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Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23173A0472023-06-28028 June 2023 SLRA - NRC Presubmittal Meeting Slides - 6-28-23 ML23173A0462023-06-28028 June 2023 DNPS SLR Pre-submittal Meeting Presentation Rev. 1 ML23145A1322023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - Constellation Slides ML23165A0242023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - NRC Slides ML23055A2712023-03-0202 March 2023 March 2, 2023, Preapplication Meeting to Discuss Planned Amendments to Adopt TSTF-505 and 10 CFR 50.69 (EPID L-2023-LRM-0007) - Slides ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1822021-07-13013 July 2021 and Quad Cities Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8572020-08-25025 August 2020 Quad 2019 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17156A7972017-06-0505 June 2017 Presentation for 2016 Dresden Nuclear Power Station EOC Open House ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16189A4332016-07-12012 July 2016 July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan ML16189A2552016-07-0707 July 2016 Annual Assessment Meeting/Open House (Hand Out) ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15013A1562015-01-14014 January 2015 Meeting Slide Regarding Dresden Nuclear Power Station Pre-Application Meeting for Providing Natural Gas as a Primary Fuel to Station Auxiliary Heating Boilers RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014 Transmittal of Proprietary Meeting Slides ML14167A4122014-06-17017 June 2014 NRC Slides for Quad Cities 2013 EOC Public Meeting ML14232A7852014-05-19019 May 2014 Fuel Transition License Amendment Request Pre-Submittal Update Meeting ML13149A2062013-05-22022 May 2013 NRC Slides from Public Meeting ML12164A5962012-06-12012 June 2012 Annual Assessment Meeting Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1203301242012-02-0909 February 2012 Handout for Public Meeting on February 9, 2012 (Slides) ML1109602872011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Assessment Presentation (Short) ML1016800822010-06-15015 June 2010 Annual Assessment Meeting, Reactor Oversight Program - 2009, Slides ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML0914003382009-05-14014 May 2009 Slides Presented at the Dresden Station 2008 EOC Public Meeting ML0911802252009-04-0707 April 2009 NRC - Quad Cities Annual Assessment Meeting Slides ML0911802142009-04-0707 April 2009 NRC End-of-Cycle Meeting Slides ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. ML0814405062008-05-22022 May 2008 EOC Summary Meeting Slides ML0812209792008-04-30030 April 2008 Meeting Slides, Dresden Annual Assessment Meeting, Reactor Oversight Program - Cy 2007. ML0714404642007-05-23023 May 2007 End-of-Cycle Meeting - NRC Slides 2024-01-30
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23251A0782023-09-0606 September 2023 DRE1 Decom Pre-Submittal Slides ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23173A0472023-06-28028 June 2023 SLRA - NRC Presubmittal Meeting Slides - 6-28-23 ML23173A0462023-06-28028 June 2023 DNPS SLR Pre-submittal Meeting Presentation Rev. 1 ML23145A1322023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - Constellation Slides ML23165A0242023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - NRC Slides ML23055A2712023-03-0202 March 2023 March 2, 2023, Preapplication Meeting to Discuss Planned Amendments to Adopt TSTF-505 and 10 CFR 50.69 (EPID L-2023-LRM-0007) - Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML22053A2912022-02-22022 February 2022 NRC Slides for February 25, 2022 Meeting - Acceptance Review of Proposed Alternative to Adopt ASME Code Case N-921 at Dresden and Quad Cities ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1822021-07-13013 July 2021 and Quad Cities Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8572020-08-25025 August 2020 Quad 2019 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18207A1882018-07-26026 July 2018 Slides for Dresden 2017 EOC Open House ML18086A8432018-03-27027 March 2018 NUREG-1021, Revision 11 Implementation ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17156A7972017-06-0505 June 2017 Presentation for 2016 Dresden Nuclear Power Station EOC Open House ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16189A4332016-07-12012 July 2016 July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan ML16189A2552016-07-0707 July 2016 Annual Assessment Meeting/Open House (Hand Out) ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15135A4252015-05-19019 May 2015 EOC Mtg Slides ML15013A1562015-01-14014 January 2015 Meeting Slide Regarding Dresden Nuclear Power Station Pre-Application Meeting for Providing Natural Gas as a Primary Fuel to Station Auxiliary Heating Boilers RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014 Transmittal of Proprietary Meeting Slides ML14167A4122014-06-17017 June 2014 NRC Slides for Quad Cities 2013 EOC Public Meeting ML14232A7852014-05-19019 May 2014 Fuel Transition License Amendment Request Pre-Submittal Update Meeting ML13149A2062013-05-22022 May 2013 NRC Slides from Public Meeting ML12164A5962012-06-12012 June 2012 Annual Assessment Meeting Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1205906462012-03-0505 March 2012 February 9, 2012 - Summary of Meeting with Exelon Nuclear Regarding Future Submittal of Amendment to Use Netco Spent Fuel Pool Inserts ML1203301242012-02-0909 February 2012 Handout for Public Meeting on February 9, 2012 (Slides) ML11201A2132011-07-20020 July 2011 Summary of Public Meeting to Discuss Exelon'S Plans for Implementing an Electronic Document Control System (Edocs) for Use by NRC Inspectors with U.S. Nuclear Regulatory Commission (NRC) Region III Staff ML1113202162011-05-11011 May 2011 Slides for Dresden Nuclear Power Station End-Of-Cycle Public Open House ML1109602782011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Annual Assessment Meeting Presentation (Long) ML1109602872011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Assessment Presentation (Short) ML1016800822010-06-15015 June 2010 Annual Assessment Meeting, Reactor Oversight Program - 2009, Slides ML1012000332010-04-28028 April 2010 Annual Assessment Meeting Slides ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML0914003382009-05-14014 May 2009 Slides Presented at the Dresden Station 2008 EOC Public Meeting 2024-01-30
[Table view] |
Text
. J. - ;i, Exe 1bnSM Nuclear Quad Cities Unit 1 (QC1)
Steam Dryer Instrumentation October 19, 2004 1
ia Exe krn.M Nuclear Introduction John Nosko Project Director, Steam Dryer Replacement 2
- I Agenda Exe krn.M Nuclear
- Steam Dryer Instrumentation Plan
- I Exe k5nSM Nuclear Steam Dryer Instrumentation Plan Keith Moser Corporate Asset Management Engineer 4
Topics Exek(n.
Nuclear
- Purpose of Dryer Instrumentation
- Static and Impact Testing
- Sensor Selection and Placement 5
Industry Experience ExekOnsm Nuclear
- Steam dryer degradation has been experienced across the BWR fleet
- GE and other utilities have instrumented dryers to collect data under operational conditions
- Exelon will collect data on the QC1 steam dryer to be used in a comprehensive approach to analyzing steam dryer loading 6
Purpose of Dryer Instrumentation Exekrn.m Nuclear
- Find areas on the steam dryer with the highest pressure loading
- Pressure sensors placed at high stress locations
- Verify adequacy of the new steam dryer design
- Strain gauges located to identify maximum stress locations
- Accelerometers located to identify maximum displacement locations
- Identify steam dryer modal properties
- Impact testing on steam dryer
- Gain information about the source(s) of loading
- Sensors on main steam lines (MSL)
I Use of Collected Data Exekn SM Nucl ear
- Validate structural adequacy of QC1 steam dryer
- Analyze data from pressure transducers, strain gauges, and accelerometers against design calculations
- Validate design load for QC1 replacement dryer
- Benchmark predictive tools
- Sensors on the dryer and MSLs are the most comprehensive to date
- Acoustic circuit with MSL and water reference leg data will be compared against in-vessel data points
- Scale model test methodology will be benchmarked against QC1 data
- GE/LMS International acoustic FEM will be benchmarked against the QC1 data 8
Static and Impact Test on Dryer ExekOn.m Nuclear
- Ambient and submerged tests at fabricator
- Hammer testing of major parts (hoods, skirt, cover plate, drain channels)
- Frequencies and mode shapes of the as-built steam dryer
- Testing to be performed before and after sensor installation
- Test results will be compared with analytical model
- Static testing of strain gauges 9
Sensor Selection and Placement (Steam Dryer) Exe kn.M Nuclear Dryer Sensor Locations and Quantities Location Strain Gauges Pressure Sensors Accelerometers Total Drain Channel 2 2 Outer Hood Panel - 270 Deg. 13 13 Outer Hood Panel - 90 Deg 2 5 7 1st Bank Side Panel - 270 Deg 1 1 2nd Bank Hood Panel 1 1 2nd Bank Side Panel 1 1 2 3rd Bank Hood Panel 1 1 Tie Bar 2 2 Skirt 2 4 2 8 Dome 1 1 Dryer Motion Horizontal Motion 4 4 Overall Totals 9 27 6 42 10
Sensor Selection and Placement (MSLs) Exe ksnSM Nuclear Main Steam Line Sensor Locations and Quantities Location Strain Gauges Total MSL-A - 3 Pairs 6 MSL- B 12 Pairs 24 MSL- C 3 Pairs 6 MSL-D 3 Pairs 6 Overall Total 42 Notes:
- One pair of sensors includes one circumferential gauge and one longitudinal direction gauge at the same location. The circumferential gauge is used to measure the oscillating pressure. The longitudinal gauge will be used to measure the stress due to piping vibration and to correct the pressure measurement due to the Poisson's ratio effect.
11
Sensor Selection and Placement (Past Installations) ExeIOn..,
Nuclear I Strain Gauges I Pressure Sensors I Accelerometers I
_ WOq BWR Location BMD 251-ldl a5tdn 251 251 in_
Drain Channel Skirt 7 ...
4 Dryer Bank Cover Plate Dryer Support Rin5 2 _ _
4 0_I
_ 8 Seismic Block BM.: Domesti Pla-n_ BW F FoeinPln 147M Tie Bar Dome Total Sens I Main Steam Line Note: Previous installations and data collected on plants at original licensed thermal power levels 12
Sensor Selection and Placement (Steam Dryer - 2700 View) Exek~nSM Nuclear MAVf 'et tO jf i nltWs)
Z21is F*#c.! M: vkC)¢ Cg 13 COt-z
Sensor Selection and Placement (Steam Dryer - 900 View) Exe 1n.M Nuclear X . iy T uvt4 3* up7Dw 4'
'ROX V-AC. ( LCAO4*S TO-AA 4-VTW) 14 Co3
Sensor Selection and Placement (Steam Dryer - Top View) Exek6nSM Nuclear 2W 15 C-OL
ExelInSM Nuclear Steam Dryer Sensors Mike Mustafa Corporate Engineering Projects 16
Topics Exe InSM Nuclear
- Pre-operational Sensor Testing
.s, I Sensor Specifications Exe krnsm Nuclear Dryer Pressure Sensors:
- Maximum Operating Temperature: 660 degrees F
- Maximum Operating Pressure: 1050 pounds per square inch (psi) at 550 degrees F
- Gamma Flux: 101'erg/g (no effect)
- Neutron Flux: 1018 n/cm2 (no effect)
Dryer Accelerometers:
- Maximum Operating Temperature: 1200 degrees F
- Maximum Operating Pressure: 1160 psi at 570 degrees F
- Gamma Flux: 1011erg/g (no effect)
- Neutron Flux: 1018 n/cm2 (no effect) 18
Sensor Specifications (cont.) Exek6,n Nuclear Dryer Strain Gauges:
- Maximum Operating Temperature: 600 degrees F
- Maximum Operating Pressure: greater than 1100 psi
- Radiation: No vendor data available, however, the same transducers were used in the past with material modifications for thermal expansion compatibility with dryer material Main Steam Line Strain Gauges:
- Maximum Operating Temperature: 650 degrees F 19
Sensor Cable Routing (Steam Dryer - 2700 View) Exe I(nSM Nuclear 20 Cos
Sensor Cable Routing (Steam Dryer - 900 View) Exer In Nuclear 21 COW~
Wiring Overview Exe InnM Reactor building 595 Nuclear elevation on the South side near the Located in the CRD banks.
Located within top elevation of 10 feet of the the drvwell.
drywell Steam Dryer I Strain Gauge I I Pressure I Transducer I I IAccelerometer I I - _I - _- -_ _ -_ _
Contains the signal Contains charge conditioning converters for equipment- galvanic Accelerometers and separators for PT and Dynamic Pressure JBI and JB2 contain Acc, amplifiers for all Sensors. Wheatstone bridges sensors.
for completing the Strain Gauge circuits.
PT and Acc signals pass through.
Note:
PT - Pressure Transducer Acc - Accelerometer SG - Strain Gauge MSL - Main Steam Line 22
Wiring Overview (cont.)
U0 Exektnsm Nuclear
- Installation will be reviewed under 10 CFR 50.59 process and normal plant modification procedures
- Using an existing vessel penetration with plug removed - penetration meets American Society of Mechanical Engineers (ASME) Code requirements
- Cables will be routed through existing vessel penetration
- No historical loose parts issues resulting from instrumented dryers in the industry
- Quantity and configuration of instrumentation was established to compensate for potential failed sensors 23
Pre-operational Sensor Testing Exekrnm Nuclear
- Autoclave tests on dryer sensors prior to assembly in the strings
- Function check of the data acquisition system prior to shipment to site
- Function check of the sensors after assembly
- Insulation resistance test upon arrival at US Tool &
Die
- Resistance testing and functional check after installation on the dryer
- Resistance testing and functional check at site 24
Summary Exe InSM Nuclear
- Other utilities have successfully instrumented dryers for data collection
- No loose parts have been generated in the industry as a result of instrumenting steam dryers
- Instrumentation design configuration will allow for useful data collection if some sensors should fail
- Installation requires no new vessel or containment penetrations 25
Exe krn.M Nuclear Refined Acoustic Model Keith Moser Corporate Asset Management Engineer 26
Refined Acoustic Model ExekrnSM Nuclear
- Exelon is responding to comments and a request for additional information from the NRC regarding our acoustic circuit model and reports from Continuum Dynamics, Incorporated
- Providing an update on the status of the acoustic model
- Conveying actions and schedule update related to the acoustic model 27
Refined Acoustic Model (cont.) Exekr5nlm Nuclear
- The acoustic circuit model that Exelon submitted to the NRC was the first model developed for steam dryer load definition
- Design review May 2004 with industry experts
- Higher frequencies - 200 hertz
- Higher steam flows - Dresden Unit 2 (DR2), DR3, and QC2
- Improved transducers on the water reference legs
- Use of strain gauge data - "B" MSL QC2
- Mock-up testing of an instrument line
- Expanded load mesh for FEM
- Load definition that is consistent with damage - FEM results
- Benchmark against scale model test 28
Refined Acoustic Model (cont.) Exeen)sm Nuclear Acoustic circuit model - status
- Latest acoustic circuit - draft report
- Higher steam flows - DR2, DR3 and QC2
- Improved transducers on the water reference legs
- Incorporated mock-up testing results of a instrument line
- Frequency up to 100 hertz
Refined Acoustic Model (cont.) ExekL,)n,.
Nuclear Acoustic circuit model - preliminary results predict the observed QC dryer experience on the front hood
- Pre-EPU dryer load definition for QC2 shows that the front hood is below the endurance limit - result based on dynamic FEM partial model with expanded load mesh
- EPU dryer load definition for QC2 shows that the front hood is above the endurance limit - result based on dynamic FEM partial model with expanded load mesh
- Extrapolating the DR plants against QC2 peak loads continues to support operability 30
Refined Acoustic Model (cont.) Exek)nsm Nuclear Upcoming actions for acoustic circuit analysis
- Benchmarking against GE scale model test is underway (November 2004)
- Apply lessons learned from benchmark (November 2004)
- Improve model to achieve 200 hertz frequencies (November 2004)
- Apply acoustic circuit analysis to new dryer with QC2 highest feedwater flow data - Vulnerability Review (December 2004)
- Apply 200 hertz to DR2, DR3 and QC2 (mid-January 2005)
- Pre-EPU original dryer
- EPU 2003 repair
- EPU 2004 repair
- Scale peak loads for Dresden relative to QC2 (mid-January 2005)
- Continually incorporate new information into DR operability 31
Exe k nSM Nuclear Closing Remarks John Nosko Project Director, Steam Dryer Replacement 32