ML17324B005

Rev 0 to Books 1-3 of Analysis of Pressurizer Safety/Relief Valves Discharge Piping Sys Per NUREG-0737,II.D.1,Unit 2.

ML17324B005
Person / Time
Site:	Cook
Issue date:	06/10/1986
From:	TELEDYNE ENGINEERING SERVICES
To:
Shared Package
ML17324B004	List: ML17324B003 ML17324B005 ML17334A990
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 UNION 2

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AMERICAN ELECTRIC POWER SERVICE CORPORATION 2 BROADWAY NEW YORK, NEW YORK 10004 P't". ~

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~j V 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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Revision 0 TABLE OF CONTENTS PAGE

1.0 INTRODUCTION

Book 1 of 10

2.0 CONCLUSION

S 2-1 3.0 SYSTEM DESCRIPTION/DISCUSSION 3-'1 4.0 THERMAL FLUIDS ANALYSIS 4-1 4.1 Introduction 4-1 4.2 RELAP Model 4-3 4.2.1 Pressurizer Conditions 4-3 4.2.2 Valve Modeling 4 4.2.3 Discharge Piping 4-11 4.2.4 quench Tank 4-11 4.3 RELAP Model Control Volumes 4-12 4' quarter Model 4-19 4.5 Unit 2 PORV Model 4-20 4.6 Valve Flow Rate Calculation 4-23 4.6.1 SV Flow Rate ~

4-24 4.6.2 PORV Flow Rate 4-25 4.7 RELAP Plots 4-28 4.7.1 Unit 2 - 400o Solid Liquid Case 4-29 4.7.2 quarter Model - Cold Loop Seal/Steam Case 4-113 4.8 Force Time History Plots 4-129 4.8.1 Unit 2 - 400o Solid Liquid Case 4-130 4.8.2 quarter Model - Cold Loop Seal/Steam Case 4-201 4.9 RELAP Input Book 2 of 10 4-229 4.9.1 PORV Solid 400o Liquid 4-230 4.9.2 PORV Solid 400o Liquid Restart 4-250

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Technical. Report )III E TR-5364-2 Revision 0 ENQINEERNQ SERVCES TABLE OF CONTENTS ontinue PAGE 4.10 REP I PE Input 4-260 4.10.1 Model Section A PORV Unit 2 4-261 4.10.2 Model Section B PORV Unit 2 4-271 4.10.3 quarter Model 4-278 4.11 APPENDIX A 4-286 5.0 STRUCTURAL ANALYSIS 5-1 5.1 Deadweight Analysis 5-2 5.2 Thermal Analysis 5-2 5.3 Seismic Analysis 5-2 5.4 Force/Time History Analysis 5-3 5.4.1 PORV Transient 5-3 5.4.2 SV Transient 5-4 6.0 ANALYTICAL RESULTS 6-1 6.1 Stress Summary 6-1 6.1.1 Equation A-1 Stresses 6-6 6.1.2, Equation A-2 Stresses 6-18 6.1.3 Equation B-1 Stresses 6-30 6.1.4 Equation B-2 Stresses 6-42 6.1.5 Equation B-3 Stresses 6-54 6.1.6 Equation C-1 Stresses 6-66 6.1.7 Equation C-2 Stresses 6-78 6.1.8 Equation C-3 Stresses 6-83 6.2 Support Loads 6-88 6.3 Valve Accelerations 6-125 6.3.1 DBE Seismic Valve Accelerations 6-126 6.3.2 PORV Transient Shock and SV Transient 6-130 Shock Valve Accelerations 6.4 Nozzle Loads 6-134 6.5 Valve Loads 6-140 6.6 Miscellaneous Calculations 6-146 6.6.1 Thermal Boundary Displacements 6-147 6.6.2 OBE Spectra 6-153 6.6.3 DBE Spectra '-160 7.0 DRAWINGS 7-1

8.0 REFERENCES

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A TELEDYNE ENGlNEERING SERVCES Technical Report TR-5364-2 Revision 0 TABLE OF CMfENTS Continued 9.0 COMPUTER ANALYSIS 9.1 RELAP/REP IPE Input Book 3 of 10 9.2 Deadweight, Thermal Input/Output Book 4 of 10 9.3 OBE Seismic X-Y Input/Output Book 5 of 10 9.4 OBE Seismic Y-Z Input/Output Book 6 of 10 9.5 DBE Seismic X-Y Input/Output Book 7 of 10 9.6 DBE Seismic Y-Z Input/Output Book 8 of 10 9.7 PORV Transient Shock Input Book 9 of 10 9.8 SV Quarter Model Transient Shock Input Book 10 of 10

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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.

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P. D. Harrison (TES) dated March 15, 1983 (References 2 and 3).

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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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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

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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.

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-r> TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2 Revision 0 2-2 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 ri TELEDYNE TR-5364-2 ENGINEERING SERVICES Revision 0 3-1 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.

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"Safety Valve Discharge" results, is limited to draining the SV loop seals.

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Heating the loop seals is not a viable "fix" because of the size of the loops.

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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.

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A TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2 Revision 0 4-1 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

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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 -ri-TELEDYNE TR-5364-2 ENGINEERING SERVICES Revision 0 4-2 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.

.-r> TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2 4

Revision 0 4 3 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 2 745 o e2750 27 F 7 2750 742 2700 .o 2700

'667 650 Pressure (psr) 2600 2600 2550 o'2555 o 2514 1.0 2500 0.5 Time (Sec)

The safety valve pressure boundary conditions were used in analyzing the quarter model cold loop seal case.

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Revision 0 4-4 PORV Pressure Time History (in the pressurizer) 2550 2500 Pressure 2450 (PSI) 2400 0 2350 0.8 2300 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:

Manufacturer Orifice Area 0 enin Time SV Crosby 0.022 Ft2 0.010 Sec.

HB-BP-86 (Ref. 13)

PORV Masoneilan 0.00806 Ft2 1.0 Sec.

NO-38-20721 (Ref. 14)

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r~ TELEOYNE Technical Report ENGlNEERINQ SERVtCES TR-5364-2 Revision 0 4-11 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 SCH 40 4 inch, 6 inch SCH 40S 4 inch SCH 120 3 inch, 6 inch 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

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defined in segments of straight sections from; elbow to elbow, valve to elbow,

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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 A TELEDYNE TR-5364-2'evision 4-12 ENGINEERING SERVICES 0

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.

Average control volume lengths used for the D.C. Cook RELAP Unit 2 model were:

~Pi e Size Avera e C.V. Len th 3 inch SCH 160 0.5264 feet 6 inch SCH 160 0.5019 feet 4 inch SCH 40S 0.5056 feet 6 inch SCH 40S 0.8871 feet 12 inch SCH 40 0.8526 feet 3 inch SCH 40 0.4744 feet 4 inch SCH 120 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.

~

~

r>-TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2

~ ~

Revision 0 4-13 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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A TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2 Revision 0 4-19 4--.4 M d 9 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 141o Upstream 0.010 115,000 Cold 141o Downstream 0.010 174,000 Hot 350o Upstream 0.010 156,000 Hot 350o Upstream 0.090 109,000 Hot 350o Upstream 0.130 124,000 Hot (Sat. 650o Upstream 0.090 38,000 Water)

Steam 650o Upstream 0. 010 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.

~

rE TELEYNE Technical Report ENGINEERING SERVICES TR-5364-2 Revision 0 4-20 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.

A TELEDYNE Technical Report ENGINEERINQ SERVICES TR-5364-2 4-21 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 Cont. Vol. Reference 50001 41021 RELAP RUN BHFRBGO UNIT 2 400-600 msec Solid Case Flow Junction Cont. Vol. Cont. Vol. Cont. Vol. Cont. Vol.

8415 Mass F41021 f41021 850001 550001 Flow Thermodynamic Pressure Pressure Thermodynamic LBM/Sec. PSI PSI) ualit

.407 105.9 0.0 2160.9 248.15 .0088

.408 106.4 0.0 2169.2 248.50 .0088

.409 83.6 0.0 2996.7 247.73 .0089 It can that the downstream pressure does not exhibit a sudden t

be seen increase that would reduce the flow through the valve. The upstream quality remains zero indicating that the flow through the valve is subcooled.

-ii-TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2

~

Revision

~

0 4-22 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.

. A TELEDYNE ENGINEERING SERVICES Techni cal Report TR-5364-2 Revision 0 4-23 4.6 Valve Flow Rate Calculation The following values were used in valve modeling considerations:

TES Flow Max Rating*

Rate Calculated For Steam Bore Area Opening Valve T e LBM/HR ie 3X Acccm. ~IN2 Time (Sec)

Crosb 523,332 435,000 3 6 in 2 0 010 a ety Relief (Ref. 18)

Val ve Masoneilan 199,000 1.0 p

Relief Valve

• 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).

]E TELEDYNE Technical Report TR-5634-2 ENGINEERING SERVICES Revision 0 4-24 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.

WT = 51;5 AP Napier's Eq.

ASME rated flow:

WR = 51.5A (1.03P + 14.7)(.9)(.975)C (Ref. 17) where:

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)

This is an increase of 15K above the ASME rated flow as explained above.

-rs-TELEDYNE ENGINEERING SERVICES Techni cal Report TR-5364-2 Revision 0 4-25 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.

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-ri TELEOYNE Technical Report ENGINEERING SERVICES TR-5364-2 Revision 0 4-28 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 400o Solid Liquid Case 4.7.2 . quarter Nodel Cold Loop Seal/Steam Case A RELAP volume schematic precedes each plot set.

4-29 (l TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2 Revision 0 I

4.7.1 Unit 2 400o Solid Li uid Case

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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 ) ~ ~O CC 0 O O.oo(31 Q 0 'kQ~ D

0. 14, 0.14 OA) 0. 1S TltK lSECl 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) CD o o RELAPS/NlOl/014 REACTOR LOSS OF CmlLFNT ANN.'fSIS PROGRAM m. m M I -l lD Kl fD I 0 O.H 0. 4b 0.52 0.55 0.00 O.M Tlt1E lSECI 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 lD WA) I 0 Ul 3 re 0 AO I Ol o C) fD ~ g)gg(9 () '/CO~CO O o s D O.M 0.!4 0.2< 0. 1I 0.44 T]K (SECI RFLAPS/t$ 01/014 REACTOR LOSS OF COOLFNT ANR.'!SlS PROGRAM (A D Ul O.WAI f1'O O.Q 0.4$ 0.'Q 0.55 O.M O.H Tlirt lSECl C7 RLl.nlS/IQDl/Old RLACTM l.OSS OF'OOt.BIT AHR.YSIS PROGRAtl ACP UNIT2 l L]NE RQBPS 83/05/20. This is the quality upstream of the discharge valves dur ing the subcooled discharge case; there-C3 Oe fore, the quality is zero. 8 ci'4 C) Vl < ci o O.G Q ~ +0 aeq O.a 0. II 0. 24 0.& 0. 40 TlHC tSCCl ID O O RELAPS/%$ 1/014 fKRCTOR LOSS Of COOL%IT NR TS15 f'ROQRAH I C) This is the quality upstream of the the di schar ge val ves dur ing there-O O IO subcooled discharge case; fore, the quality is zero. Vl KO %7MW ~ O ID o Vl + III ~. CA ~. ownIII I d D. 40 0. 44 0.48 0. Ll 0.00 0. SE TitlC (SCCl 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. 0.0 Q O.+Q 4eC 0.15 0. 24 0AO D. 40 TIN ISCCl C3 III'IIIIL 7C IW, IRl RD.APSltSD) IDl fKACTDR LDSS Of'M.AT f$8.'ISIS PROGRAM ~l o This is the quality upstream of l3 the discharge valves during the subcooled discharge case; there-O sO 'i8 CI for e, the quality is zero. Ql Q v ~0 CL a XJ CD X) l~ CD o VI CJI M Ch ~. CD wo C) I PV ~ ID o O < < Q 0.40Q M( 5 0.44 0. 44 O.SR 0.$ 0 O.M EKE (sec) iua aalu m.mca na menu,'isa ~, 6iciicfah~ihisinkaPia C7 m RLI.AI'S/tf)OI/014 fKACTOR l.055 OF'OOI.SIT SA.'ISIS PRODRAII 4 AEP UNIT2 1 I.INI: RLIBP5 S3/05/20. '.0 of This is the quality upstream the A O ao the discharge valves during there-8A subcooled discharge case; FV Ql fore, the quality is zero. tA jw KA ~ fD ~~ O nM ~'Jl l/l o Chwo~i IV A C) tV ~ gp fb O A oo Q c3.'/oo ~t'. A

0. 00 0.04 0. I 4 0. 2i O.M 0.40 O.m TlHE I SECI

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 This is the quality upstream of Cl the discharge valves during the 8 ci subcooled dischar ge case; there-fore, the quality is zero. N Vl $ v CL' 8 o.o Q c,.m ~c( D.

0. 00 0.04 0.14 Ill 0.2(

fSECJ 0.% 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 0.50 O.H TltK tSECl CD hall ate )R 4.J IRR 4 W, ISR) %4tWA ~ WVCRNCCII IRWIIIRI 0) CD RCl.ll/S/ISIOI/Old IKRCTOR LOSS Of'INI IN.P~RWil SI.S PROCRRII m AEP owl T2 1 I.lWC REIBP5 03ia5120. () Cb IJU IA ) t'L ci O )0 Kl ID I 0 ~~VIV I/I O WO I ~. IOQ 5o CD 0) n O s

0. 00 L ll O. la 0.2( O.M 0.40 0.<e TlwE lSEcl

C7 aoi res sama MTi a5, ~ D C7 RELAPS/t%DI/Old fKACTOR LOSS OF CE)LNI'NR.YSIS PRODRAH 2 m D D O ~ ~ Ul K O . Ip x. Ql~zsk~t 0.+ 0.5l 0.60 Tlat% tSECl 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 I t C) og Ho I 0) tg ~O 0 lD X) lD I 0 Ul K Vl 0 WAI Ql 0.9301Kgco~c C) It0 'u Sm (9 g O I Q 0 0.00 0. OI O.te O.li 0. 3l 0.40 0. 1e s lg CD IlttE tSECt Pl IC I '0 t CD C7 aa ~arc~~6~%a. ikey~ O IO REI.APS/NDI/0]0 REACTOR L055 OF'MI.AT FINFL'fS]S PROGRAII m m p ~ &C .) <<a O O 00 8ci 5) Ill ~ ci O . 07 /0~AD' d

0. 40 0. 4I O.R O.et T]HE ISECI

CD Ilail I~ ll sl II OE A &I, Ilail 44&IA4% i CIIIIICfSO'I 4 6ISOhkM Lf CD kt.'t.ft&/tMtl)t/014 fKAN'OR l.OSS 01'00t ftà ANiA~lSI VR06RAtt m AEP ttttlT2 1 LlttE RflIlVS 83/OS/20. ) 0 os ~<~ (1 III O Do 0 Cb I m ~iVlD0 VI O WOAl I CD C0 n O d rt

0. 00 O.M 0. IS 0. 2E 0.40 0.4S T]I1C tSECI

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'XXIC4 ~ 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 OA 8 ci m O l/l v ) < ci Q Ct O O. I 8 0.2L 0. 40 TINE ISECI >> 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 ~ KJ-I W ~ d 0g CD R7 CD 0 CJl D O O 0.44 0,4I 0. 51 0.50 T]ttL tSCCI C7 C7 kt:I.III"~IN)O)/0)4 REACTOR I.OSS Of'OOI fNT fINft.YSIS PROGRAM m ACR IlritT2 1 I.)NL RQ)IPS 03105120, I.o p c.~wc. N Ho R ig D0 0 Al X7 (D I 0 Vl K 'D GJ 0 WOI Ql C) lb O S

0. I I - 0.2E 0. Jl 0.40 0. 4b T)IIC ISCCI

D C 7l WF D D RELAPS/t$ 0l/Ol REACTOR LOSS OF COOLfM SA.TS 5 PRONAtl m m C) ee V O1 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. X7-0 W ( CD ~'01 n 3 0 wn C) PO ~ I Ql CD O S O I < pOVOO4~ OeQ 0.44 0.5l 0.54 0.4( TltK (SEC) fctt.Af'5/Nl0)/011 fCCACTOR l.OSS Gf COOt.FAT AN835IS PROGRAtt V ItL'P lttll12 l t.lttL RElRP5 83/05/20c Q) tg C3 O+ Ho' CO lA ) V +D O /0 W W CD X) CD I A EA CJ1 ~ 0 WO C) I FO ~ %7 CD nO 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 'n CD O d

0. 00 O.N 0.)e 0. 2E 0. 32 0.05 Tl& ISEC)

C7 hO %$ III.Q. SC ~ IW O CD RCLAPSINlOl/Ol4 REACTOR LOSS OF ClHLfNT Mi.YSIS PROGRAM m CI I4 con-This is the quality in the down-O trol volume immediately va1 ve. oa s tr earn of the saf e ty During this transient (which is a PORY transient) the safety valve remains closed; therefore, the quality in the control volume remains at 1.0. C0 Mm ~'Vl oD VI Ol ~. 04O CD I FO ~ CII CD O O I0 8 0 goo ye~ 0.44 LR 0.58 0. b4 Tlat% (SEC) 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 CD REl.fil i/tX'j01/Otl REACTOR l.OSS OF COOl.fNT AtiB.'FSIS F'ROGRAtl V tiEl'lttfT2 l L]t<E REINS 83/05/20. tz Co tV ()t 0) t.v LH 2.S2.. 9L p.Ct~ 4C-'C-8 ctt 8 Kl W W CD M 0) I 0 ~iVlD

a. 4D D Q 0 ~

EA Ao W Ct CD WA I Ql Z~ n Rm onS Q 0.15 0. RC 0. 3l 0.40 0.<a 0) TttlE lSEC) m C 0 (D O O P.2 Rl;l.RPS/t$ 01/014 FlF:RCTOR LOSS OF C001.Alt AN%.'YS IS PROGRAtl rn m Vi I (b (v ( Vl O3 (9 W I CD 0 W 0 0.4< O.Q O. 52 O.S4 ?tHE ISF:CI 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 V (a AEP fRJIT2 l f.lfJE HEI RPS 03/05/20. N tV Cb lg LH I CO Ul P4 LI g cv D D O. l4 '0.21 0.44 TltlE fSECI 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 ~ Ore hJ ~O Oa C3 CD MCD ~. I CJl 0~ Q CAB 0 AA CD I PJ ~ CD O O O.

0. l4 0. 24 0. Zl 0.40 0.04 TtttE ISECt C

0Pl 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 CI (n IIEP UhllT2 I LINE ftEIN'S II3/05/20. Cu bJ IH CD X) lD n Vl M EA 0 WO I Ql Z.>C 9.t C) CD (3 ~.'IOG Cc4C. O EV

0. t4 0. 24 0. 3l 0.40 0. 44 T]tIE ISECI

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 LN TIE IKC) 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~ gP x ~ I CD WCD I 0 >~ CJl 2 Cab N O WO I Al CO CD nO S C+ 0.00 0. IX a. Ia a.a 0. Xg 0.40 0.% T]IIL ISECI 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 C7 COOt.fNI'NB.'fSIS rn RCl.fiPS/N)DI/Old BI:ACIOR l.OSS Of PROGRBtl 4 HL'P ttttIT2 I t.lttE RElfiPS 83/OS/20. tJ Cb LH N >a ~Q

6. Q O rq ~~

ztv9 8 0Am seC

0. 00 0. l4 0.14 0. 11 TltK ISCCt

C7 m RELAPS/N30 /0]4 RERCTOR LOSS Of C93U%T ANB 'ISIS PROGRAH b0 y, pre zX fV X hIR 8 8 O o.e, 0.4I O.R O.N T]HE ISECI 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 Ill 0.24 (SCCI

0. Sl 0.%

RELfFS/NlOI/OI4 fKRCTOR L055 OF COOLfNT SA.'ISIS PHOGRA 0.4I 0.% 0.54 0.80 ZItK (SEC) hELRll'5/tlODI/DIN REACTOR l.OSS Of COOLFtlT RNR.YSIS PROGRFN flEP DNIT2 I LINE REIAPS 83/05/20. tr bJ (b \H 97.7 I Q o'I~~ I WCD I A Vl CJl M 0 WO1 CD lTI C0 o %m O Q O.N 0. II 0.25 0.4b Tlt1C ISfC) 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 O.H TlttC lSEC) 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( 0. 3R ?It)E lSEC) RELfFS/t$ 01/014 RERCTOR LOSS OF'93 l% AH%. Sf PROGRftl P7. +$CI~~ I &. $ /9 5w CD CD ohio Kl W W (~eUID CD ~A) I O GJ W ~o ~ ~, I CD ID D S O.CO O.Q TltK l SECl f tent'.I.fftl'5/I 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 CD ~ CD I 0 ~iVlD VI GO M Ae 0 WOI Ql CO CD O I ~g p gg+~ c7.+00 Oeti 0% 0.54 0-NO '.H TltK (SEC) 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 0.40 T1AC lSECl CU -C CD ll'D 'hie xa ia si<a wa rw, iw Xioesaco ~ aswfQKQ 68rvt ia 1 7 CD Ift.l.OI'S/IK)01/OIW 8:0(:TOfT I.OSS Of CNI.fWT fINfl.gS[S PHOGIIfIII C<1 I rll ('t C)" ~ ~ 1 X ( ~ PP do' CD I co I P1 Vl Eil 0

a. 1 PO CD co cj O

Q V) fll 0.4( 0.40 0.52 TIIIL ISFCI 4.54 0.60 o.a< (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. (p tV

0 0) w" IH I

CD Vl CD Kl CD CJl n M Vl 4) g Q 0 An I Z CD R7 C0 u O

0. 14 0. l4 0. bl 0. 44 TlnE tSECi

REI.APS/tSOI/014 REACTOR LOSS Of CN3LFNT AHA YSIS PROGRAM Ce Qb

3. 9I .S sec S>C-&5"

0. fI O.Q i

.i'cs'l T It% 0.5l '(SEC I 0.54 0.4( CD Vl W W Kl Cb 0 Ol CD A I CJl hD O ~ h I Cll A) O EV CD ~ IIIl X4"4 AO'W"5 rWI, IWl'4inWN. CNOIICt 1SCTZQSitUlCI U C) kLL.N'5/tSOI/OIN REACTOR 1.0SS Of'Mt.f%T fINR.YSIS PROCRRtl Pl V l tn RCP ttt<IT2 1 LINE HElBf'5 83/05/20. bJ 'I Q O ~r~O 3) LH ~t.58g g <.(CC ~C I CD 'V h HQ 8 Kl M W CD Rg >o I 0 Vl 3' CrJ D 0D WCl CD I PO ~ fD nO z Q

0. II 0.2t O.M 0. iO TlttE t5EC1 0m

C7 All ~~~, St%ttWlTT I L RELAPS/tSDl/014 fKACTOR LOSS OF COOLIE RNR.1SIS PR06RRti (i) I 9) (u D~ 4 I C) CO Ib S> 8 KIWW lD I 0 Ul ~ H. EA Ch ~. 0 W 0 4D I fO ~ K7 A) o O s O.Q 0. 44 0.$ 2 0. 64 Illa'SEC) Rfi.eanenl/Ole rrnCtOR LnSS nr Cpni.WT Wa.VSrS PROCRAn AEP UHIT2 I l.lNE RElBP5 03/05/20. o.fo53 0'IQ Q o.a 0.(4 0.14 0.M 0. 44 TlHE lSECI O O RQ.feSiND1/Old fKACTOR LOSS OF Cppt.FNT AN8.1Sts PROGRAM m rn (gi Ob (u srm I C) I Kl M0~ KJ W I lb Vl Vl O WO I QJ O P m O.Q O.Q O.SR 0.50 O.N tlVC (SCC) V) CD tlute 'ha@ rrt lt.tl tel A tRI, IICl gua r DSCMCf ~ I4 4l~~ CD Pl REI tilw/lSOl/OI4 REACTOR l.OSS OF COOl.RJT AJJl%.'ISlS PROGRAM CI 4 REP llNIT2 l I.llJE RElBP5 83/05/20. Po tV O) N gA ~r ~I Vt GJ CA 0 l CD ITl K7 CCt %m os O. II 0. 24 0. CB Tlt1E lSECI C3 RELAPS/tSO1/014 RERCTOR L055 Of CIILFNI'NR.ISIS PR06RAtl Pd. P .s ssc 5 O A Pl ~O 8 8 PS s~ 0.4< 0.4I 0.5l 0,60 TINE ISECl 4-113 A TELEDYNE Techni ca 1 Report ENGINEERINQ SERVICES TR-5364-2 ~ ~ Revision 0 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 DltcHgft.ce SHEET NO. Dp ) CHKD. BY ~DATE~ Ua'I 7 '2 PRO J. No. P 'Z ' &f'7 Cccxse y' 4'4 oo(o C ~g~W/Z E'e pWOp'o< our $ 0$ IO E ~dr~>o 5 ~ABDLVBE E EPEB 7 guE=ra d/C) ll/S ~///Q Ill'P II 27. /S2o II7 3 /93 < vCrW 0/+ . mOI'<~< glgf ~ <Ijr~5 lfgPf /ISf* IIS II I EfOp //oo TT~ /If fEP ~ 7DI FIGURE 4. 7. 2-1 RECAP RCLBPS/NNl/0 fKACTOR LO 5 Of CHION RHR.TS 1 S PROCRfN UN T2 L NE 3/ 2/05. CI ea a O o0 8o o o j= 0.0 0.2 O.i 'lit% ISEC) RELAPS/NS /0 RCA OR S PRO RAtl RE 5 83/ 2/05 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 IIIIICI I%i'L% RELAP5/t601/Ol fKA OR LO S OF'NLfNE fNR.YSlS PROQRfN AEP UNfT2 l INC RElfM'5 /02/05 bO 53 . 4 dOZ 5 5 C O 8 Gn n ill 0-O ~sV ~.ooVsa c 0.0 O.R 0.4 0. ~ TltK fSECI CD Kl ED I CJl hM Vl 0 A I Qf h C) P3 fD "o O RELAPS/f801/Old REACTOR LO 5 KC 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 O.i TltK tSCCI 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 O.i T1HE lSECl RCLAP5/NSl/01 fKACTOR LOSS 0f CI3LFN NA.'fS IS PROCRfN IKP UNfT2 L HE R if@ 83/ 2/05. Q~Q Q 0.0//5 C 0 o O d 0.0 O.l 4.4 O.e lit% (SEC) 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 I CJI CD 0 W EA lA D 0 W0 I PO C) CD a O C+ RLLm/mp ip C aCRerOR LOSS OF'tmrar rag.>S S rR RAn REP Nt L1NE REUPS 63/02/05. /AC.8(g o. zto saic hg c4 O d 0.0 0.1 O.l 0.0 ?le tSCei 0 Ilail II% ILIAN RELAPS/t$ 0 /Old REACTOR LOSS Of CKLfM ANR.ISIS PROCRfN AEP UNlT2 l LlHE RELRP O3/02/05. 'b~ a I>>O CI A P4 X sv O II. Cl ID D CD O D0 I~ Cl o 0.0 O.l 0.4 lit% ISECl I wA)0M C I CJl I/3 C/J N ID &0 I CD fD o O RLLAPS/NS]/ RL OR LOSS .fNT ANA. PRONN1 REP UNIT2 I LINE REI/IP 3/02/05. b~ OO K O ID I: O 0.0 O.R O.E O.I Tlat% lKC) 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 4I nDC Kl CD o O rt RELAPS/ /0 I;RCTOR L Ã .f% AHA. S t PRONATE RD'JHtT2 )NE R lBP 83/0 /05. U 8 8 go I 0.0 0.2 O.E O.e tltK 15EGI ( X) enM CD I CJl Ul o wnAl 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 4-129 /i TELEDYNE ENGINEERINQ SERVICES Revision 0 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) 67 segments quarter Model 26 segments Plot Set Transient 4.8.1 Uni t 2 PORV 400o Solid Liquid Case 4.8.2 quarter Model Cold Loop Seal/Steam Case 4-130 is TELEOYNE Technical Report ENGINEERING SERVICES TR-5364-2 Revision 0 4.8.1 Unit 2 - 400o Solid Li uid Case ~ )i TELEDYNE ENQINEERINQ SERVICES 4-131 C~ I BY CHKO. BY DATE~9 OATE~ 8$ VM iTE >>R9 STRICT'AURAL HOnE S~C-T i OW >ai~i5 SHEET NO. . ~* BP FIGURE 4.8.1-1 (@Id C047Iro OA7)ON sE E sHEQ7 g -><-TELEDYNE ENQINEERlNQ SERVlCES 4-132 C7C. 8 j. ~3 SHEET NO. 2 3 BY DATE oM sT 2 5TRvcT'VRA(- gobi p(oiu~ OF CHKO. ST +~~OATS~+~< 3 SRV SEC.T>o& FRom GtcKT Sv.95 A Qo) P((lES5. Qz(s Sv ASS PRKS5. P(R(." s Q(g Q(go Op SV 05< ~(( ( Q(20 Q FIGURE 4.8.1-2 (y PgljSS. Q(oe Qll 0 ( Qso Agc. l COhJTLMVQb a tJ SHE,KT 3 i0 TELEDYNE ENGINEERlNQ SERVlCES 4-133 SHEET HO. SF 3 U< iTZ srRuC.ru'RA< wool ~< ~gq cHKo. BY ~~DATg Z-// 83 tg'~ h) QQg M +RE& sHGET 2. ARC. i FIGURE 4.8.1-3 4-1 34 Technical Report TE; g NEER i qg ~=~V 'ES gyp'G: SAP2S AP .VER i', iCATiON 5c64 6-'J JN-8~ 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 v ~ I TINE P/i2 d -Z'.8Z qy CHKD. BY ~ ~~ OA>E DS'< 4-135 Technical Report TR-5364-2 Revision 0 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 /Vl+ 6 Z'.83 BY CHKO. BY ~ ~ DATE OATE 4-136 Technical Report TR-5364-2 c.i <<0 ~ hl< Revision 0 S:9'gicE '2 S AP2SAP lIt ER i,, ". 6 ' QN 5364 YEL-RED Sg;;D 4POF O <"ONS ~ ~ ~AGNITJDE 4T NQQE CO O~ CV % LA O CYY ~CO ~cu > ~ J I ~ 60 T I [ATE P//2 g ~ @ BY CHKD. BY ~ ~~ PAYB DATE 4-137 Technical Report TR-5364-2 Revision 0 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) ~ 6G T IME CV tl) 05 I l~ C V) I /0>+ Z.>3 BY CHKD. BY ~ DATE DATE d ~~~~~ 4 4-138 Technical Report TR-5364-2 Revision 0 MT.= =nvqiE ENG;NEER;Ng SERV.,"ES SAP2SKP. VERiF;CAT QN C-JJN-83 JN2 YEL RED SQi io 400F 0 oGvMS TIRE/FORCE TABLE 5 N4,0NITJDE A~ NODE POINT PnI U R) T I HE /V~+ 6-l'BZ BY 'HKD. BY ~ ~~ DATE DATE Technical Report 4-139 TR-5364-2 Revision 0 Sr >'V; Cc ~ 2SA." 'VER.,:"ATiQH 5364 UH2 YEL-RED S' iD ~ppF'-6pp~S TINE/FORCE TAB' 6. NAQH:rUD Ay HDE . O.HT o<h ~ I l o G. 0 ~ i 0 '6 0.ga I 0.P) I T I HE lA > A'P y.z g~ Bv CHKO. BY ~ oA"E OATE ~~~ 4-140 Technical Report TR-5364-2 Revision 0 ~TE'DvNE ESV.:CES SAP2SAP. VER i:=. CIT i QN 536-'N2 6-JUN-8i YEL-RED'Q~!0 ".OOF 0-.600MS TIME/FORCE !AB' T MAGNiTUDE CT NODE PQ!NT 0 Ql ~ T I ME h ~ I V) s I I I P/I+ 6.c'3 BY CHKD. BY ~ DATE DATE g~ 4-141 Technics Report 1 TR-5364-2 .Revision 0 ~ i>v QE =VC;,NEERIVG S SAP2SAP VERI~;"AT:ON 5364 6-JJN-8a UN2 YEL-RED SQ ID 400F 0-600'.S TIME/FORCE TABLE 8. MAGNITUDE AT NODE PO.VT LCi Ci~ L' I 0 ~ 5i TiME /Vl+ 4 < >3 BY CHKD. BV ~ DATE DATE ~~X 4-142 Technical Report TR-5364-2 .Revision 0 Tc, EDEN ENGiNEER.gG SERV."ES AP2S i'P 'ER: v - CAT; ON 6-JJN-gg iJN2 YEi -RED SOL,iD 400F 0-6008S T;.1E/FORCE TABLE 9 ."1AGNi UDE A. NODE POINT 310 O O h LLi Oca O~ 0 0 ~ i 0 '6 0 ~ 4 0 Sl ~ 0 '0 T I NE Pli2 s-z.az ev CHKD. BY ~ oAvc DATE ~~~ Technical Report. 4-143 TR-5364-2 Revision 0 ~TEI EDYNE ICiNEER 9< S SAP2SAP VER l F l CAT i QN 5364 6-JUN-Si UN2 YEL-RED SQL i 0 400F 0-6008S T INE!FORCE TABLE l 0 ~ MAGN! TUDE AT NQOE PQiNT "'08 0 5) ~ CD 60 T I NE W ~ ~ & ~ & AiC S-Z-S~ BY CHKD. BY ~ ~ OATZ BATE Technical Report 4-144 TR-5364-2 Revision 0 0"M ="V5.'NEER:VQ RY;~E SAP2SAP VERlF."AT;gq 6-O'JN-Qg UN2 YEL-RED SQLi.D 40QF 0-600NS TiNE/FORCE TAB" E ll NAGNiTDE AT NQOE POINT 298 <3 0 il 0 '0 P1>+ ~-z.8> BY CHKD. BY ~ ~ DATE DATE 4-145 Technical Report TR-5364-2 Revision 0 TE, DvNc ENG i NEER; NG SER'(. ",ES SAP2SAP VERiF.CATiON 5i64 6-JUN-63 UN2 YEL-RED SOLiD 400F 0-600MS TiME/FORCE TABLE l2, MAGN!TUDE AT NODE POiNT 290 oCl O CQ CT; Al 0 '9 C.17 0 '6 0 34 F TiNE O 't) ~J I P/~+ -z 83 BY CHKD. BY ~ DATE E DATE ~~~~ 4-146 Technical Report TR-5364-2 Revision 0 EO =qb'E~R -=R; .-::,:S 'A~2SAP VER i P'T i Qg "- JUN-83 NG 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, 0 60 F TiME /V/Z2 -Z'83 By CHKD. BY ~ DATE DATE d ~~~> 4-147 Technical Report TR-5364-2 Revision 0 DYNE END:NEERiNG c SAP2SAP VERiFiCA! iQN 5~64 Rq'-JdN-ag 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 0 a%i TiHE /Vl+ 0-c'SZ BY CHKO. BY ~ DATE OATE'g~ 4-148 Technical Report TR-5364-2 Revision 0 ~Pc'. envy>E ENGiNEER:NG SER'Vj~ES SAP2SAP VER F;OAT;ON 5~64 6-JUN-Bi 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 ~ CQ Ã I /9<+ 6-c'B~ BY CHKD. BY ~ DATE DATE ~~~~ 4-149 Technical Report TR-S364-2. Revision 0 'VPTE :-DYNE iNG:NEERiN- SERV';:CES SAI-2SAP 'ERi F '"g' QN 5364 6-JUN-83 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 /V~+ 6-c -8+ BY CHKD. BY ~ ~ OAYB DATE 4-150 Technical Report TR-5364-2 Revision 0 ~T"'OvN giqE~R'N( 4T. QN 5 6-JUN-gg UN2 YE'RED SQ'O 400F 0-600!1S TiÃE/FQRCE TABLE i? NAGN!TUDE AT HQOE ?QiNT 282 00 0 09 ~ 0 ~ i7 0 '6 0 '4 I

o. si 0 '0 T iI1E p//2 c'-83.

BY CHKD. BY ~ ~ DATE (p DATE 4-151 Technical Report TR-5364-2 Revision 0 EDYNE =NCiNEER:NC SERV,CE~ SAP2SA~ gER; F; C ~ 7 i Og 6- JiJN-8i 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 ~ 0 ~ 5i 0 6r T iNE /V//P >-z-sz Bs CHKD. BY ~ ~ oA7E DATE 4-152 Technical Report TR-5364-2 Revision 0 ?p ~ t= 'L C DYNE ENGiNEERiNC SERE;., ES SAP2SA~ VERl."tCA iGN :36~ 6-JUN-S~ 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 IJ~ 0.5i 0 'O TiN= I /V~+ c'-8> BY CHKO. BY ~ ~DATE a OATE 4-153 Technical Report TR-5364-2 Revision 0 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 262 0 '6 0 '0 T I NE 4~2 @-r-e 8> CHKD. BY ~ ~ oAvc DATE 4-'I 54 Technical Report TR-6364-2 Revision 0 7C", gvqg ENQ: 'uEE~ HG -=RV j ~ES SAP2SAP VER..=;-CA:GN 5o64 6-J~JN-83 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 I 0 0 a%i Ti:IE /VI2 6-c'83 BY CHKO. BY ~ ~BATE OATE 4-155 Technical Report TR-5364-2 Revision 0 Tc r lvNc =NCTREERINC ".iv, ~:ig SAPZSAP VER iF i COT i QN 5364 6-JJN-83 UN2 YEL-RED SQ: .-0 ALOOF 0-60GMS TIRE/FORCE TAB: E 22 MAGNITUDE AT'NODE PQ.NT 0 09 0; i7 0.26 0.34 0 ~ 0 '1 TiliE BY 4<2 DATE (p-c'8g CHKO. BY ~Q OATE g~ 4-156 Technical Report TR-5364-2 Revision 0 ~ -'D"NE "NGi HE Ri qG SER g I CES SAP2S~P VERi=icATION 536'N2 6-JUN-83 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 T 0 34 I [ATE 0 'I 0 '0 sv 4~2 Dv<E S-z.e CHKO. BY jQg OATE ~~~~ 4-157 Technical Report TR-5364-2 Revision 0 gPTE~"OYNE lGiNEERiNQ SERyiC-S SAP2SAP VER i F I CAT I ON 5i6~ 6-JUN-83 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 .4Q 0 51 ~ T I ME A~+ i'.83 BY CHKO. BY ~ DATE Ei DATE g~ 4-158 Technical Report TR-5364-2 Revision 0 "PPTEi EO" NE ENGiNEERiNG SERViCES SAP2SAP VER I r i CAT i QN 5a64 6-JUN-S3 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 0 '0 TIME /9>+ -Z.8~ BY CHKD. BY ~ DATE DATE d ~~~~ Techni ca Report 1 4-159 TR-5364-2 Revision 0, PPTEi EDvNE ENG NEERlNG ERViCES SAP2SAP VERiFiCATION 5364 6-JUN-SV UN2. YEL-RED SOLiD 400F 0-600NS TiNE/FORCE TABLE 26. MAGNITUDE AT NODE PO NT 242 T ..QE ~ 00 0,09 0 ~ I . 0 '6 I 34 0 I Si ~ 0 I 60 F YID CO ~ t CL C) 4 CO /Vl2 5 Z'.8Z BY CHKD. BY ~ ~ DATE DATE 4-160 Technical Report-TR-5364-2 Revision 0 gPT EL iD Y NE ERG NEERiRG SFRViC"S SAP2SAP VERi.- iCATION 5364 6-JUN-83 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 T 1 0.34 i'lE 0 'i /ViP 6.Z. 8~ BY CHKO. BY ~ OATE OAYE ~~~ 4-161 Technical Report TR-5364-2 Revision 0 'PPTELEO".NE lNEERiNG SAP2SAP VERIFiCATION 5364 6-JUN-8g 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 0 ~ i7 0.26 0 34 TINE 0 51 F 0 '0 O pl/+ 6-c'Q BY CHKO. BY ~ DA7E OATE ~~i> 4-162 Technical Report TR-5364-2 Revision 0 PPTELEDvNE ENGINEER'NC SERV SAP2SAP VERIFICATION 5364 6-JUN-83 UN 2 YEL-RED SOLID 400F 0-600NS T I flE/FORCE TABLE 29. NAGNI TUDE AT NODE PQ I NT ED ~A CQ TINE 0 17 ~ 0 26 0.34 0 43 0 ~ 5j 0 '0 /9~2 BY CHKD. BY ~ ~ DATE DATE e-c B~ ~ ~, 4-163 Technical Report TR-5364-2 Revision 0 ~TELEO~NE ENGINEER<NC SERVICES SAP2SAP YERi ICA.IQN 5364 6-JiJN-83 UN2 YEL-REO SOLID 400F 0-6OOMS TIME/EQRCE TABLE 30. MAGlYiiTUOE A! NOOE PQiNT 226 I NF F 00 0 ~ 'i 7 0.26 T 0.34 AS! 0 '0 ~/P 6-c'83~ BY CMKD. BY ~ ~ DATE DATE Technical Report TR-5364-2 Revision 0 ~E.1CiuEER:NC SERV,CES SAP2SAP VERiFiCATiQN 5364 6-JJN-83 UN2 YEL-RED SOLiD 400F 0-600NS Tif1E/FORCE "TABLE 31. f1AGNiTUDE AT NODE POiNT 219 Mcp ~ CF~ <v) 0 0 '9 0 17 ~ 0.26 0-34 0 '3 0-60 B TI YiE ,0' Ol YD y-Z-Z CHKD. BY ~ DATE DATB ~ 4-165 Technical Report TR-5364-2 Revision 0 PPTELED"NE ENGiNEER!NG SEPV ACES SAP2SAP V RiFiCATiQN 5364 6-JUN-Qg UN2 YEL-RED SQ'O 400F 0-600NS TINE/FORCE TABLE c2 NAGNiTUDE AT NODE PQiNT Ca <V C) lX a U Cl) 0 I 7 0 ~ 6 0 ~ 3 0 5) I P/~+ 6-c'.8g BY CHKD. BY ~ ~ DATE DATE 4-166 Technical Report TR-S364-2 Revision 0 "IGTNce.R<NC gc,qg,CCS Sh SAP VERi IC4TIQN 6-JUN-83 UN2 YEL-RED SO: iD ~OOF 0-6OOI".S TINE/FORCE TABLE 33. HAGN.:UOE AT NODE PQ,NT 195 ~o V C) 0 00 F 0 ~ 9 0 0 '0 /V~V 6-c'~ BY CHKD. BY ~ DATE DATE g~ 4-167 Technical Report TR-5364-2 Revision .0 PPTELEO~NE ENGiREERiRG ~ERyi"ES SAP2SAP VERIFICA! IQN 5c64 6-JUN-83 UN2 YEi -REO SQLiO 400F 0-600~S TINE/FORCE TABLE 34. RAGNiTUOE AT NQOE PQINT CD CO CD h 00 0 i 26 ~ 60 O 0 C3 /Vl+ BY ~ ~ DATE 6-c Bg ~ CHKD. BY DATE 4-168 Technical Report TR-5364-2 ~!ELEOYNE ENG NE R;NG S=RV;CES SAP2SAP VERiFiCATiQN 5364 6-JUN-83 UN2-YEi -REO SQI iO 400F 0-600MS TiNE/. QRCE TABLE, 35. NAGNiTUOE AT NOOE POINT i84 TiÃE 0 00 F 0 '6 0 '0 C3 ') CV ~/2 BY CHKD. BY ~ ~~ DATE DATE di-r'-~ 4-169 Technical Report TR-5364-2 T~ ~D"NE ENjTNEER;NG SERViCES SAP2SAP VERiF.CA!.ON 5364 6-JUN-S3 UN2 YEL-RED SQ'O 400F 0-600NS TiflE/FORCE TABLE 36. NAGNiTUDE AT NODE POiNT i82 / .09 'V ~. i7 0' 0 51 T I NE /VIP 6-c'.Bg BY CHKD. BY ~ ~ DATE DATE 4-170 Technical Report TR-5364-2 Revision 0 PPT:i EO.NE EuGiNEERiNG SERYiC SAP2SAP YER IF i CAT i QN 5364 6-JUN-83. 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 0 TiNE I ~ 0 'l 0 '0 C' ~ I W ~ /@~2 >-Z-a~ BY CBKD ~ BY ~ ~ BATB BATE 4-1 71 Technical Report TR-5364-2 Revision 0 TY TELEDYNE, ENG i NEER i NG SERY i CES SAP2SAP VER i F i CAT i ON 536< 6- JUN-83 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 ~ ~ dQ 0 ~ TiME /0/2 BY CHKO. BY ~ ~ OAjB OA7$ 0 c Bg 4-172 Technical Report TR-5364-2 Revision 0 LEDvNE "NGiNEERING SERVICES SAP2SAP VERIFICATIQN 5364 6'-JUN-83 UN2 YEL-RED SQi ID ALOOF 0-6OQNS TINE/FQRCE TABi E, go, RAGNiTUDE AT NODE PQ;NT 98 O F 00 0 09 F 0-i IE 0 ~ . l 0 '0 ~Q C) O ~l I ~ I I I I /Vl+ Z.8+ BY CHKD. BY kg DATE DATE ~ d 4-173 Technica 1 Repor t TR-5.364-Z Revision 0 PP'T E':0" N E ENG!NEER;NG SERViCES SAP2SAP VER(FiCAT'01 5364 6-JJN-83 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 I 7 ~ 34 S 60 ~J ~ ~ ~/2 ~ 6 c'B~- BY DATE CHkD. BY DATE ~~ 4-174 Technical Report TR-5364>>2 Revision 0 ~TE'OYNE ENGiNEERiNG SERViCES SAP2'SAP VERi.=iCATiON 5364 6-JUN-83 UN2 YEL-REO SQ iO 400F 0-600MS TifRE/FORCE TABLE 4l. f1AGNiTUOE AT NOOE PoiNT ,CD CL C) F 00 0 ~ 5I 6-c'8g CMKD. BY ~ ~ DATE DATE 4-1 7S Technical Report TR-5364-2 Revision 0 PPT EL Dv NE ENG i NEER I NG S""RV i CES SAP2SAP VER I F i CAT i QN 5364 6- JUN-83 UN2 YEL-RED SOL! 0 '00F 0-6008S T i NE/FGRCE TABLE ~2. IAGN; TUDE AT NODE PO iNT D t'ai 0 0 ~ i ~ 60 a U ~ P 5-Z'~ DHKD. BY ~ DATE DATE ~~ 4-176 Technical Report TR-5364-2 Revision 0 gPTc.Lc.DvNE ENG!NEERING SERVICE SAP2SAP VERI.-"ICATIQN 5364 6-JUN-83 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 I /4+ 0 -z'. B~ ~ BY DA ) E CHKO. BY kg OATE 4-177 Technical Report TR-5364-2 Revision <3 %'T~'"O" NE "NGiN ERiNG SER:g,C=S SAP2SAP VERjFiCATjgN .6-JUN-8g UN2 YEL-REO SO'O 400F 0-600NS TINE/FORCE TABLE 44. NAGHiTUOE AT'NOOE ~QiNT 82 O Q ~ Q U 0 00 F 0 ~ 6 I D.34 0 '0 TI Pl>+ d.i'8> BY CHKD. BY ~ ~ DATE DATE 4-178 Technical Report TR-5364-2 Revision 0 PPTEi EOCENE !VG.NEER!NG $ EPy=C SQP2$ Ap yER i c'-. r q, 6-JUN-83 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 /VIP a,-i'.8g BY 'CHKO. BY ~ DATE OATE ~~~~ 4-179 Technical Report TR-5364-2 Revision 0 PPTELED"NE. ENGiNEERiNG SERViC SAP2SAP VER I F i CAT i ON 5364 6-JtlN-83 UN2 YEL-REO SOLiD 40GF 0-600MS Ti ME/FORCE TABLE 46 MAGNiTUOE AT NODE POiNT ~ 78 'i W~ fD I hi~ C3 i ME F 00 0 '9 0 ~ Sl 0 '0 U /V~+ 6.c'-8g BY CHKD. BY ~ ~DAiE OATE 4-180 Technical Report TR-5364-2 Revision 0 ~TEl EOCENE c.AGiNEiRiNG SERV;CES SAP2SAP YER IF I CAT I QN 5364 6-JUN-83 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 T I NE 9- 00 0 09 F 0 ~ I EL C) ~CD /VI2 5-/.8g BY "CHKD. BY ~ DATE DATE / 4-181 Technical Report TR-5364-2 Revision 0 TEL.D,NE ENGiNE"RiNG S<RViC S SA~2S4~ VERi~ CATiON 6-JUN-83 UN2 Y= -REO SOi !0 400~ 0-600f"iS Tif1E/FORCE TABLE 48 NAGNiTUDE AT NODE PQiNT C' I Qadi ~ 26 0 ~ 0 5 ~ T I l1E P/12 BY CHKO. BY ~ DATE GATE g -Z ~~~ 8> 4-182 Technical Report TR-5364-2 Revision 0 ~TEf EDYNE ENG I t<EER f NG $ -R>/f- CES SAP2 SAP Lt ER I F I CAT f QN S364 6-JJN-S3 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 5 I 0 '0 E /Vl+ 0-c'g BY CHKD. BY ~ ~ DATE DATE 4-183 yechn>ca1 Report TR-5364-2 Revision' 4gpT Ei wr1YQE ENGiNEERi>G SAP2SAP VER < F CAT I QN < ~364 6-JUN-ag UN2 YEL-RED SOLi D 400~ 0-600t.S TiÃE/FORCE TABLE 50. MAGNiTUOE AT NOOE POINT ~ C3 I 0 CI lc F 00 ~ I 7 Oi "6 0 60 ~ ~ & /VI2 S~, ~ ~ 6 -c BY DATE . CHKO. BY OATE 4-184 Technical Report TR-5364-2 Revision 0 ~TE'D"~~ ENGiNEERiNG "ERV;CES SAP2SAP VER i F i CAT i ON 5364 6-JUN-83 UN2 YEL-RED SOLiD 400F 0-600MS TIME/FORCF TABLE 51. MAGNiTUDE AT NODE POiNT h O F 00 D d P4 0 ~ 1 A>+ z'-80 BY CHKO. BY ~ ~DATE d OATE 4-185 Technical Report TR-5364-2 Revision 0 "NGiNEc.R!NG SERVICES SAP2SAP VERIFI CAT;QN 5364 6-JUN-R3 UN2 YEL-RED SQL I 0 ~OOF 0-600NS TINE!FORCE TABLE 52 f1AGNITUDE AT NODE POINT F 00 ~ 9 0~ i ~ 26 O.r34 TI U o /VIP -8g BY CHKO. BY ~ OATE DATE dr-c ~~ Technical Report 4-186 TR-5364-2 ~TE gYNE ENCiNEERiNC SERV;CES SAP2SAP YERi~iCATiQN 5364 6-JUN-83 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 +/2 -c'8> BY CHKD. BY ~ DATE DATE 4 ~~~ 4-187 Technical Report TR-5364-2 Revision 0 ~TELEDYNE ENGiNEER.HG S~RViC SA. 2SAP VER iFi CAT i ON 5364 '-JUN-S3 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 /9/2 g-c'-B~ BY CHKD. BY ~ ~ DATE DATE 4-188 Technical Repot t TR-5364-2 Revision 0 EN0 j N c. E R i !V G S " 9 V j C.- S SAP2SAP Lr'ERjFiCATiON 5364 6-JUN-83 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 5l ~ iV /9/2 6-c'9~ BY CHKD. BY ~ DATE DATE ~~~ 4-189 Technical Report TR-5364-2 ,Revision 0 TELEDYNE ENGiNEERiNG <<RVjCES SAP2SAP VERiFiCATiON 5364 6-JUN-83 UN2 YEL-RED SOLiD 400F 0-600MS TiME/FORCE TABLE 56. MAGNiTUDE AT NODE POiNT 12S iV lO h ~ ~lO OJ CL o Ol 0 '6 0 ~ 0 '0 /ViC "c'8g BY CHKD. BY ~ ~ DATE (y DATE 4-190 TecHnical Report R-5364-2 evlsion 0 PPTEi EDYNE ENGiNEERiNG SERV CES SAP2SAP VERiFiCATION 5364 6-JUN-83 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 ~ PII2 0 Z 83 BY CHKO. BY ~ DATE OATE g~ 4-191 Technical RePor t TR-5364-2 TELEDYNE ENGiNEERiNG SERViCES SAP2SAP VERiFiCATiON 5364 6-JUN-83 Uf<2 YEL-RED SOLi0 400F 0-600NS Tif1E/FORCE TABLE 58. MAGNiTUDE AT NCDE POiNT F 00 0 ~ i7 0 34 ~ 0 '3 0 /Vl2 -2'8g = BY CHKD. BY ~ ~ DATE OATE d 4-192 Technical Report TR-5364-2 Revision 0 ~ E':OYNE ENGiNEERiNG SERViCES SAP2SA: VERi."iCATiQN ~364 6-JUN-83 UN2 YEL-REP SQLiD 400F 0-600f"S Ti5E/FQRCE TA9i E 59, 5AGNj..UPE AT NQPE PQiNT 48 o<h T I NE F 00 0 '9 ORBIT 0 26 0 34 0 '3 0 '0 CO CD CO /V~V 4-c-83 BY CHKD. BY ~ DATE DATE ~~~~ 4-1 93 Technical Report R 5364-2 ev>sion 0 ~TEY EO" ~<E. ENGiNEER;VG SERViCES SAP2SAP VERiF;CATiQN 5364 6-JUN"GD 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 60 F tA ~l 0 CI W C) /9/P g-c.>~ ~ ~ BY BATE CHKO. BY OATE 4-I 94 Technical Report TR-5364-2 Revision 0 TELEQY>l-= SAP2SAP 'lJ'ERjFjpb,TjQN 5Q6Q 6-JUN-83 UN2 YEL-RED SQL'0 400c 0 60QNS Tit1E/FORCE TABLE 61. NAGViTUDE AT NODE: GENT 0 '9 0 '6 0. a3 0 5i (I/8 g-1 8g BY CHKO. BY ~ ~ DATE OATE 4-195 Technical Report TR-5364-2 Revision 0 =GYVE =8=;NE;-8;NC SERV!CES SAP2SAP VERi."tCATiQN 5364 ."-JUN-83 UN2 YEL-RED SQLiD 400F 0-600~iS Ti>EfFORCE TABLE 62 RAGNiT' AT NODE POiNT NE 0 '9 0 '6 0+4 0 ~ -'. 3 0. S) ~CI O CY Qe O /Pl+ BY CHKD ~ BY ~ ~DATE DATE 6-Z-B~ 4-196 Technical Report TR-5364-2 .Revision 0 ~~E EOCENE

NCiNEER!N" SFRVICES SAP2SAP YERiFiCATiON i364 6-JUN-83 UN2 YEL-RED SOi iD 400F 0-600NS TiÃE/FORCE TAB! E 63 NACNiTUDE AT NODE POiNT O

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