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| | number = ML15226A525 | | | number = ML15226A525 |
| | issue date = 09/03/2015 | | | issue date = 09/03/2015 |
| | title = McGuire-HAhn_8-13-2015 | | | title = HAhn_8-13-2015 |
| | author name = Ahn H | | | author name = Ahn H |
| | author affiliation = NRC/NRO/DSEA/RHMB | | | author affiliation = NRC/NRO/DSEA/RHMB |
Revision as of 18:34, 10 April 2019
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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
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 Accident
Project stage: Request
ML14142A3512014-05-28028 May 2014
Request for Additional Information Regarding Flood Hazard Reevaluation Report
Project stage: RAI
ML15100A3662015-04-0909 April 2015
NRR E-mail Capture - McGuire Nuclear Station-Fukushima 2.1 Flooding-FHRR Review RAIs
Project stage: Other
ML15230A0702015-09-0303 September 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10CFR50.54 Information Request - Flood Causing Mechanism Reevaluation
Project stage: Other
ML15226A5252015-09-0303 September 2015
HAhn_8-13-2015
Project stage: Other
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)
Project stage: Other
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)
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML15230A0702015-09-0303 September 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10CFR50.54 Information Request - Flood Causing Mechanism Reevaluation
ML15226A5252015-09-0303 September 2015
HAhn_8-13-2015
ML15141A0542015-05-0707 May 2015
Enclosure 6, MNS EAL Wallcharts
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
ML1214500142012-05-23023 May 2012
NFPA 805 LAR Status Matrix - May 2012
ML11207A4572011-07-21021 July 2011
Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model
ML1025600662010-09-0808 September 2010
Response to Request for Additional Information Related to the License Amendment Request Applicable to Technical Specification (TS) 3.8.4 DC Sources-Operating
ML0828300142008-10-0606 October 2008
Response to Request for Additional Information License Amendment Request for Implementation of Alternative Source Term
ML0823302222008-08-20020 August 2008
Choice Letter Attachment Q - Pump Strainer Dp Data Analysis
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0715002972007-05-22022 May 2007
Units 1 & 2 - Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model
2020-09-16
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Text
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 Structures Upstream a m ailures (combined event)762.6 ft msl5.1 ft767.7 ft mslFHRR Section 1.2.3 FHRR 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 3-1 Streams and RiversReservoir Level at Cowans ord Dam767.9 ft msl5.1 ft773.0 ft mslFHRR Section 1.2.2 FHRR Section 1.2.8 (Table 1.2.8-1)Storm SurgeSurge in Lake Norman760.0 ft msl14.8 ft 774. f t m slFHRR 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 Elevation Note: 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 ElevationReference Note 2: Reevaluated hazard mec hanisms bounde d by the current de sign basis (s ee Table 1) are not included in thi s table.Note 3: Reported values are rounded to the nearest one-tenth of a foot.761.1 ft mslMinimal761.1 ft mslFHRR Section 2.1 Local 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 2.8 Upstream a m 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.
