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MONTHYEARRS-15-064, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report2015-03-12012 March 2015 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report Project stage: Request ML15093A3122015-03-17017 March 2015 NRR E-mail Capture - Request for Additional Information: LaSalle Flooding Hazard Reevaluation Report Project stage: RAI ML15148A2862015-07-21021 July 2015 Nuclear Regulatory Commission Plan for the Audit of Exelon Generation Company, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 -Flooding Project stage: Other ML15211A4822015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation Project stage: Other ML15219A6612015-09-0303 September 2015 Tables 1 and 2 Project stage: Other 2015-03-17
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MONTHYEARML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports RA15-075, Transmittal of the 2014 Regulatory Commitment Change Summary Report2015-11-20020 November 2015 Transmittal of the 2014 Regulatory Commitment Change Summary Report ML15211A4822015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15219A6612015-09-0303 September 2015 Tables 1 and 2 ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T RS-14-111, Supplemental Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-06-0404 June 2014 Supplemental Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RA-13-081, Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term.2013-09-16016 September 2013 Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term. RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013 Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010 Re-Submittal of the Exelon Cyber Security Plan RS-10-001, LaSalle, Units 1 and 2, Attachment 5 - Summary of Regulatory Commitments2010-01-27027 January 2010 LaSalle, Units 1 and 2, Attachment 5 - Summary of Regulatory Commitments ML1003213162010-01-27027 January 2010 Attachment 5 - Summary of Regulatory Commitments ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0620505382006-07-19019 July 2006 Oak Ridge Institute for Science and Education - Analytical Results for Thirty-Seven Water Samples, Batch Two, from the Vicinity of LaSalle Station, LaSalle, Illinois (Inspection Report No. 050-00373/2006-004) (Rfta No. 06-001) ML0415403852004-05-25025 May 2004 2003 Annual Radiological Environmental Operating Report - Errata ML17037B8491975-08-23023 August 1975 08/21/1975 Summary of Meeting with Mark II Owners, Sargent & Lundy, Bechtel, Stone & Webster, Burns & Roe, and the NRC Staff to Discuss Load Factors and Load Combinations Proposed by the Mark II Owners and Their Architect ... 2016-03-11
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LaSalle, Units 1 & 2 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Runup Hazard Elevation Local Intense Precipitation LIP Zone 1 (North portion of site) 710.1 ft MSL Not 710.1 ft MSL FHRR Section 2.2.1 applicable LIP Zone 2 (South portion of site) 710.3 ft MSL Not 710.3 ft MSL FHRR Section 2.2.1 applicable Streams and Rivers Riverine 521.8 ft MSL 0.7 ft 522.5 ft MSL USFAR Revision 19 Section 2.4.3 FHRR Section 2.2.2 Failure of Dams and Onsite Water Control/Storage Structures No impact on No impact on No impact on the site the site the site FHRR Section 2.2.3 identified identified identified Storm Surge PMF on Lake at Dike 704.3 ft MSL 2.9 ft 707.2 ft MSL FHRR Section 2.2.4 PMF on Cooling Lake at Plant 704.3 ft MSL 1.3 ft 705.6 ft MSL FHRR Section 2.2.4 PMF on Cooling Lake at Lake 704.3 ft MSL 1.8 ft 706.1 ft MSL FHRR Section 2.2.4 Screen House Seiche Not included Not included Not included FHRR Section 2.2.5 in DB in DB in DB Tsunami Not included Not included Not included FHRR Section 2.2.6 in DB in DB in DB
LaSalle, Units 1 & 2 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Runup Hazard Elevation Ice-Induced Flooding No impact on No impact on No impact on the site the site the site FHRR Section 2.2.7 identified identified identified Channel Migrations/Diversions No impact on No impact on No impact on the site the site the site FHRR Section 2.2.8 identified identified identified Note: Reported values are rounded to the nearest one-tenth of a foot.
LaSalle, Units 1 & 2 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Runup Hazard Elevation Local Intense Precipitation LIP for entire site 710.8 MSL Minimal 710.8 MSL FHRR Section 3.1 Storm Surge Lake screen house 701.0 MSL 9.6 ft 710.6 MSL FHRR Section 3.4.4 Inlet structure 701.0 MSL 11.0 ft 712.0 MSL FHRR Section 3.4.4 Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA. The staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood associated effects during its review of the MSA.
Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table.
Note 3: Reported values are rounded to the nearest one-tenth of a foot.