ML17324B005: Difference between revisions
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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. | 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. | ||
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0 A TELEDYNE ENQiNEERINQ SERVlCES 4-6 BY ~AM OATE ~ Z'OMAL'6 C. Oc",g SHEET HO. 0F & | 0 A TELEDYNE ENQiNEERINQ SERVlCES 4-6 BY ~AM OATE ~ Z'OMAL'6 C. Oc",g SHEET HO. 0F & | ||
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=VC;,NEERIVG S | =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~ | ||
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4-'I 54 Technical Report TR-6364-2 Revision 0 7C", gvqg ENQ: 'uEE~ HG -=RV j ~ES | 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 | ||
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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 | 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 | ||
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Technical Report 4-186 TR-5364-2 | 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 | ~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 | ||
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4-187 Technical Report TR-5364-2 Revision 0 | 4-187 Technical Report TR-5364-2 Revision 0 | ||
~TELEDYNE | ~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 | ||
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 | |||
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4-198 Technical Report TR-6364-2 Revision 0 PPTEi EDYNE ENGiNEER;NG SERViCES SAP2SAP VERiFiCA!.ON 5364 6-JUN-83 UN2 YEL-RED SOLiD 40GF 0-600f1S TiÃE/F RCE TABLE 65. NAGNiTUDE AT'QOE PO.NT | 4-198 Technical Report TR-6364-2 Revision 0 PPTEi EDYNE ENGiNEER;NG SERViCES SAP2SAP VERiFiCA!.ON 5364 6-JUN-83 UN2 YEL-RED SOLiD 40GF 0-600f1S TiÃE/F RCE TABLE 65. NAGNiTUDE AT'QOE PO.NT | ||
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ENGINEERiNG SEPVICES SAP2SRP VERIFiC4TiQN 5364 2<-~lAY-S3 QUARTER MODEL VNiT 2 LOQPSEAL TiME/FORCE TABLE 16 MACNiTUOE AT NODE POiNT 64 | ENGINEERiNG SEPVICES SAP2SRP VERIFiC4TiQN 5364 2<-~lAY-S3 QUARTER MODEL VNiT 2 LOQPSEAL TiME/FORCE TABLE 16 MACNiTUOE AT NODE POiNT 64 o | ||
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Latest revision as of 02:23, 24 February 2020
ML17324B005 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 06/10/1986 |
From: | TELEDYNE ENGINEERING SERVICES |
To: | |
Shared Package | |
ML17324B004 | List: |
References | |
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TR-5364-2, TR-5364-2-R, TR-5364-2-R00, NUDOCS 8608060055 | |
Download: ML17324B005 (295) | |
Text
TEC'8NICAL REPORT TR.,5364"2 REVISION 0 BOOK a OF Xo t
DONALD C. COOK NUCLEAR GENERATBfG, PLANT,,
ANALYSIS OF PRESSURIZER+SAF~/RELIBP VALVED, DISCHARGE PIPING SYSTEM PER NUTMEG-QV3Tj UNION 2
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AMERICAN ELECTRIC POWER SERVICE CORPORATION 2 BROADWAY NEW YORK, NEW YORK 10004 P't". ~
"" "; -'~'"J TECHNICAL REPORT TR-5364-2 REVISION 0 t..
~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.
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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
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and the SRV quarter model are given in Figures 4.7.1 and 4.7.2, respecti vely.
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r>-TELEDYNE Technical Report ENGINEERING SERVICES TR-5364-2
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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.
ASME rated flow:
WR = 51.5A (1.03P + 14.7)(.9)(.975)C (Ref. 17) where:
= 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.
Technical Report TR-5364- 2 Revision 0 )5 TELEDYNE ENQINEER)NQ $ ERVlCE$
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Technical Report TR-5364" 2 Revision 0 P$~Q-LEDYQE ~QUEER)gQ $ ERQCE$
4-27 SY ~El OATS~2~ SHEET NO.
PROJ. NO.
~SF FIGURE 4.6.1-2 JSA/
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Fig.4.6.1-2
-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
A TELEDYNE ENQINEERINQ '
SERVICES 4-30 ~
POrLV'I/IDO WE'LW J SHEET NO. OF Zoot c SC+E~~7 tC.
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TELEDYNE ENQINEERINQ SERVICES 4-32 PNLV Mc Oc~ we~A p ~one.c sc~< ~eric. SHEET HO 3 OF CHKO. BY~+OATS 8 IF 83 VN T 2 S l2 EhohlSV8',N. ACCT'< ES~ F QoH gqpH FIGURE 4 7 ~ 8IO OI CowvouKv7 Gll 7 S 30 Cow pouauT ~DI RQ'P: ~QEMCu YANK DwC . 'ERG gP 5>DCL ESP ) 57 8e + 7 Qp c.oAyouzuC g l3 'o7 X 0 n n 0 0 5' I m m v'vive. 7ro A (zZ~ 5. '1 5og ll lrl V o) 7 I picVDrr~~ I Lr 'jr,on] (2ao ) Jl rvCJ o>,g glrA CI ro& s" ) 5 // o/~ c r/g>~48 g /~ >4/~ 9-~s 'D Q 0 m Z 0 0Z A TELEDYNE ENGINEERINQ SERVICES 4-34 SY ' CHKO. BY DATE J J~ ~C OATE~<Y S3 AooS6 +gaea//'d's 78& SHEET NO. PROJ. NO D OP ~3E'0 U~>>Z ~ FIGURE 4.7.1-5 QpRv'/dMducs~ ~/zH/ WCk'4Q < .Kn/'rQ'~gc rid ~ QHc'D ~ /QJA/4 r/OJE3 ~ / 3 AA /Oooo 'IE COB Sos.z5 > " <<c~4>5 9o1 C3 JE;A ~~c//o/l v"wC/-/~r'/ I 8o5 J )s/~~ T /i)A/ g//c.'/0 ~ QW~Cv Q~e r/n // 8c>b Jd~c ~ /M ~ N,'CJAJ C JT /P JE/ /of C7 Cl rn RELfFS/t$ 01/0)4 REACTOR LOSS OF COOL%? AHA.YSIS PROGRRII (a tV IQ AEP UNIT2 l LlNE RENPS 83/05/20. Cb
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This is the quality upstream of the discharge valves dur ing the subcooled discharge case; there-C3 Oe fore, the quality is zero.
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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.
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This is the quality upstream of the discharge valves during the subcooled discharge case; there-fore, the quality is zero.
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'i8 CI for e, the quality is zero.
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Ouring this transient (which is a PORY transient) the safety valve remains closed; therefore, the quality in the control volume remains at 1.0.
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4-113 A TELEDYNE Techni ca 1 Report ENGINEERINQ SERVICES TR-5364-2
~
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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 '
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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
~
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