipment changes expected for MUR is NMC-F Committed ro Nuclear Exce/nCe Proposed MUR Uprate Submittal
- System Design
- Evaluated for 7.4% uprate and will bound the MUR Other
- Operations procedure and training changes
- Simulator changes
- Changes to protection system settings and emergency settings 1)
7 Conoraedto Nuclear Etc1e Proposed MUR Uprate Submittal Expected License and Technical Specification Changes:
- Operating License, Maximum Power Level will change to 1673 MWt
- Definition of Rated Power will change to 1673 MWt
- Methods for the COLR will include CENPD-397-P-A 20 NM Commrted to NuclearExce, ED Conclusion MUR Uprate Summary and conclusion for MUR
- A 1.4% increase to a rated power of 1673 MWt
- Achieved using AMAG Crossflow UFMD that has an NRC approved topical report
- RIS 2002-03 guidance will be considered
- Links to other submittals
"*Relies on analyses from AST and Fuel Transition
"*Assumes the COLR is approved 2!
N1*
Committed toNuclear 1elne "
Conclusion MUR Uprate MUR Uprate Schedule
- LAR submittal in December 2002
- UFMD installation and commissioning complete by March 2003
- Approval needed by April 2003 for implementation in May 2003 Commilred to Nuclear Excel1ee Stretch Power Uprate Overview
- Increase RTP by 6.0% from 1673 MWt to 1772 MWt Links to previous submittals:
- AST (uses methodology)
- Fuel Transition (LOCA and non-LOCA Accident Analysis)
- Gothic 7.0 (uses methodology)
Commotted to NuclearExcellence Stretch Power Uprate Overview Minimal Plant Modifications
- FW valve trim change
- I&C setpoint/range changes
- Certain turbine bolting changes Proposed submittal content
- Standard Westinghouse format for submittal (e.g.
Byron/Braidwood)
- References AST, Fuel Transition, and Gothic 7.0 analyses and methodologies
- New analyses for systems/components, containment integrity, and radiological analyses 24 NM Commttred to NuclearExca 2, I)
Stretch Power Uprate Overview
- Stretch Uprate Schedule
- LAR submittal in February 2003
- Approval needed by November 2003 to support implementation in December 2003 25
Committed to Nuclear Excellence Summary/Wrap-up KNPP Submittal Interdependencies 26 Commmtted to NuclearExcelence I Summary/Wrap-up
"* Several submittal interdependencies
"* Timely reviews and approvals needed to meet power uprate schedules
"* NRC Feedback