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Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24102A1882024-03-31031 March 2024 Omaha Public Power District Presentation Given at the March 27, 2024 Public Meeting on Submittal of Phase I Final Status Surveys for the Decommissioning of Fort Calhoun Station, Unit 1 ML24102A1622024-03-18018 March 2024 NRC Presentation on Reviews of Final Status Survey Reports Given at the March 27, 2024, Public Meeting with OPPD on Fort Calhoun Station Unit 1 Submittal of Phase I Final Status Surveys – (License No. DPR-40, Docket No. 50-285) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information ML24029A1742024-01-30030 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 ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides 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) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23229A1722023-08-17017 August 2023 RR Pen-75 Pre-Submittal NRC Meeting Handout ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation 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 ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22222A1112022-07-28028 July 2022 2022 Kmkt Fort Calhoun Flood Finding and 2011 Missouri River Flooding Reduce ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML22124A1492022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Non-Proprietary (Public) ML22124A1482022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Redacted (Public) ML22098A0512022-04-11011 April 2022 2 Cycle 25 High Burnup Lead Test Assembly NRC Pre-Submittal Meeting on April 22, 2022 (EPID L-2022-LRM-0022) (Slides) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (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 ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 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 ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) 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 ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 2024-05-16
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WLA/ýi[ Or'A USE OF ULTRASONIC FLOW MEASUREMENT TO DETERMINE REACTOR POWER-PURPOSE OF THIS PRESENTATION.
- To inform the ET and the LT of the status of the staffs review of the application of ultrasonic flow meters (UFMs) in determining reactor power* MEASURE FOR SUCCESS OF THIS PRESENTATION
+ ET and LT are aware of staff activities
+ ET and LT are advised of potential need for regulatory action to address deficiencies in the application of UFMs PRESENTERS:
Warren Lyon Presentation Date: June 8, 2006 1 K.'.'
John Nakoski 2 BACKGROUND
,/ UFMs uses: Feedwater flow measurement for MURs and power recovery v/ Appendix K to 10 CFR 50.46 changed to allow decrease in 2% uncertainty assumption for reactor power used in LOCA analyses V Importance is tied to compliance with the licensed thermal power upon which accident and transient analyses are conducted V Currently, 2 UFM devices have approved topical reports* Caldon -Check and CheckPlus* Westinghouse/AMAG
-Crossflow 3 CROSSFLOW UFM HISTORY 1999 Generic Crossflow UFM topical report approved.
Licensees beging requesting MURs January 2003 -Byron/Braidwood operating above rated thermal power (RTP). Region III requests NRR assistance on review of allegation related to Crossflow application at Byron/Braidwood.
July 2003 -Ft. Calhoun submits first MUR LAR based on Crossflow August 2003 -Byron/Braidwood reduce power, staff begins assessment of basis for operating above RTP. Power recovery application of Crossflow UFM.January 2004 -NRC approves Ft. Calhoun MUR LAR February 2004 -NRC establishes task group to review UFMs May 2004 -Ft. Calhoun licensed RTP returned to pre-MUR level July 2004 -NRC task group identifies issues and recommends actions.January 2005, Calvert Cliffs and March 2005, Ft. Calhoun submit MUR LARs based on Crossflow August 2005 -Westinghouse, Calvert Cliffs, & Ft. Calhoun provided issues related to Crossflow 4 CROSSFLOW UFM HISTORY (con't)* September 2005 -New issue identified with Crossflow use at Calvert Cliffs. Swirl in feedwater flow adversely affects Crossflow measurement.
- October 2005 -Staff places Calvert Cliffs and Ft. Calhoun MUR reviews on hold* October 2005 to January 2006 -Calvert Cliffs, Ft. Calhoun, W/AMAG, Owners Group, & NRC continue interactions on issue resolution.
NRC obze.es tracer testing at Calvert Cliffs.* February 2006 -NRR staff completes theoretical assessment of Crossflow uncertainty claim.Additional RAIs provided to W/AMAG* March 2006 -NRC & W/AMAG meet to discuss RAI responses* April 2006 -NRC provides detailed RAls on issues that must be resolved for use of Crossflow.
NRR issues User's Need memo to RES to peer review theoretical assessment.
W/AMAG describe model being developed that confirms original bases. Staff informs W/AMAG of schedule for and issues to be resolved for completion of reviews.* May 2006 -RES provides response to NRR User's Need memo. RES substantiated NRR position that Crossflow does not obtain sufficient information to support uncertainty analyses.+ June 2006 -W/AMAG provide additional information on theoretical and empirical bases for Crossflow uncertainty claim.5 OVERVIEW$ Caldon Check and CheckPlus UFMs are acceptable
$ Westinghouse/Advanced Measurement and Analysis Group (W/AMAG)review is ongoing. Anticipated staff finding is unacceptable.
RES supports NRR position on capability of Crossflow UFM.,$ Use of external UFMs for power recovery under 10 CFR 50.59 has not been shown to be acceptable 6
PLANT-SPECIFIC STATUS -RECENT MUR LARs/ Seabrook (Caldon) UFM is acceptable (ML061360034, May 22, 2006)V Calvert Cliffs (W/AMAG) is on hold -an amended LAR is anticipated V Ft. Calhoun (W/AMAG) is on hold pending generic review completion 7
ACCEPTANCE CRITERIA Traceability
-relating a measurement to a standard Standard maintained by a national laboratory
-National Institute of Standards and Technology (NIST)Each step between measurement and standard -clearly defined and no unverified assumptions Unbroken path between measurement and standard Total measurement uncertainty reflects aggregate uncertainties of each step Applicability
-provide accurate information over range of use* Sound basis (theoretical understanding or equivalent)
Calibration is constant or change is fully understood, predictable, and verifiable 8
ACCEPTANCE CRITERIA ASSESSMENT V Caldon Check and Checkplus meet all criteria/ VW/AMAG Crossflow has not been shown to meet criteria, but staff has not completed review of all submitted information 9
Ultrasonic Flow Meter Comparison Caldon Check & CheckPlus W/AMAG Crossflow m rn I~.A... ..... .... ..... .. ...M -7.7; ... ..... .....1-IJ.LL:1 4:.,4: 10
- W/AMAG CROSSFLOW REGULATORY IMPACT Potentially effected measurement uncertainty recapture power uprates: Plant % Uprate MWt 1 Increase Salem 1&, 8 2 1.4 48 x 2 =96 Hope Creek 1.4 46 SONGS 2&3 1.42 48 x 2 =96 STP 1&2 1.4 53 x 2= 106 Plant % Uprate MWt Increase Pilgrim 1.5 30 Hatch 1&2 1.4 48 x 2 = 96 Kewaunee 1.4 23 Palisades 1.4 35.4* Total MWt increase from Use of Crossflow based MURs = 528 MWt* This equates to about 185 MWe* Regulatory impact from the use of Crossflow for power recovery has not been fully assessed 11 W/AMAG CROSSFLOW CONCLUSIONS
,/ Theoretical, analytical, and understanding basis is weak ,/ Empirical data basis is weak/ Meter self-assessment does not appear viable S"'An unbroken path from calibration used during meter operation to reference standards has not been achieved ,/ NRC-approved topic report is no longer valid ,/ NRC review is nearing completion although work remains/" Regulatory action may be required to address the use of Crossflow and other external UFMs for MURs and power recovery applications 12