Letter Sequence Other |
|---|
|
|
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
[Table View] |
|
|---|
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
[Table view] |
Text
McGuire, 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 760.4 ft msl 0.0 ft 760.4 ft msl FHRR Section 1.2.1 Streams and Rivers Reservoir Level at Cowans 767.9 ft msl 5.1 ft 773.0 ft msl FHRR Section 1.2.2 Ford Dam FHRR Section 1.2.8 (Table 1.2.8-1)
Failure of Dams and Onsite Water Control/Storage Structures Upstream Dam Failures 762.6 ft msl 5.1 ft 767.7 ft msl FHRR Section 1.2.3 (combined event) FHRR Section 1.2.3 (Table 1.2.8-1)
Standby Nuclear Service Water 746.9 ft msl 1.5 ft 748.4 ft msl FHRR Table 3-1 Pond (combined event)
Standby Nuclear Service Water 727.8 ft msl Not 727.8 ft msl FHRR Table 3-1 Pond Dam Downstream applicable (combined event)
Storm Surge Surge in Lake Norman 760.0 ft msl 14.8 ft 774.8 ft msl FHRR Section 1.2.4 Seiche No Impact No Impact No Impact FHRR Section 1.2.4 on the Site on the Site on the Site Identified Identified Identified Tsunami Not included Not included Not included FHRR Section 1.2 in DB in DB in DB
McGuire, 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 Not included Not included Not included FHRR Section 1.2 in DB in DB in DB Channel Migrations/Diversions Not included Not included Not included FHRR Section 1.2 in DB in DB in DB Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Note 2: The wave hieght value of 5.1 ft for the Streams and Rivers, and Upstream Dam Failures (combined event) is wave setup plus runup.
McGuire, 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 761.1 ft msl Minimal 761.1 ft msl FHRR Section 2.1 Streams and Rivers River PMF in Lake Norman 777.9 ft msl Not 777.9 ft msl FHRR Section 2.2 and 2.8 applicable Failure of Dams and Onsite Water Control/Storage Structures Upstream Dam Failures 778.5 ft msl Not 778.5 ft msl FHRR Section 2.3 and 2.8 (combined event) applicable Standby Nuclear Service Water 735.9 ft msl 0.9 ft 736.8 ft msl FHRR Tables 2.4.2-1 and 2.4.2-2 Pond Dam Downstream (combined event)
Storm Surge 778.5 ft msl 0.0 ft 778.5 ft msl FHRR Table 3-1 FHRR 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.
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.
