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Category:Graphics incl Charts and Tables
MONTHYEARML23129A2642023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section I, Figures ML23129A2742023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section III Figures III-2-1 to III-10-1 ML23129A2762023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section VI, Figures ML23129A2832023-04-20020 April 2023 1 to Updated Safety Analysis Report, Appendix D(1), Figures ML23129A2842023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section V, Figures ML23129A2932023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section X, Figures ML23129A2992023-04-20020 April 2023 1 to Updated Safety Analysis Report, Appendix G, Figures ML23129A3042023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section VII, Figures ML23129A3062023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section Xiv, Figures XIV-4-1 to XIV-6-20 ML23129A3072023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section II, Figures ML23129A3082023-04-20020 April 2023 1 to Updated Safety Analysis Report, Appendix C, Figures C-2-2 to C-2-12 ML21130A0802021-04-21021 April 2021 0 to Updated Final Safety Analysis Report, Appendix D(1), Figures IR 05000298/20200042021-02-0303 February 2021 Integrated Inspection Report 05000298/2020004 NLS2016049, Revision to Flood Hazard Reevaluation Report2016-09-29029 September 2016 Revision to Flood Hazard Reevaluation Report ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports NLS2015011, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20142015-01-21021 January 2015 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2014 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 ML14077A0192014-03-28028 March 2014 Final Cooper Section 3 4 IE PRA Record-of-Review 03-13-2014 ML14077A0202014-03-17017 March 2014 Final Cooper Section 3 4 Fpra Record-of-Review 03-17-2014 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML1019004182010-06-28028 June 2010 Quick View Chart NLS2008042, Response to Request for Additional Information 10 CFR 50.55a, Request RI-35, Revision 12008-04-11011 April 2008 Response to Request for Additional Information 10 CFR 50.55a, Request RI-35, Revision 1 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0623601282006-08-22022 August 2006 Probability of Nonrecovery ML0623601322006-08-22022 August 2006 New-Recovery.XLS - NUREGCR-5496 ML0623601342006-08-22022 August 2006 New-Recovery.XLS - Plots (5496) ML0622204782006-08-0909 August 2006 New Recovery .Xls - NUREG/CR-5496 ML0622205032006-08-0909 August 2006 New-Recovery .Xls - Plots (5496) NLS2005003, Response to Request for Additional Information Regarding Relief Request RI-35 Cooper Nuclear Station2005-01-0505 January 2005 Response to Request for Additional Information Regarding Relief Request RI-35 Cooper Nuclear Station ML0623601432004-02-19019 February 2004 SW System Chart, Rev. 1 ML0317700762003-06-26026 June 2003 Report on the Status of Open TIAs Assigned to NRR 2023-04-20
[Table view] Category:Letter type:NLS
MONTHYEARNLS2024053, Licensee Guarantees of Payment of Deferred Premiums2024-07-30030 July 2024 Licensee Guarantees of Payment of Deferred Premiums NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024 Data from Metamic Coupon Sampling Program NLS2024052, Supplement to the Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow2024-07-24024 July 2024 Supplement to the Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow NLS2024051, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2024-07-0303 July 2024 Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation NLS2024037, 2023 Annual Radiological Environmental Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Report NLS2024030, Annual Radioactive Effluent Release Report2024-04-25025 April 2024 Annual Radioactive Effluent Release Report NLS2024033, Preparation and Scheduling of Operator Licensing Examinations2024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations NLS2024031, Notice of Intent to Apply for Subsequent Renewal of Operating License2024-04-22022 April 2024 Notice of Intent to Apply for Subsequent Renewal of Operating License NLS2024036, Nebraska Public Power District 2023 Financial Report2024-04-19019 April 2024 Nebraska Public Power District 2023 Financial Report NLS2024027, Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation2024-04-0303 April 2024 Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation NLS2024024, Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation2024-04-0101 April 2024 Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation NLS2024018, Property Insurance Coverage2024-03-20020 March 2024 Property Insurance Coverage NLS2024017, Response to an Apparent Violation in NRC Inspection Report 05000298/2023012; EA-24-0012024-03-0808 March 2024 Response to an Apparent Violation in NRC Inspection Report 05000298/2023012; EA-24-001 NLS2024009, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Support Inspection of2024-03-0808 March 2024 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Support Inspection of NLS2024001, Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow2024-02-16016 February 2024 Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow NLS2024006, Response to Nuclear Regulatory Commissions Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commissions Request for Additional Information for Relief Request RC3-02 NLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2024007, Emergency Plan Implementing Procedure 5.7.1, Revision 732024-01-16016 January 2024 Emergency Plan Implementing Procedure 5.7.1, Revision 73 NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector2024-01-15015 January 2024 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20232024-01-10010 January 2024 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 NLS2023053, ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-30030 November 2023 ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023050, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023049, 10 CFR Part 21 Report Regarding HGA Relays2023-09-0606 September 2023 10 CFR Part 21 Report Regarding HGA Relays NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023047, Licensee Guarantees of Payment of Deferred Premiums2023-07-26026 July 2023 Licensee Guarantees of Payment of Deferred Premiums NLS2023033, 10 CFR 50.55a Relief Request RC3-022023-06-27027 June 2023 10 CFR 50.55a Relief Request RC3-02 NLS2023039, Preparation and Scheduling of Operator Licensing Examinations2023-06-0101 June 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2023038, Nebraska Public Power District 2022 Financial Report2023-05-22022 May 2023 Nebraska Public Power District 2022 Financial Report NLS2023031, Annual Radiological Environmental Report2023-05-11011 May 2023 Annual Radiological Environmental Report NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023030, Annual Radioactive Effluent Release Report2023-04-27027 April 2023 Annual Radioactive Effluent Release Report NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2023027, Annual Report of Individual Exposure Monitoring2023-04-13013 April 2023 Annual Report of Individual Exposure Monitoring NLS2023021, Quality Assurance Program Changes2023-04-10010 April 2023 Quality Assurance Program Changes NLS2023020, Decommissioning Funding2023-03-29029 March 2023 Decommissioning Funding NLS2023019, Property Insurance Coverage2023-03-23023 March 2023 Property Insurance Coverage NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022054, Preparation and Scheduling of Operator Licensing Examinations2023-01-0505 January 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2022055, Emergency Plan, Revision 812023-01-0404 January 2023 Emergency Plan, Revision 81 NLS2022053, CNS-2022-11 Post Exam Submittal2022-11-22022 November 2022 CNS-2022-11 Post Exam Submittal NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022048, Management Change and Correspondence Update2022-11-0101 November 2022 Management Change and Correspondence Update NLS2022047, Core Operating Limits Report, Cycle 33, Revision 02022-10-14014 October 2022 Core Operating Limits Report, Cycle 33, Revision 0 NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022037, Emergency Plan, Revision 80, Summary of 50.54(q) Analyses2022-08-18018 August 2022 Emergency Plan, Revision 80, Summary of 50.54(q) Analyses 2024-07-30
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Text
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 H
Nebraska Public Power District
Always there when you need us" NLS2016049 September 29, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Revision to Nebraska Public Power District's Flood Hazard Reevaluation Report Cooper Nuclear Station, Docket No 50-298, DPR-46
References:
- 1. NRC Letter, "Request for Infom~.ation Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012
- 2. NPPD Letter to NRC, "Nebraska Public Power District's Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated February 3, 2015
- 3. NPPD Letter to NRC, "Addendum to Nebraska Public Power District's Response to Nuclear Regulatory Commission Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated July 31, 2015
- 4. NPPD Letter to NRC, "Addendum to Nebraska Public Power District's Response to Nuclear Regulatory Commission Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated October 29, 2015
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 2 of Reference 1 requested that each licensee perform a reevaluation of external flooding sources and report the results in accordance with the NRC's prioritization plan. In Reference 2, Nebraska Public Power District (NPPD) submitted the flood hazard reevaluation report (FHRR) report for /IO/ 0 COOPER NUCLEAR STATION ./ f... f.._
P.O. Box 98/Brownville, NE 68321-0098 /V Telephone: (402) 825-3811 I Fax: (402) 825-5211 http://www.nppd.com ENCLOSURE 1 TO THIS LETTER CONTAINS SECURITY-RELATED INFORMATION.
UPON SEPARATION FROM ENCLOSURE 1, THIS COVER LETTER IS DECONTROLLED.
SECURITY-RELATED INFORMATION-WITHHOLD UNDER 10 CFR 2.390 NLS2016049 Page 2 of2 Cooper Nuclear Station (CNS). In References 3 and 4, NPPD submitted Addendums A and B to the FHRR as a result of requests for information and the FHRR audit.
The purpose of this submittal is to submit a revised FHRR for CNS as discussed in Reference 4.
This revised FHRR also incorporates the addendums previously submitted. The attachment to this submittal provides a summary description, per section, of the revisions to the FHRR.
NPPD requests Enclosure 1, which contains security-related information, be withheld from public disclosure in accordance with 10 CFR 2.390. A redacted version of the FHRR is provided as Enclosure 2 and is suitable for public disclosure.
There are no new regulatory commitments contained in this submittal. Should you have any questions or if additional information is required, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.
I declare under penalty of perjury that the foregoing is true and correct.
q(2-4tJb 0 . Limpias Vice President- Nuclear and Chief Nuclear Officer
/bk
Attachment:
Flood Hazard Reevaluation Report, Revision 1 - Revision Summary Table
Enclosures:
- 1. Cooper Nuclear Station Flood Hazard Reevaluation Report, Revision 1 (Security-Related Version)
- 2. Cooper Nuclear Station Flood Hazard Reevaluation Report, Revision 1 (Redacted Version) cc: Regional Administrator, w/attachment/enclosures NPG Distribution, w/o attachment/enclosures USNRC - Region IV CNS Records, w/attachment/enclosures Director, w/attachment/enclosures USNRC - Office of Nuclear Reactor Regulation Cooper Project Manager, w/attachment/enclosures USNRC - NRR Plant Licensing Branch IV-2 Senior Resident Inspector, w/attachment/enclosures USNRC-CNS ENCLOSURE 1 TO THIS LETTER CONTAINS SECURITY-RELATED INFORMATION.
UPON SEPARATION FROM ENCLOSURE 1, THIS COVER LETTER IS DECONTROLLED.
NLS2016049 Attachment Page 1 of 3 ATTACHMENT Flood Hazard Reevaluation Report, Revision 1 - Revision Summary Table FHRR Section # Description of Revision Section 1.1.1 Capacity of 836 is revised to 835.5 Section 1.2. l Description revised Section 1.2.1.1 Minor text change Section I.2.1.4 Text n_10dified Section I.7 Reference 1.7-4, USAR Revisicm xxvi7 revised to xxvil Section 1.7 References I. 7- I 8 and I .7-19 are added Section 2. I .4.2 Last paragraph "Figure 2. I-8 through Figure 2. I-IO" is revised to "Figure 2.1-8 through Figure 2. I-11" Section 2.1.4.3 First paragraph "Zone B and Zone D" is revised to "Zones B and D" Table 2.1-6 An additional row for Cross-section D1450 added to the table Table 2.I-7 An additional row for Cross-section DI450 added to the table Figure 2.1-5 Figure revised to show addition of building Figure 2.1-7 Figure is revised to show new cross section DI450 Figure 2. I-9 Figure is revised Figure 2.I-10 Figure is revised Figure 2.I-I 1 New figure is added in Revision I Section 2.2.5.4 Section is modified Section 2.2.6 Reference 2.2-13 of previsions version is renumbered as Reference 2.2-4, Reference numbers are revised in the text accordingly Section 2.2.6 New Reference 2.2-35 (AASHTO) added, reference numbers are revised in the text accordingly Table 2.2-2 Reference numbers are updated Table 2.2-2 Reference number is updated Table 2.2-14 Table updated according to revised forces Section 2.3 First paragraph, TUFLOW FV software for 2D analysis is added Section 2.3 .3 Section is revised to include 2D analysis Section 2.3 .3 .2 Section title is revised to identify that it pertains to ID analysis Section 2.3.3.3 Section title is revised to identify that it pertains to ID analysis Section 2.3.3.4 New section added to address 2D analysis using TUFLOW FV Section 2.3.5.I Section is revised to include 2D analysis results Section 2.3.5.2 Section is revised to include 2D analysis results Section 2.3.5.3 Section is revised to include 2D analysis results Section 2.3.5.4 Section is revised to include AASTHO method and 2D analysis results for Debris force Section 2.3.6 New reference for TUFLOW FV software (Reference 2.3-3) is added, reference numbers are revised in the text accordingly
NLS2016049 Attachment Page 2 of3 FHRR Section # Description of Revision Section 2.3.6 New reference for Chow, Open Channel Hydraulics (Reference 2.3-14) is added, reference numbers are revised in the text accordingly Section 2.3.6 New reference for Fred, Danny L., Flood Routing Methods and Manning's n (Reference 2.3-15) is added, reference numbers are revised in the text accordingly Section 2.3 .6 New reference for AASHTO, LRFD Bridge Design Specification (Reference 2.3-27) is added, reference numbers are revised in the text accordingly Table 2.3-7 ,New table for Manning's roughness coefficient is added, table numbers are revised accordingly Table 2.3-9 (Old 2.3- Table is revised according to revised analysis 8)
Table 2.3-9 and These tables are deleted in new Revision 1 of FHRR Table 2.3-10 of Revision 0 Table 2.3-10 New table Model Boundary for TUFLOW is added, table numbers are revised accordingly Table 2.3-11 New table for Upstream boundary sensitivity analysis is added, table numbers are revised accordingly Table 2.3-12 New table Monitoring Point Summary is added, table numbers are revised according! y Table 2.3-'13 New table Monitoring Point Summary is added, table numbers are revised accordingly Table 2.3-14 Table is same as Table 2.3-11 of Revision 0 FHRR Table 2.3-15 Table (Table 2.3-12 ofFHRR, Revision 0) is revised for new water levels using 2D analysis Table 2.3-16 Table (Table 2.3-13 ofFHRR, Revision 0) is revised for new water levels using 2D analysis, some new building locations are also added Table 2.3-17 Table (Table 2.3-14 ofFHRR, Revision 0) is revised for new water levels using 2D analysis, some new building locations are also added Table 2.3-18 Table (Table 2.3-15 of FHRR, Revision 0) is revised for revised hydrostatic and hydrodynamic forces Table 2.3-19 Table (Table 2.3-16 of FHRR, Revision 0) is revised for revised forces on Intake Structure Table 2.3-20 Table (Table 2.3-17 of FHRR, Revision 0) is revised for revised debris impact loads Figure 2.3-8 New Figure Land Use Classes for Manning's Roughness Coefficient is added, table numbers are revised accordingly Figure 2.3-9 Figure is same as Figure 2.3-8 of Revision 0 FHRR Figure 2.3-10 Figure is revised Figure of Figure 2.3-9 of Revision 0 FHRR for Peak stage at CNS due to System and Non-System dam failure Figure 2.3-11 Figure is revised Figure of Figure 2.3-10 of Revision 0 FHRR for Peak discharge at CNS due to System and Non-System dam failure
NLS2016049 Attachment Page 3 of3 FHRR Section # Description of Revision Figures 2.3-11 Figures are deleted in Revision 1 of FHRR through 2.3-14 of Revision 0 Figure 2.3-12 New figures based of2D analysis are added through Figure 2.3-25 Figure 2.3-26 Figure is same as Figure 2.3-15 of Revision 0 FHRR Figure 2.3-27 Figure is same as Figure 2.3-16 of Revision 0 FHRR Figure 2.3-28 Figure is same as Figure 2.3-17 of Revision 0 FHAA Figure 2.3-29 Figure is Revised.from Figure 2.3-18 of Revision 0 FHRR Figures 2.3-19 Figures are deleted in Revision 1 ofFHRR through 2.3-22 of Revision 0 Figure 2.3-30 New figure for ground cover is added Figure 2.3-31 Figure is Revised from Figure 2.3-23 of Revision 0 FHRR Figure 2.3-32 Figure is Revised from Figure 2.3-24 of Revision 0 FHRR Figure 2.3-33 Figure is Revised from Figure 2.3-25 of Revision 0 FHRR Figure 2.3-34 Figure is Revised from Figure 2.3-26 of Revision 0 FHRR Section 2.4 Minor revision to the text Section 2.5 Minor modification with one paragraph added Section 2.6 One sentence added after first paragraph Section 2.8.4 Text modified according to updated analysis results Section 2.8.6 Maximum PMF flow revised Section 3.3 Text modified as per revised Section 2.3 Section 3 .10.1 Text modified as per revised Section 2.3 Section 3 .10.2 Text modified as per revised Section 2.3 Section 3 .11.1 Text modified for Reference to updated Tables of Section 2.3 Section 3 .11.3 Text modified for Reference to updated Figure of Section 2.3 Table 3.14-1 Reevaluated flood levels for dam breach are revised Table 3.14-2 Forces in the table are revised