ML17334A490
| ML17334A490 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/15/1983 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17334A491 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM AEP:NRC:0585D, AEP:NRC:585D, NUDOCS 8312210221 | |
| Download: ML17334A490 (608) | |
Text
{{#Wiki_filter:' REGVLATI{ y~NPORMATION DISTRIBUTION{,TEM (RIDE) ACCESSION NBR;S312210?21 DOC ~ DATE: 83/]2/15 NOTARIZED; NO DOCKET FACIL:50 315 Donald C. Cook IVucl ear Power Pl anti Uni t,'1i Indiana '8 05000315 50-316 Donal a C ~ CooK (Vucl ear. Power Pl anti Unit ',2i 'ndiana 8 05000316 AUTH'AhlE AUTHOR AFF1LIATION
-', Al 'EXICHEM ~ P ~ Indi ana 8 Mi chi gan E ec t r i c Co ~
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':RECIP ~ NAME RECIPIENT AFFILIATION ;.'DEHTONEH ~ RE Office of Nuclear Reactor Regulationi Director
SUBJECT:
. Forwards Rev 0 'to Technical Rept TR-5364 3i "Analysis of Pressurizer Safety valve Discharge Piping Sys, i",. Vols 1'.
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8 2 8 Rev 0 to Technical Rept TR-5364 4iVols 1 8 Riper NUREG 0737i Item II,U ~ 1 ~ DISTRIBUTION CODE ~ A046S COPIES RECEIVED:LTR I ENCL J (
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TITLE! OR Submittal: TMI Action Plan Rgmt NUREG-0737 8 NUREG 1 ('jy/ r kg/ Q/ SW: 0660'OTES:
'ECIPIENT COPIES REC IP IFNT COPIES ID CODE/NAME LTTR ENCL 'ID CODE/NAME LTTR ENCL'RR ORB1 BC 01 7 g, INTERNAL: ELD/HDS3 1 0 IE/DEPER DIR 33 IE/DEPER/EPB'RR si IE/DEPER/IRB ERICKSONi P 1 1 NRR PAULSONiW ~ 1 NRR/DHFS/DEPY29 1 NRR/DL -DIR 14 1 NRR/DL/ADL 16 1 NRR/DL/DRAB 18 PL NRR/DSI/ADRS. 27 1 NRR/DSI/PEB 1 NRR/DSI/AS 6 1 AB 1 NRR/DST DIR 30 1 EG ILk . 04 RGN3 1 EXTERNALS ACRS 34 10 CP LPDR 03 2 2 NRC PDR '02 1 NSIC 05. 1 1 NTIS 1 1 gag 3PS
,Q, Qlr~~s f h) g,s I TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL
/>> Cy Cy INDIANA 8 MICHIGAN ELECTRIC ColMPANY P.O. BOX 1663I COLUMBUS, OHIO .43216 December 15, 1983 AEP:NRC:0585D Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG-0737, Item II.D.1 PWR RELIEF AND SAFETY VALVE TEST PROGRAM ll Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
References:
(1) Letter No. AEPsNRC:0585C dated July 9, 1982 (2) Letter from Mr. S.A. Varga, NRC, dated March 14, 1983 (3) Letter No. AEP:NRC:0585G dated October 14, 1983,
Dear'Mr. Denton:
This letter and its Attachment concerns the plant specific evaluation of the Relief (PORV) and Safety Valves (SV) and the related discharge piping analysis for the Donald C. Cook Nuclear Plant as detailed in Reference (1). It is submitted in compliance with the requirements of item II.D.1 of NUREG-0737. In Reference'(3) we requested an extension to the submittal date of July 1, 1983 noted in Reference (2) for the plant specific evaluation up t'o December 15, 1983.
~
The following are the Indiana 6 Michigan Electric Company's responses as applicable to the Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2. This document has been prepared following Corporate procedures which incorporate a reasonable set of. 4 controls to insure its accuracy and completeness prior to signature by the undersigned. Very truly yours, I 83122i022i 83i2is P.'xich ~g~~ygs I f PDR P ADQCK 05000315 PDR Vice President y egg/
~" ""'e yof MPA/cam Attachments 0 cc: John E. Dolan W. G. Smith, R. C. Callen Jr. - .Bridgman <o P~.
G. Charnoff y
~
E. R. Swanson, NRC Resident Inspector - Bridgman
ATTACHMENT'TO AEP:NRC:0583D Item I plant specific Re rta far'safet a Relief valve (sv/PORv) e=""""' The Pressurizer Power Operated Relief Valves (PORV) at Cook Plant are Masoneilan relief valves, Model $ 38-20721. These valves are the same as those tested in the EPRI valve test program. The Masonei1an valve's performance was acceptabl'e under various transient conditions performed during the test. We have reviewed the EPRI test results, and the D. C. Cook spec'ific piping system analysis performed by Teledyne Engineering Nuclear'lant Services (TES) and conclude that the valves tested represent the relief valves design installed at D. C.'ook Plant, and that the conditions tested by EPRI envelope'he range of expected operating and accident conditions including the use of PORV's to mitigate cold overpressurization for the D. C. Cook Plant; and therefore, it that the PORV's at the D. C. Cook Nuclear Plant are is'oncluded qualified as required by Item II.D.l of NUREG-0737 for 'plant specific applications. The Pressur'izer Safety Valves (SV) at Cook Plant are Crosby Model NHB-BP-86-6M6 equipped with loop seals upstream of the valves ~ This model type valve was tested at the Combustion Engineering test facility in Windsor,'onnecticut. The tests were conducted both with a water and without a water loop seal. The tests confirmed the ability of the safety valves to open and close under their expected operating fluid conditions. It is concluded from these tests that the SV's are qualified as required by Item II.D.1 of NUREG-0737 for plant specific applications. Westinghouse Electric Corporation has completed the study to evaluate the overall operability of the safety valves and the effect of safety'valve performance on the system overpressurization and has issued WCAP-10105. The above WCAP Report was submitted to the NRC by Westinghouse Owner's Group letter No. WOG-77 dated 7/27/82. The as-built piping analysis performed by Teledyne Engineering Services for the D. C. Cook Plant, with the loop seal configurationf indicated that the inlet and discharge piping and supports 'would be overstressed for the accident condition loads (SV thermal transients and SV shock) and that the loading was beyond that envelope tested under the EPRI program. To mitigate this overstress concern, Indiana 6 Michigan Electric Company has decided to drain the water in the safety valve loop seals as noted in Reference (3) of the cover letter. A design modification was initiated to drain each of the (3) pressurizer safety valve loop seals to the pressurizer and to install drain lines to each of the loop seals. This modification has been completed in both Units.
Based on .the EPRI SV test program report, Westinghouse evaluation report WCAP 10105, TES piping evaluation report, and our review of the above reports, we conclude'hat the safety valves and the associated discharge piping system are qualified for the plant specific applications in the drained loop seal configuration. Item 2: Plant S ecific Submittal for Pi ing and Supports Evaluation. Teledyne Engineering Services (TES) has completed the plant specific PORV/SV discharge piping analyses for the Donald C. Cook Nuclear Plant. The mathematical model consists of the discharge piping from the pressurizer up to the Pressurizer Relief Tank, including the relief and safety valves. The analyses consisted of thermal hydraulic analyses using RELAP-5/MOD 1 computer code to generate hydrodynamic data for control volumes of each segment of the pipe. This is then input into REPIPE Computer code to derive the force time histories on the piping system, one for the inlet junction and the" other for the outlet junction. SAP2SAP then combines the two force time histories into one. The stress analyses of the piping system were performed using TMRSAP computer code. The stress analyses of the as-built piping system indicated that the discharge piping system was overloaded for the safety valve transient followed by the seal water discharge through the discharge piping. The calculated stresses in the piping and its supports exceeded the allowable limits. To eliminate this concern, an analysis was performed without water in the loop seals. ',This analysis with the dry loop seal showed that the loads-and stresses are within the allowable limits for the piping system and supports with a few exceptions. For Unit No. 1, TES results indicate that the loads on eight pipe supports exceed the design loads as shown on the original as-built support drawings and for Unit No. 2, twenty-four supports exceed the design loads. A reanalysis of these supports for the increased loads was performed by, AEPSC and it was determined that: 1) for Unit No. 1, six supports were found to be adequate to resist the revised loads and only two supports needed modifications; and 2) for Unit No. 2, seventeen supports were found to be adequate to resist the revised loads while seven supports needed modifications. A design modification was initiated to modify these supports. All supports requiring modification have'been reworked. and are now capable of carrying the revised loading. The following TES reports of the piping analysis using the drained loop seal pre,attached: Unit No. 1; Technical Report TR-5364-3; Volumes 1 and 2 Unit No. 2; Technical Report TR-5364-4, Volumes l.and 2. The TES evaluation also showed that the safety valve accelerations due to the SV transient shock condition exceeded the vertical'allowable of 2g's by less than lg. However', we were informed by Westinghouse, who is the safety valve supplier, that the v'alves have been successfully seismically tested for 4g-vertical and 6g-hohizontal accelerations. Based on the above information, we conclude that the acceleration on the SVs during an SV transient are within the test acceleration values and are acceptable.
References:
- 1) EPRI PORV/SV Test Program Reports as identified in our letter No. AEP:NRC:0585B dated April 7, 1982.
- 2) Westinghouse WCAP-10105, "Review of Pressurizer Safety Valve Performance as observed in the EPRI Safety and Relief Valve Test Program," dated June, 1982. (Non-proprietary)
- 3) Teledyne Reports TR-5364'-1, Rev. 0, Books 1,2,3, of 15 TR=5364-.2, Rev. 0, Books 1,2 of 10 TR-5364>>3, Rev. 0, Books 1,2 of 3 TR-5364'-4, Rev. 0, Books 1 2 of 3
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HFGUiATORV OQGf(Ef FILE TELEDYNE ENCIIMEERllVG EERllVG SERVICES ((~TELEDYNE DOC UfihEbl7 ENQINEERINQ SERVICES TES PROJ. NO. r4 78& BC'ATE D 0 D TECHNICAL REPORT TR-5364-3 REVISION 0 BOOK 2 OF 3 DONALD C. COOK NUCLEAR GENERATING PLANT ANALYSIS OF PRESSURIZER SAFETY VALVE DISCHARGE PIPING SYSTEM, %1TH DRAINED LOOP SEALS PER NUREG OZ3Z, ILD.1, UNIT 1 JULY 18, 1983
AMERICAN ELECTRIC POWER SERVICE CORPORATION 2 BROADWAY NEW YORK, NEW YORK 10004 TECHNICAL REPORT TR-5364-3 REVISION 0 BOOK 2 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.1, UNIT 1 JULY 18, 1983
~TELEDYNE ENGINEE RING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-890-3350
Technical Report A TELEDYNE TR-5364-3 ENQINEERINQ SERVICES Revision 0 TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
Book 1 of 3
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 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 REPIPE 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 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
Technical Report TR-5364-3
~< TELE'(NE Revision 0 ENQINEERlNQ SERVICES TABLE OF CONTENTS Continued PAGE 6.3 Valve Accelerations 6-79 6.3.1 DBE Seismic Accelerations 6-80 6.3.2 SV Transient Shock Valve Accelerations 6-84 I
6.4 Nozzle Loads 6-88 6.5 Valve Loads 6-94 7.0 DRAWINGS 7-1
8.0 REFERENCES
8-1 9.0 COMPUTER ANALYSIS Book 3 of 3 9.1 RELAP Input 9.2 REP IPE 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
~< TELEDYNE Technical Report ENQINEERINQ SERVICES TR-5364-3
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Revision 0 5-1 5.0 STRUCTURAL ANALYSIS Thermal and force/time history analyses were performed for the drained loop seal condition of the pressurizer safety and relief valve discharge piping using the TMRSAP computer program; a modified version of SAPIV. The computer model used was based on TES isometric drawing E-5763, Revision 3, which is shown in Section 7.0. In general, the structural analysis was done in accordance with AEP letter dated November 29, 1982 from Mr. Sam Ulan of AEP to Mr. L.B. Semprucci. of TES (Reference 1) and AEP letter dated March 15, 1983 from Mr. Sam Ulan of. AEP to Mr. Pat Harrison of TES (Reference 11). For the drained loop seal analysis,
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it was
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not necessary to reanalyze the
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deadweight, normal thermal, PORV transient thermal, OBE seismic and DBE seismic
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conditions. The as-built analysis of the pressurizer safety. and relief valve
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discharge piping, contained in TES Technical Report TR-5364-1, Revision 0
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(Reference 2), should be referenced for all analytical results for the above conditions. This report contains the results for the SV transient thermal condition and the SV transient shock force time/history analysis. The emergency 'ondition is shown to be acceptable, per this report, except as noted in Sections 6.2 and 6.3.2, for a drained loop seal condition. The normal and upset conditions were shown to be acceptable per the as-built analysis and report (Reference 2). The draining of the loop seals will not adversely affect the analysis of the normal and upset conditions.
0 Technical Report sr-TELEDYNE TR-5364-3 Revision 0 5-2 ENQtNEERlNQ SERVlCES 5.1 SY Transient Thermal Anal sis Thermal analysis was performed for the SV transient condition. The temperature distribution was obtained from the RELAP5 output, as shown in Section 4.9. Throughout this report, thermal case 1 refers to normal operation, thermal case 2 to PORV operation, and thermal case 3 to SV operation. Boundary displacements were calculated for the quench tank nozzle, pressurizer nozzles, and support 1-GRC-R-616, which connects to the pressurizer. 5.2 Transient Shock Anal sis Based on the results obtained from the RELAP5 analysis, presented in
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The analysis was
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Section 4, the SV transient shock analysis was performed.
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at one millisecond intervals for a length of .65 seconds. All loads
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'alculated peaked previous to .65 seconds, indicating that the analysis was performed for a
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sufficient length of time.
Techni cal Report . <<-TELEDYNE TR-5364-3 Revision 0 6-1 ENQlNEERLNQ SERVlCES 6.0 ANAlYTICAL RESULTS Section 6.0 contains all analytical results rel ati ve to emergency conditions. That is, stress equations C1, C2 and C3 (as defined in Reference 1), support loads for all restraints, valve accelerations for DBE seismic and SV transient shock conditions, nozzle loads and valve end moments. For easier reference, the results presented in Section 6.0 include loadings for all conditions with deadweight, normal thermal, PORV transient thermal, OBE seismic, and DBE seismic results being taken from TES Technical Report TR-5364-1, Revision 0. S.l ~Et S Stress calculations were based on the 1967 Edition of the ANSI B31.1 Code (Reference 13), the AEP letter dated November 29, 1982 (Reference 1), and the AEP letter dated March 15, 1983 (Reference 11). For this report, stress
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~
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combinations C1, C2 and C3 are presented, TES Technical Report TR-5364-1 should
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be referenced for A1, A2, Bl, B2 and B3 stresses. ~ Stress combinations C1, C2 and C3 are as follows: Cl normal pressure stress + deadweight stress + DBE stress < 1.8 Sh C2 SV transient pressure stress + SV .transient weight stress + SV transient shock stress < 1.8 Sh C3 SV transient thermal stress range <1.25 Sc + .25 Sh The stresses presented conservatively consider all moments to be intensified, although B31.1 allows for intensification factors to be omitted in the torsional direction. Allowable stresses for stress combinations Cl, C2 and C3, -were obtained by using the maximum temperature the piping experienced during the SV
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transient event to determine Sh. The value of Sc was based on 70oF per Reference 10.
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A suranary of allowable stresses for the emer gency condition is given in Table 6.1-1.
Technical Report A TELEDYNE TR-5364-3 ENQINEERlNQ SERV!CES Revision 0 6-2 Section 119.6e1 of the 831.1 Code indicates that the thermal range stress calculations shall be based on the range between the minimum and maximum temperature. Stresses for the maximumrange of thermal moments, due to all thermal conditions considered, were analyzed and found to be satisfactory. Stresses were calculated as follows:
'Pressure p52 p2 42
~Dd dd
~75i M Z
Thermal
~iM Z
Seismic
~75i M Force/Time Histor
~75i M where:
d = inside diameter of pipe D = outside diameter of pipe i = intensification factor MA
= resultant moment due to deadweight loadings Mg = resultant moment due to seismic loadings MC
= range of resultant moments due to thermal loadings MD = resultant moment due to force/time history analysis Z = section modulus
0 TECHHICAL REPORT TR - 5364 - 3 REVo HO 0 TELEDYNE ENGINEERING SERVICES tttftftftfftttttffftfttftfttffffftttffttttftttttttttft BY PROJECT) Di Ca 5364 COOK UHIT 1 13 JULY 1983 cHKD ~k sAvE 2/i&~ SUIIHARY OF ALLOMABLES tfffftftttfffttftftfftfffffftftftfffffffffffifttffffff SHEET HOe OF TABLE 6.1-1 SUHHARY O'F ALLOWARLES HAIN RESER I I I I I NODES I HATERIAL ITEMPERATURE ( F)l Sh (PSI) I I I I I 1 THRU 44 I SA-358-316 CL 1 I 394 I 16336 I I I I I 46 rHRU 422 16234 I
. I 74 THRU 142 16195 I
I 200 THRU 206 452 16144 I I 260 THRU 2'95 I SA-312-304 I 452 I 14742 I I I I LOOF'S I- I I I I I -I I HODES LOOP C I HODES LOOP B I NODES LOOP A I HATERIAL I TEHPERATURE ( F)l Sh (PSI) I I I I I I I -I I 98 TIIRU 109 I 144 THRU 156 I 208 TMRU 216 I SA-312-304 I 445 I 14770 I I- I I I I I I I li0 TKRU ii40 I 157 THRU 163 I 220 TMRU 2230 I I 460 I 14710 I I I I I I I I I ii5 I 165 I 225 I
' 460 I 11740 t I I--"I- I I I I I I 120 I 170 I 229 I SA-376-316 I 670 I 1 i480 t I I I I I I I I I 122 THRU 138 I 172 THRU 185 I 233 THRU 244 I I 670 I 16000 I I I I I I I I
'OTEL LOOP C REFERS TO THE SRV LOOP COHTAIHIHG VALVE SV-45C THIS HOTATIOH IS TYPICAL OF LOOPS B AHD A ALSO' ALLOMABLE AS PER HOTE (6)STABLE A 1 OF B 3ioii0t 1967 CODEo PORV LOOF'51 I
NODES HAT ERIAL ITEHF'ERATURE ( F)l S7I (PSI) I I 610 I I SA-312-304 I I I
'00 I I
I 14350 I I I I I 615 THRU 625 I 13508 I I I I I 630 653 I 14300 I I I I I 635 THRU 665 I SA-376-304 I 653 I 14300 I I I I I- I NOTEl PORU LOOP 1 51 REI.ERS TO THE PORV LOOP CONTAINING UALUES, NHO-151 AND NRV-151. THES IS TYPICAL OF LOOPS 152 AND 153.
- - 6-4 TECHHICAL REPORT TR 5364 3 REVt HO@ 0 TELEDYNE ENGINEERING SERVICES tttfttttfffffffffttfffffffffffftfttitftffftfftfttffttt BY MTE V~3f+
PROJECTI 5364 13 JULY 1983 Bo Co COOK UHIT 1 cHKo~k DATE 2/JRP~ OF ALLOMABLES
'UMMARY ttffffffffftfffffftftttffffffttffffffffftffffffffffftt SHEET HO( OF TABLE 6.1-1 (Cont)
PORV LOOP 153 NODES HATERIAL I TEHPERATURE ( f) I Sh (PSI ) I I I 560 THRU 555 I SA-312-304 I 500 I 14550 I I I I I 550 THRU 533 I 567 I 14416 I -I -I I 530 THRU 525 I I I 13468 I I I I I 515 I I 14300 I I -I I 510 THRU 450 I SA-376-304 I -14300 I I I I 440 THRU 750 I SA-376-316 I 16000 I- -I I PORV LOOP 152 I I NODES I MATERIAL ITENPERATURE ( f)l Sh (PSI ) I I I I I 300 THRU 325 I SA-312-304 I 500 I 14550 I I I I I 335 THRU 340 I 600 14350 I I I 350 I 700 14200 I I I 355 THRU 375 I 816 13952 I I I 380 THRU 385 I 13220 I I I 390 14300 I I 400 THRU 431 I SA-376-304 I 653 I 14300 I- I I I
Technical. Report <c-TELEDYNE TR-5364-3 Revision 0 6-5 ENQINEERINQ SERVICES 6.1.1 E uation C-1 Stresses
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6-16 Technical Report TR-5364-3 A TELEDYNE Revision 0 ENQlNEERINQ SERVlCES
'.1.2 E uation C-2 Stresses
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6-27 Technical Report A TELEDYNE TR-5364-3 ENGINEERiNQ SERVtCES Revision 0 1 6.1.3 E uation C-3 Stresses
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Technical Report ss TELEDYNE TR-5364-3 ENGINEERING SERVICES
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Revision 0 6-38 Support loads are given for each support on the pressurizer relief line piping. Support load combinations were calculated in accordance with Table II of Reference 1. Thermal-1 refers to the normal thermal operating case, thermal-2 refers to the PORV transient thermal condition, and thermal-3 refers to the SV transient thermal loading. I~a The support load combinations considered are as follows: D1 deadweight + normal thermal +/-'BE D2 deadweight + PORY transient thermal +/- (OBE)2 + (PORV transient shock)g~ El deadweight + normal thermal +/- DBE E2 deadweight + SV transient thermal +/- SV transient shock The results of the support load combinations indicate that the Following supports exceed the load given on the support drawing. 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 Review of these supports to ensure acceptability falls outside of the TES work scope and is, therefore, the responsibility of others.
Techni cal Report <c TElEDYNE TR-5364-3~ ENGlNEERlNQ SERV(CES
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Revision 0 6-39 The support loads given are taken from the TMRSAP computer analysis. The support loads given act on the support. The following explanation details the procedure followed in extracting these support loads. Four different methods of modeling supports were used in the analysis, presented in this report. Constant force supports were modeled using a FORCE card. Supports in a global coordinate direction were modeled using a RESTRAINT '~1 card for deadweight, thermal and seismic analyses and were modeled with a SPRING card for force/time history analysis. For any supports not oriented in, a global coordinate direction a FLEX card was used to represent the support, regardless of the type of analysis being executed. Because of the various methods used, slightly different procedures are used to extract the support loads. In general, there are two tables. in the TMRSAP output which are used to obtain support loads: the "Boundary Element Forces/Moments" table and the "Pipe Forces/Moments/ Displacements/Member Global Directions" table. The former table is used for supports modeled using FLEX or SPRING cards and the latter for supports modeled using a FORCE or RESTRAINT card. In the "Boundary Element Forces/Moments" table (see Figure 6.2-1), support loads can be extracted directly and are given in pounds in the direction indicated by the SPRING or FLEX card. The supports in this table are referenced only by the "element number" and, therefore, the "Boundary Elements" table (see Figure 6.2-2) must be used to determine which element number corresponds to which support. The "Pipe Forces/Moments/Displacements/Member Global Direction" table (see Figure 6.2-3) gives the global forces on the x, y, and z directions for each TMR node number. Note that the SAP node number is internally generated by the program and does not correspond to the node number input. To .show equilibrium between the "j" and "i" ends of a node, the force at the "i" end of the node is subtract'ed from the force at the "j" end of the node. The only exception to this procedure is when a RESTRAINT card is used. the RESTRAINT card instructs the program to change the sign at the "i" end of the node and to generate a reaction on the pipe at that node. Therefore, the support load is obtained by adding the "j" and "i" forces together and then, flipping the sign in order to
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generate the reaction on the support, instead of the reaction on the pipe.
6-40 Techni cal Report TR-5364-3 A TELEDYNE Revision 0 ENGINEERING SERVICES The following list gives all of the possible combinations of analysis type, support type and support orientation encountered on TES Project 5364 and refers to the appropriate detailed explanation which follows. 0 i <<i Support N~dl I ~E
- 1. deadweight constant force global FORCE
- 2. deadweight rigid global RESTRAINT
- 3. deadweight rigid skewed FLEX
- 4. thermal rigid global RESTRAINT
- 5. thermal rigid skewed FLEX
- 6. seismic rigid global RESTRAINT D seismic rigid skewed FLEX seismic snubber global RESTRAINT
- 9. seismic snubber skewed FLEX
- 10. f/t history rigid global SPRING
- 11. f/t history rigid skewed FLEX
- 12. f/t history snubber global SPRING
- 13. f/t history , snubber skewed FLEX A The load for a constant force support modeled with a FORCE card is obtained by subtracting the force at the "i" end of the appropriate node from the force at the "j" end in the "Pipe Forces/
Moments/Displ acements/Member Global Directions" table. The resulting sign and magnitude indicates the force on the pipe and should agree with the value entered on the FORCE card. To determine the load on the support, the sign obtained from the TMRSAP output should be flipped.
6-41 Technical Report TR-5364-3 A TELEDYNE
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Revision 0 ENGINEERINQ SERVICES In deadweight and thermal analyses, rigid supports orientated in a global coordinate direction were modeled using a RESTRAINT card. The support load for this case is obtained by adding the x, y, or z forces at the "i" and "j" ends of the appropriate node. The resulting sign must then be flipped to obtain the reaction on the support, as opposed to the reaction on the pipe. Skewed supports modeled with FLEX cards in deadweight and thermal analyses require a two step process in determining the support load. The FLEX card generates a boundary element and the first step is to determine which boundary element number corresponds to which support. This can be done by looking in the "Boundary Elements" table which lists the boundary element number and the node at which that element is modeled. Once the boundary element number has been determined, then the "Boundary Element Forces/moments" table is used to extract the support load. The load from this table acts along the direction of the support as input by the analyst. This axial (relative to the support) force can then be broken down into the appropriate global components. An alternative method would be to follow the procedure outlined in B above to determine the force in each appropriate component direction. D The procedure for global rigid and snubber supports in seismic analysis is similar to procedure B. One difference is that seismic output has, no signs since it is assumed that all forces can act + or -. Therefore, rather than flipping the sign of the support load obtained a +/- is applied. Procedure D is followed for the x, y, and z shock directions and then the x and y loads are combined by the SRSS method as are the loads for the y and z shock directions. The greater value is then listed on the support load summary sheet.
6-42 Technical Report TR-5364-3 A TELEDYNE Revision 0 ENQINEERINQ SERVICES E Skewed supports in seismic are the same as skewed supports in deadweight and thermal except that again the boundary element force extracted must be considered +/-. Since no signs are carried in the TMRSAP output of a seismic analysis, it is not recommended to use the alternative method given under C when extracting..support loads from a seismic run. In a force/time history analysis, no RESTRAINT cards are used; FLEX cards are used to represent skewed supports and SPRING cards are used to represent global supports. Both of these techniques generate boundary elements and therefore, the procedure is essentially the same as that described in C above. The only difference is that the "Boundary Element Forces/Moments" table does not list a single value but rather a table of times and forces (see Figure 6.2-4). At the end of this table, the maximum absolute positive and negative values are given. The maximum absolute value is conservatively used with a +/- applied.
6-43 Technical Report T -5364-3 ion 0 Figure 6.2-1 8c,LENIENT O U N 0 A R Y e.'L E M: A T f 0 R C S l M C H E N T S LOAO fORCE, MOM=NT KUMBiR CA SP
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Technical Report TR-6364-3 ision 0 Figure 6.2-4 I T 3 N K H STORY ESPOW EIJE?{EAT TCPE (I{ {I U R O A ) / / / OUTPUT SET
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0 k 6-47 Technical Report <tI TELEDYNE TR-5364-3 evision 0 ENGINEERINQ SERVICES SUPPORT LOAD SlÃQRY SHEET DONALD C. COOK BY: DAIE:~4 UNIT gl PROJECT 5364 CHECKED BY: ~ DATE: ~i+ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS QY QZ FX FY FZ MX MY MZ EADWEIGHT-1 rOOZ ,OC / THERMAL-1 -. /Ss,ofay'odo THERMAL-2 -,ddS ,859 -/Bo THERMAL-3 , oo] .558l/lS SEISMIC-OBE ~,o/9 ZZZ/ SEISMIC-DBE f,oo/ ~,ozz f97/ BLOWDOWN-SV BLOWDOWN-PORV ~,oo5 ~989 TES COMBINED LOADS SUPPORT DRAWING LOADS FX FY
>/
NORMAL/UPSET 7/ DESIGN (+) g++7i
+/
EMERGENCY 315'1 W5 DESIGN (-) /g$ /g NITS: DISPLACEMENTS: FORCES INCHES POUNDS TES COMBINED LOADS ARE Gr ar THAN THE LOAD SHOWN MOMENTS : INCH-POUNDS ON THE SUPPORT DRAWING
6-48 Technical Report w TELEDYNE TR-5364-3 vision 0 ENGINEERING SERVICES SUPPORT LOAD SIJ$ 9RY SHEET DONALD C. COOK BY: DATE 7~/+ UNIT fl DATE:~7i+ PROJECT 5364 CHECKED BY: GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER
- 2- 984 NODE NUMBER DESIGN LOADINGS DI SPLACEMENTS FORCES MOMENTS QY QZ FX ;FY FZ MX MY EADWEIGHT-1 Q ,oo/ /020 THERMAL-1 ,OOZ ",//8 Z/7o THERMAL-2 ,097 "570 THERMAL-3 ,5%7 -4oo SE ISMIC-OBE ,0/9 /4~
SEISMIC-DBE ~,02/ ~ 25/ BLOWDOWN-SV -.o/V o/0 ,22'7 ~pose BLOWDOWN PORV 0 f,os 20/ TES COMBINED LOADS SUPPORT DRAWING LOADS FX FY t/b'/ NORMAL/UPSET
-// 8 DESIGN (+)
EMERGENCY DESIGN (-) 764/ NITS: DI SPLACEMENTS: INCHES TES COMBINED LOADS ARE FORCES . : POUNDS THAN THE LOAD SHOWN MOMENTS : INCH-POUNDS ON THE SUPPORT DRAWING
6-49 Technical Report s> TELEDYNE TR-5364-3 vision 0 ENGINEERINQ SERVICES SUPPORT LOAD SUQIARY SHEET DONALD C. COOK BY: DATE: 7-i>-~> UNIT 81 PROJECT 5364 CHECKED BY:++~ DATE:~+ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y QZ FX FY FZ MX MY EADWEIGHt'-1, gg$ -Q/Q, gp9 THERMAL-1 THERMAL-2 , Ao .Szl-.9' THERMAL-3 06',Sd7 SE ISMIC-OBE ~.o~ +o +o// SEISMIC-DBE ~u5 ~o
+. ///
229'/7o
+ o/8
+. 22/
BLOWDOWN-SV -o65- , 10790 BLOWDOWN PORV,OO8 v',0/4
-, CUk .O/O TES COMBINED LOADS SUPPORT DRAWING LOADS FX FY NORMAL/UPSET DESIGN (+)
EMERGENCY - to9'50 (-) DESIGN iMo9 UNITS: DISPLACEMENTS: INCHES TES COMBINED LOADS ARE
'FORCES POUNDS THAN THE LOAD SHOWN MOMENTS : INCH-POUNDS ON THE SUPPORT DRAWING
6-50 Technical Report <> TELEDYNE TR-5364-3 evision 0 ENQlNEERlNQ SERVlCES
.SUPPORT LOAD SUQSRY SHEET DONALD C. COOK BY: DATE:~+~
UNIT fl + 7 ~+i~ PROJECT 5364 CHECKED BY: DATE: GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER d C -~88 NODE NUMBER
+Z DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS
+Y QZ FX FY FZ MX MY EAD WEIGHT-1 ,os/ .w0 THERMAL-1 ,$/f /. oJ,She THERMAL-2 , /9l ,49 ,9z<
THERMAL-3 , j7z ,s9< SEISMIC-OBE +QOQ +.0/o SEISMIC-DBE 2,0/0 +.008 f~/$ BLOWDOWN-SV y.a@ +,2/9
,175 I,oop +,G/4 BLOWDOWN-PORV l/ .oo8 .ca TES COMBINED LOADS SUPPORT DRAWING LOADS FX NORMAL/UPSET DESIGN (+)
EMERGENCY DESIGN (-) NITS: DISPLACEMENTS: INCHES TES COMBINED LOADS ARE FORCES POUNDS THAN THE LOAD SHOWN 'N MOMENTS : INCH-POUNDS THE SUPPORT DRAWING
6-51 I Technical Report r> TELEDYNE TR-5364-3
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evision 0 ENGINEERING SERVICES SUPPORT LOAD SUQIARY SHEET DONALD C. COOK BY: DATE:Zl~~ UNIT 01 PROJECT 5364 CHECKED BY: DATE: GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER
+X DESIGN LOADINGS X'ISPLACEMENTS FORCES MOMENTS FX FY MY EADWEIGHT-1 THERMAL-1 -)9CpO -I//0'OO THERMAL-2 THERllAL-3 loW4 SEISMIC-.OBE +,M2 ~IBAD SEISMIC-DBE BLOWDOWN-SV
+.ms ill
+, ized +/Qg~
BLOWDOWN-PORV
.coC TES COMBINED LOADS SUPPORT DRAWING LOADS FX
)786 +88 NORMAL/UPSET - 5'7I - i<53 DESIGN (+) /Dg7o 4i EMERGENCY
-3089 -e585 DESIGN (-) $Z$ (p /O087 UNITS: DI SPLACEMENTS: INCHES TEE LONBIIIEO LIIAOS IIRE~&
FORCES POUNDS THAN THE LOAD SHOWN MOMENTS : INCH-POUNDS ON THE SUPPORT DRAWING gpT +op P ~<
0 6-52 Technical Report W TELEDYNE TR-5364-3 vision
~ ~
0 ENGINEERlMQ SERVICES SUPPORT LOAD STORY 'HEET DONALD C. COOK BY: DATE:~+ UNIT gl PROJECT 5364 CHECKED BY: DATE .'~+~~i++ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER
- C -C - /c9 NODE NUMBER
+X DESIGN LOADINGS DISPLACEMENTS 'FORCES MOMENTS FX FY FZ MX MY EAD WEIGHT-1 ,oo8 ,CrO/ /goo THERMAL-1 OZ -,OZ2 THERMAL-2 ,0/9 /oS -,o/'s THERMAL-3 , d/g SE ISMIC-OBE .COZ SEISMIC-DBE ~
BLOWDOWN-SV
-AosV v'. /W y,oh
,0 /0/ ,oT/
BLOWDOWN-PORV 4 os TES COMBINED LOADS SUPPORT DRAWING LOADS FX NORMAL/UPSET -tao@ DESIGN (+) EMERGENCY - iXOO DESIGN (-) )zoo NITS: DI SPLACEMENTS: INCHES TES COMBINED LOADS ARE FORCES POUNDS THAN THE LOAD SHOWN MOMENTS : INCH-POUNDS ON THE SUPPORT DRAWING
6-53 Technical Report <<-TELE'(NE TR-5364-3
~ ~
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6-54 Technical Report -r>-TElHXNE TR-5364-3
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0 ENGlNEERlNQ SERVfCEB SUPPORT LOAD SUKWRY SHEET DONALD C. COOK BY: DATE:~~~> UNIT $ 1 PROJECT 5364 CHECKED BY: /72 / DATE: / GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER Q- -Q5Z NODE NUMBER i/ 0
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6-55 Technical Report rs-TELEDYNE TR-5364-3 evision 0 ENQINEERINQ SERVICES l SUPPORT LOAD SUQRRY SHEET DONALD C. COOK BY: DAIE:~i~- > UNIT fl PROJECT 5364 CHECKED BY: DATE: 7 GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER / K8C-C-999 NODE NUMBER /// DESIGN LOADINGS DISPLACEMENTS FORCES i%MENTS X +Y FY FZ MX MY MZ EADMEIGHT-1 , OOZ .O@8 ,o9C -rD(
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6-56 Technical Report <>-TELEDYNE TR-5364-3 evision 0 ENGlNEERIMQ SERVICES'ONALD SUPPORT lOAD SlMARY SHEET C. COOK BY: OATE:~+ gl UNIT PROJECT 5364 CHECKED BY: DATE: >> GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DI SPLACEMENTS FORCES MOMENTS QY QZ FX FY MX MY DEADWEIGHT-1 .oM ,c66 THERMAL-1 . f78 sr8,818 THERMAL-2 -//o 28',zqf THERMAL-3 ra~,zxz SE ISMIC-OBE Zoz 1 P+/ SEISMIC-DBE BLOWDOWN-SV ,0&5 os'
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6-58 Technical Report ~< TELEDYNE TR-5364-3 vision 0 ENQINEERINQ SERVICES SUPPORT LOAD SUMARY SHEET DONALD C. COOK BY: DATE:~+ gl UNIT PROJECT 5364 CHECKED BY: +~~ DATE:~+ GLOBAL COORDINATE'SYSTEM NORTH MARK NUMBER j6 < ~ ~5 4 NODE NUMBER F290
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6-59 Technical Report rt TELEDYNE TR-5364-3 evision 0 ENQlNEERlNQ SERVlCES SUPPORT LOAD SlMARY SHEET DONALD C. COOK BY: DATE:7 i< >> gl UNIT PROJECT 5364 CHECKED BY: ~~~ DATE:~+ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X QY QZ FX FY FZ MX MY EADWEIGHT-1 .os,os'oz7 THERMAL-1 ,g99 EST -,ZC THERMAL-2 THERMAL-3 ,297 g,68 .oaz Sf ISMIC-OBE .Dfy,o/9 .07/ SEISMIC-DBE ~Co 7,CSZ +IZZ BLOWDOWN-SV w,oco 7 oM , 07Z f-.@zan'0 BLOWOOWN-PORV v'.coS + gag 7". 009
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6-60 Technical Report TR-5364-3 A TELEDYNE evision 0 ENQINEERINQ SERVICES P~ SUPPORT LOAD SlK%RY SHEET DONALD C. COOK BY: DAYE f1 UNIT PROJECT 5364 CHECKED BY: ~~~ DATE:M+~+ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER /- <<- +->~8
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I 6-61 Technical Report >> TELEDYNE TR-5364-3
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0 6-62 Technical Report -<> TELEDYNE TR-5364-3 vision 0 ENQINEERINQ SERVICES SUPPORT LOAD SUQRRY SHEET DONALD C. COOK BY: DATE: UNIT fl ~~~i PROJECT 5364 CHECKED BY: DATE: GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER 6~6 8 DOO NODE NUMBER
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0 Technical Report 6-63 A TELEDYNE TR-5364-3 evision 0 ENQINEERINQ SERVICES SUPPORT LOAD SUKNNY SHEET DONALD C. COOK BY: UNIT gl PROJECT 5364 CHECKED BY: GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER ~ Q 40/ NODE NUMBER
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6-64 Technical Report -><-TELEDYNE TR-5364-3 ENGINEERINQ SERVtCES vision
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Technical Report 6-65 -W-TELE'(NE TR-5364-3 vision 0 ENQlNEERING SERVICES SUPPORT LOAD SCARY SHEET DONALD C. COOK BY: DAIE:~d- ~ UNIT tl PROJECT 5364 CHECKED BY: DATE: GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER
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6-66 Technical Report -rs-TIB EDYNE TR-5364-3
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evision 0 ENQINEERINQ SERVICES SUPPORT LOAD SlKQRY SHEET DONALD UNIT fl C. COOK BY: DAIE:~ PROJECT 5364 CHECKED BY: DATE: +i~ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER SO DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X QY FX FY FZ MX MY MZ EADMEIGHT-1
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Technical Report TR-5364>>3 6-67 A TELEDYNE vision 0 ENGINEERING SERVICES SUPPORT LOAD SlJPARY SHEET DONALD C. COOK BY: DATE UNIT gl PROI3ECT 5364 CHECKED BY: DATE: GLOBAI COORDINATE SYSTEM NORTH MARK NUMBER C-
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0 6-68 Technical Report s> TELIEOYNE, TR-5364-3 vision 0 FNGINEERlMQ SERVlCES SUPPORT LOAD SUKQRY SHEET DONALD C. COOK BY: DATE: UNIT 81 PROJECT 5364 CHECKED BY: DATE: GLOBAl. COORDINATE SYSTEM NORTH MARK NUMBER 6 C ~" Od'ODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y FX FY FZ MX MY MZ EAD WEIGHT-1 -,eye i.Z5 -.o5e Ni/ THERMAL-1 ,Coa 9'dz ,5iq THERMAL-2 ~ i'PW /97 .5'7/ THERMAL-3 ,7z'o S,75 .6dZ SE ISMI C-OBE +id ~.~z5 SEISMIC-DBE ",843 ~,7~ +,Z/6 BLOWDOWN-SV +,ozV Po84 .QCcrC BLOWDOWN-PORV +,/Z0 + /O/
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6-69 Technical Report <<-TIELEDYNE TR-5364-3 vision 0 ENQINEERINQ SERVICES SUPPORT LOAD SENARY SHEET DONALD C. COOK BY: DAlE:~~ UNIT Ol PROJECT 5364 CHECKED BY: DATE: ~ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y FX FY FZ MX MY EADWEIGHT-1 -yg, +$ g -/M THERMAL-1 THERMAL-2 ,877 8c8 ,004 THERMAL-3 , 8'P$ g +f SE ISMI C-OBE +/Zz,04~ +i' SEISMIC-DBE +, jap ~08
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Technical Report 6-70 ri-TELEDYNE TR-5364-3 evision 0 ENGtNEERINQ SERVICES SUPPORT LOAD SUK4RY SHEET DONALD C. COOK BY: DATE:~7- ~~~, UNIT gl PROJECT 5364 CHECKED BY: DATE: + GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER
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6-71 Technical Report <>-TELEDYNE TR-5364-3 ENQINEERIMQ SERVICES evision 0 DONALD UNIT fl C. COOK SUPPORT lOAD SlMNY SHEET BY: DATE: DATE:
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Technical Report 6-72 TELEDYNE P~ TR-5364-3 evision 0 ENGINEERING'ERVICES SUPPORT LOAD SUKNRY SHEET DONALD C. COOK BY: DATE: ~ i>- gl UNIT PROJECT 5364 CHECKED BY: +~~ DATE:~P> GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER dZO DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS
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'6-73 Technical Report ~> TELEDYNE TR-5364-3 ENQINEERINQ SERVICES, vision 0 SUPPORT LOAD SUCRRY SHEET DONALD C. COOK BY: DATE:~~~+
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Technical Report 6-74 <> TELEDYNE TR-5364-3
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6-75 Technical Report << TELEDYNE TR-5364-3
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6-76 Technical Report -w-TFl ~mt NE TR-5364-3 ENQlNEERINQ SERVlCES vision 0 SUPPORT LOAD SlMARY SHEET DONALD C. COOK BY: DA~:~/- Z-~ UNIT fl DATE: PROSPECT 5364 CHECKED BY: GLOBAI COORDINATE SYSTEM NORTH MARK NUMBER 6 4 S NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS FX FY MX MY EADWEIGHT-1 .g// ,o'er THERMAL-1 .ZBI THERMAL-2 THERMAL-3 .de SEISMIC-OBE -.D9 W~( SEISMIC-DBE 1,87 ~r/@ <EE 7 BLOWDOWN-SV Wj P97 ~oaZ Q 0 .a9 BLOWDOWN-PORV +o48 ./
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0 6-77 Technical Report <<TELEDYNE TR-5364-3
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0 Technical Report TR-5364-3 A TELEDYNE evision 0 679 ENGINEERINQ SERVICES 6.3 Valve Accelerations Valve accelerations are presented in this section for the DBE seismic condition and the SV transient shock condition. The DBE seismic accelerations are taken directly from TR-5364-1, Revision 0 and are presented in this report since the DBE event constitutes an emergency condition. The horizontal allowable was taken as 3g and the vertical allowable as 2g based on the attachments to AEP letter dated September 16, 1982 from Mr. J. L. Williams of AEP to Mr. L. B. Semprucci of TES (Reference 14). For the seismic condition, the resultant horizontal acceleration was compared against the 3g allowable. The vertical acceleration values of valves SV-45A, SV-45B, SV-45C, NM0-151, NRV-151 and NRV-153, exceed the 2g criteria. The horizontal acceleration alues of valves NMO-152 and NM0-153, exceed the 3g criteria. However, TES was informed per Reference 12 that the NMO and NRV series valves can accept valve accelerations up to 6g in any direction. Since it is not in the work scope of this project to qualify the SV valves for vertical accelerations over 2g, this task is assumed to be the responsibility, of American Electrice Power Service Corporation and will not be further addressed other than to report the acceleration values in Section 6.3.2.
6-SO Technical Report ss TElEDYNE TR-5364-3 evision 0 ENQlNEERlNQ SERVlCES 6.3.1 DBE Seismic Accelerations
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Technical Report 6-84 r< TELE%ME TR-5364-3 Revision 0 ENGINEERING SERVICES 6.3.2 SV Transient Shock Valve Accelerations
ss TELEDYNE 6-85 ENGINEERiNG SERVICES Technical Report TR-5364- 3 Revision 0 DONALD C. COOK BY: 2/72k DATE: 7 B/& UNIT fl CHECKED BY: C~+ DATE: 7 ~> PROJECT 5364 VALVE ACCELERATIONS VALVE NODE NUMBER Abo VALVE WEIGHT bSS J8~ DIRECTION FORCE (LBS)
/boy'S ACCELERATION
/zSg z,~<~ i971
/.~A'7@o /,ized ALLOWABLE VALVE NODE NUMBER
//7o VALVE WEIGHT DIRECTION X Y FORCE (LBS) gzf ~s7z.
ACCELERATION 2,os 2~ 78' ALLOWABLE
6-86 w TELEDYNE ENGlNEERING SERVlCES Technical Report TR-5364- 3 Revision 0 DONALD C. COOK 8Y: J0 H+ DATE: B /~ UNIT fl CHECKED BY: CWA DATE: 7 /3" PN PROJECT 5364 VALVE ACCELERATIONS VALVE
/I/mo -/S/
NODE NUMBER VALVE WEIGHT
/8s DIRECTION FORCE (LBS) 50$ g7g a~o /tzz KS/ 8/Zg ACCELERATION z,z.7o g,egg Z Iz5'.le /. 378 9,57o ALLOWABLE VALVE NODE NUMBER VALVE HEIGHT q~ /ds DIRECTION FORCE (LBS)
ACCELERATION ALLOhABLE
6-87 ss TELEDYNE ENGlNEERlNG $ ERVtCES Technical Report TR-5364- 3 Revision 0 DONALD C. COOK BY: W DATE: 7/Z g9 UNIT tl CHECKED BY C~+ PATE. 7-'Z3 gQ PROSPECT 5364 VALVE ACCELERATIONS VALVE
%WY- /4i eEv- jsS NODE NUMBER VALVE WEIGHT
+/o /8~ +/o ll~
DIRECTION Y FORCE {LOS)
.gyp'CCELERATION
~ 9pg q ~gg /.K5o ALLOWABLE VALVE NODE NUMBER VALVE WEIGHT DIRECTION FORCE (LBS) io7/
ACCELERATION iNs 2.Z.9'/ Z,077 ALLOWABLE
Technical Report 6-88 ><-TELEDYNE TR.-5364-3
~ ~
Revision 0 ENGlNEERlNQ SERVICES 6.4 Nozzle Loads I Forces and moments for the four pressurizer nozzles and the quench tank nozzles are given in this section for all loading conditions. The directions indicated represent the load on the appropriate nozzle.
Technical Report 6-89
~>-TELEDYNE TR-5364-3 evision 0 ENGlNEERING SERVICES NOZZLE LOAD
SUMMARY
SHEET DONALD C. COOK BY: <+< DATE: 7->>-+~ UNIT gl PROJECT 5364 CHECKED BY: ~ DATE: ~/+ ~ GLOBAL COORDINATE SYSTEM NORTH NODE NUMBER
+X DESIGN LOADINGS DISPLACEMENTS fORCES MOMENTS
+X QY QZ FX FY FZ MX MY MZ DEADMEIGHT-1 -/ooo - o -/2 2 0 THERMAL-1 390 /4 7 /5 0 Cko80 gaia /Q/84 THERMAL-2 ->o Sd lo -8Qo - 9'w THERMAl-3 ~o z2.369 BS~8 SE ISMI C-OBE M'0 M(47 sEio ~ 7676 ~/ps3 ~3&
SEISMIC-DBE ~8WO +/Z68/ ~omar BLOMDOMN-SV cl+/M /$ 6 /Q />75'0 i/g/39/ gp'ps ~ ~zyzz~ BLOMDOMN-PORV /-/036 / t22?- 238K+ /g i8iyo UNITS: DI SPLACEMENTS: INCHES FORCES POUNDS MOMENTS : INCH-POUNDS
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Technical Report 6-92 >< TELEDYNE
-5364-3 ENGINEERING SERVICES ision 0
'OZZLE"LOAD
SUMMARY
SHEET DONALD C. COOK BY.. C&8- DAYE.~>tJ UNIT Ol PROJECT 5364 CHECKED BY: ~~~ DATE:~7/>iP> GLOBAL COORDINATE SYSTEM NORTH NODE NUMBER
+Z DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y FX FY FZ MX DEADWEIGHT-1 0 lg 930 /6830
-9'40 THERMAL-1
-8'Q
-4+0 2o ro Z2/50 -/'7bdO THERMAL-2 30 - OO 0 0 0 -zz gb'0 THERMAL-3 ~/o -2<99 -393 i SEISMIC-OBE +08 I "jl91 SEISMIC-DBE J-]f32 ~1782 t+Ol 469 iZZWM cg20 BLOWDOWN-SV ~Cia ~~s78 <<pong c~r FDo ~36387 BLOWDOWN-PORV i 7E >zzr<
UNITS: DI SPLACEMENTS: INCHES FORCES POUNDS MOMENTS : INCH-POUNDS
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Technical Report 6-94 <<-TELEDYNE TR-5364-3 evison 0 ENQINEERINQ SERVICES 6.5 Valve Loads Section 6.5 gives the moments on each end of all valves in the piping system for all loading conditions. The moments reported are those acting on the pipe at the point where the valve and pipe meet.
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6-96 << TELEDYNE Technical Report ENGlNEERlNQ SERVlCES TR-5364-3 Revision 0 VALVE END MOMENTS Donald C. Cook BY: /7) DATE: 7 /B/N Unit 81 Project 5364 CHECKED BY: 8W/P DATE: V /3 "8& MV-'A VALVE NUMBER NODE MX MY
-+bred'Z DEADWEIGHT 9"o -lo9o ~g 7V!o HERMAL-1 raze dozZ z+Nc9 -b'dzo yg8S7 HERMAL-2 -974% ZS/o 2z/7 -8+o+ A +/+
HERMAL-3 /XECo / +/zo /+ F/z /75'77 C 8/< /z +os EISMIC OBE -Z7~ -+87~ ~ r~W EISMIC DBE +4784 +8 /8'89'rorz'0'9/SZ LOWDOWN PORV + /od+ dm ~ 5ii </8%4 LOWDOWN SV ~ /PE'b +ro z -f gent +Diaz.
+9ozi'ALVE NUMBER NODE MX MY MZ DEADWEIGHT HERMAL-1 HERMAL-2 HERMAI -3 EISMIC OBE EISMIC DBE LOWDOWN PORV LOWDOWN SV UNITS: INCH-POUNDS
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-r<-TELEDYNE Technical Report 6-98 ENGlNEERlNG SERVlCES TR-5364-3 Revision 0 VALVE END MOMENTS Donald C. Cook BY: Sff)k DATE: 9 Is Unit 5'1 Project 5364 CHECKED BY: ~Ad DATE: 7/3"E3 VALVE NUMBER NODE goo MY DEADWEIGHT ao /+z9" -/87 -~/ 8 HfRMAL-1 2/Z HERMAL-2 HERMAL-3 jo&5, -8// 0 @so EISMIC OBE ggyg g @8~ W/Z@D +$ +4zzs <yzeiy EISMIC DBE + g gg + g7 /@7' ~dD9o ~/88z/
LOWDOWN PORV + g9 + +//S 9 9/6 + s9/0 LOWDOWN SV ~ />/Z/ + >+~> ++99m +/S~/o VALVE NUMBER NODE
,X MY MZ DEADWEIGHT - R/z -D/
HERMAL-1 -/o 3 ZO7Z -/B7/ -$ 7Og 8/ HERMAL-2 -/276 -7/Bz HERMAL-3 7/9 -7395 //z - ~f/ EISMIC OBE +/0+g /gonzo ~i z'r/ ~ gd/9 ~/d/go EISMIC DBE + /6/g9 - 5//Zb LOWDOWN PORV 3 /5 egg
+/p+g+ //zoo
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LOWDOWN SV CoB +/zg@/ 7o95'NITS: INCH-POUNDS
]< TELEDYNE Technical Report 6-99 ENGINEERING SERVlCES TR-5364- 3 Revision 0 VALVE END MOMENTS Donald C. Cook Unit Pl BY: RA DATE: 7/BA4 Project 5364 CHECKED BY: CQ/9 DATE: 7/3 83 VALVE NUMBER /U V- W~/
NODE MX DEADWEIGHT" Noel -%79 74/9'5/ HERMAL-1 7779 bbo HERMAL-2 @ Voz + +974 /Kz
/'ERMAL-3 w ++77 ~VS/7 EISMIC OBE y BS EISMIC DBE 7
+g 7+~+
LOWDOWN PORV + ggg + +/ +egg+ +QQ7 + gag /T LOWDOWN SV w +/~g W Z,gyp -Z3ZZ -/g /+@ 5Vag 2// VALVE NUMBER NODE MX MX MY DEADWEIGHT 9o HERMAL-1 HERMAL-2 977Z HERMAL-3 Vora -eIg< ldbo EISMIC OBE ~ ggga + gpgZ -//Z8'7 EISMIC DBE t 70 +~ // LOWDOWN PORV + 'Pgg/ ~D/ /9 78 +92+ + 7/gZ FSS LOWDOWN SV ~/VSz/ + PHD /EaVV +ro73 + floe -lo7& T UNITS: INCH-POUNDS
Technical Report A TELEOYNE TR-5364-3 Revision 0 7-1 ENQINEERINQ SERVICES 7.0 DRAMINGS
J f de a
Technical Report A TELEDYNE R-5364-3 ENQINEERlNG SERVlCES vision 0 8-1
8.0 REFERENCES
- 1. Letter from Mr. S. Ulan of AEP to Mr. L. B. Semprucci of TES, dated November 29, 1982.
\
- 2. Teledyne Engineer ing Services Technical Repor t TR-5364-1.
- 3. -
Crosby Valve and Gage Company Drawing No. H-51688, Revision A.
- 4. Technical Paper 8410 by Cr ane.
- 5. Westinghouse Electric Company, Drawing No. 110E272.
- 6. ITI Report, "Evaluation of REL'AP5/MODl for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads," February 1982.
Prepared by Intermountain Technologies.
- 7. Review of Pressurizer Safety Valve Performance as observed in the EPRI Safety and Relief Valve Test Program. WCAP-10105.
- 8. ASME Code NB7000, Section III.
- 9. Teledyne 'Engineering Services Technical Proposal PR-5653, dated May 14, 1981.
- 10. TES letter 5364-44, dated May 28, 1983 from Mr. P. D. Harrison of TES to Mr. Sam Ulan of AEP.
s>-TELEDYNE Technical Report R-5364-3 ENQINEERINQ SERVICES ision 0 8-2
8.0 REFERENCES
Continued
- 11. Letter from Mr. S. Ulan of AEP to Mr. P. D. Harrison of TES, dated March 15, 1983.
- 12. Letter from Nr. Sam Ulan of AEP to Mr. P. D. Harrison of TES, dated Nay 26, 1983.
- 13. 1967 Edition of USAS B31.1 Power Piping Code.
- 14. Letter from Nr. J. L. Williams of AEP to Mr. L. B. Semprucci of TES, dated September 16, 1982.
- 15. EPRI Power Safety and Relief Va'tve Test Program Guide for Application of Valve Test Program results to Plant-Specific Evaluations. Interim Report, July 1982 (Research Project V102).
AMERICAN ELECTRIC POWER SERVICE CORPORATION 2 BROADWAY NEW YORK, NEW YORK 10004 TECHNICAL REPORT TR-5364-4 REVISION 0 BOOK 2 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 2 JULY 18, 1983 4FTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-890-3350
r~ sP
rs TELEDYNE Technical Report ENQlNEERINQ SERVtCES TR-5364-4
~ ~
Revision 0 TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
Book 1 of 3
2.0 CONCLUSION
S 2-1 3.0 SYSTEM DESCRIPTION/DISCUSSION 3-1 4.0 THERMAL FI UIDS 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 4-17 4,5 RELAP Plots 4-23 4.6 Force Time History Plots 4-72 4.7 RELAP Input 4-143 4.8 REPIPE Input 4'-162 4.8.1 REPIPE Input - Section A .4-163 4.8.2 REPIPE Input - Section B 4-170 4.9 Appendix A 4-178 5.0 STRUCTURAL ANALYSIS Book 2 of 3 5-1 5.1 SV Transient Thermal Analysis 5-2'-2 5.2 Transient Shock Analysis 6.0 ANALYTICAL RESULTS 6-1 6.1 Stress Summary 6-1 6.1.1 Equation C-1 Stresses 6-5 6.1.2 Equation C-2 Stresses 6-17 6.1.3 Equation C-3 Stresses 6-29 6.2 Support Loads 6-41
Technical Report -ss TELEDYNE TR-5364-4 Revision 0 ENQINEERINQ SERVICES TABLE OF CONTENTS ontsnued PAGE 6.3 Valve Accelerations 6-86 6.3.1 DBE Seismic Acceler ations 6-87 6.3.2 SV Transient Shock Valve Accelerations 6-91 6.4 Nozzle Loads 6-95 6.5 Valve Loads 6-101 7.0 DRAWINGS 7-1
8.0 REFERENCES
8-1 9.0 COMPUTER ANALYSIS Book 3 of 3 9.1 RELAP Input 9.2 REP IPE 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
-w-TELEDYNE Technical Report TR-5364-4 ENGlNEERlNQ SERVlCES Revision 0 5-1 5.0 STRUCTURAL ANALYSIS Thermal and force/time history analyses were performed for the drained loop seal condition of the pressurizer safety and relief valve discharge piping using e
the TMRSAP computer program; a modified version of SAPIV. The computer model used was based on TES isometric r drawing E-5761, Revision 2, which is shown in Section 7.0. In general, the structural analysis was done in accordance with AEP letter dated November 29, 1982 from Mr. Sam Ulan of AEP to 'Mr. L.B. Semprucci of TES (Reference 1) and AEP letter dated March 15, 1983 from Mr. Sam Ulan of AEP to Mr. Pat Harrison of TES (Reference 11). For the drained loop seal analysis, it was not necessary to reanalyze the
~
~
~ ~
deadweight, normal thermal, PORV transient thermal, OBE seismic and DBE seismic
~
conditions. The as-built analysis of the pressurizer safety and relief valve
~ ~ ~
~ ~
discharge piping, contained in TES Technical Report TR-5364-2, Revision 0
~ ~ ~ ~ ~
(Reference 2), should be referenced -for all analytical results for the above conditions. This report contains the results for the SV transient thermal condition and the SV transient shock force time/history analysis. The emergency condition is shown to be acceptable, per this report, except as noted in Sections 6.2'nd 6.3.2, for a drained loop seal condition. The normal and upset conditions were shown to be acceptable per the as-built analysis and report (Reference 2). The draining of the loop seals will not adversely affect the analysis .of the normal and upset conditions.
yb Technical Report -.sr-TELEDYNE TR-5364-4 Revision 0 5- 2 ENQINEERtNQ SERVtCES 5.1 SV Transient Thermal Anal sis Thermal analysis was performed for the SV transient condition. The temperature distribution was obtained from the RELAP5 output,. as shown in Section 4.9. Throughout this report, thermal case 1 refer s to normal operation, thermal case 2 to PORV operation, and thermal case 3 to SV oper ation. Boundary displacements were calculated for the quench tank nozzle, pressurizer nozzles, and support 2-GRC-R-616, which connects .to the pressurizer. 5.2 Transient Shock Anal sis Based on the results obtained from the RELAP5 analysis, presented in
~
Section 4,. the SV transient shock analysis was performed.
~ ~ ~
The analysis was calculated at one millisecond intervals for a length of .65 seconds. All loads
~ ~ ~
~
peaked previous to .65 seconds, indicating that the analysis was performed for a
~ ~
sufficient length of time.
0 1
Techni cal Report -sr-TELEDYNE TR-5364-4 Revision 0 6-1 ENQINEERlNQ SERVICES 6.0 ANALYTICAL RESULTS Section 6.0 contains all analytical results relative to emergency conditions. That is,. stress equations Cl, C2 and C3 (as defined in Reference 1), support loads for all restraints, valve accelerations for DBE seismic and SV transient shock conditions, nozzle loads and valve end moments. For easier reference, the results presented in Section .6.0 include loadings for all conditions with deadweight, normal thermal, PORV transient thermal, OBE seismic, and DBE seismic results being taken from TES Technical Report TR-5364-2, Revision 0. 1.1 ~tt 1 Stress calculations were based on the 1967 Edition of the ANSI B31.1 Code (Reference 13), the AEP letter dated November 29, 1982 (Reference 1), and the AEP letter dated March 15, 1983 (Reference 11). For this report, stress
~
~ ~ ~
combinations Cl, C2 and C3 are presented, TES Technical Report TR-5364-2 should be referenced for Al, A2, Bl, B2 and B3 stresses.
~ ~
~ Stress combinations Cl, C2 and C3 are as follows:
Cl normal pressure stress + deadweight stress + DBE stress < 1.8 Sh C2 SV transient pressure stress + SV transient weight stress + SV transient shock stress' 1.8 Sh C3 SV transient thermal stress range'1.25 Sc + .25 Sh The stresses presented conservatively consider all moments to be intensified, although B31.1 allows for intensification factors to be omitted in the torsional direction. Allowable stresses for stress combinations Cl, C2 and C3, were
~
obtained by using the maximum temperature the piping experienced during the SV
~ ~
transient event to determine Sh. The value of Sc was based on 70oF per Reference 10.
~ ~
~
A summary of allowable stresses for the emergency condition is given in Table 6.1-1.
Technical Report -rs-TELEDYNE TR-5364-4 ENQlNEERlNQ SERVlCES . Revision 0 6-Z Section 119.6.1 of the B31.1 Code indicates that the thermal range
~
~ ~
stress calculations shall be based on the range between the minimum and maximum
~
temperature. Stresses for the maximum range of thermal moments, due to all thermal conditions considered, were analyzed and found to be satisfactory. Stresses were calculated as follows: Pressure Pd2 P2 d2
'~di d
~75i M Thermal
~iM Z
Seismic
~75i M Force/Time Histor
~75i ii where:
d inside diameter of pipe D outside diameter of pipe i f intensif i cation, actor MA resultant moment due to deadweight loadings MB resultant moment due to seismic loadings MC range of resultant moments due to thermal loadings Mp resultant moment due to force/time history analysis Z section modulus
TECNIICAL REPORT TR - 5364 - 4 TELED YNE. ERG NEER X NG SERV X CES pjt t)f)) SSNNNSNSSSNNSNSSSNSSNSSNSNNSNNSNNSN PROJECTI 53M ih JULY 19O3 Do Co COOK NIIT 2 ceo k~~b qA~ ~JrS/Ã3 NNY OF ALLONSLES SNNNNSNNNSNNNNSNSNNNNSNNSNNNSN TABLE 6.1-1 PORV LOOP 151 1 I NODE MATERIAL ITEMPERATURE ( F)l Sh (PSI ) I S'30 I I SA-312-304, I 447 I 14762 I I I I I 286 THRU 288 600 14350 I I I 760 14080 I I I 292 THRU 318 14294 I I I I 320 THRU 342 SA-376-316 I 653 I 16000 I I PORV LOOP 152 NODES I MATERIAL ITEMPERATURE ('"F)l Sh (PSI) I I I I 240 THRU 402 Sk-312-304 I 800 I 14000 I I I I 404 THRU 344 P I 864 I 13780 I I I I 346 I 653 14300 I I I I 350 THRU 356 SA-376-304 I 653 I 14300 I I I PORV LOOP 153 I NODES MATERIAL ITEMPERATURE (~ F) I Sh (PSI) I -I I I I 232 THRU 236 SA-312-304 I 440 I 14790 I I I I 238 THRU 239 I I I
'60 I I
I 14430 I 240 THRU 244 I ' 800 I
----- ---------------- ------14000 I I -------- I I 246 THRU 261 I 890 I 13650 I I I I I I 259 THRU 262 I 956 I 13292 I I I I 266 THRU 284 SA-376-304 . I 653 I 14300 I I I NOTE'ORV LOOP 151 REFERS TO THE PORV LOOP CONTAINING VALVES NMO-151 AND NRV-15io THIS IS TYPICAL OF LOOPS 152 AND 153'
TECHMICAL REPORT TR " 5364 " 4 TKI IEDY'NK K UINEKRINR SKRVIDK8 p 88888888888888888888888 BY DATEB698 PROJECTI 5364 Do Co CON m(IT 2 14 JULY 1983 CHKD ~ DATE TABLE 6 .l-l (Cont) MAIN RISER I I I I I I NODES I MATERIAL TEMPERATURE ( F) I Sh (PSI) I I I I, I I I 2 THRU 24 ISA-358-316 CL 1 I 16372 I I I I I I I 26 THRU 36 I 409 I 16273 I I I I I. I 38 THRU 51 I I 16237 I I I I I I 52 THR0 71 I I 432 I 16204 I 72 THRU 219 I I 440 I 16180 I I I I I 222 THRU 230 I SA-312-304 I 440 I I '4790 I I LOOPS I I I I I I MODES LOOP C
- I I
MmjES LOOP B I "I- -"" -I" NDES LOOP A I MATERIAL I TENPERATURE ( F) I Sh (PSI) I I I I 72 TNU 82 I I I 126 TNU 136 I I "I 176 THRU 190 I SA-312-304 I I 440 I I 14790 I I I 84 THRU 96 I 138 THRU 146 I I 445 I 14770 I I I I I I I I 98 I 148 I 195 I I 464 I 14694 I I I I I I I I 103 I 152 I 196 I I 464 I 11706 8 I I I I 107 156 I I I I
-I 200 I
I SA-376"316 I I-672 I I 11468 8 I I I 108 THRU 124 I 158 TMRU 174 I 202 THRU 218 I SA-376"316 I 672 I I I I I I ALSO'6000 I I HOTE1 LOOP C REFERS TO SRV LOOP C(mTAIIIIMO VALVE SV-45C THIS IS TYPICAL OF LOOPS B ND A 8 ALL(mABLE AS PER IIOTE (6) STABLE A I OF B 3ioie0r 1967 CGSEt
Technical Report -A TELEDYNE TR-5364-4 Revision 0 6-5 ENQINEERINQ SERV(CES 6.1.1 E uation C-1 Stresses
ss TIELEDYNF Technical Report ENGlNEERINQ SERVCES 64-4 6-6
'on 0
'I DONALD C. COOK BY: C/VA DATE: 7-/3 82 UNIT 82 PROJECT 5364 CHECKED BY: IVS DATE: W /5/
'STRESS SlMARY - EQUATION Cl PRESSURE DEADWEIGHT DBE EQUATION ALLOWABLE STRESS STRESS STRESS C1 STRESS STRESS NODE 8 (KSI) (KSI) (KSi) (KSI) (KSI)
-3 X'2
,3 ,3 xv
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w TELEDYNE Technical Report 6-7 TR-5364-4 ENG,lNET SERVICES ion 0 DONALD C. COOK BY: DATE: 7 J3 "E~ UNIT 82 PROJECT 5364 CHECKED BY: 0ATE: I / /+ STRESS SUGARY - EQUATION C1 PRESSURE DEADWEIGHT'TRESS EQUATION ALLOWABLE STRESS STRESS C1 STRESS STRESS NODE 0 (KSI) (KSI) (KSI) (KSI) (KSI)
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6-10 A TELEDYNE Technical Report ENGINEERING SERVICES TR- 364-4 ion 0 DONALD C. COOK BY: ~&A DATE: 7 i'3 ~3 UNIT N 7/+//+ PROJECT 5364 CHECKED BY: R DATE: STRESS SU/SARY - EQUATION C1 PRESSURE DEADWEIGHT DBE EQUATION ALLOMABLE STRESS STRESS STRESS Cl STRESS STRESS NODE 0 (KSI) (KSI) (KSI) (KSI) (KSI) go. a /3. 8 gg 7 Z,o 3. '7 Z'2 X xv I 3
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6-12 -s> TELEDYNE Technica1 Report
- 364-4 ENGINEERING SERVCES ion 0 DONALD C. COOK BY: DATE: '7-r-83 UNIT f2 PROJECT 5364 CHECKED BY: DATE: 7 <+~43 STRESS SORRY - EQUATION C1 PRESSURE DEADMEIGHT DBE EqUATION ALLOMABLE STRESS STRESS STRESS C1 STRESS STRESS NODE 0 (KSI) (KSI) (KSI) (KSI) (KSI)
.3 Z+ zz xv'
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Technical Report TR-5364-4 r< TELEDYNE Revision 0 6-41 ENQINEERINQ SERVICES 6.2 ~5d Support loads are given for each support, on the pressurizer relief line piping. Support load combinations were calculated in accordance with Table II of Reference 1. Thermal-1 refers to the normal thermal operating case, thermal-2 refers to the PORV transient thermal condition, and thermal-3 refers to the SV transient thermal loading. The support load combinations considered are as follows: D1 deadweight + normal thermal +/- OBE D2 deadweight + PORV transient thermal +/- (OBE)2 + (PORV transient shock)g~ El deadweight + normal thermal +/- DBE E2 deadweight + SV transient thermal +/- SV transient shock The results of the support load combinations indicate that the following supports exceed the load given on the support drawing. Review of these supports to ensure acceptability falls outside of the TES work scope and is, therefore, the responsibility of others. 2-GRC-R-585 2-GRC-R-586 2-GRC-S-609 2-GRC-R-607 2-GRC-S-587 2-GRC-S-611 2-GRC-R-589 2-GRC-R-612 2-GRC-R-591 2-GRC-R-614 2-GRC-S-594 2-GRC-S-624 2-GRC-S-596 2-GRC-S-626 2-GRC-S-598 2-GRC-S-629 2-GRC-S-599 2-GRC-S-630 2-GRC-R-600 2-GRC-S-631 2-GRC-R-601 2-GRC-S-632 2-GRC-R-605 2-GRC-R-633
0~ 2 $
Technical Report -A TELEDYNE TR-5364-4 Revision 0 6- 42 ENQINEERlNQ SERVCES The support loads given are taken from the TMRSAP computer analysis. The support loads given act on the support. The following explanation details the procedure followed in extracting these support loads. Four different methods of modeling supports were used in the analysis presented in this report. Constant force supports were modeled using a FORCE card. Supports in a global coordinate direction were modeled using a RESTRAINT card for deadweight, thermal and seismic analyses and were modeled with a SPRING card for force/time history analysis. For any supports not oriented in a global coordinate direction a FLEX card was used to repr esent the support, regardless of the type of analysis being executed. Because of the various methods used, slightly different procedures are used to extract the support loads. In general, there are two tables in the TMRSAP output which are used to obtain support loads: the "Boundary Element Forces/Moments" table and the 'Pipe Forces/Moments/ Displacements/Member Global Directions" table. The former table is used for supports modeled using FLEX or SPRING cards and the latter for supports modeled using a FORCE or RESTRAINT card. In the "Boundary Element Forces/Moments" table (see Figure 6.2-1), support loads can be extracted directly and, are given in pounds in the 'direction indicated by the SPRING or FLEX card. The supports in this table are referenced only by the "element number" and, therefore, the "Boundary Elements" table (see Figure 6.2-2) must be used to determine which element number corresponds to which support.'he "Pipe Forces/Moments/Displacements/Member Global Direction" table (see Figure 6.2-3) gives the global forces on, the x, y, and z directions for each TMR node number. Note that the SAP node number is internally generated by the program and does not correspond to the node number input. To show equilibrium between the "j" and "i" ends of a node, the force at the "i" end of the node is subtracted from the force at the "j" end of the node. The only exception to this procedure is when a RESTRAINT card is used. the RESTRAINT card instructs the program to change the sign at the "i" end of the node and to generate
~
reaction on the pipe at that node. Therefore, the support load is obtained by
~
adding the "j" and "i" forces together and then flipping the sign in order to
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generate the reaction on the support, instead of the reaction on the pipe.
Technical Report -r<-TELEDYNE TR-5364-4 Revision 0 6-43 ENQINEERlNG SERVlCES The following list gives all of the possible combinations of analysis type, support type and support orientation encountered on TES Project 5364 and refers to the appropriate detailed explanation which follows. Support Anal sis T e Su ort T e D i ti ~Nd 1i ~E1 ti
- 1. deadweight constant force global FORCE
- 2. deadweight rigid global RESTRAINT
- 3. deadweight rigid skewed FLEX
- 4. thermal rigid global RESTRAINT
- 5. thermal rigid skewed FLEX C
- 6. seismic rigid global RESTRAINT D
- 7. seis'mic rigid skewed FLEX
- 8. seismic snubber global . RESTRAINT
- 9. seismic snubber skewed
- 10. f/t history rigid global SPRING
- 11. f/t history rigid skewed FLEX
- 12. f/t history snubber global SPRING.
- 13. f/t history snubber skewed FLEX The load for a constant force support modeled with a FORCE card is obtained by subtracting the force at, the "i" end of the appropriate node from the force at the "j" end in the "Pipe Forces/
Moments/Displacements/Member Global Directions" table. The resulting sign and magnitude indicates the force on the pipe and should agree with the value entered on the FORCE, card; To determine the load on the support, the sign obtained from the TMRSAP output should be flipped.
Technical Report A TELEDYNE TR-5364-4 6-44 Revision 0 ENQINEERINQ SERVICES In deadweight and thermal analyses, rigid supports orientated in a global coordinate direction were modeled using a,RESTRAINT card. The support load for this case is obtained by adding the x, y, or z forces at the "i" and "'j" ends of the appropriate node. The resulting sign must then be flipped to obtain the reaction on the support, as opposed to the reaction on the pipe. Skewed supports modeled with FLEX cards in deadweight and thermal analyses require a two step process in determining the support load. The FLEX card generates a boundary element and the first step is .to determine which boundary element number corresponds to which support. This can be done by looking in the "Boundary Elements" table which lists the boundary element number and the node at which that element is modeled. Once the boundary element number has been determined, then the "Boundary Element Forces/Moments" table is used to extract the support load. The load from this table acts along the direction of the support as input by the analyst. This axial (relative to the support) force can then be broken down into the appropriate global components. An alternative method would be to follow the procedure outlined in B above to determine the force in each appropriate component direction. D The procedure for global rigid and snubber supports in seismic analysis is similar to procedure B. One difference is that seismic output has no signs since it is assumed that all forces can act + or -. Therefore, rather than flipping the sign of the support load obtained a +/- is applied. Procedure D is followed for the x, y, and z shock directions and then the x and y loads are combined by the SRSS method as are the loads for the y and z shock directions. The greater value is then listed on the support load sumnary sheet.
Techni cal Report -s<-TELEDYNE TR=5364-4
~ ~
Revision 0 6-45 ENQlNEERINQ SERV(CES Skewed supports in seismic are the same as skewed supports in deadweight and thermal except that again the boundary element force extracted must be considered +/-. Since no signs are carried in the TMRSAP output of a seismic analysis, it is not recommended to use the alternative method given under C when extracting support loads from a seismic run. F In a force/time history analysis, no RESTRAINT cards are used; FLEX cards are used to represent skewed supports and SPRING cards are used to represent global supports. Both of these techniques generate boundary elements and therefor e, the procedure is essentially the same as that described in C above. The only difference is that the "Boundary Element Forces/Moments" table does not list a single value but rather a table of times and forces (see Figure 6.2-4). At the end of this table, the maximum absolute positive and negative values are given. The maximum absolute value is conservatively used with a +/- applied.
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SUMMARY
SHEET DONALD" C. COOK f2 BY: DATE: i UNIT PROJECT 5364 CHECKED BY: DATER i+ ++ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NURSER
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Technical Report A TEI EDYNE TR-5364-4 R~' ion 0 ENQlNEERINQ SERVtCES SUPPORT LOAD SUKQRY SHEET DONAI D C. COOK BY: DAYE:~8 f2 UNIT PROJECT 5364 CHECKED BY: ~~ DATE:~+ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER + ++~ E ~8~ NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y QZ FX FY FZ MX MY MZ THERMAL-1 /7oO THERMAL-2 . 0(u7 ,goo THERMAL-3 ,AD%7 SE ISMI C-OBE + /// SEISMIC-DBE +go]
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Technical Report TR-5364-4 A TELEDYNE
'on0 6-52 ENQINEERINQ SERVICES SUPPORT LOAD SUNMARY SHEET 1
DONALD C. COOK BY: DA1E:~7 UNIT 82 PROJEC'f 5364 CHECKED BY: DATE:~W~ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS FX FY MX MY MZ EIGHT-1 THERMAL-1 ; ZZd 1',0/ ,g7$ THERMAL-2 ,gas .97o ,830 THERMAL-3 , sf),ro7 SE ISMI C-OBE Zwg +o ,657 SEISMIC-DBE ~do7 ~O W g//
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SHEET DONAI D C. COOK BY: OA~: 7/ UNIT 82 PROJECT 5364 CHECKED BY: BATE:~~<~i~+ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS FX FZ IGHT-1 ,u/ THERMAL-1 Z5/ /QO THERMAL-2 /'. C -2// THERMA -3 SE ISMI C-OBE +,Oo +a<~ SEI SMI C-DBE BLOWDOWN-SV BLOWDOWN-PORV ~ao4 0 TES COMBINED LOADS SUPPORT DRAWING LOADS FX FY NORMAL/UPSET roSQ DESIGN (+) /gpss Jo44 EMERGENCY 31Ol
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Technical Report s< TELEDYNE TR-5364-4 R ion 0 ENGINEERlMQ SERVfCES 0 SUPPORT LOAD SUYÃRY SHEET DONALD C. COOK BY: UNIT N PROJECT 5364 CHECKED BY: GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER
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Technical Report rs TELEDYNE TR-5364-4
'on 0 ENQINEERINQ SERVICES I SUPPORT LOAD
SUMMARY
SHEET DONALD C. COOK BY: DATE:~ UNIT 82 PROJECT 5364 CHECKED BY: ~~ DATE7M+I+ GLOBAI COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS
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Technical Report TR-5364-4 6-5S A TELEV(NE R ion 0 ENQINEERlNQ SERVICES SUPPORT LOAD SUKRARY SHEET DONALD C. COOK BY: DATE:~8 UNIT Inj'2 PROJECT 5364 CHECKED BY: DATE:~+i~i~~ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS
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Technical Report sr-TELEDYNE TR-5364-4 6-59 ReA 'on 0 ENQINEERlNG SERVlCES SUPPORT LOAD SUMNY SHEET DONALD -C. COOK BY: DATE:~ UNIT 82 PROJECT 6364 CHECKED BY: ~~ DATE:M+~~ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NUMBER
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Technical Report 6-60 r> TELEDYNE TR-5364-4 ion 0 ENQINEERINQ SERVICES, SUPPORT LOAD SIARY SHEET DONALD C. COOK BY: DATE: ~ UNIT 82 PROJECT 5364 CHECKED BY: i<~ DATE:M+i+ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER 4-4 NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y QZ FX FY FZ MX MY MZ" EI.GHT-l,d 5,024 , 009 THERMAL-1 ,/77 Z 74 THERMAL-2 THERHAL-3 .WD Z,g~ SEISMIC-OBE +op +o 7 g,y SEISMIC-DBE ,07 <0' 0 '7> BLOWDOWN-SV
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Technical Report <> TELEDYNE TR-5364-4 6-61 R sion 0 ENQINEERiNQ SERVICES SUPPORT LOAD S%48Y SHEET DONALD C. COOK BY: DATE:~8 UNIT N PROJECT 5364 CHECKED BY: ~~ DATE:+i~~~ GLOBAL COORDINATE SYSTEM NORTH MARK NUMBER NODE NllNBER DESIGN LOADINGS DISPLACE MENTS FORCES MOMENTS FZ MY EIGHT-1 QfP THERMAL-1 -/l z rz, 1<5 THERMAL-2 z. 75,297 THERMAL-3 Z.7I SE ISMI C-OBE 2,os'/cp SEI SMI C-DBE +D7Z
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, )g7 BLOWDOWN-SV
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,OOZ TES COMBINED LOADS SUPPORT DRAWING LOADS FX FY NORMAl/UPSET DESIGN (+)
EMERGENCY DESIGN (-) f2/0 9/79 U DISPLACEMENTS : INCHES TES COMBINED LOADS ARE /F FORCES POUNDS THAN THE LOAD SHOWN MOMENTS . : INCH-POUNDS ON THE SUPPORT DRAWING
~~qpk 4j +F~ 4 + <x
Technical Report -s<-TELEDYNE TR-5364-4 Revision 0 6- 86 ENQINEERIMQ SERVICES
'.3 Valve Accelerations Valve accelerations are presented in this section for the DBE seismic condition and the SV transient shock condition. The DBE seismic accelerations are taken directly from TR-5364-2, Revision 0 and are presented in this report
~ t since the DBE event constitutes an emergency condition. The horizontal allowable was taken as 3g and the vertical allowable as 2g based on the attachments to AEP letter dated September 16, 1982 from Mr. J. L. Williams of AEP to Mr. L. B. Semprucci of TES (Reference 14). For the seismic condition, the resultant horizontal acceleration was compared against the 3g allowable.
The vertical acceleration values of valves SV-45A, SV-45C, NRV-151, and NRV-153 exceed the 2g criteria. ~ The horizontal acceleration'values of valves NMO-151 and NM0-153, exceed the 3g criteria.
~ ~
~ However, TES was informed per Reference 12 that the
~
NMO and NRV series valves can accept valve accelerations up to 6g in any direction. Since it is not in the work scope of this project to
~ ~
~
~ ~ ~ ~
qualify the SV valves for vertical accelerations over 2g, this task is assumed to be the responsibility of American Electric Power Service Corporation and will not be further addressed other than to report the acceleration values in Section 6.3.2.
Technical Report A TELEDYNE TR-5364-4 6-87 Revision 0 ENQINEERINQ SERVICES 6.3.1 DBE Seismic Accelerations
-s>-TELEDYNE Technical Report TR-5364- 4. ENQINEERINQ SERVICE~J Revision 0 6-88 DONALD C.'OOK BY: M DATE: ~7/j9 UNIT ¹2 PROJECT 5364 CHECKED BY: DATE: ~1~~8 VALVE NO.
NODE NO.
/9'+o ACCELERATION ACCELERATION go+
ACCELERATION A A AA A A A A x /oz /.97 ./Z .$ 'o SC s-e V ID D K UJ CA CC M
.o< .OZ .o5 ,0(, o3 ,O5 .0& ,op,oc
,+z ,/( i,o7, g/ ,./0', o5
/./o g /./8 y A
gT .ZC g ,/9 g zT /.+o g /./Z 9 /sz 9 ACCEL. ALLOWABLE ACCEL. ALLOWABLE ACCEL. ALLOWABLE VERTICAL A T
.Z$ 9 25'g Zg ./19 HORIZONTAL
/ 78' g z,Ãg 9g i,~5g
- HORIZONTAL ACCELERATION =
2 (AxT) + (AzT 2
-r<-TIB EDYNE T echnical Report Tg-5364-. 4. 6-89 ENQINEERINQ SERVICES Revisten 0 DONALD C. COOK BY: ~5 DATE: 75 UNIT ¹2 CHECKED BY: DATE: P- %89 PROJECT 5364 VALVE NO. /Y@o-i5/ /Yir)o-g/z NODE NO.
c 7J ACCELERATION ACCELERATION ACCELERATION A. ' A A A A A A
.3K /9 .39 .78 .eo .39, 9o hC O
CD M UJ w I O C/l CY Y of .sl .C, , I(,og;/ I ,/z .i9 CD Z,5'o .z+, 0/ .e9 C/l , 93 l C/l M C/l C/l CL LU A yT ,3Z g C/l M zT /'.og 9 /,c/g g ACCEL. ALLOWABLE ACCEL. ALLOWABLE ACCEL. ALLOWABLE VERTICAL A T
~ Z2 9 <<9 ~s HORIZONTAL
//~j >9 . J.o7g /C5g
- 2 + 2 HORIZONTAL ACCELERATION = (AXT) (AzT)
s< TELEDYNE Technical Repot t ENGtNEERtNl- SERVICES TR-5364- 4 Revisi'on 0 6-90 DONALD C. COOK BY: lDATE: 5 UNIT ¹2 PROJECT 5364 CHECKED BY: DATE.'7 5-VALVE NO. 4E~-/5 / /Ygv'-/5g e'dv'-ll'3 NODE NO. ACCELERATION ACCELERATION ACCELERATION A A A A AAy A x,51 Dlw hC D U MM C/7 Oc
,oa ~ /2 ,o9 .ZZ /O 1 .8( 2Z /,Es ,7Z ,/g /-z4
/oZ /,58 ,$z A
yT ~ 30 9 ,25 9 , 3T J A T /.ck 9 /.5(. $ ACCEL. ALLOWABLE ACCEL. ALLOWABLE ACCEL. ALLOWABLE VERTICAL A T
$ 0g gp i i P7y 379'.
HORIZONTAL 3g 7Cy
- 2 2 HORIZONTAL ACCELERATION = (AxT) + (AzT)
Technical Report rs-TELEDYNE TR-5364-4 6-91 Revision 0 ENQINEERINQ SERVlCES 6.3.2 SV Transient Shock Valve Accelerations
r> TELEDYNE Technical Report.. 6-92 ENGINEERING SERVICES TR-5364-4 Revision 0 DONALD C. COOK UNIT 82 BY: DATE:7 / - 9 PROJECT 5364 CHECKED BY: wc: ~ra)gs VALVE ACCELERATIONS VALVE
+v-qEA NODE NUMBER
/9Ão gKyo VALVE WEIGHT DIRECTION X FORCE (LBS)
ACCELERATION ALLOWABLE 9'9/7
/cVP
/,60
/8', Cia/
Z/zg,'7/,89" / 1z 6/o 2g g9o
/.sbg 9+
VALVE NODE NUMBER
/o5 VAI VE WEIGHT DIRECTION FORCE (LBS) g0 t /914 //4Z ACCELERATION y qq g,D/ /k7 ALLOWABLE
-r~ TELEDYNE Technical Report, ENG1NEERING SERVlCES 6-93 TR-5364-4 Revision 0 DONALD C.
UNIT 82 COOK PROJECT 5364 CHECKED BY'ATE: - X 8& BY: DATE: 7 VALVE ACCELERATIONS VALVE A/Mo- ls/ ISO- iSZ NODE NUt1BER VALVE WEIGHT
+do Z.Ss goo ~~
DIRECTION FORCE (LBS) ygyi 688 Ji7t is~@ AV ACCELERATION y gg /. 7Z~ g~ 994 g,S7~ ALLOWABLE 9+ Zg VALVE O'Ho-15s NODE NUMBER Z7/ VALVE WEIGHT DIRECTION FORCE (LBS) ACCELERATION g i8 J pcs i. 28~ ALLOWABLE
s< TELEDYNE 6-94 ENGINEERING SERVICES Technical Report TR-5364-4 Revision 0 DONALD C. COOK BY: DATE: 9 UNIT 82 PROJECT 5364 CHECKED BY: f774 DATE: 7 5/cS VALVE ACCELERATIONS VALVE NfV- j5I hlfYV-iSZ NODE NUMBER VALVE WEIGHT DIRECTION (LBS) FORCE P9'z ACCELERATION z,m~ Sop i 99~ ALLOWABLE 3 Z~ 8y VALVE ARv- Is@ NODE NUMBER VALVE WEIGHT DIRECTION X FORCE (LBS) ACCELERATION 2, ob> , 76~ ALLOWABLE
ir Technical Report >< TELEDYNE TR-5364-4 Revision 0 6 95 ENQINEERINQ SERVICES 6.4 Nozzl e Loads Forces and moments for the'four pressurizer nozzles and the quench tank nozzles are given in this section for all loading conditions. The directions indicated represent the load on the appropriate nozzle.
0 Technica1 Report 6-96 TELEDYNE TR-5364-4
~
Revision 0 ENQINEERINQ SERVICES NOZZLE LOAD
SUMMARY
SHEET DONALD C.~ COOK BY: DATE:~+ UNIT- 82 DAyE.~T/X/P9'~< PROJECT 5364 CHECKED BY: GLOBAL COORDINATE SYSTEM NORTH NODE NUMBER DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y QZ FX FY FZ MX MY MZ IGHT-1 70 -Zoo -922o -~go THERMAL-1 5gu //So 89q~o ~/rw -///0 THERMAL-2 )ao -//0 -277ZO THERMAL-3 8'9 -52~ SEISMIC-OBE ~4/i@ SEISMIC-DBE
/szf ~zgyy BLOWDOWN-SV -/8~7 /ogz5 f7DSg /7947]
~lW +/~4~
~Sf'//7 BLOWDOWN-PORV -~AS/ ~Sere U DISPLACEMENTS : INCHES FORCES POUNDS MOMENTS : INCH-POUNDS
~ ~
I I I'
) ~
rr J r Jr r r i / g g 4 P ~r /'r r) rj r rf rf~ irrr ~ ~ I I II II
'~M~~m~~~ ]+ t' r rr
Technical Report 6-98 r< TELEDYNE TR-5364-4 Revision 0 ENQINEERINQ SERVICES NOZZLE LOAD
SUMMARY
SHEET D ALD C. COOK BY: OATE:~+ UNIT f2 PROJECT 5364 CHECKED, BY: DAVC:~>> GLOBAL COORDINATE SYSTEM NORTH NODE NUMBER DESIGN LOADINGS DI SPLACEMENTS FORCES MOMENTS
+X +Y QZ FX FY EIGHT-1 -9'/0 gg -7/9D -2'0)go T MAL-1 -pe /47% -luFN -QZ90 THERMAL-2 -+70 Zo bgbd -9Ko 79o THERMAL-3 -//Z 8]7 W.+z SE ISMI C-OBE - /g/0 "7Wo ~/s9s SEISMIC-DBE +]RV /90'JK818 9149 BLOWDOWN-SV ~y87z '(<88 'S$ 88 BLOWDOWN-PORV ~ W ~yzlz ~zo8i DISPLACEMENTS : INCHES
.FORCES POUNDS MOMENTS : INCH-POUNDS
Te'chnica1 Report rs TELEDYNE TR-5364-4 6-99 Revision 0 ENQINEERINQ SERVICES NOZZLE LOAD
SUMMARY
SHEET DONALD C. COOK BY: OATE N~8 UNIT 82 PROJECT 5364 CHECKED BY: DATE: GLOBAL COORDINATE SYSTEM NORTH NODE NUMBER +i8 DESIGN LOADINGS DISPLACEMENTS FORCES MOMENTS X +Y FX FY FZ MX MY MZ EIGHT-1 d -989'lo /9/do -Isa -gs7d TH RMAL-1 -sro -8@o -spy Z/H'2477 z407o THERMAL-2 'Fo oo -/o -9~o /Shoo THERMAL-3 Zbd -lee l85 -3757 8<so gpss SE ISMI C-OBE 7'//oo +zz& ~)4(93 '7<ok SEISMIC-DBE BLOWDOWN-SY
'ul -'18'SSI ~9742 ~ZSH ~l~
'r-AcZ ~g>8~ 'yqN r SLOWDOWN-PORY
//sN ~/ooo /Ms DISPLACEMENTS : INCHES FORCES POUNDS MOMENTS : INCH-POUNDS
Technical Report -~<-TELEDYNE TR-5364-4
~ 6-100 ENG!NEERlNG SERVlCES Revision 0 NOZZLE LOAD
SUMMARY
SHEET DONALD C.~ COOK BY: DATE:~~8~ UNIT f2 PROJECT 6364 CHECKED BY: DATE:~7 GLOBAL COORDINATE SYSTEM NORTH NODE NUMBER
+Z P
'ESIGN LOADINGS DISPLACEMENTS fORCES MOMENTS FX FY FZ EIGHT-1 -/sc ro /BSo ~Dzo -/99ro THERMAL-1 7D -do -jingo -Srzr THERMAL-2 9ld<D zd 4 THERMAL-3 297<~ s%s7 SEISMIC-OBE +lgz ~iizt~) ~i~z<8 SEISMIC-DBE
~179 -/~sos BLOWDOWN-SY 85< S9d 2$ so /o854
+pop'P9cl BLOWDOWN-PORV Coz48 ~N+< /g8f /ryder DISPLACEMENTS : INCHES FORCES , : POUNDS MOMENTS : INCH-POUNDS
Technical Report 6-101 -r<-TELEDYNE TR-5364-4 Revison 0 ENQtNEERlNQ SERVlCES 6.5 Valve Loads Section 6.5 gives the moments on each end of all valves in the piping system for all loading conditions. The moments reported are those acting on the pipe at the point where the valve and pipe meet.
~
~
~ ~
C
r< TELEDYNE Technical Report ENGINEERINQ SERVICES TR-5364- 4 Revision 0 6-103 VALVE END MOMENTS Donald C. Cook Unit A'2 BY: DATE:F- 9 Project 5364 CHECKED BY: k~5 DATE:7//<~~3 VALVE NUMBER
.NODE
/o9, /a7 .
MX MY MZ DEADWEIGHT 7OB HERMAL-1 HERMAL-2 -/os'/ /d/8Z HERMAL-3
-/<C5Co -/99~1 /QJZo EISMIC OBE 98>s + "7O / + F4C /+4 EISMIC DBE ~ ]w/s/ 7'/997 + ~88/
LOWDOWN PORV + )SD
+'ag ~79'aa7 LowDowN sv /g7p J +fg'/// +gag VALVE NUMBER NODE MX MY DEADWEIGHT HERMAL-1 HERMAL-2 HERMAL-3 EISMIC OBE EISMIC DBE LOWDOWN PORV LOWDOWN SV UNITS: INCH-POUNDS
r< TELEDYNE Technical Report 6-104 ENQlNEERINQ SERV(CES TR-5364- 4
~ ~
Revision 0 VALVE END MOMENTS Donald C. Cook BY: DATE: /8 89 Unit ¹2 Project 5364 CHECKED BY: DATE:7 /K VALVE NUMBER lr- /9) NODE MX MX MZ DEADWEIGHT /9o5 /898 9>9 / do /0 o HERMAL-1 657 /7 / -6/49 -25'7o HERMAL-2 A7s5' 9 -zs79'5
-/0/5 -2o4q HERMAL-3 798 79K -7g+ 69o EISMIC OBE 70o8 ~ b l<Z ~/589 + 7q'4/ ~78/4 ~ 6/s/
EISMIC DBE + ///qc <enz 'ace~ ~ymss < Ps~ LOWDOWN PORV ~ ss7c ~//zW Fd 7/ ~add / SV ~ ggg7'//4p +///pg +/y7/g JDfrgg 5/f+7g
~/&47'OWDOWN VALVE NUMBER /LJW NODE MX MY MZ DEADWEIGHT 6OZ~ ZCo7 HERMAL-1 -SO77 s +/ -//d8z -+S8/
HERMAL-2 -Z5B/ /84z Dd -&Sdz - /e~ HERMAL-3 Z4/z 92 SS+b -ro EISMIC OBE ~ 6Z'P4 ~ d7 +ir~e ~>8~8 EISMIC DBE ~ygoto + /~Z/ <790 +/8074 7'/7/ O 7 LOWDOWN PORV 8687 Sdd'/ -/O Z -47o9 do9
+
LOWDOWN SV ze97 -/rasa /86 +/9/bo 4099' UNITS: INCH-POUNDS
r< TELEDYNE Technical Report ENGINEERLNQ SERVtCES TR-5364- 4 6-105 Revision 0 VAI VE END MOMENTS Donald C. Cook BY: DATE: ~ 5-Unit 5'2 Project 5364 CHECKED BY: /8 DATE:~//9 /0 VALVE NUMBER
. NODE MY DEADWEIGHT 8ow -zz~
HERMAL-1 uo80 <B8s HPB9 HERMAL-2 888Z /8~ /Zdc -/os% HERMAL-3 EISMIC OBE Z28ob S/OC + gP/5'6dz
+ </l@
gz8y -4zsd 7/24 82'~ ZdO~ ZFB EISMIC DBE 87& + 7Sl'Z 7 + ymZ "- P/W </SSÃl LOMDOMN PORV ~ g70O ~ ZD9'b +gazed "z997 ~7&46 LOWDOWN SV qadi~ ~g tggyg ~gg g pe + yggP VALVE NUMBER 0- 5Z NODE MX MZ MY DEADWEIGHT HERMAL-1 9'87> -4l bd Bd S5 pP -89zz HERMAL-2 882 -4864 487/ 6 /B9 -6974 HERMAL-3 S-o8 -bcas- s<gi zino -F8dr EISMIC OBE rz9C +sr z +ts8 ~9"izu EISMIC DBE + bZ98 +9 87 ~yE%6 LOWDOWN PORV +zM8V +as86 +%PC '1<8 ~d 97i LOMDOMN SV -J Z5@ Idol< - 44T '-668 ~ ddt UNITS: INCH-POUNDS
sc TELEDYNE Technical Report 6-106 ENGINEERINQ SERVICES TR-5364- 4 Revision 0 VALVE END MOMENTS Donald C. 'Cook BY: DATE: 7- 189 Unit I'2 Project 5364 CHECKED BY: ~~ DATE:~V// /PX VALVE NUMBER NODE 2'6Z MX
-zz DEADWEIGHT HERMAL-1 HERMAL-2 H
4'~8'8/ 9o h9'8 -BB/8 -Wc
-9589 o -ZolW
-ada~ -a~a
-B96O HERMAL-3 -SZ8 /O9 EISMIC OBE os'/49' re ~ Ze +zeus~
EISMIC DBE +/95do ~ /zs/ +69/8 ~B/ZO LOWDOWN PORV + 8579 ~/Z9b ~ /zi ~/9~4 ~/sc W LOWDOWN SV ggg/ < ffgP ypgy f gyp f @ryan f gg//'ALVE NUMBER NODE MY DEADWEIGHT /eo -/G/ M0 S 0 HERMAL-1
-l/oh'5'8/
gQO OZD -// OO -ZSd C -Z/W~ HERMAL-2 -/MZ' -%4og HERMAL-3 -9/8C EISMIC OBE ~z/87 O/dr ~ZV/O EISMIC DBE yboE +>dZ ~u'/eZ <q/Sa + <DZ LOWDOWN PORV +85+/ +//Z4 '<Za/ <g pg ~/z/ LOWDOWN SV + y84 < 45Zd ~ gpy ~98// UNITS: INCH-POUNDS
.Techni.ca1 Report -~<-TELEDYNE TR-5364-4 Revision 0 7-1 ENGINEERINQ SERVICE~I
~" ~
7.0 DRAMINGS
-<<-TELEDYNE Technical Report TR-5364-4 ENQINEERINQ SERVlCES Revision 0 8-1
8.0 REFERENCES
- 1. Letter, from Mr. S. Ulan of AEP to Mr. L. B. Semprucci of TES, dated November 29, 1982.
- 2. Teledyne Engineering Services Technical Report TR-5364-2.
- 3. Crosby Valve and Gage Company Drawing No. H-51688, Revision A.
- 4. Technical Paper 8410 by Crane.
- 5. Westinghouse Electric Company, Drawing No. 110E272.
- 6. ITI Report, "Evaluation of RELAP5/NOD1 for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads," February 1982.
Prepared by Intermountain Technologies.
- 7. Review of Pressurizer Safety Valve Performance as observed in the EPRI Safety and Relief Valve Test Program. WCAP-10105.
- 8. ASME Code NB7000, Section III.
- 9. Teledyne Engineering Services Technical Proposal PR-5653, dated May 14, 1981.
- 10. TES letter 5364-44, dated May 28, 1983 from Mr. P. D. Harrison of TES,.
to Mr'. Sam Ulan of AEP.
-A TELEDYNE Technical Report TR-5364-4 ENGtNEERlNG SERVICES Revision 0 8-2 8.0 , REFERENCES Continued
- 11. Letter from Mr. S. Ulan of AEP to Mr . P. D. Harrison of TES, dated March 15, 1983.
- 12. Letter from Mr. Sam Ulan of AEP to Mr. P. 0. Harrison of TES, dat'ed May 26, 1983.
- 13. 1967 Edition of USAS B31.1 Power Piping Code.
- 14. 'etter from Mr. J. L. Williams of AEP to Mr. L. B. Semprucci of TES, dated September 16, 1982.
1
- 15. EPRI Power Safety and Relief Valve Test Program Guide for Application of Valve Test Program results to Plant-Specific Evaluations. Interim Report, July 1982 (Research Project V102).
AMERICAN ELECTRIC POWER SERVICE CORPORATION 2 BROADWAY NEW YORK, NEW YORK 10004 TECHNICAL REPORT TR-5364-4 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.1, UNIT 2 JULY 18, 1983 NCTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-890-3350
Techni cal Report rs TELEDYNE TR<<5364-4 ENGINEERING SERVICES
~ ~
Revision 0 I TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
Book 1 of 3
2.0 CONCLUSION
S 2-1 3.0 SYSTEM DESCRIPTION/DISCUSSION 4.0 THERMAL FLUIDS ANALYSIS 4-1 4.1 Introduction 4-1 4.2 RELAP Model 4-3 4.2.1 Pressurizer'onditions 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 4-3.7 4.5 RELAP Plots 4-23 4.6 Force Time History Plots 4-72 4.7 RELAP Input 4-143 4.8 REP IPE Input 4-162 4.8.1 REPIPE Input - Section A 4-163. 4.8.2 REPIPE Input - Section B 4-170 4.9 Appendix A 4-178 5.0 STRUCTURAL ANALYSIS Book 2 of 3 5-1
'.1 SV Transient Thermal Analysis 5-2 5.2 Transient Shock Analysis 5-2 6;0 ANALYTICAL RESULTS 6-1 6.1 Stress Sumary 6-1 6.1.1 Equation C-1 Stresses 6-5 6.1.2 Equation C-2 Stresses 6-17 6.1.3 Equation C-3 Stresses 6-29 6.2 Support Loads 6-41
Technical Report rs TELEDYNE TR-5364-4 Revision 0 ENGlNEERlNG SERVlCES I TABLE OF CONTEHTS Continued PAGE 6.3 Val ve Accel er ations 6-86 6.3.1 DBE Seismic Accelerations 6-87 6.3.2 SV Transient Shock Valve Accelerations 6-91 6.4 Nozzle Loads 6-95 6.5 Valve Loads 6-101 7.0 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 Tr ansient Shock Input
Technical Report A TElEDYNE TR-5364-4 Revision 0 ENQ,INEERINQ SERVlCES
.'N
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.1 for the Donald C. Cook Nuclear. Power Plant, Unit P2. This activity was performed in. a'ccordance with the TES guality Assurance program which meets the requirements of 10CFR50, Appendix 8, 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. Ulan (AEPSC) dated May 28, 1983 (Reference 10). The majority of the analysis was performed after the receipt of AEPSC letter s dated November 29, 1982 and March 15, 1983 (References 1 and ll), which were issued after more complete information was available from %he EPRI data. This analysis was per formed 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.
~< TELEDYNE Technical Report ENQINEERINQ SERVICES TR-5364-4 ~ ~
Revision 0 2-1
2.0 CONCLUSION
S The analysis performed by TES on the Pr essurizer Safety/Relief Valve Discharge Piping System with the Safety Valve loop seal drained, indicates that all criteria of NRC NUREG-0737, Item II.D.l are met, with the following qualifications:
- 1) Valve accelerations due to the SV transient shock condition for valves SV-45A 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 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.
2-GRC-R-585 2-GRC-R-605 2-GRC-R-586 2-GRC-S-609 2-GRC-S-587 2-GRC-S-611 2-GRC-R-589 2-GRC-S-624 2-GRC-R-591 2-GRC-S-626 2-GRC-S-596 2-GRC-S-629 2-GRC-S-598 2-GRC-S-630 2-GRC-S-599 2-GRC-S-631 2-GRC-R-600 2-GRC-S-632 2-GRC-R-601 2-GRC-R-633
~~ TELEDYNE Technical Report ENGlNEERlNG SERVlCES TR-5364-4
~
Revision
~
0 2-2 This report documents that the safety/relief valve discharge piping for Unit 2 is acceptable for emergency conditions assuming drained loop seals. TES Technical Report TR-5364-2, 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 str ess on the discharge system, see Technical Report TR-5364-2, 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 summary sheets have. been included in this report for all supports and supercede the loads reported in TR-5364-2.
4 r<-TELEDYNE Technical Report ENGINEERlNG SERV(CES TR-5364-4
~ ~
Revision 0 3-1 3.0 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-5761, Revision 2, generated 'rom AEP drawings 2-GRC-22, sheets 1 and 2; 2-GRC-23, sheets 1, 2 and 3; 2-GRC-24; 2-GRC-25; 2-5435-26; 2-GRC-27; 2-5435-8; 2-RC-22, sheets 1 and 2; 2-RC-23, sheets 1, 2, and 3; 2-RC-24; 2-RC-25; 2-RC-26;,a'nd 2-RC-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 pressurizer, complicates the modification effort in
~
addition to causing longer run times.
~ ~ ~
~
Modification of this complex system, to attempt to secure satisfactory
~ ~ ~ "Safety Valve,'Discharge" results, is limited to draining the SV loop seals.
Heating the loop seals is not a viable "fix" because of the size of the loops. These long loops contain sufficient quantity of water such that on SV Discharge, the water seal does not "flash" completely enough to reduce the very high, loads caused by the water slug. Modification to the support system is also a poor option because of the very limited space in the annulus around the pressurizer, which makes construction very difficult.
Technical Report -rs-TELEDYNE TR-5364-4 ENQINEERINQ
~ ~
Revision 0 SERVICES'.1 4.0
~ THERMAL FLUIDS ANALYSIS Introduction The following thermodynamic fluid analysis determines the fluid forces which act on the pressurizer safety valve dischar ge piping of the American Electric Power Service Corporation (AEPSC) Donald C. Cook Nuclear Power Plant, Unit 2.
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; RELAP5 MOD1 was chosen. RELAP5 MOD1 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.'hen the safety valve opens, the loop seal is shot through
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the discharge piping with tremendous force. In TES Technical Report TR-5364-1,
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TES performed a fluid analysis to determine the magnitude of the loads applied
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Technical Report TR-5364-4 r<-TELEDYNE Revision 0 4-2 ENGINEERING 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-536$ -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 seal 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 2 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 'ata 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
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each segment of axial, unbalanced is analyzed structurally. 'oads
~s-TEUHXNE Techni cal Report ENGINEERING SERVICES TR-5364-4 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 condition as specified by the AEPSC, November 29, 1982 letter to Mr. L.B. Semprucci, pages 1-7, (Reference 1):
~5f t Pressure Time History (in the pressurizer) 2750 e 62750
, ~Pi 2750 2700 2700 2667 650 Pressure (PS1) 2600 < 2600 2550 o'2555 o 2514 l.o 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).
A-TELEDYNE Techni cal Report ENQlNEERlNQ SERVlCES TR-5364-4
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Revision 0 4 4 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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Techni cal Report TR-5364-4 O~ TIELEDYNE ENQINEERINQ SERVICES Revision 0 4-8 DATE+IKU CO-N SHEET NO ~ OF~ CIIKO. BY~C/ CATE~// 83 A)UCcEAk GAJ- <7A71CA/ UA)ITS 4 5 2 PROJ. NO. D&bk
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Technical Report ~R-R364-. 4 Revision 0 Pb TELEDYNE ENQINEERINQ SEIMGES 4-9 OA eel e I IV 83 aaVPLD C.. /'~"Oi SHEET NO. OF~
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Technical Report rs-TELEDYNE TR-5364-4 ENQINEERlNQ SERVlCES 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 recomended 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 schematic of the discharge system modeled in RELAP for the SV Unit 2 model is represented in Figure 4.7.1.
Technical Report TR-5364-4 4-12'-TELEDYNE ENQlNEERlNQ SERVtCES Revision 0
.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. Figure 4.2.1 represents the D.C. Cook Unit 1 and 2 quench Tanks. Pressure in the air volume of the quench tank never exceeded 30 psia during the Unit 2 SV transient case of steam and drained loop seals RELAP5 run for 0.5 seconds.
Technical Report A TELEDYNE ENGINEEIRING SERVICES 4-13
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-~II TIELIEDYNE Technical Report ENQINEERINQ SERVICES TR-5364-4 evision 0 4-17 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 9 3X Accum. ~IN2 Time Sec Crosb 452,393 435,000 3.6 in2 0.010 afety Relief (Ref. 15) Val ve
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1 The maximum rating for
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steam at 3X accumulation value is from the Crosby Valve and Gage Safety Valve Drawing No. H-51688, Revision A (Reference 3). e 2 Flow rate at 2500 psig plus 3X accumulation.
A TELEDYNE Technical Report ENGlNEERlNQ SERVlCES TR-5634-4 evision 0 4-18 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(5 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 summary 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. WT
= 51.5 AP Napier's Eq.
ASME rated flow: WR
= 51.5A (1.03P + 14.7)(.9)(.966)C (Ref. 8) where:
WT
= theoretical flow WR
= rated flow H
coefficients: 1.03 - applies 3X accumulation 0.966 - valve flow coefficient 0.9 - represents theor etical flow rate reduced 10K to equal ASME rating C = 1.0771 calculated on Figure 4.4.1-2 following.
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Technical Report TR-5364-4 Revision 0 FIGURE 4.4.1-4 FIGURE 3-5 STEAN OISCHARGE CYCLE (STABL") 600 CROSBY 6M6 4-22 600 400 8 30 U H Cl Vl 200
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-~~-TELEDYNE Technical Report ENGINEER(NQ SERVlCES TR-5364-4 evision 0 4-23 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 accur ately 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.
TR-5364-4
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)4 TELEDYNE ENQlNEERlNQ SERVlCES Revision 0 4-24 FEY-4P HoDE'C SHEET HO OF SCHEMATIC.
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Technical Report A TELEDYNE TR-5364-4 ENQINEERINQ SERVICES
~ ~
Revision 0 4-72 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 2 has 67 pipe segments and correspondingly 67 force time histories.
\
TR-'S3o"4 'evision 0 yq ~LEDYNE ENQlNEERlMQ SERVlCES Y C.EY OATS~SF~ B ~Q )gg, 5TQ&c. pugAL Noh'pe~~fQ SHEET NO. / OF 8 CHKO, BY OATS~F8 P+R'4 Sic-T> oN CQ (gQ FIGURE 4.6.1-1
)< TELEDYNE ENQINEERINQ SERVlCES Revisi.on 0 4-74 y CZC DATg 3-JJ-83 'v~ IT Z SHEET NO. 2 OF 3 STRvcTVRAI goyZ pIoIu~
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zR-s3s4-e Revision 0 A TELEDYNE ENQ1NEERINQ SERVlCES DATE~+/I > CHKD. BY~DATE ~ ~l
<Mif2, 4-75 STRuC.TVRAt MODE 'po ups
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Technical Report Tk-5364-4 Revision 0 4-76 l!48iNlfING SERvI cEs SAP2SAP VERIFI CAT ION 5364 6"JUL"83 DC COOK UNI T2 r SV NODIF I CAT ION TINE/FORCE TABLE ) e MAGNITUDE AT NODE POINT 2)6 T I HE 00 0.2) 0.29 0.36 0.43 0+SO ~00 ~l C) ~$ OO LO I EO LO Cb C7 I CV D fP I
Technical Report TR-5364-4 Revision 0 4-77 lklL NING 6" JUL" 83 sERY I cEs SAP2SAP VERIFI CATION 5364 DC GOOK UHI T2 r SV HODI FI CAT ION TINE/FORCE TABLE 2. HAGNI TUDE AT NODE POINT 214 TINE 0.45 0. 50 00 ~ 7 0.2) 0.29 0.36 <a lY~ C) ~Ok
Technical Repot t TR-5364-4 Revision '0 4-78 5)NN)ING sERYIQEs SAP2SAP YERIF I CATION 5364 6-JUL-83 DC COOK" UH I T2 e SV MODI F I CAT I OH TINE/FORCE TABLE 3 ~ HAGHITUDE AT HODE POIHT 00 C7 0 CO T I HE, 00 D. 23 0.29 0 36 Vcu CL D 'IO CO 00 I 00 CO I
Technical Report TR-5364-4 Revision 0 4-79
~535[Iins sEsv~cEs SAP2SAP VERI F I CAT ION 5364 6-JUL-83 DC COOK-UN I T2 e SV NODI F I CAT I ON TINK/FORCE TABLE 4e MAGNITUDE AT NODE POINT 205 lO Ol 00 7 0 'i T INE 0 '9 Oi36 0+45 0.$ 0 0
~CO CO O I CO CO o EO
Technical Report TR-5364-4 Revision 0 4-80 lklH)ING'sERv t cEs SAP2SAP VKRIFICAT ION 5364 6- JUL-83 DC COOK"UNI T2r SV MODIFICATION TIME/FORCE TABLE 5e MAGNITUDK AT NODK POINT 202 TIKE 0.2) 0.29 0.43 0 50
Technical Report TR-5364-4 Revision 0 4-8l Str58)ING SERVICES SAP2SAP VERIFI CAT I OH 5364 6- JUL" 83 DC COOK-UHIT2e SV MODIFICATION TINE/FORCE TABi E 6r MAGNITUDE AT NODE POINT )96 T THE 0 00 0 0.'l 4 0.2l 0.29 0.36 0.43
Technical Report TR-5364-4 Revision 0 4-82 345831NG sERv't t;Es SAP2SAP VERIFI CATION 5364 6"JUL"83 DC COOK UHI T2 ~ SV NODIFI CATION TIt1E/FORCE TABLE T. MAGNITUDE AT NODE POINT 1 8F' T I NE 00 0. O.l4 023 9 .35 0.$ 0 EO 04 I 'b C4 og 9 l
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Technical RepoI t 4-83 TR-5364-4 Revision 0 kkkRIING SERVICES SAP2SAP VERIFICATION 5364 6"JUL"83 DC COOK-UNIT2t SV MODIFICATION TIME/FORCE TABLE Sr MAGNITUDE AT NODE POINT CO tO TINE 0 00 0.0 0.)4 '21 29 0.36 0.45 O I a ill I LLjo Mcn lK CD
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Technical Report TR-5364-4 Revision 0
@HNNING SERVICES SAP2SAP VERIFICATIOH 5364 6- JUL"83 DC COOK-UHIT2e SV NODIFICATIOH TINE/FORCE TABLE 9 ~ HAGHI TUDE AT HODE POIHT 182 lO OI IO T INE 00 0-07 0.)4 .2l 29 0.36 0.43 0.50 o
CO CO
~ ++
I LO o lO o Oo ~00 O I ~lO ~IO ~C4 U 7 o Ltl o CO IO CO I
Technical Report TR-5364-4 Revision 0 lfkiSNkING sERY I cEs SAP2SAP VER IF l CAT l ON 5364 6- JUL-83 HAGGAI DC COOK-UHlT2. SV HODIFICATlOH T l HE/FORCE TABLE ) De TUDE AT NODE POI HT 00 0.07 Oel4
- 0. 2)
TIf1K
.29 0.36 '.43
Technical Report TR-5364-4 Revision 0 SAP2SAP VERIFICATION 5364 6- JUL-83 DC COOK-UNIT2e SV HODIFICATION TINE/FORCE'ABLE t1. MAGNITUDE AT NOPE POINT )TS h 0$ CV Ol T I NE 0 00 0.07 0.)4 0'2) ~ 29 0.36 0.43 0.50 ~l M ~ . ~tO a~ LL7
'0 1
;0
Technical Report TR-5364-4 Revision 0 4 7
~5>%5IRs sERvIcEs SAP2SAP VERI F I CATION 5364, 6- JUL-83 DC COOK"UNIT2e SV MODIFICATION TINE/FORCE TABLE 1 2e HAGNI TUDE AT NODE POINT CO CO CV T1NE 00 4 7 0. 1 0 F 28 0.56 0.45
~l QJ CO LL Cl ~CO O IO CO I Ol Ol C) CO I CO o
TR-5364-4 Revision 0 NBIINlfING SERVICES SAP2SAP VER IF I CAT I ON 5364 6"JUL"83 DC COOK-UNIT2e SV HODIFICATION TIVE/FORCE TABLE 13'1AGNI TUDE AT NODE POINT TINE 00 ~ t O. 1 0.28 0 38 Oo43
TR-5364-4 Revision 0 l5H(lNliIRG SERVICES SAP2SAP YERIFICATION 5364 6-JUL-83 DC COOK-UHI T2r SY HODIFI CATION TINK/FORCE TABLE ) 4r HA'GHI TUDE AT NODE POINT f66 Cl CO TIFF. 00 ~ 4 0. 1 0.28 0.38 0. 45 0.50
~ vvl v
~ ~ ~ ~ ~ ~ avg v v TR-5364-4 Revision 0
~56@5>vs sEsvicEs SAP2SAP VERIFICATION 5364 6-JUL-83 OC COOK-UHIT2e SV HODIFICATION TINE/FORCE TABLE 15. HAGGAI TUDE AT HODE POINT 00 0.2l I
T NE 0.29 0.36 0.45 LLJ~ Ch O~ U CO IO I CO C) CO I a h h I
I CVIIII I '4Q I INC@VI 4 TR-5364-4 CAGES Revision 0 SHAN't HG SERV SAP2SAP VKRIFICATION S364 6- JUL-83 DC COOK-UHI T2e SY NODIFICATION TINE/fORCE TABLE 16e MGNITUDK AT HODK POINT 158 Cl Ol Cl C7
~
TINE 00 0.21 0.2S 0.36 0-43 0.$ 0 ~cn a~I LL CV IO I EO h I a 08 Ol CV I
Techni cal Report TR-5364-4 Revision 0 flhB/Nivo sERvrcEs SAP2SAP VKR I F I CAT I OH 5384 6- JUL-83 DC COOK-UHIT2e SV NODIFICATIOH T IMK/FORCK TABLK 1 7 ~ NAGHI TUDE AT HOOK POIHT TINE 0 00 0 Oe)4 0. 1 0.29 0.36 0.43 CO tO CO
~ ++
l UJ~ &co C) ~f0
Technical Report TR-5364-.4 Revision 0 4 " ~NNNNtss sssvicEs SAP2SAP VKRIFICATIOH 5364 '-JUL"83 DC COOK UHI T2r SV NODIFI CATION T INK/FORCK TABLK 1 8 ~ HAGHI TUDK AT HODK POINT Ch O tO Ol T I HE 0 00 0.) 4 0 0.38 CQ tO tO I ~CO ~O ~Oh Cl h o CO Ol I CO tO I
Technical Report TR-5364-4 Revision 0 "-'4
~QP@5>gs sEsvicss .'AP2SAP VKRIFI CAT ION 5364 8" JUL" 83 DC COOK-UNI T2. SV NODIF ICATION TINK/FORCK'TABLK 19e HACNITUOK AT NODK POINT TINE 00 0.0 0.14 1 0- S 0.36 0.43
Technica1 Report TR-5364-4 P Revision 0 4-95 83583't NG sERvl c KS SAP28AP VKRIFI CATION 5364 6" JUL "83 DC COOK" UHI T2. SV HODIFI CATION TINK/FORCE TABLE 20'AGNITUDE AT NODE POINT 136 TINE 00 0007 0.14 Rl 0 9 0.56 0+43 0.50 ba, 07 OJ I IO CO I UJCO M~ ggCh ~Ol tl 7 O CO IO CO I tO h a OJ I CO h h
Technical Report TR-5364-4 Revision 0 4-96
~@II%NING SERVICES SAP2SAP VE',RIFICATIOH 5364 6- JUL-83 DC COOK-UHI T2, SV HODIF I CATIOH TINE/FORCE TABLE 21 ~ HAGHI TUDE AT NODE POIHT 0 00 0.07 0 14 . 2l,. 0.38 0.43 CO I
Technical Report TR-5364-4 4-97 Revision 0 llh$ 6" 8lCING sERYIcEs SAP2SAP VERIFI CATION 5364. JUL-83 DC COOK-UHI T2. SV 'ODIFI CATIOH TINE/FORCE .TASLE 22'AGHITUDE AT HODE POIHT l 32
~ ++
T I NE 0 00 0 07 0+14 .21 2S 0.36 0.43 0.50 CO CO CO I CO CO ICJ t QJ 45 CD e Qh ~04 4-7. CO Ol CO CO Cl I
Technical Report TR-5364-4 Revision 0 4-98 SRB)ING SERVICES SAP2SAP VERIFI CAT ION 5384 6-JUL-83 DC COOK-UNIT2r SV MODIFICATION TINE/FORCE TABLE 23. MAGNITUDE AT NODE POINT 130
,. T I HE 00 0.07 0.14 0.21 .29 0.36 0.45 0.50
Technical Report TR-5364-4 Revision 0 4-99 St%SING SERVI CES SAP2SAP VERIFI CAT ION 5364 . 6" JUL"83 DC COOK-uHIT2. SY HODIFICATIOH TINE/FORCE TABLE 24 ~ NAGHI TUOE AT NODE POIHT '28 T 1 HE 0 0 0-07 0.)4 D. 29 0+43 0.50 a 00 I
Technical Report TR-5364-4 Revision 0 4 '" ~NRNhrvs sEsvicEs SAP2SAP VERIF I CATION 5364 6- JUL-83 DC COOK'UHIT2. SV HODIFICATIOH TINE/FORCE TABLE 25'AGHITUDE AT HOOK POIHT 122 CO CP 40 CO 00 TINE 0.29 0.36 0.43 0.50 00 ~ 7 1 ~ bee o'C CD LO lO I
Techni cal Report TR-5364-4 Revision 0 4-101 5)%NING SERVI CES SAP2SAP VKRIFI CATION 5364 6"JUL-83 DC COOK-UNIT2. SV NODIFICATION TINE/FORCK TABLK 26'AGNITUDK AT NODK POINT 120 TINE 00 ~ T 0. ) 0 '9 0+36 0.43 0+50
Technical Repor t TR-5364-4 Revision 0 4-102
~53583>ve sEavicEs SAP2SAP VKRIF I CATION 5364 6- JUL" 83 DC GOOK-UNIT2e SV MODIFICATION TINK/FORCK TABLK 27r l&GNITUDK AT NOOK POINT TINE e 7 0. ) 0 ~ 29 Oe45
'echnical Report TR-5364-4 Revision 0 4-103
~NIrINrNs sERvrcEs SAP2SAP VERIFI CAT ION 5364 6-JUL-83 DC COOK-UNIT2e SV MODIFICATION TINE/FORCE TABLE 28m MAGNITUDE AT NODE POINT TIME 00 ~ T 0. 1 0.29 0 36 0.45
Technical Report TR-5364-4 Revision 0 4-104 53fNIINS SERVICES SAP2SAP VKRIFICATIOH 5364 6-JUL-83 'C COOK-UNI T2e SV HODIFICATION TINE/FORCE TABLE 29. HAGGAI TUDK AT NODE POIHT TINE
~ 7 0.2) 0.'29 0+43 0 '0
'O O~ 9 I LLJ~ a~CO CO CO 50 I 04 dO h I
lechnical Keport TR-5364-4 Revision 0 4-105 Ilk%SING SERVICES SAP2SAP VKRIFI CAT I OH 5364 6- JUL-83 DC COOK-UHI T2. SV HQDIFI CATIOH T.I HK/FORCE TABLE 30 o IWGHI TUDK AT NODE POINT )03 T INE 0 00 0.) 4 0.2 0.28 0 3S 0.43 0 50 Ol lO I LO CO IC7 I
j cvi>)> i l;a > !CAPUT'K TR-5364-4 Revision 0 4-106
~Q)fQ@iNG SERYICES SAP2SAP AERIFICATION 5364 6-JUL-83 DC COOK-UHIT2e SV NODIFICATION TIME/FORCE TABLE 3) ~ HAGHI TUDK AT NODE POINT TINE 0 00 Oo 0.$ 4 0 2 0.29 0+38 0 43
Technical Report TR-5364-4 4-107 Revision 0.
~NBNI>Ne sEsvrcEs SAP2SAP VKRIFICAT I OH 5364 6- JUL" S3 DC COOK-UHI T2. SV NODIFI CATIQH TIRE/FORCE TABLE 32r HAGHI TUOK AT HOOK PGIHT 88
.T IHE 00 0 0 0.14 0.28 0.36 0.50 C)
Ol 1 CO CO Ol O~ I a a LO h lg'9 OP I
Technical Report TR-5364-4 Revision 0 4-108
~iNNNIivs sEsvrcEs SAP2SAP VERIFICATION 5364 6"JUL-83 DC COOK-UHIT2e SV HODIFICATIOH TINE/FORCE TABLE 33m MAGNITUDE AT NODE POINT , 86 T I NE 0 00 O.OF 0.14 0.29 0 F 55 Oe45 Oe50
Technical Report TR-5364-4 Revision 0 4-109 SLN8lfiNS SEIIV I CES SAP2SAP VERIFICATIOtil 5364 6- JUL" 83 DC COOK-UliIIT2o SV NODIFICATION TINE/FORCE TABLE 34o MAGNITUDE AT HODE POINT T INE DD D.DF Dol4 0 Rl 0.29 0+38
Technical Report TR-5364-4 Revision 0 4-110 3lfHNIIRG SERVICES SAP2SAP VERIFICATION 5364 6" JUL-83 DC COOK-UNIT2e SV MODIFICATION ' TINE/FORCE TABLE 35. MAGNITUDE AT NODE POINT 82 T I HE I/P 0 00 0. 0?'.14 2l 0 ~ 29 K 0+36 0.45 0.50 tO h Of I CO EO yg ~ O O I
~CO o'o U f Cl Of CO CO I
CO CO lO CV I C) CO
'I
Technical Report TR-5364-4 Revision 0 4-111:: flhilN[ING sERvI cEs SAP2SAP VERI F I CATION 5364 6" JUL-83
~
DC COOK UNI T2r SV HODIFICATION T I NE/FORCE TABLE 36. NAGNI TUDE AT NODE POI NT 80 T I HE 00 O.OF 0+14 .21 0.28 0 36 0+45 Oe50 C5 Oi I CO CV tO o> i QJCV ~Cl ~CO C) LL.7 a O Ol i C4 CV i
Technica1 Report TR-5364-4 Revision 0 4-112
~I>'I8hiRs sERvicEs SAP2SAP VKRIFI CATIOH 5364 8- JUL-83 DC COOK"UHIT2e SV HODIFICATIOH TINE/FORCK TABLK Sate HACHITUDK AT HODK POINT TINE 0 00 0.0l 0.14 D.aa 0 ~ 58. 0 45 O'SD CO Ol 0$
O~ ~CO 9 l Ol 40 I lO h CO CO l
Technical Report TR-5364-4 Revision 0 4-113 Sf%NING SERVICES SAP2SAP VERIFICATION 5364 6" JUL"83 DC COOK-UNI T2. SV HODIFICATIOH T I HE/FORCE TABLE 38m HAGGAI TUDE AT HOOK POIHT TIt1E 00 0 'F 0.)4 0~ Oi29 Oe36 Oe43 CO C5
~ >+
l ~ 0 C)g 'Q 9 l QJO LL7 LO
~,
Ol l Ol fO CO l
}i Technical Report TR-5364-4 Revision 0 4-114 5BQ3lMG sERvtcEs SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK"UNI T2r SV HODIFICATION TINE/FORCE TABLK 3Se MAGNITUDE AT NODE POINT TILDE 0 Ol 0. )4 0. ) 0+28 0.58 0.45
Technical Report TR-5364-4 Revision 0 4-115 SLSl83I Nc s ERY I GEs SAP2SAP VERIFICATIOH 5'564 6-JUL"83 DC COOK-UHI T2t SV NODIFICATIOH TINE/FORCE TABLE 40o NACHITUDE AT HODE POIHT O EO 40 EO o CO CC A LI
~t 40 0 00 0.14 2 0.29 Oe58 TINE
0 Technical Report TR-5364-4 Revision 0 4-116
~5hmmfiss sERvicEs SAP2SAP VERIFICATION 5'364 6-JUL-85 DC COOK"UNI T2. SV NODIFICATION, TINE/FORCE TABLE 4). MAGNITUDE AT NODE POINT 404 00 0.)4 0.29 0.38 0.50 T ONE
Technical Report TR-5364-4 Revision 0 4-.117 SHINING sERYIGEs SAP2SAP VERIFICATION 5364 6-JUL-85 DC COOK-UNI T2 e SV NODIF I CAT I ON TINE/FORCE TABLE 42. MAGNITUDE AT NODE POINT 2SO CQ
~ +>
~lO U CO O8 0 00 0.t4 F 29 0+58 0+45 0..50 . EO T lNE Ol I
Technical Report TR-5364-4 4-]18 Revision 0 8LIIING sERY'tcEs SAP2SAP VKRIFIGATI OH 5364 DC COOK-UHI T2e SV HODIFICATIOH TINK/FORCK TABLK . 43m HACHITVDK AT HOOK POIHT 286 a Ol a EO tO lO QJW lK 0 A Oui'INE21 - 0 9 0+58 Oe45 ~lO CO CV CO Ol
$ O I
Technical Report TR-5364-4 Revision 0 4-119
~Nhmmhiss sEsv~cEs SAP2SAP VERIFI CAT IOH 5364 6- JUL"85 DC COOK-UHI T2e SV NODIFICATIOH TINE/FORCE TABLE 44o HAGHITUDE AT NODE POINT 262 Ol CY IO Ob Cl CO 00 40 EO
~CO ~CA LL.g CO 00 .07 0. 14 '0.29 0 38 Oo45 0+50 T INE CO 04 I+ I
lecnnscal Keport TR-5364-4 Revision 0 4-120 IkiIIINGsERYIcKs SAP2SAP VERIFICATION 5384 6-JUL-85 DC COOK-UNIT2r SV NODIFICATIOH TINE/FORCE TABLE 45e MAGNITUDE AT NODE POINT 258 CO C) Ol
'Cl CO C7 h ~lO T ~00 CC aLL.~
tO 00 0. 4 0.28 0+56 0.45 0 50 T IHE 4P
~ ~+
O
Technica1 RepoI t TR-5364-4 Revision 0 4-121 llhNNlhNG sERY IcEs SAP2SAP VKRIFICATIOH 5364 6-JUL-83 DC COOK-UHIT2t SV NODIFICATIOH I TINK/FORCK TABl K 46e HAGHITUDK AT HOOK POIHT 250 Ol h CO Ol Cl ~lO CK C) 0 CQ LO 0 00 0aM 0.50 T7 E CO I
Technical Report TR-5364-4
~ 4-122
~
Revision 0
~5HNirss 6-sEsvfcss SAP2SAP VERIFICATION 5384 JUL-83 DC COOK-UNI T2. SV NODIFI CATION TIME/FORCE TAB'LE 4F ~ MAGNITUDE AT NODE POINT 248 Cl CO Of Of EO QJef A
LL Of lO 00 0 0.38 0+43 Oi50 Of TI E I
Technical Report TR-5364-4 Revision 0 4-l23
/(%NING 6- JUL-83 SERVICES SAP2SAP VKRlFlCATlON 5364 DC COOX-UvlT2. SV VODlFlCATlOV Tlt1K/FORCK TABLK 48. HAGNlTUDK AT HOOK PO1NT 246 lO a
Ol EO 4P tO C) Ol lO ~OI ~CO CC C) U
~
00 0 0 4 0.58 Oe 45 0.50 T E
Techni cal Report TR-5364-4 Revision 0 4-124 SHIIl8$ lNG SERV'tCES SAP2SAP VERIFICATION 5364 . 6- JVL-83 DC COOK-VNIT2. SV NODIFI CATION TINK/FORCE TABLE 49o MAGNITUDE AT NOOK POINT 0.43
Technical Report TR-5364-4 Revision 0 4-125 lkSBIING SERVICES SAP2SAP VKRIFICAT IOH 5364 6- JUL-83 DC COOK"UHI T2r SV HODIFICATIOH TINE/FORCK TABLK 50. HAGHITUDK AT HOOK POIHT 242 I I1E 0.50 g) 00 0 ~,l CC LL CO a I CO CCl CO I
Techni cal Report TR-5364-'4 Revision 0 4-126 SH383ING sERvtcEs SAP2SAP VERI FI CAT I OH 5364 6-JUL-83 DC COOK-UHIT2e SV NODIFICATIOH TINK/FORCE TABLE 51 ~ HAGHITUDK AT HOOK POIHT 240 ES o CO CO CO CO lK C) ~m 00 0.'5S 0 45 Oe50
Technical Report TR-5364-4 Revision 0 lck$ 8$ ING SERVlCES SAP2SAP VKRIFICATION 5364 6-JUL-83 HAGGAI DC COOK-UNI T2. SV NOOIFICATION T I HK/FORGK TABLK 52. TUDK AT NOOK POINT Ch C9 0 00 0 l 0e 0 58 Oe4
Technical Report TR-5364-4 Revision 0 4-128 NL%NING SERVICES SAP2SAP VERIFICATION 5364 6- JUL-83 DC COOK-UN I T2. SV HODI FI CATION TINE/FORCE TABLE 53. MAGNITUDE 'AT NOOK POINT 236 o> <<0 Oo LaS CDm ggIO a L ~000 0 t Oe 0.56 Oe4 0 50
t "I, f 1
)I H
il P
Techni cal Report TR-5364-4 Revision 0 4-129 8388)'tNG sERY'tcEs SAP2SAP VERIFICATION 5364 6-JUL-83 DC COOK-UNIT2e SV NODIFICATION TINK/FORCE TABLK 54'AGNITUDE AT NOOK POINT Vl Cl 0 O CO O Qh T NE
.0 0 l 0. 1 0. 9 tLI~
&co ~o CD LL.7
Technical Report TR-5364-4 Revision 0 4-130 QLIIING sERv1GEs SAP2SAP VERIF I CAT I OH 5364 6-JUL-85 DC COOK UHIT2e SV NODIFICATIOH . TINE/FORCE TABLE 55 ~ NAGHITUDE AT HOOK POIHT
- 0. 0aM
Technical Report TR-5364-4 Revision 0 4-131 lck%5lNG SERVICES SAP2SAP VKR!F I CAT ION 5364 6- JUL-83 DC COOIll-UHI T2. SV NODIFI CAT I OH TINK/FORCK TABLK 56 e NAGHITUDK AT HOOK POIHT TINE 00 0 F 07 0.1 0.21 0.29 0 38 0.43
Technical Report TR-5364-4 Revision 0 4-132 llh$ 6-8$ ING SERVICES SAP2SAP VKRIFICAT I OH 5384 JUL-83 DC COOK-UHI T2. SV NODIF I CAT I OH T I NK/FORCK TABLE ST o HACHI TUOK AT HOOK POI HT o CO a CO IO TINE 0 00 O.OF Oe 4 0.2) 0.29 0.38 Oo43 gCO -9 I U
~CO
~
~CO LL.7
Technical Report TR-5364-4 Revision 0 4-133 StlIN>vs sERvicss SAP2SAP VKRIFI CAT ION 5364 6-JUL-83 DC COOK-UNIT2e SV HODIFICATION TIt1K/FORCE TASLK 58 . IAGNITUDK AT NODE POINT TINE 00 OeOF 0~ 4 Oral 0+29 0.56 0.43 0.50
Techni cal Report TR-5364-4 Revision 0 4-134 lkl@ltNG sERvtcEs SAP2SAP VKRIFI CATION S364 6-JUL-83 DC COOK-UNIT2e SV NOGIFICATION TINK/FORCK TABLK SB e l&GNITUDK AT NGDK,POINT Cl
@II TIME 00 0.07 0~1 0.2) 0+29 0 38 CDn
Technical Report TR-5364-4 Revision 0 4-135 SLSNIfING sERv'tcEs SAP2SAP VKRIFI CAT I OH 5364 6-JUL-83 DC COOK-UHIT2o SV HODIFICATIOH TINK/FORCE TABLE 60' NACHITUDK AT HOOK POIHT Cb o T I HE 00 O.OT Oe 4 2$ 0 29 0.58 Oe43
Technical Report TR-5364-4 Revision 0 4-136 BHNIIHG sERY IGEs SAP2SAP VERIFICATION 5364 6"JUL-83 DC COOK-UNI T2. SV NODIF I CATI ON T I NE/FORCE TABLE 6) e HAGHI TUDE AT NODE POINT TINE 0 00 .or 0.14 21 Oe28 0+58 0.43 Oe50 hLJ~ Q~ CC C) CI LO Ol CO I
Technical Report TR-5364-4 Revision 0 4-137 N 3llLINIRG SERVICES SAP2SAP VKRIFICAT ION 5364 6- JUL-83 DC COOK-VHIT2e SV NOOIFICATIOH TINK/FORCK TABLK 62 e HAGNITVDK AT NOOK POINT CO a CO a Al 0 00 0.0? 0.$ TINE 4 0.2) 0.29 0.38 0.43 a Ol yo Ot
~C9 O I LIJCO lK~
a CO a CO CO CO I
r
~,
Techni cal Report TR-5364-4 Revision 0 4-138 SLS/NING sERY I GEs SAP2SAP VERIFICATION 5364 6" JUL-83 DC COOK UHI T2o SV NODIFI CAT ION T I NE/FORCE TABLE 63 o HACH I TVOK AT NOOK POINT 50 00 O CV CV TINE 00 0.0T 0+14 0.21 0.28 0+58 0+45 0050 CO O~ Ct I ~m CDcy ~o C) ~O Ol CO CO lO I lO CO h I
P Technical Report TR-5364-4 Revision 0 4-139 IL%NING SERVICES SAP2SAP VERI FI CAT ION 5364 DC COOK UNI T2o SV HODIFICATION TINE/FORCE TABLE 64. MAGNITUDE AT NODE POINT O tO Cl Ol ma oo 0.0 0 > T I HE 0.29 0.58 0.43 0.50 CO CO EO l/P
Technical Report TR-5364-4 Revision 0 4-140 53%NIHG SERVICES SAP2SAP VKRIFICAT ION 5384 8- JUL-83 DC COOK"UNIT2e SY NODIFICATION TINK/FORCK TABLK 85. HACNITVDK AT ItIODK POINT 40 CO o Ul TINE 00 0. 0.14 0.2) 0.29 Oe 45 tO co O@ 0 I LLt~ lK '
Technical Report TR-5364-4 Revision 0
~@HONING sERYIGKs SAP2SAP VERIFICATION 5364 6- JUL-85 DC COOK-UN I T2 r SV NODI F I CAT I ON TINE/FORCE TABLE 68m HAGHITUDE AT NODE POINT t~ ~ I TINK 0 14 ~ 2 0 2S 0 5B Oo 45 0-50
Technical Report TR-5364-4" Revision 0 4-142 lllHNS'tNG sERY I GEs SAP2SAP VKRIFICATIOH 5364 6-JUL-83 DC COOK"UHI T2e SV HODIFICATIOH TINK/FORCE TABLK SFe MAGNITUDE AT HOOK POINT / C) Sl CI CKI PJ LEE 00 Ol' 0.29 0.58 Oo43 LtJgg Cbce lK~ a LL.7
r<-TELEDYNE Technical Report ENQlNEERlNQ SERVlCES, TR-5364-4
~ ~
Revision 0 4- 143 4.4 ~RE IR I Included here is the RELAP5 NOD1 input listing for the transient steam case. The SV model has: 387 volumes 386 junctions Heat structures were not included in the RELAP model because of the program capacity. Including heat structures would have further reduced the number
~
~
of available control volumes. This is a conservative assumption, ITI (Reference 6)
~
showed higher loads were computed without heat structures.
RELA 1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAGE 1 LISTING OF INPUT DATA FOR CASE 1 1 =AEP UNIT2 1 LiNE RELAPS 2
- AEP D. C. COOK UNIT2
.,... 4,*
3 5
- DISCHRAGE PIPING THIS IS THE NUMBERING SYSTEM
- WHERE COMPONENTS NUMBERED IN FOR THE:
UNIT2S'ELAP MODEL 100'S ARE VALVE SV-45C AND ARC 1 LEVEL 669'-2" 200'S ARE VALVE SV-45B AND ARC 2 LEVEL 670'-10" 8 t 300'S ARE VALVE SV-45A ARN ARC 3 LEVEL 672'-6" 9
- 400'S ARE PORV NRV-15{ AND ARC "A" 10 f 500 S ARE PORV NRV-153 AND ARC f
"6'1 600'5 ARE PORV NRV-152 AND ARC "C"
- "-- -{3 f 12 --*---- --- 700'S ARE 6" DISCHARGE PIPING
'00>S-A'E" i2'"" "OiSai 14 f 900 S QUENCH TANK PORTION 15
- 999 ATMOSPHERE 16 100 NEW TRANSNT 101 RUN ~
18 102 BRITISH BRITISH 19 104 NOACTION 20 2{ 22 ffffffffttftftttttftffffttttftttttttt TIME STEP 23 ttttftffttttffttttttttttftttttttttft\ f CONTROL 24 25 201 0.500 1.0-7 2.0-4 11001 5 50 250 26 27 ttt tt ftft t t t tf tft t tt tttt t f tfttt t t tt t
\'
28 MINOR EDITS 29 30 tftffffttttfttttffftttffftttftfftffftt 32 33 30{ MFLOWJ 105000000 34 302 MFLOWJ 205000000 35 303 MFLOWJ 305000000 36 304 MFLOWJ 700010000 C 37 305 MFLOWJ 811'140000 38 306 MFLOWJ 811790000 39 307 MFLOWJ 307000000 40 308 MFLOWJ 207000000 41 309 HFLOWJ 107000000 42 310 MFLOWJ 900000000 43 44 311 QUALS 102020000 45 312 QUALS 202020000 46 313 QUALS 302020000 47 314 QUALS 104200000 DATE
, 48, 315 QUALS 204200000 49 50 316 317 QUALS QUALS 304200000 811140000, DHKD. BYCVH DATE > <> >> N 51 318 QUALS 811790000 52 319 QUALS 106010000 53 -320 QUALS 106390000 54, 321 QUALS 206010000 55 322 QUALS 206330000 56 323 QUALS 306010000
RCL I/054 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 3 115 2020 811680000,811690000,811700000,811750000,811720000 1 16 2 121 81 1730000, 8 11740000, 81 1750000. 8 1 1760000, 8 1 1770000 117 2022 811780000, 811790000, 811800000, 811810000. 811820000 118 2023 811830000.811840000,811850000;811860000,811870000 1 19 2024 81 1880000, 81 1890000, 81 1900000, 81 1910000, 8 1 1920000 120 2025 811930000,811940000,811950000,811960000,8'!1970000 12 1 2026 8 1 1980000, 8 5 5990000, 8 53010000, 8 13020000, 8 13030000 C I 0 122, 2027 813040000 813050000p 813060000e 813070000p 813080000
~
123 2028 8 53090000, 8 53 500000, 813 5 50000, 813120000, 813130000 124 2029 813140000,813150000,813160000,853170000,813180000 0 WO 125 2030 813190000, 8 13200000, 8132 10000, 8 13220000, 8 13230000 128 203'I 8 13240000, 8 13250000, 813260000, 813270000, 813280000 127 2032 813290000, 813300000, 901010000,901020000, 903010000 128 2033 903020000,903030000,903040000,903050000,903060000 129 2034 903070000.903080000 130 131 132 t 134 135 138 tefffttffffffttftttffefttffteffete
' " "'""""""""""e'""""" """""""'"'
)37 e TRIPS 538 fttttttftttttttettttttttttftttfftt 139 140 501 P 907050000 GT NULL 0 114.7 f
L *QUENCH TANK BLOW OUT PATCH I...................-...............--. ------ I
~ ---"I-- ~
145 503 TIME 0 GE NULL 0 0.0 L VALVE OPEN 142 504 TIME 0 GE NULL 0 5. 0 L
- VAI.VE CLOSED 43 600 504 144 145 tfettffttttttffftffttttttttfttttttftte'ffffttttfttttt f '"'"
146 347
'"'i" ' tfttetftetttteteeeettetteet
'"KYD'RODY'HAMIC"'COMPONEAT'S"e"""
148 fettfftffteetttttttttftftff iit'iff0tfsttifif tiiitffffet'et'f'f'f't'ai'f'et tee Se'fif'et eettef
)49 '51"""'i 150 152 153 ftfttftfttffffe'ttffee*fftfttftfftetffttft\tfft 154
- SAFETY VALVES DISCHARGE SECTION 55'5 fffefffft*fffttfffftf*ttfftetftetf'tfftffffftff Z'. Pl 158 157 158 559 ftffttftfttttfffetttettttftftfftfttttttttttttttttetttftffftttttt 669'-2" 560 e SAFETY VALVE-45C DISCHARGING AT ELEV, ARC 161 effefetfttftfefftftttttttfftttiefiiifeefeffttftttfffttffttffffff 1 162 183 184 teteteeeeffeeeettee 165 f PRESSURIZER E1 188 tetftttfttttttttfet 167 168 1000000 "PRESS1" TMDPVOL 169 100010 ) 0. 0 20. 0 500. 0 O. O O. 0 0. 0 0. 00005 0. 0 1 5 170 -
1000200 2 171 500020) 0-0 2500.0 1.0 O. 5 2554.0 3.0 0.3 2555 0~ 1.0 0.5 2600.0 .1.0 172 '000202 0.7 2687.0 1.'O 0.9 2700.0 5.0 1. 1 2740.0 1.0 1.3 2745.0 1.0 VJ cnai
REL 1/0!4 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 2 57 324 QUALS 306250000 58 325 QUALS 903030000 59 326 QUALS 903180000 60 61 327 P 102020000 B2 , 328 P 202020000 ...........................--------- <- t -0 63 329 P 302020000 CJl M 64 330 P 104200000 w ~.Wo 65 331 P 204200000
.~ ~
tD &0 I Ctt 66 332 P 304200000 67 333 P 811140000 CD 68 334 P 811790000 69 335 P 106010000 o tD 70 336 P 106390000 71 337 P 206010000 . 72 338 P 206330000 73 339 P 306010000 74 340 P 306250000 75 341 P 903020000 76 342 P 903030000 77 343 P 903180000 78 79 80 81 82 83 84 tttftffttftf*ttftfttftttttttttfttttttttftfttftttf 86 FORCE CARDS FOR REP IPE* 87 tf 88 f ttttttftftttff tftff f f ftttttttttfftfttffttttttttt 89 So 92 94 95 f f MAIN DISHCHARGE PIPING .........,.....,..,..................................,...........,..........---,--"-- ---""- ---.------ ~ "- '"-'"-- SB 2001 5, 161 t 97 2002 700020000,700030000,700040000,700050000 98 2003 700060000,700070000f700080000t700090000,700100000 99 2004 700110000,700120000,702010000,702020000,702030000 100 2005 306250000, 801010000, 803010000, 206330000, 805010000 101 2006 807010000, 106390000, 809010000, 8 1 1010000, 81 1020000 102 2007 8 11030000, 8 1 1040000, 81 1050000, 81 1060000, 8 1 1070000 103 2008 811080000, 811090000, 811100000, 811 ) 30000, 8 ) 1120000 104,, 2009 811130000, 811140000,811150000, 811160000t 811170000 ........
'lo~ 2010 811180000, 811190000, 811200000, 811210000. 8 3 {220000 10B 201 1 8 1 1230000 t 8 1 1240000, 811250000, 811260000, 81 1270000
'l07 2012 811280000,811290000,811300000,811310000, A 3320000 108---. 2013- ..--811330000 811340000t 811350000t 811360000,811370000
~
109 2014 811380000,8113S0000.811400000,8114'l0000.8)1420000 ...., 110.......2015..........81.1430000 t 8.11440000t,s.i1450000,.81,1460000,,811470000............................................... 111 2016 811480000,8114S0000,811500000,811510000,831520000 1 12 2017 811530000, 811540000, 81 1550000, 811560000, 81 1570000
'1 13, 2018 . 81 3580000, 811590000, 8 0600000, 811610000, 51 'l620000 1 14 2019 81 1630000, 8 1 1640000, 81 1650000, 811660000t 8 1 1B70000 CARPI
REL 1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 4 173 1000203 5 2747.0 1.0 1.7 2748.0 1.0 1.9 2750.0 1.0 2.0 2750.0 1.0 174 175 t LOOP SEAL GEOMETRY 176
'l77 1010000 "LPSL1" SNGL JUN 178 1010101 100000000 102000000 0. 0 0. 0 0. 0 1000.... t THIS IS A SHORT RADIUS ELBOW LEAVING tD X7 fD 179 1010201 1 0.0 0.0 0.0 n 180 1020000 "LPSL1" 181 182 1020001 3 PIPE o wn 183 1020101 0. 1465 3 184 1020301 0. 299 1 185 1020302 0.6237 3 186 1020401 0.0 3 1020601 43. 1 188 1020602 0.0 3 189 1020801 0.000151 0.0 3 190 1020901 0.0877 0.0877 191 1020902 0.0 0.0 2 192 102100'l 00 3 193 1021101 1000 2 194 1021201 2 2500. 1. 0 0. 0 0. 0 195 1021300 1 196 1021301 0.0 0.0 0.0 2 197 198 1030000 "LPSL1" SNGLClN 199 '030101 102010000 104000000 0.0 0. 1836 0. 1836 1000 200 1030201 1 0. 0 0. 0 0. 0 201 202 1040000 "LPSL1" PIPE 203 1040001 20 204 1040101 0. 1465 20 205 1040301 0. 50 'IO 206 207 208, 1040302 1040401 1040601
'.0
- 0. 62 14 20
-90. 0 7 20 209 1040602 0.0 10 210 1040603 90.0 20 21 1 1040801 0. 000151 0. 0 20 212 1040901 0.0 0.0 6 213 1040902 0. 1836 0. 1836 .7 214 1040903 0.0 0.0 9 215 1040904 0. 1836 0. 1836 10 216 1040905 0.0 0.0 19 217 1041001 00 20 218 104 1 101 1000 '1 9 219 1041201 2 2500.0 1.0 0.0 0.0 20 220 1041300 1 221 1041301 0.0 0.0 0.0 19 222 223 224 tttttttttt'ttttttttttttttttttttt t SV-45C CROSBY 6MB 225 226 ttttttttttttttttttttttttftttttt 227 228 229 1050000 "SRV'I" VALVE 230 1050101 104010000 106000000 0.01897 0.0 0.0 0100 tA VP CORI
REL 1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAff PAG 5 231 1050201 1 0.0 0.0 0.0 232 1050300 NTRVLV 233 10503Q1 503 5Q4 1QQ.Q Q.Q e CROSbY BM6 OPENING IN 10 I/SEC 234 e t .....,........................-...-----.- - -"------ --- - -- -'"----""----"'"--'"'""'"""""" 235 e DISCHARGE PIPING
~
236 237 1060000 "DISCAAf" PIPE CD Rl CD 238 1060001 39 C I 0 239 1060101, 0. 20069 39 240 1060301 0. 526 4 We~ M 241 1060302 1.094 14 I Ql
- 242 e ARC STARTS HERE LEVEL 669-2" 243 1060303 1.000 20 244 1060304 0;8994 29
- 245 1060305 0.7436 35 O 246 t ARC ENDS 247 1060310 0.7980 39 248 1060401 0.0 39 249 1060601 0.0 4 250 1060602 -90.0 14 1060603 0.0 39 252 1060801 0.000152 0.0 39 253 1060901 0.0 0.0 3 254 1060902 0. 1800 0. 1800 4 255 1060903 0.0 0.0 13 256 f060904 0.1800 0. 1800 14 257 1060905 0.0 0.0 38 258 1061001 00 39 259 1061101 1000 38 260 106'1 201 4 17. 7 120. 0 0. 93424 0,0 39 2B1 1061300 262 1061301 0.0 0.0 0.0 38 263 2B4 1070000 "DISCHA1" SNGLaNN 265 1070101 106010000 80S000000 0.0 0. )CIAO 0. 3560 1000 tLOSSES FOR A 12 IH ECBOM 266 1070201 1 0.0 0.0 0.0 267 268 269 270 eeeee*eeteeeeeeeeteeeteeteaeteeeeeeeteeteeteteeteeeeeet 271 e HAIN'ISCHARGE f2" HEADER TO QUENCH TANK 272 ttttteeettttettttttttttteett'etttttttettttt'ettttttttttte 273 274 275 276 8090000 "DISCHA1" BRANCH 277 809000% 0
......2?8......, 809010/ 0.77708 0.5 0.0 0.0 -90.0 -0.5 0.0001B9 0.0 00 279 8090200 4 17.7 $ 20.0 0.93424 0.0 0 0 280 281 8100000 "DISCHA1" SNGLJUfl 282 8100101 809010000 811000000 0.0 0.0 0.0 1000 283 8100201 1 0.0 0.0 0.0 284 285 8110000 "DXSCHIA" PiPf. 5 286 811000'1 99 287 288, 81 10101 8110301
- 0. 777 1.039 14 f 99 0
CO4'I
f r 'I C gg Il' ' J 4 11 S 1
REL D1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 6 289 8 1 10302 0.52995 18 290 8110303 0.5 22 291 8110304 0.52995 26 292 8 1 10305 0. 95729 56 293 8110306 0.475 66 294 8110307 0.49359 79 295 8110308 0.46875 8i 296 8110309 0.50 95 297 8110310 0.95 99 0 WO 298 8110401 0.0 99 299 8110607 -90.0 14 C7 300 8 1 10602 -45. 0 18 301 8110603 -90. 0 22 302 8110604 -45.0 26 303 8110605 -90.0 56 304 8 1 10606 0. 0 87 305 8 1 10607 -90. 0 95 306 8110608 0.0 99 301 8 f10801 0.000169 0.0 99 308 8 1 10901 0 0 0 0 13 309 8 1'10902 0. 078 0. 078 14 310 8110903 0.0 0.0 17 31 1 8 1 10904 0. 078 0.078 18 312 8110905 0. 0 0.0 21 313 8110906 0.078 0.078 22 314 8110907 0 0 0 0 25 315 8110908 0.078 0.078 26 I 316 8110909 0.0 0.0 55 317 8110910 0. 156 0. 156 56
,318 8110911 0.0 0.0 65 319 8110912 0.026 0.026 66 320 8110913 0.0 0.0 78 321 8110914 0. 13 0. 13 79 322 8110915 0.0 0.0 86 323 324 325 811091B
- 8) 10917 8110918 0.0 0.0 '4
- 0. 156 0. 156 87
- 0. 156 0. 156 95 326 8110919 0.0 0.0 98 327 811'1001 00 99 ~
328 8111101 1000 98 329 81 { 1201 4 17. 7 120.0 0. 93424 0. 0 99 330 8111300 331 8111301 0.0 0.0 0.0 98 332 333 8120000 "DISCHA1" SNGLUUN 334 8120101 811010000 813000000 0.0 0.0 0.0 1000 335 8120201 1 0.0 0.0 0.0 Xl Pl 336 337 8130000 "DISCHA1" PIPE 338 8130001 30 339 8130101 0. 7771 30 340 8130301 0. 95 6 34'1 8130302 1.0 20 342 8130303 0.5 30 343 8130401 0.0 30 344 8130601 0.0 30 345 8130801 0.000169 0.0 30. 34B 8130901 O.O 0.0 5 CO>I
REL D1/014 REACTOR LOSS OF COOLANT ANAlYSIS PROGRAM PAG 7 347 8 130902 0. 15B 0. 15B 6 348 . 8130903 0.0 0.0 19 349 8130904 0. 156 0. 156 20 350 8 130905 0. 0 0. 0 29 351 8131001 00 30 t, 352 8131101 1000 29 353 8131201 4 17. 7 120. 0 0. 93424 0. 0 30 354 8131300 1 . ..,..........~.'..CEJ ~ 355 8131301 0.0 0.0 0.0 29 356 ... ........ ....O.. W O I Ql 35i 358 359 ttftttttttttttttttttttttttttttttttttttttttttttttttttt't 360 361 tttt'tttttttttittttit't'tit'tit'tt'tt't'tt'tttt't't'i't't'ttittttttt'i"""'62 SAFETY VALVE 456 AT ELEV. 670'-10" ARC 2 O 363 364 365 tttttttttttttttttt t PRESSURIZER //2 t 366 367 *ttttttttttittttt't 368 369 370 2000000 "PRESS2" TMDPVOL 37'1 2000101 0.0 20.0 500.0 0.0 0.0 0.0 0.00005'0.0 11 372 2000200 2 2000201 0.0 2500.0 1.0 O.f 2514.0 1.0 0.3 2555.0 1.0 0.5 2600.0 1.0 3?4,... 2000202 0.7 2667.0 1.0 0.9 2700IO 1IO 1. 1 2740.0 1 ' 1I3 2745-0 1-0 375 -2000203 1.5 2747.0 1.0 1.7 2748.0 1.0 1.9 2750.0 1.0 2.0 2750.0 1.0 376 377 t LOOP SEAL GEOMETRY k2 SRV 378 t ............,.....................,......................................-.......-.-.---- ---------- - ~---------
~ ~ "-~
379 2010000 "LPSL2" SNGLJUN 380 ..201010'1, 200000000 202000000 0.0 0.0 0.0 1000 *THIS IS A SHORT RADIUS ELBOW LEAVE 0 381 2010201 1 0.0 0.0 0.0 382 ...,...,......,.....,........,........................,..... -...-......--.- -.-- . -""-" - ----- .~- 383 2020000 "LPSL2" PIPC 384 2020001 3 385 2020101 0. 1465 3 386 2020301 0. 317 1 387 2020302 0.6289 3 388 2020401 0.0 3 389 2020601 46. 1 390 2020602 0.0 3 391 2020801 0. 000151 0. 0 3 392 2020901 0.09388 0.09388 393 2020902 0.0 0.0 . 2 394 2021001 00 3 395 2021101 '1000 2 396 2021201 2 2500. 1.0 0.0 0.0 397 2021300 1 398 2021301 0.0 0.0 0.0 2 399 400 2030000 "LPSL2" SNGLIJUN m 401 2030101 202010000 204000000 0. 0 0. 1836 0. 183B 1000 402 2030201 1 0. 0 0. 0 0. 0 403 404 2040000 "LPSL2" PIPE CORI
REL D1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 9 463 464 ttttttetttttttttettttetttttttttttttttttttttttttttt 465 e SAFETY VALVE 45A AT ELEV. 672'-6" ARC 3 466 teteetetttteettttttttttetttttttttttttttttttttttttf 467 468 e Xl I t
~'V7 0 469 I 47Q eeeteeeeeeeeetteee X t PRESSURIZER k3 0 ~
471 W>> 472 eeteeeeeeeeeeeeeet WO 4 e 474 3000000 "PRESS3" THDPVOL 475 3000101 0.0 20.0 500.0 0.0 0.0 0.0 0.00005 0.0. 11
, 476 3000200 2 477 3000201 0 0 2500.0 1.0 0. 1 2514.0 1.0 0.3 2555 0 1.0 0.5 2600.0 ~.0
~ ~
4?8,..3000202 0,7 2667.0 1.0 0.9 2700.0 1.0 1. 1 2740.0 1.0 1.3 2745.0 1.0 . .... ...... .........,.............rt 479 3000203 1.5 2747.0 1.0 1.7 2748.0 1.0 1.9 2750.0 1.0 2.0 2750.0 1.0 480 481 t LOOP SEAL GEONETRY P3 SRV 482 483 3010000 "LPSL3" SNGLJUM 484 3Q101Q1 3QQQQQQQQ 3Q2QQQQQQ Q.Q 0.0 Q,Q 1000 e THIS IS A SHORT RADIUS ELBOW ME WILL 485 3010201 1 0 0 0 0 0 0 486 487 3020000 "LPSL2" PIPE 488 3020001 3 489 3020101 0. f465 3 490 302030'l 0. 317 1 '...........................................................................................Vl...... 49 1 3020302 0. 6185 3 492 3020401 0.0 3 493 3020601 46. =- 1 494 3020602 0.0 3 495 3020801 0. 000151 0. 0 3 496 3020901 0.09388 0.09388 1 497 3020902 0.0 0.0 2 498 3021001 00 499 3021101 1000 2 500 302 1201 2 2500. 1. 0 0. 0 0. 0 3 501 3021300 1 502 3021301 0. 0 0. 0 0. 0 2 503 504 3030000 "LPSL3" SNGLUUN 3030101 302010000 304000000 0. 0 0. 1836 0. 1836 1000 ll> 506 3030201 1 0.0 0.0 0.0 507 508 , 3040000 "LPSL3" PIPE* 509 3040001 20 510 3040101 0. 1465 20 511 3040301 0. 5 10 512 3040302 0. 6188 20 513 3040401 0. 0 20 514304060'I -90.0 7 515 3040602 Q. 0 10 516 3040603 90. 0 20 517 3040801 0.00015'1 0.0 20 518 3040901 0. 0 0. 0 6 519 3040902 0. 1836 0. 1836 7 520 3040903 0.0 0.0 9 COPI
REL D5/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 10 521 3040904 0. 1836 0. 1836 10 522 3040905 0.0 0.0 19 523 3041001 00 20 524 3041101 1000 19
- 525 3041201 2 2500.0 1.0 0.0 0.0 20 526 3041300 1 527 3041301 0.0 0.0 0.0 19 528 529 530 531 ttttttttttttttttttttttttttt t SV-45A CROSBY 6M6 532 533 ttttttttttttttttttttttttttt 534 535 3050000 "SRV3" VALVE
....... 536 3050101 304010000 306000000 0. 01897 O. 0 0. 0 0100 537 3050201 1 0.0 0.0 0.0 538 3050300 HTRVLV 539 3050301 503 504 100.0 0.0 t CROSBY GRS OPENING IN 10 hlSEC
" 540 ----'t S4i --'-OiSNNG'E-i IP'iNG'"---'--------'"----------------"--------'--------"--
" -'""-"'"'""""'42 543 3060000 "OISCHA3" PIPE 544 3060001 25 545 3060101 0.20069 25 546 3060301 0.526 4 547 3060302 0.969 12 548 t ARC STARTS LEVEL 672'-6" 549 3060303 0.636 15 550 3060304 0.991 18 551 552 3060305 3060306
- 0. 99 0.799 f 21 25 553 t ARC ENDS 554 3060401 0.0 25 556 3060602 -90.0 12 557 . 3060603 0.0 25 558 3060801 0.000152 0.0 25 559 3060901 0.0 0.0 3 560 3060902 0. 1800 0. 1800 4 561 3060903 0.0 0.0 11 582 3060904 0. 1800 0. 1800 12 583 3080905 0.0 0.0 *24 564 3061001 00 25 565 ~ 3061101 1000 24 566 -
3061201 4 17. 7 120. 0 0. 83424 0. 0 25 567 3061300 1 568 3061301 0.0 0.0 0.0 24 569 570 571 572 573 574 tttttttttttttttttttttttttttttttttttttttttt t PIPING 575 576 ttttttttttttttttfttftttttttttttttttttttttt PORV 577 578. VJ
REL Dt/Oi4 REACTOR LOSS OF COOLANT ANALYSIS PROGRAN PAG 11 579 5000000 "PORVB" PIPE 580 5000001 16 ~ 581 5000101 0. 05132 1B < 3 IN SCH405 582 5000301 0.497 3 583 5000302 0.556 6 584 ~ ARC STARTS LEVEL 684'" " '"""' 585 5000303 0. 365""'""'7'""'i 586 5000304 0.6448 13 587 5000305 0.53217 16 588 5000401 0.0 16 589 5000601 0.0 3 590 5000602 -90.0 B 59'I 5000603 0.0 16 592 5000801 0.000153 0.0 1B 593 5000901 0.0 0.0 2 594 5000902 0.2088 0.2088 3 595 5000903 0.0 0.0 5 596 5000904 0.2088 0.2088 6 597 5000905 0.0 0.0 15 598 5001001 00 16 599 5001 101 1000 15 600 5001201 4 17. 7 120. 0 0. 93424 0. 0 16 601 5001300 1 602 5001301 0.0 0.0 0.0 15 0 604 5010000 "PORVB" SNGLdUN w THIS UNCTION IS ON ARC B 605 5010101 500010000 502000000 0.0 0.0 0.0 1000 606 5010201 'I 0.0 0.0 0.0 607 608 5020000 "PORVB" PIPE
- REDUCER ON ARC B 3IN X4IN 609 502000'l 2 B10 5020101 0. 05132 1 > 3IN SCH40S 611 5020102 0.08840 2 > 4fN SCH40S 612 5020301 0.3385 1 613 5020302 0. 511 2 614 5020401 0. 0 2 615 '020601 0. 0 2 616 5020801 0. 000153 0. 0 1 617 5020802 0. 000134 0. 0 2 B18 5020901 '.0544 0.0399 1 619 5021001 00 2 620 502110 t 1000 62'1 502'l201 4 17.7 --i'i'O".O-'O'."93424 0.0 2 622 5021300 623 502 l 301 0. 0 0. 0 0. 0 'l B24 625 626 5030000 "PORVB" SNGLdUN e ON ARC 6 627 '030101 502010000 504000000 "'0'. 0 0. 0 0. 0 1000 628 5030201 1 0. 0 0,0 0,0 629 630 5040000 "PORVB" BRANCH a ON ARC B 0'42 631 5040001 0 632 5040101 0 0884 0.361 0.0 0.0 0.0 0.0 0.000134 0 0 00 633 5040200 4 17.7'l20.0 0.93424 0.0 0 0 634 63'5 5050000 "PORVB" SNGLJUN + 0th ARC 6 636 505010t 504010000 506000000 0.0 0.0 0.0 1000 COPI
RE 001/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PA 12 637 5050201 1 0.0 0.0 0.0 638 639 640 5060000 5060001 "PORVB'IPE 9 i OM ARC 8 641 5080101 0.0884 9 642 5080301 0.6211 8 643 5060302 0.6398 9 644 5060401 0.0 9 645 5060601 0.0 9 B46 5060801 0.000134 0.0 9 647 5060901 0.0 0.0 8 648 5061001 00 9 649 506110'1 1000 8 BSO 5061201 4 17. 7 120. 0 0. 93424 0.0 9 651 5061300 1 652 5081301 0.0 0.0 0.0 8 653 654 5070000 "PORVB" SNGLaJUN 655 5070101 506010000 508000000 0. 0 0. 0 0. 0 1000 658 5070201 1 0. 0 0. 0 0. 0 657 658 5080000 PDRVB" PIPE + REDUCER ON ARC 6 4IN X BIN B59 5080001 2 660 5080'101 0.0884 1 661 5080102 0. 20069 2 662 5080301 0.5792 2 5080401 0.0 2 664 5080601 0.0 2 Vl 665 5080801 0. 000134 0. 0 666 5080802 0. 000152 0. 0 2 667 5080901 0. 1483 0.0815 1 668 5081001 00 2 669 5081101 1000 1 670, 5081201 4 17.7 120.0 0.93424 0.0 2 ..........................................,..........;,............ 67 1 508 1300 672 5081301 0.0 0.0 0.0 1 673 674 5090000 "PORVS"'SNGLa/UN
- ON ARC 8 675 5090101 508010000 510000000 0.0 0.0 0.0 676 5090201 1 0.0 0.0 0.0 6
678 5100000 "PORVB" BRANCH e DN ARC B 8 232 679 5100001 0 680 5100101 0.20069 0.75 0.0 0.0 0.0 0.0 0.000152 0.0 00 . 681 5100200 4 17. 7 120. 0 0. 93424 0. 0 0. 0 682 683 5'110000 "PORVB" SNGLVUN + ON ARC 8 684 511010'I 510010000 700000000 . 0.0 0.0 0.0 1000 685 5110201 1 0.0 0.0 0.0 686 687 4000000 "PORVA" PiPE + 3iA SCH40S 688 4000001 8 689 4000101 0. 05132 8 690 4000301 0, 4141 4 691 4000302 0.4375 8 692 4000401 0.0 8 ~
. 693 4000601 0.0 4.-
694 4000602 -90.0 8 CORI
V i
'h i
REL t/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 13 695 4000801 0.000153 0.0 8 B9B 4000901 0.0 0.0 3 697 4000902 0.2088 0.2088 4 698 4000903 0.0 0.0 7 699 4001001 00 8 700 400t 101 1000 7 701 4001201 4 17.7 120.0 0.93424 0.0 8 Cb X7 (D
,702 400t300 t c > n 703 4001301 0.0 0.0 0.0 7 704 705 4010000 "PORVAB" SNGLJUN 70B 40'l0101 400010000 510000000 0.0 0. 1800 0. 1800 1000 707 4010201 1 0. 0 0. 0 0. 0 708 709 6000000 "PORVC" PIPE 0 710 6000001 7 711 6000101 0.05132 7 < 3iN SCH40 712 6000301 0. 4722 3 713 6000302 0.4375 7 714 6000401 0. 0 7 7 15 6000601 0. 0 3 716 6000602 -90.0 7 717 6000801 0.000153 0.0 7 , 718 6000901 0.0 0.0 2 719 6000902 0.2088 0.2088 3 720 6000903 0. 0 0. 0 6 72 'l 6001001 00 7 722 6001101 1000 6 723 600120 1 4 17. 7 120. 0 0. 93424 0. 0 7 724 6001300 1 725 6001301 0.0 0.0 0.0 6 726 727 6010000 "PORVBC", SNGLsNN 728, 60 10101 600010000 504000000 0. 0 0. 1932 0. 1932 1000...
729 6010201 1 0.0 0.0 0 0 ~ 730 731 7000000 "PORVBO" PIPE
- bOQNSTREAbl OF ARCS 732 7000001 12 733 7000101 0. 20069 12 734 7000301 0.50 2 735 7000302 1.0333 12 736 7000401 0.0 12 737 7000601 0.0 2 738 7000602 -90. -12 739 7000801 0.000152 0.0 12 740 7000901 0.0 0.0 1 741 7000902 0. 1800 0. 1800 2 742 7000903 0.0 0.0 743 7001001 00 i2 744 7001101 1000 11 745 700120i 4 i7.7 120.0 0.93424,0.0 12 746 7001300 1 747 7001301 0. 0 0. 0 0. 0 ii 748 749 7010000 "PORVb" SNGLiJUN
'750 7010101,700010000 702000000 0,0 0.0 .0.0. 'l000.........,........,....,...
751 7010201 1 0.0 0.0 0.0 752 CC+I
R OD1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PA 14 753 754 755 756 757 tate>>eteeeeteeeeettt't'iet*eietteetee'e'tii'teeeeeetette 758 ee ae 759 te MAIN ARC CONNECTiONS 760 761 tetetettttteftetttttttteettttttttttttteeititttteteat ~e O
~
WO
~
762 763 764 765 766 7020000 "PORVD" PIPE t REDUCER 6 X12'iji ABOVE SRV ARCS INTERSECTION W/ DISCH 768 7020001 3 769 7020101 0.20069 770 7020102 .77708 3 771 7020301 0.75 1 772 7020302 0.5833 3 773 7020401 0.0 3 774 7020601 -90.0 3 775 7020801 0.000152 0.0 776 7020802 0.000169 0.0 3 777 7020901 0.4930 0.2045 778 7020902 0;0 0.0 2 779 7021001 00 3 780 7021101 1000 2 781 7021201 4 17. 7 120. 0 0. 93424 0. 0 3 782 . 7021300 783 702130'I 0. 0 0. 0 0. 0 2 784 785 8000000 "PORVD" SNGLJUN 786 8000101 702010000 801000000 0.0 0.0 0.0 1000 787 8000201 1 0.0 0.0 0.0 788 789 3070000 "PORVO3". SNGLJUN .....,790 3070101 306010000 1* 801000000 0.0 0. 156 0. 156 1000 e 12 IN ELBOW LOSS 791 3070201 0.0 0.0 0.0 ~ 792 793 8010000 "PORVD" BRANCH
- CONNECTS ARC3 W/ DISCH 794 8010001 0 795 8010101 0. 77708 0. 5 0. 0 0. 0 -90. -0. 5 0. 000169 0 0 00 79B 8010200 4 17.7 120.0 0. 93424 0.0 0.0 797 m z'.
798 8020000 "PORVO" SNGLJUN m 799 800 8020101 8020201 801010000 1 0.0 803000000 0.0 0.0 0.0 0.0 0.0 1000 mm 801 802 8030000 "PORVD" SNGLVOL 803 8030101 0.77708 1.1667 0.0 0,0 -90. -1.1667 0.000169 0-0 00 804 8030200 4 17;7 120.0 0.93424 0.0 0 0 805 806 8040000 "PORVDa SNGLJUN 807 8040101 803010000 805000000 0. 0 0. 0 0. 0 1000 808 8040201 ,1 0.0 0.0 .0.0 809 810 2070000 "PORVD" SNGLJUN COPI
REL D1/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM PAG 15 811 2070101 206010000 805000000 0.0 0. 156 0. 156 1000
- t2 IN ELBOtt LOSSES 8 12 2070201 1 0. 0 0. 0 0. 0 814 8050000 "PORVD" BRANCH e CONNECTS ARC2 lt/ DISCH 815 8050001 0 816 8050101 0. 77708 0. 5 .0.0 . 0.0 ...-..90.........-..0:.5......0...000169...0:..0...00..--- "------"----
8050200 4 17.7 120.0 0.93424 0.0 0.0
--------------'------- ------------'17 ------ '-'-" --"" -' "ro"4 rn 818 819 8060000 "PORVD" SNGLJUN 820 8060101 805010000 807000000 0. 0 0. 0 0. 0 1000 ...,...,.............. O ...W A 821 8060201 1 0.0 0.0 0.0 I 822 4
'....,.............................,.........................................."----- -- ------ ~---------
823 8070000 "PORVDO SNGLVOL
~
824 807010t 0.77708 t. 1667 0.0 0.0 -90. -t. 1667 0.000169 0.0 00 825 8070200 4 17.7 120.0 0.03424 0.0 0.0 826 827 8080000 "PORVD" SNGL4JN 828 8080101 a07OtOOOO 808000000 0.0 0.0 0.0 1000 829 8080201 t 0.0 0.0 0.0 830 831 9000000 "QTANKD" SNGLilUN 832 9000101 813010000 901000000 0.0 0. 1560 0. 1560 1000 833 900020) t 0.0 0.0 0.0 834 835 9010000 "QTANKD" PIPE 836 9010001 2 837 9010101 0. 77708 2 838 9010301 1.02083 2 839 9010401 0.0 2 840 9010601 "90.0 2 841 90t080t 0.000169 0.0 2 842 9010901 0.0 0.0 1 843 90't1001 00 2 844 901 1 101 1000 1 845 9031201 4 17.7 120.0 0.93424 0.0 2 846 9011300 1 847 9011301 0.0 0.0 0.0 1 848 849 itetiiiieseeiiiiiiieiiiii te 850 85 1 852
+ i QUENCH TANK ee 4j 853 i*itieeitteiet7iieiiVi7ii 854 855 856 9020000 9020101 "QTANK-IN" SNGLiJUN 901010000 903000000 0. 0. 0, 1000.
~ -- --------- -------------- --- - -- - - z 857 9020201 1 0. 0. 0.
858 859 860 i SPARGER 12 IN SCH40 PiPE 861 9030000 "SPARGER" PIPE 862 + NO OF VOLUMES 863 9030001 18 864 + FLOW AREA 865 9030101 0.7773 18 866 + VOL. LENGTHS 867 9030301 1. 125 2 868 9030302 1. 1333 7
%D CO@I
t l
REL 01/014 REACTOR LOSS OF COOLANT ANALYSTS PROGRAM PAG 16 869 9030303 1.0 18 870 4 VOL. VOLS. 871 9030401 0.0 18 872 873 + VERTICAL ANGLES 874 9030601 -90. 7 875 9030602 0.0 18 876
- PIPE ROUGHNESS 877 9030801 1.69-4 0.0 18 878 + aJUNCTION LOSS COEFF. 0 W
"""~'" 0 I"'l 879 9030901 0.0 0.0 6 880 9030902 0. 156 0.156 7 881 9030903 0.0 0.0 17 882 4, VOL. CONTROL FLAG 883 9031001 00 18 884 i JJUN. CONTROL FLAG 885 903110f 1000 17-886 > INITIAL COND.
887 9031201 4 17.7 120. 0. 93424 0. 2 888 9031202 3 17.7 120. 0.0 0..18-889 + a)lN. INITIAL COND.
.890 9031300 1 891 9031301 0.0 0.0 0.0 17 892 893 > SPARGER EXIT 894 895 S040000 "EXIT" SNGLalUN
,896 9040101 903010000 905000000 0.0 1.0 1.0 1000 897 9040201 1 0. 0. 0.
898 899
- WATER VOL.
900 901 9050000 "QT. WATER" SNGLVOL 902 9050101 260.4706 5.6667 0.0 0.0 90. 5.6667, 0.003 0,0 01....,....... ...,... 903 9050200 3 17.7 120. 904 905 iee INTERFACE 906 907 9060000 "INTERFACE" SNGLVUH 908 9060101 905010000 907000000 0. 0 0. 0 0. 0 1000 909 S06020't 1 0.0 0.0 0.0 ~ 910 91 '1 + AIR VOLUME 912 913 9070000 "QT. AIR" SNGLVOL 9 4,
'1 9070101 260. 4706 1. 2439 0. 0 0. 0 90. 1 ~ 2439 0. 003 0. 0 01 915 9070200 4 17. 7 120. 0. 93424 916 917 4 RUPTURE DISC 918 919 9080000 "RLJP. DISC" VALVE 920 . 9080101 907010000 999000000 1.77 0. 0. 1100 921 9080201 1 0. 0. 0.
922 9080300 TRPVLV 923 9080301 501 + VALVE OPENING TRIP 924 ++ . 925
..926 i PIPE OUTSIDE ENVIRONMENT CORI
RE 927 928 OD1/014 9990000 9990101 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM "ATMOSPHERE" 10000. TMDPVOL
- 0. 0 0. 0 0.0 0. 0 00001 0.0
- 17 10000. ~ 1 1 929 9990200 4 930 9990201 0. 0 14. 7 120. 0. 91907 932 933 934
( I 0 935 t ttttttatttttttttttttttettt Me+ W 0 WO 936 937 -
- t PLOT CAROS 938 t .............,..........O.....,
939 t'tttttttttttttttttttttttttt 940 941 942 943 20300100 MFLOWJ 105000000 944 20300200 MFLOWJ 205000000 945 20300300 HFLOWJ 305000000
- 946 20300400 MFLOWJ 700010000 947 20300500 MFLOWJ 811140000 948 20300600 MFLOWJ 811790000 949 20300700 MFLOWJ 307000000 950 -
20300800 MFLOWJ 207000000 951 20300900 HFLOWJ 107000000 952 20301000 MFLOWJ 900000000 953 954 20301100 QUALS 102020000 955 20301200 QUALS 202020000 956 20301300 QUALS 302020000 957 20301400 QUALS 104200000
, 958 959 20301500 20301600 QUALS QUADS 204200000 304200000 960 20301700 QUALS 811140000 961 20301800 QUALS .811790000 962 20301900 QUALS 106010000 963 20302000 QUALS 106390000 964 20302i00 QUALS 206010000 965 20302200 QUALS 206330000 96B 20302300 QUALS 306010000 967 20302400 QUALS 306250000 968 20302500 QUALS 903030000 969 - 20302600 QUALS 903180000 970 971 972 20302700 20302800 P
P 102020000 202020000
....-....----..------------ ----------------- --------------"fig fg 20302900 302020000 X) Pl Z.'73 P
974 20303000 P 104200000 975 20303100 P 204200000 976 20303200 P 304200000 977 20303300 P Bf1140000 978 20303400 P 811790000 979 20303500 P 106010000 980 20303600 P 106390000 98 1 20303700 P 206010000 982 20303800 P 206330000 983 20303900 P 306010000
, 984 20304000 P 308250000 U)
COPI
R 001/014 REACTOR LOSS OF COOLANT ANALYSIS PROGRAM 9 20304100 P 903020000 986 20304200 P 903030000 987 20304300 P 903180000 988 e 989 990 991 992 993 994 .END OF CASE COI'I
A TELEDYNE Technical Report ENQINEERINQ SERVlCES TR-5364-4 Revision 0 4- 162 e 4.8 ~EE t 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...,On the Unit 2 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
i Technical Report A TELEDYNE TR-5364-4 ENQfNEERiNQ SERVfCES Revision 0 4-163 4.8.1 REPIPE In ut - Section A
SPI INL .KBLOCK=300 KPIPE~13,KPLOT(1)~O,KNAVE>1,
~
KPRINT"--1, KPNV= 1, KSTEP-"3,
- NDROPV=700020000,306250000,206330000,506390000i903080000$
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