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MONTHYEARMNS-14-025, Submittal of Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Re Recommendations 2.1, 2.3 & 9.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-12012 March 2014
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Project stage: Request
ML14142A3512014-05-28028 May 2014
Request for Additional Information Regarding Flood Hazard Reevaluation Report
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NRR E-mail Capture - McGuire Nuclear Station-Fukushima 2.1 Flooding-FHRR Review RAIs
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Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10CFR50.54 Information Request - Flood Causing Mechanism Reevaluation
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HAhn_8-13-2015
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ML16293A6662016-10-31031 October 2016
Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624)
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MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017
Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal
Project stage: Request
2015-04-09
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Category:Graphics incl Charts and Tables
MONTHYEARRA-20-0263, Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-09-16016 September 2020
Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)
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Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
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Response to Request for Additional Information Related to the License Amendment Request Applicable to Technical Specification (TS) 3.8.4 DC Sources-Operating
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2020-09-16
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McGuire, Units 1 & 2Table 1. Current Design Basis Flood Hazards for Use in the MSAMechanismStillwater Elevation Waves/ RunupReferenceDesign Basis Hazard ElevationLocal Intense Precipitation760.4 ft msl0.0 ft760.4 ft mslFHRR Section 1.2.1Failure of Dams and Onsite Water Control/Storage StructuresUpstream am ailures (combined event)762.6 ft msl5.1 ft767.7 ft mslFHRR Section 1.2.3FHRR Section 1.2.3 (Table 1.2.8-1)Standby Nuclear Service Water Pond (combined event)746.9 ft msl1.5 ft748.4 ft mslFHRR Table 3-1Standby Nuclear Service Water Pond Dam Downstream (combined event)727.8 ft msl727.8 ft mslFHRR Table 3-1Streams and RiversReservoir Level at Cowans ord Dam767.9 ft msl5.1 ft773.0 ft mslFHRR Section 1.2.2FHRR Section 1.2.8 (Table 1.2.8-1)Storm SurgeSurge in Lake Norman760.0 ft msl14.8 ft774. ft mslFHRR Section 1.2.4Seiche No Impact on the Site Identified FHRR Section 1.2.4TsunamiNot included in DBNot included in DBNot included in DBFHRR Section 1.2 McGuire, Units 1 & 2Table 1. Current Design Basis Flood Hazards for Use in the MSAMechanismStillwater Elevation Waves/ RunupReferenceDesign Basis Hazard ElevationNote: Reported values are rounded to the nearest one-tenth of a foot.Ice-Induced FloodingNot included in DBNot included in DBNot included in DBFHRR Section 1.2Channel Migrations/DiversionsNot included in DBNot included in DBNot included in DBFHRR Section 1.2 McGuire, Units 1 & 2Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSAMechanismStillwater Elevation Waves/ RunupReevaluated Hazard ElevationReferenceNote 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.761.1 ft mslMinimal761.1 ft mslFHRR Section 2.1Local Intense PrecipitationStreams and Rivers777.9 ft mslNot applicable777.9 ft mslFHRR Section 2.2 and 2.8River PMF in Lake NormanFailure of Dams and Onsite Water Control/Storage Structures778.5 ft mslNot applicable778.5 ft mslFHRR Section 2.3 and 2.8Upstream am ailures (combined event) FHRR Tables 2.4.2-1 and 2.4.2-2Standby Nuclear Service Water Pond Dam Downstream (combined event)Storm Surge778.5 ft msl0.0 ft778.5 ft mslFHRR Table 3-1FHRR Section 2.4.1 (Table 2.4.1-1)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.
