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Category:Meeting Briefing Package/Handouts
MONTHYEARML19269B6892019-10-0303 October 2019 NEIMA Section 108 Public Meeting Slides - Oyster Creek - October 3, 2019 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 ML18225A1752018-08-15015 August 2018 Decommissioning License Transfer Application NRC Pre-Submittal Meeting ML18201A2372018-07-17017 July 2018 Slides 7/17/2018 PSDAR Meeting ML18201A2842018-07-17017 July 2018 PSDAR Public Meeting the NRC Review Process ML18201A3072018-07-17017 July 2018 Post Shutdown Decommissioning Activities Report (PSDAR) Public Meeting Presentation 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 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 ML17062A5522017-03-0909 March 2017 E EMRV Failure Slides for Regulatory Conference Meeting Notice for 03/09/17 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 ML16092A1402016-04-0606 April 2016 4/6/16, Meeting Slide for Pre-Submittal Meeting with NRC Regarding Oyster Creek Decommissioning Post-Shutdown Emergency Plan License Amendment Request 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 ML15265A3592015-09-21021 September 2015 NRC Oyster Creek Decommissioning Pre-Submittal Meeting Slides 09-21-15 ML15118A8042015-05-0505 May 2015 Webinar 2015 Slides Presentation ML15265A3742015-02-21021 February 2015 NRC Pre-Submittal Meeting 09-21-15 - Decommissioning Submittal List ML12173A1322012-06-21021 June 2012 Summary of Public Meeting with Exelon Generation Company, LLC Regarding Items of Public Interest Related to Oyster Creek Nuclear Generating Station ML12110A3402012-04-19019 April 2012 Annual Assessment Meeting - 2011 ROP-NRC Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1012300492010-05-0303 May 2010 Slides for the Oyster Creek Annual Assessment Public Meeting ML0934102382009-12-0404 December 2009 Meeting Presentation, ACRS Meeting with the U.S. Nuclear Regulator Commission ML0928701922009-10-0909 October 2009 FEMA Public Meeting at Oyster Creek Slides, October 2009 ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML0919801452009-06-17017 June 2009 NRC Discussions with Nj DEP Engineers ML0919605452009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, to Describe Current Regulatory Footprint, Additional Options & Actions, and Gov'T & Public Outreach Needs ML0919605462009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options in Response to RA Questions ML0919605472009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options in Response to RA Questions ML0919605572009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, to Describe Current Regulatory Footprint, Additional Options & Actions, and Gov'T & Public Outreach Needs ML0919605582009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, to Describe Current Regulatory Footprint, Additional Options & Actions, and Gov'T & Public Outreach Needs ML0919605592009-06-17017 June 2009 09/23/2008 DRS Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options in Response to RA Questions on a Lr Regulatory Foodprint ML0919605602009-06-17017 June 2009 09/23/2008 DRS Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options, in Response to RA Questions ML0919805202009-06-17017 June 2009 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0916802102009-05-28028 May 2009 Oc Aam Public Feedback Form, 05/28/2009, 2008 Annual Assessment Meeting ML0913205742009-05-12012 May 2009 Meeting Slides, Oyster Creek Annual Assessment Meeting 2008 Reactor Oversight Process ML0912702392009-05-0404 May 2009 Calvert County Sheriff- Special Operations Team ML0912406092009-04-23023 April 2009 Meeting, Slides, New Jersey State Police Response to Hostile Action at Nuclear Power Plants, National Radiological Emergency Preparedness Conference ML0919801442008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues with Handwritten Notes ML0919801392008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0919801402008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0919801422008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0919801432008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. ML0810606002008-04-15015 April 2008 Meeting Slides, NRC Annual Performance Assessment of Oyster Creek 2007 Reactor Oversight Program. ML0715204362007-05-23023 May 2007 Feedback Forms, List of Attendees, & Final Slides from the Oyster Creek 2007 Annual Assessment Meeting (Aam) ML0634206092006-11-0404 November 2006 Powerpoint: Oyster Creek 1R21 Outage Startup PORC Update on Drywell Shell Inspections November 4, 2006 (PA) ML0622301292006-07-12012 July 2006 Powerpoint Presentation Associated with Oyster Creek Draft EIS Public Meetings ML0610003702006-04-10010 April 2006 NRC Slides for Annual Assessment Public Meeting with Amergen Reference CY2005 Oyster Creek Station Performance ML0509800822005-04-0808 April 2005 05/12/2005 - Oyster Creek Annual Assessment Meeting Slides for Meeting with Amergen ML0430302762004-09-27027 September 2004 Attendance List for Oyster Creek EDG Cooling Fan Regulatory Conference 2019-10-03
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Seismic Analysis of the Oyster Creek Reactor Building Stee I Superstructure And Modification Presenter: Swadesh C. Ramdeen, P.F.
Objective To present the seismic verification and modification of the reactor building steel superstructure for modification of the reactor building crane to single-failure-proof" in accordance with NUREG-0612 and NUREG-0554.
Purpose The reactor building steel superstruicture need to be re-analyzed for upgrade of the reactor building crane.
The Upgraded crane is a single-failure-proof I05-'T'on capacity crane. The original crane was a non-single failure-proof I00-Ton capacity crane.
This presentation does not include the seismic verification of the bridge and trolley, these were evaluated in a separate calculation.
Methodology Perform dead load, modal and response spectrum analysis of'the reactor building steel superstructure A finite element model of the entire RB steel structure wvas created with a simplified model of the crane and new trolley In the model the crane wheels are positioned at the location that produces the worst case stresses in the building structure The trolley is modeled at the worst case trolley location on the bridge (see slide)
Methodology continued:
A modal evaluation was perlormed. The program was set to deteimine 50 modes which excite the stricture into the rigidI range.
This resuLlts in approximately 98 to 99 % of mass participation in all three direction and the 47th mode exceeding 33 hertz.
Modal damping is 4% for OBE and 7% Ibr SSE in accordance with USNRC Regulatory Guide 1.61 Modal combinations are per USNRC Regulatory Guide 1.92 l*Response Spectrum evaluation is peerlormed by combining the 3 direction responses by the SRSS Method.
Load Combinations and Acceptance Criteria (1)DL + LL + OBE < Normal allowable stresses from AISC Spec.
(2) DL + LL + SSE < 1.6 x Normal allowable stresses from AISC Spec.
DL: Dead loads inlclu(ICS the building and crane structure, and crane hook load.
LL: Live load due to snow on the building roof OBE: Operating basis earthquake loads on the operating floor level which is the base of the steel superstructure SSE: Saie Shutdown Earthquake loads on the operating floor level which is the base of'the steel superstructure
Computer Program Used Computer and Structures, Inc. Program SAP2000 Plus Version 7.21 This is a linear finite element analysis program capable of perl'orming static, modal and response spectrum analysis.
This program was verified by EQE (the analysis vendor) under thcir quality assurance program
Results The liaximum interaction ratios for the various elements of'thc slcel superstructure:
Building (CoMPonent I)L + LL+ OBE < 1.0 DL+ LL + SSI, < 1.6 W 14 X 74 Coilumis 0.94 1.16 Colum1n Bracing 0.77 1.05 Crane Rail Giirder 0.96 1.15 Rool"Ilruss Cords 1.00 1.37 RooFl"rIuss Iricing 0.98 1.09 The mnaxiLmum-i computed displacements (NS, EW, VERTICAL) in inches relative to the operating floor:
lluildingl Co(in )Ollcnt i)L + LL+ OBE I)L+ LL + SSE R0o( flr ISS ,Ioinits 0.39, 0.44, 0.26 0.51, 0.64, 0.37 Crane Runway/lB1ridge 0.95, 1.07, 0.48 1.22, 1.45, 0.61
Results continued:
It was known that the clip connecting the rail girder to the building columns will require modification as such no stresses were computed for this component. The results of this activity are as follows:
- 1. The analysis results (force magnitude) confirms that the existing bent plate clip will be overstressed and a modifik-ation is required at each connection (total-- 14)
- 2. The calculated forces were used to design a modification
- 3. The modification was installed in July of 2000 The final details of the modification were reconciled in the building analysis.
Summary The modified reactor building super structure and reactor building crane rail girders are adequate for the Oyster Creek Safe Shutdown and Operating Bases earthquakes for a fully loaded crane with the trolley at any location on the crane bridge.
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