ML17334A492
| ML17334A492 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/18/1983 |
| From: | TELEDYNE ENGINEERING SERVICES |
| To: | |
| Shared Package | |
| ML17334A491 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TR-5364-3, TR-5364-3-R, TR-5364-3-R00, NUDOCS 8312210225 | |
| Download: ML17334A492 (239) | |
Text
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!I ECHNrjCAL REPOR ii TECHNICAL REPORT TR-5364-3 REVISION 0 BOOK 1 OF 3 DONALD C. COOK NUCLEAR GENERATING PLANT ANALYSIS OF PRESSURIZER SAFETY VALVE DISCHARGE PIPING SYSTEM, MTH DRAINED LOOP SEALS PER NUREG 073V, ILD.1, UNIT 1
.~ULY 18~%983 8312210225 83i2i5 PDR ADOCK 05000315
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AMERICAN ELECTRIC POWER SERVICE CORPORATION 2 BROADWAY NEW YORK, NEW YORK 10004 TECHNICAL REPORT TR-5364-3 REVISION 0 BOOK 1 OF 3 DONALD C. COOK NUCLEAR GENERATING STATION ANALYSIS OF PRESSURIZER SAFETY VALVE DISCHARGE PIPING SYSTEM, WITH DRAINED LOOP SEALS PER NUREG 0737, II. D.l, UNIT 1 JULY 18, 1983 PV'TELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-890-3350
-r<-TELEDYNE cal . Report H'echni ENGINEERING SERVICES TR-5364-3 Revision 0 TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
Book 1 of 3
2.0 CONCLUSION
S 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 4.2.3 Discharge Piping 4-4 4.2.4 quench Tank 4-4 4.3 RELAP Model Control Volumes 4-11 4.4 Valve Flow Rate Calculation 4-19 4.5 RELAP,Plots 4-25 4.6 Force Time History Plots 4-63 4.7 RELAP Input 4-134 4.8 REP IPE Input . 4-154 4.8.1 REPIPE Input - Section A 4-155 4.8.2 REPIPE Input - Section B 4-161 4.9 Appendix,A 4-169 5.0 STRUCTURAL ANALYSIS Book 2 of 3 5-1 5.1 SV Transient Thermal Analysis 5-2 5.2 Transient Shock Analysis 5-2 6.0 ANALYTICAL RESULTS 6.1 Stress Sumary 6-1 6.1.1 Equation C-1 Stresses 6-5 6.1.2 Equation C-2 Stresses 6-16 6.1.3 Equation C-3 Stresses 6-27 6.2 Support Loads 6-38
Techni cal Report TR-5364-3 A TELEDYNE Revision 0 ENQINEERINQ SERVICES TABLE OF CONTENTS ont nued PAGE
- 6.3 Valve Accel erations 6-79 6.3.1 DBE Seismic Accelerations 6-80 6.3.2 SV Transient Shock Valve Accelerations 6-84 6.4 Nozzle Loads 6-88 6.5 Valve Loads 6-94
- 7. O,DRAWINGS 7-1
8.0 REFERENCES
8-1 9.0 COMPUTER ANALYSIS Book 3 of 3 9.1 RELAP Input 9.2 REPIPE Input 9.2.1 REPIPE Input Section A 9.2.2 REPIPE Input Section B 9.3 Thermal Case 3 Input/Output 9.4 SV Transient Shock Input
Technical Report << TELEDYNE TR-5364-3 Revision 0
, ENGlNEERINQ SERV!CES
1.0 INTRODUCTION
American Electric Power Service Corporation (AEPSC), 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.l for the Donald C. Cook Nuclear Power Plant, Unit 81..
This activity was performed in accordance with the TES quality 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 Engineering Services Technical Proposal PR-5653 (Reference 9), dated May 14, 1981 and modified as stated in AEPSC letter dated November 29, 1982, from Mr. Sam Ulan (AEPSC) to Mr.~ L.~ B.~ Semprucci (TES); in AEPSC letter from Mr. Sam Ulan (AEPSC) to Mr.~ P.~ D. Harrison (TES) dated March 15, 1983 (References 1 and 11) and in TES letter 5364-44 from Mr. P. D.Harrison
~ ~ (TES) to Mr. S. 'Ul an (AEPSC) dated May 28, 1983 (Reference 10).
The majority of the analysis was performed after the receipt of AEPSC letters dated November 29, 1982 and March 15, 1983 (References 1 and ll), which were issued after more complete information was available from the EPRI data.
This analysis was performed using 1 arge digital computer programs supplemented with any necessary hand calculations. The RELAP5 MOD1 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 size of the pressurizer 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 overconservative overlap analysis.
J' rs-TELEDYNE Technical Report ENQINEERlNQ SERV(CES TR-5364-3
~ ~
Revision 0 2-1
2.0 CONCLUSION
S The analysis per formed by TES on the Pressurizer Safety/Relief Valve Discharge Piping System with the Safety Valve loop seal drained, indicates that all criteri a of NRC NUREG-0737, Item II.D.1 are met, with the following qualifications:
- 1) Valve accelerations due to the SV transient shock condition for valves SV-45A, SV-45B and SV-45C exceed the vertical allowable of 2g's (Reference 14). The accelerations exceed the allowable by less than 1g and, therefore, it is TES's opinion that these valve accelerations are acceptable. However, setting the criteria of acceptance of these accelerations is out of the TES work scope and is, therefore, the responsibility of others.
- 2) The supports listed below exceed the loads given on the- As-Built l
support drawings (see Section 6.2). These support loads, while exceeding. the previous loads, do so in most cases by a small percentage. However, acceptance of these loads is out of the TES work scope and is the responsibility of others.
1-GRC-R-585 1-GRC-R-589 1-GRC-R-591 1-GRC-R-601 1-GRC-S-608 1-GRC-R-613 1-GRC-S-614
,1-GRC-R-616
Technical Report
<<TELEDYNE-TR-5364-3 ENQINEERINQ SERVlCES Revision 0 2-2 This report documents that the safety/relief valve discharge piping for
. Unit 1 is acceptable for emergency conditions assuming drained loop seals. TES Technical Report TR-5364-1, Revision 0 (Reference 2), which is based on the as-built condition, documents the acceptability of the system for normal and upset conditions. Draining the loop seals will not affect the normal and upset conditions.
The purpose of the loop seals was to protect the safety valves from leaking by keeping free hydrogen and high temperatures away from the valve seats. It should be noted that while draining the loop seals relieves the overwhelming stress on the discharge system,'ee TES Technical Report TR-5364-1, Revision 0 (Reference 2), it also leaves the valve seats unprotected and, therefore, susceptible to leaking. While it is beyond the responsibility of TES, this
~ ~ ~ ~
~
condition can result in serious consequences and should be investigated.
~ ~ ~ ~
Support load su@vary sheets have been included in this report for all supports and supercede the loads reported in TR-5364-1.
-rs-TELEDYNE Technical Report TR-5364-3 ENGlNEERlNQ SERVlCES
~ ~
Revision 0 3-1 I'.0 SYSTEM DESCRIPTION/DISCUSSION The Pressurizer Safety/Relief Valve Discharge Piping System 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-5763, Revision 3, generated from AEP drawings 1-GRC-6, sheets 1, 2, 3, and 4; 1-GRC-7; 1-GRC-8; 1-GRC-9; 1-5435-8; 1-RC-6, sheets 1, 2, 3 and 4; 1-RC-7; 1-RC-8; and 1-RC-9.
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 pressurizer, 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.
These long loops contain sufficient quantity of water such that on SV Discharge, the water'eal 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.
Technical Report ><-TELEDYNE TR-5364-3 ENQINEERINQ SERVICES Revision 0 4-1 4.0 THERMAL FLUIDS ANALYSIS 4.1 Introduction The following thermodynamic fluid analysis determines the fluid forces which act on the pressurizer safety valve discharge piping of the American Electric Power Service Corporation (AEPSC) Donald C. Cook Nuclear Power Plant, Unit 1.
These forces are generated by the sudden opening of the pressurizer safety valves during one of the pressurizer transients described in the AEP letter of November 29, 1982 to TES (Reference 1).
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 this 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 to choose and test a computer program which would predict the fluid forces; REL'AP5 MOD1 was chosen. RELAP5 MODl is the latest in the family of RELAP programs developed at the Idaho National Engineering Laboratory.
The D.C. Cook Units 1 and 2 pressurizer safety valves have "Cold Loop Seals". A "Cold Loop Seal" is a subcooled slug of water trapped between the safety valve seat and the pressurizer nozzle by a loop of piping. The function of this slug of water is to prevent the safety valve from leaking, this is .
accomplished by keeping free hydrogen away from, and maintaining reduced .
temperatures at the valve seat. While the loop seal provides a benefit, it also
~
has a serious drawback.~ When the safety valve opens, the loop seal is, shot through
~
the discharge piping with tremendous force. In TES Technical Report TR-5364-1,
~ ~ ~
TES performed a fluid analysis to determine the magnitude of the loads applied
Technical Report TR-5364-3 r<-TELEDYNE Revision 0 4-2 ENQINEERINQ SERVICES to the discharge piping by the propulsion of the cold loop seal. These loads
~ ~
were calculated to be greater than 100,000 lbf for a single safety valve discharge.
The simultaneous discharge of the pressurizer's three safety valves with loop
~
seals could result in loads of over 300,000 lbs.
As explained in TR-5364-1, TES also performed a sensitivity study to determine if raising the loop seal temperature (by electrical trace heating) would reduce the loads. Increasing the loop seal temperature did lower the loads.
somewhat, however, a significant reduction was not obtained. It was then suggested that the loop seals should be drained so that when the safety valves operated, they would discharge steam only.
This report presents the analysis for the steam discharge that was performed for the Unit 1 pressurizer safety valves.. The maximum fluid force calculated in this analysis is 24,000 lbf for simultaneous discharge of all three safety valves. It can be seen that draining the loop seals provides a significant force reduction.
In this analysis, as before, TES has used RELAP5 MOD1 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 MOD1 is identified by the following computer job control language at Control Data Corporation:
BEGIN, RELAP5; R5M2, INPUT=INPUTFILE, SCM=377000B 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.
I<. TELEDYNE Technical Report ENGlNEERIMQ SERVCEFi TR-5364-3 Revision 0 43 4.2 RELAP Model 4.2.1 The D.C. Cook pressurizer was modeled as a single time dependent volume with the following transient condition as specified by the AEPSC, November 29, 1982 letter to Mr. L.B. Semprucci, pages 1-7 (Reference 1):
~Ef1 ft Pressure Time History (in the pressurizer) 2750 o e2750 2750 2700 2700 2667 650 Pressure (ps')
2600 2600 2550 o'2555 0 2514 1.0 2500 0.5 Time (Sec)
These are the same safety valve pressure boundary conditions that were used in analyzing the quarter model cold loop seal case of TR-5364-1 (Reference 2).
s>-TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-3
~
~
Revision 0 4.2.2 Safety valves were modeled as RELAP junctions emulating Crosby HB-BP-86 valves (Reference 3) with orifice areas of 0.01897 Ft2 and a valve opening time of 0.010 seconds.
Valve orifice areas were calculated using the Crosby Valve and Gage Company Drawing No. H-51688, Revision A (Reference 3) provided by AEP, and RELAP (Run ID BAICDRO) implementing rated flows. Calculated values are included in Section 4.6 and 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 8410 by Crane (Reference 4). 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.
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 5).
The sparger for D.C. Cook is a perforated pipe submerged in water within the quench tank as indicated in Figure 4.2.1. It is represented in RELAP as a pipe similarly submerged and of equal volume.
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0 Technical Report A TELEDYNE TR-5364-3 ENQINEERINQ SERVICES Revision 0 4-11 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 6) 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 recommended 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 1 is represented in Figure 4.3.1. All arcs for Unit 1 were modeled in RELAP as having no fluid losses. Essentially, RELAP alculates 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 1 model wer e:
~Pi e Size Avera e C.V. Len th 3 inch SCH 160 0.4644 feet 6 inch SCH 160 0.5264 feet 4 inch SCH 40S 0.4471 feet 6 inch SCH 40S 0.8614 feet 12 inch SCH 40 0.8064 feet 3 inch SCH 40 0.4744 feet 4 inch SCH 120 0.5056 feet The schematic of the discharge system modeled in RELAP for the SV nit 1 model is represented in Figure 4.7.1.
Technical Report A TELEDYNE TR-5364-3 ENQINEERINQ SERVICES evision 0 4-12 quench Tank modeling was achieved using twenty control volumes and twenty junctions. Eighteen volumes comprise 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 5) 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 equal 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.
igure 4.2.1 represents the D.C. Cook Unit 1 and 2 quench Tanks. Pressure in the
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ir volume of the quench tank never exceeded 30 psia during the Unit 1 SV transient case of steam and drained loop seals RELAP5 run for 0.5 seconds.
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>i]'-17 p P5 gy OK Ogyg3 2S-8B u<>V' SA,iv AR,C, Cogegc>>Dgg SHEET NO. / OF CHKD. BY ~~DATE~~~~'ij~
B'RAM<HiS + WE'ES FIGURE 4.3.1-5 7Q SOS.~
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A TELEDYNE Techni cal Report ENQINEERINQ SERVICES TR-5364-3 evision 0 4-19 4.4 Valve Flow Rate Calculation
'The following values were used in valve modeling considerations:
TES Flow2 Max Rating> Actual Rate Calculated For Steam Bore Area Opening Valve T e LBM HR I 3'C Accum. ~IN2 Time Sec Crosb 452,393 435,000 3.6 in2 0.010 afety Relief (Ref. 15)
Val ve
~
The maximum rating for
~
steam at 3X accumulation value is from the Crosby Valve and Gage Safety Valve Drawing No. H-51688, Revision A (Reference 3).
2 Flow rate at 2500 psig plus 3X accumulation.
r< TELEDYNE Technical Report ENGINEERING SERVICES TR-5634-3 evision 0 4-20 The valve flow rates normally used by TES in the RELAP analysis of the SVs would be a 15K increase in the ASME rated flow: 1(C to consider the ASME underating of the theoretical flow and 5X to cover tolerances. However, in this particular case, Westinghouse has provided AEPSC with a sumary of the EPRI flow rate tests of the Crosby 6M6 safety valve (Reference 7). Also, see Figure 4.4.1-
- 4. A comparison was made in an effort to achieve a more realistic flow rate.
The flow rate chosen which most closely bounds the test data is the following ASME flow rate. All calculations are included as Figure 4.4.1.
= 51.5A (1.03P + 14.7)(.9)(.966)C (Ref. 8) where:
= theoretical flow WR
= rated flow coefficients:
1.03 - applies 3X accumulation 0.966 - valve flow coefficient 0.9 - represents theoretical flow rate reduced lOX to equal ASME rating C = 1.0771 calculated on Figure 4.4.1-2 following.
TR-5364-3 )< TELEDYNE ENQINEERINQ SERVICES Revision 0 4-21 DATE + ~ 88 ~gosS ) 6H vAa vE SHEET NO. OF HKD. BY~~DATE~ MODEL. +LOW AIRED CAg.C'>ger/gjQS FIGURE 4.4.1-1
&p: A~E ZecZZ- A/.8-FFZ<. g $ IIJ8 yyg42 (/ye~)
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CHQS8 Y 6Ng VALVE PROPERTIES MlInfVFAC7-VEEN : CZOS8) VALVE'eAC<E. aO.
7 :SPR/IJe LO~Xea SAeEr> VALVE V/'Z'v/gDZL A/O : //g 8p gg dM$
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VAR/OVAL 1' TIIZ FolLouud6 CALCVLATINLs A cMS7AIJT SEr PNwu~'E g~Eo ro cALcvLA7E A Flow) ANFA Foz ~eF RzuIpw AoszL AA)s Z)O~S'fOr O'ZcEssAR/L Y 8'Ec KESs&p- fREWgg/Zrg IA)P& C4MJTIC45 g 7/I&'E ARE r/OA)$ 4 IJ8 Ega FLOuJ EA pEPIME IJ78 /-
IESULYS YIELDIAJ5 8/F/=PARFAIT RATEs. ALL O/= 7IIESE A'E PRESENTED IAI 7PE PA'OCZZVnlC~ NSE'; A ~~ONEATr NC SZi ZCVu SUCFI 7'IIA7 I7 AJWX8 BF CONS&'ATIl/E'F COMA'ti'E8 H/ITII TEST TA 8l/7 /7 4/OUL 0 ST/L L 8E'~FALI57 IC
TR-5364-3 (> TELEDYNE ENQlNEERlNQ SERVlCES Revision 0 4-22 OATE~>-
BY~MDATK~063 I~ c/Qs'BY bed wA L vE SHEET NO. OF s KD EF~APS ~OUI F~Oa /fed CA/-C./Illri045 FIGURE 4.4.1-2 VARiOUS Fi Ou) PA7ES FOX SNAB CA'CMV VALVE PEON DirFZEEiJ7 SO~RcG zoo~ pro. ay usoJo spy,,~~) X/.a~A,(s os.~+A.t) e~
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4 TR-5364-3 ~)< TELEDYNE ENQINEERINQ SERVICES Revision 0 4-23 DATE O cl'O~Y'e& v c.va- SHEET NO. ~ OF~
BY~DATE~~ PROJ. NO. ~ZAN KD. YS'LA/5 pfOSzi a.ou 8A'EA C/ICVMri045 I
FIGURE 4.4.1=3 I/) ZlAP PPPBEL FaA'HE bbfd CA'OSS) LIJO'u = ~i54893//
8AM> Oe AaueP77OnJ X 7 PASZ 4.
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PHIAL& i IIE'OMPV7EI A VAf 882 CS A vw~vw wucL OPEN Ma< iu 7'~N 8AzCngg P. PdZZ P~
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.~TELIEIÃbK Technical Report TR-5364-3 4-24 MSSN SRfCB)
Revision 0 FIGURE 4.4.1-4 FIGURE 3-5 STEAN OISCHARGE CYCLE (STABLE) 600 CROSBY 6M6 500 400 30 O
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Techni cal Report A TElEDYNE TR;5364-3 ENQtNEERlNQ SERVtCES
'sion 0 4-25 4.5 RELAP Plots The following plots represent RELAP mass flows, pressures and qualities at various points along the discharge piping. 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 trends 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. A RELAP volume schematic precedes the plot set for the transient steam case.
echnical Report A TELEDYNE ENQINEERINQ SERVlCES TR-5364-3 4-26 Revision 0 DATE~ A Zl gP ~oDEL Sch&YHTZC SHEET NO. OF.3 BY CHOATE~+ f44'V Gt war N~
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TR-5364-3 4-27 BYTES~~ OAT E d2~~~Z rFELAP /YODEL 9 CgZ /4AVZ'C SHEET NO. ~~OF~
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0 Technical Report A TELEDYNE TR-5364-3 ENGIMEERlNQ SERVlCES ision 0 4-63 4.6 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 the 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 0.5 seconds. Unit 1 has 67 pipe segments and correspondingly 67 force histories. 'ime
TR-5364- 3 A TELEDYNE ENQIN=ERIMQ SERVlCES Revision 0 4-64 BY DATE~ ~RV~MdrCliA ~P= Pd~AV S SHEET NO ~ OF CH Y M~DATK+~8
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~~80 FIGURE 4.6.1-1
,,, ppTELEDYN= ENGIN=ERIMQ S""RVICES TR-5364- 3 Revisio 0 D ATE+~+8Z SHEET NO.. ~OF 7
BY CHK OATEN/~~
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4-66 QTR VCPVAQ~~ ~dg~ +4 <<h' SHEET NO 'F MUD) +.r":IU (Ih )~Q FIGURE 4.6.1-3 QB Qss Qs(. QI QSQ i/
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Technical Report TR-5364-3 Revision 0 4-67 IIH@51NG sERYIGEs SAP2SAP VERiFICATION 5364 . 6- JUL-83.
DC COOK-UNIT) r SV NODIFICATION TINE/FORCE TABLE 1, MAGNITUDE AT NODE POINT 620
Technical Report TR-5364-3 Revision 0 4-68
~NBNN~~o sERv~cEs SAP2SAP--VER IF I CAT ION 5364 6- JUL-83 DC COOK-UNI Tl e SV NODIFI CATION TINE/FORCE 'TABLE 2e NAGNITUDE AT NODE POINT tO Ol 00 03 O
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08 I
Technical Report TR-5364-3 Revision 0 4-69
~SHRIVING sERvt CES SAP2SAP VERIFICATION 5364 6- JUL-83 DC COOK-UNITtt SV NODIFICATION TINE/FORCE TABLE 3e MAGNITUDE AT NODE POINT CO CO 00 o0 0.36 0.43 0.5(
T I NE
Technical Report TR-5364-3 Revision 0 4-70 NfmtIINIIING SERYICES SAP2SAP VERIFICATION 5364 6- JUL."83 DC COOK"UNITle SV NODIFICATION TINE/FORCE TA8LE 4 ~ NAGNI TUDE AT NODE POINT 536 IO a
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Technical Report TR-5364-3 Revision 0 4-71
,e SAP2SAP VER IF I CAT ION 5364 DC COOK-UNI T1 e SV NODIF I CAT IOH lllBIIINI!NGSERV!CES 6-JUL-83 TINE/FORCE TABLE Si MAGNITUDE AT NODE POINT.
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Technical Report TR-5364-3 Revision 0 4-72 NBNN1NG sERYIGEs SAP2SAP VER IF I CAT I ON 5364 6-JUL"83 DC COOK-UNI Tl e SV MODIFICATION TINE/FORCE TABLE 6t MAGNITUDE AT NOOK POINT 550
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Technical Report TR-5364-3 Revision 0 4-73 IIHNSIHG SERVICES SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNIT) e SV NODIFICATION TINK/FORCE TABLE 7e MAGNITUDE AT NODE POINT 555 I E D
QJ CO
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Technical Report TR-5364-3 Revision 0 N)88fING SERVICES SAP2SAP VER I F I CAT I ON 5364 6-'UL-83 DC COOK" UNI T1 t SV NODIFI CAT ION TINE/FORCE TABLE 8. MAGNITUDE AT NODE POINT 560 CO o
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Technical Report TR-5364-3 4-75 Revision 0 tk%5lHG sERYIGKs SAP2SAP VERIFICATION 5364 6- JUL-83 DC COOK-UNIT l I SV NODIFICATION TINE/FORCE TABLE 9 ~ NAGNI TUDE AT NODE POINT EO OI O
LLJ~
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00 07 0 '4 0. 9 0.36 0 43 Ol T I NE o
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Technical Report TR-5364-3 Revision 0 4-76
~59@liNs seRvices SAP2SAP VERIFICATION 5364 6-SUL-83 DC COOK-UNIT) I SV NODIFICATION T INE/fORCE TABLE ) 0 ~ HACNI TUDE AT NODE POINT CV Ol tO 08
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Technical Report TR-5364-3 Revision 0 4-77 3lhfNNIRG SERVICES SAP2SAP VERIFICATION 5360 s-ou}.-ss DC COOK-UNI T l,'V NODIF I CAT ION TINE/FORCE TABLE 1 1 . NAGNI TUDE AT NODE POINT 00 0 0 .43 D.50
Technical Report TR-5364-3 4-78 Revision 0 tl&fHltlNG SERVICES SAP2SAP VERIFICATION 5364 6- JUL-83 DC GOOK UN I T 1 ~ SV NOD I F I CAT I ON TINE/FORCE TABLE 12'AGNITUDE AT NODE POINT 360 CO OJ C7 Cl CI
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U C5 Yl 0 00 0. 0~ .36 0.43 0.50 TI E
Technical Report TR-5364-3 4-79 Revision 0 DHNNING SERV I CES SAP2SAP VERiFICATION 5364 6- JUL-83 DC COOK-UNI T1 e SV NODIF I CATION T I NE/FORCE TABLE 1 3 r NAGNI TUOE AT t tODE POINT 355 a
CO lO CO
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Technical Report TR-5364-3 4-80 Revision 0 NBNIING SERVICES SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK" UHI T ) e SV NOD IF I CAT I OH TINE/FORCE TABLE ) 4 e NAGH I T UDE AT HODE POINT, 350 LO oCA CO OJ M
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Technical Report TR-5364-3 Revision 0 4-81 8388)ING SERVICES SAP2SAP VERIF ICATION 5364 6-JUL"83 DC COOK-UNI T f . SV NODIF I CAT ION TINE/FORCE TABLE f 5e NAGNI TUDE AT NODE POINT 00 0 0
Technical Report TR-5364-3 4-82 Revi,sion 0 II ESBBIIING SERVICES SAP2SAP VER IF I CAT I OH 5364 6- JUL-83 DC COOK-UNITl, SV NODIFICATION TINE/FORCE TABLE l 6e NAGNI TUDE AT NODE POINT a
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Technical Report TR-5364-3 Revision 0 4-83
.NIENNING SERVICES SAP2SAP VERIF I CAT ION 5364 6- JUL"'83 DC COOK-.UNIT) e SV NODIFICATION TIRE/FORCE TABLE ) Te MAGNITUDE PT NODE POINT h
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~ ~+
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Technical Report TR-5364-3 4-84 Revision 0 N~S(NING SERVICES SAP2SAP VERIFICATION 5364 DC COOK UNIT1 SV NODIFICATION
~
T I ME/FORCE TABLE 1 8 ~ NAGNI TUDE AT NODE POINT h
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Technical Report TR-5364-3 Revision 0 4-85 NcfNNING sERYIcfs SAP2SAP VERIFICATION 5364 DC COOK-UNI T1 r SV NOD IF I CAT ION TINE/FORCE TABLE 1Se MAGNITUDE AT NODE POINT 310
- 0. 0 3 0.50
Technical Report TR-5364-3 4-86 Revision 0
@~SlNIlNG sERYIGEs SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK UN I T ) ~ SV NODIF I CAT ION TINE/FORCE TA8LE 20. NAGN I TUDE AT NODE POINT 300
.0 0~ 0 3 0.50
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Technical Report TR-5364-3 4-87 Revision 0 N)B(SING SERVICES SAP2SAP VERIF I CAT ION 5364 6" JUL-83 DC COOK-VNI T 1 . SV MODIF I CAT I ON TIME/FORCE TABLE 21 r MAGNI TVDE AT NODE POINT tO CO o
TXl1E 00 0. 1 0.2S 0.36 LLIcl
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Technical Report TR-5364-3 4-88 Revision 0 BtLNENt NG sERY1GEs SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNI T ) e SV NODIF I CAT ION TINE/FORCE TABLE 22. MAGNITUDE AT NODE POINT TINE 00 0. 1 0.29 0.36
~Ci QO O I
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Technical Report TR-5364-3
, Revision 0 4-89 kkfQNING SERVICES SAP2SAP VERIFICATION 5364 6"JUL-83 DC COOK-UNI T1 r SV NOD IF I CAT I ON TINE/FORCE TABLE 23 ~ NAGNI TUDE AT NODE POINT 130 Ol o
h C7 CO TINE
~oo 0. ) 0.29 0.36 0.43 0.50 O~
a i
Technical Report TR-5364-3 Revision 0. 4-90 NHII811NG SERVICES SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNIT l . SV t10DIF ICATION TINE'/FORCE TABLE 24. NAGNITUDE AT NODE POINT l26 TINE 0.$ 0 0 00 0. 1 0.29 0.36 0.43
~CV
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Technical Repor t TR-5364-3 Revision 0 4-91 BANNING SERVICES SAP2SAP VERIFI CAT ION 5364 6-JUL-83 DC COOK UN I T 1 ~ SV NODI F I CAT I OH TINE/FORCE TABLE 25. NAGHI TUDE AT NODE POINT )20 a
CA CO CD LO TINE a0 00 0 4 0.21 0.29 0.36 0.50 o
Ol O~
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CO h
C5 LIl CV I
Technical Report TR-5364-3 Revision 0 4-92 5LfIIN[ING SERV1CES SAP2SAP VERIFICATION 5364 6- JUL-83 DC COOK-VNI T 1 v SV NODIF I CAT ION TINE/FORGE TABLE 26r MAGNITUDE AT NODE POINT
~ ~ I TINE '.43 0 00 0 0.)4 0. 1 0.29 0.36 0.50
!O tO 1
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Technical Report TR-5364-3 Revision 0 4-93 N)SNI'tNG sERYIcEs SAP2SAP VERIFICATION 5364 6- JU'83 DC COOK" UHI T i . SV NOOIF I CAT ION TINE/FORCE TABLE 2T. NAGNITUDE AT NODE POI'HT O
T I NE 0 00 0. 0.)4 0.29 0.36 0.43 M
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Technical Report TR-5364-3 Revision 0 4-94
~lILflINltINGsERYIcEs SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNIT l e SV NODIFI CATION TINE/FORCE TABLE 28. NAGHI TUDE AT NODE POINT T I NE 0 00 0.0T 0.14 0 21 0.2 0.36 0.43 l/)
ED I
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Technical Report TR-5364-3 Revision 0 4-95 LIILNNLING SERVICES SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNI T1 e SV HODI F I CAT ION TINE/FORCE TABLE -
- 29. MAGNITUDE AT NODE POINT 00 O.OF 0.14 0.36
Technical Report TR-5364-3 Revision 0 4-96 SAP2SAP VERIF I CAT I ON 5364
- 8) flItII N G SERVICES 6-JUL-83 DC COOK-UNI T ) . SV NODIF I CAT ION TINE/FORCE TABLE 30. MAGNITUDE AT NODE POINT 102 T I NE 0 00 O.OT O.l4 .2) 0. 0.43 0.50 lO Cl Ol I
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Technical Report TR-5364-3 4-97 Revision 0 NBNIItiG SERVICES O SAP2SAP VERIFICATION 5364 DC COOK"UNIT 1 e SV NODIFICAT IOH 6-'JUL" 83 TINE/FORCE TABLE 31. MAGNITUDE AT Nf'DE POINT T I HE
.0 O.OF 0.)4 '.ll 0. 9 0.36 0.43 O
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Technical Report TR-5364-3 4-98 Revision 0 lkfliNk'tNG sERYI GEs SAP2SAP VERIFICATION 536'4 6- JUL" 83 DC COOK-UHITI ~ SV NODIFICATIOH TINE/FORCE TABLE 32e MAGNITUDE AT NODE POINT T I NE 00 0.07 0 )4 02) 0 9 0.36 0.43
Technical Report TR-5364-3 4-99 Revision 0 SH(NING SERVICES SAP2SAP VERIFICATION 5364 6- JUL-85 DC COOK-UHI T i . SV NOD I F I CAT I OH TINE/FORCE TABLE 33 e NAGHI TUDE AT NODE POI HT T IVE O.OT 0.)4 0. 0 9 t'-4~ 0.50 tO ill I
CD O 0
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Technical Report TR-5364-3 4-100 Revision 0 SAP2SAP VERIFICATION 5364 NL8( I I N G SERV 1 GES 6-JUL-83 DC GOOK"UNI T1. SV NODIF I CAT ION T I HE'/FORCE TABLE 34 ~ NAGNI TUDE AT NODE POINT 184 IO CO PO o
CO T I NE 00 ~ 7 0- 1 0.29 0.36 0.50 QJM
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Technical Report 4-101 TR-5364-3 Revision 0 kkSkIIRG SERVICES SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNITt SV MODIFICATION e
TIME/FORCE TABLE 35 ~ MAGNITUDE AT NODE POINT t82 T INE 00 0. 1 0.29 0.36 0.45 0.50
f 0
Technical Report TR-5364-3 4-102 Revision 0 III4BNIING SERVICES SAP2SAP VERIF I CAT ION 5364 DC COOK-UHlTl SV MODIFICATION
~
TIME/FORCE TABLE 36e MAGNI TUDE AT NODE POINT hs.
CA Yl h
O CO TINE 00 0.2) 0-29 ~ 0.36 0.43
Technical Report TR-5364-3 4-103 Revision 0 I!IBII81INS SERVICES SAP2SAP VER IF'I CAT ION 5364 6"SUL-83 DC COOK-uNITi. SV MODIFICATION TIME/FORCE TABLE 3Te MAGNITUDE AT NODE POINT 1T6 CO Ol
~ 7 0.21 0.29 0.36 0.45 0.50 LLtcu Mcu
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Technical Repor t TR-5364-3 Revision 0 4-104 lN)IIIIIINGSERYICES SAP2SAP VERIF I CATION 5364 6" JUL-83 DC COOK UNIT 1 r SY HODIFI CATI"ON TINE/FORCE TABLE 38. MAGNITUDE AT NODE POINT Ol o
Cl CO T I NE cO 00 0 4 0.21 0 '9 0.36 0.43 le IO I
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Technical Report TR-5364-3 4-105 Revision 0 k@SNIING SERVI CEG SAP2SAP VERIFICATION 5364 6- JUL" 83 DC COOK-UN I T / e SV NOD IF I CAT ION TIME/FORCE TABLE 39 ~ NAGHI TUDE AT NODE POINT Cl 0) h CO 00 O. l 4 0-'2'l '.
TINE 29 0.36 0.43 lO I
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Technical Report TR-5364-3 Revision 0 4-106 84$ lf51NS SERV1CES SAP2SAP VERIFICATION 5364 6- JUL" 83 DC COOK-UHI Tl e SV NODIFI CATION TINE/FORCE TABLE 40 e HAGN I 7 UDE AT NODE POINT ')57 T IME 0 00 0. 0.14 0 2'I 0. 9 36 0.43 0 F 50 CD 0
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Technical Report TR-5364-3 4-107 Revision 0 IIILS(NING SERVICES SAP2SAP VERIFICATION 5364 6'-SUL "83 DC COOK-UNIT1 e SV NODIFI CATION TINE/FORCE TABLE 41 ~ MAGH I TUDE AT NODE POI HT 150 T INE 00 0.07 0.14 .36 0.43 0.50 IA Y7 ED I
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Technical Report TR-5364-3 Revision 0 4-108
@LANSING SERVICES SAP2SAP VERIF I CAT ION 5364 6- JUL-83 DC COOK"UNITl. SV MODIFICATION TIME/FORCE TABLE 42e MAGNITUDE AT NODE POINT TINE 0 00 0.07 O.l4 .2] 9 +36 0-43 C) 0 CV C9 lO LO I
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Technical Report TR-5364-3 4-109 Revision 0 8)5(IIRG SERVICES SAP2SAP VERIFICATION 5364 6"JUL"83 DC COOK-UNITt SV MODIFICATION e
TIME/FORCE TABLE 43. MAGNITUDE AT NODE POINT, 146 o
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Technical Report TR-5364-3 Revision 0 4-110 N)N/NING SERVICES SAP2SAP YERIF I CATION 5364 6-SUL-83 DC COOK-UNI T l e SY NODIFICATION TINE/FORCE TABLE 44'AGNI TUDE AT NODE POINT '44
... TINE 0.07 0.14 0-21 29 0.36 0.43 O.SO
Technical Report TR-5364-3 Revision 0 4-111
%8/NING sERYIGEs VERIFICATION 5364 6- JUL-83 'AP2SAP DC COOK-UNIT 1 e SY'ODIFICATION TINE/FORCE TABLE, 45'AGNITUDE AT NODE POINT h
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,TR-S364-3 Revision 0 4-112 Nlf(NIING SERVICES SAP2SAP .VERIFICATION 5364 6" JUL" 85 DG COOK UNI Tl r SV HODIFICATION TINE/FORGE TABLE 46'AGNITUDE AT NODE POINT 240 o
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Technical Report TR-5364-3 Revision 0 4-113 QBNIING SERVICES SAP2SAP VERIFI CAT ION 5364 6" JUL-83 DC COOK-UNIT) SV NODIFICATION e
TINElFORCE TABLE 4F'e MAGNITUDE AT NODE POIHT T I NE 00 7 0. i 0.2a 0.36 0.45
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Technical Report TR-5364-3 Revision 0 4-114 1)LfNNING SERVICES SAP2SAP VER IF I CAT ION 5364 6"JUL"83 DC COOK UNIT l r SV MOOIFICATIOtt TIME/FORCE TABLE 48'AGNITUDE AT NODE POINT CD h
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Technical Report TR-5364-3 Revision 0 4-116 lkiSlNIIIIG SERVICES SAP2SAP VERIFICATION 5364 6" JUL "83 DC COOK-UNITt SV MODIFICATiON TIME/FORCE TABLE e
'0e MAGNITUDE AT NODE POINT 225
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0 Technical Report TR-5364-3 Revision 0 4-117 N)SIIING SERVICES SAP2SAP VERIFICATION 5364 6- JUL-83 DC COOK-UN'I T1 ~ SV MODIFICATION
,- TINE/FORCE TABLE 5l . MAGNITUDE AT NODE POINT 222 Lll Ol CO 04 T I NE 0 00 0. .2l 0.29 0.36 0.43 O.SO'
Technical Report TR-5364-3 Revision 0 4-118 IIILHINIING SERVICES SAP2SAP VERIF I CAT ION 5364 6-SUL-83 DC COOK-UNI T1 e SV NODIF I CAT ION TINE/FORCE TABLE '52'AGNITUDE AT NODE POINT 214 CO T I NE 0 00 0.0 0.2) 0.29 0.36 0.45 0.50 O
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Technical Report TR-5364-3 Revision 0 4-119 N)INNING SERVICES SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNIT) SV MODIFICATION
~
TINE/FORCE TABLE 53 MAGNITUDE AT NODE POINT 208.
TINE 0 00 0.0 0.14 0 21 0.29 0 43 0 50 CO h
Technical Report TR-5364-3 Revision 0 4-120 NHIINIIRG SERVICES SAP2SAP VERIFICATION 5364 6-JUL"83 DC COOK-UNIT) SV MODIFICATION e
TIME/FORCE TABLE 54 e MAGNITUDE AT NODE POINT 298 Ol
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Technical Report TR-5364-3 Revision 0 4-121 NHNIIRG SERVICES SAP2SAP VERIFICATION 5364 6- JUL-83 DC COOK-UHI T ) o SV NOD IF I CAT ION TINE/FORCE TABLE 55 ~ NAGHI TUDE AT NODE POINT I NE o oo 0.21 0. 0.36 h
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Technical Report TR-5364-3 Revision 0 4-122
~IILfNNING SERVICES SAP2SAP VERI F I CAT ION 5364 6-JUL"83 DC COOK-UNIT1 e SV MODIFICATION TIME/FORCE TABLE 56 e MAGNITUDE AT NODE POINT h TINE 0 00 0 Ol 0.21 0. 29 0.36 0.43
0 Technical Report TR-5364-3 Revision 0 4-123 NH(hNING sERYIGEs SAP2SAP VERIFICATION 5364 DC COOK-UNITl SV MODIFICATION e
TIME/FORCE TABLE 57 e MAGNITUDE AT NODE POINT Ol Ol h
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Technical Report TR-5364-3 R'evision 0 4-125 NL'NN11NG sERYIGEs SAP2SAP VERIFICATION 5364 '"JUL"83 DC TINE/FORCE TABLE '9 COOK-UNIT ) e SV NODIF I CAT ION e NAGNI TUDE AT NODE POINT TINE 00 O-OT 0.1 0.2l 0.29 0.36 0. .50
Technical Report TR-5364-3 Revision 0 .
4-126 Bf@NS I NG SERVICES
'SAP2SAP VERIFICATION 5364 6-JUL"83 DC COOK-UNI T l e SV NODIFI CAT ION TINE/FORCE TABLE 60 e MAGNITUDE AT NODE POINT 60 lO o
T I NE CO 00 0.07 0.14 2l 0.2S 0.36 0.43 0.50 OJ
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Technical Report r TR-5364-3 4-127 Revision 0 NkfllNkING SERVICES SAP2SAP VERIFICATION 5364 6- JUL-83 DC "COOK-UNIT1 e SY MODIFICATION TINE/FORCE TABLE 61 e NAGNI TUDE AT NODE POINT r
,Ol CV TINE
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Technical Report TR-5364-3 4-128 Revision 0 6NNIING sERvIcEs SAP2SAP VERIFICATION 5364 6" JUL-83 DC COOK-UNIT1r SY NODIFICATIOH TINE/FORCE TABLF 62. NAOHITUOE AT HOOE POINT e 48 h
O O
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Technical Report TR-5364-3 Revision 0 4-129 llhjtNIING SERYICES SAP2SAP VER IF I CATION 5364 6" JUL-83 DC COOK UNI T l r SV fhODIFI CATION TINE/FORCE TABLE 63 ~ NAGNI TUDE AT NODE POINT IO Cb o
h tO CV TIME 0 00 0.07 0.2) 0 29 0 '3 rr 0
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Technical Report TR-5364-3 Revision 0 4-130 BANNING SERVICES SAP2SAP VERIF I CAT ION 5364 6" JUL "83 DC COOK 'UNIT1 ~ SV NODIFICATION T I t1E/FORCE TABLE 64. NAGN I T VDE AT NODE POINT..
T INE Q) 00 0.0 0.14 0. 1 0.2S 0.36 0-43 Oe50
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Technical Report TR-5364-3 4-131 Revision 0
@LSN31HG sERYI GEs SAP2SAP VER I F I CAT I ON 5364 . 6" JUL-83 DC COOK-UNI T1 e SV NODIF I CAT ION TINE/FORCE TABLE 65 e NAGNI TUDE AT NODE POINT T INE 00 0 0 0. I 4 0.21 0.29 0.56 0.43
Technical Report TR-5364-3 Revision 0 4-132 NB(Nfrws sEsvrcEs SAP2SAP YERIFICATION 5364 6"JUL-83 DC COOK-UNIT l . SV NODIF I CAT ION-T I NE/FORCE TABLE ~ 66 ~ NAGNI TUDE AT NODE PO I NT
' ooo 0.14 . 2l TINE 0.29 0.SS 0.43 ce N O@J 9 I
Technical Report TR-5364-3 Revision 0 4-133 l51583ING SERViCES
'l, SAP2SAP VERIF I CAT ION 5564 OC COOK" UNI T1 r SV MODIFICATION T'INE/FORCE TABLE 6-JUL-83 MAGNITUDE AT NODE POINT CO Ol T I NE 0 00 07 ~ l4 0. 0.29 0.36 0.43 Ol CO I
Technical Report A TELEDYNE TR-5364-3 ENGINEERINQ SERVICES
~ ~
Revision.O 4-134 Included here is the RELAP5 MODl input listing for the transient steam case.
The SV model has:
375 volumes 374 junctions Heat structures were not included in the RELAP model because of the
~
program capacity. Including heat structures would have further reduced the number
~
~
I of avail able control volumes. This is a conservative assumption, ITI (Reference 6)
~
~
~
~
s'howed higher loads were computed without heat structures.
~
.RELAPS 1~014 PEACTOR: Loss oF coot.ANT ANALYsIs PRoGRm LISTING OF INPUT DATA FOR O':QE 1 1 =D.C.COOK UNIT1 3 SV S OPEN 2 r DISCHARGE PIP!N<G
- THIS IS THE NiG):)BERING SYSTEM FOR UNIT1'S RELAP MOPFL 3
"-'"5 -"
4 4
'4 '"
WHERE COMPONENT:S,NUMBERED IN 100)s ARE VALVE SV-45C THE; AND ARC mD ARC
- 1. LEVEL '69~'-2>>"'"""""'
670'-10" 4 200'S ARE VAl VE SV-45B 2 LEVEL 6'n' 7 t 300 5 ARE VALVE SV 45A ARN ARC 3 LEVEL
>>A>>
672 O MO 4 40P)S ARE PORV NRV-151 AND ARC 4 500'S ARL= PORV NRV-153 AND ARC "8" 9 "C" CO
" 10 4 600'S ARE PORV NRV-152 AND ARC -"
ii" " *""'"""'"""""'700'SAND 800'S ARE 6>> AND 12>> MAIN DISCHARGE PIPING 12 4 900'S QUEENCH TANK PORTION 'O 13 4 999 ATMOBSPHERE 14 15
]6 NE'M TRAN ASNT 17 100 18 101 RUN 19 102 BRITISH BRITISH 20 104 NOACT ION 2i ttettttetrtteteett Getttfefttfttftfftffftttt 23 4 TIME STEP CCDNTROL 24 tttettttttttfttett 4444444feefttttt44444tttt 25 26 201 0. 500. 1. - . ~ "4, 11001) 5150) 250 27 28 29 eeeef erect trterrtt teeee44eeeeffetefetfefff t
E+ITS 30 31 4 MINOR etettteeittetetert<<tettfeeeeeeteetteffff fft
'332 34
" '* 301"'F'LOWJ 302 MFLOMJ 10fR&i0000 206~00 35 303 MFLOWJ 30600ippo 36 304 MFLO'MJ 3080)OPPQO.
37 305 MFLOMJ 2080)1100 38 306 MF LOWJ 702~00 39 307 MFLOXJ 1080)00000 40, 308 MFLONJ 9770)PPPOO 41 4 42 309 QUALS 1052)00000 43 310 QUALS 1070'Ppooo 44 311 QUALS 1073:80000 45 312 QUALS 70 10:10000 46 313 QUALS 811970000 314 8132)60000 47 48 . 315 OVALS QUALS 97818'0000 . .,CHKD,,,....BY ~A'pgT))),' Zp-gg 49 316 QUALS 2052~0 50 317 QUALS 2070 top 51 318 QUALS 305$ POOPO 52 319 QUALS 207260000 53 320 QUALS 3070 )POOP 54 321 QUALS 307180000 55 56 323 P 105ZPOOOO
I/O'l4 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 2 RELA 57 GQ4 P 107010000 58 ~6 P 107330000 59 3~7 P 701010000 60 3.'31 P 8 1 1970000 Bt 3:32 P 8 13260000 62 2.33 P 978020000
~34 'P 978030000 I 0
"---------'"-------~.Vl X 63 .
64 ~5 P 205200000 lA-GJ M 65 3:36 P 2070 f 0000 O MA BB %37 P 305200000 67 3:38 P 207260000 C) 68: ~9 P 307010000 sAO P 307180000 70 r 71
...7.2 r e t t tt t t t t f 't tf t r t t tftttt tt t t t f t t ff f tt tt
'"73 FORCE CARDS FOR REPIPE 74 r at t t tftt tfff t tf t f f t tff tft t f ftf f tftt tt t 75
'776 78 79 80 81 PIPING DOWNSTREAM OF THE PORV'S 82 83 2001 5, 215 84 2002 4 1 1010000! 4 1 1020000~ 4 1 1030000, 411040000, 411050000 85 2003 411060000 411070000, 411080000, 411090000, 411100000
~
86 2004 411110000, 411120000, 411130000, 411140000, 411150000 87 2005 411160000,411l70000,41!180000,4'l!!SOOOO 88 89 2006 51 1010000, 51 1020000, 51 1030000, 51 1040000 ~ 5!!050000 90 2007 511060000e 5!!070000,51]080000,511090000,511100000 91 2008 51 1 1 10000, 51 1 120000, 51 1 130000, 51 1 140000, 511150000 92 2009 511160000,511170000) 511180000,511190000 93 94 2010 611010000 611020000,611030000,B11040000,611050000
~
95 201 1 6 1 'l060000, 61 1070000, 61 f080000 96 r 97 2012 515010000,515020000,515030000, 0'l5040000,515050000 98 2014 5 15060000, 515070000 i 515080000, S 15090000, 515100000 99 2015 515110000,515120000,701010000,513010000 100 101 102 l03 r r
iO ELEVATION 672'"
104 105 SV ARC FROhl VALVE 45A bOWfl 106 107 2018 301010000, 303010000, 303020000,303030000, 303040000 108 2019 ... 305010000,305020000,305030000,305040000,305050000 109 2020 305060000,305070000,305080000,305090000,305100000 110 2021 .....3051.10000 305120000'05130000. 305140000r 305150000,....,.............,....,
~
111 2022 305160000, 30S170000, 305180000, 305190000, 305200000 112 2023- 307010000.307020000,307030000,307040000,307050000
- 113 2024 307060000,307070000,307080000,307090000,307100000 114 2025, 307 1 10000 307 120000t 307130000~ 307 140000t307150000
RELAP /014 REhlOTWR LOSS OF COOLANT ANALYSIS PROGRAM 115 2026 30716000>>.307170000,307180000,801010000 116 117 118 1'l9 fD -Ãt.A) 120 121 ~ t SV ARC FR(OH VALVE 45B DOWN TO ELEVATION 670'0" ~'l nK I
122 123 2029 201010100<0 203010000. 203020000, 203030000;203040000 o mn 124 203Q 205010f0010,205020000,205030000,205040000,2050500QQ I 125 2031 205080(00lp 205070000, 205080000, 205090000, 205 jppppp
~
CD 126 2032 205110>00lp 205120000,205130000,205140000,205150000
~
127 2033 205160lOOS>. 205170000,205180000,205190000, 205200000 128 2034 20701ptOOt0.207020000,207030000,207040000,207050000 129 2035 20708ONO<O 207070000, 207080000, 207090000, 207100000
~
1 10lOOtD. 207 120000i 207130000, 207 140000, 20? 150000
" 130 2036 " 207 j6ONOt0,207170000,207180000,207190000,2Q72QQQOQ 131 2037' 207 132 2p38 2072 10100(0, 207220000, 207230000, 207240000, 207250000 133 2p39 20726C'IOOlp, 805010000 134 135 136 137 138 139 14p t Sy ARC F~ VALVE 45C OOWN TO ELEVATION 669'"
141 142 2Q42 10101~<), 103010000$ .103020000, 103030000$ .103040000..
143 2043 10508JrA). 105020000, 105030000, 105040000, 105050000 2044 10506dr~, 105070000, 105080000, 105090000, 105100000
--" " 144 j45-' 'j051MrA, 105120000, 105130000, 105'l40000, 105150000 2@45 146 2046 1051~a 105170000, 105180000, 105190000, 105200000 147 2047 1070&/~ ~ 107020000, 'l07030000, 107040000, 107050000 107100000 10706WAH, 107070000, 107080000, 107090000, 148 j 49
" 2048 2P49 1Q71 MrÃrg, 107120000, 107130000, 107140000, 107150000 150 2050 10718K<>A). 107170000$ 107180000, 107..190000i 107200000 151 2051 j0721WA4 107220000, 'lp?230000. 107240000, j07250000 107280000,'107290000, 152 153 2P52 2053 10728CP<jt9, 107270000, 1073 1M'), 107320000, 107330000, 809010000 10730000P mH
~m 154 155 156 t 157 158 t 159 ttttittttttt PELAP trttttttttttttttttttttttitttttttttttttttttttttttttttt j6j"-gl'5 16Q RUN QF
~ ~
INCiUbES'S'AFETY" RELiEF "VALVE CiAES'ANO'NAiN ELEV. 684'-9" TO ELEV. 649'- 1/2" t LJlfE tttttttttttttttttttttttttttttttttttttttttttttttttt BETWEEN 162 163 tttttt$ ttttttt OISCHARGE
~ ~ ~
164 165 166 167 168 tfttfi'ettttt at ~ ~ ttttttttttttttttttttt'tt t t
169 17p t t t t et it t it t'tt it if it f if$ $ $
itit it tt t t TRIP%
~ ~ ~
171 172
G~S, -'OF COOLANT ANALYSIS PROGRAM RELAP yo'l4 REACTOR 0.0 L s VALVE OPENING TRIP 501 TIME 0 GF NULL 3 t i 5.0 L JOB TERMINATION TRIP 74 502 TIME 0 GE NULP t GE @NULL 0 1 14. 7 L WENCH TANK RUPTURE PRESS.
175 515 P 982Q1QQQQ 176 600 502, 177
- AGsstftftfssffffsssfsfsffffffs 178 r tssssrrrr sssssftsffsssssttrrrr--" >>Gtfftt'Stfttffftftffftff Sf Srrtr GP>> ~ =
' COMPONENTS KNthtt1 t 180 s
" s HYOROD sssssr rr>>
tssssssssf rr>>>>+ssftfsttttststfsttffst 181 182 s
sttstfttftstsssfts
~
ssssts rr<<
~ rr~ ~~sstttffttttftftfffsfffffffftffff 183 sf tsststss err ~ssf sf st ttfttttftftt sf f 185
- SAFETY VALVES ttftttstttsfftssssss>>
DI~~E SECTION
~ftttfffftffftttttttf 186 f tttssssss<<<<
187 188 189 f s r r <<>> a t t s f t t t ftftf t t s s s t. t ff ffftf t f s t tftftf t s t s f f r1,xriSCHARGING AT ELEV. 669'-2" ARC 191 t SAFETY VAj VE 1
s tf s ff s s t tt tfftff f f tf s fft t t t fft t ft tt t t f s f tft 192 ftstftftfststtttsr ~
193 194 t PRESSURIZER COJ4vW1ssNT "PRSRZ41", ~VPVOL 195 1010000 196 1010200 2
- 0. 0. 00005 0.
197 1010101 0. 20. 500.. 1,2514.,
- 0. 11 1..3,2555., 1..5,2600., 1 7 2667. 1.
- 0. 2500.. ~ ~
198 1010201 ~
2740 1 1 3 2745 i 1 5 2747 1 1 7 2748 99 1010202 9 2700 1 1 200 1010203 1. 9 2750.,
~
1 201 202 s PIPE COMPONENTS 203 1020000 "PRZ1-EXIT'LGJUN 1020101 101000000 %%~000 0.0 0.0 0.0 1QQQ 204 0.0 205 102020i 1 0.0 0 ~
206 207 s VALVE UPSTREAM 208 209 1030000 LS1 IN" 210 s NO. OF VOLS.
211 1030001 4 212 s VOL. FLOW AREA 4 213 1030101 0. 14653 214
- VOL. LENGTHS 2 i5 1030301 0. 3490 2 16 1030302 0. 4236 217
- VOL. CAL. AUTO 218 1030401 0.0 219
- VERT. ANGLES 220 1030601 45. 1 221 1030602 0. 0 222 t PIPE ROUGHNESS 0 4
- 1. 513-4 A'A 223 1030801 224 f GJUN. LOSS COEFF
- '25* '1O309Oi" O.O918 0
22B '030902 0.0 lg 227 4 228 1031001 00 h
229 230 1031101 1000 t
RELAP /014 REACTOR LGc'SS OF COOLANT ANALYSIS PROGRAN PAG 5 231 2500. 1 ,0.0,0 ~ 0 4 232 1031201 2 233 234 t INITIAL JUN FLO'MS 235 1031300 236 1031301 0.0 0.0 " '0 3 -RJM W 237 t CD WrD I
238
- LOOP SEAL SNGLJUN
~~V) ~
239 1040000 JUN-LS1" 240 1040101 1030'10000 105000000 0.0 0. 1836 0. 183B 1000 . e-Y.o 241 1040201 1 0. 0 0. 0 i 0. 0 QP 242 '*
243 1050000 LPSL 1 P IPE 244 1050001
- 0. 14653 20'45 1050101 O 246 t 247 1050301 0.50 248 1050302 0.6203 2<0 .
249 250 1050401 0.0 251 252 1050601 1050602 0 0 10 253 ~
"20 254 1050603 90.
255 256 1050801 1. 513-4 00. 0 20 257 258 1050901 0.0 CO 0 6
, W 1836 7 259 1050902 0. 1836 260 1050903 0.0 CP 0 . 9 261 1050904 0. 1836 CP. 183B 10 262 1050905 0. 0 cP. 0 19 263 264 1051001 00 265 266 10511O<<000 267 t
- 268 1051201 2 2500. ..1 ' 0.0 0.0 20 269 270 271 1051300 1051301 0. 0 0. 0 r0 0
~ 19 p ITl I 272 273 t CROSBY BNB MFETY VALVE kf SV-45C" .Qg 274 t VALVE OPEN I/iTH PROG. START" 275 1060000 "SVN01" V.'ALVE 276 1060101 105010000 107000000 0. 01897 0. 0 0. 0 0100 1. 0 1. 0 277 1060201 1 0.0 P 0 0.0 278 1060300 NTRVLV 279 1060301 501 505 '100. 0.0
- VALVE Of'ENS QITH PROG. START 280 281 i 'ALVE"OKNSTRM/ OOWNSTR~ "
PIPING PIPE 282 1070000 <
283 1070001 33 t 33 285 1070101 0. 20069 285 287 - 1070301 0. 5261 288 , 1070302 0.9943
COOLANT ANALYSIS PROGRAM RELAP ii014 REACTOR l.OSS Us 289 1070303 0. 9132 290 ...1070304 0.8472 30 291 1070305 1.085 292 293 1070401 0.0 294 295 1070601 0. 0 296 1070602 -90 297 1070603 0.0 298 "P 299 1070801 1.52-4 0.
300 1070901 0.0 0.0
- 0. 18- 4 301 1070902 0. 18 'l4 302 1070903 0.'0 0. 0
- 0. 18 15 303 1070904 0. 18 32 304 1070905 0. 0 0. 0 305 306 107 1001 00 33 307 1071101 1000 32 308 '!20 '- 0 93424 309 1073201 4 17.7 310 311 1071300 1 3'l2 107130'1 0.0 0.0 0.0 313 314 315 316 i'tijtjtiDIS ~GING
~ << -t it*titiiitiitititttttittttjitiiitttjtj 670'"10" 318 jtiifif fiitj ifif<<ijtfit<<+> itttttttttittttttittttttitttttjtjifttifi SAFETY VALVE N2 AT ELEV. ARC 2 319 COMPOltlTtN
'2320 1
- PRESSURIZER 2plp'000
- <<PRSRZ<2 T~ VOL 322 O. 0. 0.00005 0.
323 2010101 0. 2p. 500. 0 1'j'24
"" 2010200 "" 02 25pp. 1. .: '740.
4 ~ , ~ 3,2555., 1 ~ 5,2600., 1. .7,2667.','f:
2pj02pj i 1. 1. 3, 2745., 1. 1. 5, 2747., 1. 1. 7, 2748. 1.
. 9, 2700., 1.
p 326 2010202 1 327 2010203 1. 9,2750., 1.
328 329
- PIPE COMPONENTS <<jeGLdUN 330 2020000 "PRZ2 EXIT" 331 332 2020101 201000000 20 ~00 0.0 0. 0 0. 0 1000 333 334 2020201 1 0.0 0.0 335 336 j VALVE UPSTREAM "LS2 IN" 33i 2030000 338
- Np OF VPL.
339 2030001 4 340
- VOL. FLOW AREA 341 2030'lp { 0. 14653 4 342 j VOL LENGTHS 343 2030301 0.3490 1 344 2030302- 0.4236 4 345 t VOL. CAL. AUTO.
346 2030401 0.0 4
ANALYSIS PROGRAM PAG 7 RELAP /014 REACTPR LOSS OF'.<<ODLANT 347 i VERT. ANGLES 348 2030601 45.
349 2030602 0. 4 350 PIPE ROUGHNESS 351 2030801 1.513-4 0.0 352 JUN LOSS COEFF.
353 203090{ 0. 0918 .0. 0918 354 2030902 0.0 0.0 355 356 2031001 00 4 357 358 2031 101 1000 3 359 0. 4 360 2031201 2 2500.
361
- INITIAL JUN. FLOWS 362 2031300 1 363 2031301 0.0 0.0 0.0 364 365
- LOOP SEAL 366 367 2040000 "JUN-LS2" 2040101 203010000 2050hKPA70 0.0 0. 1836 0. 1836 368 369 2040201 1 0.0 0.0 370 371 2050000 "LPSL 1" PIM
, 372 2050001 20 373 374 2050101 0. 14653 20 375 376 2050301 0.50 10
= 377 2050302* 0.6203 20 378 379 2050401 0.0 20 380 381 2050601 -90. 7 382 2050602 0.0 10 383 2050603 90. 20 384 385 2050801 1. 513-4 0. 20 38B 387 2050901 0.0 0.0 388 2050902 0. 1836 0. 18M 389 390 391 392 2050903 2050904 2050905 i
0.0
- 0. 1836 0.0 '.0 0.0 0.
20 182@
393 2051001 00 394 395 2051101 1000 - 19 39B ~
1.0 0.0 0.0 20 397 2051201 2 2500.
398 i INITIAL JUN. FLOWS 399 2051300 1 400 2051301 0.0 0;0 0.0 !9.
401 SV-456 402 i CROSBY 6MB SAFETY VALVE ~2 403 404 2060000 "sv N02 VALVE CO%1
RELAP 1/014 REACTpR LOSS pF:'OOLANT ANALYSIS PROGRAM P Al 2p5010000 2070~~0 0. 0189? 0. 0 0. 0 0100 1. 0 1.0 408 2p60101 2060201 1 0.0 0,0 0 ~ 'i 407 2060300 MTRVLV 408 2060301 ,501 502 100. 0.0 VALVE OPEN WITH PROG. START 409 410
- VALVE DOWNSTREAM PIP!N+I 411 2070000 "DWNSTRMiY2" P IP+." 0
~ ~--- . --
~ ~ ~ ~ - ~" CA V 412 207000 'I 26 4 13 414 2070101 0. 20069 26 ~ -- - --- '-- = o- TI o 415 O*- .~
416 2070301 0. 5261 4 ~ ~
417 2070302 0. 9271 14 418 2070303 0.8852 23 419 2070304 1.085 26 420 421 2070401 0.0 26 422 423 2070601 0.0 4 424 2070602 -90. 14 425 2070603 0.0 26 426 427 2070801 1.52-4 0. 2<.
428 429 2070901 0.0 0.0 430 2070902 0. 18 0. 18 .. 4.
431 2070903 0.0 0.0
- 0. 14 432 2070904 0. 18 -
18 433 2070905 0.0 0.0 434 435 2071001 00 26 436 437 2071101 1000 25 438 0 93424 0 26 439 2071201 4 17.7 120. ~
440 441 2071300 1 442 2071301 0. 0 0. 0 0. 0 443 444 tttttttttttttttttttttttttttt>ttttttttttttttttttttttttttttttttt tttttt 445 AT EL'EV. 672 i Bn SAFETY VALVE g3 Df~GING ARC 3 44B - t'tttttfttttttttttttttttttgtttttttttttttttttttttttttttttttttttt tttttt 447 448 449 t PRESSURIZER CO'MPONffff 450 3010000 "PRSRZP1" TMDf !OL 451 3010200 2 3010101 0. 2p. 5pp. 1,'i614 0, 0. 0. 0.00005 0.
452 453 3010201 0..2500.,1.. ~ 1 ~ .3.2555..1..5,2600.', f"."'" 7 2667., 1.
454 30'l0202 .9,2700. 1. 1. 1,,$
~
740., 1. 1.3,2745., 1. 1.5,2747.q 1. 1.7,2748., 1.
455 3010203 1.9,2750., 1.
456 t PIPE COMPONENTS
-'"3020000--" -"P'RZ3'XIT" 5f jCilalUN 457 0.0 0.0 0.0 1000 458 302010'1 301000000 30309Q000 459 460 3020201 '1 0.0 0.0 P.U 461 t VALVE UPSTREAM 462
RELA 1/014 REACTOR LOSS OF O'ODLANT ANALYSIS PROGRAM PAG 463 3030000 "LS2 IN" PIPE 464 t 465 3030001 4 4ee 467 3030101 0. 14653 4 468 t 469 303030 I 0. 3125 (D M(D 1
I o 470 3030302 0.4236 4 'Vl'K 471 lh 472 3030401 0.0 4 a-wo 473 1 474 3030601 45. 1 'C7 475 3030602 0.0 4 (b
476 '
477 3030801 1 '13-4 0.0 478 'C 479 3030901 0.0918 0.0918 1 480 3030902 0.0 0.0 3 481 482 3031001 00 483 t 484 3031101 1000 3 485 486 3031201 2 2500 1. O.O 0.0 4 487 t 488 3031300 1 489 3031301 0.0 0.0 0.0 490 "4S1 3040000 "aJUN-LS3" SNGLdlW 492 '3040101 303010000 305000000 0.0 0. 1836 0. 'l836 1000 493 3040201 1 0.0 0.0 0.0 494 495 3050000 "LPSL 2" PIPE 496 3050001, 20 497 t 498 3050101 0. 14653 20 499 500 3050301 0.5 10 501 3050302 0.6203 20 502 503 3050401 0.0 20 504 505 3050601 -90. 7 506 3050602 0.0 10 507 3050603 90. 20 508 509 3050801 1.513-4 0.0 20 510 t 511 3050901 0.0 0.0 6 512 3050902 0. 1836 0. 1836 7 513 3050903 0.0 0.0 9 514 3050904 0. 1836 0. 1836 10 5'IS 3050905 0.0 0.0 19 516 517 3051001 00 20 518 t 519 305110'000 19 520
REACTOR LOSS OF COOLANT ANALYSIS PROGRAM 10 RELA 1/014 521 3051201 2 2500. 1.0 0.0 0.0 20 522 523 3051300 1 524 3051301 0.0 0.0 0.0 19 525 e 526 e CROSSBY 6M6 SAFETY VALVE l'3 SV-45A 527 528 3060000 .".SV N03" VALVE t '".
VALVE OPEN WITH PROG. START 529 3060101 305010000 307000000 01897 0. 0 0. 0 0100 1.
530 3060201 1 0.0 0.0 0.0 0 .W.O 1
531 3060300 MTRVLV 532 3060301 501 502 100. 0.0 t VALVE OPENS WITH PROG. START 533 534 e VAL'.VE DOWNSTREAM PIPING "3p70ppp "DWNSTRMP3e PIPE 536 3070001 18 537 538 3070101 0: 20069 18 539 540 3070301 0 5261
~ 4 541 3070302 1.034 12 542, 3070303 0;801 15 543 3070304 1.085 j8 544 545 3070401 0 0~ 18 546 " "'"' " '""""""' "'--------'"--""---"---""-"'"-'-"---*" .."-- -- ---- --
~ ~ ~ - ~ ~ ~ - ~
547 3070601 0 '0 4 548 3070602 -90. 12 549 3070603 0.0 18 5 50 t 551 3070801 1 ~ 52 4 0. 18 552 553 3070901 0.0 0.0 3 554 3070902 0. 18 0. 18 4 555 3070903 0.'0 0.0 11 556 3070904 0. 18 0. 18 12 557 3070905 0.0 0.0 17 558 t 559 3071001 00 18 560 307 1 101 1000 17 561 562 3071201 4 17.7 120. 0.93424 0. 18 563 564 307 1300 0.0 0.0 0.0
" """ j7'"""------'-"""
565 3071301 5 e 567 568 eteteeeeeeeettttetttettttttetttttttttttttttt "569 g54V DISCHARGE SECTIpN tete eeet ee eeet ettttettittttttfttfeeet tttf tet e
57p 571 573 2
t t e f f e e e e e e e e e t tt tt f et et t t etc tet t tt et tet et et et t tete 'et POR~/ NRV-151 DISCHARGE LINE ARC "A" 574 575 e
ieetteee ~ eetettetttet\ttttttettttttttttt'etttttftttttt 576 577 ~
578 4110000 "PORV1" PIPE
RELA 01/014 REACT:10R LOSS OF COOLANT ANALYSIS PROGRAM 579 4110001 19-580 581 4110101 0.054132 17 582 4110102 0. 200989 'l9 583 584 4110301 0. 372', ....4. --- - - - Cb. ~.AD C I 0
~ ~ ~
585 4 i 10302 0. 3859 8
- 0. 581,, 1'7 ~ Vl&
586 4110303 ~ ~ - ~ ~ 4(i -M,W 587 4110304 0.349 19 0 WO
, 588 ~ -I- Dl 589 4110401 0.0 19 590 591 4110501 0.0 4 592 4 1 10602 -90. 8 593 4110603 0. 0 19 594 595 4110801 1. 53- t4 . 0. 17
.. 596 4110802 1.52-=4 ~ 0 19 597 598 4110901 0 0 0 0 3 """"
- 0. 2088 '4 599 4110902 0. 20848 600 4110903 0.0 . 0.0 7 601 4110904 0. 20848 0. 2088 8 602 41 10905 0. 0 0. 0 16 603 4110906 0. 378@4 0. 1565 "'j7'04 4 '1 10907 0. 0 0.0 18 605 606 4111001 00 19 607 4111101 1000 18 608 609 4111201 4 1 7 7
~ 120. 0. 93424 0. 0'""'""j9" 610 611 4111300 1 612 4111301 0.0 rO 0 0.0 18 613 "ENrd+MAIN" SNGL JUN 0.0 0'.-j8'P." j'8'000 614 4120000 615 41201014110.~00 701000000 616 4120201 1 (P-0 0. 0 0. 0 617 619 8
ttttttttttttttt stttttttttttttttttftttttttttttttttttt 620 t PORV NRV-103 DISCHARGE LINE ARC "6" 621 titteettattttr<+tttttttttttttttttttttttttttttattttett 622 623 624 625 5110000 "PONl2L INE" PiPE 626 5110001 19 627 628, 5110101 0.05132,, 18 629 5110102 0. 08i840 19 630 631 51'l0301 0. 4:W3 3 632 5110302 0.3620 7 633 5110303 0. 35 9 634 5110304 0 6098 18 635 5110305 0. 371 19 636
PAG 12 RELAPSE I/014 REACTOR: ~OSS OF COOLANT ANALYSIS PROGRAM 637 5110401 0.0 19 638 639 5110601 0.0 3 640 5110602 -90. 7....
641 5110603 0. 0 19
Ã7, M.W 642 643 5110801 1.53-4 .0 644 5110802 1.34-4 .0 19 645 O WO 0.0 2
'47"-" 5110901 646 5i10902 0.0 0.2088 0 '088 0 0.
3 6 ,, C) 648 5110903 0.0 649 5110904 0.2088 0 2088
~ 7 650 51 10905 0. 0 0 '0,
~ 17 -o O
651 5110906 0.0544 0.0399 j8'52 653 5111001 00 19.
654 t 18 655 5111101 1000 656 120. 0. 93424 0. 0 19 657 51 1 1201 4 17 7 658 659 5111300 1 660 511'130'1 0. 0 0. 0 0.0 18 jVH 661 662 5120000 "JUNC " SNGL JUN
'"p. 0 663 5120101 5110100003 51300000p 0. p 0. 0 1000 664 5120201 1 0.0 (P 0 665 666 C 667 668 5130000 "4X4X3TEE"-
669 5130001 0 670 5130101 0.08840 0.3524 0.0 0.0 0.0 0.0 1.34-4 0.0 Pp 17.7 120. 0.93424 0.'0 67' 5130200 4 "0.'0'72 673 5140000 "4 IN JOHS" SNGL JUN 674 5130iOONP 515000000""
0.'0" 0 0 "p 0.0 8 0 0-0 ~.m 676 .
5140201 677'"""'i""-"" 1 "4INSCK4+" PIPE a~.m.
678 679 5150000 5150001 12 ZO Pl 680 10 681 5150101 0. 0884 682 5150102 0. 20069 12 Rim 683 684 5150301 0. 3524 1, 5150302 0.6963 10 685 12 686 5150303 0. 349 687 688 5150401 0. 0 689
, 690 5150601 0.0 691 692 5150801 1.34-4 0;0 10 693 5150802 1.52-4 P 0 12-694
REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PA 13 RELAP 4/0)14 695 0. 0 0.0 696 5".509902 0. 1483 0. 0815 697 51509803 0.0 0.0 698 t 699 5 -5 i:O01 00 12 700 701 5;5) 1101 1000 11 702 703 515t2201 4 17.7 120. 0.93424 0.0 12 o Ro 704 705 < 1512800 C) 706 301 0.0 0.0 0.0 11 707 t 708 0"000 "ENTERMAIN" SNGLalUN 709 5160t101 515010000 701000000 0.0 0. 18 0. 18 3000 710 51602201 1 0.0 0.0 0.0 711 712 713 f ft'%ttttttttttttttt tftttttttttttttttttttttttttttttt
~
752'.1509901 RV NRV-152 DISCHARGE LINE ARC "C" 714 715 tttyaattttftttttttttetttttttttttttttttttttttttttttttt 716 t 717 718 719 611OMO "PORVDISC3" PIPE 720 61<0~1 8 721 t 722 g 11< i101 0. 05132 8
" 723 .
724 611>@01 0.3723 4 725 g11~02 0. 3646 8 726 727 61 1~01 00 8 728 e 729 61 iry601 0. 0 4 730 61 141602 -90. 8 731 732 611rJN01 1.53-4 .0 8 733 734 61 A%01 0. 0 0. 0 735 611M02 0. 2088 0. 2088 4 736 61M%03 0.0 0.0 737 738 611 0001 00 6 1 1 9101 1000"'
739 740 741 1 [ 5201 4 17. 7 120 ~ 0. 93424 0.0 8 742 743 611 ti 300 1 744 611 5301 0.0 0.0 0.0 7 745 746 6124900 "PORVLINE" SNGLJUN m 747 61/0101 611010000 513000000 0.0 0.1932 0.1932 1000 748 6120201 1 0.0 0.0 0.0 749 750 ~ t f Otttttttttftttttttttttttttttttttttttttt HAIN DISCHARGE LINE SECTION 751 e
~ f+ f tttttttttttttttttttttttttttttttttttttt
RELAP /014 REACTpR LpSS pp CCOOLANT ANALYSIS PROGRAH PAG 14 753 754 755 < HAIN DISCHARGE LINE 756 7010000 "ENTERHAIN" BP~CH 757 7010001 0 758 7010101 0.20069 0.7035 0:0 12P'.0.93424 0.0 0.0 0.0 1.52-4 0.0 0.0 0.0 00 759 70'l0200 4 17 7 760 761 7020000 ""HAINLINE4 SNGLUUUN 762 7020101 701010000 7030006000 0. 0 0. 0 0. 0 1000 763 7020201 1 0.0 0.0 0.00 764 765 7030000 "MAINLINE" PIPE 766 767 7030001 14 768 769 7030101 0.20069 'l2 77p 7p30102 p.777p8 14 t 112 IN LINE STARTS HERE 771 772 7030301 0.7035 1 773 7030302 1.0076 12 774 7030303 0.5834 14 ~ .12 IN LINE STARTS HERE 775 776 7030401 0.0 14 777 i 778 7030601 0.0 1 779 7030602 -90. 14 780 781 7030801>> 4'1.52-4 0. 12 782 7030802 1.69-4 0. 14 783 784 7030901 0. 180 0. 180 785 7030902 0.0 0.0 786 7030903 0.493 0.2045 787 7030904 0.0 0.0 13 788 789 7031001 00 *14 790 7031101 1000 13 791 792 7031201 4 17. 7 120. 0;.93424 0 0 '14 793 794 7031300 1 795 7031301 0.0 0.0 0.0 796 797 798 7040000 "HAINLINE" SNGL~ ............,..........
799 7040101 703010000 801OCt9000 0 0 0 0 0 0 1000 800 7040201 1 0-0 0.0 P.P 801
$ 02 3080000 "CON. 1" SNGLJUt~ 0.'156'ppp'""-'"
803 3080101 3070100pp 8p1000000 0.0 0. 156 '--'04 3080201 1 0.0 0.0 0, 0 805 806 807 808 809 672'-6" 810 CONNECTION TO HAIN LEONE AT ELEV.
RELA 1/034" REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAt 15 811 812 813 8010QW>0 ."12-BRANC1" BRANCH 814 Sp ipon~1 ...., 0.
815 8010'" 41 0.77708 0.8334 0.0 0.0 -90. -0.8334 1.69-4 0.0 00 816 80102000. 417.7 120. 0.93424 0.0 0.0 8'17 'C I A 818 80200000 "MAINLINE" SNGL JUN ~ Vl&
819 Sp201C01 801010000 803000000 0. 0 0. 0 0. 0 1000 Es cil w 820 80202101 1 0.0 0.0 0.0 ,.0...4 ..O I QP 821 822 803~00 "MAINLINE" SNGLVOL 823 8p30 ~gp1 0. 77708 0. 8334 0. 0 0. 0 -90. -0. 8334 1. 69-4 0. 0 00.
824 80302iop.,.
t 4, 17. 7 120. 0. 93424 0.0 0.0 .... ~ ...-. 'n O
825 826 CONNECTION TO MAIN LINE AT ELEV. 670'-'10" 827 828 829 80400~ "MAINLiNE" sNGLJUH 830 8Q4Q1r01 803010000 805000000 0. 0 0 0 0. 0
~ 1000 831 80402W1 1 0.0 0.0 0.0 832 *
- 833 20800~ "CON.2" SNGLJUN 834 20801rP1 207010000 805000000 0.0 0. 156 0. 15B 1000 835 2pspjcD1 1 0.0 0.0 0.0 836 837 80500~ "HAINBR.3" BRAIvcH 838 8050&P1 ....,0...,........
839 80501i91 0.77708 0.8334 0.0 0.0 -90. -0.8334 f.69-4 Q.o 00 840 80 4 17.7 120. 0.93424 0.0 0.0 841 842 806(gpQO "MAINLINE" SNGLJUN 843 SP601+1 805010000 807000000 0.0 0.0 0.0 1000
'44 8060~~1 1 0.0 0.0 0.0 845 t 846 807~
80701r'01 "MAINLINE" SNGLVOL
- 0. 77708 0. 8334 0. 0 0. 0 -90. -0. 8334 1. 69-4 0. 0 00 847 848 8070~ 4 17.7 120. 0.93424 0.0 0.0 849 t 850 851 ONNECTION TO HAIN LINE AT ELEV. 669i-2" 852 853 854 855 808~
spSQ 1'01 "MAINLINE" SNGLJVM 807010000 809000000 0. 0 0. 0 0. 0 1000 856 '"
857 Bosom'01 i o.o "o.o '"o.o 858 859 108(Y~ "CON.3" SNGLJUN 860 1080 $ 01 107010000 809000000 0. 0 0. 156 Q. 156 1PPP 861 1080101 'I 0.0 0.0 0.0 862 863 809<PA+ "MAINBR4" BRANCH 864 8090<1 0 865 8090)01 0.77708 0.8334 0.0 0.0 -90. -0.$ 334 1 67-4"" p.p-'"'0'0'"
866 809 C400. 4 17 7 120 0 93424 0 0 0 0 867 t 868 8100000 "HAINLINE" SNGL JUN cr<<
REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 16 RELA 1/014 869 8 100101 8 a09010000 81 1000000 0. 0 0. 0 0. 0 1000 870 8100201 0.0 0.0 0.0 871 872 873 81 10000 '-'MAINLINE" PIPE 874 lD Kl lb 875 8 10001 97 I 0 Vl ~
1 876 l/l 877 8110101 .77708 97 878 t O WA 879 8110301 1
..O'149 14 1 AP 880 8110302 0~.5303 18 C) "-
881 8110303 00.5 22 tb 882 8110304 0' 53125 26
~+.9908 56 O 883 8 110305 884 81 10306 0 ~ 5,, 64 885 8110307 00. 8750 72 886 8110308 (P 5104 80 887 8110309 (P. 4993 88 888 81 10310 1 .0556 97 889 t 890 81 10401 O.o 97 891 892 8110601 --90. 14 "
893 8 1 10602 --45. is 894 895 8110603 8 1 10604
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'622 56 896 8110605 897 8110608 (P.'0 80 898 8110607 - 88 899 8110608 d>.0, 97 900 t 69-4 0". 97 901 8110801 11 ~
902 903 8110901 0.0 13 904 905 8110902 8110903 (P.078 (Po 0.078 00 '714 908 8110904 g 078. , 0. 078 18 4)0 00 21 907 908 8110905 8 1 10906 (P.078 0.078 22 mm IZ 909 8 1 10907 (9.0 0.0 25 910 8110908 (P.078 6).O 0.078 0.0 26 55
@m 911 8110909 912 8110910 P. 156 0. 158 56 913 8110911 io.O 0 0 63 P.026 0.026 64 914 8110912 P.o 0.0 mm 915 916 8110913 8110914 8110915 P.
IO.O 13 0. 13 0.0 71 72 79
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917 918 8110916 8110917
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"'----.- - 0m 926
C 1c
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RELA 1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PA 17 927 8111201 4 17.7 120. 0.93424 0.0 97 928 929 8111300 1 930 8111301 0.0 0.0 0.0 96 931 932 X7 lD
'"'MAiNOiSC=" SNGLi/UN
~ ..CJl 0 933 8120000 934 8120101 81 10100049 813000000 0. 0 0. 156 0. 156 1000 2 935 8120201 1 0. 0 0. 0 0.'0 Ul Ql ~
936 .O... W.O 937 8130000 "MAiNLiNEt" PIPE I CA
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- 0. 0
-90. '624 951 952 8130801 1. 69-4 0. 26 953 954 8130901 0.0 0.0 13 955 8130902 0. 156 0. 156 14 956 8130903 0. 0 0.0 23 957 8130904 0. 156 0. 156 24 958 8130905 0.0 0.0 25 959 960 8131001 . 00 26 961 962 8131101 1000 25 963 964 8131201 4 17.7 120. 0.93424 0.0 26 965 966 8131300 '25 967 8131301 '0.0 0.0 0.0 968 969 t tt t t t t t t t t t t t t t t t tt t t't tttt t t tt t t tt 970 97 1
~ 'ttttttttttttttttt 972
- QUENCH TANK 973 ttttttttttttttttt 974 975 97B 977 9770000 .QTANK-ft1" SNGLJUW'78 9770101 813010000 978000000 0. 0. 0. 1000 979 9770201 1 0. 0. 0.
980 981
- SPARGER 12 fN SCH40 PiPE 982 983 9780000 "SPARGER" PIPE 984 t NO OF VOLUMES
COOLANT ANALYSIS PROGRAM PA 18 REf Ap 1/014 REACTpR 1.OSS gs 985 9780001 18 986 t FLOW AREA 987 9780101 0.7773 18 988
- t VOL..LENGTHS 989 9780301 1. 125 2 990 9780302 1. 1333 7 CD MA>
991 9780303 1.0 18 1 O 992 t VOL. VOLS. C/l 993 9780401 0.0 18 W 0 994 t 1 Ql 995 t VERTICAL ANGLES 996 9780601 -90. 7 997 9780602 0.0 18 998 t PIPE* ROUGHNESS 999 9780801 1. 69-4 0. 0 1000 t JUNCTION LOSS COEr s 0.0 0. 0 6 1001 9780901 1002 9780902 0. 156 0. 188,.....,..?...,.
1003 9780903 0. 0 0. 0 1004 t VOL. CONTROL FLAG 1005 978 1001 00 18 1006 t JUN. CONTROL FLAG 17 1007 9781101 1000 1008 t INITIAL COND.
1&a O.S3424 0. ""2" 1009 9781201 4 17.7 20 0. 0 0. 18
'NITIAL ~~'.
1010 9781202 3 17. 7 1 .
'1011 '" t" " -"-'-JUN 1012 9781300 1 10'13 9781301 0. 0 0. 0 0, G 1014 t SPARGER EXIT 1015 9790000 "EXIT" SNGLJUN 9w~p0000 0. 0 1. 0 1. 0 11pp 1016 9790101 978010000 1017 9790201 1 0. 0.
1018 t QUENCH TANK 1019 1020 t WATER VOL.
"QT. WATER" Sl4%, Vpi 1021 1022 9800000 9800101 260.4706 5.~7120 0,0 0.0 90. 5.6667 p.pp3 0.0 01 1023 9800200 3 17.7 1024 t INTERFACE "INTERFACE" 1025 1026 9810000 9810101 980010000 982~0 o 0 0. 0 0. 0 1000 1027 9810201 1 0.0 0. 0 'P.P 1028 t AIR VOLUHE 1029 9820000 "QT.AIR" SNGLML 0. pp3 p p p1
- 0. 0 0. 0 90. 1. 2439 1030 9820101 260. 4706 1. 24 P9 ...
- 0. 93424 1031 9820200 4 17. 7 1?4 1032 1033 t RUPTURE DISC VAL-VE 1034 9830000 "RUP.DISC 0. 1100 982010000 99S%XNOO 1 ~ 77 0 1035 9830101 1036 9830201 1 0. 0.
1037 9830300 TRPVLV
~ VALVE OPENING TRIP 1038 9830301 515 1039 ttttttttt'tt-----'"------'--------------. --....,.
1040 ttttt tttttttttttt t it t t t t t ttt 1041 1042 t PIPE
~
OUTSIDE ENVIROMENT t
k l.
II II I
I
RELAP 1/014 REACTOR LOSS OF , OPLANT ANALYSIS PROGRAM Pn 19 1043 t ttt tt t't t t t t t t t t*tt t tt tt f t + <At t t tt t tt t tt f 1044 1045 TMNOPVOL gggplpj"-'p'pp'p ""-" jpppp 1046 9ggpppp <<ATMOSPHERE<
1047 0.0 0.0 0.0 0.0 .00001 0.0 11 1048 9990200 4 1049 9990201 0 0 14 7 120. 0 9284 1050 1051 1052 t tt t t t ttt t t t t t t ttt t t tt ttte t > t t t ttt tttttt 1053 1OS4 *ttttttttttttttttttttttff+Okttttttttttttt PLOT CARDS 1055 t 1056 1057 20300100 MFLOKJ 10600000ll-1058 20300200 MFLOWJ 20600004>-
1059 20300300 MFLOWJ 30600004il"-
1060 20300400 MFLOWJ 30800004~.
1061 20300500 MFLOWJ 20800004<.
1062 20300600 MFLOWJ 70200000<.
1063 20300700 MFLOWJ 10800004<
1064 20300800 MFLOWJ 97700000'W.
1065 20300900 QUALS 1052000lT~
1066 20301000 QUALS t0705000<-
1067 20301100 QUALS 1073300( ~
1068 20301200 QUALS 70101004~
1069 20301300 OVALS 8 1 197000~
1070 20301400 QUALS 813260~
1071 20301500 QUALS 978 1804~
1072 20301600 QUALS 205200~
1073 20301700 QUALS 207010~
1074 20301800 QUAl.s 30520~
1075 20301900 QUALS 20726066+
1076 20302000 QUALS 30701~
1077 20302100 OVALS 307180&&
1078 20302300 P 10520CKK+
1079 20302400 P 'l0701(RH+
1080 20302600 P 10733065+
1081 20302700 P 70101~
1082 20303100 P 81 197CKYr'+
1083 20303200 P 8 13260Ci A 1084 20303300 P 9780200%
1085 20303400 P gi80304 W 1086 203O3SOO P Z0520pp,r9 1087 20303600 P. 2070100,+
1088 .20303700 P 305200Cr,'W 1089 20303800 P 20726~
1090 20303900 P 109 '1 P 307 3070100A'0304000 180' 1092 1093 t 1094 1095 1096 END OF CASE
Ph TELEDYNE Technical Report TR-5364-3 ENGfNEERING SERVlCES .
Revision 0 4-154 4,8 ~PI E These are input listings of Control Data Corporation's RELAP post-processor, REPIPE. Each set represents direction cosines of the RELAP model as well as structural node assignments. Og the Unit 1 SV model, it was necessary to break up the model in two sections, of approximately equal size, because of REPIPE's size limitations.
~In ut Set Model Section 4.8.1 4.8.2
0
-~>-TELEDYNE Technical Report ENGINEERINQ SERVICES TR-5364-3 Revision 0 4-155 4.8.1 REPIPE In ut - Section A
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Technical Report A TELEDYNE TR-5364-3 ENGINEERINQ SERVICES
~ ~
Revision 0 4-161 4.8.2 REPIPE In ut - Section B
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SSTEPS TSTEP( 1)~0.001,0600,- 1 '1$
Technical Report
-s>-TELEDYNE TR-5364-3 ENQINEERINQ SERVICES 4 l69
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Revision 0 4.9 APPENDIX A
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