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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
[Table view] |
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APPENDIX 5-A DESIGN BASES FOR STRUCTURES, SYSTEMS AND ECUI24ENT 1.0 GENERAL The design bases for structures for normal operating conditions are governed by the applicable building design codes. The design bases for specific systems and equipment are stated in the appropriate PSAR Section. The basic design criterion for the maximum loss of coolant accident and seismic con-ditions is that there be no loss of function if that function is related to public safety.
2.0 CLASSES OF STRUCTURES, SYSTEMS AND EQUIR4ENT 2.1 CLASS 1 Class 1 structures, systems and equipment are those whose failure could cause uncontrolled release of radioactivity or those essential for immediate and long-term operation following a loss of coolant accident. When a system as a whole is referred to as Class 1, portions not associated with loss of function of the system may be designated as Class 2.
The following are typical Class 1 structures:
Containment structure shell.
Portions of the auxiliary building that house safeguards systems, con-trol rocm, fuel storage facilities, and radioactive materials.
Enclosures for the service water pumps and auxiliary feedwater pumps.
Supports for Class 1 system components.
Typical Class 1 equipment and systems follow:
Reactor vessel and internals including control rods and control rod drives.
Other reactor coolant system components (steam generators, pressurizer, pumps, etc.) and piping, including vent and drain piping inside the containment.
Containment penetrations up to and including the first isolation valve outside contairment.
Main steam and main feedwater piping up to the stop valves.
Atmospheric dump and main steam safety valves and associated piping from main steam headers.
5-A-1 ,
0323
New and spent fuel storage racks and fuel handling equipment.
Steam-driven auxiliary feedwater pump.
Main emergency generator including fuei supply.
Containment building crane (unloaded condition).
Control boards, switchgear, load centers, batteries, and cable runs serving Class 1 equipment.
Critical service water.
Component cooling.
Containment spray system.
Containment air recirculation.
Low pressure injection and decay heat removal system.
Injection and purification system.
Safety injection tanks and piping.
Radioactive waste treatment.
)
2.2 CLASS 2 Class 2 structures, systems and equipment are those whose failure would not result in the release of radioactivity and would not prevent reactor shutdown.
The failure of Class 2 structures, systems and equipment may interrupt power generation.
30 DESIGN BASES 3.1 CLASS 1 STRUCTURES DESIGN Normal Operation -- For leads to be encountered during normal plant operation (excluding earthquake loads), Class 1 structures are designed in accordance with design methods of accepted standards and codes insofar as they are applicable.
Accident, Seismic and Tornado Loads -- The Class 1 structures are in general proportioned to maintain elastic behavior when subjected to various com-binations of dead loads, thermal loads, accident loads, seismic and tornado loads. The upper limit of elastic behavior is considered to be the yield strength of the effective load-carrying structural materials. The yield strength (Y) for steel (including reinforcing steel) i,s , considered to be the guaranteed minimum given in appropriate ASTM specifications. The yield _
5-A-2 '
strength (Y) for reinforced concrete structures is considered to be the ul-timate resisting capacity as calculated from the " Ultimate Strength Design" portion of the ACI-318-63 code when % is taken as unity. Reinforced concrete structures are designed for ductile behavior whenever possible; that is, with steel stresses controlling the design.
The final desi 6n of Class 1 structures (except the containment structure) satisfies the most severe of the following load cabination equations. (Design equations for the containment structure are given in Section 5, Containment System.)
.Y = (1.25D + 1.OR + 1.25E)
Y= (1.25D + 1.25H + 1.25E)
Y= (1.25D + 1.25H + 1.25W)
(0 90 D is used where dead load subtracts for critical stress in the above three equations.)
Y = 1/p (1.0D + 1.8E) (For structural elements carrying mainly earthquake forces .)
Y = 1/%
Y=1// 1.0D((1.0D
+ 1.0H + + 1.0E')
1.OR + 1.0E')
However, limited yielding is allowable under load conditions specified by the last two equations and under jet or missile forces, provided the deflection is checked to insure that the affected Class 1 systems and equipment (except shielding in the containment vessel under LOCA loading) do not suffer loss of function and the structure retains its required integrity.
Y = required yield strength of the structures.
D = dead load of structure and equipment plus any other permanent loads contributing stress, such as soil or hydrostatic loads. In addition, a portion of " live load" is added when such load is expected to be present when the plant is operating. An allowance is also made for future permanent loads.
R = force or pressure on structure due to rupture of any one pipe.
H = force on structure due to thermal expansion of pipes under operating conditions.
E = " design' seismic load resulting from ground surface acceleration of 0.lg.
E'= " maximum seismic load" resulting from ground surface acceleration of 0.2g.
LW = tornado load.
,/ = 0 90 for reinforced concrete in flexure.
p=0.85for. tension, shear, bond,andanchorageinreinforcedconcrete.
5-A-3 t ,. >
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p = 0 75 for spirally reinforced concrete ecmpression members.
p=070fortiedcompressionmembers.
p = 0 90 for fabricated structural steel.
p = 0 90 for reinforcing steel (not prestressed) in direct tension.
p=095forprestressedtendonsindirecttension.
The contaire nt structure and engineered safeguards systems ccmponents are protected by barriers frcm all credible missiles which might be generated from the primary system. Local yielding or erosion of barriers is permis-sible due to jet or missile impact, provided there is no general failure.
The final design of the missile barrier and equipment support structures in-side the containment will be reviewed to assure that they can withstand applicable pressure loads, det forces, pipe reactions and earthquake loads without loss of function. The deflections or deformations of structures and supports will be checked to assure that the functions of the containment and engineered safeguards equipment are not impaired.
32 CLASS 1 SYSTEMS AND EQUIIMENT DESIGN Components and systems classified as Class 1 will be designed in accordance with the following criteria:
(a) Primary steady state stresses, when combined with the seismic 3
stress resulting from the response to a ground acceleration of 2 0.lg acting horizontally and 0.067g acting vertically and occurr-ing simultaneously shall be maintained within the allowable working stress limits accepted as good practice as set forth in the appropriate design standards, e.g., ASME Boiler and Pressure Vessel Code, ASA B.31.1 Code for pressure piping.
(b) Primary steady state stress when combined with the seismic stress resulting from the response to a ground acceleration of 0.2g acting horizontally and 0.133g acting vertically and occurring simultaneously, shall be limited so that the function of the component or system shall not be impaired as to prevent a safe and orderly shutdown of the plant.
33 CLASS 2 STRUCTURE DESIGN Class 2 structures are designed in accordance with design methods of accepted codes and standards insofar as they are applicable. Seismic design is in accordance with the Uniform Building Code with the appropriate working stress allowance and shear coefficients.
3.4 CLASS 2 SYSTES AND EQUIEMENT DESIGN Class 2 systems and equipment are designed in accordance with design methods of accepted codes and standards. Wind loads and seismic loads, where applic-able, conform to the requirements of the Uniform Building Code.
g 5-A-4 03 %
L-
4.0 MITID A3D EARTHGUAKE LOADS FOR CLASS 1 STRUCTURES 4.1 WIND FORCE Class 1 structures (except the enclosure over the fuel storage facilities) are designed to resist the effects of a tornado.
The structure will be analyzed for tornado loading (not coincident with ac-cident or earthquake) on the following basis:
(a) Differential bursting pressure between the inside and outside of the containment structure is assumed to be 3 pounds per square inch positive pressure.
(b) Lateral force will be assumed as the force caused by a tornado funnel having a peripheral tangential velocity of 300 mph and a forward progression of 60 mph. The applicable portiens of wind design methods described in ASCE Paper 3269 will be used, par-ticularly for shape factors. The provisions for gust factors and variation of wind velocity with height do not apply.
(c) Tornado driven missiles equivalent to an airborne 4 inch by 12 inch by 12 foot plank traveling end-cn at 300 mph, or a h000 pound automobile flying thrcugh the air at 50 mph and at not more than 25 feet above the ground, will be assumed.
4.2 SEISMIC FORCES (E MID E')
AEC publication TID 702k, "Huclear Reactors and Earthquakes," is used as the basic desi 6n guide for seismic analysis.
The " design earthquake" to be used for this plant is a ground acceleration of 0.10g horizontally and 0.067g vertically, acting simultaneously. The " maximum earthquake" is a ground acceleration 0.20g horizontally and 0.133g vertically, acting simultaneously.
Seismic loads on structures, systems and equipment are determined by realistic evaluation of dynamic properties and the accelerations from the attached ac-celeration spectrum curves. (Figures 5-A-1 and 5-A-2) 5 Critical Dancing
" Design Earthquake" (E) " Maximum Earthquake" (E')
(0.lg ground surface (0.2g ground surface acceleration) acceleration)
Welded steel plate assembilies 1 1 Welded steel framed structures 2 2 Bolted or rivited steel fremed structures 25 25 Reinforced concrete equipment supports 2 3 Reinforced concrete frames and buildings 3 5 Prestressed concrete structures 2 5 Steel piping 05 05 5-A-5 I
0327
50 FLOODING Class 1 structures are designed for 358 feet "=aximum probable" flood level.
Class 2 structures are designed for 338 feet " design flood level."
6.o LOADINGS COM40N TO ALL STRUCTURES Ice or Snow Loading -- a uniformly distributed live load of 20 pounds per square foot on all roofs provides for any anticipated snow and/or ice loading.
REFERENCES 1.
AEC Publication TID-7024, " Nuclear Reactors and Earthquakes."
- 2. Housner, G.W.,
"Desisrn of Nuclear Power Reactors against Earthouakes,"
Proceedings of the Second World Conference on Earthquake Engineering, Volume, Japan 1960, Page 133 3 Housner, G.W.,
" Behavior of Structures During Earthcuakes," Journal of the Engineering Mechanics Division, Proceedings of the American Society of Civil Engineers, October 1959, Page 109 4.
Task Comittee on Wind Forces, ASCE Paper No. 3269, " Wind Forces on Structures."
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