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==2.0 CONCLUSION== | ==2.0 CONCLUSION== | ||
S 3.0 SYSTEM DESCRIPTION/DISCUSSION 4.0 THERMAL FLUIDS ANALYSIS 4.1 Introduction 4.2 RELAP Model 4.2.1 Pressurizer Conditions 4.2.2 Valve Modeling 4.2.3 Discharge Piping 4.2.4 quench Tank Book 1 of 10 PAGE 2-1 3-'1 4-1 4-1 4-3 4-3 4 4-11 4-11 4.3 4'4.5 4.6 RELAP Model Control Volumes quarter Model Unit 2 PORV Model Valve Flow Rate Calculation 4.6.1 SV Flow Rate 4.6.2 PORV Flow Rate 4-12 4-19 4-20 4-23~4-24 4-25 4.7 RELAP Plots 4.7.1 Unit 2-400o Solid Liquid Case 4.7.2 quarter Model-Cold Loop Seal/Steam Case 4.8 Force Time History Plots 4.8.1 Unit 2-400o Solid Liquid Case 4.8.2 quarter Model-Cold Loop Seal/Steam Case 4-28 4-29 4-113 4-129 4-130 4-201 4.9 RELAP Input 4.9.1 PORV Solid 400o Liquid 4.9.2 PORV Solid 400o Liquid Restart Book 2 of 10 4-229 4-230 4-250 3Q-"q.f)~iQ..~.'gf r e~-(l~'1 I QQ C el'j I~~7 tt b'I 5~~3-8" t d~--'d C'p f Cii-i'" 1'\J 0 Technical. | S | ||
Report TR-5364-2 Revision 0 TABLE OF CONTENTS ontinue)III E ENQINEERNQ SERVCES PAGE 4.10 REP I PE Input 4.10.1 Model Section A PORV Unit 2 4.10.2 Model Section B PORV Unit 2 4.10.3 quarter Model 4.11 APPENDIX A 5.0 STRUCTURAL ANALYSIS 5.1 Deadweight Analysis 5.2 Thermal Analysis 5.3 Seismic Analysis 5.4 Force/Time History Analysis 5.4.1 PORV Transient 5.4.2 SV Transient 6.0 ANALYTICAL RESULTS 6.1 Stress Summary-4-260 4-261 4-271 4-278 4-286 5-1 5-2 5-2 5-2 5-3 5-3 5-4 6-1 6-1 6.1.1 6.1.2, 6.1.3 6.1.4 6.1.5 6.1.6 6.1.7 6.1.8 Equation A-1 Stresses Equation A-2 Stresses Equation B-1 Stresses Equation B-2 Stresses Equation B-3 Stresses Equation C-1 Stresses Equation C-2 Stresses Equation C-3 Stresses 6-6 6-18 6-30 6-42 6-54 6-66 6-78 6-83 6.2 Support Loads 6.3 Valve Accelerations 6.3.1 DBE Seismic Valve Accelerations 6.3.2 PORV Transient Shock and SV Transient Shock Valve Accelerations 6.4 Nozzle Loads 6.5 Valve Loads 6.6 Miscellaneous Calculations 6.6.1 Thermal Boundary Displacements 6.6.2 OBE Spectra 6.6.3 DBE Spectra 7.0 DRAWINGS | |||
===3.0 SYSTEM=== | |||
DESCRIPTION/DISCUSSION | |||
===4.0 THERMAL=== | |||
FLUIDS ANALYSIS 4.1 Introduction | |||
===4.2 RELAP=== | |||
Model 4.2.1 Pressurizer Conditions | |||
====4.2.2 Valve==== | |||
Modeling 4.2.3 Discharge Piping 4.2.4 quench Tank Book 1 of 10 PAGE 2-1 3-'1 4-1 4-1 4-3 4-3 4 4-11 4-11 4.3 4'4.5 4.6 RELAP Model Control Volumes quarter Model Unit 2 PORV Model Valve Flow Rate Calculation 4.6.1 SV Flow Rate 4.6.2 PORV Flow Rate 4-12 4-19 4-20 4-23~4-24 4-25 4.7 RELAP Plots 4.7.1 Unit 2-400o Solid Liquid Case 4.7.2 quarter Model-Cold Loop Seal/Steam Case 4.8 Force Time History Plots 4.8.1 Unit 2-400o Solid Liquid Case 4.8.2 quarter Model-Cold Loop Seal/Steam Case 4-28 4-29 4-113 4-129 4-130 4-201 4.9 RELAP Input 4.9.1 PORV Solid 400o Liquid 4.9.2 PORV Solid 400o Liquid Restart Book 2 of 10 4-229 4-230 4-250 3Q-"q.f)~iQ..~.'gf r e~-(l~'1 I QQ C el'j I~~7 tt b'I 5~~3-8" t d~--'d C'p f Cii-i'" 1'\J 0 Technical. | |||
Report TR-5364-2 Revision 0 TABLE OF CONTENTS ontinue)III E ENQINEERNQ SERVCES PAGE 4.10 REP I PE Input 4.10.1 Model Section A PORV Unit 2 4.10.2 Model Section B PORV Unit 2 4.10.3 quarter Model 4.11 APPENDIX A 5.0 STRUCTURAL ANALYSIS 5.1 Deadweight Analysis 5.2 Thermal Analysis 5.3 Seismic Analysis 5.4 Force/Time History Analysis 5.4.1 PORV Transient 5.4.2 SV Transient 6.0 ANALYTICAL RESULTS 6.1 Stress Summary-4-260 4-261 4-271 4-278 4-286 5-1 5-2 5-2 5-2 5-3 5-3 5-4 6-1 6-1 6.1.1 6.1.2, 6.1.3 6.1.4 6.1.5 6.1.6 6.1.7 6.1.8 Equation A-1 Stresses Equation A-2 Stresses Equation B-1 Stresses Equation B-2 Stresses Equation B-3 Stresses Equation C-1 Stresses Equation C-2 Stresses Equation C-3 Stresses 6-6 6-18 6-30 6-42 6-54 6-66 6-78 6-83 6.2 Support Loads 6.3 Valve Accelerations 6.3.1 DBE Seismic Valve Accelerations 6.3.2 PORV Transient Shock and SV Transient Shock Valve Accelerations | |||
===6.4 Nozzle=== | |||
Loads 6.5 Valve Loads 6.6 Miscellaneous Calculations | |||
====6.6.1 Thermal==== | |||
Boundary Displacements 6.6.2 OBE Spectra 6.6.3 DBE Spectra 7.0 DRAWINGS | |||
==8.0 REFERENCES== | ==8.0 REFERENCES== |
Revision as of 13:28, 18 October 2018
ML17324B005 | |
Person / Time | |
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Site: | Cook ![]() |
Issue date: | 06/10/1986 |
From: | TELEDYNE ENGINEERING SERVICES |
To: | |
Shared Package | |
ML17324B004 | List: |
References | |
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TR-5364-2, TR-5364-2-R, TR-5364-2-R00, NUDOCS 8608060055 | |
Download: ML17324B005 (295) | |
Text
TEC'8NICAL REPORT TR.,5364"2 REVISION 0 BOOK a OF Xo t DONALD C.COOK NUCLEAR GENERATBfG, PLANT,, ANALYSIS OF PRESSURIZER+SAF~/RELIBP VALVED, DISCHARGE PIPING SYSTEM PER NUTMEG-QV3Tj
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AMERICAN ELECTRIC POWER SERVICE CORPORATION 2 BROADWAY NEW YORK, NEW YORK 10004 P't".~TECHNICAL REPORT TR-5364-2""";-'~'"J t..~j V REVISION 0 BOOK 1 OF 10 DONALD C.COOK NUCLEAR GENERATING STATION ANALYSIS OF PRESSURIZER SAFETY/RELIEF VALVES DISCHARGE PIPING SYSTEM PER NUREG 0737, II.D.l, UNIT 2 JUNE 10, 1983~TELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSfTTS 02254 617490-3350
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Technical Report TR-5364-2 Revision 0 E ENGlNEERNQ SERVlCES'.;TABLE OF CONTENTS
1.0 INTRODUCTION
2.0 CONCLUSION
S
3.0 SYSTEM
DESCRIPTION/DISCUSSION
4.0 THERMAL
FLUIDS ANALYSIS 4.1 Introduction
4.2 RELAP
Model 4.2.1 Pressurizer Conditions
4.2.2 Valve
Modeling 4.2.3 Discharge Piping 4.2.4 quench Tank Book 1 of 10 PAGE 2-1 3-'1 4-1 4-1 4-3 4-3 4 4-11 4-11 4.3 4'4.5 4.6 RELAP Model Control Volumes quarter Model Unit 2 PORV Model Valve Flow Rate Calculation 4.6.1 SV Flow Rate 4.6.2 PORV Flow Rate 4-12 4-19 4-20 4-23~4-24 4-25 4.7 RELAP Plots 4.7.1 Unit 2-400o Solid Liquid Case 4.7.2 quarter Model-Cold Loop Seal/Steam Case 4.8 Force Time History Plots 4.8.1 Unit 2-400o Solid Liquid Case 4.8.2 quarter Model-Cold Loop Seal/Steam Case 4-28 4-29 4-113 4-129 4-130 4-201 4.9 RELAP Input 4.9.1 PORV Solid 400o Liquid 4.9.2 PORV Solid 400o Liquid Restart Book 2 of 10 4-229 4-230 4-250 3Q-"q.f)~iQ..~.'gf r e~-(l~'1 I QQ C el'j I~~7 tt b'I 5~~3-8" t d~--'d C'p f Cii-i'" 1'\J 0 Technical.
Report TR-5364-2 Revision 0 TABLE OF CONTENTS ontinue)III E ENQINEERNQ SERVCES PAGE 4.10 REP I PE Input 4.10.1 Model Section A PORV Unit 2 4.10.2 Model Section B PORV Unit 2 4.10.3 quarter Model 4.11 APPENDIX A 5.0 STRUCTURAL ANALYSIS 5.1 Deadweight Analysis 5.2 Thermal Analysis 5.3 Seismic Analysis 5.4 Force/Time History Analysis 5.4.1 PORV Transient 5.4.2 SV Transient 6.0 ANALYTICAL RESULTS 6.1 Stress Summary-4-260 4-261 4-271 4-278 4-286 5-1 5-2 5-2 5-2 5-3 5-3 5-4 6-1 6-1 6.1.1 6.1.2, 6.1.3 6.1.4 6.1.5 6.1.6 6.1.7 6.1.8 Equation A-1 Stresses Equation A-2 Stresses Equation B-1 Stresses Equation B-2 Stresses Equation B-3 Stresses Equation C-1 Stresses Equation C-2 Stresses Equation C-3 Stresses 6-6 6-18 6-30 6-42 6-54 6-66 6-78 6-83 6.2 Support Loads 6.3 Valve Accelerations 6.3.1 DBE Seismic Valve Accelerations 6.3.2 PORV Transient Shock and SV Transient Shock Valve Accelerations
6.4 Nozzle
Loads 6.5 Valve Loads 6.6 Miscellaneous Calculations
6.6.1 Thermal
Boundary Displacements 6.6.2 OBE Spectra 6.6.3 DBE Spectra 7.0 DRAWINGS
8.0 REFERENCES
6-88 6-125 6-126 6-130 6-134 6-140 6-146 6-147 6-153'-160 7-1 8-1 l rP 1 1: C'i i J l" l.
Technical Report TR-5364-2 Revision 0 A TELEDYNE ENGlNEERING SERVCES TABLE OF CMfENTS Continued 9.0 COMPUTER ANALYSIS 9.1 9.2 9.3 9.4 9.5 9.6 9.7 9.8 RELAP/REP IPE Input Deadweight, Thermal Input/Output OBE Seismic X-Y Input/Output OBE Seismic Y-Z Input/Output DBE Seismic X-Y Input/Output DBE Seismic Y-Z Input/Output PORV Transient Shock Input SV Quarter Model Transient Shock Input Book 3 of 10 Book 4 of 10 Book 5 of 10 Book 6 of 10 Book 7 of 10 Book 8 of 10 Book 9 of 10 Book 10 of 10 8 II~4>VW>C~L"~'<<II II"~"%~..~c I~~f.%III'~I;l~II I I (i~Oc0%I I 4%t Q I%%%~f PP%gI~'%t'~
Techni cal Report TR-5364-2 Revision 0~~r>TELEDYNE ENGINEERING SERVICES
1.0 INTRODUCTION
American Electric Power Service Corporation (AEP), purchase order number 02676-820-1N, authorized Teledyne Engineering Services (TES)to analyze the Pressurizer Safety/Relief Valve Discharge Piping per NRC NUREG-0737, Item II.D.1 for the Donald C.Cook Nuclear Power Plant, Unit 82.This activity was performed in accordance with the TES guality Assurance program which meets the requirements of 10CFR50, Appendix B, and ANSI N45.2.11 as interpreted by Regulatory Guide 1.64, Revision 2.The scope of work for this effort is described in detail in Teledyne Fngineering Services Technical Proposal PR-5653 (Reference 1), dated May 4, 1981 and modified as stated in AEP letter dated November 29, 1982, from Mr.Sam Ulan (AEP)to Mr.L.B.Semprucci (TES)and in AEP letter from Mr.Sam Ulan (AEP)to Mr.~~~~P.D.Harrison (TES)dated March 15, 1983 (References 2 and 3).The majority of the analysis was performed after the receipt of AEP letters dated November 29, 1982 and March 15, 1983 (References 2 and 3), which were issued after more complete information was available from the EPRI data.This analysis was perf ormed using 1 arge dig ital computer programs supplemented with any necessary hand calculations.
The RELAP5 MODl Cycle 14 computer program was used to do the thermal fluid transient analysis.The structural analysis, for all loading conditions, was done utilizing the TMRSAP computer program.The si ze of the pressuri zer safety/relief valve discharge piping system was so large that the computer models, for both RELAP and TMRSAP, strained the limits of.the programs.This condition necessitated multiple RELAP runs in order to execute the thermal fluid transient analysis for the appropriate length of time.For the structural analysis it was necessary to expand the core of the TMRSAP program in order to avoid an overly conservative overlap analysis.
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Technical Report TR-5364-2 Revision 0 2-1><TELEDYNE ENGINEERING SERVICES
2.0 CONCLUSION
S The analysi s perf ormed by TES on the Pres suri zer Safety/Re 1 i ef Val ve Discharge Piping System indicates that all criteria of NRC NUREG-0737, Item II.0.1's met for normal and upset (PORV discharge) conditions and is not met for the emergency (SV discharge) condition.
Evaluation of normal and upset conditions required structural analysis for deadweight, thermal, OBE seismic, and PORV transient shock loading conditions.
Details of the various loadings considered are provided in Section 5.Based on preliminary SV thermal hydrodynamic transient analysis, excessive loads and stresses were anticipated.
It was decided, for economic reasons, that a quarter model SV thermal transient analysis (RELAP5)should be performed to check the adequacy of the system for the emergency condition.
In addition, due to the similarities of the Unit 1 and Unit 2 geometries, it was determined that the results of one unit could be considered applicable to the other unit.The quarter model consisted of the the Unit 2 geometry from the pressurizer, through valve SV-45C, and continuing down to the quench tank, therefore, the SV transient analysis considers only the effect of valve SV-45C opening.Although forcing functions were applied to the limited geometry described, the entire structural
~model was utilized for the analysis.The results of the quarter model analysis, which are considered to be realistic, indicate substantial failure of the entire quarter model geometry.Considering that TES is required to analyze for the simultaneous opening of all three SV valves (Reference 3), which is a more severe loading condition, it is evident that the quarter model analysis is sufficient to predict the failure, for the emergency condition, of both Units 1 and 2.This report, for Unit 2, contains the analysis and results for the quarter model SV thermal condition and the SV thermal transient shock condition.
p~/A fg ptA I'cQ)%f j"a, J gl 4 1 rk I"I'~lA.~a l'~F<<I<<'P.f S Technical Report TR-5364-2 Revision 0 2-2-r>TELEDYNE ENGINEERING SERVICES Section 6 contains a summary of all node point stresses, support loads, valve acceleration
'calculations, pressurizer and quench tank nozzle loads, and moments on the end of each valve for all loading conditions.
It should be noted that valves NRV-151, NRV-152, NRV-153, NM0-151, NM0-152, and NMO-153 are in excess of the vertical acceleration criteria of 2g for the PORV transient shock condition.
Also, the acceleration of valves NM0-151, NMO-152 and NMO-153 exceeds the 3g horizontal criteria for the PORV transient shock condition.
These values are considered acceptable per the approval given by AEP in their letter of May 26, 1983 from Mr.Sam Ulan of AEP to Mr.P.D.Harrison of TES (Reference 7).Valve SV-45C has acceleration values in the 12-30g range for the SV transierit shock condition, which exceeds all criteria.
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Technical Report TR-5364-2 Revision 0 3-1 ri TELEDYNE ENGINEERING SERVICES 3.0 SYSTEM DESCRIPTION)DISCUSSION The Pressurizer Safety/Relief Valve Discharge Piping consists of all of the piping from the pressurizer nozzles, down to the sparger in the quench tank.This information is depicted on TES drawing E-5761, Revision 2, generated from AEP drawings 2-GRC-22, sheets I and 2;2-GRC-23, sheets I, 2, and 3;-2-GRC-24, 2-GRC-25, 2-GRC-26 and 2-GRC-27.The"Discharge" piping constitutes a very large system resulting in a large computer model.The size and geometrical complexity, which is due mainly to the sweeping curves around the pressuri zer, complicates the modification effort in addition to causing longer run times.Modification of this complex system, to attempt to secure satisfactory.
~~~~"Safety Valve Discharge" results, is limited to draining the SV loop seals.Heating the loop seals is not a viable"fix" because of the size of the loops.These long loops contain sufficient quantity of water such that on SV Discharge, the water seal does not"flash" completely enough to reduce the very high loads caused by the water slug.Modification to the support system is also a poor option because of the very limited space in the annulus around the pressurizer, which makes construction very difficult.
C QP I ge r t t*l Technical Report TR-5364-2 Revision 0 4-1 A TELEDYNE ENGINEERING SERVICES 4.0 THERMAL FLUIDS ANALYSIS 4.1 Introduction The thermodynamic fluid analysis determines the fluid forces which act on the pressurizer safety and relief valve discharge piping of the American Electric Power, Donald C.Cook Nuclear Power Plant, Unit 2.These forces are generated by the sudden opening of the pressurizer safety and relief valves during one or more of the pres suri zer trans i ents des cr i bed in the AEP l et ter of November 29, 1982 to TES (Reference 2).These fluid forces and the resulting loads and stresses on the piping system became of increased concern as a result of the incident at Three Mile , Island.Following the Three Mile Island incident, the NRC issued NUREG 0578 and NUREG 0737, which required that each utility determine the effect of safety/~~relief valve operation upon the valve and the discharge piping.An elaborate program involving both testing and analysis was established under the general management of the Electric Power Research Institute (EPRI).The EPRI program included intensive testing of safety and relief valves as well as a full scale safety valve test facility, built at Combustion Engineering in Connecticut.
Simultaneously, an analytical program was initiated by Intermountain Technologies, Inc.to choose and test a computer program which would predict the fluid forces;RELAP5 MODl was chosen.RELAP5 MOD1 is the latest in the family of RELAP programs developed at the Idaho National Engineering Laboratory.
In this analysis, TES has used RELAP5 MODl version 2.11 as it is made available through Control Data Corp with a post-processor, REPIPE version 3.10, which calculates the fluid forces.This version of RELAP5 MODl is identified by the following computer job control language at Control Data Corporation:
8EGIN, RELAP5, R5M2, INPUT=INPUTFILE, SCM=3770008 Technical Report TR-5364-2 Revision 0 4-2-ri-TELEDYNE ENGINEERING SERVICES The computer.analysis procedure for the thermal analysis portion is included in Appendix A.RELAP5 calculates hydrodynamic data for control volumes in each segment of pipe.REPIPE then takes this data and defines two force time histories for each segment, one set for inlet junction forces and the other for outlet junction forces.A TES generated program, SAP2SAP, adds these force time histories.
Finally, one force time history for each segment of axial, unbalanced loads is analyzed structurally.
Technical Report TR-5364-2 Revision 0 4 4 3.-r>TELEDYNE ENGINEERING SERVICES 4.2 RELAP Model 4.2.1 The D.C.Cook pressurizer was modeled as a single time dependent volume with the following transient conditions as specified by the American Electric Power, November 29, 1982 letter to Mr.L.B.Semprucci, pages 1-7 (Reference 2):~Ef 4 7 Pressure Time History (in the pressurizer) 2750 2700 Pressure (psr)650 2 745 742 27 7 F.o 2700'667 o-e2750 2750 2600 2600 2550 o'2555 2500 o 2514 0.5 1.0 Time (Sec)The safety valve pressure boundary conditions were used in analyzing the quarter model cold loop seal case.
t~~!<0 Techni cal Report TR-5364-2 Revision 0~~4-4 rs TELEDYNE ENGINEERING SERVICES PORV Pressure Time History (in the pressurizer) 2550 2500 Pressure 2450 (PSI)2400 0 2350 2300 0.8 0 6 Time (Sec)1.2 Using the above pressure boundary conditions, two cases were analyzed.Case 1 is a steam discharge preceded by a condensate loop seal and Case 2 is a 400oF subcooled water discharge.
It was determined in the Unit 1 PORV as-built analysis (Reference TES repor't TR-5364-1, Section 4.5.2)that Case 2 was the controlling case and, therefore, the Case 1 analysis is not repeated in this report.4.2.2 Safety valves and power operated relief valves were modeled as RELAP junctions using the following information:
SV Crosby HB-BP-86 (Ref.13)0.022 Ft2 Manufacturer Orifice Area 0 enin Time 0.010 Sec.PORV Masoneilan NO-38-20721 (Ref.14)0.00806 Ft2 1.0 Sec.
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Technical Report TR-5364-2 Revision 0 4-11 r~TELEOYNE ENGlNEERINQ SERVtCES Valve orifice areas were calculated using the EPRI Safety and Relief Valve Test Report (Reference 16)and RELAP (Run ID BAICDRO)implementing rated flows.Calculated values are included in Figure 4.6.1.4.2.3 Discharge piping was modeled from all safety and power operated relief valves to the quench tank.This discharge piping included the following pipe sizes: 3 inch, 12 inch 4 inch, 6 inch 4 inch 3 inch, 6 inch SCH 40 SCH 40S SCH 120 SCH 160 Friction factors for long and short radius elbows and reducers were taken from technical paper$410 by Crane (Reference 19).Calculations of~~~~~these frictional losses are included in Appendix A.The discharge piping is defined in segments of straight sections from;elbow to elbow, valve to elbow, etc.The SV model is modeled from one safety valve to the quench tank.This is a simplified model which was determined to be an adequate representation of safety valve discharge piping and is referred to as"The Quarter Model".This Quarter Model was used to get bounding loads for the cold loop seal discharge, and is further explained in Section 4.4.4.2.4 The Quench Tank was modeled in two parts: the sparger and the tank itself, using cylindrical volumes containing water and air.The quench tank volumes were taken from Westinghouse Dwg.No.110E272 (Reference 15).The sparger for D.C.Cook is a perforated pipe submerged in the water within the quench tank as indicated in Figure 4.2.1 of this report.It is r epresented in RELAP as a pipe similarly submerged and of equal volume.
Technical Report TR-5364-2'evision 0 4-12 A TELEDYNE ENGINEERING SERVICES 4.3 RELAP Model Control Volumes The"Evaluation of RELAP5/MOD1 for Calculation of Safety/Relief Valve Discharge Piping Hydrodynamic Loads" report prepared by Intermountain Technologies Inc.(Reference 18)recommends using ten or more control volumes per bounded segment when modeling valve discharge piping for RELAP5, while avoiding significant control volume length differences to preserve pressure wave shapes.The ten control volume criteria recomnended by ITI was adhered to by TES in all cases, except in piping arcs and in segments less than three feet in length.The D.C.Cook discharge piping is modeled using as few as one control volume per segment (pipe segments with lengths less than 0.5 feet)and up to thirty-two control volumes per segment.Arc modeling for Unit 2 is represented in Figure 4.3.1.All arcs for Unit 2 were modeled in RELAP as having no fluid losses.Essentially, RELAP calculates these as straight sections of pipe.REPIPE, however, distributes the calculated forces to pre-assigned node points matching the TES structural models.model were: Average control volume lengths used for the D.C.Cook RELAP Unit 2~Pi e Size Avera e C.V.Len th 3 inch SCH 160 6 inch SCH 160 4 inch SCH 40S 6 inch SCH 40S 12 inch SCH 40 3 inch SCH 40 4 inch SCH 120 0.5264 feet 0.5019 feet 0.5056 feet 0.8871 feet 0.8526 feet 0.4744 feet 0.4471 feet The schematics of the discharge systems modeled in RELAP for the PORV~~~Unit 2 model and the SRV quarter model are given in Figures 4.7.1 and 4.7.2, respecti vely.
Technical Report TR-5364-2 Revision 0~~4-13 r>-TELEDYNE ENGINEERING SERVICES quench Tank modeling was achieved using twenty control volumes and twenty junctions.
Eighteen volumes conprise the sparger model while the remaining two are single volumes modeling the water and air spaces of the quench tank.The water and air volumes as determined from Westinghouse Dwg.No.110E272 (Reference 15)were input to RELAP to insure proper quenching capacity.Eighteen control volumes forming the sparger are initially 88K full of water representing a submerged pipe.The discharge holes were modeled as a single hole with an area of.7773 ft.2, at a point on the sparger where the sum of the small hole areas equals the 12 inch schedule 40 discharge area.Finally, the tank rupture disk is modeled as a pressure actuated valve placed on the air volume and set to blow out at 100 psig discharging to atmosphere.
Figure 4.2.1 represents the O.C.Cook Unit 2 quench Tank.
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Technical Report TR-5364-2 Revision 0 4-19 A TELEDYNE ENGINEERING SERVICES 4--.4 9 M d 1 A review of the testing that was done at Combustion Engineering in Connecticut indicated that the as-built analysis for the safety valves could potentially fail the system.The cold loop seal discharge.
test at C.E.produced loads of 175 Kips.The D.C.Cook Unit 2 pressurizer has three safety valves with a loop seal larger than the C.E..test facility loop seal, therefore, it was decided to make a small'ELAP model of the D.C.Cook Safety Valve discharge line.This model contains one safety valve (SV-45C)including corresponding loop seal, and discharge piping through arc level 669'-2" up to, but not including, the quench tank.This model would be less expensive to run than the full three valve model.The results of this quarter Model confirmed TES's suspicion that the cold loop seal case would fail.At this point, TES was able to make a parametric study of loop seal temperature and valve opening times versus peak loads, as shown~~below.Only the steam discharge proved to be acceptable, therefore, TES is recomnending draining the loop seals.Loop Seal Loop Seal Temperature Position of Valve Opening Max Load Condition oF Loo Seal Time Sec LBF Col d Cold Hot Hot Hot Hot (Sat.Water)Steam 141o 141o 350o 350o 350o 650o 650o Upstream Downstream Upstream Upstream Upstream Upstream Upstream 0.010 0.010 0.010 0.090 0.130 0.090 0.010 115,000 174,000 156,000 109,000 124,000 38,000 6,000 The loop seal temperature distribution was calculated and input to~~~RELAP, and is included in Appendix A.The temperatures used for the cold loop seal ranged from 584.4o at the pressurizer to 141.1o at the valve.
Technical Report TR-5364-2 Revision 0 4-20 r E TELEYNE ENGINEERING SERVICES 4.5 Unit 2 PORV Model The inlet piping to the PORV's is sloped toward the valves and, during normal oper ating conditions, a saturated water (condensate) loop seal is formed (at the inlet to the PORV).As specified in American Electric Power's letter of November 29, 1982, (Reference 2)referring to PORV transient conditions, the following cases were to be analyzed: Case Transient Condensate/Steam Discharge 400o Solid Liquid Discharge In the D.C.Cook Unit 1"as-built" analysis, it was determined that Case 2 was the controlling case (Reference TES Report TR-5364-1, Section 4.5.2).~Therefore, only the Case 1 analysis is pres'ented here.As in the Unit l."as-built" analysis, the 400oF solid water case exhibited unstable behavior (oscillations in the flow rate).At approximately
.400 seconds the flow suddenly decreases approximately 30 ibm/sec in lmsec.This behavior can be seen plotted in Section 4.7.1.A careful review of the RELAP output did not reveal a good physical reason for such behavior.The reasons for such behavior could be 1.A sudden reduction in the valve area vs.time data.2.A build up of back pressure in the discharge line which will cause the valve flow rate to suddenly decrease.3.A sudden decrease in pressure in the pressurizer boundary condition which would result in reduced flow.
Technical Report TR-5364-2 4-21 A TELEDYNE ENGINEERINQ SERVICES All these things were considered to determine if they were possible sources of the flow rate fluctuation.
The review indicated that they were not the source of the problem.A partial tabulation of this review is shown below: UNIT 2 Valve Junction f415 Cont.Vol 50001 Flow Cont.Vol.41021 Reference RELAP RUN BHFRBGO UNIT 2 400-600 msec Solid Case Junction 8415 Mass Flow LBM/Sec.Cont.Vol.Cont.Vol.F41021 f41021 Thermodynamic Pressure PSI Cont.Vol.850001 Pressure PSI)Cont.Vol.550001 Thermodynamic ualit.409 83.6.407 105.9.408 106.4 0.0 0.0 0.0 2160.9 2169.2 2996.7 248.15 248.50 247.73.0088.0088.0089 It can be seen that the downstream pressure does not exhibit a sudden increase that would reduce the flow through the valve.The upstream quality t remains zero indicating that the flow through the valve is subcooled.
Technical Report TR-5364-2 Revision 0~~4-22-ii-TELEDYNE ENGINEERING SERVICES The pressure increases upstream which corresponds to a sudden reduction in flow area, however, the flow area increases, it does not decrease.The pressurizer time dependent volume does not exhibit any sudden change in pressure which would correspond to this flow change.Past experience with the RELAP programs has shown problems with subcooled water and low quality steam flow.These problems have manifested themselves as severe oscillations in the flow rate.It is TES's opinion that the results fran the RELAP run are highly conservative and overpredict the fluid forces.When the fluid forces from this RELAP run were combined with the seismic, deadweight, and thermal expansion loads, the c'ode allowables were~~~~~~~~~~slighlty exceeded.Since the principal fluid loads appear to be a result of an instability in the flow rate predicted by RELAP and not a result of an actual physical phenomena, it was decided that these loads were overly conservative and could justifiably be reduced by 2(5 at the structural input p'oint.The fluid forces presented in Section 4.8 and elsewhere in Section 4.0 are the"as calculated" loads and have not been reduced by 2(C.It should be noted that an alternative modeling pr actice that could have been employed in the solution of this problem would have been to make the PORV valves time dependent junctions and specify the valve flow rate, however, this method requires the elimination of upstream piping.At the beginning of.this project it was decided to place the entire system, upstream and downstream piping, in one model as the flow instability was not anticipated.
Had this alternative been used, the flow rate oscillation and the resulting forces would not have occurred.
Techni cal Report TR-5364-2 Revision 0 4-23.A TELEDYNE ENGINEERING SERVICES 4.6 Valve Flow Rate Calculation The following values were used in valve modeling considerations:
Valve T e TES Flow Max Rating*Rate Calculated For Steam Bore Area Opening LBM/HR ie 3X Acccm.~IN2 Time (Sec)Crosb a ety Relief Val ve Masoneilan p Relief Valve 523,332 199,000 435,000 3 6 in 2 0 010 (Ref.18)1.0*The maximum rating for steam at 3X accumulation value is from the Crosby Valve and Gage Safety Valve Orawing No.H-51688, Revision A (Reference 13).
Technical Report TR-5634-2 Revision 0 4-24]E TELEDYNE ENGINEERING SERVICES 4.6.1 The valve flow rates used in the RELAP analysis of the SRVs were obtained by increasing the ASME rated flow by 15K;10K to consider the ASME underating of the theoretical flow and 5$to cover tolerances.
TES flow rate calculations are included in Figure 4.6.1.where: Napier's Eq.WT=51;5 AP ASME rated flow: WR=51.5A (1.03P+14.7)(.9)(.975)C (Ref.17)WT=theoretical flow WR=rated flow coefficients:
1.03-applies 3X accumulation 0.975-valve flow coefficient 0.9-represents theoretical flow rate reduced 1(C to equal ASME rating The equation TES uses to calculate the valve flow rate is Wmax=1.05 x 51.5A (1.03P+14.7)C(0.975) explained above.This is an increase of 15K above the ASME rated flow as Techni cal Report TR-5364-2 Revision 0 4-25-rs-TELEDYNE ENGINEERING SERVICES 4.6.2 The Masoneilan PORV maximum flow rate for steam was taken from the EPRI Safet and Relief Valve Test Re ort (Reference 16)as 199,000 ibm/hr (Table 4.5.1-1b).
A valve opening time of 1.0 second is used based on total valve opening times of all Masoneilan valves tested, times are listed in Table 4.5.2-1.Since full open times averaged 2.76 seconds, with a minimum value of 1.64 seconds, TES has assumed 10(5 opening'n 1.0 second, because independent'esting has shown that flow is not always directly proportional to stem travel.Most often full flow is obtained before full stem travel.Because 1 second is a very long opening time, this was not considered overly conservative.
Technical Report TR-5364-2 Revision 0)5 TELEDYNE ENQINEER)NQ
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Technical Report TR-5364-2 Revision 04-28-ri TELEOYNE ENGINEERING SERVICES 4.7 RELAP Plots The following plots represent RELAP mass flows, pressures and qualities at various points along the discharge piping.Since RELAP had to be restarted, the plot time scales may vary (i.e.0.0-0.2 seconds or 0.0-0.400 seconds).Also, the ordinate axis may not always be correct;many times multipliers will be off (CDC is aware of this problem in RELAP).However, the plots do depict the trend accurately and are calculated and reported in RELAP every 0.001 seconds.Correct peaks and times at which they occur are listed with each trace.Plot Set Transient 4.7.1 Unit 2 4.7.2.quarter Nodel 400o Solid Liquid Case Cold Loop Seal/Steam Case A RELAP volume schematic precedes each plot set.
Technical Report TR-5364-2 Revision 0 4-29 (l TELEDYNE ENGINEERING SERVICES I 4.7.1 Unit 2-400o Solid Li uid Case A TELEDYNE ENQINEERINQ SERVICESCHICO.BY Y OATE~+IY I 4-30~'POrLV'I/I DO WE'LW J Zoot c SC+E~~7 tC.uQ IT2 Pond s6'cTioN o/SHEET NO.OF FIGURE 4.7.1-1 Et II BIO<os gt TM'Qb/OI og//01 Co~P (Q qb c.o P.~coo hloTB+INO<ICAT KS A Cowl1ovi QT Gf G I<<<&'.N V6 6E=Q5 I 1ST'E: b1 OVT 51bf couTs'.ot voI.oH ch AWE cow Tarot vol'vH g Mvm SC RS.'fATD 7 HVRQ~S I ISTCP IM+Ibg VOI v~E'5'Re V RQSe~r Vk f VZA'S EIID I/I I 0>~wvHIB CQ oI T~o 1 5 8 4 H 6'J T.VOE vM'C5 351 ASVINS.4 giaour Co<I'JO T'6;QI qC.E SHCC'1 (0)
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9o1 C3 JE;A I 8o5 l~~c//o/J)s/~~T/i)A/Q~e r/n//8c>b g//c.'/0~QW~Cv Jd~c~/M~N,'CJAJ C JT/P JE//of ,
C7 RELfFS/t$01/0)4 REACTOR LOSS OF COOL%?AHA.YSIS PROGRRII AEP UNIT2 l LlNE RENPS 83/05/20.Cl rn IQ 9)(a tV Cb t/4-ioR.I el~cIoc~c bt~~o g CD o CD 8 8~O<<8 K Cl/0 M W C0~e I 0~iUl&Vl GJ H O WO I Al C)A)O 5 m Sm O.CI 0.!I 0.24 TlIK ISECI 0.e 0.4b REI.RPS/NO1/Old RC8CTOR LOSS Of'KM.AT AN%.VSIS PROGRFN Od.3 a.P9¹Ca.0 Z a.~Bc 0.4{0.44 0.5l 0.54 TltK lSECl O.H lD RELAPS/tSOI/Ol4 RDICTOR LOSS N COOLIE RNR.YSIS PRONRII AEP UNIT2 I LINE REUVS 83/05/20.Ip Co',0 O (O'5'o-'Ioo-'ec M S~R C3 o S R Wg C3 O O t,a 0.14 TllX (SEC)0.4b CD W CD I 0~i Vl&Q 4)D Ol~0 WO I Al C)CD O I Ct' RELRPS/NOI/014 REflCTOR LOSS OF COOLfST ANHDStS PROCRAtl a r-~-c.S./ST~gZ~~0.44 0.4I O.SR 0.5b T]NE ISECI OAQ D IICI.II("~/tGOI/014 REIII:TOR I.OSS Of C%l.fttT ANR YSIS PROGBAII fiEP lltIIT2]LINE Rf:IRP5 0.5/05/20.
C7~~Cu 4" 4 tV CO IH ci 0.00 0.1$0.4b CD M lD I 0~e Vl&vl 4)D S>0 4 0 I Ol C)lD O s Z Sm RELAPS/AD]/Old REACTOR LOSS Of'NLfST flHfi.YSlS PROQRNl XJ-I W lD X)0)n (Jl S EA GJ W Cl 0 A n I C)A)O 0.55 RELfFS/t$01/OI4 REACTOR LOSS Of COOLfM RHR.ISIS PROGRAff AEP UHIT2 I LINC RElBPS 83/05/20.30.5$o.a 0.14 O.H Tlat%fSEC)0.45 CCCCC<<~ae.Jd&K WiPTid~~SRfiiSTi le RELAPS/t$01/Old REACTOR LOSS OF COOL@IT ANR.YSIS PROCRAtl a 9~".O bt~a 8 C)o 8 8 Nlt R X7-I M CD W CD I 0 CJ1 D M GJD o wn I CD CD o o g a.fCVD C2 0.d0 O.i)0.%0.52 0.54 TltlE tSECl O.dd C)C)7%hQI W N A'4 IW A le~I&Jk~~bsaCf MD SMCt Df REI IIPS/tl)0]/0]4 RLACTOR I.OSS Of COOI.ftIT RIIB.YSIS F'ROGRAII AEP IIWIT2]L]NE Rt:IMPS 83/OS/20.n O I0 oQ J 4-r Kl W W ID Kl ID I O Vl S M Io~0 WO I DP ED ID 0 00 0.14 0.14 T]HE I SEC I 0.31 0.ie C)C7 ius io mum sc&~i'.Q RTTi RElAPS/tSOl/Oll fKACIOR l.OSS OF Cfmt.AT ANFLYSIS PROGRfO o/5@,y'+y~op c4 M o g E3 o Cl r o O 8 i rz./ZScs fb Mrp i A (Jl H tji GJ~C)4~A I lD'o O rt 0.4).'--O.R 0.4d 0.5l O.S4 T]tK lSEC)'0.54 CQ C7 Sauau" uzi'-Ieae~, i's<<iaaf, iiavCtaeI.O amruei if f A.l<f>if-Xlplioia RMCrOR Lass of'npfmt fed.>sts VROf;Rnff REP tftffT2 l l.lllE HEIR'S B3>OS/20.V).0 6)Q V (')I)8 CO a')K Kl M W CD M CD I O~iVl&Vl 0 4 A I C)CD O~I O.N O.fa 0.24 t]WC fSEC)0.El O.cd C7 REI.BPSINDI/014 fKACTOR I.OSS Of'MLFNT fINFl.ISIS PROGRRII C7 O C)oo CDÃ7 fD o Ul 3 EA 0 w o I C)O O 0.4)L45 O.M IIHC ISCCI 0.5b 0.50 O.N
C7 heal jul Nil.v tal Bee, leal JAHwel~cwcIos lA ssAAcV1V kELIJf'5/Jlj01/OI4 fKACTOR LOSS Uf CAOJ.NJT f8'.'fSf5 PROGRfltl flEP litf[T2 l l.ltJE HElBP5 83/05/20.tQ Q 0 r4 I l l a C3 8 R A~C)L.Z 0 15 0.ji T]tlat lSEC)0.32 0.40 RELAPS/N301/014 REACTOR LOSS OF COOLfNT RNR.VSIS PROBRRN CI IA D O 0.40 0.48 0.5R TItK lSECI CD na ao xi>>.is w>>ia,'sa-~.caaettmi.o
%shams~!ttl:l.ld a/tK)O]/Old REOCTOR l.055 Ot COOl.fNT FNR.IStS PROGRRtt OLI'JtllT2 l l.)tlL Rf:LIPS 03/05/20.CD rn 4 bl Cb IH Ci 0 CD o O 0 R CD L.i~'xJ CD MCD C C n~~VlV Vl O O O I AP'P 0.00 0.0l 0.le 0.24 TltK ISEC)0.C0 O.Ce-t2..2.LQ n.2.97 PD~C)CD CI O s Ct CD IIII RO CLX~&liAl IR~t, Rf'XPSf%IR~I, WAIF" RELAPS/tSDl/Dll RfACTOR LOSS OF'mlLFNT RNR.'fSIS PROGRfN C1 pz CD rn CD I bl IQ (u ID CI C3 D 0 Si R CI Q O 9/.oui't-I M CCI M ID I O CPI D Ill 0 W 0 I C)K7 fD O 0.j1 I]HE (SECI 0.b4 fcEf.fliS/]if lO)/014 REACTOR I.ASS Of'OO].BJT AtA.YSIS Pf]OCRAlf fiEP OtJfT2]L]NE f<QBPS f]3/05/20.
Cp 1 CJ IP 0.00 0.C4 0.I5 0.21 T]HE lSECl 0.'R 0.40 0.45 Kl M W CD Xl CD cin Ul~Vl O WO I Al C)CD o 1 RQ.RP5/tSOI/Ol 4 RERCTOR l.OSS OF CMI.FBI'NFl.ISIS PROGRRI 0.4b O.R T]NE (SEC)0.60 ea 4aa u 44.a 4e)S 4444 4ai iaeieee 0 aiiCiaCtie
\~SihP e RE<.r>>a/e)O>/O)~
REnCrna EOSS Or COOEWr AHa.VSrS VRnCRAn AEP tlWl72 l l.lNE HEIBP5 83/05/20.(p (b W Cl 8d o lA)~CC~O 0 O D O.oo(31 Q 0'kQ~0.14, 0.14 TltK lSECl OA)0.1S C 0 lTI V)
RFLAPS/N)OI/010 REACTOR LOSS OF COOLRJT ANf%.'ISIS PROGRAM.0 3O8~.///OO~zcS O d O Oo 8~8 QB gl K.aoB(/.ago 0.44 0.5l llHE ISECl REi.p~a/rppi/O>~
ra-RIOR i.OSS ar Conner nba.>SC (SCC)0.32 O.OOqaI@O~~-'C'.C-0.40 0.48 CD RELAPS/NlOl/014 REACTOR LOSS OF CmlLFNT ANN.'fSIS PROGRAM o o m.m M-I-l lD Kl fD I 0 O.H 0.4b 0.52 Tlt1E lSECI 0.55 0.00 O.M C7 was uu'vi)sa" niami ivy m~nae, tucwd~is"ilaw 4.)Rt:I.life/tl)01/014 REflCTOR LOSS Of Clal.RlT AHf%.TS[S PHOGHAtl Kl'tllT2 1 LlNE ROMPS 03/05/20.C3 C)ID Ho C)C)lA<o 0 re o o D O.M 0.!4 0.2<T]K (SECI 0.1I~g)gg(9 ()'/CO~CO 0.44 lD WA)I 0 Ul 3 0 AO I Ol C)fD O s RFLAPS/t$01/014 REACTOR LOSS OF COOLFNT ANR.'!SlS PROGRAM (A D Ul O.WA I f1'O O.Q 0.4$0.'Q Tlirt lSECl 0.55 O.M O.H C7 RLl.nlS/IQDl/Old RLACTM l.OSS OF'OOt.BIT AHR.YSIS PROGRAtl ACP UNIT2 l L]NE RQBPS 83/05/20.C3 O e 8 ci'4 C)This is the quality upstream of the discharge valves dur ing the subcooled discharge case;there-fore, the quality is zero.Vl<ci o O.a 0.II 0.24 TlHC tSCCl O.G Q~+0 aeq 0.&0.40 ID RELAPS/%$1/014 fKRCTOR LOSS Of COOL%IT NR TS15 f'ROQRAH O O I C)O O IO This is the quality upstream of the di schar ge val ves dur ing the subcooled discharge case;there-fore, the quality is zero.Vl K~O O%7MW ID o Vl+III~.CA~.own I III d D.40 0.44 0.48 0.Ll TitlC (SCCl 0.00 0.SE
RO.AI'5/tSOI/014 Rf ACTOR LOSS Of CKIIMT AN%.ISIS PROGRAtl AEP UNIT2 I Llttf.HDBPS 83/05/20.This is the quality upstream of the discharge valves during the subcooled discharge case;there-fore, the quality is zero.0.15 0.24 TIN ISCCl 0.0 Q O.+Q 4eC 0AO D.40 C3 III'III IL 7C IW, IRl RD.APSltSD)
IDl fKACTDR LDSS Of'M.AT f$8.'ISIS PROGRAM~l o l3 O sO 8 CI'i Ql Q v CL~0 a This is the quality upstream of the discharge valves during the subcooled discharge case;there-for e, the quality is zero.<<Q 0.40Q M(XJ l~CD X)CD o CJI M VI Ch~.CD wo I PV~C)ID o O 5 0.44 0.44 O.SR EKE (sec)0.$0 O.M iua aalu m.mca na menu,'isa~, 6iciicfah~ihisinkaPia RLI.AI'S/tf)OI/014 fKACTOR l.055 OF'OOI.SIT SA.'ISIS PRODRAII AEP UNIT2 1 I.INI: RLIBP5 S3/05/20.C7 m 4'.0 A O ao 8A FV Ql tA j w K~A O This is the quality upstream of the discharge valves during the subcooled discharge case;there-fore, the quality is zero.IV A A A 0.00 0.04 0.I 4 0.2i TlHE I SECI O.M oo Q c3.'/oo~t'.0.40 O.m fD~~n~'Jl M l/l Ch~i o wo gp tV~C)fb O REl.APS/N$
1/Old REACTOR LOSS Of CH)LfST RNB.TSfS PROGRAtl This is the quality upstream of the discharge valves during the subcooled discharge case;there-fore, the quality is zero.0.%O.KR TltK lSECI C7'ani~a.usi iiYa~, im~.biian~iw caa7iacs V'a Rf:I.OPS/tSO]/Old fKACTfiR l.055 Of COOl.fNI'HA.ESfS PROQRAtl flEP QJIT2 l l.fhf;Ilf:(Jlf'S 83/OS/20.O Cl 8 ci N Vl$v CL'8 This is the quality upstream of the discharge valves during the subcooled dischar ge case;there-fore, the quality is zero.D.0.00 0.04 0.14 0.2(0.%Ill fSECJ o.o Q c,.m~c(0.44
RELY/tSD]/010 REACTOR LOSS Of CNL84T NFL'JSt5 PAOGRNf This is the quality upstream of the di schar ge val ves dur ing the subcooled discharge case;there-fore, the quality is zero.O.iI 0.5l TltK tSECl 0.50 O.H CD hall ate)R 4.J IRR 4 W, ISR)%4tWA~WVCRNCCII IRWIIIRI 0)RCl.ll/S/ISIOI/Old IKRCTOR LOSS Of'INI IN.P~RWil SI.S PROCRRII AEP owl T2 1 I.lWC REIBP5 03ia5120.CD m ()Cb IJU IA)t'L ci O~.IOQ 5o)0 Kl ID I 0~~VIV I/I O WO I CD 0)n O s 0.00 L ll O.la 0.2(TlwE lSEcl O.M 0.40 0.<e C7 aoi res sama MTi a5,~RELAPS/t%DI/Old fKACTOR LOSS OF CE)LNI'NR.YSIS PRODRAH D C7 2 m D D O~~Ul K O.Ip x.Ql~zsk~t 0.+0.5l Tlat%tSECl 0.60 nba Iaa iu.e'nC a eS,"im u~, CieoaaSZA am&%V t<o.tits/tant/Ota REttCTOR l.OSS Or CteLt>Jr AHa.rStS PROCRntt fiEP tttJIT2 l LltJE REtBPS 83/05/20.(p tV Cb ,IH I Ch I og C)Ho 0)tg~O 0 Q 0 0.00 0.OI O.te O.li 0.3l IlttE tSECt 0.40 0.1e-0.9301K (9 g gco~c lD X)lD I 0 Ul K Vl 0 WA I Ql C)It0'u O s I t I Sm I lg CD;Pl I IC'0 t CD C7 aa~arc~~6~%a.
ikey~REI.APS/NDI/0]0 REACTOR L055 OF'MI.AT FINFL'fS]S PROGRAII O IO m m p~&C.)<<a O O 0 0 8ci 5)Ill~ci O.07/0~AD'd 0.40 0.4I O.R T]HE ISECI O.et
CD Ilail I~ll sl II OE A&I, Ilail 44&IA4%i CIIIIICfSO'I 4 6ISOhkM Lf kt.'t.ft&/tMtl)t/014 fKAN'OR l.OSS 01'00t ftÃANiA~lSI VR06RAtt AEP ttttlT2 1 LlttE RflIlVS 83/OS/20.CD m)0 os~<~(1 II I O D o 0 d 0.00 O.M 0.IS 0.2E T]I1C tSECI 0.40 0.4S Cb 0~iVlD VI O WO I Al CD C0 n O rt I m RQ.APS/tSOI JDI4 REACTOR LOSS DF CIILfNT RHfi.ISIS PROGRfN This is the quality in the con-trol volume immediately down-stream of the safety valve.Ouring this transient (which is a PORY transient) the safety valve remains closed;therefore, the quality in the control volume remains at 1.0.0.45 0.$l Tlt1c (sEcl C7 hiR~lk a~l4 le 1I PH~IQ lk&fAV4~~M$1.0 Ol'XXI C4~f RI:I.I'>fa/IX101/010 Ht:IM:TOM LOSS OI CDOI.RI1'NR.TSIS I'ROGRAII RCP IlkllT2 1 1.1Nf;IKIfiI'S 03/05/20.CJ CJ O A 8 ci m O l/l)v<ci Q Ct O O.I 8 0.2L TINE ISECI 0.40
>>1L St~RQ.APS/t$01/014 REACTOR LOSS OF C93LfST RNR.YS[S PROGRAtt a'~3~v'c o O>>go Vl Cd O ill I~~g d 0 KJ-I W CD R7 CD 0 CJl D O O 0.44 0,4I 0.51 T]ttL tSCCI 0.50 C7 kt:I.III"~IN)O)/0)4 REACTOR I.OSS Of'OOI fNT fINft.YSIS PROGRAM ACR Ilrit T2 1 I.)NL RQ)IPS 03105120, C7 m I.o p c.~wc.N Ho R ig D 0 0 0.I I-0.2E T)IIC ISCCI 0.Jl 0.40 0.4b Al X7 (D I 0 Vl K GJ'D 0 WO I Ql C)lb O S D C 7l WF RELAPS/t$0l/Ol REACTOR LOSS OF COOLfM SA.TS 5 PRONAtl D D m m C)ee O This is the quality in the con-trol volume immediately down-stream of the safety valve.During this transient (which is a PORV transient) the safety valve remains closed;therefore, the quality in the control volume remains at 1.0.I<pOVOO4~X7-0 W CD (>n~'01 3 0 wn I Ql PO~C)CD O S V O1 OeQ 0.44 0.5l TltK (SEC)0.54 0.4(
fctt.Af'5/Nl0)/011 fCCACTOR l.OSS Gf COOt.FAT AN835IS PROGRAtt ItL'P lttll12 l t.lttL RElRP5 83/05/20c V Q)tg C3 O+Ho'CO lA)V+D O O/0 W W CD X)CD I A CJ1~EA 0 WO I FO~C)%7 CD n O RCI.RPS/%01/0) 4 fKRCTOR LOSS OF COO!.FNT AH%.TSIS PROGRAII J8>Q~O.Sl TINE ISCCI HEI Bf'5/)ill)l/Ol1 fKACTOR l.OSS Of COOLft)l')A.'fSIS PHOflRR)l REP f)NIT2 I LINE RE)A lPS 03/OS/20.O d 0.00 O.N 0.)e 0.2E 0.32 Tl&ISEC)0.05 CD'n O C7 hO%$III.Q.SC~IW RCLAPSINlOl/Ol 4 REACTOR LOSS OF ClHLfNT Mi.YSIS PROGRAM O CD m CI I4 O oa O This is the quality in the con-trol volume immediately down-s tr earn of the saf e ty va1 ve.During this transient (which is a PORY transient) the safety valve remains closed;therefore, the quality in the control volume remains at 1.0.I 0 8 0 goo ye~C0 Mm o~'Vl D VI Ol~.04O I CII FO~CD CD O 0.44 LR Tlat%(SEC)0.58 0.b4 RCI.fIr~/renI/OIC RDICrnR L0SS Or CIII.@IT IIaa.>SOS PIIOCIIm flEP IIIT2 I L]NE REIflpS 83/05/20.0.I4 D.24 TIIIE ISECI CD nba~mKiF&nm.C RELAPS/t$01/014 REACTOR LOSS OF'(ILfST ANN.ISIS PROGRAtl o Oo o tfl K OQ 0 8 d.'.40 0.44'.D TIHC lSECl
'A'\
CD htt!tsk h.at X I'k A tht WS W+fWO~C4dK?+E$1ll Sly A LS REl.fil i/tX'j01/Otl REACTOR l.OSS OF COOl.fNT AtiB.'FSIS F'ROGRAtl tiEl'lttfT2 l L]t<E REINS 83/05/20.CD V Co ()t t.v tz tV 0)LH 2.S2..9L p.Ct~4C-'C-8 ctt 8 a.Ct n 0.15 0.RC 0.3l TttlE lSEC)0.40 0.<a Kl W W CD M 0)I 0~iVlD EA 4D D Ao~W 0 WA I Ql CD n o S Q Z~Rm Q 0)m C 0 (D Rl;l.RPS/t$
01/014 FlF:RCTOR LOSS OF C001.Alt AN%.'YS IS PROGRAtl O O P.2 rn m Vi I (b (v (9 W CD (I O Vl 3 0 W 0 0.4<O.Q O.52?tHE ISF:CI O.S4
CI heal~11 1I 34 AE A Ser ISLI$4~i Qh%+KlsS llI haSStUI&kl REf.APS/N)f)l/014 REACTOR f.OSS Of COOf&lT flNR JSfS PROGRAM AEP fRJIT2 l f.lfJE HEI RPS 03/05/20.V N lg (a tV Cb LH I CO Ul P4 LI g cv D D O.l4'0.21 TltlE fSECI 0.44 REI JiPS/NOI/OIW REACTOR LOSS OF CXILfST RNR.YSIS PRODRAN n.PYg sac@0.4S 0.52 TlnC'ISCC)
CD i'O i'fifa eIC'am, CSO~,'~Sid iW aiiUR A kEt.flP5/ti)01/0)4 fcEACTOR I.OSS Of OOOi.f%T RNA.'/SI5 PROCRAtl AEP UttIT2 I LINE RElflt'5 B3/05/20.$)O xP 2'I~.0 7 g~'C(I 00 P4~O h re J~O Oa C3 O O.0.l4 0.24 TtttE ISECt 0.Zl 0.40 0.04 CD MCD I 0~.CJl~Q CAB 0 AA I PJ~CD CD O C 0 Pl V)
RELRPS/t$01/014 REACTOR LOSS OF CMLFNT AHFL SIS PROGRAtI-Z3'cC O.Q 0.4I O.D TltIC ISECI REIM5/tIOI)]/014 REACTOR I.OSS Of COOI.Ft(T ANR.'fSIS PROGRAtt IIEP UhllT2 I LINE ftEIN'S II3/05/20.
CI Cu (n bJ IH-Z.>C 9.t (3~.'IOG Cc4C.CD X)lD n Vl M EA 0 WO I Ql C)CD O EV 0.t4 0.24 0.3l T]tIE ISECI 0.40 0.44 n RELRPS/NSI/011 REACTOR LOSS OF'M.AT SA YSIS PROGRfN ID W CD I 0 Vl V M GDW 0 WO I C)Kl CD o Oo8 L%0.50 TIE IKC)LN
C)7C RLI.OI a/tf)OI/014 REACTOR LOSS OF'OOI.BtT RNfl.TSIS PROGRRII AL'P IIN[T2 I LlNE REIBPS 83/OS/20.g P~g x~I CD WCD I 0>~CJl 2 Cab N O WO I Al CO CD n O S C+0.00 0.IX a.Ia a.a T]IIL ISECI 0.Xg 0.40 0.%
RELAP5/t$01/Old REACTOR LOSS OF COOLFN RHR.'ISTS PROGRAM O.Q 0.'D TltK lSECI C7~aMXau u.mii m arne,>~', e~WS C.O aikuai a RCl.fiPS/N)DI/Old BI:ACIOR l.OSS Of COOt.fNI'NB.'fSIS PROGRBtl HL'P ttttIT2 I t.lttE RElfiPS 83/OS/20.C7 rn 4 tJ Cb LH>a N~Q 6.O-ztv9 80Am seC Q rq~~0.00 0.l4 0.14 0.11 TltK ISCCt RELAPS/N30
/0]4 RERCTOR LOSS Of C93U%T ANB'ISIS PROGRAH C7 m b 0 zX y, pre fV X hIR 8 8 O o.e, 0.4I O.R T]HE ISECI O.N RLI.AI i/INDI/Oll fKACTOR I.OSS OI'OOI.Qkl'IAASIS PROCRAN AEP UIIIT2 I LINE RQBPS 83/05/20.N O j5 a C7 0.00 O.IS 0.24 Ill (SCCI 0.Sl 0.%
RELfFS/NlOI/OI 4 fKRCTOR L055 OF COOLfNT SA.'ISIS PHOGRA 0.4I 0.%ZItK (SEC)0.54 0.80 hELRll'5/tlODI/DIN REACTOR l.OSS Of COOLFtlT RNR.YSIS PROGRFN flEP DNIT2 I LINE REIAPS 83/05/20.-97.7 I Q o'I~~tr bJ (b\H O.N 0.II 0.25 Tlt1C ISfC)0.4b I WCD I A CJl M Vl 0 WO 1 CD C0 o O lTI%m Q C 0 C7 C7 rn/tM1/014 REACTOR LOSS Of fN S S PRONAti~a x l 0&9.5z5po.sd 7>fQ~O gP,P+g Q<J 0.%u 4'C'0.5l TlttC lSEC)O.H REl flP5/t)OO)/014 fKACTOR LOSS Of COO).fNt 8Nf%.'ISIS PROOR8tl fQ;P IIWIT2 I Llt)E HE)BI'5 83/05/20.o.oa~0.04 0.14 0.2(?It)E lSEC)0.3R RELfFS/t$01/014 RERCTOR LOSS OF'93 l%AH%.Sf PROGRftl P7.+$CI~~&.$/9 5w I CD CD Kl W W CD~A)(I O~eUID GJ W~o~~, ohio I CD ID D S O.CO O.Q TltK l SECl tent'.I.fftl'5/I f IQ I/Q1 4 REACTOR LOSS Ql I:00I.BIT AHf%3Sf S PROGRAII fit;P ItttfT2 l I.ltIE Rf:IJIP5 83/05/20.~0.Ie O.lt 0.3l I'ItIC ISCCI
U O m m RELfFS/NDl/0]l fKACTOR LOSS OF CKLfST RNR.ISt5 PRONRtl gj~g/+os~Sec~g p gg+~c7.+00 Oeti 0%TltK (SEC)0.54 0-NO'.H CD~CD I 0~iVlD VI GO M Ae 0 WO I Ql CO CD O I HEt.fits/tf)01/Old REACTOR LOSS Of COOl.BtT ANB.'tSIS VROliRAN AEt'tW[I2 1 LltJE RELAP5 83/05/20.~C)o O.M 0.04 O.t0 0.24 T1AC lSECl 0.40
CD CU-C'hie xa ia si<a w a rw, iw Xioesaco~aswfQKQ 68rvt ia 1 7 Ift.l.OI'S/IK)01/OIW 8:0(:TOfT I.OSS Of CNI.fWT fINfl.gS[S PHOGIIf III ll'D I C<1 CD rll C)"~~X ('t 1 (~PP do'CD a.0.4(0.40 0.52 4.54 TIIIL ISFCI 0.60 o.a<co I Vl Eil 0 1 PO CD co cj O I P1 Q V)fll (0 ,01 REl.tll a/t$0)/O]l RCflCTOR l.OSS OF'OOl.ftlf ANf%.ISfS PROGRAM REP UNIT2 l l.lNE BEIBVS 83/05/20.;0 w" (p tV 0)IH I CD Vl CD Kl CD n CJl M Vl 4)g 0 An I CD R7 C0 u O Q Z 0.14 0.l4 TlnE tSECi 0.bl 0.44 REI.APS/tSOI/014 REACTOR LOSS Of CN3LFNT AHA YSIS PROGRAM 3.9I.S sec Ce Qb S>C-&5".i.i'cs'l W W CD Kl Cb I h CJl D Vl Ol~0 A h I Cll CD A)O O EV 0.fI O.Q 0.5l 0.54 T It%'(SEC I 0.4(
CD~IIIl X4"4 AO'W"5 rWI, IWl'4inWN.
CNOIICt 1SCTZQSitUlCI U kLL.N'5/tSOI/OIN REACTOR 1.0SS Of'Mt.f%T fINR.YSIS PROCRRtl C)Pl Q O~O r~RCP ttt<IT2 1 LINE HElBf'5 83/05/20.V l'I 3)tn bJ LH-~t.58g g<.(CC~C I CD'V h HQ 8 Rg 0.II 0.2t O.M TlttE t5EC1 0.iO Kl M W CD I 0>o Vl 3'CrJ D 0 WCl D I PO~CD fD n O z Q 0 m C7 All I L~~~, St%ttWlTT RELAPS/tSDl/014 fKACTOR LOSS OF COOLIE RNR.1SIS PR06RRti D~4 (i)I 9)(u I C)CO Ib S>8 H.KIWW lD I 0 Ul~EA Ch~.0 W 0 I fO~4D K7 A)o O s O.Q 0.44 0.$2 Illa'SEC)0.64 Rfi.eanenl/Ole rrnCtOR LnSS nr Cpni.WT Wa.VSrS PROCRAn AEP UHIT2 I l.lNE RElBP5 03/05/20.-53 0'IQ Q o.fo o.a 0.(4 0.14 TlHE lSECI 0.M 0.44 RQ.feSiND1/Old fKACTOR LOSS OF Cppt.FNT AN8.1Sts PROGRAM srm O O m rn (gi Ob (u I C)O.Q O.Q O.SR tlVC (SCC)0.50 O.N KJ W M I Kl lb I 0 Vl~Vl O W O I QJ O P m V)
CD tlute'ha@rrt lt.tl tel A tRI, IICl gua r DSCMCf~I4 4l~~REI tilw/lSOl/OI4 REACTOR l.OSS OF COOl.RJT AJJl%.'ISlS PROGRAM REP llNIT2 l I.llJE RElBP5 83/05/20.CD Pl CI Po O)4 tV N gA I~r~Vt GJ CA 0 l CD K7 CCt o s ITl%m O.II 0.24 Tlt1E lSECI 0.CB C3 RELAPS/tSO1/014 RERCTOR L055 Of CIILFNI'NR.ISIS PR06RAtl O A Pd.P.s ssc 5 Pl~O 8 8 PS s~0.4<0.4I 0.5l TINE ISECl 0,60 Techni ca 1 Report TR-5364-2 Revision 0~~4-113 A TELEDYNE ENGINEERINQ SERVICES 4.7.2 uarter Model-Cold Loo Seal/Steam Case Techni ca 1 Report-TELEDYNE ENt"INEERiNG SERVlCES 4-114 sv DATE I IB.BB CHKD.BY~DATE~DltcHgft.ce Ua'I 7'2 SHEET NO.Dp)PRO J.No.P'Z'&f'7 Cccxse y'4'4 oo(o C~g~W/Z E'e pWOp'o<our IO$0$E~dr~>o 5~ABDLVBE E EPEB 7 guE=ra d/C)/S2o/93<vCrW 0/+ll/S~///Q Ill'P II 27.II7 3.mOI'<~<~<Ijr~5 lfgPf glgf I EfOp//oo~7DI/If fEP TT~/I Sf*IIS II FIGURE 4.7.2-1 RCLBPS/NNl/0 fKACTOR LO 5 Of CHION RHR.TS 1 S PROCRfN UN T2 L NE RECAP 3/2/05.CI ea a O o 0 8o o o j=0.0 0.2'lit%ISEC)O.i RELAPS/NS/0 RCA OR RE 5 83/2/05 S PRO RAtl o n 0 0.0 0.2 0.<Tlat%tSEC1 CD Xl CD (I n CJI M ICI 4J D own I~N CD O IIIII CI I%i'L%b O RELAP5/t601/Ol fKA OR LO S OF'NLfNE fNR.YSlS PROQRfN AEP UNfT2 l INC RElfM'5/02/05 53.4 dOZ 5 5 C O 8 Gn n ill 0-O~sV~.ooVsa c 0.0 O.R TltK fSECI 0.4 0.~
CD Kl ED I h CJl M Vl 0 A h I Qf C)P3 fD"o O$RELAPS/f801/Old REACTOR LO 5 K C f8 AN%.Sl PROGRAM AEP IJIIlT2 L)NE RQBP 83/0/5.F95 2./d.ZZC o'c O Z m O O d 0.0 O.R TIE ISKCI RQJFS/t$0/fKA OR 0 OF.%ANH.S PH RfN P UNl 1 L NE RELY'02/4.2 TltK tSCCI O.i RELAPS/t$0/0 REA OR OSS MLS'NR.ISIS PRmlRfN REP UNfT2]LlWE RELAP5 83/0/05.H aQ-D 8 8 8 0.0 0.2 T1HE lSECl O.i RCLAP5/NSl/01 fKACTOR LOSS 0f CI3LFN NA.'fS IS PROCRfN IKP UNfT2 L HE R if@83/2/05.0 Q~Q Q 0.0//5 C o O d 0.0 O.l 4.4 lit%(SEC)O.e
lKLAPS/tSOI/01 fKR OR LO S Of'ElLFN ANI.NSlS PROGRAtt REP UN I T2 1NE RC BPS 3/02/05.0.1 L4 tltK tSKCl CD X7 CD (I 0 CJI W EA lA D 0 W 0 I PO C)CD a O C+RLLm/mp ip C aCRerOR LOSS OF'tmrar rag.>S S r R RAn REP Nt L1NE REUPS 63/02/05./AC.8(g o.zto saic hg c4 O d 0.0 0.1?le tSCei O.l 0.0 0
II%Ilail ILIA N'b a~O I>>RELAPS/t$0/Old REACTOR LOSS Of CKLfM ANR.ISIS PROCRfN AEP UNlT2 l LlHE RELRP O3/02/05.CI A P4 X sv O II.Cl ID D CD O D 0 I~Cl o 0.0 O.l lit%ISECl 0.4 I wA)C I 0 CJl M I/3 C/J N ID&0 I CD fD o O RLLAPS/NS]/
RL OR LOSS.fNT ANA.PRONN1 b O~O REP UNIT2 I LINE REI/IP 3/02/05.K O ID I: O 0.0 O.R O.E Tlat%lKC)O.I CT R L 5 Of CMllM ANB.Sl PROGRAM AEP Wl T2 INC REPS/02/05.O o QO 83 h O 2I mi O 0.0 0.2 0.4 TltK lSECI
KlWW CD M CD n Vl 3 Vl Ol~0 4 n I DC Kl CD o O rt RELAPS//0 I;RCTOR LÃ.f%AHA.S t PRONATE RD'JHtT2)NE R lBP 83/0/05.U 8 8 go I 0.0 0.2 tltK 15EGI O.E O.e CD X)e (I n CJl M Ul o wn Al tD'n O j RELAPS/NOI/O RERCTOR LOSS 0f'.M'A.YSIS PROGRAII REP UN(T2 I ItK REI 83/02/05.ZaeZ.Zg>o.SF'o 8 8 0.0 0.3 0.4 O.l
Technical Report TR-5364-2 Revision 0 4-129/i TELEDYNE ENGINEERINQ SERVICES 4.8 Force Time Histor Plots The following are force versus time plots for each pipe segment at a node point described by the structural model.A drawing indicating force placement precedes each set.Since the force time histories were plotted after balancing and merging(i.e.
SAP2SAP and MERGE), each plot is unbalanced force versus time from 0.0 to 0.6 seconds.The problem was run to 0.6 seconds because all significant forces in the area of concern (piping about the PORV's)had diminished in this time.Unit 2 (PORV)quarter Model 67 segments 26 segments Plot Set Transient 4.8.1 Uni t 2 PORV 4.8.2 quarter Model 400o Solid Liquid Case Cold Loop Seal/Steam Case Technical Report TR-5364-2 Revision 0 4-130 is TELEOYNE ENGINEERING SERVICES 4.8.1 Unit 2-400o Solid Li uid Case
~)i TELEDYNE ENQINEERINQ SERVICES 4-131 BY C~DATE~9 CHKO.BY OATE~8$VM iTE STRICT'AURAL HOnE>ai~i5>>R9 S~C-T i OW SHEET NO.BP I.~*FIGURE 4.8.1-1 (@Id C047Iro OA7)ON sE E sHEQ7 g
-><-TELEDYNE ENQINEERlNQ SERVlCES 4-132 BY C7C.DATE 8 j.~3 CHKO.ST+~~OATS~+~<
3 oM sT 2 5TRvcT'VRA(-
gobi p(oiu~SRV SEC.T>o&SHEET NO.OF 2 3 FRom GtcKT Sv.95 A Qo)P((lES5.Sv ASS Qz(s PRKS5.s P(R(." Q(g Q(go Op SV 05<~(((y (Q(20 Q PgljSS.FIGURE 4.8.1-2 Q(oe Qll 0 (Qso Agc.l COhJTLMVQb a tJ SHE,KT 3 i0 TELEDYNE ENGINEERlNQ SERVlCES 4-133 cHKo.BY~~DATg Z-//83 U<iTZ srRuC.ru'RA<
wool~<~gq tg'~h)QQg M SHEET HO.SF 3+RE&sHGET 2.FIGURE 4.8.1-3 ARC.i Technical Report 4-1 34 TE;g gyp'G: NEER i qg~=~V'ES 6-'J JN-8~SAP2S AP.VER i', iCATiON 5c64 iJN2 YEi-,RED SQL i D ALOOF 0-60" NS TiNE/FORCE TABLE 1.MAGN!T JDE AT NODE I-Q.NT 340 I lD)N I TINE v~I qy P/i2 OA>E d-Z'.8Z CHKD.BY~DS'<~~
Technical Report TR-5364-2 Revision 0 4-135 SAP 2S 4P, VER!";C 4='!OR 5364 UN2 YEL-RED SOLiD<OQF 0-600 lS T,IME/FORCE TABLE 2 RAGNI UDE AT NO.E PO NT h O~O~CO Oa U n TiNE BY/Vl+DATE 6 Z'.83 CHKO.BY~OATE~
4-136 Technical Report TR-5364-2 Revision 0 c.i<<0~hl<S:9'gicE S AP2SAPlIt ER i,,".6'QN 5364'2 YEL-RED Sg;;D 4POF O<"ONS~~~AGNITJDE 4T NQQE CO O~CV%LA O CYY~CO~cu T I[ATE>~J I~60 BY P//2 PAYB g~@CHKD.BY~DATE~~
Technical Report TR-5364-2 Revision 0 4-137 SAP2SAP VER'iGAT;CN 5+64 UN2 YE'REO SQ'O 400F 0-600~S TiNE/F RCE TAB E 4.f1AGNiTUOE AT NCOE 0:NT 326 1 I I I I O o~UJ Oem~v)T IME~6G CV'tl)05 I l~C V)I BY/0>+DATE d Z.>3 CHKD.BY~DATE~~~~~
4 4-138 Technical Report TR-5364-2 Revision 0 MT.==nvqiE ENG;NEER;Ng C-JJN-83 SERV.,"ES SAP2SKP.VERiF;CAT QN JN2 YEL RED SQi io 400F 0 oGvMS TIRE/FORCE TABLE 5 N4,0NITJDE A~NODE POINT PnI U R)T I HE BY/V~+DATE 6-l'BZ'HKD.BY~DATE~~
Technical Report TR-5364-2 Revision 0 4-139 Sr>'V;Cc~2SA."'VER.,:"ATiQH 5364 UH2 YEL-RED SŽiD~ppF'-6pp~S TINE/FORCE TAB'6.NAQH:rUD Ay HDE.O.HT h I o<~l G.o I lA>0~i 0'6 0.ga T I HE I 0.P)Bv A'P oA"E y.z g~CHKO.BY~OATE~~~
4-140 Technical Report TR-5364-2 Revision 0~TE'DvNE ESV.:CES 6-JUN-8i SAP2SAP.VER i:=.CIT i QN 536-'N2 YEL-RED'Q~!0
".OOF 0-.600MS TIME/FORCE
!AB'T MAGNiTUDE CT NODE PQ!NT h~I V)s I I I T I ME 0~Ql BY P/I+DATE 6.c'3 CHKD.BY~DATE g~
Technics 1 Report TR-5364-2.Revision 0 4-141~i>v QE=VC;,NEERIVG S 6-JJN-8a" SAP2SAP VERI~;"AT:ON 5364 UN2 YEL-RED SQ ID 400F 0-600'.S TIME/FORCE TABLE 8.MAGNITUDE AT NODE PO.VTLCi Ci~L'I TiME 0~5i BY/Vl+DATE 4<>3 CHKD.BV~DATE~~X Technical Report TR-5364-2.Revision 0 4-142 Tc, EDEN ENGiNEER.gG SERV."ES 6-JJN-gg AP2S i'P'ER: v-CAT;ON iJN2 YEi-RED SOL,iD 400F 0-6008S T;.1E/FORCE TABLE 9."1AGNi UDE A.NODE POINT 310 O O hLLi Oca O~0 0~i 0'6 0~4 T I NE 0~Sl 0'0 ev Pli2 oAvc s-z.az CHKD.BY~DATE~~~
Technical Report.TR-5364-2 4-143 Revision 0~TEI EDYNE-ICiNEER 9<S 6-JUN-Si SAP2SAP VER l F l CAT i QN 5364 UN2 YEL-RED SQL i 0 400F 0-6008S T INE!FORCE TABLE l 0~MAGN!TUDE AT NQOE PQiNT"'08 T I NE 0~5)CD 60 W~~&~&BY AiC OATZ S-Z-S~CHKD.BY~BATE~
Technical Report TR-5364-2 Revision 0 4-144 0"M="V5.'NEER:VQ 6-O'JN-Qg RY;~E SAP2SAP VERlF."AT;gq UN2 YEL-RED SQLi.D 40QF 0-600NS TiNE/FORCE TAB" E ll NAGNiTDE AT NQOE POINT 298<3 0 il 0'0 BY P1>+DATE~-z.8>CHKD.BY~DATE~
Technical Report TR-5364-2 Revision 0 4-145 TE, DvNc ENG i NEER;NG SER'(.",ES 6-JUN-63 SAP2SAP VERiF.CATiON 5i64 UN2 YEL-RED SOLiD 400F 0-600MS TiME/FORCE TABLE l2, MAGN!TUDE AT NODE POiNT 290 Cl o O CQ CT;Al 0'9 C.17 0'6 0 F 34 TiNE O't)~J I BY P/~+DATE E-z 83 CHKD.BY~DATE~~~~
Technical Report TR-5364-2 Revision 0 4-146 EO=qb'E~R N G-=R;.-::,:S"-JUN-83'A~2SAP VER i P'T i Qg UN2 YEL-REO SQLiO~OOF 0-600MS TiME/FQRCE TAB=E i3.MAGNi~JOE AT NOOE PQ;NT 286 00 0~iT 0.26 0.34, TiME 0 F 60 By/V/Z2 DATE d-Z'83 CHKD.BY~DATE~~~>
Technical Report TR-5364-2 Revision 0 4-147 DYNE END:NEERiNG c Rq'-JdN-ag SAP2SAP VERiFiCA!iQN 5~64 UN2 YEi-RED SQLiO 400F 0-600l",S TiNE/FORCE TABi E i4 NAGNiTUDE AT NODE PQiN1 QJ O~4 cn 0'9 0~i TiHE 0 a%i BY/Vl+DATE 0-c'SZ CHKO.BY~OATE'g~
Technical Report TR-5364-2 Revision 0 4-148~Pc'.envy>E ENGiNEER:NG SER'Vj~ES 6-JUN-Bi SAP2SAP VER F;OAT;ON 5~64 UN2 YEL-RED SOLiD 400F 0-600NS TjNE/FOR E TABI E l5 NAGNjTUDE AT NODE POiNT g44 0~i?'26 0.34 0 0~60 CQÃI BY/9<+DATE 6-c'B~CHKD.BY~DATE~~~~
Technical Report TR-S364-2.
Revision 0 4-149'VPTE:-DYNE iNG:NEERiN-SERV';:CES 6-JUN-83 SAI-2SAP'ERi F'"g'QN 5364 VN2 YEL-REO SO iO~QQF Q-6QQi S TiNE/FORCE TABLE 16 NAGNi~UDE AT NODE PQiHT O Ch 0~i?0'6 0'4 T I NE BY/V~+OAYB 6-c-8+CHKD.BY~DATE~
Technical Report TR-5364-2 Revision 0 4-150~T"'OvN giqE~R'N(6-JUN-gg 4T.QN 5 UN2 YE'RED SQ'O 400F 0-600!1S TiÃE/FQRCE TABLE i?NAGN!TUDE AT HQOE?QiNT 28200 0~09 0~i7 0'6 0'4 I T iI1E o.si 0'0 BY p//2 DATE (p c'-83.CHKD.BY~DATE~
Technical Report TR-5364-2 Revision 0 4-151 EDYNE=NCiNEER:NC SERV,CE~6-JiJN-8i SAP2SA~gER;F;C~7 i Og UN2 YEL-RED SQ~iD 400F 0-600NS TiNE/FORCE TABLE 18, MAGNITUDE AT NQOE~OiNT 280 CD-~Al Oo~0 J~J v~4b T iNE 0~5i 0 6rBs/V//P oA7E>-z-sz CHKD.BY~DATE~
Technical Report TR-5364-2 Revision 0 4-152?p~t='L C D Y N E ENGiNEERiNC SERE;., ES 6-JUN-S~SAP2SA~VERl."tCA iGN:36~UN2,YEi-RED SQ<;0~00-0-600."lS TiKE/FORCE TAB': 9~NAGNiTUDE PAT NQDE PQ:NT 272 U'g C3 cr C L)O'~~~00 0 r6" c4 TiN=IJ~0.5i I 0'O BY/V~+DATE a c'-8>CHKO.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-153 SAP2SAP'ERi;"iCA iQN 5e6~UN2 YEI-RED SQ'O 400F 0-600 S TiÃE/FORCE TABLE 20~AGN!7'JDE AT NODE PQ NT 2620'6 T I NE 8>4~2 oAvc@-r-e CHKD.BY~DATE~0'0 Technical Report TR-6364-2 Revision 0 4-'I 54 7C", gvqg ENQ: 'uEE~<HG-=RV j~ES 6-J~JN-83 SAP2SAP VER..=;-CA:GN 5o64 UN2 YEL-RED SO': 400~0-600f'iS T!QE/FQQQE TABj E 2l.lAGN:TiJDE AT NODE.0!NT 257 A~C7 O Cj C)O-0 0 0 09 0'6 0'4 Ti:IE I 0 0 a%i BY/VI2 BATE 6-c'83 CHKO.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-155 Tc r lvNc=NCTREERINC 6-JJN-83".iv,~:ig SAPZSAP VER iF i COT i QN 5364 UN2 YEL-RED SQ:.-0 ALOOF 0-60GMS TIRE/FORCE TAB: E 22 MAGNITUDE AT'NODE PQ.NT 0 09 0;i 7 0.26 0.34 TiliE 0~0'1 BY 4<2 DATE (p-c'8g CHKO.BY~Q OATE g~
Technical Report TR-5364-2 Revision 0 4-156~-'D"NE"NGi HE Ri qG SER g I CES 6-JUN-83 SAP2S~P VERi=icATION 536'N2 YEL-RED SQi iD 400F 0-600NS TINE/FORCE TABLE 23.MAGNiTUDE AT NODE POiNT 248 LL.O O Q C)0~il 0 26 0 34 T I[ATE 0'I 0'0 sv 4~2 Dv<E S-z.e CHKO.BY jQg OATE~~~~
Technical Report TR-5364-2 Revision 0 4-157 gPTE~"OYNE lGiNEERiNQ SERyiC-S 6-JUN-83 SAP2SAP VER i F I CAT I ON 5i6~UN2 YEL-REO SOLiO 400F 0-600NS TiNE/FORCE TABLE 24.NAQNiTUOE AT NGOE PQiNT AI C3 CY CI~o i C 0~1,7 0 26 0.34 T I ME.4Q 0~51BY A~+DATE Ei i'.83 CHKO.BY~DATE g~
Technical Report TR-5364-2 Revision 0 4-158"PPTEi EO" NE ENGiNEERiNG SERViCES 6-JUN-S3 SAP2SAP VER I r i CAT i QN 5a64 UN2 vEL RED SOLIO 400F 0 600t1S TINE/FORCE TA8LE 25'AGNITUDE AT NODE POINT 244 CJl EQ CD C3~0 0 26 0.34 TIME 0'0 BY/9>+DATE d-Z.8~CHKD.BY~DATE~~~~
Techni ca 1 Report TR-5364-2 Revision 0, 4-159 PPTEi EDvNE ENG NEERlNGERViCES SAP2SAP VERiFiCATION 5364 6-JUN-SV UN2.YEL-RED SOLiD 400F 0-600NS TiNE/FORCE TABLE 26.MAGNITUDE AT NODE PO NT 242~00 0,09 0~I.0'6 T..QE 3 4 I 0~Si I 0 F 60 I YID CO~t CL C)4 CO BY/Vl2 DATE 5 Z'.8Z CHKD.BY~DATE~
Technical Report-TR-5364-2 Revision 0 4-160 gPT EL iD Y NE ERG NEERiRG SFRViC"S 6-JUN-83 SAP2SAP VERi.-iCATION 5364 UN2 YEL-RED SQL i D 400F 0-600NS TiNE/FORCE TABLE 27, MAGNITUDE AT NODE PQiNT U'C3 C)0~0 0~iT 0.26 0.34 T 1 i'lE 0'i BY/ViP OATE 6.Z.8~CHKO.BY~OAYE~~~
Technical Report TR-5364-2 Revision 0 4-161'PPTELEO".NE lNEERiNG 6-JUN-8g SAP2SAP VERIFiCATION 5364 UN2 YEL-REO SQL"0 400F 0-600NS Tit1E/FORCE TAB'28.t1AGNITUOE AT NOOE PQ;NT 236 hJ CV~co C3 CY C)U O 0~i7 0.26 0 34 TINE 0 F 51 0'0 BY pl/+DA7E 6-c'Q CHKO.BY~OATE~~i>
Technical Report TR-5364-2 Revision 0 4-162 PPTELEDvNE ENGINEER'NC SERV 6-JUN-83 SAP2SAP VERIFICATION 5364 UN 2 YEL-RED SOLID 400F 0-600NS T I flE/FORCE TABLE 29.NAGNI TUDE AT NODE PQ I NT ED~A CQ 0~17 TINE 0 26 0.34 0 43 0~5j 0'0 BY/9~2 DATE e-c~B~, CHKD.BY~DATE~
~,
Technical Report TR-5364-2 Revision 0 4-163~TELEO~NE ENGINEER<NC SERVICES 6-JiJN-83 SAP2SAP YERi ICA.IQN 5364 UN2 YEL-REO SOLID 400F 0-6OOMS TIME/EQRCE TABLE 30.MAGlYiiTUOE A!NOOE PQiNT 226 F 00 0~'i 7 T I NF 0.26 0.34 AS!0'0 BY~/P DATE 6-c'83~CMKD.BY~DATE~
Technical Report TR-5364-2 Revision 0~E.1CiuEER:NC SERV,CES 6-JJN-83 SAP2SAP VERiFiCATiQN 5364 UN2 YEL-RED SOLiD 400F 0-600NS Tif1E/FORCE"TABLE 31.f1AGNiTUDE AT NODE POiNT 219Mcp~CF~<v)B 0 0'9 0~17 0.26 0-34 TI YiE 0'3 0-60 ,0'Ol YD DATE y-Z-Z CHKD.BY~DATB~
Technical Report TR-5364-2 Revision 0 4-165 PPTELED"NE ENGiNEER!NG SEPV ACES 6-JUN-Qg SAP2SAP V RiFiCATiQN 5364 UN2 YEL-RED SQ'O 400F 0-600NS TINE/FORCE TABLE c2 NAGNiTUDE AT NODE PQiNT Ca<V C)lX a U Cl)I 0 I 7 0~6 0~3 0 5)BY P/~+DATE 6-c'.8g CHKD.BY~DATE~
Technical Report TR-S364-2 Revision 0 4-166"IGTNce.R<NC gc,qg,CCS 6-JUN-83 Sh SAP VERi IC4TIQN UN2 YEL-RED SO: iD~OOF 0-6OOI".S TINE/FORCE TABLE 33.HAGN.:UOE AT NODE PQ,NT 195~o V 0 C)F 00 0~9 0 0'0 BY/V~V DATE 6-c'~CHKD.BY~DATE g~
Technical Report TR-5364-2 Revision.0 4-167 PPTELEO~NE ENGiREERiRG
~ERyi"ES 6-JUN-83 SAP2SAP VERIFICA!IQN 5c64 UN2 YEi-REO SQLiO 400F 0-600~S TINE/FORCE TABLE 34.RAGNiTUOE AT NQOE PQINT CD CO CD h00 0 i 26~60 O 0 C3 BY/Vl+DATE 6-c~Bg CHKD.BY~DATE~
Technical Report TR-5364-2 4-168~!ELEOYNE ENG NE R;NG S=RV;CES 6-JUN-83 SAP2SAP VERiFiCATiQN 5364 UN2-YEi-REO SQI iO 400F 0-600MS TiNE/.QRCE TABLE, 35.NAGNiTUOE AT NOOE POINT i84 0 F 00 TiÃE 0'6 0'0 C3')CV BY~/2 DATE di-r'-~CHKD.BY~DATE~~
Technical Report TR-5364-2 4-169T~~D"NE ENjTNEER;NG SERViCES 6-JUN-S3 SAP2SAP VERiF.CA!.ON 5364 UN2 YEL-RED SQ'O 400F 0-600NS TiflE/FORCE TABLE 36.NAGNiTUDE AT NODE POiNT i82.09'V~.i7 0'T I NE/0 51 BY/VIP DATE 6-c'.Bg CHKD.BY~DATE~
Technical Report TR-5364-2 Revision 0 4-170 PPT:i EO.NE EuGiNEERiNG SERYiC 6-JUN-83.SAP2SAP YER IF i CAT i QN 5364 UN2 YE'RED SOLiD 40OF 0-600MS TiNE/FORCE TABLE 37.MAGNiTUDE AT NODE POiNT i80 w~O Q C)F 00-09~l 7 I 0~TiNE 0'l 0'0 C'~I W~BY/@~2 BATB>-Z-a~CBKD~BY~BATE~
Technical Report TR-5364-2 Revision 0 4-1 71 ENG i NEER i NG SERY i CES TY TELEDYNE, 6-JUN-83 SAP2SAP VER i F i CAT i ON 536<VN2 YEL-RED SQL i 0 400F, 0-600f1S TiNE!, ORCE TABLE 38.NAGNi T JDE AT NODE POi NT~00~09 0 I T 0~26~0~TiME~dQ 0~BY/0/2 OAjB 0 c Bg CHKO.BY~OA7$~
Technical Report TR-5364-2 Revision 0 4-172 LEDvNE"NGiNEERING SERVICES 6'-JUN-83 SAP2SAP VERIFICATIQN 5364 UN2 YEL-RED SQi ID ALOOF 0-6OQNS TINE/FQRCE TABi E, go, RAGNiTUDE AT NODE PQ;NT 98 O~Q C)O F 00 0 F 09 0-i IE 0~.l 0'0~l I~I I I I BY/Vl+DATE d Z.8+CHKD.BY kg DATE~
Technica 1 Repor t TR-5.364-Z Revision 0 4-173 PP'T E':0" N E ENG!NEER;NG SERViCES 6-JJN-83 SAP2SAP VER(FiCAT'01 5364 UN2 YEL-REO SQi iO 400F 0-6008S Tif"E/FORCE TAB'40.NAGNiTUOE AT NODE POiNT CtC o At LLi~C3 Ct C)'4*OO~J I 7~34~S~60 BY~/2 DATE 6 c'B~-CHkD.BY~DATE~~
Technical Report TR-5364>>2 Revision 0 4-174~TE'OYNE ENGiNEERiNG SERViCES 6-JUN-83 SAP2'SAP VERi.=iCATiON 5364 UN2 YEL-REO SQiO 400F 0-600MS TifRE/FORCE TABLE 4l.f1AGNiTUOE AT NOOE PoiNT ,CD CL C)F 00 0~5I DATE 6-c'8g CMKD.BY~DATE~
,
Technical Report TR-5364-2 Revision 0 4-1 7S ENG i NEER I NG S""RV i CES PPT EL Dv NE 6-JUN-83 SAP2SAP VER I F i CAT i QN 5364 UN2 YEL-RED SOL!0'00F 0-6008S T i NE/FGRCE TABLE~2.IAGN;TUDE AT NODE PO i N T D t'ai 0 a U 0~i~60~P DATE 5-Z'~DHKD.BY~DATE~~
Technical Report TR-5364-2 Revision 0 4-176 gPTc.Lc.DvNE ENG!NEERING SERVICE 6-JUN-83 SAP2SAP VERI.-"ICATIQN 5364 UN2 YEL-RED SQL!0 400F 0-600NS TINE/."QRCE TABLE 43.~MAGNITUDE AT NODE PQiNT CA 40 (D CV 00 0'9 I 0~5 O CJ)Al IBY/4+DA)E 0-z'.B~CHKO.BY kg OATE~
Technical Report TR-5364-2 Revision<3 4-177%'T~'"O" NE"NGiN ERiNG SER:g,C=S.6-JUN-8g SAP2SAP VERjFiCATjgN UN2 YEL-REO SO'O 400F 0-600NS TINE/FORCE TABLE 44.NAGHiTUOE AT'NOOE~QiNT 82 O Q~Q U 0 F 00 0~6 I D.34 TI 0'0 BY Pl>+DATE d.i'8>CHKD.BY~DATE~
Technical Report TR-5364-2 Revision 0 4-178 PPTEi EOCENE!VG.NEER!NG
$EPy=C 6-JUN-83 SQP2$Ap yER i c'-.r q, UN2 YEL-RED SQLiQ 400F 0-600MS Ti."lE/FORCE TABLE 45.NAGNiTJQE AT NODE POiNT C3 Q C)'o~oo 0~iT Q.60 BY/VIP DATE a,-i'.8g'CHKO.BY~OATE~~~~
Technical Report TR-5364-2 Revision 0 4-179 PPTELED"NE.
ENGiNEERiNG SERViC 6-JtlN-83 SAP2SAP VER I F i CAT i ON 5364 UN2 YEL-REO SOLiD 40GF 0-600MS Ti ME/FORCE TABLE 46~MAGNiTUOE AT NODE POiNT 78 W~'i fD I hi~C3 U F 00 0'9 i ME 0~Sl 0'0 BY/V~+DAiE 6.c'-8g CHKD.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-180~TEl EOCENE c.AGiNEiRiNG SERV;CES 6-JUN-83 SAP2SAP YER IF I CAT I QN 5364 UN2 YEL-REO SQ'i IO<OOF 0-600NS TIMBRE/FORCE TABi E 47.>AGNiTdOE AT NODE PQiNT hi)~I i I CD ag I/)CD 9-00 I EL C)~CD 0 F 09 T I NE 0~BY/VI2 DATE 5-/.8g"CHKD.BY~DATE/
Technical Report TR-5364-2 Revision 0 4-181 TEL.D,NE ENGiNE"RiNG S<RViC S 6-JUN-83 SA~2S4~VERi~CATiON UN2 Y=-REO SOi!0 400~0-600f"iS Tif1E/FORCE TABLE 48 NAGNiTUDE AT NODE PQiNT C'I Qadi~26 0~T I l1E 0~5 BY P/12 DATE g-Z 8>CHKO.BY~GATE~~~
Technical Report TR-5364-2 Revision 0 4-182~TEf EDYNE ENG I t<EER f NG$-R>/f-CES 6-JJN-S3 SAP2 SAP Lt ER I F I CAT f QN S364 VN2 YEL-RED SOLiD 400F 0-600f1$T I NE/FORCE TABLE 49.HAGNi, UDE AT NODE PQ'NT l4S O LLi~C3 O Lr F 00 F 09 0'4 E 5 I 0'0 BY/Vl+DATE 0-c'g CHKD.BY~DATE~
yechn>ca1 Report TR-5364-2 Revision'4-183 4gpT Ei wr1YQE ENGiNEERi>G 6-JUN-ag SAP2SAP VER<F<CAT I QN~364 UN2 YEL-RED SOLi D 400~0-600t.S TiÃE/FORCE TABLE 50.MAGNiTUOE AT NOOE POINT~I C3 0 CI lc F 00~I 7 Oi"6 0~60~&BY/VI2 DATE 6-c.S~, CHKO.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-184~TE'D"~~ENGiNEERiNG"ERV;CES 6-JUN-83 SAP2SAP VER i F i CAT i ON 5364 UN2 YEL-RED SOLiD 400F 0-600MS TIME/FORCF TABLE 51.MAGNiTUDE AT NODE POiNT h O F 00 D d P4 0~1 BY A>+DATE d z'-80 CHKO.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-185"NGiNEc.R!NG SERVICES 6-JUN-R3 SAP2SAP VERIFI CAT;QN 5364 UN2 YEL-RED SQL I 0~OOF 0-600NS TINE!FORCE TABLE 52 f1AGNITUDE AT NODE POINT o F 00~9 0~i~26 O.r34 TI U BY/VIP OATE dr-c-8g CHKO.BY~DATE~~
,
Technical Report TR-5364-2 4-186~TE gYNE ENCiNEERiNC SERV;CES 6-JUN-83 SAP2SAP YERi~iCATiQN 5364 UN2 YEL-REO SQLiO 40QF 0-600MS T1ME/FORCE TABLE 53 MAGNi TUOE AT NQOE PQiNT CU QJ W C3 0 C)F 00 0~0~26 0-S BY+/2 DATE 4-c'8>CHKD.BY~DATE~~~
4-187 Technical Report TR-5364-2 Revision 0~TELEDYNE"" ENGiNEER.HG S~RViC'-JUN-S3 SA.2SAP VER iFi CAT i ON 5364 UN2 YEL-RED SOI i0 40QF 0-600fiS TiflE/FORCE TABLE 54.NAGNiTUDE'T NQOE POiNT 132 CTY o P7-00 0~i 0'6~Si~60 0: I BY/9/2 DATE g-c'-B~CHKD.BY~DATE~
Technical Repot t TR-5364-2 Revision 0 4-188 E N 0 j N c.E R i!V G S" 9 V j C.-S 6-JUN-83 SAP2SAP Lr'ERjFiCATiON 5364 UN2 YEL-RED SOLio 400F 0-oOQt1S TINE/FORCE TABLE 55.MAGNjTUDE AT.NODE POiNT QJ CYY C3 C3 U 00 0 0~~26 0~5liV BY/9/2 DATE 6-c'9~CHKD.BY~DATE~~~
Technical Report TR-5364-2 ,Revision 0 4-189 TELEDYNE ENGiNEERiNG
<<RVjCES 6-JUN-83 SAP2SAP VERiFiCATiON 5364 UN2 YEL-RED SOLiD 400F 0-600MS TiME/FORCE TABLE 56.MAGNiTUDE AT NODE POiNT 12S iV lO h~OJ~lO CL o Ol 0'6 0~0'0 BY/ViC DATE (y"c'8g CHKD.BY~DATE~
TecHnical Report R-5364-2 evlsion 0 4-190 PPTEi EDYNE ENGiNEERiNG SERV CES 6-JUN-83 SAP2SAP VERiFiCATION 5364 UN2 YEL-RED SQi i0 400F 0-600MS TIME/FORCE TABLE: 57 MAGNiTUDE AT NODE POiNT 60 F 00 0~i7 0~4 P.d 0~0~60 BY PII2 DATE 0 Z 83 CHKO.BY~OATE g~
Technical RePor t TR-5364-2 4-191 TELEDYNE ENGiNEERiNG SERViCES 6-JUN-83 SAP2SAP VERiFiCATiON 5364 Uf<2 YEL-RED SOLi0 400F 0-600NS Tif1E/FORCE TABLE 58.MAGNiTUDE AT NCDE POiNTF 00 0~i7 0~34 0'3 0 BY/Vl2 DATE d-2'8g=CHKD.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-192~E':OYNE ENGiNEERiNG SERViCES 6-JUN-83 SAP2SA: VERi."iCATiQN
~364 UN2 YEL-REP SQLiD 400F 0-600f"S Ti5E/FQRCE TA9i E 59, 5AGNj..UPE AT NQPE PQiNT 48 o<h F 00 0'9 ORBIT T I NE 0 26 0 34 0'3 0'0CO CD CO BY/V~V DATE 4-c-83 CHKD.BY~DATE~~~~
Technical Report R 5364-2 ev>sion 0 4-1 93~TEY EO"~<E.ENGiNEER;VG SERViCES 6-JUN"GD SAP2SAP VERiF;CATiQN 5364 UN2 YEL-.REO SQ iD 400F 0-600MS Tif1E/FORCE TAB E 60.NAGNiTUDE AT NODE PQiVT F 00?0'6 E 0'4 0~Si 0 F 60 tA~l 0 CI W C)BY/9/P-BATE g-c.>~CHKO.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-I 94 TELEQY>l-=
6-JUN-83 SAP2SAP'lJ'ERjFjpb,TjQN 5Q6Q UN2 YEL-RED SQL'0 400c 0 60QNS Tit1E/FORCE TABLE 61.NAGViTUDE AT NODE: GENT 0'9 0'6 0.a3 0 5i BY (I/8 DATE g-1 8g CHKO.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-195=GYVE=8=;NE;-8;NC
."-JUN-83 SERV!CES SAP2SAP VERi."tCATiQN 5364 UN2 YEL-RED SQLiD 400F 0-600~iS Ti>EfFORCE TABLE 62 RAGNiT'AT NODE POiNT 0'9 0'6 NE 0+4 0~-'.3 0.S)~CI O CY Qe O BY/Pl+DATE 6-Z-B~CHKD~BY~DATE~
Technical Report TR-5364-2.Revision 0 4-196~~E EOCENE:NCiNEER!N" SFRVICES 6-JUN-83 SAP2SAP YERiFiCATiON i364 UN2 YEL-RED SOi iD 400F 0-600NS TiÃE/FORCE TAB!E 63 NACNiTUDE AT NODE POiNT O cDC4 C3 Q D F 00 F 09 Go w 7.B4P"I 0~51 BY/9/2 DATE 6-Z'd3~CHKD.BY~DATE~~~
Technical Report TR-5364-2 Revision 0 4-197~TE: EDYNE ENC,NEERiSC SERVICES 6-JUN-83 SAP2SAP VERIFiCATIQN 5364 UN2 YEt-RED SOi iD 400F 0-600MS TiME/FORCE TABLE 64.NAGHi~UD AT NODE POiNT O~09 0~F 60 Technical Report TR-6364-2 Revision 0 4-198 PPTEi EDYNE ENGiNEER;NG SERViCES 6-JUN-83 SAP2SAP VERiFiCA!.ON 5364 UN2 YEL-RED SOLiD 40GF 0-600f1S TiÃE/F RCE TABLE 65.NAGNiTUDE AT'QOE PO.NT~W O ,~I 7 0~2,6 o'.~Q o~s E F 60 Technical Report TR-5364-2 Revision 0 4-199~~E EDYNc.ENGiNEERiNG SzPq'C=z 6-JUN-ag SAP2SAP VERiFlCA<iON 5364 UN2 YEL-PED SQL!0 400F 0-600HS TIME/FORCE.TABLE 66'AGNiTUDE AT NGOE POiNT~io Q.C)CO 0'9 0 I 7 I ME 2 34 0'3~60o I BY/Vi'+DAYE 0-Z-8g CHKD.BY~DATE~
Technical Report TR-5364-2 Revision 0 4-200~TELEOYNE ENG;.flEERiNG SEqy;CES 6-JUICE-83 SAP2SAP yER i F i CAT i QN 5364 UN2 YEL-.REO SQLiO 4QOF 0-600HS TihE/FQRCE TABLE 6?.MAGNiTUOE AT NQOE POiNT 0'TiNE 0'4 0..1 F 60 o<BY A~+DATE Ei z.B>CHKD.BY~OATE~
Technical Report TR-5364-2 Revision 0 4-201 A TELEDYNE ENGINEERING SERVICES 4.8.2 uarter Model-Cold Loo Seal/Steam Case Technical Report 4-202 A TELEDYNE ENGINEERING SERVICES BY~~~DATE+/<CHKD.BY~DATE~un'WeCrrr S~ooos (zzF)z,JHsy: EO<V Vsc SHEET NO.OF PROJ.NO./F0/SCW/bO/t/p IISI/9 JI.o 2I cd'FD 5 21 S 2'F 24 f5 24~C PP'4'31+I FIGURE 4.8.2-1 0
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