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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
.
e MODAL CONTRIBUTION TO DYNAMIC ANALYSIS RESULTS
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Prepared for Point Beach Nuclear Plant Unita 1 and 2 WISCONSIN ELECTRIC POWER COMPANY Milwaukee, Wisconsin Prepared by
(*iMPUTECH ENGINEERING SERVICES, INC.
Berkeley, California Ju!/,1981 REPORT NO. R553.02 0110130471 011007 DR ADOCK 050002
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< TABLE OF CONTENT 8 i
k 1 INTRODUCTION . . . . . . . . . . . . ....................... 1 l
2 SE LECTION OF WALLS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3 ANALYSIS M ETHODOLOGY , . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4
' 4 4 A N A LY S I S RE S U LT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1 2- i r
1 5
1 DISC U SSION OF RE S U LTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 4
6 CONCLUSIONS . . ............................ . . . . . 3 l
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1 INTf9000CrlON 3
The Nuclear Regulato>y Committee (NRC) staff on June 9-11. 1981 reviewed the criteria and calculations performed on IE Bulletin 80-11 *
- Masonry Wall Design " for the Point Beach Nuclear Power Plant. Action item 2 resulting from the meeting stated that tne licensee will provide documentation including calculation st;oets that in 'icate that the adoption c" live (5) modes of selsmic response will generally provide 95 % of the total response.
This short report describes the four walls that were selected to document the results the analyses that were perfo ined. the results of the analyses and a discussion of results and conclusions. Appendices A through D provide summaries of the computer culput from which the analysis results were obtained.
2 SELECTION OF WALLS To provide a cross-section of the boundary conditions and openings of the masonry walls at the Point Beach Nuclear Power Plant. the four walls given in Table 1 were selected to document the results of the analyses.
The four walls include two with coor openings and two without openings. Two of the walls are reat connected at their top boundary but a're pinned on the ather three boundaries, one wall is pinned on all four bounderles and the fourth wall is pinned on only two boundaries.
TABLE 1 DESCRIPTION OF WALLS Wall Wai, Boundary Openings Numbs
- Thickness Conditions (in) 5-29/2A 8 Pinned on 3 sides Door on one side Free on top 20/9 8 Pinned on 4 sides Door on one side 65-1/15 12 Pinned on 3 sides None Free on top 64-E/15 42 Pinned on 2 sides None Top and one side free
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3 ANALYSIS METHODOLOGY g
" All walls were analyzed in accordance with the procedures given in Criteria for the Re-evaluation of Concrete Maconry Walls for th3 Point Beach Nuclear Power Picnt ". Specifically, plate analysis was used to assess the out-of-plane response of all walls. The computer program SAP was used to perform a finite Cement dynamic analysis ultilizing the response spectrum method. The Computech pre-processor program GENIN was used to generate input files for the analyses.
For each wall an eigenanalysis was carried out to extract the first five frequencies and mode shapes and the individual modal response:,, were combined using the square root of the sum of the squares procedure.
The SAP output was summarized using the post-processor computer program GENOUT. The computer printout of GENOUT lists seperately the values of the moments and reaction fore es for first mode dynamic response, the SRSS of the first five modes of dynamic response and the values from static loads.
Also given is the absolute sum of the static and SRSS dynamic response values which are the values used to assess the adequacy of the walls.
4 ANALYSIS RESULTS o
The detailed results of the analyses of the four walls are given in Appendices A through D. A sumniary of the results is given in Tables 2 and 3. Table 2 contains a summary of results for walls 5-29/2A, 20/9, and 64-E/15. Table 3 contains a similar summary for wall 65-1/15. For each wall an analysis was perormed assuming the wall was either grouted or ungrouted. The maximum moment parallel (Mx) and normal (My) to the bed joints and the maximum boundary shear fbtce (F) are given in Tab!es 2 and 3. In Table 2 the value of each moment at force resulting from the '.;rst mode and the SRSS of the first five modes are g:ren. Table 2 also contal, s the percentage contribution of the first mode to the SRSS of the first five modes for each maximum moment and force quantity.
Table 3 which contains a summary of results for wall 65-1/15 includes the results from the first mode, the SRSS of the first five modes and the SRSS of the first ten modes. In additlon the Table also contains the .
percentage contribution of the first mode to the SRSS of both the first 5 and 10 modes respectively for each maximum moment and force quantity.
l Also included is the percentage of the SRSS of the first 5 modes to the first 10 modes for each maximum moment and force quantity.
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5 DISCUSSION OF RESULTS
- The results of the analyses for walls 5-29/2A. 20/9. 64-1/15 presented in Table 2 indicates that the first mode contribdes between 97.9 % and 99.9 % of the SRSS of the first five modes for the maximum moments and boundary forces in the walls. Thus for the openings and boundary conditions of these three walls a first mode analysis would have been sufficient to produce 95 % of the tctal maximum response quantitles. A five mode SRSS r.nalysis is therefore adequate for these three walls. '
The results for Wall 65-1/15 presented in Table 3 Indicate that the first mode contributes 90 % of the SRSS of the first 5 modes of response end 90 %
of the SRSS of the '3rst 10 modes of response. The percentage of SRSS of the first 5 modes to the GRSS of the first 10 modes is 99.9 % for the maximum moments and forces. Thus for a waH pinned on three sides and free at the top a first mode analysis would not have been adequate. However.
it is clear that an SRSS of five modes is always equivalent to an SRSS of ten modes.
6 CONCLUSIONS Four walls were selecteo to provide documentation that indicates that the adoption of five (5) modes of response will generally provide'95 % of the total response. The four wolls selected, covered the full range of boundary conditions and openings found in the masonry walls at the plant.
The results clearly indicate that five modes of SRSS response provide 99.9 %
of the total response, in fact for three of the four walls the first mooe of response provided 97.9 % or greater of the total response.
As all tne masonry walls at the Point Beach plant wure analyzed using the first five modes of response It is clear that 99 % of the total response of all the walls has been included in the analytical results.
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TABLE 2
SUMMARY
OF RESULTS FOR WALLS 5-29/2A. 20/h. AND 64-E/15 Wall Mx1 Mx5 Mx1/Mx5 My1 My5 My1/My5 'F1 F5 F1/F5 Number (Lb-in/in) (Lb-in/in) % (Lb-in/in) (Lb-in/in) % (Lb) (Lb) %
5-29/2A Grouted 155.4 155.4 100.0 51.66 51.71 99.9 79.93 80.07 99.3 Ungrouted 83.32 83.32 100.3 27.69 27.72 99.9 42.85 42.92 99.8 i
M Ungrouted 142.2 142.2 100.0 99.06 100.3 98.8 54.49 55.16 98.8 i Part. Grcut 173.9 173.0 100.0 121.2 122.7 98.8 66.64 67.46 98.8 64-E/15 Grouted 64.21 85.96 97.9 101.8 103.2 98.6 229.6 231.1 99.4 Ungrouted 43.61 44.58 97.8 52.75 53.51 98.6 118.9 119.8 99.2 u
Notations:
M- Maximum moment per linear length F : Maximum shear force at boundary i x : Parallel to the bed joint y Normal to the bed joint 1 First mode only 5 SRSS of the first five modes 4
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SUMMARY
OF RESULTS FOR WALL 65-1/16 Wall idoment 1st SRSS SRSS 1st/5 1st/10 5/10 Number or Force Mode 5 Modes 10 Modes % % %
65-1/15 Grouted Mx (Lb-in/in) 172.6 174.5 174.6 98.9 98.8 99.9 i My (Lb-in/in) 27.43 30.26 30.27 90.6 90.6 99.9 l F (Lb) 77.35 84.87 84.98 91.1 91.0 99.9 )
l Ungrouted Mx (Lb-in/In) 109.0 110.1 110.2 99.0 98.9 99.9 My (Lb-in/in) 17.31 19.10 69.10 90.6 90.6 100.0 F (Lb) 48.83 53.56 53.63 91.2 91.0 99.9 Notations: )
M. Maximum moment per linear length F : Maximum shear force at boundary x : Parallel to the bed joint y: Normal to the bed joint 1 : First mode only 5 : SRSS of the first five modes j 10 : SRSS of the first ten modes
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