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MONTHYEARRS-15-163, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report2015-08-12012 August 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
ML16091A1362016-03-31031 March 2016
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request- Flood-causing Mechanism Reevaluation (CAC Nos. MF6598 and MF6599)
Project stage: Other
ML16089A3532016-03-31031 March 2016
MSFHI Tables, Public, 3-29-2016
Project stage: Other
RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016
Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
Project stage: Other
ML17255A5242017-09-25025 September 2017
NRC Report for the Audit of Exelon Generating Company Llc'S Flood Hazard Reevaluation Report Submittal Relating to the NTTF Recomendation 2.1--Flooding for Peach Bottom Atomic Power Station, Units 2 and 3-Public Redacted
Project stage: Acceptance Review
ML17284A0352017-10-30030 October 2017
Staff Assessment of Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Re-evaluation (Public)
Project stage: Acceptance Review
2016-06-30
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Category:Graphics incl Charts and Tables
MONTHYEARML23110A1742023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, Chapter 13, Figures
ML23110A1752023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, Appendix N, Tables
ML23110A1912023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, Chapter 14, Figures
ML23110A2212023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, Chapter 1, Figures
ML23110A2512023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, PEA Chapter 6, Figures
ML23172A2812023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, Appendix C, Figures - Redacted
ML23173A0232023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, Chapter 12, Figures - Redacted
ML23173A0492023-04-10010 April 2023
9 to Updated Final Safety Analysis Report, Appendix a, Figures - Redacted
ML20339A3972020-12-10010 December 2020
Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident
ML19114A1962019-04-0808 April 2019
Revision 27 to Updated Final Safety Analysis Report, Appendix J, Figures
ML18354B0662018-12-20020 December 2018
Summary of Monitoring Well Installation Details
ML16089A3532016-03-31031 March 2016
MSFHI Tables, Public, 3-29-2016
ML16091A1362016-03-31031 March 2016
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request- Flood-causing Mechanism Reevaluation (CAC Nos. MF6598 and MF6599)
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
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
ML13338A1702013-11-22022 November 2013
Assistance in Obtaining Information on Dams
ML13255A3772013-09-16016 September 2013
MACCS2 Runs to Source Term Crosswalk ACRS Sep 2013
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
ML11255A3522011-08-25025 August 2011
Soarca Project Document List for the Peach Bottom Site
NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010
Re-Submittal of the Exelon Cyber Security Plan
ML12124A2972010-03-11011 March 2010
Soarca Documents Review/Approval Process
ML0822604012008-08-0707 August 2008
Transmittal of Supplemental Response to Request for Additional Information License Amendment Request - Application of Alternative Source Term
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
2023-04-10
[Table view] |
Text
Peach Bottom Atomic Power Station, Units 2 & 3 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 Not included Not included Not included FHRR Section 2.3.1 in DB in DB in DB Streams and Rivers Probable Maximum Flooding Not included Not included Not included FHRR Section2.3.2.2 from Rock Run Creek in DB in DB in DB Probable Maximum Flooding 131.4 ft Not 131.4 ft FHRR Section 2.3.2.1 from Susquehanna River NAVD88 applicable NAVD88 REDACTED REDACTED REDACTED REDACTED REDACTED Failure of Dams and Onsite Water Control/Storage Structures REDACTED REDACTED REDACTED REDACTED REDACTED Storm Surge Not included Not included Not included FHRR Section 2.3.4 in DB in DB in DB Seiche Not included Not included Not included FHRR Section 2.3.5 in DB in DB in DB Tsunami Not included Not included Not included FHRR Section 2.3.6 in DB in DB in DB
Peach Bottom Atomic Power Station, Units 2 & 3 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 2.3.7 in DB in DB in DB Channel Migrations/Diversions Not included Not included Not included FHRR Section 2.3.8 in DB in DB in DB Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Peach Bottom Atomic Power Station, Units 2 & 3 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 Emergency Cooling Tower 127.0 ft Minimal 127.0 ft FHRR Section 3.1.3 & Table 3.1.3.1 (Emergency Heat Sink) NAVD88 NAVD88 Unit 3 Reactor Building Door 246 135.2 ft Minimal 135.2 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Unit 3 Reactor Building Door 244 135.4 ft Minimal 135.4 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Unit 3 Recirculation MG Set 135.9 ft Minimal 135.9 ft FHRR Section 3.1.3 & Table 3.1.3.1 Room NAVD88 NAVD88 Unit 2 Recirculation MG Set 135.9 ft Minimal 135.9 ft FHRR Section 3.1.3 & Table 3.1.3.1 Room NAVD88 NAVD88 Unit 2 Reactor Building Door 183 135.5 ft Minimal 135.5 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Unit 2 Reactor Building Door 198 135.2 ft Minimal 135.2 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Diesel Generator Building (SW) 132.0 ft Minimal 132.0 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Diesel Generator Building (SE) 127.5 ft Minimal 127.5 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Diesel Generator Building (NE) 117.6 ft Minimal 117.6 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Diesel Generator Building (NW) 120.8 ft Minimal 120.8 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88
Peach Bottom Atomic Power Station, Units 2 & 3 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Runup Hazard Elevation Pump Structure 117.5 ft Minimal 117.5 ft FHRR Section 3.1.3 & Table 3.1.3.1 NAVD88 NAVD88 Storm Surge Conowingo Maximum Controlled 118.5 ft Not 118.5 ft FHRR Section 3.4.3 Water Elevation Antecedent NAVD88 applicable NAVD88 Condition Seiche Seiche in Length Direction 112.8 ft Not 112.8 ft FHRR Section 3.4.4 & Table 3.4.3.2.4 (Conowingo Maximum NAVD88 applicable NAVD88 Controlled Water Elevation Antecedent Condition)
Seiche in Width Direction 112.3 ft Not 112.3 ft FHRR Section 3.4.4 & Table 3.4.3.2.4 (Conowingo Maximum NAVD88 applicable NAVD88 Controlled Water Elevation Antecedent Condition)
Ice-Induced Flooding 111.5 ft Not 111.5 ft FHRR Sections 3.7 & 3.7.3 NAVD88 applicable NAVD88 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.
