Letter Sequence Request |
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MONTHYEARML14156A1302014-06-0606 June 2014
Request for Additional Information Regarding Flood Hazard Reevaluation Report
Project stage: RAI
ML15119A1932015-04-29029 April 2015
NRR E-mail Capture - Catawba Nuclear Station-Fukushima 2.1 Flooding-FHRR Review RAIs
Project stage: Other
ML15155A6312015-06-0808 June 2015
Nuclear Regulatory Commission Plan for the Audit of Duke Energy Carolinas, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 Flooding for Catawba Nuclear Station, Units 1 and 2
Project stage: Other
ML15278A0172015-10-0505 October 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(F) Information Request; Flood-Causing Mechanism Reevaluation (TAC Nos. MF3625 and MF3626)
Project stage: Other
ML15268A2982015-10-0505 October 2015
Interim Staff Response Enclosuflooding Tables 1 and 2
Project stage: Request
ML15352A1922015-12-21021 December 2015
Revised 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
2015-12-21
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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
ML15352A1922015-12-21021 December 2015
Revised Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation
ML15268A2982015-10-0505 October 2015
Interim Staff Response Enclosuflooding 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
CNS-14-100, Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds2014-09-11011 September 2014
Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds
ML12312A0692012-10-17017 October 2012
Table 16.8-1-2 Unit 2 Cpcopds
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
ML1103500032011-02-0909 February 2011
Correction Letter for License Amendment Nos. 262 and 258, Regarding Technical Specification 3.8.4 DC (Direct Current) Sources - Operating.
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
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
ML0529902932005-10-19019 October 2005
FAQ Log 10/19/2005
ML0506100192005-02-17017 February 2005
Request for Relief Number 05-CN-001 Limited Weld Examinations During End-of-Cycle 14 Refueling Outage
ML0403602192004-01-22022 January 2004
/22/2004 Meeting Handouts by the Licensee - Enclosure 3
ML0307904262003-03-20020 March 2003
Attachment - Table 1 Summary of Relief Requests
2020-09-16
[Table view] |
Text
Catawba, 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 Unit 1 Side of the Yard 594.7 ft msl Minimal 594.7 ft msl Response to NRC Request for Additional Information Regarding the FHRR, dated July 28, 2015 (ADAMS Accession No. ML15222A535)
Unit 2 Side of the Yard 594.7 ft msl Minimal 594.7 ft msl Response to NRC Request for Additional Information Regarding the FHRR, dated July 28, 2015 (ADAMS Accession No. ML15222A535)
Streams and Rivers Lake Wylie CNS Intake 581.1 ft msl Not 581.1 ft msl FHRR Section 1.2.2 and Table 3-1 applicable Standby Nuclear Service Water 583.5 ft msl 1.0 ft 584.5 ft msl FHRR Section 1.2.2 Pond Dam Failure of Dams and Onsite Water Control/Storage Structures Lake Wylie CNS Intake 592.4 ft msl 1.5 ft 593.9 ft msl FHRR Table 1.2.8-1 (Combined Effects)
Standby Nuclear Service Water 592.4 ft msl 2.2 ft 594.6 ft msl FHRR Table 1.2.8-1 Pond (Combined Effects)
Allison Creek CNS Discharge 592.4 ft msl 1.2 ft 593.6 ft msl FHRR Table 1.2.8-1 (Combined Effects)
Storm Surge Lake Wylie Storm Surge and 569.4 ft msl 8.4 ft 577.8 ft msl FHRR Section 1.2.4 Seiche
Catawba, 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 Seiche No Impact No Impact No Impact FHRR Section 1.2 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 Ice-Induced Flooding No Impact No Impact No Impact FHRR Section 1.2 on the Site on the Site on the Site Identified Identified Identified Channel Migrations/Diversions No Impact No Impact No Impact FHRR Section 1.2 on the SIte on the Site on the Site Identified Identified Identified Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Catawba, 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 Unit 1 Side of the Yard 595.5 ft msl Minimal 595.5 ft msl FHRR Section 2.1 and Table 3-1 Unit 2 Side of the Yard 595.6 ft msl Minimal 595.6 ft msl FHRR Section 2.1 Streams and Rivers Lake Wylie CNS Intake 590.7 ft msl Not 590.7 ft msl FHRR Section 2.2.2 applicable Standby Nuclear Service Water 583.0 ft msl 0.8 ft 583.8 ft msl FHRR Section 2.4.1 and Table 2.4.3-1 Pond Dam (LIP)
Failure of Dams and Onsite Water Control/Storage Structures Lake Wylie CNS Intake 602.2 ft msl 1.0 ft 603.2 ft msl FHRR Section 2.8.1, Table 3-1, and (Combined Effects) Table 2.8.1-1 Standby Nuclear Service Water 602.2 ft msl 1.0 ft 603.2 ft msl FHRR Table 2.4.2-1 and Table 3-1 Pond (Combined Effects)
FHRR Table 2.8.1-1 Allison Creek CNS Discharge 599.8 ft msl Not 599.8 ft msl FHRR Table 2.3.2-4 and Table 3-1 (Combined Effects) applicable 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.
