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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20217J5801997-08-0505 August 1997 Revised Pages to CAA-96-146, Criticality Analysis of Point Beach Nuclear Plant Spent Fuel Storage Racks Considering Boraflex Gaps & Shrinkage W/Credit for Integral Fuel Burnable Absorbers ML20140D0481997-04-15015 April 1997 Suppl to Evaluation of EQ Impact of Wepc TS Change Request 192 ML20147J2821997-03-10010 March 1997 Rev 2 to Potential Failure of Redundant SR Circuits,Within Mcb ML20140G9941997-02-27027 February 1997 MR 96-069*A, Replace Breakers in 1Y-06, MR 96-069*B, Replace Breakers in 1Y-05 ML20140H0121996-11-15015 November 1996 MR 96-070, Replace Breakers on 2Y-05/06 ML20117L0141996-09-30030 September 1996 Evaluation of Possible Water-Hammer Loads in Svc Water Sys for DBA Conditions ML20117L0051996-09-0909 September 1996 Rev 0 to Operability Assessment for Transient Conditions in Pbnp Svc Water Sys During Coincidental LOCA & Loop,Safety Related ML20141G8411996-05-14014 May 1996 Criticality Analysis of Point Beach Nuclear Plant Spent Fuel Storage Racks Considering Boraflex Gaps & Shrinkage W/ Credit for Integral Fuel Burnable Absorbers ML20096H0181996-01-16016 January 1996 Rev 1 to Seismic Evaluation Rept ML20096H0221996-01-16016 January 1996 Rev 1 to Relay Evaluation Rept ML20094M9461995-11-14014 November 1995 Repair Roll Qualification ML20087H5701995-06-30030 June 1995 Rev 0 to Seismic Evaluation Rept ML20087J7251995-06-30030 June 1995 Rev 0 to Relay Evaluation Rept ML20086B4951995-06-0202 June 1995 Rev 0 to Point Beach Nuclear Plant Emergency Action Technical Basis Document ML20081G4681995-02-27027 February 1995 Rev 0 to Evaluation of Covered Cable Trays in AFW Pump Room at Point Beach Nuclear Plant,Fire Zone 304 ML20078S3621995-02-17017 February 1995 Unit 2 Refueling 20 Repair/Replacement Summary Rept for Form NIS-2 ML20057D9391993-09-21021 September 1993 Rev 0 to Pbnp Diesel Generator Addition Project Design Summary ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20086U1171992-01-0707 January 1992 Rev 0 to Eighteen-Yr Inservice Tendon Surveillance Test Rept,Units 1 & 2 Containment Bldg Post-Tensioning Sys ML20082D4651991-07-22022 July 1991 Wisconsin Electric Power Co Point Beach Nuclear Plant Simulator Certification Rept - Jul 1991 ML20081M7581991-06-27027 June 1991 Addendum to Annual Results & Data Rept for 1987,1988 & 1989 Point Beach Units 1 & 2 ML20247C5971989-04-30030 April 1989 Containment Liner Plate Leak Chase Channel Pressure Boundary at Point Beach Units 1 & 2 ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20195C3001988-10-31031 October 1988 Final Rept for Increased Peaking Factors & Fuel Upgrade Analysis ML20153G7751988-08-31031 August 1988 Safety Evaluation for Increased Peaking Factors & Fuel Upgrade at Point Beach Nuclear Plant Units 1 & 2 ML20154H2571988-04-25025 April 1988 Supplemental Analyses & Comments/Responses to Epri/Wog Analysis of Decay Heat Removal Risk at Point Beach ML20154H1511988-03-31031 March 1988 Difference Between Sandia & NUMARC Analysis of Decay Heat Removal Related Risk for Point Beach ML20154H1871988-03-30030 March 1988 Final Draft Supplemental Analyses & Comments/Responses to Epri/Wog Analysis of Decay Heat Removal Risk at Point Beach ML20148C9851988-02-29029 February 1988 Response to 10CFR50,App R 'Alternate Shutdown Capability,' 4,160 Volt Switchgear Room ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235J3751987-08-31031 August 1987 Rev 1 to Evaluation of Pressurizer Safety & Relief Valve Sys Final Rept ML20236D3901987-07-22022 July 1987 Summary Rept:Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Nuclear Plant Unit 1,1987 ML20236J7371987-07-0101 July 1987 Partially Withheld Final Rept of Ad Hoc Investigation Committee for 870619 Release. Related Info Encl ML20215B6761987-06-0202 June 1987 Evaluation & Analysis of Point Beach Nuclear Plant Unit 1, Reactor Vessel Safety Injection Nozzle-to-Shell Weld Indication ML20205P5461987-03-31031 March 1987 Crdr Summary Rept ML17347B6741987-02-11011 February 1987 Results of Boraflex Exam,Point Beach Nuclear Plant. ML20236N4481987-01-21021 January 1987 Rev 3 to Emergency Operating Procedures, Training Course Syllabus ML20204F1541986-06-30030 June 1986 Evaluation of Containment Liner Plate Leak Chase Channel Sys for Point Beach Nuclear Plant Units 1 & 2 ML20086U1111985-05-15015 May 1985 Containment Bldg Post-Tensioning Sys Thirteen-Yr Surveillance ML20115G3561985-04-30030 April 1985 Radwaste Cost-Benefit Analysis ML20087N4381984-03-30030 March 1984 Sizing of Ultrasonically Detected Indications in Point Beach,Unit 1 Reactor Pressure Vessel Outlet Nozzles ML20087N4431984-03-27027 March 1984 Reactor Vessel Outlet Nozzle-to-Shell Weld Flaw Indication Fracture Mechanics Evaluation for Point Beach Nuclear Plant, Unit 1 ML20087K2161984-03-0505 March 1984 Westinghouse Safety Evaluation,Cracked Control Rod Guide Tube Support Pins ML20107F2701984-01-31031 January 1984 Nonproprietary Software Design Rept for Class a Model & Meteorological,Radiological Effluent & Dose Repts for Point Beach Nuclear Plant ML20080K9511983-12-31031 December 1983 Criteria for Determining Duration of Integrated Leakage Rate Tests of Reactor Containments ML20081E5171983-10-31031 October 1983 Final Rept,Response to 10CFR50 App R `Alternate Shutdown Capability.' ML20077M4371983-08-31031 August 1983 Safety Evaluation for Point Beach Units 1 & 2 Transition to Westinghouse 14X14 Optimized Fuel Assemblies ML20072L9751983-06-0808 June 1983 Present Status & Projected Future Progression of Steam Generator Tube Corrosion/Degradation at Point Beach Unit 1, Wisconsin Electric Power Co,Two Creeks,Wi ML20072C4431983-03-0101 March 1983 Amend 1 to Steam Generator Repair Rept 1999-06-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
[Table view] |
Text
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ACTION ITEM 5 EVAL; ATION OF SINGLE WYTHE ASSUMPTION TO RciPRESENT
, MULTIPLE WYTHE WALLS Prepared for Point Beach Nuclear Power Plant, Units 1 and 2 WISCONSIN ELECTRIC POWER COMPANY Milwaukee, Wisconsin s
Prepared by L
COMPUTECH ENGINEERING SERVICES, INC.
Berkeley, California i
t September,1981 l
l l
REPORT NO. R553.07 i
l . 8109220729 810915 PDR ADOCK 05000266 l G PDR
{ -.
e TABLE OF CONTENTS 1 INTRODUCTION .. . . . ... . . I 2 ANALYSIS METHODOLOGY . . . . . ... .... . 1 3 RESULTS . . . . . . . . 1 4 DISCUSSION OF RESULTS . 2 5 CONCLUSIONS .. . .... .. 2 l
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1 INTRODUCTION The Nuclear Regulatory Commission (NRC) staff on June 9-11, 1981 reviewed the criteria and calculations performed on IE Bulletin 80-11
- for the Point Beach Nuclear Power Plant. Action item 5 resulting from the review meeting stated that with regard to out-of-plane loading, tne licensee shall demonstrate that the use of the single wythe assumption for multiple wytne walls results in a conservative evaluation with respect to frequency shift and out-of-plane drift consideration.
This short report presents the analyses that were performed, the results of the analyses, a discussion of the results, and the conclusions.
2 ANALYSIS METHODOLOGY All walls were analyzed in accordance with the procedures given in
- Criteria for the Re-evaluation of Concrete Masonry Walls for Point Beach Nuclear Power Plant.* Specifically, plate analysis was used to assess the out-of-plane response of the wall. The computer program SAP 5A was used to perform a finite element dynamic analysis. utilizing the response spectrum method.
All wythes in a multiwythe wall were assumed to respond as single wythe walls Decause of the difficulty in perifying the adequacy of the collar joint between the wythes. This was assumed to be conservative when using the re-evaluation criteria and the objective of Action item 5 is to validate the degree of conservatism.
Two double wythe walls (Wall Nos. 24 and 65-1) were selected to compare the results obtained from the wall acting either as a single or double wythe wall using tne re-evaluation criteria, in using the re-evaluation criteria the walls were assumed to have pirened supports at all appropriate boundarles. As a co'iseouence no forces are induced in the wall due to out-of-plane drift.
The validity of this assumption is addressed in Computsch Engineering Services. Inc. Report No. R553.11. Some of the results of Report No. R553.11 are incbded in th;5 report for the purpose of aodressing Action item 5. Wall 24 is 164 inches long.156 inches high and consists of two wythes of twelve inch wide units. Wall 65-1 is 109 inches long.176 inches high and consists of two wythes of six inch wide units. Each wall war anaiyzed as both a singis and double wythe wall using the same number of nodes. mesh size and Doundary conditions. Two boundary conditions were used for each wall; one simply supported on each boundary and the other fra d. For the fixed boundary condition the out-of-plane drift effects were included as reported in Report No. R553.11.
3 RESUt.TS The results of the analyses performed using the simply supported boundary conditions are given in Table 1 and 2. Table 1 compares the frequencies of each wall acting either as a single or double wytha wall. Table 2 compares the maximum stress ratios for each wall acting either as a single 1
a
or double wythe wall. The values given in Table 2 are based on the procedures given in the re-evaluation criteria. That is the walls are assumed to have simply supported boundary conditions.
The results given in Table 3 are extracted from Report No. R553.11 and provide a comparison of the single or double wythe wall with fixed boundary conditions incorporating the effects of out-of-plane drift.
4 DISCUSSION OF RESULTS From the results presented in Table 1 it is clear that the single wythe assumption is conservative with respect to frequency shift. The fundamental or first mode frequency of the double wythe wall is approximately twice that of the single wythe wall. For walls with more than two wythes the shift In frequency would be even greater. The effect of out-of-plane drift effects depends on how this is incorporated in the analysis of the walls and is further discussed in Report No. R553.11. For the case of simply supported boundary conditions, out-of-plane drif t does not Induce forces in the walls and the maximum stress ratios given in Table 2 indicate that the maximum stresses in the wall due to other out-of-plane forces for the double wythe wall are approximately one-half of those of the corresponding single wythe wall.
For the case of fixed boundary conditions, incorporating out-of plane drift effects the results given in Table 3 indicate that the maximum stress ratios for the double wythe walls are from 50 to 130 percent less than the corresponding single wythe walls .except for Wall 24 spanning in the vertical direction. In this case the maximum stress ratio for the double wythe wall is 7.5 percent greater than the single wythe wall. Therefore. for Walls 24 and 65-1 the use of the single wythe assumption to represent double wythe walls generally results in a conservative evaluation regardless of how out-of-plane drift effects are incorporated.
5 CONCLUSIONS Two walls were selected to demonstrate that the use of the single wythe assumption for multiple wythe walls results in a conservative evaluation with respect to frequency shift and out-of-plane drift considerations. The results indicate that the frequency of the double wythe walls are almost twice those of the equivalent single wythe wall. Thereforo, from frequency shift considerations the use of the single wythe assumption is conservative.
The impact on out-of-olane drift considerations depends on how this is incorporated in the analysis With the method used in the re-evaluation criterla no forces are induced in the wall due to out-of-plane drift effects and the maximum stress ratios from other out-of-plane forces in the double wythe wall are approximately one-half of those in the single wythe wall. If fixed boundary conditions are used and out-of-plane drif t effects are included, then the maximum stress ratios in the doubie wythe walls were 50 to 130 percent less than those in the single wythe wall, except for one case in wnich the maximum stress ratio for the vertical span of the single wythe wall was 7.5 percent greater than the double wythe wall.
2 i
The single wythe assumption is therefore conservative for the procedures specified in the re-evaluation criteria and is reasonably conservative for the procedure of including out-of-plane drif t effects specified in Report No. R553.11.
l 3
TABLE 1 FREQUENCY OF WALLS WITH SIMPLY SUPPORTED DOffNDARY CONDITIONS Wall No. Thickness Wythes Frequencies (!!z) 1 12 1 15.39, 37.72 24 25 2 32.06, 78.57 6 1 .15.28, 24.99, 43.97 65 - 1 12 2 30.56, 49.99, 87.95 TABLE 2 MAXIMUM STRESS RATIOS OF WALLS WITH IMPLY SUPPORTED BOUNDARY CONDITIONS Wall No. Thickness Wythes Mx/Mxa My/Mya i 12 1 .3726 .1561 f 24 s..
25 2 .1809 .0751 6 1 .4834 .1572 65-1 12 2 .2146 .0697 l-Note: Subscripts x and y denote stress ratios on horizontal and vertical strips respectively 4
TABLE 3 MAXIMUM STRESS RATIOS OF WALLS WITH FIXED BOUNDARY CONDITIONS INCLUDING OUT-OF-PLANE DRIFT EFFECTS Wall No. Thickness Wythes Mx/Mxa My/Mya 12 1 0.244 0.210 24 25 2 0.129 0.226 6 1 0.264 0.136 65-1 12 2 0.117 0.097 Note: Subscripts x and y denote stress ratios on horizontal and vertical strips respectively
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