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Category:PRELIMINARY SAFETY ANALYSIS REPORT & AMENDMENTS (PSAR
MONTHYEARML19326C4541970-09-30030 September 1970 Lists Revisions to PSAR Per Suppl 19 to Application ML19326C3051970-07-13013 July 1970 List of Deletions & Additions to Psar:Reactor Bldg Ring Girder Design ML19326C2641970-05-0404 May 1970 List of Deletions & Additions to Psar.Responds to AEC 700126 & 690929 Requests for Info Re Anchorage Zone Buttress Reinforcement ML19326C2891970-03-0909 March 1970 Table of Contents & Change Directions for Psar.Responds to AEC Requests for Info Re Anchorage Zone Buttress Reinforcing.Addl Info Encl ML19326C3011970-01-0606 January 1970 Table of Contents & Change Directions for Psar.Addl Info Re Anchorage Zone Buttress Reinforcing ML19326C2521969-11-14014 November 1969 Table of Contents & Change Directions for Psar.Response to AEC 690929 Questions ML19326C2761969-10-31031 October 1969 Table of Contents & Change Directions for Psar.Response to AEC Questions ML19326C4811968-09-0606 September 1968 Lists Deletions & Insertions to Application for License & Psar,Vols I & Ii,Per Suppl 10 to Application ML19326C4951968-08-27027 August 1968 Lists Deletions & Insertions to Psar,Vols I & II Per Suppl 8 to Application ML19326C5291968-08-15015 August 1968 Amend to Psar,Providing Supplemental Info in Response to Div of Reactor Licensing'S Informal Questions.List of Updated Pages Only ML19326C5541968-07-11011 July 1968 Correction to Suppl 5 to Psar,Providing Supplemental Info in Response to AEC Informal Questions.List of Updated Pages Only ML19326C3891968-07-0303 July 1968 Amend to Psar,List of New & Addl Pages ML19329E1651968-06-28028 June 1968 App 5J of AR Nuclear 1 PSAR, Compilation of Info on Post-Tensioning Hardware Sys for Use W/Prestressed Concrete Containment Structures. Compiled by Bechtel Corp on 680628. Ltrs Encl Releasing Proprietary Info ML19326C5471968-06-0505 June 1968 Amend to Psar,Responding to Questions in AEC 680506 Ltr & Correcting Errors in Certain Pages.List of Updated Pages Only ML19326C5651968-05-0303 May 1968 Amend to Psar,Responding to Questions Raised in AEC 680403 Ltr.List of Updated Pages Only ML19326C5371968-02-0808 February 1968 Amend to Psar,Providing Informally Requested Info Re ECCS & Electrical Sys.List of Updated Pages Only ML19329E1341967-11-24024 November 1967 Chapter 1 of AR Nuclear 1 PSAR, Introduction & Summary. Includes Revisions 1-18 ML19329E1351967-11-24024 November 1967 Chapter 2 of AR Nuclear 1 PSAR, Site & Environ. Includes Revisions 1-18 ML19329E1361967-11-24024 November 1967 Chapter 3 of AR Nuclear 1 PSAR, Reactor. Includes Revisions 1-18 ML19329E1371967-11-24024 November 1967 Chapter 4 of AR Nuclear 1 PSAR, Rcs. Includes Revisions 1-18 ML19329E1391967-11-24024 November 1967 Chapter 6 of AR Nuclear 1 PSAR, Engineered Safeguards. Includes Revisions 1-18 ML19329E1381967-11-24024 November 1967 Chapter 5 of AR Nuclear 1 PSAR, Containment Sys. Includes Revisions 1-18 ML19329E1691967-11-24024 November 1967 App 5K of AR Nuclear 1 PSAR, Prestressing Sys. Includes Revisions 1-18 ML19329E1601967-11-24024 November 1967 App 5D of AR Nuclear 1 PSAR, Load Factors & Load Combinations. Includes Revisions 1-18 ML19329E1591967-11-24024 November 1967 App 5B of AR Nuclear 1 PSAR, Containment Proof Tests. Includes Revisions 1-18 ML19329E1481967-11-24024 November 1967 Chapter 15 of AR Nuclear 1 PSAR, Tech Specs. Includes Revisions 1-18 ML19329E1451967-11-24024 November 1967 Chapter 12 of AR Nuclear 1 PSAR, Conduct of Operations. Includes Revisions 1-18 ML19329E1531967-11-24024 November 1967 App 2C of AR Nuclear 1 PSAR, Groundwater Hydrology. Includes Revisions 1-18 ML19329E1711967-11-24024 November 1967 App 5K,Part 1,of AR Nuclear 1 PSAR, Reactor Bldg Prestressing Sys Stressing (Movable) End-Anchor Bearing Plate Test for AR Nuclear 1. Prepared for Util ML19329E1681967-11-24024 November 1967 App 5J,Part 2,of AR Nuclear 1 PSAR, Nuclear Reactor Post-Tensioning Tendons for Bechtel Corp. Prepared for Submittal to Util ML19329E1671967-11-24024 November 1967 App 5J,Part 1,of AR Nuclear 1 PSAR, Dimensional Info & Test Repts for 90- & 170-Wire Sys. Prepared for Bechtel Corp for Transmittal to Util.Includes Revisions 1-18 ML19329E1641967-11-24024 November 1967 App 5H of AR Nuclear 1 PSAR, Containment Structure Instrumentation. Includes Revisions 1-18 ML19329E1631967-11-24024 November 1967 App 5G of AR Nuclear 1 PSAR, QC Procedure for Field Welding of Liner Plate. Includes Revisions 1-18 ML19329E1621967-11-24024 November 1967 App 5F of AR Nuclear 1 PSAR, Description of Finite Element Technique to Be Used in Containment Structural Analysis. Includes Revisions 1-18 ML19329E1611967-11-24024 November 1967 App 5E of AR Nuclear 1 PSAR, Yield Reduction Factors. Includes Revisions 1-18 ML19329E1581967-11-24024 November 1967 App 5A of AR Nuclear 1 PSAR, Design Bases for Structures, Sys & Equipment. Includes Revisions 1-18 ML19329E1571967-11-24024 November 1967 App 2G of AR Nuclear 1 PSAR, Stability of Soil Slopes. Includes Revisions 1-18 ML19329E1561967-11-24024 November 1967 App 2F of AR Nuclear 1 PSAR, Dardanelle Dam. Prepared for Util.Includes Revisions 1-18 ML19329E1551967-11-24024 November 1967 App 2E of AR Nuclear 1 PSAR, Seismology. Includes Revisions 1-18 ML19329E1541967-11-24024 November 1967 App 2D of AR Nuclear 1 PSAR, Geology. Includes Revisions 1-18 ML19329E1721967-11-24024 November 1967 App 5K,Part 1,App A,Of AR Nuclear 1 PSAR, Stressing End-Anchor Bearing Plate Test Rept. Prepared for Bechtel Corp for Submittal to Util ML19329E1521967-11-24024 November 1967 App 2B of AR Nuclear 1 PSAR, Surface Water Hydrology. Includes Revisions 1-18 ML19329E1501967-11-24024 November 1967 App 1B of AR Nuclear 1 PSAR, Qa. Includes Revisions 1-18 ML19329E1491967-11-24024 November 1967 App 1A of AR Nuclear 1 PSAR, Technical Qualifications. Includes Revisions 1-18 ML19329E1471967-11-24024 November 1967 Chapter 14 of AR Nuclear 1 PSAR, Safety Analysis. Includes Revisions 1-18 ML19329E1461967-11-24024 November 1967 Chapter 13 of AR Nuclear 1 PSAR, Initial Tests & Operation. Includes Revisions 1-18 ML19329E1441967-11-24024 November 1967 Chapter 11 of AR Nuclear 1 PSAR, Radwaste & Radiation Protection. Includes Revisions 1-18 ML19329E1431967-11-24024 November 1967 Chapter 10 of AR Nuclear 1 PSAR, Steam & Power Conversion Sys. Includes Revisions 1-18 ML19329E1421967-11-24024 November 1967 Chapter 9 of AR Nuclear 1 PSAR, Auxiliary & Emergency Sys. Includes Revisions 1-18 ML19329E1411967-11-24024 November 1967 Chapter 8 of AR Nuclear 1 PSAR, Electrical Sys. Includes Revisions 1-18 1970-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
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APPENDIX 2-B SURFACE WATER HYDROLOGY 1.0 PURPOSE AND SCOPE In connection with the safety aspects of the proposed nuclear power plant on Dradanelle Reservoir, near Russellville, Arkansas, certain surface water in-vestigations were made. These included the source and dependability of the cooling water supply, location and extent of lakes and reservoirs, the magni-tude of floods, and effect of possible failure of upstream dams.
2.0 WATER SUPPLY The plant site is located on a peninsula on the left bank of Dardanelle Reservoir on the Arkansas River, abcut 7 river-miles upstream frce the dam.
The downstream side of the peninsula is formed by the floeded valley of Illinois Bayou, a left bank tributary to the Arkansas River. The plant will require 1,700 efs for once-through cooling for a one-unit installation or 3,LCO cfs for two units. This water will be taken from the Illinois Eaycu embayment. The 6 discharge will flow into the reservoir south from the plant. (see Figure 2-2 in section 2) Consumptive use will be about 20 efs for the unit.
2.1 OPERATION OF DARDANELLE PESERVOIR Dardanelle Reservoir is part of the Arkansas River navigation project, pre-sently under construction. The project will provide a minimum 9 fsot navigation depth frcm the mouth of the Arkansas River at the Mississippi River to Catoosa, Oklahoma, near Tulsa, on the Verdigris River, a distance of more than 500 miles. There are 17 locks and dams in the system. Thirteen of these are simple locks and dams, providing navigation lifts of 30 feet or less.
Dardanelle, Ozark, Robert S. Kerr, and Webbers Falls Dams (in order from dcwn-stream to upstream) are higher, with lifts up to 5h feet, and include scme storage for hydropower generation.
Upstream from the head of navigation, there are seven large multi-purpose reservoirs. These reservoirs control the flow frcm about lh0,000 square miles of drainag'e area with about 12,000,000 acre-feet of stcrage of which about 6,000,000 acre-feet are reserved for flood control.
Dardanelle Reservoir is 258 miles upstream from the mouth. A navigation lift of 54 feet raises shipping to the top of the power pool at elevation 336 feet.
The minimum navigation pool elevation is 336 feet, providing a normal two feet of storage in the reservoir for power generation Power generation is en the basis of mean daily inflow equaling mean daily outflow, within the 336-338 feet limits.
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jgllh 2-B-1 - '
7-11,68 Supplement No. 6 ;
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2.2 HISTORICAL' RECORDS OF FLOW Daily streamfl'ow records for the period January 1923, to September 1957, col-lected.at the,Dardanelle gaging station just below the dam, have been adjusted by the Corps of Engineers.to reproduce flows as they would have been regulated by the complete' system of dams upstream. The maximum regulated daily discharge during this 35 year period was L80,000 cfs, while the minimum was 400 cfs.
2.3. LOW TLOW It is possible- for the inflow to the reservoir to be zero undervery exceptional circumstances, but these conditions would exist for only a few hours, during which time there would be more.than enough water in storage in the reservoir to supply the comsumptive use of the plant.
3.0 LAKES AND RESERVOIRS IN VICINITY Lakes and reservoirs with a surface area of 100 acres or more within a 50 mile radius of- the site, and det' ails on ownership, location, use, and size of these bodies of ' water are shown in Figure 2-11. No drinking water supplies are taken from the Arkansas River between Dardanelle Reservoir and the mouth at the Mississippi River.
h.0 FLOODS The highest flood experienced at the Dardanelle Dam site occured in 19h3, with a peak flow of 683.000 cfs. Dardanelle Dam is designed to hold a water level no higher than 338 feet to a discharge of about 900,000 cfs. At higher
' discharges, the reservoir level would rise. The levels along the river chan- !
nel in this area are generally designed for flows of 830,000 cfs.
4.1 b%XIMUM PROEAELE FLOOD The Corps of Engineers has computad the maximum probable flood flow at Dar-danelle Dam as 1,500,000 cfs. At this flow the water level at Dardanelle Dam l
would be 353 feet. The upper end of Dardanelle Reservoir is at Ozark Dam, H about 51 miles upstream. During maximum probable flood conditions, the level of Dardanelle Reservoir at the downstream side of Ozark Dam would be 389.5 feet. No profile for this condition is available, but it is reasonable to assume a straight-line variation. On this basis, the maximum probable flood level-at the plant site is 358 feet.
4.2 FAILURE OF UPSTREAM DAMS The seven storage reservoirs in the headwaters of the Arkansas River are from about 180 to nearly 300 miles upstream from the site. Water from Eufala and Tenkiller Reservoirs must pass through five other impoundments to reach the site; from Keystone and Ft. Gibson, six: from Oolagah and barkham Ferry, seven; and from Fensacola, eight.-In the extremely unlikely event of total failure of one of these dams, the flood wave would be so attenuated by valley and reservoir surcharge storage as to be negligible by the time it reached the plant site.
'It-is considered, therefore, that failure of one of these dams would not con-stitute a hazard to the plant.
()5$Eh b 2-B-2' 2-8-68 Amendment No. 1
The failura of Ozcrk D;m, tha next dam upstream from Dardanelle , presents at maximum power pool level of 372 feet and Dardane gation pool level of 336 feet, there would be a head of 36 feet The following assumptions were made:
- 1. Ozark Dam fails completely and instantaneously.
- 2. The flood wave released is 36 feet high.
- 3. The channel between Ozark Dam and the plant site is of uniform cross-section identical with the section just downstream from the dam .
- h. There is no overflow from the channel.
- 5. No gate changes are made at Dardanelle Dam.
Using these assumptions, the hydrograph of the reservoir level at the site was computed. The maximum rise was about 6.6 feet (reservoir level , 3L2.6 ft) about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after the failure of the dam.
All of the assumptions in this analysis are co. servative . Complete and instantaneous dam failures is essentially impossible
. The head above Ozark Dam would be less than 36 feet by the amount of slopee sur- in th face of the 51 miles length of Dardanelle Reservoir
. The cross-section
( than that directly below Ozark. '2here would o er be sufficien open the gates at Dardanelle Dam and lower the reservoir level .
These actual conditions all differ from the assumptions in such a way as to lower the flood level at the site, so that the computed level rep-resents a theoretical maximum value and the true level ably lower.
er- would be c The of standard Ozark Dam wasproject 600,000flood used by the Corps of Engineerse in th design Under these conditions, cfs the and head for Dardanelle Dam it Dam across Ozark was 625 would 000be . cfsonly 5 0 feet.5.0As only feetfailure high, noof Ozark further studyDam at this was made. time would wave release a flood For the maximum probable flood, the head differential at Ozark would be resulting from an Ozark failure tions as for the previous study, except as follows:
was investigated, g
p-using
- 1. The flood wave released is 11.5 feet high.
- 2. Locks and Dams 13 and 14 are completely submerged soarge that surch will contribute to the flood. storage upstream to Robert S. Kerr Dam (86.5 0252 M
2-B-3 2-8-68 Amendment No.1 '
This computation indicated a maximum theoretical rise in the water level
- at the site of 6.8 feet 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> after the Ozark failure. As in the l
previous case, however, the complete and instantaneous failure of the
! dam is so unlikely as to be practically impossible. All levees would be
- overtopped and an additonal estimated 50 square miles would be flooded, providing a great amount of extra valley storage. .It has been estimated l- that the actual rise at the plant site resulting from failure of Ozark Dam would be about 3 feet. Therefore, the failure of Ozark Dam during a maximum probable flood would result in a maximum 361 foot water level.
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02s3 2-B-4 2 4 -68 Amendmai9 TR%.JL