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| | number = ML18044A528 | | | number = ML18044A528 |
| | issue date = 02/15/1980 | | | issue date = 02/15/1980 |
| | title = Forwards Interim Rept in Response to NRC 780125 Ltr & 791120 Memo Re Asymmetric LOCA Loads | | | title = Forwards Interim Rept in Response to NRC & 791120 Memo Re Asymmetric LOCA Loads |
| | author name = Lundvall A | | | author name = Lundvall A |
| | author affiliation = BALTIMORE GAS & ELECTRIC CO. | | | author affiliation = BALTIMORE GAS & ELECTRIC CO. |
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| | contact person = | | | contact person = |
| | document report number = NUDOCS 8002190745 | | | document report number = NUDOCS 8002190745 |
| | | title reference date = 01-25-1978 |
| | package number = ML18044A530 | | | package number = ML18044A530 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC |
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| =Text= | | =Text= |
| {{#Wiki_filter:BALTIMORE GAS AND ELECTRIC COMPANY | | {{#Wiki_filter:}} |
| * P. 0. BOX 1475 BALTIMORE:, MARYLAND 21203 February 15, 1980 ARTHUR E. LUNDVALL, .JR.
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| Vt.CE* PRESIDENT SUPPLY Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission Washington, D. C. 20555
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| ==Subject:==
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| Calvert Cliffs Nuclear Power Plant Units Nos. 1 & 2, Dockets Nos. 50-317- & 50-318 Palisades Nuclear Power Plant, Docket No. 50-255
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| * Fort Calhoun Nuclear Power Plant, Docket No. 50-287 Millstone Nuclear Power Plant Unit No. 2, Docket No. 50-336
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| * Asynunetric LOCA Loads Interim Report
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| ==References:==
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| (a) NRC letter dated 1/25/78 from V. Stello, Jr. to all PWR licensees, Asymmetric LOCA loads.
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| (b) NRC memorandum dated 11/20/79 from S. B. Hosford to D. G. Eisenhut, Asymmetric LOCA loads.
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| ==Dear Mr. Denton:==
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| In our continuing effort to. respond to the requirem~nts of Reference (a), the Combustion Engineering Owners' Group (CEOG) comprised of Baltimore Gas and Electric, Consumers Power, Northeast Utilities and the Omaha Public Power District hereby submits ten copies* of the CEOG Interim Report in response to Reference (b). One of these copies is being forwarded directly to your Mr. Steve Hosford for review.
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| The results presented in the report show that for reactor coolant system supports for Calvert Cliffs, Millstone 2 and Palisades, significant margins to failure remain.
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| The preliminary evaluation of the Fort Calhoun steam generator s~pports $bowed that modification to a portion of the supports could be required. Materials for this modification h.ave been purchased a*nd OPPD plans to replace the affected supports during the current refueling outage.
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| Although the detailed plant specific analysis is not complete, we expect the results to show that the steam generator with the modified supports is capable of withstanding the applied loads.
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| The detailed plant specific analysis of the Fort Calhoun reactor rv\
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| vessel supports is still in progress. An evaluation of the total support capabi~ity of the support system has been performed.
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| * Based on the evaluati?f' we expect that the results .of the detailed analysis will demonstrate the adequacy of the Fort Calhoun vessel supports.. ~I;)?, /
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| .
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| .
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| ~
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| ~~
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| '
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| 8 0 0 2 l 9 074.5" "
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| le \
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| l Mr. H. R. Denton Page 2 February 15, 1980 The ~esults of the Calvert Cliffs and Millstone ECCS analyses
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| . show that integrity and functionability of the piping is maintained. The
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| . plant specific analyses for Fort Calhoun and.Palisades are still in progress.
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| On the basis of results for.the generic plant and maximum accelerations,
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| * we expect that these analyses will show that the integrity and function~
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| ability of the piping is maintained.
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| We believe that, on the basis of these results and the additional information on fuel testing presented in this report, continued operation of Calvert Cliffs 1 and 2, Fort Caihoun, Millstone 2, and Palisades should be allowed.
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| It is the intention of the CEOG to complete.the entire asymmetric*
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| loads evaluation and submit an appendix to the enclosure on or before July 1, 1980.
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| (\..
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| I
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| __.;~*
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| I cc: J. A. Biddison, Esquire G. F. Trowbridge, Esquire E. L. Conner, Jr. - NRC P. w. Kruse - CE
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| I I *REGULATORY DOCKET ALE COPY I
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| I I REACTOR COOLANT SYSTEM I
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| ASYMMETRIC LOADS I
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| I EVALUATION PROGRAM I . INTERIM REPORT I
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| I NORTHEAST UTILITIES I BALTIMORE* GAS & ELECTRIC COMPANY I OMAHA PUBLIC POWER DISTRICT I CONSUMERS POWER COMPANY I
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| I I
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| ,,
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| I
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| '.I I
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| I I
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| I I REACTOR COOLANT SYSTEM I ASYMMETRIC LOADS I
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| INTERIM REPORT I
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| I I
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| Prepared by I
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| COMBUSTION ENGINEERING, INC.
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| I for.
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| 'I I BALTIMORE GAS AND ELECTRIC COMPANY CONSUMERS POWER COMPAN~
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| I NORTHEAST UTIL~TIES 1- OMAHA PUBLIG POWER DISTRICT 1*
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| .1 1* February 8, 1980
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| .,,.
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| ..*
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| '
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| * TABl,.E *OF CONTENTS'* ..
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| SECTION* . ..SUBJECT I . l.O INTRODUCTION ..
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| PAGE NUMBER
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| : 1. 0. l I 2.0 3.0 TO BE INCLUDED IN FINAL REPORT REFERENCES AND CODES 3. 0.1
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| .I* .
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| ==4.0 DESCRIPTION==
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| OF EVALUATION ..
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| * 4. 1 . 1
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| : 4. 1
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| ==SUMMARY==
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| I 4;2 . PIPE BREAKS*
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| 4.1.1
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| : 4. 2. 1 4.*2. *1 I 4.2.2.
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| DESIGN BASIS METHOD OF.ANALYSIS 4.2. 1
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| : 4. 2. 1 I 1* 4.2.3 RESULTS OF GENERIC ANALYSIS 4.2.2
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| .. 4. 2.4 PLANT SPECIFIC. FLOW AREA EVALUATIONS 4.2.3
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| *I' 4.3 SUBCOMPARTMENT ANALYSIS 4.3.1
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| : 4. 3. 1 I 4.3.2 DESIGN BASIS .
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| DESIGN FEATURES
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| : 4. 3. 1 4.3.2 I 4.3.3 4.4 DESIGN EVALUATION .11 SLOWDOWN LOAD 4. 4. 1 I 4.4.1 PRESSURE LOADS 4.4.1 DRAG LOADS I 4.4.2 4.5 REACTOR VESSEL, RC PIPE AND RCS SUPPORTS 4.4.7
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| : 4. 5. 1 I 4. 5. 1 DESIGN BASIS 4. 5. 1 4.5.2 METHOD OF ANALYSIS 4. 5. 1 I* 4.5.3 INSTABILITY ANALYSIS OF SUPPORTS 4.5. l 4.5.4 MODELS I* 4.5.5 . FORCING F8NCT!ONS
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| . 4.5~4 4.5.6.
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| .I . 4. 5.6 4.5~7 COMPUTER CODES
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| * 4.5.7 I RESULTS OF ANALYSIS
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| .. . 4.5.7 I 4. 5.8 .. EVALUATION:OF COMPONENTS AND SUPPORTS 4.5.8 .*
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| I.
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| I
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| 11* SECTIO.N SUBJECT , PAGE NUMBER I'. 4.6:
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| '4.6.l R~AtTOR vtssEL- INTERNALS '
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| TO BE INCLUDED IN-FINAL REPORT
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| : 4. 6 .1 I 4.6.2 . INTERNALS ANALYSIS'MObE(S 4. 6~1 FUEL**
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| " I;*. 4.7
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| : 4. 7. l ' TO BE INCLUDED IN FINAL REPORT' 1: 4.7.2 FUEL TESTING 4.7.3 FUEL ANALYSIS MODELS 4.7.11 I 4.8 TO BE INCLUDED IN FINAL REPORT.
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| 4:9 EMERGENCY CORE COOLING SYSTEM (ECCS) PIPING 4.9.l I 4. 9. l DESIGN BASIS 4.9 . .l I 4.9.2 4.9.3 METHOD OF ANALYSIS RESULTS OF ANALYSIS
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| : 4. 9. 1 4.9.2 I
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| ,, 4.9.4 EVALUATION. OF ECCS PIPING 4.9.2 I
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| I*
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| .. ,.
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| I I
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| .f I
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| I*.
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| '1* '
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| "
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| .__ -------- .. '
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| -.~-----------------,-~----------------,-~-~-
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| 1
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| * 0 -. HlTRODUCTI Otl .
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| This document presents resulti of an evaluation of rea~tor coolant system components, component supports, and ECC~ piping when subjected to*loads resulting from postulated pipe ruptures. *-
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| The methods of analysis usP.d in the evaluation are those presented in
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| _the pl an. subni tted to NRC. in August 1978. The -methods and results of the.computation of pipe break area, break opening.time, subcornpart111ent pressure, reactor vessel asymmetri.c pressures, -and structura 1 analyses following design basis pipe ruptures in the reactor coolant system are presented. * -
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| In addi.tion*, this document presents information on the ongoina effort in the evaluation of reactor internals and fuel, including spacer grids. *
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| . .
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| The results of the evaluation ofCEDMs, reactor internals, and fuel will. be presented at a later date.
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| ==3.0 REFERENCES==
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| ANO CODES 3.1 Design Basis Pipe Breaks for the Cor.bustion Engineering Two Loop Reactor Coolant System CENP0-168A, Combustion Engineering Inc.,
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| June, 1977 3.2 ICES-STRUDLII, The Structural Desi~n Language, Engineering Users Manual, First Edition, Massachusetts Institute of Technology, tfovember, 1968 3.3 SAPIV, A Structural Analysis Program for Static and Dynamic Response of Linear Systems, University of California, Berkeley, June, 1973 3.4 Design Basis Pipe Breaks for the Combustion Engineering Two Loop Reactor Coolant System CENP0-168A, Appendix A-5, Combustion Engineering Inc., June, 1977 1 3.5 "Description of Loss-of-Coolant Calculational Procedures",
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| CEN PD- 26 , Comb us t i o n En gi ne e ri ng I nc . , Augus t , 1. 9 71 3.6 Standard Review Plan 6.2.l.2, "Subcompartment Analysis",
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| February, 1975 3.7 CESSAR, "Combustion Engineering Standard Safety Analysis* Report",
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| Section 6. 2 .1. l :..4 approved December 31 , 1975 I 3.8 "Reactor Plant Subcompartment Analysis", CENPD-141 Revision 2, March 1978
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| * 3.9 Combustion Engineering Inc., "Method for the Analysis of Blo1*1do1vn Induced Forces in a Reactor Vessel' 1 , CENPD-252-P, December, 1977 (Proprietary)
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| I 3.10 ~*1ARC-COC, Noh-Linear Finite Element Analysis Program, Control Data Corp., Minneapolis, Minn. 1976 I 3.11 "Structural Analysis of Fuel Assemblies for Combined Seismic and Loss of Coolant Accident Loadings", CENPD-178P, August, 1976 11 3.12 Topical -Report on Dynamic Analysis of Reactor 1/essel Internals rl Under Loss of Coolant Accident Conditions with Application of Analysis to CE 800 Mwe Class Reactors 11 , CENPD-42, 1971
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| ~1 l;ll "CESllO\.f: *_ f\ Co111putr.*1* Cud1~ Lo '..iolvr~ i.111: Uy11c1111ic ":esµu11se 01* .Lu111µcJ i11ass Systems", Described and Verified in above Reference 3.12.
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| 3 ..1.:l "5A~\i-150R - A Finite Eler.ient Program to Determine the Stiffness I and 1-~ass ,'1atrices of Shells of Revolution 11 , Described and verified in above Reference 3.12.
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| ~-1
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| ~ I
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| --1 .., n 1
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| -I I 3. 15 "DYNASOR - A Finite Element Program for the Dynamic Non-Linear Analysis of Shells of Revolution'', Described and verified in
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| --1 3. 16 above Reference 3.12.
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| "LOAD - A Computer Code to Calculate Dynamic Axial LOCA Loads
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| -I 3. 17 Using the Control Volume Formulation", Calculation SP80-STA-25, 5/15/78 .
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| "ASHSD - A Dynamic Stress Analysis Code of AxisyrTirnetric Structures
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| -I Under Arbitrary Loadirig'', Described and verified in above Reference
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| : 3. 12.
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| -I 3. 18 "RUMBLE - A Computer Code to Compute Fuel Bundle Stresses Based on Deflected Shapes", Described in above Reference 3. 11.
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| : 3. 19 "DDIFF Code Topical Report", CENPD-141, April 30, 1974 I 3.20 RELAP4/~10D5, MJCR-IWREG- 1335, A Comprehensive.For Transient Thernal-Hydraulic Analysis of iluclear Reactors and Related Syster1s.
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| I 3.21 "Reactor Cool ant *system Asymmetric Loads Ev al uati on Pl an 11 , Combus-tion Engineering, Irie., August 4, 1978.
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| I*
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| --1 I
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| --1.
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| -I
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| -I
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| ~
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| I
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| -I
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| *
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| ==4.0 DESCRIPTION==
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| OF EVALUATION
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| -f 4.. l Sumr.ia r 1 1
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| -1 A detailed evaluation of reactor coolant system components, component supports, and ECCS piping has been perfonned for the C9ribustion
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| -I Engineering ~eneric plant when subjected to the effects of thrust, subcompartment pressure, and reactor vessel asymmetric pressures following desi~n ba~is pipe ruptures in the reactor coolant system.
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| __, The results show that significant margins to failure rer.iain.
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| The results of the generic plant evaluation were used in the evaluation
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| * of specific plants, v1here appropriate. \Jhere significant difference beh1een the generic pl ant and a specific pl ant existed, srP.cifi c pl ant
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| -I
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| ,
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| analyses have been performed. In particular, plant specific mass and energy releases were calculated for Fort Calhoun; a separate reactor cavity subcompartment pressure analysis for each plant was performed; and a plant
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| __ specific structural analysis for the Palisades reactor inlet break was perforned.
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| The results presented in this document show that for reactor coolant system
| |
| -I supports for Calvert Cliffs, Millstone 2 and Palisades, significant margins to failure remain.
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| I The preliminary evaluation of the Fort Calhoun steam generator supports showed that modification to a portion of the supports could be required. Materials for this modification have been purchased and OPPD plans to replace the affected
| |
| ----1, supports during the current refueling outage. Although the detailed plant specific analysis is not complete, we expect the results to show that the steam generator with the modified support~ is capable of withstanding the applied loads.
| |
| * I The detailed plant specific analysis of the Fort Calhoun reactor vessel supports is sti 11 in progress. /\n eva*1 uati on of the totn 1 suDport capabi 1 i tv of the support system has been perfori11ed. Based on this evaluation, we expecf that the results of the detailed analysis will demonstrate the adequacy of the Fort Calhoun vessel supports.
| |
| :I The results of the Calvett Cliffs and Millstone ECCS analyses shov1 that integrity and functionability Of the p*iping is maintained. The plant specific analyses for Fort Calhoun and Palisades are still in progress.
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| --1 *
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| . .
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| On the basis of results for the generic plant and maximum accelerations, we expect that these analyses will show that the integrity ancl function-abil ity of the piping is maintained.
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| -I lie believe that, on the basis of these results and the additional inforir1ation on fuel testing rresented in this rerort, continued npO.ration cl of Calvert Cliffs 1 and 2, fort Calhoun, ~ill stone 2, and Palisades should be a1"lovied.
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| Figures 4.1.1 through 4.1.5 shov1 the pro~tess of the asymmetric loads
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| --1 evaluation.
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| |
| *.. : .. . ~!
| |
| ...... . ~ *. ** .. *.. *,*. :* *..
| |
| ""!:
| |
| >
| |
| J\. N ;'\ L {r* I l>A L . s~ nu~ N c I P: c;. J 9 II E v /\ L u ,'\ T I 0 N 0 ~ II cs .*I
| |
| ., - *. ':.
| |
| ~-
| |
| ',:.
| |
| C ll r.1 I' Cl fJ l N T S I\ fol S U !' I' ll H I S l
| |
| ., : ,: .*'
| |
| I) ' .. *!'
| |
| .*.PALISADES FICUHE '1 .. 1.5
| |
| ~*. '
| |
| .. ;. s .t .
| |
| | |
| ~ 1 F **..: 7Qri*&. rr *-r*fi*n.,. Rs6r * .,.: "'i',.°t!::c+t 1 w -....,. . . .
| |
| *d~.,.._--* .,,_tt_ _ _...,.*,.,. d...,._._..._-e...sw-..**-=_...,,*..,."....--....;.*_..*.,..
| |
| .* . , *...,._,__.*...,.,*.............. . .......__.-*.,....---...*<.........-..a...-c*a..._........._
| |
| .._~i.:...~-..~~
| |
| I.
| |
| I 4~2 PIPE BREAKS 4.2.1 DESIGN BASIS I As stated in Reference 3.21, guillotine ruptures were postulated to occur at the following locations:
| |
| I a) Reactor Vessel Hot Leg Nozzle b) Reactor Vessel Cold Leg Nozzle I c) Steam Generator Outlet Nozzle d) Steam Generator Inlet Nozzle 4.2.2 METHOD OF ANALYSIS 1: For each postulated guillotine, -a dynamic non-linear time history analysis was performed using methods discussed in I Reference 3:1. Each analysis generated pipe end deflection time histories, from which flow area time histories and maximum flow areas \*Jere mechanistically determined. **
| |
| .
| |
| I Calvert Cliffs was selected as the model pl~nt to be used
| |
| .in the generic analysis. For each ~ostulated break, assessments_
| |
| .
| |
| were made for Millstone, Palisades and Fort Calhoun. These I assessments are explained in Section 4.2.4.
| |
| 4.2.2.1 Generic RV Outlet Nozzle Guillotine Analysis I A three-dimensional model of the reactor coolant system was constructed using lumped mass parameter I techniques. The mathematical model represents the total Reactor Coolant System (RSC) mass and stiffness, with discontinuity at the Reactor Vessel (RV) outlet nozzle. The model is shown in Figure 4.2.1. It contains I lumped mass representations of the RV, both Steam Gener-ators (SG), all four Reactor Coolant Pumps (RCP), and piping of the lA and lB cold legs as well as mass detail I of the ruptured hot leg. The non-linearities of the RV gapped supports are represented as in the SG #2 lower gapped support parallel to the hot leg. The lower support I system of SG #1 was modelled in detail, and includes the non-linearities of the lower stop and all four vertical pads in order to calculate its movement following the I postulated rupture. The resulting model consists of 71 mass dynamic degrees of freedom (d.d.o.f.) and 8.non-linear support locations.
| |
| I The physical definition of the resulting model was supplied in the STRUDL computer code Reference 3.2 which generated the condensed stiffness matrix. This matrix, along with I the mass definition, gapped support definition, damping, and a set of three-dimensional time history forcing function a~ discussed and developed in Reference 3.1 was supplied I to the DAGS computer code (Reference 3.4). DAGS 9enerated the severed pipe end deflection time history as well as the deflection time hi story of the safe end of the RV outlet I nozzle.
| |
| 4.2.1
| |
| | |
| 4.2.2.1 Generic RV Outlet Nozzle Guillotine Analysis (Cont'd)
| |
| Each time history was supplied to a DAGS post-processor, which generated fl ow area time hi story contributions of each end of the severed pipe, from which a conservative flow area.and rise time were determined for this rupture.
| |
| 4.2.2.2 Gen~ric RV Inlet Nozzle Guillotine Analysis The details of mathematical model analyzed (Figure 4.2.2)--
| |
| were essentially the same as those for the RV Outlet
| |
| .Nozzle Guillotine, except that the discontinuity of 1*
| |
| *. f the piping was represented at the lA loop RV inlet nozzle safe end, and greater mass detail was included at the lA loop RCP discharge le~J. The time history forcing function was applied at the rupture location.
| |
| I This model tonsists of 62 mass d.d.o.f. 's and 8 non-linear support* locations. Analysis techniques similar to those used for the RV outlet nozzle guillotine were I used for this rupture to determine the fl ow area and rise time.
| |
| 4.2.2.3 Generic SG Outlet Nozzle Guillotine Analysis I
| |
| The severance of the pipe from the lA loop SG outlet nozzle was modelled, and greater mass detail was in-I cluded at the lA loop RCP suction leg (See Figure 4.2.3).,-
| |
| This model consists of 75 mass d.d.o.f. 's and 8 non-
| |
| * linear support locations. Using techniques -0utlined _
| |
| in Section 4.2.2.1 the flow area and rise time were determined for this rupture.
| |
| * 4.2.2.4 Generic SG Inlet Nozzle Guillotine Analysis The discontinuity of the hot leg pipe* at* the SG #1 inlet nozzle safe end was modelled~ and greater mass detail was included at the hot. leg. Effects of plastici,.*
| |
| in the ruptured hot leg were included in the model at ,
| |
| the RV outlet nozzle safe end and hot leg pipe interface
| |
| (~ee Figur~ 4.2:4), and thes~ effec~s were includ~d in t i 1 rigorous time history analysis. This model conta.ins 75 mass d.d.o.f. 's and 7 gapped support locations. As in the RV hot leg nozzle guillotine analysis, flow area contributions of both the comoonent nozzle and the ~
| |
| severed pipe end were generated on a time history basis, __
| |
| and the flow area and rise time were determined.
| |
| 4.2.3 RESULTS OF THE GENERIC ANALYSIS The results of the generic flow area analysis are summarized in Table 4.2-1. It can be noted from this summary that the SG outle I
| |
| nozzle guillotine and the RV inlet nozzle guillotine result in full double-ended circumferential ruptures. The hot leg nozzle *
| |
| * guillotine ruptures develop less than full area breaks because ~
| |
| of the inherent strength of the hot leg piping and the stiffness of the supports of the major components. -
| |
| 4.2.2 I
| |
| | |
| *1 4.2.3 RESULTS OF THE GENERIC ANALYSIS (Cont'd)
| |
| I All four cases show rise times equal to or greater than 20 milliseconds. Pipe motion contributes almost all the
| |
| ,'I motion, and except for the RV outlet guillotine case, the components do not move appreciably as compared to the pipe.
| |
| For the RV outlet guillotine, the pipe motion relative to I the components is small. SG motion is the major contributor and total break area development is small.
| |
| 4.2.4 PLANT SPECIFIC FLOW AREA EVALUATIONS
| |
| .11 Table 4.2-2 shows results of the specific operating plants for flow areas and rise times, I 4.2.4.1 Calvert Cliffs 1 &2
| |
| ,. '
| |
| I The Calvert Cliffs plant was used as the basis for the generic flow area analysis models; therefore, the generic results are directly applicable to Calvert II Cliffs.
| |
| 4.2.4.2 Millstone 2 I The Millstone 2 plant is identical to Calvert Cliffs in RCS piping, component size and layout, therefore th~ generic results are directly applicable.
| |
| I 4.2.4.3 Palisades I An evaltiation of the flow areas and respective rise
| |
| *times of the Palisades RCS was made by comparison of the Palisades plant RCS geometry and size to that of the generic plant. It was found that for parameters which I control the flow areas and rise times; ie., pipe size and weight, pipe layout and length, system pressure, and SG.and RV support schemes, the Palisades plant was virtually I identical to the generic plant. Therefore, the results for the generic plant results are directly applicable.
| |
| I 4.2.4.4 Fort Calhoun An evaluation of the flow areas and respective rise times for the Fort Calhoun RCS was made by comparison of the I Fort Calhoun plant RCS parameters to those of the generic plant. The ~esults of these comparisons follow.
| |
| I 4.2.4.4.1 RV Inlet Nozzle Guillotine and SG Outlet Nozzle Guillotine I The similarity in layout and length between the Fort Calhoun cold leg loop and the generic loop resulted in full double ended break flow
| |
| ,I areas for each of these ruptures. Because Fort Calhoun's cold leg pipes have 24 inside diameter 11 as compared to the 30 inside diameter for the 11 1 generic plant, a full area break for the Fort 4.2.3
| |
| | |
| 4.2.4.4.1 RV Inlet Nozzle Guillotine and SG Outlet I' Nozzle Guillotine (Cont'd)
| |
| Calhoun plant is 905 In 2 . I In order to evaluate the rise times for these .I two ruptures, the natural frequency of the re-sulting cantilevered cold leg for Fort Calhoun
| |
| -~~~~ ~~-7 ~~~;d ~~~--~~~e-9~~~r~~:~~-~~-r~~~~~-~~~:rmrnl away from the component to create fl ow area)
| |
| * following the pipe tension release. That is, the rise time is a direct function of the pipe's~
| |
| fundamenta 1 frequency. Si nee it was determined
| |
| * that both the Fort Calhoun and the generic thrust forces were each large enough to cause full areal breaks, the amplitude of the thrust would only be a minor factor in rise time evaluation, and
| |
| *Fort Calhoun's smaller thrust would only have a slowing effect on the rise time.
| |
| I The fundamental frequency for the Fort Calhoun .
| |
| pipe was compared to the fundamental frequency for the generic plant pipe by comparing paramete:
| |
| *I for each cold leg. The fundamental frequency (f) is proportional to mass (M), pipe length (l), and pipe bending moment of inertia (I): I By computation:
| |
| MFt. Calhoun = 59% MG ener1c. ; M' = .59 I
| |
| 1 Ft. Calhoun =
| |
| 43% 1Generic; I = .43I 1.
| |
| LFt. Calhoun = 90% LG ener1c . ; l' = .90 f Ft. Calhoun = ~ :t,i'~)~ /'I\ '. x f Ft. Calhoun = (.l}3)fa
| |
| /~**c .
| |
| r~ sq) x f Ft. Calhoun = *9999 fG eneric. .
| |
| Rise times for the two Fort Calhoun cold leg nozzle guillotines postulated were, therefore, I
| |
| evaluated to be virtually the same as those for the generic plant. They are presented in Table 4.2-2.
| |
| I 4.2.4.4.2. RV Outlet Nozzle Guillotine and.SG Inlet Nozzle Gui 11 oti ne
| |
| ,1 Fort Calhoun 1 s steam generator and reactor vessel. support and accident restraint systems are entirely different than the generic plant's I
| |
| systems, and the strength and stiffness of the
| |
| *hot leg piping is lower than the generic plant.
| |
| For these reasons, a plant specific analysis I
| |
| for Fort Calhoun was performed. The results 4.2.4 of the analysis for these breaks is presented in Table 4.2-2. I
| |
| | |
| - - **- ;,.. - - .. ;.. - - .. -* - - ...,-* ... I-8V OUTL_ET NOZZLE GUILLOTINE BR£AK Al?CA ANALYSIS
| |
| ~
| |
| .
| |
| N FIGURE ~- 2.1 L ':.;\
| |
| | |
| RV INLET NOZZLE GUILLOTJN£ BREAK AREA ANALYSIS
| |
| .m FIGURE '/-. 2.2
| |
| | |
| - - .. ,*- - - - - - - - .. - - .. - - ... *-
| |
| SG OUTLET NOZZLE GUILLOTINE BR£./IK AREA ANALYSIS
| |
| .
| |
| ..i:::. .
| |
| .
| |
| N
| |
| . --..i FiGUR£ 4. 2.3
| |
| | |
| -- -- - - - -- - - - - - --* -
| |
| SG INLET .NOZZLf GUIL.LOTIN£ BREAK AREA ANALYSIS
| |
| -* -
| |
| I
| |
| !
| |
| I!
| |
| .
| |
| co ..
| |
| ----
| |
| ~1 :
| |
| F IGUR£ l/. 2.1-
| |
| .
| |
| . **"
| |
| ;
| |
| | |
| ---~-----~-~-----~~ ..
| |
| TABLE 'f.2 - 1 GENERIC PLANT PIP£ f3R£1JI< AREAS AND BREAK OPENING TIMES BREAK FLOW AREA RISE 1 IM£ POSTULATED RUPTURE (1N~) (MILL/S~CONDS)
| |
| *,+:=-
| |
| . N l..O RV INLET GUILLOTINE i'll'-1~ :Z.OA 23.
| |
| RV OUTLET GUILLOTINE* 135=.!9A* 20.
| |
| ~
| |
| SG INLET GUILLOTINE /000 = l.LfA 24.
| |
| SG OUTLET GUILLOTINE I'-/- I lf. = Z.OA 20.
| |
| .'
| |
| | |
| TABLE.: 'l. 2 - .i, PLANT .5Pt.C/Flt2 PIPE BREAK AREAS AND BREAK OPENING TIMES FOR MASS AND ENERGY RELEASES
| |
| /'05TULAT£.D RUl'TUR£ CALVERT CLIFFS* MILLSTON£* ?AL/SADES FORT CALHOUN
| |
| .
| |
| ..i::-
| |
| N RV INLET (1N:1) /l/-1'1- I l/-1 '-}- JL/-J'f *qo5
| |
| __,
| |
| 0 TIM£ (11SEC) '23. 23. 23. ; 23.
| |
| '
| |
| I RV OUTLET (1N 2 135
| |
| "
| |
| ) 135 135 . 200 ..
| |
| .**'
| |
| TIME (MSEC) 20. 20. zo . 20.
| |
| - I I'
| |
| SG INLET (IN~) 1000 .1000. 1000 '
| |
| 1608.
| |
| TIM£ (MSEC) 2.Lf. 24. 2'-1. 28.
| |
| SG OUTLET (!Nz). /Lfl'f I LJ- J lJ. lt./-/L/- i905 I
| |
| TIM£ (MS£C) 20. 20. :zo. I 20.
| |
| to
| |
| "
| |
| *G£N£RIC PLANT
| |
| "
| |
| | |
| I
| |
| : 4. 3 SUBCOMP ARTMEtlT AN/\L VS IS I 4.3.l Design Bases Subcompartment pressures in the steam generator compartment resulting I from dispersion of fluid emanating from design basis pipe breaks I were calculated~ Methods for detennination of characteristics* of design basis pipe breaks* are discussed in Section 4.2. Definitions I of design basis pipe breaks are a*lso stated in Section 4.2. The.
| |
| calculated subcompartment pressures constitute one of the forcing I . .
| |
| functions employed. in. the evaluation of the structural desi.gn.
| |
| I 4.3.2 Design Features I The steam generator compartment was subdivided into nodes to reflect physical plant characteristics with respect to components, structures, I ptping and other major obstructions *. t1i 11 stone 2 pl ant arrangement I drawings are shown in Figures 4-.3.l through 4.3.13, Calvert Cliffs l & 2. arrangement drawings in Figures 4.3.14 through 4.3.20, I Palisades drawings in Figures 4.3.21 through 4.3.30, and Fort Calhoun arrangement drawings can be seen in Figures 4.3.31 through I 4.3.41. The steam generator compartment layouts for Millstone 2, I Calvert Cliffs 1 & 2, and Pa-lisades are alike:. the compartment contains the steam generator flanked by two reactor coolant pumps.
| |
| I In the Fort Calhoun compartment there. are walls which extend back from the primary shield wall to the secondary shield wall between I the steam generator and reactor coolant pumps.
| |
| * I
| |
| *The gener.ic analysis nodal model. is shown in Figures 4.3.42 and I 4.3.43, and node and flow path foformation in Tables 4 *.3.1 and 4.3.2 *.
| |
| * I I 4-* ~ - l*
| |
| -- - --*-**. **-*-"-*--*""
| |
| | |
| 1~
| |
| Tabul a~ions of node and fl ow path parameters for the Mi 1lstone 2 and Calvert Cliffs 1 &2 steam generator.subcompartment analysis I
| |
| *are given in Tabl.es 4.3.1 and 4.3.2. Palisades parameters are in Tables 4.3.3 and 4.3.4, and Fort Calhoun node. and flow path data* are I pre~ented in Tables 4.3.5 and 4.3.6. The-meth-od~-by-wnfch the values-- 1-in Tab 1es 4. 3. 1 through .4. 3. 6 were determined for each s'peci fi c. .
| |
| *.*plant from . . those calculated- for the ge*neric . .
| |
| plant is.explained .
| |
| irr
| |
| . -
| |
| .* *1*
| |
| Section"4.3~3.J. - All **~o*d~- and flow _path tables correspond to the ..........** '
| |
| .
| |
| -~~ '
| |
| ,,.":
| |
| *. "w**
| |
| .
| |
| nodalization.sche~e -0f Figures 4.3.42 and 4.3.43:
| |
| *:.I*
| |
| The space _occupied by piping and component insulation was deducted in .
| |
| determining
| |
| ' *.
| |
| volumes* and vent areas .
| |
| in* the.steam generator compartment.
| |
| ' '
| |
| -1
| |
| ..
| |
| . There were* no movab 1e obstructi ans *to vent fl ow .that required treat-ment *. *. - .*. ,_. *.. * ..'* ..
| |
| - .
| |
| ,-
| |
| > .1:;*;:*
| |
| ,.
| |
| :*,_-_
| |
| ***: *1,
| |
| -
| |
| .... 4.3.3 ~-*Des.ign Evaluatfon*:~- ... ~- . --- --~~--~~~*--*~ ---~ ~~~:~ -~.:. -*: --*
| |
| \ . .
| |
| 4.3.3.1 Method for Mass and Energy Rel eases*
| |
| The modified CEFLASH-4 computer program was *used. to compute the* I*
| |
| pipe. rupture release rates. The CEFLASH-4 program is described I:_
| |
| *'*-in* Ref~rence 3*.s**an~.its*.acceptability:.is-stated i_n_ Reference 3'.6~. , '-*
| |
| **" ....
| |
| . . ' .. '
| |
| *!-
| |
| ~
| |
| * * : The modification to: this CEFLASH-4 code is: the incorporation of* a .. *-* :.1*- -
| |
| critical.flow correlation subroutine which conservatively maximizes
| |
| "' *. .: the bl.owdown
| |
| : "( .
| |
| rates~ .. This is the same critical flow*
| |
| -- ~ .. :, **.
| |
| s~broutineo
| |
| - ' ' . as* '. -
| |
| * 1-
| |
| ,:_; :;'~* .-
| |
| _, ... ** ..**.*discussed: in Reference.J. 7~ The Henry/Fauske critical _flow carrel ati on -, .
| |
| * is* used: for sub cooled . and
| |
| . . . . 1ow qua Ti ty fl . .. ufd . . co~diti ans and the*. Moody-_ -
| |
| critical flow correlation for: the .remainder of the *saturation -I
| |
| * *regime *. A flow multiplie_r o-f *0.7 ~1as used throughout *. Appendix A
| |
| *discusses the selettion of this flow m~ltiplier~ I
| |
| *Reactor coolant system- nodalization shown iri Figure 4~3.44 was used. -
| |
| -1
| |
| *4*3.2-.
| |
| I
| |
| | |
| ... - . . . . ,. .~ . - .*- . -.... -: .. *.
| |
| , ': .. -* -* ,. . .
| |
| . .*
| |
| .: ,:
| |
| .* .. -.
| |
| '! -:-*
| |
| :*
| |
| I
| |
| _
| |
| *. ,,* -
| |
| _-: ..",-'*
| |
| ,* -* . . :.:. _*.. *~* . :* *' ..
| |
| 4.3.:3.Z Results for Mass and Energy Releases I Blowdown release rates were generated for each pipe break postulated I I in the reactor cavity and steam generator compartment. Slowdown mass- *flow rate and energy release rate as functions of time are I provided 'as* fol lows~'* .*. *
| |
| .*_,:
| |
| . _*: <
| |
| .. '*
| |
| . -: . '..~ ,* .* .. * . .
| |
| Generic. Analysis I ':-~;>Postulated Pipe *Break -,-Table, Numbers* -
| |
| I -------.~~.-~~----,_.C nv'~~~;~)4l135~. ~n: bre~k ;, *C.**. outlet
| |
| '.** '
| |
| in~break
| |
| . 2* - '
| |
| I SG, inlet. 1000 in break.
| |
| - SG. ~utlet* 1414 i~ 2 break 4.3.9A.and 4.3.lOA and 4~3.98 4~3~108 I -*-*- ..
| |
| *.These tables are- for- the generic mass. and energy release analysis.-..
| |
| *- .. ,-,. ..
| |
| : ~( -- . -. *,_ *' '. -*:. - ... * .. *. .':':.:;*.
| |
| *:,'... ';
| |
| I
| |
| .:. '.*',
| |
| -__ ;_*Plant specific mass. and energy releases are. discussed in Section***
| |
| .*. *. . . ;4; :i.3.3.; : : ,,,, :* r~;~ '.** :, .*,. :** * * *. . *.* . ,
| |
| I -**. * - :-~~;4:~3-~3~*. 3: **AppTfcati-o~*;'af Mass-* and Energy Release Resu1ts'.-c'~'~:::~:.
| |
| This. section discusses. the determination- of pipe break releases I .
| |
| *.<:for*
| |
| .
| |
| the individual plants. under consideration.
| |
| . .
| |
| A comparison of I
| |
| . \},'.;~~i~~~~~~;~~~~t~I~~!"~~~~~;~~~~;:~~::::o:\:~e .***
| |
| I * *-* < :.. L:X;'-.:;<,<:j:~c; ,_
| |
| * I *.,: .. *:_ . :.,* :~_,\The* ..:::::* .. *, < Millston~.
| |
| :<:::~~f?i*~Jti;:/;~
| |
| Calvert_ Cliffs and
| |
| *.*.,*.~.(*.;; :;>:~-:~:*:~f:.-~-:~"~~.:.::~;:~i~~~J~~~~J!ssenti a:11*y- ;*den.ti,ca1~~-:*an*d:.:*served.**
| |
| -~.:* .** .-.~:--.*_.
| |
| Reactor Coolant Systems are*.
| |
| __,.*-,_-**:*** .
| |
| a-s **the. bas.;*s.- for~ the. gener_i*c*... .._.: ,~ ... * ->*.** *:* *:. -~:. * ._
| |
| .- .. *,* ..... .
| |
| *. *: ,. ">>:<:t*~:,{:,:'_1)~r;~fk~,::.:->~:,: . *;f:.,,. *< *;~'.:. ;:_~t: ::*,_:\vi,-' ;>*,* . '{J::.,1.,;,;~.r,*:**;:: '. ;iz*>,;o*;,, :_;>~r'~.,;;.*~; ~:~i;~,) ::::. '.~~§:~*~: ~.\<'. *: *.. *1:1;:c:->~.<~-:.J:sf':(; ,:;:::;r:~?~/~<*:i.i*. :**~ .*: : *_:_**_
| |
| 3 s*
| |
| I *.: * .:.{.;~.**r::*/I:~~-J:~a~~~~s]s~.~ ~~*****r:~_:]. ~dfcated'\~-~-~!ab:Je,*4*~3~1,s;<;:~~>r*,~1
| |
| . . isades* sYstenf ;;~: * .*: _-_ :.* , . . .*
| |
| *c':)/* similat. 9~~metri-cairy, and' thennodynarni,ca11:y to: the: generiG,\ ex.cept~
| |
| -I
| |
| -. :. I* *, : < **
| |
| * l i - *** * * * * ** C ~: * * * .. ' *~ ... ' * * * ~ * - * .' * ' * ._. *. : '
| |
| .... *the' intti.al pressud zer'- press~re *. Since the Palisades system * . * . *.: *. _,-'
| |
| pressure is initial Ty. less th~n that of- the generic, this c,auses the-. generic system model to be. conservative for* the Pali sades I ' , ~
| |
| ... , ...
| |
| app'i'ication. '. *
| |
| .-*.:,
| |
| - - '
| |
| .
| |
| .
| |
| :.
| |
| '
| |
| :*
| |
| '
| |
| ,- ..
| |
| ..... *, :*. : .
| |
| .. .
| |
| I
| |
| \
| |
| * ~o *
| |
| ' ' *' **
| |
| . .;" *~ *.* :
| |
| ,; . . -~-' -
| |
| *: ,,*.::' .;:' -* .:*:.*. *f* .... *.' .
| |
| .. .
| |
| | |
| . ~.::;_ . .. -.-.... : *;-
| |
| ~
| |
| --.-.*;~......:::*: ..~~::-. -=~* .* :'..-.~~;,\,:: ~~- .'
| |
| . < ...::.../'*;.: ~ .. ~'.:.
| |
| *' * -* ; : *; ;
| |
| * I *, ~ : ,. ' ; : * * ~ "<. *- *
| |
| ..
| |
| priate for Calvert Cliffss Millstone, and Palfsades~ so the mass and:
| |
| energy releases of Tables 4o3.7A through 40:3. lOB were used for these*
| |
| plants *
| |
| . '. :.: . .*...
| |
| .. '* ~ ,
| |
| dedicated.Fort Calhoun.CEFLASH4 RCS input. model~ was used-~. The :* .. _, ..
| |
| Fort* Ca 1houn* mass. 'and energj releases are: given as' ; ncii"cated .here;.: . <>. ,.>*: .
| |
| . *. ** * * *. *. **. .*. Pos~~t~~1~~~f :rI~J'>iLn~*\~~~;x*~.Jtl~:ab1e. Number~ 'J\i) ;~;.~*,t~{;*~~~!t~
| |
| 2
| |
| . . RV .. ml et. break . , .
| |
| 9.05 .Jn . *c. ,, . , ..4.3.J 1A. and. 4,3.ll B *.. , . , , ,,, I.
| |
| "Di~:r~~~J*~r**~g~i~;~~~~;.~h.;~1:*''~~1~~1~~*~~7~*~2~g~*!:Jt~fi\i$~**~,,,~i~~!l~~ft;i SG' inlet 1608. in ** break .* * * * * * * **. 4*~3.13A and 4*.3*.13s * *. * * *. ' __ /; *;-:*:
| |
| ****. SGou~ii~ 905 in2.,bre~k .'. > , ,.f*,~:J4A and 4.3,.148 .* ., .* .,
| |
| *- - _., 4.3.3".-4' Method for. -Steam- Generator Subcompartment. Pressure Analysis* *_ * ~,-*_
| |
| . . .<>: o:.:.: *<"-.:/ ~. . *:;:*_-~.. ,:_~*; ';*.:.: *1:<>,,;;," :-:*(.~'.:::::.-.: .:.< ;_;<'..**., :*,* :;:: '\ _,.__;.,,':>: :.:,. :: *k-:'.;, :".~<2>:,.-,' . -:,,.:,. :---.-* ::::.: ..,,.,:~:;<,;> '.:~~\: :,,;_ .
| |
| ..-., :*:~:'.;:. :~':.-Jtie' oriii=F:~f:m)of '(Ret~;en~e:*3:s> :.-.co~p~t~r; P.r~g-;an{"~~s-~'dseci*'.ti><*?~:**(::'/)~.~:*\f~JtK~:~r~;~~
| |
| --.." - ,:1::'_.--_*:: ;- . :*. -: :'~-* ::< .......,.. ,;-,<*<(.:.~;I~:.* -~*- ~:. *.....* *: '~:._~/:},. _.~,-:> : ,.__....._.< :'.".*":*/ .,: -:*>~~::,_ .--:-.-.: .".. "\ ,~,* *. ;~~ :~Y/~2(~: ::~i.::~~:*,,':~;., .."':~(~::~
| |
| . I.** perfonrr the. steam* generator compartment subcompartment pressure - - * .. * ::.-"~-- *,_,
| |
| . .*. . . -, \ ~n;l;~js<
| |
| -:* ***-* .<,.;,._;>"~:<-.-'._
| |
| A c~pa~;nt im:,1 ~i.~~ode '. spac.,-t;~'.: l'ressurec r~sp~nse *<.~';+ N
| |
| . :. ** *. * *. -.*,* .- *_--- .. - :-,c:: . <.,*">.":-,/*- 1
| |
| "'"-*:*;:*:.::_:~* *,;:::*/-('.*-'z.:,::...:-._~<<:.:;**;:~*;'~':::*'._~:.*:~-.:*;~;",:,.Y<.-*',;~* . >''-*'.:::~,*'. :-,
| |
| **-* -** ..... ,.*:,.analysis. was made *.. , _.,, ** .*:*".. ""****:* ,<<.*\*'.>>~ ""'"**''*c*--***" ._., ... -"* ..._
| |
| **~~~~~
| |
| * *~ .
| |
| _:: .._in. pressure with1n.. a node because . of* geometric. influences were
| |
| .. . . . ~
| |
| precluded*
| |
| . ..
| |
| -- *
| |
| -
| |
| '
| |
| , : by . the _-model *.5.elec~ed~ _. Ad~~nt~ge- wa~ ~~k~n.~f- _nod~l i z~ti.on:- s~n.sit1v.ity_
| |
| .*. *.**. .**. :~::::r:::~ iri;S:~~:~:~:~. Gu::::::a::;.::~:::t:: :::1::v::' s""'
| |
| 0
| |
| ***--...**
| |
| studl~s,7~~i~:t(;;*k~;"JJ:;~;.~:~~:~J./~'~.J~.f~)iil~!i~1~~~~~fl~~,~~J~*
| |
| | |
| ., ''. ,,:*
| |
| I ..;
| |
| I 4.3.3.5 Reactor Cavity Analyses I Independent reactor.cavity analyses. were.performed for- the. Calvert
| |
| *-
| |
| I
| |
| -~.
| |
| Cliffs- Units, *Millstone, 2,. Fort. Calhoun and Palisades*. The° Calvert .
| |
| Cliffs and Millstone, .cavit:i.~s are very similar,* differing
| |
| - in . the, type of. ne~troti streaming; shield I ' . . ~*
| |
| I 4.3.3.5.1 *Description of the Cavities **** ..
| |
| I a) Calvert Cliffs
| |
| .....*
| |
| ,* .. :.
| |
| *_ .:. '
| |
| . . .:: '
| |
| I
| |
| :., . ,.
| |
| *. ~e reactor: cavity* ,of the B.G.&E *. Calve~ ~liffs Units rand.' i ~s:
| |
| composed of two diff~~ent 'se~tions (Z) :' The support* on"' th~***-r~~c~~r* *:* '
| |
| I * *. ***.*. * *..... yessel. (RV)* hot leg rests. on*'a*. shelf ~t*
| |
| 1\ 1 :~*~
| |
| elevation 29 '-4.~'~ * *The two*:
| |
| dfscharga:. l:eg* ~iipports sit o~-* ~h~lves~.at*. elevad.o~- 30''~10'~.'.> *The::
| |
| *.1**
| |
| * * : **:.: ** * :.
| |
| *- *-- -'--,~-* -'*.
| |
| ...
| |
| *:-,:.=--:'***"'*-'-~c .** portions of: each support are, s~t:'*agains~""part:i.al walls. exte~ditig: o~t- .*
| |
| into the reactor cavity.* Thus, each* leg is set in a*"well" bounded on I , . either Sid~ by* partial Walls and extending . fTOM elevation 29 I -4 II (or:
| |
| * *.* .30.*;:,.10 11) to*the*vess~l ~~aielevation (44'~10")~ ** *' :>*;~*~>.::*-*,,*: .
| |
| I <:, * ,*.~*. ***~~1;.,t~: -~~;;;~t~; ::;.~**~~~~;;;~iii:~~ ~'~ !~i:1~1*~;~~ ;:~:~~:1*:;f,~~x:.1~* '
| |
| *. " '}\_(r{ p~lyh~dron. .nii~.~ sh~~*e i;c,:~x~e~d~~<t~-. t'i~e *~~tt~m*.*,0£ th~" ~arlty ~f. *: . ".'" :'*,."' ";\,,*. I I . *. * . *,;_ elevation, 8.'-5~~' *. In this -~ower region,- insulation is placed against. '
| |
| *the* walls* of* .the. cavityc aJ1d aroimd* the excore neutron detector&. This ,; *.* .. ,
| |
| I I *.*.-...:~. *:; .. ;. ,* .' {*> **.:: ~ :**< *,,*. -
| |
| I +/-fi"i~e.upp*e:r:*~~vity~;-insulatiori ~gainst ~6z*zi'es**
| |
| **:**
| |
| * ** '. :i.s:placed' the vessel,' the,
| |
| ***.and legs. A convection barrier of in~ulation at* elevation 2~P-4" is I placed across the-annular air space from* the insulation on the wall of
| |
| , I- - ,, . .. ~ .~
| |
| I ..>~
| |
| .
| |
| :
| |
| | |
| *.: .*.
| |
| I the lower cavity to the insulation on the vessel in the upper cavity.
| |
| This convection barrier is held in place by stainless steel rivets I
| |
| and screws which attach stainless steel angles to the insulation. At the narrowest portions of ~he cavity, upper and lower insulation panels are so closely spaced as to block flow without. an additional barrier.
| |
| * The penetrat~ons~ in th.e upper primary shield wall (PSW) af-_e_ tapered ....
| |
| *::.:
| |
| to .their* widest diameter* at. the exterior face* of* t'he*wall-~ Above the--
| |
| seal at elevation 48'~3~"' there. is. a rietitron--shi-eld consisting of
| |
| *_:,-*
| |
| water bag~ 4 resting on a steel .. framework ( ). The framework is supported inthe cavity at the seal elevation. The neutron shield water bags are designed to blow away if the .cavity is pressurized by a LOCA -""'.
| |
| I the water bags tearing- op-en' as t1iey are pushed away -from the frame.
| |
| --_I
| |
| :")*'; ;
| |
| :I
| |
| *and,_ the annular *space between the. reactor and. the- PSW at elevation 44' ..
| |
| .:~:r:i:::r::ed::::r~sa:l:::::a~yl:c::"on~~tiOn of.insulation and . . . .. . j . *.*
| |
| b) Millstone 2 I
| |
| The*. Millstone* 2 cavity is 'esse~tially identical to that of. Calvert Cliffs~-
| |
| * However the neutron*
| |
| drastically diff~r-~tit.
| |
| cylindrical ann~lus:
| |
| . _,_ ---~~-
| |
| streaming shield configuration. i_s -
| |
| .-
| |
| Th~. streaming shield. c-on~'ists' of a segmented
| |
| _composed of tanks containing water-. The bottom
| |
| .. ,
| |
| . I-.
| |
| *;*..
| |
| _ and. top of *each shield segment: are designed to rupture under the
| |
| . *for~es resU:1t:i.ng f~~m LOCA~. .The ~hield structure. i~ clamped on ..
| |
| -I
| |
| '*/~.
| |
| - ..*:**:
| |
| _the vessel flange. Differences in the ves*sel insulation placement*
| |
| were. considered in* the modelling of 'the cavity. I I
| |
| I
| |
| ';.
| |
| I
| |
| : 4. '3 .t:::,
| |
| I
| |
| _ _ _ _ _ _ _ _ _ _ _ _ _ _..:..___ _ _ _ _ _~--~-----=----=----=--=----=--=---=--=---=---~-----. ---------------------------------
| |
| | |
| I I c) "" Palisades I The reactor cavity of the Consumers Power Palisades Plant is essentially a cylindrical annulus formed by the reactor vessel.and the inner face I of the primary* shield.wall (PS"W) extending from elevation 590 1 to the (Ll) . .*
| |
| * refueling pool seal, el. 624 '-6". The reactor. vessel is supported 1* on*. one hot. leg and two d*ischarge legs* The supports rest. on beams which.
| |
| * extend across the ~avity *both vertically. -an.d. *laterally into -the. primary: .
| |
| I shield wall. Each support structure. occupies about 9 feet: vertically and 12 feet laterally within the volume of the cavity.
| |
| I Insulation covers the reactor vessel in the region of the cavity above
| |
| * the supports* and .is placed against the PSW below the supports <3 )
| |
| * At*
| |
| I the interface at the support elevation, there is a convection barrier
| |
| * ..
| |
| across the width of the annulus which prevents therm.al contact between I the two regions.
| |
| I ~------ --*--*~ -~-.-
| |
| Concrete blocks *a.re bolted in p!ace in the openings for the legs in the primary shield wall between the legs and the wall. The blocks are shaped I to prevent any flow through _these penetrations. There is an open 30 inch access passage* in the lower cavity just above elevation 590 1
| |
| * This I passage leads. into one of. the steam generator (E-50A Ill) compartments *.
| |
| I d) Fort Calhoun I The* reactor cavity of the* Ft* Calhoun.* Unit l NPP' is essentially. a series of; stacked cylindrical annuli extending from. elevation 976 '-6". to ...
| |
| I elevation 1013 '-0" * (lJ_J
| |
| * The four reactor vessei supports sit on a ledge at elevation 1001' -6 7/a"*; beneath this elevation,_ the *cavity has an I irregular shape as there ~re cutouts in the. primary.shield wall to accommodate excore neutron detectors. In the immediate area of* the I nozzles, the cavity takes the appearance of six interlocked pipe penetra-tions. Above the legs, the primary shield wall (PSW) is brought to within I
| |
| I
| |
| | |
| . ~
| |
| '.:--
| |
| ,. ,_ .... .,_.__
| |
| ';.* .*. '*
| |
| -'' *'.
| |
| . '*; **.,*.. ** *'
| |
| .. '~*
| |
| : a. few inches of* the vessel up to the seal elevation. Within each of the pipe penetrations, a .. sand plug blocks* an access passage into the refueling pool.
| |
| I
| |
| . . . . *I***
| |
| ....-
| |
| Insulation within the cavity - is* placed between the. vessel and the- PSW; .. . . . . .
| |
| -.
| |
| .
| |
| such. that there are sizable gaps. between the insulation and: the: vesse!. * * .
| |
| . ' .' . . . . .. . .
| |
| *:*/'I .
| |
| . (14)* *,* ..; :.
| |
| -.above* the legs*. At. the. bot~om.of the RVI, the. insulatiot1.is***"squared!:.0££n_,***.:hL:.~*'"
| |
| .::::t;~.er~:ea:~*::~a~~n~::::~1:::: :*.:::.*:.i5::ij~J£'.~;\lfI; 1
| |
| ,,.*.*.
| |
| on:. the' legs *.
| |
| *:'.
| |
| At* the~. bottom of the cavity, a barrier door. separates access The tunnel opens
| |
| * into the* contai~ent:
| |
| . --. --*
| |
| . ,.. ' ..
| |
| . ..
| |
| **1
| |
| *- : .-~
| |
| :..-: . .* : **,. "
| |
| '~* ..... ., ..... . .. * .. .
| |
| .. **.-
| |
| ~-
| |
| \ ..
| |
| -,---***. *'.,,_*
| |
| . . ' ... .';. .\ .~*.
| |
| . . .*
| |
| - --** ..... *
| |
| ; - *- . . ... ,
| |
| | |
| I I 4.3.3.5.2 Derivation of the Subcompartment Model I
| |
| The analysis of the pressure transient due to, a pipe break in this I compartment is. perf armed using the RE.l..AP4-MOD6 computer code (l) ~** . This code- simulates. the reactor: cavity in a lumped parameter representa,-. . :.-:.-.,
| |
| I . tion. as a series- of sub compartment. volumes linked. by junctions; with: .*
| |
| *fl()~ pro~~~'tie~: in- thl~
| |
| *:*'*
| |
| *particular :_' tlle-program options used study*
| |
| I include:
| |
| (a) the REJ..AP-4 CONTAINMENT option, to account for the I presence of air. in the volumes; (b) the thermal homogeneous equilibrium model (HEM), for I determining the. critical flow. for air-steam-wate_r
| |
| * .. */, -.
| |
| mixtures; and I . (c) .*. the: compressible single-stream form of the momentum .
| |
| . . . .
| |
| equation,. as this break c~se produces relatively 1------:_ -* * ' . .
| |
| high pressures in the cavity subcompartments.
| |
| .
| |
| I The effective inertia (Z/A) for each junction is calculated in a manner consistent* with the methods used by the RE.'tAP-4. code for one-dimensional I models.
| |
| ~:Lan~ ~'
| |
| For a pair* of: vo_lumes vi. and vk' . with. cross-sectional* areas, and* lengths, i~. the dir~ction:.-of f_lo_~* Z~i: ~nd~. Z:k'' and. 'for'.*~..
| |
| __
| |
| .... :.
| |
| v~- and ~k.:~ith a~e~ Aj andc length Zj' where I junction between and* Z:k: and may be zerpl *the ine~tia coefficient, t1 << *ii_ .
| |
| .-. *
| |
| * I ' . . . -. -. .
| |
| re :,:i:,r:~ '.A:.~'*+* *. *.~.***
| |
| . . ~* .. *. ;
| |
| I Flow coefficients. for friction and .ir~eversibie .losses
| |
| ' ,. -_~,-:*
| |
| we~e*: *ai~o computed I in a manner consistent. with .the calculations: p~rform~d by* .REW-4.
| |
| * The I
| |
| I \.
| |
| I
| |
| *'1.: - - .* . '.'_~* .
| |
| ' .:..:
| |
| * ' I ' * ' . * *,,::*=*
| |
| ..i *..
| |
| 4-*.3 A:
| |
| ***~---*--,~*--------.--~*--:---.~**----. ,----,--,*----- -*-*- *-*-** --~-,. --*.---*-**-***** -......,.--*-- . -*-****~-.-...----- ~"'""'."'"""--*-*-;--:o--...,-*- ....."":",_,,_....,~-.- ~ --..--..,,-..-----~--*---.-*-*~~------:
| |
| | |
| . ~ .
| |
| junction "fo:tm loss _coefficient" utilized in the* analysis is a combina-tion of the wall. friction losses (~) and any irreversible friction I losses due to area changes, turns, obstructions and gratings. The.total.
| |
| wall~: friction loss
| |
| _.. *'
| |
| ..
| |
| where DHi, J, k. are** tlia hydr~ulic** diameter~ of the .s!stelil. *. Typical values ..
| |
| . ~fi density and. flow for*.. the:. upper cavity _were.* used to._ -~~lculatec the*'. ... '.
| |
| | |
| I I K e
| |
| :a (1 - _M_ ) 2 * (5)
| |
| Ak (6)
| |
| I
| |
| ,I Additional losses due to turns in flow direction or other changes in area were included as:
| |
| I (6)
| |
| (7)-
| |
| I Thus, the total loss: coefficient for each junction is calculated from Equations 3, 5, 6 and 7 as:.
| |
| I K (RELAP-4) = -7 l{__ + Kc + Ke + KI (8)
| |
| I I Loss coefficients for both forward and_ reverse flow through the junc-tion (in the sense of the RELAP-4 definition) were.modelled consistently.
| |
| I A multi-volume model of the reactor cavity compartment is constructed I by considering all the physical flow restrictions as division between subcompartments. A flow restriction is defined by* the presence-of _an object in the flow path which alters the area of the. cross-section-, with I .
| |
| the subdivision* defined at the poin_t -of minimum flow area.
| |
| -
| |
| This mini~
| |
| mum flow- area is the'. junction flow. area used in the RELAP-4 analysis.
| |
| I By choosing v~lumeboundaries at* the var:f.ou~ physical flow restrictions,
| |
| : a. method consistent with the lumped-parameter model used by REI.AP-4 I as described above, calculated. differential pressures will reflect the actual parameters- for flow in the c:ompartment ,. and the consequent _.
| |
| I external asymmetric loads -on -~he.RV can. be re~istically c~lculated. <7 ,Sl _.
| |
| . . . - .
| |
| I Figures 4.3-81 through 4.3:....ss show-a s~hematic:ofthe subcompartment models employed for each of the cavities analyz.ed. For Calvert Cliffs I (Figures 4.3-81 and 4.3-82), junctions in the model are defined in the I
| |
| I 4-* ~. r1
| |
| | |
| ..
| |
| . *' .. *
| |
| **. *;;;s: * **::;:::r*.itt
| |
| .. *: . '.*. .*.* *.,*' .. -*;.**,-
| |
| :,;* ,:* :. ** ..:. .'
| |
| .~ . : *:. : . .; . :; "
| |
| .. .. ._ ': .
| |
| . -* .. '"
| |
| .1 upper cavity by the hot and cold legs, the partial shield wall,* pipe penetration entrances,* the convection barrier and lowest elevation of the supports, and the reactor*vessel flange. In the. lower cavity, the subdivisions are defined by the, presence of. the. excore neutro.n. *
| |
| .detectors. and the angles madeby*the PSW that create a minimum_ flow
| |
| *" ...
| |
| ~!~::h:~g~:::~:l:~::iS~:::e: ,:~~~~:.~njd ;::~~;i~;frc;,.r.,¥i~Jll~li 1
| |
| The actual values of volume
| |
| * and flow. area used in the RELAP-4 analyses*
| |
| are* given in *Tables 4. 3..;.21a. and 4 *. 3-:-21b. . The calcuation of these* para-:-
| |
| . . .
| |
| meters* is .based* on detailed* drawings. and realistic "worst case'.' approxi~.
| |
| i mad.ens. were used wher~ uncertainty existed.* . The. upper cavity sub-
| |
| *. division~ corresponds*. to: that:. used: on mari.y other. plants. and which has; ....
| |
| . b~-~~: shown' i~-- s~~iti:~it~:~~tudf~:~, {T-, S} tb be:: :~on~ervati~e* in'*:* ~~f6'ui~~-.
| |
| ting; forces and*. moments-. on': the reactor. vessei due; to . a. pipe break .in
| |
| *. * ._..; i~*::~ha**c~~+/-t;.;~''.. -Th~~~:-*stl.ldi~s:sugg~~-t:-*ih-~f*:_~h,~~~-/)~_no,mof~ *th~~- a +1o%_ *"'
| |
| tincert~fnty in the rescl.t~ obtained;. azid-c::tkLiCfigtir~: is applied to th~'-:
| |
| ., *-
| |
| results given in this. report..
| |
| assumed to be the.volumes .. over.supported legs.
| |
| The break- .locations for this study were ..
| |
| Volumes 2 and. 3 wer.e* the . **I*
| |
| ...
| |
| **-.
| |
| . ..
| |
| ..
| |
| .I
| |
| . ~ : . *,, ...
| |
| .* :* ...*:* ...
| |
| *.",.*,
| |
| .-.* .
| |
| .... *: ... -* .*.*.-:
| |
| - . . **
| |
| .- ...... ,
| |
| :, *;, *"'
| |
| *..... ._,:
| |
| "'.
| |
| *:.' -*
| |
| <-;
| |
| ....*..:*:.. *<: . "*:," ,... ~- .' ..
| |
| . : ~
| |
| ";*,; ..:....,.
| |
| '. ' ' . .
| |
| ... ' .* .... , . *. ,£ *~*,,
| |
| ... ~ ....
| |
| .' _,,. .
| |
| | |
| . *..:_'
| |
| I I The. actual values of volume and flow area used in the RELAP-4 analyses I are given in Tables 4.3-22a and 4.3-22b.
| |
| parameters is based on* detailed-drawings and consideration has been.
| |
| The calculation of these I given to the bending of' the:-- insulation panels in . the mid..,.region of **
| |
| * tha cavity' under the influence: of.. the signifi.can:i: pressure . forces.~
| |
| '*_'~-~
| |
| ~~S': m~de.ll~d~: :~~-~-!~~-~- s~t11plY: .~u?:~o;::_e~ *. ~f-* the ~ed~~s:::.'. :_ .~~: ,.:<~;~{~?iJ~/~;~;~:';:;}:J~:i~:~-'.**
| |
| I
| |
| * insulat:ou deflection of tha insulation-.:against.
| |
| .. as:
| |
| .. :-~* . <_:-: _,~.; *..: ~-* ;.* ~* ;:- :.:< ~ **:: _:>-:~:.;:*:: ;:~. -~. :.*.-.:. _-- :: ;_. :;_ ~::.... .
| |
| 1
| |
| ***
| |
| the,*co.ncrl!t~. of*** the:.PSW' has: the* .. ,:':'~>;:~~;;:;*:S:;;,~*zrf:;:::,'
| |
| -..:\,~"*::~:~* .;* :.:.: '.**: :***" :-~!::_.;r. *~**!"~*~'. :: .? ~ ~*~\~\:{:*.~/?.:. ~*; "<:"'=*.'2~ -~~>;" :* ;~ - *:*.:;* *-* ~--:'. ~.-t::~.:.~~**/~:\.(~~:~ri*~~-!:~:;'.*~~;~*J:~~1f;~.:*r~. .}~*:*:~{ ;~~::~:
| |
| **
| |
| ,.
| |
| . '., ,. ;* effect<of'.'increasing* the; flow- .area: betWe*en::.the' volt:imes*' modelling., the:*> . ;c):;-;ii'.l;f:,'~-.~.););t)i"~~
| |
| I ' ..
| |
| * c~vity mid..;regi~h~~ ' The ~re~{-"+/-b~~~i~n~ and ~od~llilig ~;~: 'iden~:id~~ ;~'~-:,}:,:'.'.'~i''.i,?'.~~~{t':/_;~~:~'.t:.*;,::,
| |
| those employed for Calvert. Cliffs. ...
| |
| I
| |
| -* For_ Palisades (Figures 4.3-85 and4.3-86), volumes.and. junctions are.
| |
| - . :*** .-
| |
| **.. _.,
| |
| ... * *
| |
| . *
| |
| ,_.
| |
| r' I .defined as.for. the Calvert Cliffs, and Millstone.2 Plants.
| |
| . arid. 4 *. 3~23b. give the: vaiues of. the volum.e and £.l~w area parameters*::
| |
| .,., "*-'
| |
| employ~d*~ *:v~i~t~~'.*j?~~ci;i. W:~;~\1i~ :.bre~k :'i~c~t:io~~,.'.f~~"the.
| |
| 0 I '
| |
| leg:.break; and volumes* 3: and': 4:: wer.e the* br~ak location~: fo~ the .
| |
| .'**:* )t~:.,',*' '.**,*~ .* 'Y''\.'"',:'.' ... ;.*.,,.<,':*:.....** . '.';.;,,.'':".:,''.,I,~'*:.,,<_": '~>:*::''.:*<:' *',"t**."-::*:**.:'*:*:-:--*,~;,. "v".':
| |
| dis.charge.
| |
| '~/
| |
| *.leg: break,. 'with* the' flow- 'being*, equally :divided: between..
| |
| I : . * ' ** .* . -,-.* *- . _;~:);;i~~-\~)\'.X~- :.):;, . ,- .
| |
| volumes*.:* . ,. ;;. . .. . . ..
| |
| _, -"-\. '*
| |
| * . . . . . _.***Y.*c*
| |
| I Figures 4.3-87 and 4.3-88*'.show. a*. schematic of the Fort.
| |
| '
| |
| <.
| |
| * r*> ,.' '~.,:,..
| |
| -
| |
| ment model.
| |
| I I
| |
| I I
| |
| I volume.*.*
| |
| -:_<<*'"
| |
| .,_ ...* *.-.**:::.
| |
| - *"**:
| |
| **"**,*
| |
| I I
| |
| 1*
| |
| | |
| '.'.~. ~
| |
| . ,.;;;;:;*;.
| |
| 'l._*
| |
| -..... *'
| |
| ,,, .. - ...
| |
| . -' .* . -*.*, .
| |
| .... *,.
| |
| ~ '* . ** ..
| |
| The position of the insulation in the cavity determines the cavity I
| |
| free volume and flow areas and thus will have a siginif icant effect on the differential pressure calculated by REI.AP *.
| |
| I For Calvert Cliffs and Palisades~ *the insul~t~on occupies approximately - *1*
| |
| . *. . ~:f;::::e::l~~~~~~~:r,~ii~~;:l:::e;:~;::~=:?i:~:.:.;:*i;'~~~t;~f~I~;
| |
| The *principal component.' of the- ins:ulati6n _is: the-convection'-barrier. that: ':*::-*~*:'~'::::I;''.;~,
| |
| blocks f iow from upper to. lower cavity volumes-. For the CalveJ;'t Clif fS*. '
| |
| cold. leg break, for eX~ple, this . flow obstruction* maintains the pres-.*
| |
| sure* differentials .
| |
| (V7-Vl)
| |
| .
| |
| arid. (Vl0-V4) . .
| |
| at constant high ],.evels.of_ about
| |
| *.:I<
| |
| .*.._ .. ''*.* .. :*:*
| |
| . ~ . :: .: ; - -_~;,* -~ ' ,;:
| |
| .60 psid,. or about 600, o_oo lbf. laterally. The lack of an insulation
| |
| .. *barrierwould. have. the effect.of: distributing the .flow throughout: :the_.
| |
| entire:' c~v:l.'ty d~ring/_ an e_arly port:tciti: of':-~11~:-- transient reducing' the'~:
| |
| upper cavity vol~es- wili* be pres~urized.'. t,o well above :3Cf ps{a. iii- *; ,, . ~ . . ..
| |
| . . . . .. . '
| |
| all volumes-- of the ~p_per cavity. Given the time histocyof the pres-
| |
| . surization. of the upper* cavity,_ it is* clear. that the* pressure differential . **
| |
| between upper and lawe~- ~avity* volumes{ WiI.l tear aw~y :the conve,cti~n * . *. : -.* :::::*+>*;.~<
| |
| . 5:::~=jdf~~::::::t~~~F:;;::e:~:::::::;ts::J''J~;~~~tl~i~!~
| |
| ~gailist
| |
| * the ~es~~l where it, is not to~. completely~,
| |
| '.*' .,- .*.. . . *- ,.'.*
| |
| ';:.. ***..
| |
| ' *. -_'.-_"*~-~.':. *. :-.- ;* ~".-', .,. . ' '* ~~;: ' . ' _:',,"":.},::**\;>,;-.~*: ..':*:*~*-.*~ <~', -,.~<>*.,. .-:..:*.~.- '"" ~--:* <~*'
| |
| )_~;~i ~--- , *_;*:<-;~*,';>.,,:.;~~-fi'fa,_;,t/_ ;;;~:-::;;_i~}1;;,,,_;::::e.t: .----'*'._ . * <:_:_ -*;.:* ,:;~- ' :"* -- '<* * - --
| |
| ** *... *.* ..-:There is_ an. average-cross-sectionaLarea of 900 in for the. convection
| |
| .-.*''.:_>\,~~;!~~:_ ~~ne1s** a~sumeci:--,t~ . . .
| |
| '~~~~ awaj:I~: t:ii1~---~~i~~is .:-- - Tlie,;~ne1s
| |
| *~ ...... ': . .: .., - , . . '"*" ,' .. ' . . -_, ..
| |
| . , assumed. to begin': tearing* at three times their: assUm.ed weight*~ approxi;..
| |
| . _mately 431Tlbf'' translating to a; presenire: o~ each* sectio_n of ~**~ psid~ . :
| |
| *:_ . ::.1**.*
| |
| *..*,-_ .. .:.
| |
| Once this "pressure:'"differ~ntia1 was reached; the 'area w~~: ass~ed' to open at a linear rate. ta 95% free area in 50 msec,*and to 99% free area
| |
| .**,.
| |
| .I
| |
| ......
| |
| '**;";_' _; . . \;._.-- ..
| |
| .*: '*'--,!**
| |
| :;~:1
| |
| '\,
| |
| - . ,': ,.
| |
| . . . . .. ..... -.
| |
| ''. . .. *.. ; .".. : . :< . ."
| |
| ; *.*. >c:;:J,
| |
| *~\ '. '. : *:-;- " :.-: - ~ ....
| |
| ... '* .. <*. - ,,* .. ***.- . **'.:\;;:
| |
| . '.' ... *.
| |
| .. .. * :.*:.- .*:_; *._.*.-<+*--~'~-_LA:._ . - ***, ,*:.
| |
| -,; ....
| |
| :_., ...
| |
| *,,,, ..-
| |
| L
| |
| | |
| -- - *.< .. - ' . ::'*'
| |
| .:*
| |
| I ,*,,-
| |
| '*-, _ . .*.,*
| |
| ,'..(*.-: _.*-
| |
| . ~: -. . .- : ..
| |
| *.,:*--*.
| |
| '.*:: ,
| |
| *,',
| |
| .
| |
| - - **~
| |
| .. ; - .
| |
| ' . ~
| |
| *..
| |
| ;; ..... ;
| |
| . .. ..
| |
| - .
| |
| .**- ' .
| |
| I by 0.1 sec,. remaining at 99% free area thereafter. This model is I typical of the movement of. panels of this size-and weight under this type 0£' pressurization curve (g.), and assumes that some insulation wilL I . remain attached at the on a +5 psi .. differential: betWeen barrier~
| |
| * Note: that the area will open. up** only * - :. ,- **;" ; -.
| |
| - '"
| |
| I
| |
| '*~ ... '
| |
| I Al.1. other :i.nsiilation!
| |
| . . *. ' . . . . . .
| |
| remain: in place. during the transient*.:
| |
| * This* is in conformance with I . present regulatocy. positidns (lO) ,. and results. in the most realistic, defensible model for insulation . mo.,;,em~nt possible. . . ..* .*.
| |
| . ' . -*:-
| |
| I
| |
| '**'* ,
| |
| . For. M;_llst~~~-. ~*:* :~he;: insul~~i-~n- *~:lqw *.th~'.* ~eut~on.:. s~~eall¢.ng shield'.\$.:
| |
| ' '/***,~:.*.'~' '~ , .... '*'.-
| |
| **
| |
| I .assumed to tear. 11'tilay and blow. through the shield; panels as they rupture*;,
| |
| I . "*:*. .* . : . . . . 2* ,.
| |
| For* Palisades there. is an average* cross-sectional area of 12 ft -for I the convection barrier panels assumed to* tear_ away in the.
| |
| ' . -~~-:~ . ' --* '. -. ~ : . -- .
| |
| analysis~. The
| |
| . _ panels_ are. assumea to* tear away at. three times their asf?umed weight, .
| |
| I I >0;;~2I!IFt:~~~t~~2~f
| |
| -
| |
| .-at 90% free area. thereaf
| |
| :*,.'. ..
| |
| ter'o: .
| |
| :i~ir~:!~~~~~r~s:~£::?t~:~~,,~~~.;t.~*,,.,~.
| |
| ,;:*t*-,:- . . -,
| |
| I I
| |
| I ' ' . .
| |
| The results: of. the* an~lysi~*-show* -
| |
| pressures of about: 100' psia. or above in the upper cavity volumes, and I *: *'
| |
| I I'
| |
| | |
| '***1
| |
| ' .
| |
| pressure differentials of from 220 to 240 psid across the legs adjacent I
| |
| to the purtured discharge leg *. Given the time history of the.pressure I transients in the most realistic conceivable scenario, .it is clear.. that the* cavity pressures are likely to first.collapse insulation nearest I the break against the vessel,.. pulling .it. away from the rest of- the insula- * .
| |
| tion panels. As: the pressure "waves" travel around the' cavity in either* *.. -
| |
| * 1 direction; the insulation behind the."wave front" can* be* envisioned
| |
| :eb~:l::::d0~n::et::d:e::e~L~::.:~m:P::::::~:~b::kt::r~~so~ *** *. *. . > * ~:1 region. of the cavity pressurizes. Insulation can be visualized to become press_ed against the vessel. in the. lower cavity -in a* similar
| |
| . - .
| |
| I:.*
| |
| manner. At the bottom of the reactor vessel, pressures will built to 140 to 160 psia. . The supports holding~the insulation away f~om the vessel .
| |
| hemisphere in this region are' not designed to withstand forces of this magnitude, and this insulation.will also crush up against the-vessel with.
| |
| considerable deformation *. . ~* ...: ,' :.* *.
| |
| . : _':**---
| |
| The present regulatory position on the.movement of insulation during asymmetric pressure loadings is that any assumption of movement must be justified.analytically. Traditionally, insulation has been- left_ in place
| |
| *1~.
| |
| durinr. the transient, as it* is* not possible. to predict. \i.'i.th any certainty the mo~ement of any piece ~f;*i~sU:iatiQn,du~i~g: the. pressure.t:rans:ient. ; A*
| |
| def~n~ible: yet: reatisttc case. assumes. minim~ in~~lation ~~~em~nt:whiie ....
| |
| acknowledging that in an arrangement of insul~tion such as that which .
| |
| exists. in the plants analysed, some panels, will blow away or crush under any conceivable circumstances, The selection. of a.ss.'lJlllptian~* is condi'<:"'
| |
| tioned-*by the nece.ssity of C:alcul~ti:nk
| |
| .* * *' I
| |
| * a:, ~~~~sibla:y~t-~eal~s~i~: as¥JIJDle...- .. *
| |
| * * * * ' 'l '* , '** ' *'
| |
| * tric load~ This* load-will occur wh:en -the* ftee: voli.ri:pe* and flow area are .
| |
| smallest and the ~urface area ~f- the y~ssel that experiencE!s the* trans:;l"- .*
| |
| . .
| |
| . . . . .. . .- . . . . . . .
| |
| ent* is the largest possible. In this analysis, .the nozzle covers on the.
| |
| ruptured leg and the.two adjacent legs are assumed ta be pushed off. In addition, insulation in the lower cavity is .-assumed t~ be crushed up against the vessel hemisphere. Except for Millstone 2,. no.other insula- I tion is assumed to move during the transient althoug~ in all likelihood,
| |
| *.** I
| |
| *I .
| |
| * I
| |
| ,> . . .
| |
| I the-. insulation in the moddle region would also collapse against the vessel. This set. of assumptions is believed to. be the most realistic, I defensible .model for insulation* movement. possible *.
| |
| . *; .. ,*
| |
| , .
| |
| I , The> barrier door in th~* l~~er cavit; frl For.t, Calhoun. wil~*. .pa~tially '. ~
| |
| <.
| |
| *blow,* out. when the* cavity. is. pressurized:*.,._ The s'tudy'. assumed: that:. 5LS9.T .,' i *-.';")*2"<<-::,d,*'.
| |
| *:. 2T , .. ,*:_~~ ::.:*,~ ,,-._.-.*~-.-' : .. * ~-:~ *: .> *. * .. ~--~~-- ...*.. .:\-_;., .;.~_,.,_-~*,~.,,*-,-./---_.. __.* .~:.*.*;::.-~';*:*r.J~*-_.,~,:*::-:~ * ..;~:,~'./1:-'~.;<~~;~-~~:~,;:::::~*~'.::~*;_:_~,*~~~-~>:.-
| |
| I . ', - .. ft*. 0£*.free area becomes** available at~a*.Iinear rate .. 2*:msec a£ter.a Io-**~*<*''*,~*;~::-:. *~:;**;}*
| |
| :-. °' * .:.
| |
| * _. i __ -* _ -~ 4 ~ , . , " ** . - : * ( .:- , ,-- _ ,_ ~ * '" * : , _._.
| |
| psi* pressure, dif f*erential, is_ reached: across'' the, door. :- This\'a;rea:::.-- :::.:. :-:-:.. ;*, :~::*:: :*.'.,,~;; , ,*.-'
| |
| ,. ;.:* ~ ~ ::,.~;*, -~: :_:-.~}~ :.:::t.<-.:i :.~--~ **>-*-:.:r ;;::~;":}.~.::**:, -s~~*:i-;:~~-*-=l~.~-~* .-*:~<~3 ~,'*~-:~':")*:**);*;t'*i':/~?f:/-;\1/ ~"*~:,~. ~-\:~~~::* )~*~\rYK-:*
| |
| *, , , _'. ...
| |
| < -~ '* :~-'~:*.'.:: '* **':* .*. :; ;. *:*.) :: -::. *. '_'* ,.:., * :'- .*.~ '; ~ ' *';;**~*_- :::.:* -- ,*.~._' ~~' * ._." ~ ~* : ,~~ ::-,~ ~:~:" *:,*:*:**:*~:,*<*:~.- =.~ (*_.'.--~*-:*_;,~~~;:.f:\~~~;~t-'.. ~:?:.r-;;;~,.- jj'*** ,. *!::*~--
| |
| 1 I - * :. * >'. **.-:'-: * ** :::,
| |
| . : represents. the' sum* of- the area:. of: several 'steel: panels' in:* the door';;. *. * *** * * ' ...., '. :.'');t>'
| |
| * * *
| |
| * _. * ' * * * * ~ '* ' * * ', * , * * * *,: *: ' . ' : * '* * * ~ I ' * * * * * * ' ; * * ' ",_ * *
| |
| * and* the* delay t_~:m~: was* employed to enhance- the numerical st~bility* .of I
| |
| * the* model. .. *.* .. -: __ ,. ~ .. '
| |
| *- :*. ~ .. ', -*.'
| |
| *<<' ..
| |
| ~o~el (l~_) '. ~~clud~s: a: ~lightl~ er~nt:. :ub--
| |
| I . . A proposed general c.avity
| |
| . _*. _divi~~on_~ o,~. i;~l.U1ll~~(~h;~~~~j:~ ~b~e,~ :~sed~;~I1 thi.~-~:~.~u~!*'.*~~<-:.~ ~y.' of* the.-*_ **
| |
| * diff
| |
| . re_f~renced: studies:' ' '.' ~: . ni'e: geneJ:'.al* cavity model seems to: ha~e*~ *:
| |
| I .. been formulated _fo_t:: Cl-".regui~~~: ~~thog~~~l ~a~ t~ with no: flow*, obs true~,, .
| |
| 'i tio~s; s~,,e ~hanges' in c'Civi.~y:*;c*;~;~.:~*ecfi~~-: a~,,,th~:,leg~ '~ci" ac*.-.;. ~h~nge' I iri:: vess.el. ~~dius *. : Fbr.~ su~h. ~~,~~lik~ly ar~~g~en~:,* -~hi~ '~~bdivision is correct,, as it* ~cco~ts for a:11. maj~or flow obstructions within the I cavity. In the case of the. Calv:ert: Cliffs Units* 1 and. 2. reactor cavity,
| |
| , hbWever, th~se-'subdi~i~:io~~ ~i~\:~~c~~d~ry~,,:'~si:'th~**p~~~~~~nt: of* insuia~-,,
| |
| .; ~ . *,: , '. ~ .. ' ~
| |
| I I
| |
| I I
| |
| I .*This i~ ~* *mod~i'* that. *RELAP . c2n *~se
| |
| . lly;whe~ the small. volume *h~s -~time* depend~nt junct_ion as in this case *.
| |
| only _witJl;': ~reat :*difficulty~-: espe~i~~- .
| |
| .. ,
| |
| I *.In.addition, the effect.of such secondary subdivisions is usually small~
| |
| ,assuming that* mode*l a. *can. b.e created: that is n~~~i~a!iY:' -;tai~i;*~--~~d-~hf~h -* -:-:-*:-*------- --- ---
| |
| I ---:.:* _: ..'.--
| |
| * c *_ :; *;*:** ** .,; * \.. *_-,: -~- ~:
| |
| * 1*
| |
| | |
| I splits the blowdown mass correctly. The subdivision will distribute the I
| |
| same flow among the "split" volumes, leading to similarly split pressure transients. The effect of these subdivisions is included in .
| |
| the -+10%
| |
| I multiplier described above; no study every seen by Ebasco has found a more significant change in results due to any change in the modelling I system described in this report.
| |
| *.I
| |
| *. . . I"'.
| |
| . .
| |
| 4.3.3.5.3 Effect of Neutron Streaming Shields I
| |
| This.section describes. how the presence of Neutron Streaming Shields has been considered in the analysis~ There is.no neutron strealiiing I shield for Palisade~. In the Calvert Cliffs units, the neutron shield*. *--*,.
| |
| and frame are very similar to the shield used in Florida Power and Light's St. Lucie Unit 1 Plant.' An. analysis. of shi:eid movement for that I -. ."
| |
| plant: design under 2 . .
| |
| s~ilar*pressurization( 9 ) showed that for the* cast
| |
| . ---1*.
| |
| of 1. 0 ft holes in the waterbags, the free area of the shield was made available 150 msec after the start of the.accident. This assump-
| |
| .tion was used with a linear opening rate for the Calvert* Cliffs. neutron shield. Ths: same St. Lucie Unit 1 study also showed. that the presence ., .
| |
| of' the> shield had little ef feet: on pressures or forces within the.
| |
| cavity,
| |
| . whiCh is reasonable.to
| |
| . suppose. in the case. as well as both
| |
| *~
| |
| shield designs elevate the shield above the seal elevation and thus do not directly block flow from the cavity.
| |
| '.; ... - I, The Millstone* Unit 2 neutron shield consists of. 16.water tanks, l'-9" high filled to a: 16" height with water~ These tanks are arranged in an annulus around* the*vessel at. the flange elevation and are supported
| |
| .'*I as shown in Figure .4. 3-89. Reference (11) , Figure 4 .1. 2 provided the information relating to rotation angle of the slowest panel of a torn I
| |
| shield face as a function of time, from the instance at which the bottom or top plates begin to. tear.. The tearing is initiated when a 20 psid I is applied across the plate. The notched plate then divides into 4 I
| |
| | |
| I I panels which rotate about their edges. This information was used to I derive the area available for flow through the. shield segments.
| |
| the angle vs. time curve from Reference* (11) was* used to jerive an area First vs. time for the* lower plate *.. This area vs. time curve showed almost I .*.
| |
| *no flow area. .for 20. insec~ opening. rapidly thereafter.
| |
| .
| |
| This curve accounted for- the flow through the.. holes in. the inner ring of the I shield structure, where"the. clamp is. located,. and .
| |
| also for the small .
| |
| lifting motion of* the.outer* shell of the ring caused by rigid rotation' I of the. entire am1ul*us.
| |
| created. in RELAP..
| |
| ~Secondly, a model of the .neutron shield was This model. consisted of 12 appropriately sized I volumes *(ref~ecting the total.volume of the shield) with time depen-dent flow areas.. Limitations on volumes, junctions and especially check valves inherent in RELAP-4, limited the detail with which the upper I plates could. be modelled *.. Hence,. only the upper plates of the shield -.(~
| |
| tanks nearest: the break were simulated to open'. Results of the analyses I showed that. the tanks- rupture in a. "wave like" manner; i. e. , the tanks
| |
| * near the> break open first, followed by* tearing of the others in sequence I . .
| |
| around the RV, synimetrically about the break.
| |
| .
| |
| I The results also show a "mixing" of. the flow into the shield segment permitted by the t~aring. of. the bottom plate, with the-water and air I contained in the shield. segment.
| |
| . the-. shield segment. which in turn ruptures.* the. upper* plate.
| |
| . .
| |
| This results in a pressurization. of
| |
| . .. .
| |
| ._*_:**:, *. .. . I I
| |
| ~
| |
| : *.~*
| |
| .' '. ~ '. ', -
| |
| . . ._.' *- . . **.- . I This "inixing" phenomenon is.considered "slowern than the real phenomenon_
| |
| which will cause the upper p;J..ate. to tear; i.e. , the slug motion of the I water:
| |
| .
| |
| ..- initially contained.. in the .. shield segment under the momentum
| |
| ~*-
| |
| 1
| |
| .. acquired when the pressure wave* liits< the* bottom; plate. pius;. the* , '*
| |
| I d'erived flow. area. vs~.> tfue:: curires! ~mploy~d to be conservative;:: i.e.~' overes.timated the* time required to open. the in the analyses. are. perceived I flow area..
| |
| leg breaks.*
| |
| Results are shown in Figure. 4. 3-90 for both cold leg and hot The figure shows that the area opening for cold legs occurs I in two main steps. First the cavity pressure below the shield is suffi-cient to break the bottom plates of the shield. The pressure then I \ '.
| |
| I *-:*
| |
| .,
| |
| :
| |
| '.-**.
| |
| ~- '
| |
| *.,*.
| |
| .4-. 3'>14'*
| |
| , . . ....
| |
| .. .,,
| |
| *_.-*. *,.: .*.:
| |
| | |
| --1 I
| |
| I remains vi_rtually the same until the shield volume itself is pressurized and the top plate break. I In Fort Calhoun, the neutron. streaming shield consists of sand plugs.
| |
| The.sand plugs were modelled as junctions between.the pipe penetrations and I
| |
| *the pool, volume 32.
| |
| * The junction trip* was set at 2.-64 psid, . representing the force necessary to Qalance the, esti:inated dead weight'. o.f the .plug.
| |
| I belay times were intr~d~ced at each"junction*to simulate that the flow
| |
| .area will not becomP. available until the plug clears the *hole completely,
| |
| -1
| |
| .*and that. this event:. will occur at different times in different *penetrations due to various position~dependent rates of pressurization. At the I
| |
| - 0 break (volumes 7, 8, 9 ) , a. -63 msec delay* was computed* At 120 from the
| |
| * break (volumes 10,, 12), a. 110.msec delay was computed.
| |
| o-*
| |
| A 161 msec*delay I
| |
| " . wcis assumed for th~ penetration 180_
| |
| * from the* 'break (volume 11) * *These
| |
| * time;:J are based on;*a first-order solut+/-.on of the nonlinear 'equation of
| |
| .- . _I motion of the sand. plug using different pressure. gradients.
| |
| I The basic equation of motion can be derived as follows. Let the position dependent mass of the sand plug be given by:* I M(z) = M
| |
| *o pAz* = M(t) (9)
| |
| .I where M is the initial mass of the sand plug, and where pAz is the mass 0
| |
| of the sand pushed up and out into the pool. (p is the density of the sand {95 lb/ft 3 } and A the cross sectional area.) Then, the basic equation I*
| |
| of motion for the piug is given by:
| |
| I Force on the plug = 144- x t.\p(t)A = ,!L (fil.U dz) (10)
| |
| . *. . dt g c dt where t.\p, the pressure differential across the plug, is given in psid.
| |
| I Substituting the expression in equation (9) for M(t), equation (10) becomes:
| |
| I 144~p(t)A = :t dz dt
| |
| , or (11)
| |
| I I
| |
| 4--3. '2-0 I
| |
| | |
| I . ~.----*-* -* .. -~-.........- -* - ~-- *- .: ... - --* - -
| |
| *---
| |
| I (12)
| |
| I Letting z 0
| |
| = M /pA, and making the substitution that:
| |
| 0 '
| |
| I d z dt2 2
| |
| * (13)
| |
| I
| |
| . The---equation of motion of the* plug *b'ecomes :,
| |
| I 144g 2 c (z z
| |
| * z )
| |
| Ap(t) (z < z ) , (14)
| |
| I p 0 - 2 0 with z, and dz/dt initially equal to zero.
| |
| I Asswirl.ng Ap(t) =a + St, t.hia* equation can .be integrated direc.tly and the I solution for z(t) becomes a cubic equation in t,:
| |
| : '~ '
| |
| I z z- z /2 =
| |
| Q
| |
| - 2 '
| |
| (15)
| |
| I I Solving. for z::=z 0
| |
| ,, a cubic equation for t 0 is obtained:
| |
| * ..'
| |
| *2* .. ' 3'
| |
| *at
| |
| * St I -z
| |
| - ...
| |
| 2 c-z-* 0
| |
| + ~
| |
| 0
| |
| >, (16)
| |
| ' 2 I to 2
| |
| .
| |
| +
| |
| 3pz.
| |
| -.,..;o;...*..,,-
| |
| . :.' 144gcl3 _.
| |
| ::I o. '
| |
| . __ -, ....
| |
| *. (17)
| |
| . *- _* . . *_ .-:> :/:~*; ':
| |
| '.*. --
| |
| z '"" 4.0 feet, and a ::I 2.64 psid.. a ranges between approximately 4100 paid/sec 0
| |
| and 282.5 psid/sec. Thus, t ranges between about 0.063 and 0.161 seconds.
| |
| 0 I
| |
| I I 4 ** 3
| |
| * z:. I *
| |
| -*~*--=-=-=--=--=--=-=--=-=*-=--~~~= **-**- *-~-----=====-=- - *- -* *-----* -------.---*-=-**_c**-:c_*-----"--'------------_---_-*_---_-*_--_-_*----_-*-_*-_*"'__;'-.-'----*-*--*-----------*_.--'-
| |
| | |
| ....-,
| |
| .. - .... :*. -
| |
| ..,
| |
| ., ' :~ .
| |
| 5.3.3.5.4. Results of Analysis.
| |
| I The models of the Calvert Cliffs, Millstone* and. Palisades-
| |
| . run* ~n RELAP4-MODEG for: tWo :cas~s <12 >:*.
| |
| " *~" :
| |
| Figur~s 4. 3-82 ,.
| |
| *_*. ' . ,
| |
| g\iillotine break_ (see Tables 4.3.12A and 4.3.i2B)
| |
| : 2. *.- '., .. . ..
| |
| -in **discharge
| |
| | |
| I I
| |
| The set. of "projectea--ai-eas" and lever arms is* given in Table 4.3.25d.
| |
| I I .
| |
| ' ; - ... -
| |
| .. '
| |
| ,* '*, .:i *.... *,
| |
| *
| |
| ..
| |
| ' " ~ :
| |
| - ~~ -_ _J.1
| |
| '.'
| |
| : *
| |
| *t I . - *- '. .--. . . . *-**
| |
| "realistic"and relatively-insensitive to more changes inthe*modelling,
| |
| . . *<. . *.,
| |
| I an additional model of the I
| |
| I I
| |
| I I
| |
| I
| |
| 'I break.ar~ shown
| |
| *I I
| |
| | |
| t,'.
| |
| ... "
| |
| /
| |
| /
| |
| .,
| |
| for FSUM (Figures 4.3.lOlC and 4.3.108) show that for the original model, 4
| |
| the total Fx. was 375 x 10 lbf' and about 350 x 10 lbf for the "CSB" 4
| |
| ~* .
| |
| 4 I
| |
| model.. Peak uplift.is 275 x 10 lbf for the original and 285 x 10 lbf for. the "CSB" model.. l1
| |
| ; ...** ~ .~. '.
| |
| of:: the moments is* very_ difficult; however, it is possibl~: to
| |
| *~
| |
| '"'
| |
| '
| |
| * Compar+/-son
| |
| :.see** a ~y-arls* totai. ~~t*:' of. abo~t:. 375: x io -_ ft~lbf: for:_ the:* original 4
| |
| . mod~l.' ~o~a;ed to. a~~ui: -400~ x: 104 ft.;..lbf: for ~he "CSB!' .model~. ''!he( x:..axis*
| |
| moment is greatly reduced* in the "CSB" model, reduced from the original by*
| |
| about a .. factor of three.. '!hus, . even: the* added consenatism of additional levels affects the.* results by much. less .than the 10%' uncertainty described
| |
| .,:.
| |
| . .
| |
| .-t*.
| |
| *!.:*
| |
| *..,_,.
| |
| I i
| |
| I l \* . *.,*::*
| |
| | |
| I I R~ferences for Section 5.3.3.S I
| |
| I
| |
| *"'
| |
| : 1. E.G.&G. Idaho, Inc., nRELAP4/MOD6 -~A COMPUTER .CODE .FOR TRANSIENT' THERMAL-HYDRAULIC ANALYSIS OF NUCLEAR REACTORS AND RELATED SYSTEMS",
| |
| User's: Manual,. CDAP TR 003,. January 1978 *. *
| |
| *I x. B.G.&E. Drawings: 60-337, 338,. 340, 342:. . . . * .** .*. -
| |
| . . *** . .
| |
| * 61-757; 758, 761,: 766,. 7.71 *(latest re:Visionsl I CE Drawings: . 3836-lO (R3), .B:, D: -11,' '""12* CRO). . '
| |
| : 3. Bechtel Specification for B.G.&.E. Calvert Cliffs Units 1 and 2 I 4.
| |
| 6750-M-339, Rl, dated May 18,* 1970, page 4.
| |
| B.G.&.E. Drawings: SMA1022; 61-759, 762; I s.
| |
| 63-85.3,* 855 (latest revisions)
| |
| Idel'Chi.k,. I. E., "Handbook of Hydraulic. Resistance - Coefficients of Local Resistance and Friction"*, AEC-tr-6630, U.S.D. of: C~, 1966.*
| |
| I .. -"Flow of Fluids Through Valves, Fittings. and Pipes", (17th Edition),
| |
| Crane, Company, New. York 1978. ,, .
| |
| I 6. Louisiana Power and Light Company, Waterfo~d. Unit N~ber j*, FSAR
| |
| .. ' -
| |
| Chapter 6, Section 6.2 .* 1.2.
| |
| I 7. Carolina Power and Light Company,. Shearon Harris Unit 1, PSAR Chapter 5~ Section 5.1.2.3~ 7 *.
| |
| I 8~.. Northeast Utilities, Millstone Nuclear--Power* Station,
| |
| ... letter to NRC dated February 23, 1978 (Doc *. No. 50-336)
| |
| _Neutron. Shielding.. .~ . * ';. :- - ~*. -. **1 __,
| |
| I Florida Power and Light Company, St;. Lucie.Unit 1, iett~~*to.NRC
| |
| *-*._
| |
| (L-76-406,Doc. No. 50-335), dated' November 29, 1976~
| |
| | |
| ==Subject:==
| |
| | |
| I . Neutron. Shielding.
| |
| _ _. .., -.
| |
| ,,_ .~* ... ,.., *' -.:-..***.-~ ......
| |
| . *. 10';.. iet~er to Ebasco from B~G.&E~, dated'August:: 20,
| |
| * i979 ~ont~ining CSB
| |
| .._.,. -* ..';-:** **,--. ~ ~ --.*
| |
| ~".--:~-::*_;;,:* -,_'(:-:-.*
| |
| .. :'. ~::*.. . ,* :*_. .
| |
| *.* --
| |
| '. : _.- ','
| |
| - .
| |
| __ . " '~ .. : '
| |
| . 1 . . . d~aft. guidelines.:*t~r* PWR.~~bcomp~rtment* Analysis._ ** .. , *~*J'C;?';*.::.;:;~> ~;*> '*'.** Y*'<:
| |
| I 11. Neutron: Stremlrl.n:g Shield. 'cEDS) *..:*
| |
| * i:;:":'.~*';>.:;.~7;*'''.;'.:;'./. * ...... *.* * * ..
| |
| ; ~ .- <..* *~
| |
| I . 12. CE letter to B.G *. &E:*. (B.G-.&E.-10577~64) dated January 11, *1~7~ .:'
| |
| : 13. OPPD Drawing Nos. 11405-S-20, 21, -M-79,. 82, -A~l3.
| |
| I
| |
| ,-------- ' '
| |
| *\.
| |
| 'I* .. ,i
| |
| ''
| |
| '..
| |
| ,,.**.4'...
| |
| ':*':
| |
| 3** *~.*~
| |
| . -- . ,*'>:* ****.-. -
| |
| _-
| |
| ..,.i '
| |
| .. _.,,.-,
| |
| '
| |
| .
| |
| *-
| |
| *.
| |
| -
| |
| ,-
| |
| ;.
| |
| '--
| |
| . : .... ,
| |
| ... ,.,.._ *,
| |
| *. '
| |
| .. ,-, _-*' ' '
| |
| | |
| .,_
| |
| I References for Section 5.3.3.5 (Cont'd)
| |
| I 11 14.* Transco Inc., drawings for. CE/OPl'D~Nos. 3742:-1. to .-9.
| |
| ,., '..' .
| |
| ,*, .. -*'.;.,,
| |
| 15~ Consumer. Power Drawings : _ C.;.154 (RW5) , C-15 7 (RW6 h M-3 (RW8) , . M- 7 (RW5)
| |
| .,
| |
| *' .-***,*.
| |
| CE Drawing. E.,..232'.""lll(RW3). . :~*:,,:---
| |
| / '
| |
| _*,_'.-
| |
| . '
| |
| .t
| |
| _., ..f/
| |
| *- ~.. *.*.
| |
| I
| |
| ' .. ' ~~*:, .'
| |
| - -__ ;~~:o**--=-** "~-~-~- _* .
| |
| ...
| |
| .. *'j1 .... -
| |
| *,*..:_ *.
| |
| ~ ,. '
| |
| .** ',, ."
| |
| . . . '. ~. .. . <: *. . .':'*. :-. , ~-
| |
| -/** . . -* .
| |
| . ._*_
| |
| *I
| |
| ..... I
| |
| | |
| *~==:-=-=-~===-:::===:=::::::==---~---* ~-~-**--------CC---.-~------------------~-------*** - -* *-- -*-** -* *, c*-*- .. ---- ,*~--=*- =--=**-=*****=--=---=*-
| |
| , 1 ,,;
| |
| - )
| |
| I~l ** ;
| |
| Table 4.3-lla t *__ !
| |
| OPPD* - Ft Calhoun Unit l .
| |
| Mass/Energy Release Rates t)~
| |
| 905 Square Inch Discharge Leg Guillotine Break at: Reactor.Vessel.Nozzle (Flow. From Pump Side)
| |
| ,,~ .. *. ,_
| |
| . . . , *:.*. . .,-
| |
| *
| |
| * Tiriie .. . Flow Rate;. .. Enthalpy>._. * - * .... *.* Energy Rate
| |
| * (Seconds) *(lb/sec). *- *<:(Btu/lb) . -~ . (Btu/sec)
| |
| *1*~-.
| |
| '. . '' *~* *, . '; . .... *.' :* .. .:!:* *. : ..
| |
| 0.00000 o.o. . 544. 70 o.
| |
| t-* .00100
| |
| * 00200 2284.0
| |
| . 4446.0 544.60 544.30 1243866.
| |
| 2419958 *
| |
| .00300 6403.0 543.90 3482592.
| |
| 1: .00400
| |
| .00500 7825.0
| |
| . 8865.0 543.20 542.50 4250540.
| |
| ' . 4809203
| |
| * I. .00600 9523.0 . .541. 70 *. 5158609 *.
| |
| '._, ,.*
| |
| *:*
| |
| * 00100*
| |
| . . .°cJ0800 .
| |
| ** 9101*.o r, :;.. . .. :.- ***:** _;--
| |
| * 541.00*
| |
| **,* 540~40;
| |
| . 5248241 *
| |
| . *.* ..* 5214320 *.
| |
| . . . :'...- .' . ...
| |
| *~
| |
| ,.
| |
| 9649.0'' :*.
| |
| I
| |
| ' .
| |
| .
| |
| * 00900 *.,_. 9411~0 . 539*.90 5116632...
| |
| * 01000 9464.0 539.60 5106774 *
| |
| .01200 11190.0 .. 539.60 6038124 *
| |
| ,,_ ..01400
| |
| .* 01600 13050.0*
| |
| 14920.0-..
| |
| 539;.60
| |
| .* 539-.60.*.
| |
| 7041780.
| |
| 8050832 *. . . ..: . "_.' .~ . . . ... '
| |
| ** .. i61so~a< : -: .*
| |
| *.,'.
| |
| .* '* '*
| |
| '*.:
| |
| . . * .. 01800* . . . .~,. '' .,
| |
| .9054488;, .. .. *' *.
| |
| ,*, ,*'.:,.'
| |
| }_ .:,;,.: ,539 ~* 60' .;. :*:,_:.
| |
| *.*:* **'-<,.*.*,* * * *'
| |
| * I
| |
| * *~ 18640. o:* *_ * **.
| |
| ".",
| |
| .
| |
| * 02000 . ..
| |
| 10058144 .
| |
| *
| |
| -.02200* *.* 2o5i0.o * .* 539.60 .. 11067196 *.
| |
| ~02400 21430*.o. * .. 539.60 11563628.
| |
| :
| |
| :*.02600:.
| |
| _, ..
| |
| * .. :_,:>~_J::?~:::o28oo'-*
| |
| . *_ -~~*.>\~03000** *. ... -..,* -
| |
| *,. ~*
| |
| ..*.. :>- :* 03200 *.*
| |
| 1:: - ~03400
| |
| .03600 .. 21420.0
| |
| .. ' .. ~. . .
| |
| . 539.80
| |
| * 11562516.
| |
| (f .03800 21420.0 . 539.80* 115625160
| |
| :,,',)
| |
| . . .. . . .: .
| |
| ..- . **. **.
| |
| :-
| |
| *.**
| |
| ,**
| |
| *-*
| |
| <**
| |
| .
| |
| *.'*. ,_*
| |
| *, .' - ~
| |
| . '.
| |
| .
| |
| I .
| |
| ** ** >:. ** * *:.~
| |
| * - - " - - - .- - - * - - . -..C..-- . .::.~.-*- .__,_***-'-*-~-----.--
| |
| .... '*. : * '
| |
| ._<,:>"~,:*::A:,~ 3* ..* .1--7 .*.
| |
| ..,.---
| |
| .* .. _*: ",**,
| |
| .****. **.
| |
| --
| |
| | |
| *~---,-.~*-"'---.,.,-...,-----'~--* .. *. *.: ..,.... ;
| |
| *. :,,* *:': .: :*,
| |
| ' ..~ '' .. . ..~ .' ' . .. . ' ....
| |
| ; .
| |
| Table.4.3-lla. (cont.)
| |
| OPPD - Ft Calhoun Unit 1
| |
| ~.' -* Mass/Energy Release Rates
| |
| .905.Square Inch-Discharge Leg Guillotine at~ Reactor: Vessel. Nozzle-.*
| |
| * \* '.(F~<?W From Pump Side) t * * '
| |
| * I*: .* 04200 *. 21430~0.. ' *.11570057.
| |
| . '.04400 * --*- * * .-_ :21440 ~ o* . : 53~i-~90 .* .. 11575456' *
| |
| *.. :
| |
| **.04600** . .21440.0: . .
| |
| 11575456 *...
| |
| **11575456~
| |
| ( .
| |
| __ _!:
| |
| ll585145 *.
| |
| . 1!585145~
| |
| : t. ..
| |
| f *.
| |
| : r. ~
| |
| i L_.:
| |
| | |
| *... *;* ...
| |
| I.
| |
| In.
| |
| ***
| |
| "~: Table 4. 3-lla (cont*.)*
| |
| (t OPPD - Ft Calhoun Unit 1
| |
| * Mass/Energy Release Rates 905 Square Inch: Discharge.Leg* Guillotine Break t~ ,. at: Reactor: Vessel. Nozzle
| |
| .... _,': ..
| |
| \ . .(Flow. From Pump S.ide) * *
| |
| ,,~
| |
| I*.
| |
| f] .~.
| |
| 1** . *.22000
| |
| .*. '.24000. '
| |
| 20560.0.
| |
| 20450.0 ..
| |
| 540.50 540.60
| |
| *- :--11112680 *..
| |
| 11055270.
| |
| ...* *r
| |
| * 26000. '-20350.0 . 540.70' '11003245.
| |
| ;.-. .
| |
| * 28000. 20240.0 540. 70' 10943768 *
| |
| .. '*30000 .. 10897120~:
| |
| 1: .. :. ' 10853856.
| |
| (,;.
| |
| *.* 108i2591. '
| |
| ,19800.0 10713780.
| |
| I
| |
| ,
| |
| .42000. . .' "19750.0. .' . 10688700
| |
| * 10663610'*.
| |
| __
| |
| ,-
| |
| ,,
| |
| I~
| |
| 1~
| |
| f
| |
| .. *.95000*
| |
| I*
| |
| *I : .
| |
| '/
| |
| <'**:.:
| |
| 1"" ~. ~~' - ~.
| |
| | |
| ----~-----------.!...;---:-*------* -.--*..,.----:. *---------~-*-:-.~:.. __
| |
| .,,(
| |
| . ____._*_* :2,_.;.~-~-:._- .... ~*:.._*-**:~-~-----:-
| |
| .
| |
| ..
| |
| Table 4.3-lla (cont.)
| |
| \ ___ :
| |
| OPPD - Ft Calhoun Unit 1 Mass/Energy Release Rates.
| |
| 1~
| |
| 905. Square Inch Discharge Leg Guillotine Break
| |
| ,.. - -
| |
| ,' .:
| |
| .* 1.':,*
| |
| at*Reactor Vessel.Nozzle
| |
| * (Flow From: Pump Side)
| |
| *"o.
| |
| . Fr~w--iat:e>
| |
| (lb/sec)
| |
| .;'
| |
| . Enthalpy
| |
| * * ...... *(Btu/lb)
| |
| ' .
| |
| -;*. . ,
| |
| *. Energy Rate~
| |
| . (Btu/sec)
| |
| *,
| |
| :<11 ':,;"Ir 1.00000 1.10000 20520.0 20910.0 544.60 545.40 11175192.
| |
| 11404314. ,. .. _., ...
| |
| .1.20000 21340.0 546~30** 11658042
| |
| * 1.30000 21810.0 547.10 11932251 *. .. ' "'- .
| |
| . I t.40000 ..* 24600*.o *
| |
| * 548.30 13488180. .** ' ( .,
| |
| ' . ' - . . . ~ .
| |
| . I.50000' <24750.0 : . .549*.20 .*.13592700
| |
| * 1.60000 *. 248GO.O . 550.10; . ' 136 75486 *
| |
| - *.*
| |
| ..... . 24990*0> *-.5~1.00' .13769490. ' *,-" '
| |
| . .
| |
| \
| |
| *..: '. 1 *.70000 ' '* ' . - .:_*.: .*' *-**, .*.
| |
| '-1~80000 .. * '::25140~0: .. :.*_ .
| |
| :~:~a: e *.~* ~ ** ;p,i';
| |
| * .* 551.90,
| |
| * * : - ----*--:-*..:.::__ - ... ... *. ... .. '
| |
| . l.90000 *. 25350.0 552~80
| |
| . : ,.:'"
| |
| ,. 2.00000 25500.0. 553.70 14119350.
| |
| ) ~~50000 26140.0 557.90 14583506.
| |
| c
| |
| '3.00000 I...: .
| |
| ...
| |
| .. '*
| |
| rI l_
| |
| r*
| |
| I I
| |
| I
| |
| '--*
| |
| r I
| |
| i~.... -
| |
| I
| |
| ......
| |
| '''. .,._.*
| |
| ..__ *.." -,,*
| |
| l
| |
| ,-.,
| |
| ' '
| |
| : ' ...
| |
| '
| |
| L
| |
| *-
| |
| ' *1:*
| |
| | |
| l~
| |
| Iii ' *'" ' - '~ ~
| |
| *.. :::*. .*
| |
| .**. .~..
| |
| ****:*'*
| |
| L_J I:
| |
| -1~
| |
| : l. ... ~
| |
| .
| |
| *'. *,
| |
| Table* 4*3-llb
| |
| ,;:_
| |
| t:;._.....
| |
| OPPD - Ft Calhoun Unit 1 Mass/Energy Rel~ase Rates 1~ 905 Square Inch.Discharge.Leg Guillotine Break*
| |
| * *... at*. Reactor. Vessel Nozzle * .;_
| |
| '**-~
| |
| 1-L-*
| |
| t~ ~
| |
| o-.. ;._:. -*
| |
| 0~00000 I ..
| |
| t .* 00100
| |
| .00200
| |
| : .* 00300_
| |
| 2184.0 3765.0 5138.0 544.10 543.00 542-.20 ..
| |
| 1188314.
| |
| 2044395 *..
| |
| 2785824.
| |
| I: ' .00400
| |
| : ~00500.,,
| |
| *.,
| |
| 6769*0
| |
| . '.,8766~0:**
| |
| 542.10
| |
| *. ,542*.40**.
| |
| 3669475 *..
| |
| 4754678* .
| |
| . . .
| |
| *-~
| |
| ;* "".":**..
| |
| .... , : .:542.". 60: 5816672.~--
| |
| :- . '-~00600
| |
| ~ *.
| |
| , . **.*.*_ 542~.40' 6633552 *...
| |
| ,,~ . ;':* :;*~~?:':;c;:'~42\'~0~.::), .*. i *': i2i9.440 '~; '
| |
| '**,.:',
| |
| * :
| |
| * 541.'~ oo,.: ... ::_._, *<~; *7641976 .::
| |
| . .00900
| |
| . . .
| |
| :15010.0 541.40* 81.58898.
| |
| .01000 I_: ...* 01200.. . '17320'.0'
| |
| ',-'
| |
| ..*.. ".I*,
| |
| . 541.20 9373584 *.
| |
| 10702958.
| |
| .'"
| |
| .* Ol400;. 19780'.0, i1~
| |
| *~ . . '. ''54r.-20
| |
| * * :54i ..7o *
| |
| : 15537852 *. *
| |
| '_17632335'~ .
| |
| ,,~
| |
| ,, __ *'*
| |
| t '' ~03600 ';. ,,**':''39780~0 ' 543*~10.
| |
| .... -:-*
| |
| '21604518 ..
| |
| llJ *03800 *. 40150.0 543*.10 . 21805465 *
| |
| .< ;*
| |
| JJ : ~~
| |
| *'.'*.
| |
| -* ....-
| |
| -'.:**:.*:.
| |
| . ... ::
| |
| '*
| |
| "
| |
| " . *., ,..
| |
| ~
| |
| ..
| |
| :.-1
| |
| .. *.:;I ll
| |
| '
| |
| . - - ~ '.,,* '
| |
| " { .i:_ .* (.:"*". '
| |
| .. ,_,**.*. <. t.~. ~
| |
| .- . - . ::~ r; .
| |
| ' *,
| |
| *---*--- . . . . .- - - - **M _ , , , : . - :* *
| |
| * __ .... - ....-....
| |
| ,... ~ ... ., ... ,.~ ,~
| |
| | |
| - -*-----*------~------*-----*- * * * -------*--*---* ----**-*--*-******-- ***--*-**---*--- *-*-***-----* .--*--*---*-- ****-- -**** - . *---*-----*-*-**~ -
| |
| ,,
| |
| table 4.3-llb (cont.)
| |
| *t*. __ .*
| |
| OPPO - Ft Calhoun Unit 1 Mass/Energy Release Rates I:*
| |
| 905 Square Inch Discharge Leg Guillotine Break at 'Reactor Vessel Nozzle (Flow From RV Side)
| |
| I rI I :
| |
| w
| |
| .
| |
| Time Flow Rate Enthalpy Energy Rate I'
| |
| (Btu/lb) (Btu/sec)
| |
| (Seconds)
| |
| .04000 (lb/sec) 40400.0
| |
| - - --*- ---*- -*-- -- -
| |
| 543.10 21941240. I
| |
| .04200 40550.0 543*.20 22028760.
| |
| . r-
| |
| .04400
| |
| * 04600
| |
| .04800 40600.0 40570.0 40450.0 543.10 543.10 543.00 22049860
| |
| * 22033587.
| |
| 21964350. 'I/
| |
| *05000 40280~0 543.00 21872040 *
| |
| ,_
| |
| .()5500
| |
| .06000
| |
| .06500
| |
| *07000 39740.0 39250.0.
| |
| 38830.0*
| |
| 38220.0
| |
| *-
| |
| 542.80 542.60 542.50 542.30 21570872.
| |
| 21297050.
| |
| 21065275.
| |
| 20726706 *
| |
| ,,
| |
| .07500 37070.0 542.iO . 20095647.
| |
| .08000
| |
| * 08500 35350.0 33340.0 541.80 541.30 19152630.
| |
| 18046942
| |
| * I r~
| |
| l .
| |
| .09000. 31380.0 29890.0 541.00 540.70 16976580.
| |
| 16161523
| |
| * 11
| |
| * 09500
| |
| * 10000 . 29310.0 540 *.70 15847917 *
| |
| .11000 31010.0* 541.00 16776410. ***
| |
| *12000 33060.0 541.40 17898684 * *a;,
| |
| * 13000 33490.0 541.50 18134835 * ....*
| |
| *14000 33250.0 541.SO 18004875 *
| |
| * 15000
| |
| * 16000 33750.0 34090.0 541.60.
| |
| 541.60 18279000
| |
| * 18463144
| |
| * t
| |
| ,_
| |
| * 17000
| |
| * 18000 33070.0
| |
| .31860.0 541.40 541.20
| |
| . 17904098 *.
| |
| 17242632
| |
| * I
| |
| .19000 30860,0 541.00 16695260.
| |
| I
| |
| ;*--.
| |
| ,-_.
| |
| I.
| |
| | |
| ..:.:**-~-~-.'--~*-~- ~--.,:: __.:.:..._ __...;....~-*-*'__________ ..;'._:~:~:..~ ~-:~~~--*-**-::_ ,.:___._::.-.. '~*---.:-**. .: ~-._ -~ - _. ..
| |
| ..:.::~_: **-:.;,*-:~:-_-~~: ~-'*-*-*- ;.:._.~ .........~.--'-"-.*.
| |
| . ' - .. . ' .. - ,: **. . . " -- ':-:* .-, . .~ '* .
| |
| f.* --:.: ... < .' - :: .. - ' *:. .. . : . ~- -..
| |
| "
| |
| **.-.
| |
| ''*.**.
| |
| -**-' . **.. ,,
| |
| ....
| |
| ,,._
| |
| I; Table 4.3-llb (cont.)
| |
| 11 ~ .-.:.....
| |
| OPPD -.Ft Calhoun Unit 1 Mass/Energy Release Rates 905 Square Inch Discharge Leg Guillotine Break I * * .* - at. Reactor Vessel. Nozzle.
| |
| (Flow .Fr~ RV Side).
| |
| ':* .*
| |
| .-_ :..,* *- '--.* ..*
| |
| ' ..:
| |
| *_,.
| |
| I*~
| |
| - ': -*
| |
| .' .,;-.: ___ *. *-. *,,,
| |
| .. :._*_ ":..(-'...:--' : .._ ~ _, '
| |
| **;r, . : *
| |
| >:ti~;;~::,~:.;.;i50)l,&i~;n.;~** .*.
| |
| ,_. . /'.Time<*.* -. , Energy: Rate: -_.-
| |
| *** <; ; ., : <(s-econcis )-
| |
| *.r. _. ':...<**;* ', *r
| |
| * 20000.:
| |
| .22000
| |
| . . ..:*' :'541: 00 541.50
| |
| .. :..:>;-"(Btu/sec)*.**.""*-
| |
| **,*;:-.,:,,::* .-. _,_ .
| |
| >-::~._.~..-:*:>J_. ~=,-;_~*;">'- :;,.*
| |
| . ...*'.' . i6s810 a) *
| |
| '17972385.
| |
| .- "". -
| |
| .''<;
| |
| ...
| |
| 1
| |
| ,~,,.
| |
| ,.
| |
| " *.* 24000 33140.0 541.40 17941996 *.
| |
| \,.~,,_
| |
| .26000 32290.0 541.30* *17478577~
| |
| .28000 31250.0 . 541.10 *.-16909375 *.
| |
| . . . . 31810.0: .* 541.20. 17215572';. .
| |
| *. 30000 .
| |
| . .. .** . -
| |
| I~
| |
| ~
| |
| .. *.:*~32000. **. 32670.0 ,.* 541.40* . -. . .
| |
| : 17687538.
| |
| '..34000: *-.. 32290.0 . 541.30 .. . 17478577-.,
| |
| .. */r}:36ooo!*-* *.-. * -***
| |
| * 1 _;:314:30~0/*** . - " . /' .54l~.10 *'.:>i7006773'~ .
| |
| I~:
| |
| '*.*.,.:!
| |
| .. ::'.,_:)_'
| |
| ;,,~:.3aooo :*31600*~0 ~~17101920'. ...
| |
| 1- *40000 .
| |
| .* 42000
| |
| ..*440()0 31800.0 31900.0 "
| |
| 31570~0-,.
| |
| 541.20 541.20
| |
| .541.20 17231808.
| |
| 17264280 ..
| |
| 17085684.
| |
| 1-~ ., . .46000' ~" 3i44o*.a , , ' 541:.20 .. *.-.17015328 *
| |
| .--- -~ .
| |
| . *\1:;'.::~~~if!E~~':*;,* ,;. -.-1t*k!~2'.F* ';:>ctit~jtf~ff L
| |
| . *- ,**:- *.;..:
| |
| --- . ;~:: 171S6040.
| |
| ;./*.
| |
| *.:: '..._'~*'17134392 *.
| |
| 1~*
| |
| '.* .::~ '" *- ,,.
| |
| ':: 16849854 *.
| |
| .
| |
| . , 31030~0 . ; .
| |
| . . .
| |
| *- ... : ,,:**541.10. 16790333 *.
| |
| .
| |
| * 60000
| |
| *1***-- ',* *-.-
| |
| *~ ; ~ ~: -~ 65Q_QQ.
| |
| ..-::;\-:~.~-,:-~--:
| |
| .
| |
| ~-:.:**- :.*-:*~~\*
| |
| ',. JQ9JQ
| |
| * Q* ~- ,
| |
| '\:* ' - :, .,, ' ; ,*\,,*~*-
| |
| ' 541*.10
| |
| ,,,**.*'':*;'..
| |
| . . .
| |
| -::*.. _*. *16*7J6"2ZJ e.
| |
| ;: ~t:.';*_.. _,_>:_,,-:*'*:f'.:*~\'.!::::*'.:****'."\'.~-'i '. "'~
| |
| -... <... ~;{;'/*,_. :~r~:V:tfl~:::::¥f~?~9:;*:~;):,;L;::::'ts*\~.:,;;:::{~~3~~~~. :,_{~~:;':-,;~:~;:A~(~\"*:;,~:~*~.:~*;~~ ~:;}f;s,r:;i~~,*,-~~:Xi:}:.~~?.~9.
| |
| 304
| |
| ****-~-
| |
| 0 . ;,. *-~~--.*
| |
| '1-.,
| |
| . I ~
| |
| ,' . ' .., ~{- 75000 " ., . 30520 0 < _, :, '""' '541 10< . ... , ' . ... ' ' 16514372' ...*
| |
| . .*. . / :,*5)ij*~ '!SOOoO *< :;< '\i~:~o~()[o . . . < ; } '.ii1~f.'1:1a* <* * * ~ ;;;:'i/ii~i7196*~ . ..
| |
| ~8sooo. ~:\ 30240 *. 0
| |
| -. -~
| |
| .. .... ._ - **.:\:o*s41.10. <_, .. . . .. 16362864. _*-*.**.**-*- ''*'
| |
| ... : 1 , * ' - - * - :' . * * .. : . '-'. *: : ' : '
| |
| * _.. ' : * - * - ...:- * '_::*: '. *.
| |
| - . . . .90000 . . : .* ,:301sO.O" . . . ' .. 54C.1o:: *....*_. 16314165.
| |
| sj . ~95000 . _* 30000.0. . 541.10 . 16233000 *
| |
| ., ._;
| |
| .
| |
| -,.
| |
| -.
| |
| *.
| |
| *
| |
| ..
| |
| ' , : * .o:* **.:*.* *-**
| |
| **r -. - .* *._ -; .
| |
| ...
| |
| ~-. ~--**.:
| |
| "*'*
| |
| . '~.
| |
| *:;.:
| |
| .'":
| |
| . '"-*.1; .*
| |
| ;.:_
| |
| _:*-, :
| |
| ,_.'
| |
| _*.-
| |
| : t. . ......... --**-----*--- ' - _,. *-*- .. **- ... ,. __ ..... ---
| |
| ): .
| |
| ,
| |
| . -~--
| |
| ' '. ,,,.
| |
| -~--* .. _,._**::':/-;::?
| |
| .
| |
| x?*~:T,*4~* ~; 3:~1J\~*<
| |
| --- ---* ---**-*- *-*-- -*-**- -*-** - .,... *------~:
| |
| ,1,':< ...~*:~1.
| |
| ...... ..
| |
| -:
| |
| ._
| |
| | |
| *--~-----*-.-~---***-* . *--- ~ . -*---*---* . *-- -- _____ .._,_ ....c.--------------------------C*:. -----*~---*-~- ~-'-:_ _____:___ _____,,_. -~''* -*-* --~*--~.: ....
| |
| I ._
| |
| . I Table 4.3-llb (cont.)
| |
| I
| |
| '
| |
| OPPD - Ft Calhoun Unit 1 L .1 Mass/Energy Release Rates 905 Square Inch Discharge Leg Guillotine Break at Reactor Vessel Nozzle * ,j
| |
| . (Flow From. RV Side)
| |
| <:**:_. ,~
| |
| Time,
| |
| * (Seconds)
| |
| Flow. Rate.
| |
| (lb/sec)-*
| |
| Enthalpy*
| |
| . * (Btu/lb)
| |
| -~--- .*_ -*-- ____ : __
| |
| * _., Energy Rate
| |
| * **. (Btu/sec). . ***;*;
| |
| 1.00000. '29830.0 541.10 16141013.
| |
| 1.10000*
| |
| 1.20000 29460.0 29180~0 541.10
| |
| . 541.10.
| |
| 15940806.
| |
| . 15789298
| |
| * I\
| |
| 1.30000 28960.0 541.10 15670256. .;>*~'- _*
| |
| . -.. -\'
| |
| 1.40000 28670.0 541.20 15516204 *.
| |
| l.50000 . : .28510.0 541~30 15432463 .:- .-. ,_.:
| |
| r- .15343276 .*.
| |
| l;.60000 28340.Q. 541.40 1.,70000_ ;28130.0 541.L,.O
| |
| ... 15229582-., *
| |
| ._
| |
| ,.;, ..
| |
| .- ;. --,_
| |
| -- .*c 1.80000 27880.0 :*541.60' --**. 15099808 *.
| |
| '. *-*\.' ' -** ----~.,.__ .. :-:--_-:-
| |
| l.90000 27640~0 541 * .70. -14972588 *.
| |
| 2~00000 27510.0 541*.80 14904918.
| |
| 2'.50000
| |
| ' -
| |
| ..
| |
| 3.00000 .
| |
| --..
| |
| 26630.0
| |
| ..
| |
| 26180.0:
| |
| 542.80 544.10 14454764 *.
| |
| . 14244538.
| |
| l
| |
| ~."; *.' * (';,{'1~ [.tj+'.;*/'t ~!,(~
| |
| ! ..
| |
| I '
| |
| L~
| |
| r-. *:.
| |
| I '
| |
| IL~'
| |
| . ; -~, ; .:
| |
| r.
| |
| ' :: -** *''
| |
| .*11?-
| |
| . .,:
| |
| -.*';-**,-..
| |
| ~' '.-
| |
| .:~~-~-- -
| |
| T'I,
| |
| -
| |
| ***., .- .
| |
| .. .
| |
| . .
| |
| ~ ..
| |
| .
| |
| **<r
| |
| '
| |
| t('*
| |
| _ ,.--
| |
| ...,
| |
| . --..*
| |
| .*
| |
| -
| |
| _., __
| |
| | |
| ____ .... '-------* ------***. -*-- -*--------------* ----- ----*---- ... -* .... - -- - . - *---~~ .-~-.-:.._-_:;_ __ ***--* _:-_ :~~--.- -*-
| |
| t.
| |
| .,; °'-C:..J Baltimore Gas & Electric Table 4.3-21a Calvert Cliffs Units l and 2
| |
| 'I.:- ' Volumes i\ *-* Volume Volume (ft 3)
| |
| Height (ft)
| |
| Elevation (ft)
| |
| I; Number*
| |
| : l. 179.98 13.1671 30.833 30.833
| |
| -*-
| |
| -t* .... _:
| |
| .... - ---
| |
| 2 4
| |
| 3 122.63 122.63 130.65 13*1671 13.1671 13.1671 30.833 30.833 I: 5 6
| |
| 130.65 147.02 13.1671 14.6671 30.833 29.333 29.333
| |
| '1*:
| |
| *~-. 7 147.02 14.6671
| |
| ' - ;
| |
| 8 130.65 13.1671 30.833 9 130.65 13.1671 30.833 10 122.63 13.1671 30.833 '
| |
| !~ ._
| |
| ,,: lL 12 122.63*
| |
| . 179.98 30.277 13.1671 13.1671 13.3331 30.833 30.833 17.5 13 13.3331 17.5 1:-. 14 15 174.94 52.792 13.3331 17.5 16 170.85 13.3331 17.5
| |
| !I_: 17 52.792- 13.3331 17.5,.
| |
| ,\_. 18' 19 169.98 265.09 13.3331 9.4171 ..
| |
| 17.5 8.083 20 265.89 9.4171 8.083 1-~' 21 22 175.08 262.86 9.4171 9.4171 8.083 8.083
| |
| _.,)'. ..
| |
| 23 175.08 9.4171 8.083 24 262.20 9 .. 4171 . 8.083 7.667 33.5
| |
| *~*
| |
| 25 87 .26' 26 171.52 6.5 34.083
| |
| *1~*
| |
| 1-~
| |
| t: -- .. ----------------- ------**------*---***---**** **-----****-~------*--
| |
| ~~~~~=~===-~- *=*-
| |
| --- :::c** - - - - - - - - - - * * ---------------. ***--*- .........- --.--. *--- --* - **- ----------- -- --- ----* - *
| |
| | |
| ..
| |
| Calvert Cliffs Units 1 and 2 Volumes
| |
| \..* : Height.
| |
| Volume* . Volume
| |
| . Number (ft3) (ft) 27>> '.:: *6.5L
| |
| ~ :'is:>*- . . *-*
| |
| I 29*'*' .171.52 6~5 . - ;' -34.os:i.
| |
| 30 129.62 6.5. 34.083
| |
| : 31. '1594.0 4.292 44.0
| |
| : 32. 51350.0. '74.0. 10.0.
| |
| *;--. *._* , *'1*"', *.
| |
| 33-* 51350.0 74.0 10.0.
| |
| ,_ .-,*
| |
| .. '.*
| |
| .*_*34.:*. : . *... ** .. "12380.0~ ' '35~0~. '34.0.***
| |
| *, *':,:/.'<. :*.
| |
| ***-~--. ,*_ :-:;*.**
| |
| ** t.
| |
| :.**.-,:::*-.
| |
| 12400~0::* ' 20.709* _48:~292' *. >_:_*_,
| |
| *(.* \ -':;-, 36 . ~.**.*. 16560.0*. : 39.5'-.. ' 29.S:* ' *.'
| |
| .... **- . ::.*
| |
| ~--** ,;**~--~\"~~~--*>
| |
| . r-.; . *~ _. C*
| |
| .*.
| |
| -- "<:.'< 3;.F>''.* ...... .
| |
| ... ,. __ , .: '
| |
| ********** 14s~O; '* . ** -:,: .* 'io.ci:> *:.:,)*:~,'..*),Yi~
| |
| .' .:-.-.,>. ":,*'. *: .'. :,._;.:'....:,?*: . ~,: *:
| |
| *-
| |
| *, __ .-** .: . . .. '.~:. ~ :".::-~- . ,:
| |
| :._ __.
| |
| I
| |
| . '- ; .. . ,*,***
| |
| . *-**, '. . ~ *~_. *,;:'; .
| |
| _,,., . -**:: '*'. '.'
| |
| :* . *.. ~ ' :.- . -
| |
| '--*-
| |
| ,r~* ..
| |
| --* ..
| |
| *o* .**
| |
| ;._. Note:*' volumes are . .1..u.1..1..i. ... *~*Y at.14.7'psia, 120 F, 0.5% RH,
| |
| . *:
| |
| except volumes 24 *which. are at. 14.7 psia, SS0°F ~
| |
| 0.01% RH.
| |
| :t
| |
| -~. ... ..
| |
| -.._ j
| |
| .. . ,*':_,
| |
| ,:. . *
| |
| .j._'
| |
| . . ' '. :11_*
| |
| . ,,:
| |
| -'. *. ....~ .: :: .. .. *_
| |
| -__.:.
| |
| ;,-*
| |
| *'' *:- ..
| |
| . .~- ' ;
| |
| . .... -.
| |
| "
| |
| | |
| . *.----***.::...'-. * * - .:-~-~-:-------*- -------* >-----*- *--:- __ ._;_ -..... ~; .: ...: _:.:~- .. **::~-*:_:__:'--: -~.. -_;-~_:=.L ~;::~ ..
| |
| I ., .: .,,.
| |
| L~:
| |
| ~
| |
| . ~' .
| |
| I. .
| |
| '
| |
| ... __. ;
| |
| Baltimore Gas & Electric Table 4.3-2lb
| |
| *** L..
| |
| Calvert Cliffs Units 1 and 2 Junctions f: I c_.* .* Inertia Coeff .
| |
| Junction- *From.
| |
| * To* *Area. Elevation* . L/ A 1*
| |
| Irreversible Loss Coeff"
| |
| ..***
| |
| * Number . Vol. Vol. . (ft2) .* (ft). . : (ft'.91) ... * * (Forward Flow) _(Reverse, Flow) *
| |
| . *"'~* ~ .: ' -- ' ... ; : . - ':"
| |
| .
| |
| , . . . . '".
| |
| . -. *i::>' **<.~!~'/:~<~::-~~~~* it~::~ ~*-
| |
| '*...' . .*. 30:. 833. : '. '* .():.;04099; *. * *o,."o4o99-.
| |
| * 0,.1934 < ..
| |
| . ; :~:
| |
| T*: ..
| |
| .:. 30*.333 0.1934* . '0~3.2063*
| |
| .......
| |
| <, 0'.32063'.*
| |
| .
| |
| . * ~ 3* . .<-. :*~7 .069* : ,
| |
| J'. 4 0.06277 0~06277
| |
| \..:
| |
| 4- 4 5 29'.978 30.833 0.1934 0.06037 0.06037' 5 5 6 27.069 30.833 0.1934 0.08218 0.06750 L.:
| |
| .,.\. 6 7.
| |
| 7 8.
| |
| .6 .
| |
| 7 11.318 27.069 29.333 30.833 0~1934 0.1934*
| |
| 0.67558 0.06341 0.67558 0.06341
| |
| '
| |
| ' .
| |
| '..;.,/:
| |
| . 8. 9: .8 . 29*978 . 30.833. 0.1934 0.03597 0.03597 1- 9 ..*101 9 . 27~069 .* 30.83j 0.1934 . 0~04699 . 0.06167
| |
| ,.
| |
| ,***:.
| |
| 10 .. 11' 10 . 18.326: 30.833 0.1934 0.32063 0.32063..
| |
| . ' :*'. . *.r
| |
| *: ll: .* *12 11 ... * *2.r.069 : .. * * *.._30-.a33}_:: ... .***0';.1934 . . 0~04163: 0 *.04163;*: . . :'(.
| |
| *. . . *. '. ~"
| |
| <15..719'
| |
| *"
| |
| 12 ; > **i .*.**-
| |
| . . :.* .:..:12:*__ .:
| |
| *.30.833
| |
| * o*.1934. *0.09442:- _0.09442' 13 .. l 31 .. *. 15.719 44.0- . 0.43447 1.53688 *. 1.02602:
| |
| 14 2 31 15**.119 44.0 0.43447 l.53688 l.02602.
| |
| ** 15 '- l
| |
| *. 4..
| |
| 31 - . 15.719 44.0 . 0.43447 l.53688 l.02602'
| |
| "*** * ~:!!::.
| |
| * 16 31~ *.* 1s**.119 44.o* 0.43447 l.53688 1.02602 j**
| |
| ~:,, >_;_.-~_r:7.:_.:.:*_.**. * "-~.*_. ~3~*-_.-.*.*_:_'.:*.'*: :.:_.*:**_.-~*.** ._ ~,:~~; . . , ::x* .-~--.*~_ *:_.~a* ~~=~
| |
| ' I..: ., l.Oi60Z *~: .
| |
| . ... . ** l'.~*02602 .. -
| |
| *.*.*,.
| |
| 1~02602.
| |
| I:
| |
| '
| |
| . . i9~.. l5~719.'<:: ; <**,i - . . 0'~'43447 . . 1~53688
| |
| .*.*.. "
| |
| ;I.. .
| |
| . 20 :. *a; *-~-* 31~ '" -~-~ i5~11~*..
| |
| ...
| |
| . '. '4,li:.o.-'.*
| |
| * o.43447 ** * *1~53688 l.02602' I~
| |
| 1*
| |
| ,. .
| |
| ....___.,._.
| |
| ..
| |
| .
| |
| I i
| |
| I 1_;
| |
| 1*i** ._ *.:
| |
| ., . :.***
| |
| '.*,*. ':' *' .. *....*** *,.*.. .' . . .. . .
| |
| *, ...,
| |
| ':-.. **!,,
| |
| 1*; -
| |
| .
| |
| .
| |
| -~*-* ..
| |
| -.. * .. .
| |
| ..*
| |
| . .. ' ~ . :.: :
| |
| * ....,...
| |
| . :. . ,.. <*:-~ .~--~ *;*:. ,_:; . _,.
| |
| ------~****-*-
| |
| '. **~.
| |
| :, ,
| |
| . _____..:...,_______ ._ ____ ._,.;__.:..~ ..- _ . ; . . . _ __ .. ----
| |
| ..., ~ ...
| |
| | |
| -;---- _....; --- ~*. **..
| |
| **:* *"<'.. . *.. *~** *- . . ; . :* .; .. ~: .*_ :,_.:. :~. -*::::: :": -* .,. *-*~,,-,., . _,.<~:-:~-~<~*,(~/] ,_. *.
| |
| :.. .: . . ., . *.
| |
| * ** ' ...
| |
| * c ' ~ . -
| |
| ---. *. .. *~ .... "_:.':-:*... ....
| |
| :/_, ****.~- _,:.:_:>.'
| |
| -** .
| |
| .-".O* -
| |
| . .*
| |
| - '~* ' *,*
| |
| . ,'.
| |
| : . : .. '.' . . ::~' *.
| |
| , '*****. *<<:*'1*
| |
| -\*--!
| |
| i..::.
| |
| Baltimore Gas & Electric I Calvert Cliffs Units l and 2
| |
| ( .' Junctions I L.
| |
| Junction.
| |
| Nuluber-From Vol To Vol::
| |
| * Elevation* .
| |
| (ft)
| |
| Inertia. Coeff;
| |
| .
| |
| '. (ft~l)
| |
| L/A.. Irreversible Lo_ss Coeff *
| |
| (F()rward Flow) (Reverse-Flow)
| |
| I
| |
| * *-: '*0°.32.817.': * *,:'*. **0~2847:.**.'";:_;:1*
| |
| .. *,. *,, *,
| |
| *'. ~ . .
| |
| . . 21:. 3,! . . 14-. : ' . 6*.647" .
| |
| * 1.35757
| |
| "::~::;~**.*.******. :~:E <*i; L.:
| |
| * :. : 2s*:* ** ... *: 4- *, ts: ::* '.' t. 11659 30~833~ " *. 2~21921 29 . < .. .:*:;:: . ;15:. . . : :iL45106 *' . 30*.833 *. .*. *1~89705 :. ..*. i
| |
| ~- - . *..
| |
| 30 6 16 6'.54764 30.833 . l.98100 0.5431.
| |
| ~* :.
| |
| 31.
| |
| 32 7
| |
| 5 .. _
| |
| 16.
| |
| 17 6.94033.
| |
| 2.45106 30.833 30.833 t.82643
| |
| * l.89705_
| |
| o.511i1 0.66886.
| |
| : o. 75813.
| |
| 1.01407 0.94844 a*
| |
| \..__.'
| |
| 33 34*
| |
| 3s*.
| |
| 10' u
| |
| 9 17 18 18.;
| |
| 1.71659
| |
| . 6.647 6*.1.1156, * * * . 30.833.
| |
| 30.833
| |
| . 30.833 2.27927 1~35757 r.35757 0.32877 0~52886*_
| |
| * 0~2847'.
| |
| :o.ss65a:
| |
| *1 *
| |
| "_::
| |
| *36:,* * .-.*12*-- -. \:{:' . -.*. i~*igsJ.1_,.-* 30~833 .. 3:.13168.. 0.6194'2- *
| |
| * 0~92339 >Jj.
| |
| '---* 37' :* ** . t.
| |
| * 25 *. 3~752:': .. * -.. 33~.5 *
| |
| * 0~18587 i *09336 ** *. r 24461 .***
| |
| * tt
| |
| ~. Ji~11249 < *-1*~0857: .);;< *. ~:'.:. :;**.***2:6:4.4_.*:-'~._*-:._~:*._~-. :,**_.-_*_*.*,~: -_:_ ._IJ;.~ -:_* .*
| |
| _*.*38*:*,*
| |
| : *39.*_
| |
| * 40 41 * *
| |
| ,z.
| |
| , 3 _:~-
| |
| * 21* *:
| |
| 4 5*
| |
| :.;2i::*?:.::::::>::£)3*;18s:. * * : .
| |
| 29 29*
| |
| <'._,' 3*Jas': ** *
| |
| . 3.185
| |
| . 3.185:
| |
| :
| |
| . 34.*oa3 j4~*083 .
| |
| 34~083 34.083 0'.11249-0~46262.
| |
| o*.46262*
| |
| * /, _.!
| |
| 1:;.08s1*
| |
| 1.09823
| |
| *l.09823
| |
| *'*
| |
| **
| |
| *.r.__.c.:*.** . .
| |
| 1 319
| |
| .1.
| |
| 3
| |
| '+'
| |
| 1
| |
| .r..
| |
| ._*
| |
| __ .. __._.*:*.**..
| |
| . ,
| |
| 42.>
| |
| * 6:
| |
| * 28* 3 *.752. * . 33.5'. o*.;:18955 r.08961 *
| |
| . 43:,: *** . T*>** .**28*. .* * :3~752 * ' 33.s - - 0~18955
| |
| * i.0896i *
| |
| * _*
| |
| * i2Jo95 * *;~ *.-
| |
| *.s* *: . ,:j;' .~* *fa;;~z~i,it~}'*';ti,;li'2fE!'.*~;;A ~~iH!rc 'c '.~.l*'._*~. o_-~8 :4 9 :8a~ :i~:2~,-*i ~1t:_~ .2**~6:34~ i3 :i_ *.,_*i~-*~ -*
| |
| '- -
| |
| -
| |
| . * ":: ~~os3 * -.
| |
| (
| |
| F ...
| |
| 47' 48*
| |
| * 11
| |
| . -.. *,_*.
| |
| .*. I2
| |
| :*
| |
| *.
| |
| *26*
| |
| zs.
| |
| .* *, .* ..
| |
| "*-i.185
| |
| ' 3.7520 33.5 o.47795
| |
| . 0*16567 l.09336 1.24467
| |
| .*
| |
| i'
| |
| :* . ... ::: ,y;,~~*:*J.,~!!f*~:i~*~~:~ ~ ,.;~;~~:, ;'.'r~*1*.~: ~: .*. . *. ::~~:;;E :... ;:._~ oo*:_*_f 52:25:10:444:**-***-**._*'._*.:_.*_____ *-~
| |
| . . .*_t_****
| |
| ._
| |
| * s2:*. *
| |
| * i4** > .. :. ~<l:. ;:-: 1J*~l31i.r* '_,*::~*1};5:; ,* * *-
| |
| *:__ *. .. ~'' ;
| |
| .*: t. <:;_~-*::,
| |
| .. : :' -~-*. .... : *-... ~ "':'
| |
| * ... _
| |
| .,
| |
| .,:, .. -*.. . *.. '* - . '. ~ :. ..
| |
| *-'"
| |
| '
| |
| *.. _;.. .., ,,.:*.'
| |
| __ _:
| |
| *.*. *, *. *_.*' '*,:
| |
| . :".. .: ".~ '
| |
| ,*, -
| |
| '1 :**** -.. <' * *...
| |
| -. . -
| |
| 4-~ .;;* .3 cg' .*",.* . ,. ,:**.. -*..
| |
| . * ! ./*
| |
| . ,;
| |
| ; -> . '1.'
| |
| --:--*- *-**- ------- --~- *--. ----~~--c ........... :*-.. .. *....:.:_. ~.:._..\:..;::.:..._ :---. ~-.:... __ , --* ;_. __.__ *:. **- ... ** **. .-.~. -* - *.._-~_ *. <...... ;.*:* -* -:, .--. - "... * * * *-'* '~* :* ,; *
| |
| * I
| |
| | |
| I :.*: _;
| |
| I'.
| |
| \ __..
| |
| Table 4.3-2lb (cont.)
| |
| Baltimore Gas & Electric Calvert Cliffs Units l and 2 J Junctions j\, __ Inertia Coeff Junction From To Elevation L/ A Irreversible Loss Coeff Number Vol .. Vol (ft) (ft.-1) (Forward Flow) (Reverse Flow)
| |
| I'\. ' S3 15 21 4.1677 17.5 1.80105 *0.62111* 0-.43873 S4 16. '22* 13.488 17.5 *o.657 0.24302 0.26012.
| |
| I:. SS S6 17 18 2.3 24 4.1677 13.419 17.5 11.5*
| |
| 1.80105 0.65988 0.62751 0.24271 0.43907 0.25920 I. 57 58 19 20 20 21 ll0.4T 118.02 8.083 8.083 0.08104 0.08104 0.01608 0.04919 0.04975 0.04081
| |
| :(: 59 60 21 23.
| |
| 22 22 112.54 110.47 8.083 8.083 0.08091 0.08091 0.06443 0.02528 0.01208 0.06 61 24 23 112.54 8.083 0.08104 0.04993 0.02239 l1. 62.
| |
| 63 19 25 24 32 118.02 28.447.
| |
| 8.083 33.5 0.08104 0.15247 0.01021 l.11594-0.01859 0.63724 I' -64 65 21*
| |
| 26 32:
| |
| 32 2.3.332
| |
| *23.332 34.083 34.083 0.67885 o.44430 1.15864 l.14352.
| |
| 0.67613 0.66101 66 28 33 28.447 33.5 0.15247 l.11594 0.63724 I. 67 68 29 30 33 33 23.332 23.332 34.083 34.083 0.44430 0.67885 l.14352 l.15864 0.66101 0.67613 1: 69 70 31 31.
| |
| 35 34.
| |
| 41S.6 77.Z 48.292 44.o*
| |
| 0.02294 0 *.10822 0.17829 0.86502.
| |
| 0.17829 0.46714
| |
| ,-,.
| |
| . 71. .31 36 77 .2: 44.o. 0.10870 0.88345 0.47216
| |
| .. 72:. .35 - 34 385.5 48.292 0.05087 0.32120 0.28796 73 35 36 385.5 . 48.292 0.05135 0.37986 0.31303 I. 74 7S 34
| |
| .* 36 37 37 404.0 428.0 69.0
| |
| . 69'.0 0.04675 0.04947 0.96696 0.96367 0.49035 0~48992
| |
| : o. 97556:
| |
| '-~
| |
| 76 32 37 1071~6 10~0 . *o.000os 0.62312 77 32 37. 126.95 84.0 0.06204 1.39058 1.16223' 78 3.3 37 1071.6 10.0 0.00805 0.97556 0.62312
| |
| 'f I~
| |
| 1.
| |
| -~
| |
| | |
| >*'.
| |
| - ...
| |
| .:.:
| |
| r Table- 4.3-2lb (cont~)
| |
| \ l Baltiincre Gas & Electric Calvert Cliffs Units l and 2 Junctions r-.
| |
| t_.
| |
| Junction From To Elevation Irreversible Loss Coeff
| |
| ,.- -~ Number . *
| |
| * Vol. Vol- (ft) (Forward Flow) (Reverse Flow) -
| |
| \..
| |
| 79:. . 33 .. - - . 37
| |
| - ../
| |
| -*. <126*.95
| |
| ..- :~. :: : . - -
| |
| . . 84 *. 0 . 0~.06204 . 1.39058
| |
| * i~1622~- - --..I r
| |
| !
| |
| .*
| |
| 1
| |
| :80 ''. . , .. *13";_ ,:* *14.. 0.85766 . ' .. "-17~5' .*t.o45cJ4' * .*. ~:~::~ .. . . <~~~;~,"Y(j 8.1: 13, 18. . 0~85766 17 .5 1.04504 82:. 14 0.85766. - '17.5 0.62330 1 .* 35513 1.38091.
| |
| 83 18 0~85766~ 17.5 0".62330 1.35513. 1.38091*
| |
| .-.**.,. --*:.:**
| |
| **. *;:
| |
| . **~:: < : : " -- - '-'
| |
| r*-
| |
| 1 j
| |
| l_ .
| |
| . . ' ..
| |
| .' .; ' . . .
| |
| - * ...... ";* :* **-- ,.*
| |
| . *_. .,:*.
| |
| r' '.*. ',. *: ! '.'*
| |
| ~+/-:: -1:.~a:~l;~,;~~;:~:~;s~ni,C:~'.~.:~{St~ *:Yi'}1i,~,./'i;i,~~~J~l\~~1i:
| |
| \.;
| |
| r*- Notes::
| |
| \.
| |
| I ..
| |
| Junctions 26, 27, 29, JO, 31, 3~, ''34* and JS open a~ 5 psid with a linear. opening.
| |
| _:rate: - 95 percent open in 50 msec-, 99 percent open at 100 msec.
| |
| *_;, )* *-* -1*. -
| |
| . .- .. i ~ ;
| |
| *:* 'OJ\incti~n- 69 is ~-- n~t~on~ shield at 1_0 msec, 100_ msec*,.
| |
| .. ,
| |
| r -. **:_.,..**..
| |
| ~-
| |
| .,_. at 150 i"
| |
| \. . .:,.
| |
| '** .
| |
| . ..'
| |
| l.-. . :_;_ . ':; ;~ '* '*.
| |
| . **.: ' .. * ,*:.::
| |
| \.
| |
| -I
| |
| ...-*.
| |
| _________ :_____:_ __ --....;. ___
| |
| * * * . iY 4.3.4'-
| |
| ~-----~-----
| |
| .
| |
| *---- -*--
| |
| ;,_ .**.**
| |
| *
| |
| .*
| |
| ' "
| |
| ... __
| |
| .* ._-:** *.
| |
| ,
| |
| '*
| |
| ~
| |
| ~ r
| |
| ....
| |
| . I
| |
| .
| |
| | |
| * ... - . ..... ..
| |
| I
| |
| : '
| |
| .. -*, - .. *'
| |
| .*., :
| |
| : . ."*,I"* . . .. ~.
| |
| ~ ' .' :. .
| |
| ,
| |
| .*.-*
| |
| *.' .-- * ... *.,
| |
| -.._t'*.: _ .:. _ .'**'
| |
| I
| |
| * Table 4. 3~22a:
| |
| Northeast Utilities I Millstpne Volumes
| |
| ~S Unit 2 1: .
| |
| Volume*
| |
| 3 Height Elevat_iori -
| |
| *Volume .Number . - (ft . ) .. (ft) **-* (ft} .-"
| |
| *- ... ,, .....-
| |
| I *'
| |
| /103'~.r~.*
| |
| *-* .
| |
| * *** -. *-<-..-1*0*
| |
| *,-., *:: -* ~
| |
| . ;~*4*~a* ;) 4.>*-* .
| |
| /t!o-.4<** _"\fi;*1_o;~-~58L{;;
| |
| .-~
| |
| ,.... *:;.*.:':'
| |
| I _:*:,,*, ".:* .'*
| |
| *3:: . :: ll0~4: * *io~4584:**
| |
| w, _ _ , . * '* -*- _.-.
| |
| 4 94.3
| |
| * I0.4584 2-.0
| |
| 'I, 5 *94.3
| |
| . 91.0 1(h4584. 2.0.
| |
| 6 10.4584 2.0.
| |
| 1: .7 8
| |
| 91.0.
| |
| _:. . 94-. 3:. .
| |
| . .4584 10 *.4584 2.0
| |
| - 2.0; *. -~
| |
| . :. :* ' ~-*~* .
| |
| I . *. ; *. 94~3' ,._
| |
| .. 9
| |
| * io~*45a4.. . 2'.0-.* :
| |
| . - .. -
| |
| * '" . ' *.-
| |
| -~. ' ..
| |
| .-_,-. --
| |
| 10 . *.. 110.4,: . 10.4584 *. 2~0 ..
| |
| ..- .... .... ** .*. '.,_* .. *;:
| |
| -.. --*--:,\-:'/.:_*:- :;?Ti1li1.4::'*. 0.;,'i1~K4sa4 *-* * *
| |
| ;* *: **,
| |
| .***11.: .* ; .. *,.:.*.
| |
| I.
| |
| '~-*' 12.
| |
| *, :-:**::
| |
| _,_ ,.. : _:1*03~_1. -- 10.4584 .
| |
| :- ~-
| |
| 13' .. 49 ..56. 15.8751 . -13.875 *-
| |
| I ..14 .271.L .. 15 *.87:5.1. . -1.J.875 1-5:* 102.22 .* 15:.875.l . .875
| |
| ***:< :' 267°. I8: :.<;{:~-:f:~:~~S751~ : _.... 0:.I:J.875
| |
| :.* "3i:i.fft::~:*<.;
| |
| .* * * ** 16 / *- *. * . . : :: ..
| |
| .. . .. . . .* :~1 if' *01.***.jtf~-~~~:~;{ i; ".;.: ;,*,~:=~:*
| |
| - - .. -~ -~ : .- - . *. . .~ -
| |
| >: 9:*.6251
| |
| '
| |
| >.*~- . *. '179~8>.
| |
| )
| |
| .' 2.0' ...: .* ,_ .- .314.12::~ .* .*. ,., 9:.62.Sr.
| |
| - . --** ~ ,* :~~ :: :*- ' - </'"*:'.'.:,:.
| |
| ,,.*..
| |
| *:*
| |
| . : <!' :-:*.: . ., ' ' . :.
| |
| "II
| |
| ~ . -
| |
| '
| |
| *.** - ... '*-,'
| |
| * r"
| |
| . . ' .. .. . .
| |
| ~
| |
| ::..*:**..... -:.:** ..
| |
| *-25 .... .:: -~.. 86-'**'
| |
| /*'. .,9* 3*..... . - ***\.:.:*:*.4:*.1917.*
| |
| 26 .* 113.l ... *.**. 4.333- . 3.66T.
| |
| I 27 *132*.T _ .4.333. . 3.667
| |
| / .''
| |
| I .
| |
| .- .
| |
| . :-' .
| |
| *''
| |
| . (\" .... *
| |
| *< ... : : *.' : ~ **. :-~ .
| |
| ", '.' '.: *:
| |
| ..... -.. ':
| |
| I I
| |
| ~. , - ~;. ~.. '
| |
| . *';_* ... *, ' .**
| |
| * .. '*
| |
| | |
| -
| |
| ~*-: '
| |
| Table 4,;3~22a (cont.)
| |
| *Northeast Utilities MiUst9ne NPS Unit 2 I
| |
| Voluine"s
| |
| : 1. .
| |
| Voluma. Number Volume.
| |
| (ft3)
| |
| Height (ft)
| |
| Elevation (ft)-
| |
| *"1*
| |
| 2"8 86.293 4. 791T . 3.!~315*
| |
| **29* . **:_.-;* ,* ... 113~-I .*. li-~333 3.667
| |
| -:** "; .**'.*:*.. '< *"1* .* ' ... -
| |
| . 30*.* ... **. 132~7
| |
| ** .... 4~333
| |
| .. ... ~.6~T 31 1613.0 40.51 12.4583
| |
| '32 6323.0 85.51 -22.5
| |
| ***1*
| |
| .,,
| |
| i 33 6323.0 85.51 -22.5
| |
| . 1590.0 40.51 -2~0: ..
| |
| 34
| |
| .35 ... . .1590'.0 34.01 2.5. '.',l -
| |
| 36: *r~OE+6: 175'~0- -22*~5
| |
| *-**'.
| |
| \:
| |
| *,
| |
| *.....
| |
| ,, *,
| |
| __
| |
| ._-, -.
| |
| ,,
| |
| .1.
| |
| ....
| |
| -*"'*
| |
| **~-
| |
| ~:- ~;* ~ ~--
| |
| .*
| |
| .*
| |
| *. *-.,~
| |
| .. ":;
| |
| -, .~
| |
| ....... : :
| |
| Note: Volumes 1 tQ 24 are initially at 14.7 psia, 550°F, 0.01%.RH, all other v~lumes are at 14. 7 p_sia, 120°F, 0.5%. RH.
| |
| :1*-
| |
| .,,,,f~'i'
| |
| - **-~*---~~, ..___,. *--------- -*-.---.----- .,. _____ _ . '
| |
| | |
| T~ble 4 *. 3-22b Northeast Utilities Millstone NPS Unit 2 Junctions l~ction From To. . Are.a Elevation Inertia Coeff L/ A
| |
| . (ft.-1 ) .
| |
| Irreversible Loss Coe*ff (Forward Flow) (Reverse Flow)
| |
| I*
| |
| tiumber Vol * *.Vol (ft2) . (ft). . .
| |
| 1 l 2. 19.sga:* 2.0 o~.19988
| |
| * 0:~.21097" 0.21097 2* 3: . 0-.1'9988.* 0*~68684 o.68684 3* 4. l-9*,$98 2:. 0 0.1~988 0.21097' 0.21097 4 5 . 15.241 2.0. 0.19988 0.41759 0.41759 5 '6 *19 .-8.9.8 2..;'0 o*.1998.8 . 0.21097 . 0.* 21097 7 6 8.602 . 2.0 0.19988 0.80289 0.80289
| |
| : 8. 7 19.898 2.0 0.19988 0.21097 0.21097 9 8 15.241 2:0 0.19988 0.41759 . 0.41759 4-*
| |
| 10 '9; .19.~8.98 2~0 0'.19988 0.* 21097 0.21097 11 10 10.54*3 2.* 0 0*19988 0.68684 0.68684 ,*,.
| |
| ".
| |
| 12 *11. *1g;~*13:9-S
| |
| * ..J'
| |
| -:2 .. a 0~!9988 0.21091 0 *.21097 1 12. *11.359 2~.o 0.19988 0.64155 0.64155 1 31 16.533 12..45833 o.6546.73 1.215 0.54740 1 1_3 14 2 .. 31 16.533 12..45833 o.556561 1.244 0.60456 15 3 *31 16.533 12.45833 o.556561 1.244 0.60456.
| |
| 116 4 31 .16~533 12.45833. 0:0.654673 0~Q54673
| |
| !.215
| |
| *.. .r.215 o.54740
| |
| . . 17 5 li. *..... _16.~33 .*.. '12'~45833. 0*~54740 .
| |
| l,1s
| |
| * 6 31. . 16.533 '12.* 45833 0~855375 1 .* 343 0.61386 19 T 31 16.533 12.45833 o*. ~55375 l.343 0.61386
| |
| -
| |
| Bi 31 16.533 . 12.45833'. ._0,.654673. 1.21.5 0.54740 l.20
| |
| .21 . 9;,_ .. 31 * .** 16.533: l_2,.4~a.i3 * *; ..... ::.o-.:654673 * * :1.21:s**
| |
| '. *='
| |
| *. *. 0.54740 .
| |
| *122.
| |
| ,.r, ..* * . . . .
| |
| 31 .. 16.533 . .12.* 4.58.3.3*:
| |
| * o.ss*6s61 1:~2.44 . o*.6o45fr
| |
| .10 ..
| |
| *23 11 . . *31 16.533 *12*;:"458'33 . o.556561. 1~244 o*.60456
| |
| *1124 .
| |
| * 12 31 ... 16.533 .*12.45833 0.654673 1~21~ 0.54740 25 13 l~.4442
| |
| * 2.o 3..37795 0.7162 1.04147 14 2.0 1.12266 0.27534 0.27430 1:~*-*'~
| |
| 8.7526
| |
| .14 8.82'53' 2."0 l.l061L. 0.25768 0.25632 I '
| |
| *I ..
| |
| I. +-;-*
| |
| . 4-* 3.
| |
| | |
| I Table 4.3-22b (cont.)
| |
| Nortµeast Utilities 1*
| |
| Millstone NPS Untt 2
| |
| .Junctions I
| |
| Junction From To Area Elevat:Lori Inertia* C6eff L/A Irreversible Loss Coeff I
| |
| . Number Vol *Vol (ft2) (ft) (ft-1). . (Forward. Flow) (Reverse Flo1 .
| |
| 2s .. 3 15 *. 1.5484 2.0 . 1 *.79478. 1.0087. 1.12775. .
| |
| 1 29 2 15 4.8316 2.0 1. 79478 0.37941 0.1+8441 30 1 16 8.*1989 2.0 1.16834 0.30074 0.28675 *I
| |
| : 31. 12 16 9 .1189** 2.0 1.16834 0.4189. 0.3685
| |
| .32
| |
| ..
| |
| 11*
| |
| 10 17 4.8316 2.0 1.79478 0.37941 0.48441 I 33 17 1.5484 2.0 1.79478 1.0087 1.12775 .
| |
| 34 35
| |
| .9 8
| |
| 18 18 8.8253
| |
| : 7. 7 2.0*
| |
| 2.0 1.10611 1.10611.
| |
| 0.25768 0.38191 0.25632.
| |
| 0.30933 I
| |
| . 36
| |
| . 37 7
| |
| 1 13 25 l.4442 0.3105 2.0 3.4375 3.37795 0.22136 0.7162 1.45764.
| |
| 1.04147 .*
| |
| 1.47107 1.
| |
| 38 39 2
| |
| 3 27 27 2.0926 2.0926 3.667 3.667 0.53543 0.53543 1.11458 1.11458 1.28635 1.28635 I
| |
| 40 4. 29 2.0926 3.66T O. 7050!F 1.11128 L28788 41 5 29 .2..* 0926 3.667 0.70509 lelll28 l.28788" I 42 *6 28*. 0.3105 . 3.4375 0.23067 1.45665 1.46745 43 7 28 0.3105 3.4375 o.23067 1.45665 1.46745 I 44 8 *: .30" .2*.0926 3.667 0.70509 1.11128 1.28788
| |
| . 45*.
| |
| ... 46. 10 9 30 26 2.0926 2.0926 3.66T 3.667
| |
| .* o. 70509 0.5.3543 1.11128 1.11458 1.28788 1.28635 I
| |
| 47 48 11 12 1
| |
| 26 25 2.0926
| |
| : o. . 31os
| |
| .3.667 3.4375 0.5.3543 0.22136 1.-11458 1.45764 1.28635 1.47107 I
| |
| q.9 *1'5 16 25.136 -13.875 0,..36732. 0.0993 0 *. 16106 1*
| |
| 50 .* 16 *17 25.136 -13.875 0.36732 0.16106 0.0993*
| |
| 51 52 13 14 19 20 2.8883 17.578
| |
| -13.875
| |
| -13.875 3.17907 0.63919 0.8189
| |
| . 0.20754 0.5371 0.23713 ii' 53 15 21 . 6.38. -13.875 1.55266 0.53593 0.401391 54 16 22: 17.318 -13.875 0.64756 0-.20912 0.23777 55 17 23 6.38 -13.875 1.55266 0.53923 0.410391 4*.S* ++
| |
| .I
| |
| | |
| ~ ' .
| |
| . . .
| |
| I .
| |
| *i,'*. .
| |
| ,'' . **'. \ . **:
| |
| ,'*
| |
| '
| |
| .
| |
| .: ,** ..
| |
| .. . ~ .. ~ . .* , ..
| |
| 1* ~
| |
| . . -~.
| |
| Table-4~'.".'22b (cont**. )
| |
| . : **.;
| |
| Northeast Utilities I Millstone NPS Unit 2
| |
| . Junctions.
| |
| I Junction From **. To * *
| |
| * Area. Elevation
| |
| .
| |
| Inertia Cocff;L/A
| |
| .. . * .. *.*... ' .. *. *:* .. _*.
| |
| Irreversible Loss Coeff
| |
| ,fmber_** Vol VoL (ft2) (ft)** .** .. *. . (fi:~l) ' . ' (Forward Flow) (Reversc_Flow)
| |
| .* *,
| |
| *i&_.*_s25-:-: : -~~*:~75*. ,-~~J:.\:. "a.:~67464. '"*
| |
| * "; ** i-*. ' .* , *:'._*?*.
| |
| 56 18 -.*24 ;'.:' .: ; o.22s2: ** o. *:.*,.*. 2s12z *
| |
| * 157' ..
| |
| . '-'*,
| |
| :. :: ~ '. .~
| |
| ****19 . *20_... ';128~99 ** * -23.S' *.<. 0:.06551. *. o**.*0*5-.3_7:2**-.. _*.* .: *..., -.:::*:
| |
| .': -~*t**a**,;0**1*
| |
| .,. .* . ..... .t.. 9*3 ***
| |
| 58 20 21
| |
| * .
| |
| 129~ 79
| |
| ' .
| |
| -23.5
| |
| -:'J,. **.**, ..
| |
| *.. 0~06~41
| |
| .c **. ,
| |
| o~06987 ....... **o~.os~sg .* .* .
| |
| * 1~9 21 2.2 . 134.6 -23.5 0.065.41 . 0 *. 02668 0;.05062 60 23 . 22 137 *. 81 . -23.5 0.06541 0.01169 0 .* 03911 61 24 23 ._.* 129. 79 -23.5 . 0.06541 . 0.06987 0.05089
| |
| *162 19 24* . 128.99 . ~23.5 0.06551 0.05.372. . 0.07293
| |
| : 63. 25 32 *. . 34:; 975 3'".4375, - . 0.17436 1.25505 0~78605 1 64 2T *3i*
| |
| ".
| |
| 16~;.547 .
| |
| .~*.
| |
| .
| |
| ..
| |
| * 3~66'1<
| |
| . . **.*
| |
| (j.49171 . t~.15026* .* 0.66504 65 2"6 .. * ,32 ..
| |
| * 16~547:. 3 .'is 6_ !_*( . *.* *.* * .*~ .* 0~66409. .; 'i:.1619. 0.676~8 166_ 2*8 jJ;. \,'34~~~975.:
| |
| " "'".
| |
| .*_1*:4375\*, . .. ::o-~17436.
| |
| _ .._,::-;-.*. : ',I_'
| |
| J .*
| |
| :.*
| |
| l.'~25505 .* .* 0'~78605 .
| |
| 67 29 3~ .. 16.547 3*.66T ' . 0 *.49171
| |
| * Ll5026. 0.66504 168 30 3_3 16 *.547
| |
| * 3'.667 o.66409 I.1619 o.67668 69 31 35. 173;.58 ' . 12.* 45833 .*. 0.11544. 0.;731Q9 0 .* 44946 110- 31 3~ 173.58
| |
| * lZ;.45833 .*
| |
| * 0.1128 0;.68053 o*.*433s9
| |
| * ~*t ,I
| |
| *I;:~~ .*:. . .* . :r~:~1:i:'3;*>1~~~,)i::~~~~i1~,:i'~~fr> .* :;"' 'f?i!f 33,. 36 119~.5 -i2.S; 0:00536 ....
| |
| 1
| |
| > :t.37504 J*****. **. . . ., ;~s;:~**
| |
| I.22161
| |
| *.,. ..
| |
| ._~z .. 36.. 237.:84' *~ .: <63~cr*:, :*: Y J'. o*.:04724 . . r.35648 *
| |
| * i ..10046
| |
| *~ ~:~ ~--:~~~
| |
| I 19 <. . 14. 15 '*. *~~398' '.: ;...13~875'.0 ' /'; 0*;33317: .*. :._. ,;' <l.3~332 ... . . 1.42108" so* 18 ... 11 2~398. . -13.875 . ' _0.3331.7. . . 1~39332- .
| |
| * 1.42108 INote:** Junctions 13 to 24 are the neutron shield tank interface. See text*for discussion of these junctions*..
| |
| * I .
| |
| .
| |
| ' ....
| |
| .*, .. *.'
| |
| ',* . ~,
| |
| .*.. *. . ' ~
| |
| .. -* _.,,_,
| |
| 1*. ". :*;, .*.
| |
| ;.
| |
| ... : .. ~
| |
| . ..-. . . :~: ..
| |
| *_,*._*_,.;
| |
| ................ * *....
| |
| ,* . ..
| |
| . ': * ...*
| |
| *.*:... :
| |
| | |
| *I*
| |
| ,,
| |
| I Table .4.. 3~23a Consumers Power Palisades Plant Reactor Cavity Subcompartment Analysis Volumes I Volume (ft )
| |
| 3 Height* (ft) Elevation (ft)
| |
| I Volume Number l 198.33 9.6276 614.8724 *.11 2 209.86 9.6276 614. 8724.
| |
| 6~4.8724 I*.
| |
| ,,
| |
| 3 198968 9.6276
| |
| -- - 198.68 9.6276 614.8724 5 209.8"6 9.6276 614.8724 6 198.33 9.6276 614.8724 7 409.4!1 15.8255. 599.0469 599.0469
| |
| .I, 8
| |
| 9 409.44
| |
| *4oa-~.67 15;.8255 15.8255*
| |
| 15.8255 599.0469 599.0469
| |
| .,.:;
| |
| 10 408.;67 409.44. 15.8255 .599~0469*
| |
| 11 12 . 409.44 15.8255 599.0469 a:.*
| |
| 13 621 *. 26 7.7240 591.3229
| |
| . 14 . *621.26 7~7240 591 *.3229 *.I.
| |
| 621.2'6 T~ 7240 591.~229 15
| |
| ,,
| |
| I.
| |
| 16 621.26 7'.7240 591.3229' 17' 621.26 7. 7240 . 591.3229 I..,.
| |
| 621.26 7~7240 591~3229 18 19 . 472.9 1 *. 323 590.0
| |
| . 4
| |
| ., 1.
| |
| 2(} 2.9071 x 10 24.5 624.* 5 21 39 *. 27' 2'.5 . 591.33
| |
| . .. 4
| |
| : 22. 5.1345 x 10 . 70 *.0 *590.0 .
| |
| 23 . l.0742 x 106 *. *130.0 649*~0
| |
| ..
| |
| ~ :'
| |
| :1--
| |
| 1.*
| |
| *1
| |
| * _, ..
| |
| . +* $.
| |
| . A_
| |
| #f' 6
| |
| | |
| '. *- - ' *-. .~ *- :.
| |
| .*.' : -.**,.*:
| |
| *1 ~<
| |
| ,* *... . -~ ; ..*.
| |
| .....
| |
| . -* -
| |
| '-_.*, .---
| |
| ; .,_:
| |
| ;
| |
| .. *
| |
| -.
| |
| 1* -*-.
| |
| _,,. .. *._ -
| |
| . -. . .. . .. -~
| |
| "
| |
| -_Table 4 ..3-23b *
| |
| * Consume-rs Power * *
| |
| :I l~.ga~1:or
| |
| *
| |
| * Palisades Plant Cavity Subco.mpartment Analysis Junctions I - ,- - .... -.*
| |
| '
| |
| ., __ ', .
| |
| -
| |
| *Junction. From.*: . . Ele,ration
| |
| * Irrevers_ible-_Loss' Coefficient Number Vol. ~- .*.. ~ft) * . *Forward K' *-Reverse- K
| |
| ;*;, ' ,* ---> ~.' .:.' '; .,*; ... :... *.:* .':* *.-
| |
| :*::
| |
| ... --~ '; : .-.
| |
| _I: _--f .'. li~'28 - - ... ::6f4::i1*24 .* - 0.44'773_;'
| |
| ' 2 ,2 3 IZ_.655 *' 614_.87-24 -0.4381 - -._0!"4828 o_.4828
| |
| *1-( I_
| |
| .3_
| |
| - -4 3 . - ' 4.
| |
| *4
| |
| _* 9 *. 37-7'
| |
| -;12_;,;:()55 *.*
| |
| '*614.8724
| |
| ' -_§14;'$724
| |
| . 0.4657
| |
| *9.04:381 o*.69.60 - .
| |
| o.4ais-
| |
| .0 *. 6-960 0.48~8-
| |
| *:S -.-
| |
| 5 6. .5 11.28 .. 61.4.8724 - 0.4477_3 o.5684- 0.5684 I 6 1 . 6 .10.283' - --614. 8724. 0.-4563 o.6327 0.6327 .
| |
| l.. -_ 20. 20.155. . 624~5 - 0~2"016 1~'09704: o.-ss98T I : .Z
| |
| *-<
| |
| -.20 - - -20.155 .
| |
| 20: * : : *- :w..iss .-
| |
| . "&24*_-5
| |
| ._-*_ 624.5'
| |
| -. *0.2016
| |
| .- 0.2016 1.09704'
| |
| * - . l.,09704c
| |
| - *-0*55987
| |
| __---.- o.,55987' ~ *, '
| |
| -9' -* -3~- _._
| |
| I *1cr 4.>' -_ 2b. . 20.-.1s:s-
| |
| -, .. _
| |
| _- 624~5 * :* b~2ol.6. 1.09104.- o.ss9s1 -
| |
| ll 5'* 20. ..20.. 155- 624 ...5 . ' 0 .. 2016 1.09704- *. 0~55987 1.12 6
| |
| -i __
| |
| 2:0 .
| |
| -1 .
| |
| .20.J.55
| |
| -:12¥.a*r
| |
| . 62-4_,..5
| |
| :614..'8724 . -- 0.:719_9_5 a.-.2016 1 *. 09704 0.58129 o.55987
| |
| ' 0.57'491 -- .~
| |
| J3 I- I~ 15-
| |
| - 2: o.6os42:
| |
| - . 0958129 0~60187 0*~57491 3: *-*
| |
| . o..58129 . - 0;;57491 .
| |
| 1 ~; .. 4-- .-*-
| |
| -_ 5. ' -** - . 0.00842 0.60187
| |
| -
| |
| * 1
| |
| *1- 19*18 6** . -_ 12: .. 12~87 - . 614.8724 -. 0~71995 0.58129 0.57491
| |
| * * * *
| |
| * *u -<
| |
| 1 :
| |
| ~*~-~
| |
| .*. ~;?,;~}*i;l~,;~,;..*~:~:: &~:
| |
| * *~-
| |
| .*; -- s
| |
| .... - ** ,~ w ,..,
| |
| , -. 24;.81''
| |
| ** ,
| |
| ::_10, >~' -* -\4~1ss'.
| |
| .J : * * - - 1 * : ,_.
| |
| :<<599~0469 * -o.32119
| |
| * ~*/*.-.:-~
| |
| _- <-~;\s99-*.q469: - * -0.18012
| |
| * . * .* !:~::~: . . 0~444*26' .
| |
| * 0.02851,
| |
| '
| |
| .'
| |
| _: o.44426
| |
| '-.0.02851
| |
| * *:'0."4-8977 .
| |
| -----0~028s:1-_
| |
| .*:i.
| |
| - .. -
| |
| 12 . . ll __ *--~:-~ 24~81 .. , ' :*_599**. 0469 - .. 0~32119 _. _0.44426 0.44426 '
| |
| 7 12.. - -44.185 - 599.0469 0.18012 '0.02851 0.02851 I 2s T
| |
| . . 14 13 . 25.36 25 .36 -* *_ ' .* 599. 0469
| |
| _: 599. 0469 0.42815.
| |
| : o. 4281~ _-
| |
| 0~3123 0.-3123
| |
| -0~2988 0.2988 26 8 I 21:
| |
| ...
| |
| ' 9 .15 -
| |
| * ZS.36 .-. 599.0469
| |
| . .* *.**." ....
| |
| . I
| |
| * o.42s15* 0.3123 - ---. o._2988
| |
| *. _=:* .
| |
| I*: *--* *' '*
| |
| .. ~-
| |
| -.,
| |
| . . ....
| |
| - ..
| |
| *. :'**.:_*' *. . - ' *...
| |
| :~ .. .. . . .. ' . . .
| |
| . * .....
| |
| :. . .
| |
| ..
| |
| I
| |
| ;_
| |
| . ' . ' . ' ; *',' ~* *'
| |
| **.
| |
| '; .',
| |
| ...... ' *- <~.
| |
| I s: 4-7 *.-.*:
| |
| | |
| I .
| |
| Table 4.* 3-23b (cont.)
| |
| Consumers Power Palisades Plant Reactor Cavity Subcompartment Analysis
| |
| *Junctions
| |
| * Junction* From To Area Elevati*on L/ A Irreversible Loss Coeff icilt Number Vol., Vol. *(ft2) *
| |
| * Cf:t) * * (.ft-1) * *Forward K Reverse K .
| |
| 28 29 10 11 16 17 25.36 25-.-36 599.0469
| |
| .. - 599.04:69 o.42s1s
| |
| *o..42815 0-.3123 0.3123 0.2988 0.2988 I
| |
| 30 31 12 13
| |
| .I8 14 25.36 35.53
| |
| -599 *.04&9
| |
| .591.3229 0.4.2815.
| |
| 0.27.325 0.3123 0.02713 0;.2988 0.02713 I
| |
| 32 14 15 35.53 591.3229 0.27325 0.02713 0 *.02113 33
| |
| -
| |
| 15 . 16 35.53 -.- 591~32-29 0.27325 o. 02713 0.02713 I 34 17 .16 35.53 .591..3.229 0.,21325 0.02713. 0.02713 35 18 17 35.53 591.3229 0.27325 0.02713 0.02713 I 36 13 18 35.53 591.3229 0.27"325 0.02713 0.02713 37 13 19 59058 591.3229 0.13812 1.0275 o. 7497 I 38 14 19* 59.58 591.3229 0.13812 1.0275 0~ 7497 I
| |
| ,
| |
| . 39 15 19 59.58 .5.91 ..3229 o._13812 1.0275 0.7497 40 16 1.9 59.58 *sg1.J2?9 O.J~812 1.0275 o. 7497
| |
| ..*
| |
| 41 17 19 59.58 591.3229 0.13812 1.027.5 o. 7497 .
| |
| 42 18 .19 59.58 591.3229 0.13812 1.0275 0.7497 43 44 13 18 .
| |
| 21 21 2.455 2.455 591.33 591.33 o..;8602 0.8602
| |
| : o. 7337 .
| |
| 0.7337 1.;18571 1.18571 I*
| |
| 45 21 22 591.33 0.82186 1.0268 0.5307 4.909 I
| |
| . 46 47
| |
| . 20 22 23 23 1186.6 120.6 649.0
| |
| *660.0 ..*
| |
| 0.01819 0.06128 o.7414
| |
| *1.378 Q.;4362 1.1sas* .,,
| |
| ,
| |
| : ,.
| |
| -
| |
| ....
| |
| . _:- ,.
| |
| . =~ *.: :
| |
| Note: Junctions 13 to 18 are a convection barrier. They are
| |
| . assumed.to open at a +12 psid pressure differential.
| |
| See text.
| |
| * I 1**
| |
| I
| |
| | |
| *.'* '
| |
| */,. ' :*:.-..:. .~~ -, - - .''
| |
| ..
| |
| Cl
| |
| ",.
| |
| .. '
| |
| [~I Table : 4. 3...;24a
| |
| ,_.I Ft Calhoun Unit l OPPD
| |
| .!*-1: React'?r. Cavity Sub compartment
| |
| ...
| |
| Analysis~
| |
| ,-,
| |
| '*
| |
| t _; , *Volumes
| |
| .
| |
| *Volume Number Height (ft) Elevation:
| |
| ~'.,:;., .;.' * , ; : *' *~ I'*
| |
| * _: *.::* ' ,* ~v,'" * '.: ~:**.:.: ' . . . ~-* . ..,.::.";'*
| |
| £: .. .;; >"*1~9i.7i* *..... .: lOOZ.333-
| |
| :1
| |
| ~ . . .
| |
| *. 2****
| |
| *,
| |
| . ,. .
| |
| . : ** '. :. . -~-;: ::
| |
| ' ..* . *20~243 .*' . *'* t~9171 . 1002.333;
| |
| . 3 13.270 T.9171 1002.333
| |
| :. 1 4 5
| |
| . 9.5821 ..
| |
| 12:~867 7.9171 7 .9171.
| |
| 1002.333 1002.333 r*1 I~ __,.
| |
| 6*- .897 7.9171 1002.333 1003.66:7 T 61'.*.776 2..084 '
| |
| ;-1
| |
| '**.
| |
| . 8*
| |
| . 9."
| |
| .* *. 61.'703:
| |
| \\; 6! *.703.
| |
| -3.855" 3~855
| |
| . 1004. 75
| |
| .* '1004.75:
| |
| ....
| |
| *'.10:** .,''" <'::~*-_;.**6i~J76* . .. * .. -. 2*~*084- * *. '*'" 100J~~66T . **
| |
| ;***-1*
| |
| '. '
| |
| ... -.-.. 61 .*. 703 . 3.855 1004. 75
| |
| ( 11.*
| |
| :I 12 13 61 *.703 9~349
| |
| '3.855*
| |
| 2.75, 1004. 75 1010.25
| |
| ...
| |
| * 14 . : .. . . ... :: - - ' - 9:.349* - .. . 2:~ 75:~ 1010.25*
| |
| I
| |
| ~~:,;.. "ar~i~:~ij~ii$r~~~
| |
| :*.* ~ :*.:/ ' . ' '
| |
| Z..75'* -*-- *" . . . ~ .
| |
| ,._/. 1010.25**
| |
| ' . .
| |
| . +".,~-~;*~:t(J*.~:~?~~-;'.<'., , >..*..*~. **:- '.._~, >;'."},*;_*i_,:_*..*,1 :~0 _,1~0 *:~.*_*.**225s*.*__'._._-'.* *.
| |
| I 1** ..
| |
| :I
| |
| ~ ...
| |
| l.T'
| |
| *1a * .*
| |
| *,-_,.' ._,., ' 9:,349,
| |
| **
| |
| 7
| |
| ..
| |
| ~;~.349~ :, - . *.\
| |
| '.*"2~75/
| |
| 2.~*:7s* **
| |
| .... -*: -
| |
| 1010~2.S
| |
| ' - -
| |
| ._.:, *. * ,., 19-*:,. -_ >:*<*'(
| |
| . ~ l0Z~06,
| |
| . - .,
| |
| 15-e42.l9*-. * . 987.0912
| |
| .\.c.~~;~~::1f ~~:~!i~~1.~t:~i~~~~tt~i~~~~i~t~~;1;~;:":* .' **~J,~'"t*i!~~~iE:**
| |
| 1
| |
| -*.
| |
| -1
| |
| *' ,.~-~ _2:! ''.*:-<::~*Y:Y~!.{120~:59. _., .. *. ~** .. 15.4219 :.. *: 98,1.0912. *
| |
| ;
| |
| . *-1** '
| |
| ** * ** 24- *. * <.'io2*.06: 15*4219 *- -. ' 987 .0912
| |
| * 25 135.49 6;.4063 980'.685
| |
| \I 26 27 147.85
| |
| *.
| |
| * 135.49 6.4063.
| |
| 6.4063 980.685 980.685
| |
| .-I
| |
| ...... :
| |
| " - _-; ___ .- . ' :_ .\ .
| |
| . **:**, ":. :*:---
| |
| ~ .' :" ... **. ,*_ -
| |
| . -<
| |
| , ~~ .. - - -.
| |
| ;--1* --- *, .. -
| |
| . "* ~ ,, . *-.
| |
| '-*,,.
| |
| -~ '
| |
| -*
| |
| .:..
| |
| :.. :.;.
| |
| -~*- ,,
| |
| < _*:-;*:
| |
| | |
| I Table 4*3..;*24a (cont.) I OPPD r - ..,
| |
| Ft Calhoun Unit 1 Reactor Cavity Subcompartment Analysis I
| |
| '
| |
| ( : Volumes I
| |
| 3 Volume Number 28 Volume (ft )
| |
| 135.49 Height (ft) 6.4063 Elevation (ft) 980.685 I
| |
| ~ -*
| |
| 29 30 142.85 135.49 6.4063 6.4063-980.685 980.685 I
| |
| 31 32 809.6 67126.0 4.1851 43.01 976.5 995.5
| |
| .1 33 1039.3 17.51 976.5 34 37347.4 62.51 994.0 ' I 35 37347.4 62.51 994.0 36 6.0E+5 125.5 994.0 I
| |
| ,.--.
| |
| \_ -' I*
| |
| /
| |
| '
| |
| I r
| |
| I*
| |
| \ -
| |
| I I
| |
| /' ...
| |
| I I
| |
| I I.
| |
| I
| |
| -- - --*. --
| |
| | |
| *.o. . . , *.*,
| |
| . '
| |
| * ...... ...~ ,,:-: ..
| |
| I} . "' .
| |
| .* :*"*: *: _"''
| |
| **.
| |
| * ~- .* ~ if *.. '
| |
| :*.'-* .: . .... .. *,
| |
| .
| |
| _* :
| |
| :.,* .. * .. *
| |
| [} Table 4*3-24b
| |
| ;I Ft Calhoun Unit 1.
| |
| OPPD l.I Reactor Cavity Subcompartment. Analysis
| |
| . Jilnctions
| |
| . --** .. ' .:*: '. :'; . . --
| |
| ~,~ *: ..:._ *..*: ' ..... *.-* . *~. . . ._ '" . , *...,: ' .. ~ '---.- ; .: _:* ~- . .,-; .
| |
| ,, Junction. From* To -* ** .. Area -Elevation.
| |
| * L/A *.* * **Irreversible Loss. Coefficient) '.*
| |
| *{
| |
| ,.,
| |
| \
| |
| . ..
| |
| .
| |
| *Number 1:.
| |
| vo~ > ~;t*K'*l~~:t:S1i~~~: ?> (ft\~k ...*. ~o~""d* K.
| |
| * *c:** f
| |
| * 6 *o. 6113-z * ** * . ~:o~
| |
| . . * ...**. *, , ;
| |
| 47735. :. :* -.~::.~c:*;~::*,;_ :,~\~~r~-~~~~'6'r**::~ *'~~~.*::.*
| |
| ~v~i:~e .K.* >
| |
| : 2. i 8. *
| |
| * 4~097 * *. 1004. 75 . . 0.876 . 0.844
| |
| - ...
| |
| *.1 3' 4
| |
| 2.
| |
| 2.
| |
| 4.097 4.0~7
| |
| ..
| |
| 1004.75 1004.75 0.875 0.875 ..*
| |
| 0~845 0.845
| |
| *.* 0.847' 0.847
| |
| .. o*.845:
| |
| :I 5 6
| |
| 3' 3:
| |
| 9 4.09T . 1004 *. 75
| |
| . 10... *. 4*~0135> ** 1003.667. 0.68014
| |
| . 0.876 0.844 0.5627 *.... :*t *.. 01034 . '
| |
| . - *- '
| |
| T ... 4:. * . 10'., -4 *.0lJS :'
| |
| * 1003.667 0.68014 o*.5621*
| |
| * c. I *.01034: --
| |
| ~I
| |
| .. . :. '* ,* -* . ., . :-,*
| |
| : 8. 4,. .* ll ; **1~1095'' - 1004. 75* 0.94722 1..31567 ..* ~*~4~~5.~< .
| |
| ... . , .
| |
| 9:* . o-~-94703*:
| |
| * r*~.3*1616::-: **-~- - ** l.43346: ...
| |
| .~ .. - .- .. . . .. . , .. . *.. .
| |
| ;I
| |
| ,
| |
| ,.
| |
| *. 1~43346>
| |
| ' '. :
| |
| 10 .. 5 14_.*...
| |
| * 1~*1095' *. 1Q04 .* 75 0.94703' . 1.31616. . .- . .
| |
| . .-
| |
| 11 .6 12 1.1095 1004. 75 0.94722 1.31567 1.43152 .
| |
| . 12 6 T 4.0135- 1003.667. 0.61732. 0.47735 . 0.8208
| |
| .. -
| |
| 13 t *. 19 4. 937a
| |
| * 1002*. 333 3. 93459
| |
| * o .43831 o*. 5008 ll 14 *.. 2: 2Cl . -5.120L 1002*.333. 3.44235 .. 0~43369 0.* 48713
| |
| .. *.. *~* * * * *
| |
| * c(~ ;*~.~~f~~!;~;~;~~::;;i~~#:,;i;:.~>::~~:;,;:* ;*~:~~:£''*.* J-;:cr~1~;~,~c:::,
| |
| . .* i:
| |
| :1
| |
| \.. .. -.
| |
| 17 -
| |
| 5'
| |
| * 23". * :: : 5 *.1201 .*.1002'.333
| |
| ~ - '
| |
| 3*.44235:.
| |
| .
| |
| o.43369* .. .c:::- 0 1~Aa11J.
| |
| *~ . . '
| |
| *
| |
| : 18.
| |
| * 6 24: ..
| |
| * 4.9378? . 1002.33 3.93459, o.43831,
| |
| * O'.soo8*
| |
| *:I * :**.* 19* .**. * *r~',;:;~.,,':.l~~~~~~. f1 ;:t~;9:~2~.*:~*.**.: ?.:~~7384 * - 0.12206 . *. ~o.;82551
| |
| *::*:\;:~0:/. .14~t;*:,;:**:1::61161:*~~2f'.1oro,**.2s:.*** c*.\2_.86os1. *-J}}~;~~_t_~:'1'.* _-.: *.,_'~:. *-_* :.'.*'.:*'.0_*..*:*_~..*:.*. ~.;.s.)4**.:1'.:.**_.-:*.* . '.
| |
| 2
| |
| :
| |
| *1 ***** :
| |
| *,.
| |
| * .*
| |
| ~
| |
| *:
| |
| ;~~,J*;~::~:~*'."f~~~:~f *;*m~~:
| |
| lT. * **1~6i16.;:'..*iol:o:~2s. * ;_ *z *. 86057-. '.
| |
| .
| |
| <~~t~~~::
| |
| * o~.65215
| |
| ... '.
| |
| * *:* * *' ' _ _ . .*
| |
| 0 8 55 1
| |
| 'a:sm1 *. * *..
| |
| c);~76541 .
| |
| ?
| |
| ._.
| |
| I
| |
| .__
| |
| * . 23 24-
| |
| * s :
| |
| 6 18* '1.4293~
| |
| '' ~
| |
| 1010 .25.
| |
| ' ... ' - ' '. ', .
| |
| 3'.17384 . 0. 72206:.
| |
| ' * :: .
| |
| ' .. 0.82551
| |
| :I
| |
| __ ;
| |
| 25 26 1
| |
| 2*
| |
| 2 3
| |
| 3.205
| |
| . 3.205 ..
| |
| 1010.25 1010.25
| |
| ** 3;.8702T .** **. 0.59364-3.87027 . 0.59364
| |
| *. 0.59364 0.59364.
| |
| :I *- .,_*,
| |
| *. *.*-.*
| |
| ::,,-
| |
| . i . . .. -
| |
| I ,-"*".,
| |
| ' - . ~\ ~ .
| |
| | |
| 1*
| |
| ~.;
| |
| ''', .... *.* ... -., . '*..
| |
| . i *'.'.,; * . ' ': .' ' . * :'; - - ..
| |
| _-.-) ..:*---:.-:.: *:;**,:: .* ;.*:_.:-:"-*;*,~>*:.'..,;**;_..
| |
| -~-- -;* * !_:;- - ' .';:_--.:,
| |
| '.: _ ..
| |
| r
| |
| '---= Table 4*3-24b. (cont.) I OPPD Ft* Calhoun Unit l. - I r_;
| |
| I ;
| |
| Reactor Cavity Subcompartment Analysis
| |
| : '~ ~- I
| |
| ....
| |
| ,. ''*.
| |
| *.
| |
| <*' -1.:-
| |
| ~ *. J\lnctions _ . .:.~ 'o:: ;.
| |
| .;_**. . . *- , .... :' ,:.***-*.*.-
| |
| L_:
| |
| r--
| |
| \ .;
| |
| .J7~_ i~;?~~~~. ~~i~*'f~,~ff~~~~:*0;* i~tf:~ ;**'i~:EJ~e*'.;:;;;J.c~;f~i~i*f11f 28- 5 4- -* _l.5104 1010.25.' 3.81_021 * - o.59364 - - - ..
| |
| o-~59364---.
| |
| ' - .
| |
| 1.
| |
| -
| |
| 29- *' 61.: '5 . 1.5104 1010.25* 3.8702T 0.59364 -- Ch.5936~ - ~,-*. - :- .
| |
| 30 -6 1~982T _io10*~25 4.6985
| |
| * o. 77529- o.77529° -_
| |
| 31 13 32:. *:l.399- :* *- 1013~0 0.40819 1.03017"'
| |
| 32'. t4-_ 32:_ *
| |
| * 3"~-399> *- 1013*.o< *- o~4osi9 r~o301i *--
| |
| -- -* *- _,_:_*. .* * * .. !' .. - . !\
| |
| '33 --*.1s:~ -- -~3z**,_-_ __ 3:~399'<-*>1013-;.o *
| |
| . . .- ~ .- - . . .. .
| |
| 0~40819--- -*_
| |
| :.<* .'.---
| |
| >r.o30lT 34 -*. *_ 16. '.* 32'.'._-*: '3 .* 399:;. : : 10_13~0 - ,. 0~.40819 t03017 ,
| |
| L.
| |
| * ::: " *v f~**:.~i:~1~z~:.::~"~* t~~,~~m .r~:~~c x
| |
| . - -
| |
| 1 37 - IY 14' l.14:Sa _ io10. 2s
| |
| * T. 04363 o.10889 - : .10889' -
| |
| **~ .-
| |
| . ::* ~~' : ~:::...:~~:~~ ;::~~!::. . ~:~~::: ~~~~:::::*l
| |
| *1~:* *** *~: .***.**if :;*~:::~: ;fu~~*ii*<* i:::Ij~ :,*~~~~:::.**. ' :,;:.r*i'3 ~:~~::~A<;j, l'
| |
| ..
| |
| L_:
| |
| .-* :'f .:*r 5;!;:~<;:1'.'~~;.1i~f~!!:~(i~i~~~::~t:~''.'':;::!!;"'1'''~:~!:f : w;*~~i~~'.~~~:~*~~Xi~:I :"* 1
| |
| . 44'
| |
| * _ - . 20, . - 21., ii~a46 * : 987*.0912. _ _ o.6385T 0.04654. * -.- _ 0
| |
| :f 0~04654, :- -. '
| |
| r I
| |
| \
| |
| -~
| |
| .
| |
| .
| |
| .
| |
| "4i >>* ._'. .. :.2iJ;'.-::",.~;:*2z.*3::*-rZ:ta46t:;~-*:.>\:'gsT~09Ii.::~" 0~638S7 ./, _*_;.-0 ~04654 _-.- .:-*_, ');__,\.().f;\.i'o:Lo46S4.'..,*: :_,:;-.
| |
| *. .~~**.***f2*~*; zt'f[~~:~~(~ft~~G~~:~~t~~i!*~~~i~:~p**!~!:*;:~~,~~1~~~~il~c~~r1~*
| |
| 1
| |
| ~
| |
| r*.1
| |
| *.
| |
| . :: .* * * .*~: . }': . * ~::~:~~ . *. ::;:~:~i t~~::: ..~~*;:::2 .* ' ;;!.'£~:~::~: \l
| |
| -__ 4a - : _1~,<--" - 2Lj;. *12.a46*-,,,-:_'.._c-98T~o912' .- o:~638s1*<* : 0.04654-> :*-;' ":'_o:~'';;**x,;o~a46s4.;: * ,.*
| |
| _\. __
| |
| *:: ':* .. ...
| |
| * I :
| |
| *. **.
| |
| -- . ,_
| |
| .. -
| |
| 1'' ., . *,'* *. *:
| |
| ...... " ...... _
| |
| ...,, -_. "
| |
| . ._. .... \' .. ~ .~ ..
| |
| __ ; ~ :
| |
| *,._:. **:.* .
| |
| ;
| |
| - ..' ... ,,
| |
| **' .** .:_.( .*
| |
| ~.
| |
| .* '."'
| |
| *-- *-* . *,:*
| |
| ~:' .
| |
| .*..: .. :* '** ..
| |
| .}."~;;,!:; /;*.:<
| |
| | |
| ,;,
| |
| ~~-.*;- ..
| |
| .. ;* ... ': -. -~*:
| |
| : *.-( .. ,- *.:**
| |
| -:~'
| |
| .- * .. *
| |
| \..~
| |
| ~~1 Table*4.3~24b (cont.)
| |
| OPPD
| |
| :, ~, Ft Calhoun Unit l Reactor Cavity Subcompartlnent Analysis.
| |
| r-~1 *' Junctions
| |
| ( _, Junction* From**
| |
| VoL Vol _ - (ft2)_,
| |
| **-- *:*
| |
| . *.,*.
| |
| Tc) *
| |
| * Area'..** - Elevation - .-. L/A: -
| |
| (ft) (ft~l) Forward K
| |
| -
| |
| Irreversib-le L~ss:.:* Coefficient. *. ** * *
| |
| -
| |
| -.
| |
| r
| |
| -, ..---*
| |
| .
| |
| _ .... _., _< -~yerse> K <.**:<; ?;
| |
| *.*Number l--, . SL. ~1<;- ** ~1~:'*:.-/* 6~6u~'i . '987';.0912*
| |
| * 1.25558 : .* 0.1969:
| |
| * T%.;:t:.;t;:~*~4ii5 ?,r>'.*~*<
| |
| * .
| |
| * o.s422s'
| |
| * 52 22 28 .. 6 .6181 987 .0912
| |
| * 1.2SSS8 0 *.7969 ~/ ' .
| |
| 53 23 29 7~8192 987.0912 1.07862 0.73452 o*.52208.
| |
| :*::1 54 24 30 6.6181 987.0912 1.25558 . 0;7969 o *. 5.4225 55 25 26 20.619 980.685 0.39784 0.01176 '. 0.01176 l.I 56 26 2T 20.619. 980.685 0.39784 0.01176
| |
| , **
| |
| 0~01176-6:~ oi:116 *
| |
| * ST 2T 28' . 20-.619* 980~685 . 0.39784 0.01176
| |
| ~I 58' 29 .
| |
| **
| |
| 28'. .. 20.619 980.685 0.39784 0.01176 *.. cr.01116:'. .
| |
| . ' . 0.~01176.
| |
| 59* 30: . 29"' - 20'.619' . : 980~685. . 0~39784 0;.01176' - .-:*-,
| |
| *'.*'
| |
| * ..
| |
| :_1
| |
| ,,
| |
| 60 . 25 . . 30 . 2Q.619-: 980.685 0.39784 0.01176 0.01176 .
| |
| 61 25 31 35.422 980.685 0.10016 0.70304 0.42311 ..
| |
| 62: 26 31 34. 652 . 980. 685 0 .10217 0 *. 7107 0.42657 63 27 . 31 35.422 980.685 0.10016. 0.70304 OA23lL 6~ 28 * *31. 35.422. 980:.685* 0.10016 0.10307 . o*;.42J1t.
| |
| ~ _I
| |
| ::::~. ::.:::~. ~:~~~~~ ~: ~~:7 .**
| |
| * t'* 51~\~~*~ri~~i~ * *
| |
| .:_;.
| |
| :: * * *. . .* ~~\ <:~
| |
| *.
| |
| ! . *.* * ** *.* * . *. ... *
| |
| :1
| |
| *. ,
| |
| . .. ~- - .' ,: : . . *- . - ..* . . . ~. .. ' ~ - ,.
| |
| 6T . 31 33
| |
| * 57.33- > * *916~~5.
| |
| * 0.22413.-
| |
| * 0.0914 : 0.03534
| |
| '-* *
| |
| * 994~*0*
| |
| . :''..
| |
| 68 .33 36
| |
| * 50.31.. 0.20699 o. 9955 0.51124 **
| |
| *~1 . * .::> t,~,¥ :~1,~:;~~i~m':;',~~h~~~:~
| |
| 0
| |
| .S061& t,~~i~r ),,'.'."'~~r1t;,tl~;~:~ . ** *. ** **
| |
| ~I
| |
| *.. 1r.:*.*. *. 9::*.::'YC'.3s:::, ;~:i~.6:.8874>_r"too4*.75*.* :r.0114. _ * *:} *_*,. :*:*0 *.50901**.-
| |
| . 12 > *
| |
| * ro
| |
| * 3s' :. :** 6*~1.61.T:< 'ioo4~,is *= > o*.50616 , ... i. 00191. . .. *'.*':: *~ io. 5145z *
| |
| ::.~* 6:8874-'._: 0~27292*
| |
| -1
| |
| ... _1 73.
| |
| 74 lL 12...
| |
| : 35*
| |
| 34 6.8874 .. -1004. 75 1004.* 75 . -
| |
| 0.27292 i*.0114. .
| |
| 1.0174
| |
| < _,**.*
| |
| . :o.so901
| |
| *o.50907 36 2315;.9 1013.0 0.01698 . 0.26588 0.25932.
| |
| 75 32 36 611.14 1056.5 . 0.05923 0.83722 0.47356 76 34
| |
| .. ::.
| |
| .. . . . *... . *, ..
| |
| . ' .... . . ... '
| |
| ;*.:_._ .... *.. . *.* . ., . ..... ,_ ..
| |
| *". ,\
| |
| . -~*. ~ ---~/~_*.
| |
| ,-.~fa::::; .. .r3 ~.*> ' ~: ,.
| |
| *-. *-------*-:---------.--. ____ :...---*-----~-- ---.-------,-- -- -**---;:---:-,,-.......--- --------- ~---:---*-.-.-.-,.--~-.--** . -** __ ,. __,_ .... -: .........-~~:_.~ _ __,_;__ *__ -~-.,......-*...~---.~--~........... "" .----*
| |
| | |
| r-.
| |
| I I '.
| |
| Table 4.3-24b (cont.) 1*
| |
| OPPD
| |
| ; '.
| |
| Reactor Cavity Subcompartment Analysis Ft. Calhoun Unit 1 I
| |
| \ } ' Junctions
| |
| * I Jtinction
| |
| * From Number Vol To Vol Elevation (ft)
| |
| Irreversible: Loss Coefficient.
| |
| Forward. K .. Reverse: IC. I i
| |
| 1T 3$ 36 .. 611.14 1056.5 0.05923 0.83722'
| |
| ', '
| |
| i
| |
| : 78. 7 32 8.125 1005~75 0.57373 1.35641 r-- 8-.15 1008.6 0.49134 1.37775 79 8 32:
| |
| **-. 80 9 32. 8.75 1008~6 0.49134- 1.3775
| |
| ,... 81 10 32 8.125 1005.75 0.57373 1.35641 i
| |
| : l. ...* 82 11 32 8 *. 75 1008.6 0.49134 1.3775' 83 12 32: 8.75 1008.6 0.* 49134° l.3775 r**
| |
| !- ,*
| |
| -- -*,, '
| |
| .._*, .. ''
| |
| *.* ......
| |
| .-
| |
| * I' *
| |
| ' - '
| |
| r-.. .* '*
| |
| ''
| |
| ---
| |
| __.., -*..,* .... *- - ,. . *- - ---- .. ,_ -*- ...
| |
| .*,.:* ..*.. *
| |
| .<* :*- -: :_ *_.- . .--:
| |
| \ . : -~
| |
| ... ' ~. .,, '.*
| |
| --. :' ... : ,~*, :- :- ..: ......-'.* ::. ' ... ,*
| |
| *'
| |
| "'
| |
| ***,.*'
| |
| .. *- .. .: . *-
| |
| ":
| |
| .
| |
| ;
| |
| :, __
| |
| .. :*-*_*:* ....
| |
| .**",
| |
| ,..
| |
| i
| |
| . r**
| |
| I
| |
| '
| |
| \.
| |
| '
| |
| _. Note: . Junctions 78 to 83 are the sand plugs.; . See text *.
| |
| . L._:* I
| |
| ( *.
| |
| -1*\
| |
| i.._.
| |
| | |
| _,_*.
| |
| . .;. *. .,,,*::
| |
| .*-*:
| |
| ........ :.: ':_
| |
| ...
| |
| Table 4.3-25a B. G. & E~ Calvert Cliffs Units 1 and 2
| |
| (] Table.of "Projected.Areas" and Lever Arms
| |
| ;~I .', ' **.....
| |
| . "* ,,
| |
| *. ; - *. ,* -~ .'
| |
| r-1 .
| |
| j .
| |
| .Level Number Pressure* Di.ff erential *.
| |
| * ti --. Vol:~ ii) . _
| |
| '.-
| |
| r
| |
| \
| |
| I
| |
| ..
| |
| 1 8. . 2' 7383.0 0.33335
| |
| ~1 9 T
| |
| 3 1
| |
| 7383.o 5163.3 10" 4 5404.8
| |
| ~-1 ';.
| |
| 6.-:
| |
| "ll -*.
| |
| 12:
| |
| :5:. ;.
| |
| . 1889"e9 1978.3' I \ . .'
| |
| ****.:
| |
| . ?;". :13;: . 7599.8 -13.1665' .*
| |
| :_.11 . 15:'
| |
| ._.**14,.:*;****
| |
| *7599.8
| |
| ! ~-.
| |
| .**' 15200.0
| |
| :*;'.*~ ..;*. *-~. ,,,. :::.:.::* . '
| |
| !'**1
| |
| ':
| |
| 24 19>
| |
| 21.
| |
| **.*: 3544.I.
| |
| 3544.1 23 20: 7088.2
| |
| ... -. *.*.
| |
| I I
| |
| ! ... ,
| |
| I, Ii *
| |
| [ \_ "'.
| |
| i*;I
| |
| \.
| |
| ;rl I' IL.
| |
| *1
| |
| '..__:
| |
| .... , *.. ~- ***~-~~** :.........-.~*-**:--'*-- --- -**----:'*-----:--.....:.--~~-~-*---;-*-. -:--***-* -----*---~-;----:----,.---- -~
| |
| .. : ,.,* ,1*'.. .. "-:> ..... *.
| |
| *I
| |
| | |
| I !
| |
| ( -,.
| |
| Table 4.3-25a- (cont.)
| |
| I '*
| |
| B. G*. & E. Calvert Cliffs Units l and 2 I
| |
| '*;.*
| |
| I ..
| |
| *'~*
| |
| I .
| |
| (_ i i
| |
| 1..
| |
| .........
| |
| *, '
| |
| ...._.
| |
| | |
| :' . ->";* _i',, .*
| |
| ' .. - .
| |
| I ,_.,- ,: ,,.:.,*.
| |
| * .. \.
| |
| *. -: . . ~ ' "; - .. - *-..
| |
| :. .
| |
| *,
| |
| ~ ~-
| |
| '
| |
| .-
| |
| '.:*'
| |
| . *-"-
| |
| .,_, .... ., - .
| |
| I Table 4.3.25b I
| |
| .NORTHEAST- UTILITIES
| |
| * I
| |
| . _,-' .. *' ,*
| |
| -. MILLSTONE NPS fl2
| |
| _Table of Projected Af:eas _and Level Arms_
| |
| I I *Level Number Pressure-Differential (Vol fl vo1 fl)
| |
| Area-I X;..Direction.
| |
| 1 -8 5372~0 -* 0. 604164 .
| |
| :I '
| |
| 9**. 5372.0 I "7' 10
| |
| -*
| |
| >*-
| |
| .-'' . _3692~9 3932 *. 6*
| |
| *-: .6-;*. *-.1351.T .
| |
| I *. - IL --* 1439.4
| |
| . *. ~~:. ,. "**'~;~;;;~~'¥}*.
| |
| ,* .2. . 9048. 8
| |
| . ,,. !," 9048'~ 8 I 22t .
| |
| 24.
| |
| **.~ *.19*... '.
| |
| 2l..
| |
| -.- .. :18098. 0
| |
| -_*3544. l 3396.5
| |
| : 23. 20 6'792.9*
| |
| I I
| |
| I I
| |
| I
| |
| . -: -.-
| |
| I
| |
| ,:_..
| |
| .'**
| |
| z;..Direction I 1. l 2
| |
| 3
| |
| .. 31
| |
| - 3l.
| |
| 3L 601.88
| |
| _601. 88 601.88
| |
| -4. -~:~:-::::-':-::*c3r7:~'.--:~:-:--::'*-:**-*::-* 60r~*as-~-- --~--:---*--c:--:-;-~--=-~-~-- -- .
| |
| I :- ..
| |
| *. 5-.*
| |
| 6 3L 31 .*-. *
| |
| .I;.
| |
| -~ .
| |
| -_601.88
| |
| . 601. 88
| |
| . . .. - 1.'
| |
| *'- ----- :.',:.. T- .... -* .> 31:- - -601. 88 *
| |
| >*-*. '. *.*:-__ .:,, *_-'
| |
| I . -... - ' -. *.~*- ~* .
| |
| *.;,*
| |
| :': . : *-~ ' - :,t-3.;*~\~';_:-_:* .~:~*:.*.:.
| |
| .:f ;~:-,;~; ;:::.~,:;,;;c:.};?~t::?-:;>'. <'. '
| |
| -. ~
| |
| :-*<::>*::~.:!
| |
| ***** ***---~- -~--- -------. ,_. . . . . --~
| |
| | |
| *-'**. ::* 'i:.
| |
| :*.,,* ...... ;,*
| |
| ''. --.
| |
| Tabla 4-. 3. 25b NORTHEAST UTILITIES I
| |
| MILLSTONE NPS tf2 Table of Projected Areas and Level Arms (Continued)
| |
| I
| |
| ..I, Pressure.Differential ~'.t"oj ectzd* Area;
| |
| 'Level Number (Vol ti* -* Vol ti) .* *(in . ) :
| |
| ....,> z~riirection, *
| |
| *.,.:*.:
| |
| 3
| |
| .... ,...
| |
| ..*' . .
| |
| I
| |
| ... ,, '. .-*
| |
| " ,:* ~ .....
| |
| ... :*
| |
| *.: .. *
| |
| '_*. .I .. ..
| |
| -._.
| |
| .. -~* " ... - . -*' .. : -,;,; :.. *-*,, ,*,
| |
| - ., , . :. r~ -~. ,.
| |
| ... .t: ** '
| |
| *. *~ ... ,*
| |
| | |
| - *.' .: ... *. . .*.:
| |
| ....
| |
| ,_*
| |
| I .**.
| |
| * *c,
| |
| ,.
| |
| * *.\ ;.
| |
| .. ; .~
| |
| ' "coi-tSmmRS
| |
| '
| |
| POWER.'
| |
| I . TABLE OF "PROJECTED AREAS" AND LEVER ARMS PALISADES PLANT .
| |
| I Lever* Numb.er Pressure Differential I
| |
| Projected Area Lever Ann
| |
| * *. (Vol No. -*Vol. No.} . .2) .
| |
| ( J,.n.
| |
| I x~direction '
| |
| ''*
| |
| * :Cpsia)*
| |
| '(ft)
| |
| *.,*. r .. ' 6991.917. l.4778T.
| |
| I* ,' ': .. 2~* .*
| |
| .. .~* ... '
| |
| .73ao.:12-r
| |
| .., ' .
| |
| .. -. :>..
| |
| -..
| |
| . :;-* *.
| |
| :'i': :isS4t~.i9'' ',
| |
| ";' .. ~* - .
| |
| *, >-11._2'+/-8 7 :
| |
| I
| |
| ,-* . . ._:- .. _-;**,,_**
| |
| 11>;,_-:< ''* > .* :8 ' *' ,, ' l554l.~79 3 '.1'6. ' ll 5843.363 -23.02343 I Y-direction lT * .14 '58.43.363* .*
| |
| 1.* 1
| |
| ' . ;5*~ " .. *, ., 2::
| |
| 1 ; *4036.785
| |
| '-4261.262
| |
| .,
| |
| . .' ~* .
| |
| :. . .'
| |
| I ' '.z'
| |
| ': **. .:__ *.. :.-.. ;. ' 6' lff.::*.
| |
| *.*.**.
| |
| '*3; ' . " 8073.570
| |
| '*. ,:,..c:.8973.059 .*
| |
| :-.
| |
| *. . .
| |
| . *".
| |
| *-.. :* '
| |
| ..
| |
| **. 11':
| |
| .*I
| |
| ;.,*.
| |
| .. : ,. *:, .. ,
| |
| -*,_.. -
| |
| "'
| |
| 9'** 12' 17946.12 3 16. 13 ' 337.3.667 ..
| |
| I
| |
| '
| |
| ;; . - .lT '.14 *. ;;;;3~13:. 667
| |
| **.. '
| |
| 6747~334; I ..* ,, ***r:.*.-*
| |
| *.' : .. : -, *:.
| |
| * ... _ ..
| |
| .I '*
| |
| . _;*_ *'*. i*:. _,_*
| |
| 1*
| |
| . :* ****~ :< *.. J. _,
| |
| *. :.~. ;. '
| |
| ., . . * ..~:'*'
| |
| .;J_ ~--i
| |
| *
| |
| -** :-1
| |
| . .. ~ .
| |
| .,
| |
| . :.. . -i. I
| |
| . .. :*
| |
| | |
| OPPD -- Ft Calhoun Unit *1 Table of ":Projected Areas" and Lever Arms I
| |
| }>r~ss~re,. Differential .
| |
| .3'
| |
| | |
| *.~
| |
| .** ::)1
| |
| *,
| |
| - *.,.*
| |
| I Table *'*4*.3-2Sd (cont.).
| |
| *I OPPD - Ft Calhoun Unit l I ::Cable of 11 Proj~cted Areas" and Lever Arms Level Numb.er :Pressure Differential I *z-dir.ection (Cont'd) -
| |
| (Vol i/: *
| |
| * (ps.id)
| |
| Vol 1F)
| |
| * Projected.Area'
| |
| . 2) *_.
| |
| ( in...
| |
| .Lever Ann
| |
| .(ft) ..
| |
| I .::*, -' -*
| |
| ~
| |
| . -.
| |
| 29:'.
| |
| '. ;*~'..3Qc. .....,
| |
| ' ..'-: . "
| |
| .'32: .,
| |
| ';
| |
| : 32. . -.
| |
| 3094.3
| |
| .. 3094-.3 ..
| |
| ,*3r* :.32 3094.3.
| |
| I 28. .. 25 3094.3 29 2'6 3094.3.
| |
| I 2.7 30 3094~.3 I
| |
| I *-. ,,*
| |
| *.',;
| |
| *I . .. :* .-
| |
| *:',i I
| |
| I 1-
| |
| .1.
| |
| I I
| |
| I
| |
| *- --*-*.------* ___________:.,:_______ ------.....:.....-----~-- *-- ~---: *-*
| |
| ': .... *. -*
| |
| .. ***.-
| |
| .
| |
| I -*-.*- *.*:.
| |
| .'.. .. :**
| |
| '**.
| |
| ...
| |
| * _-,_.,:
| |
| . . ; . . . ...
| |
| 4':* ~* *'<'
| |
| '{~ .. '."*. :- ': .... '.'
| |
| *.* .. '. ;>>**'' ..
| |
| . -*- - - *----.--*--- ___________
| |
| "* ..:,... _______ ,,_
| |
| | |
| ,r:J..BLE 4.3-26 'I GONSUHERS POWER PALISADES PLANT TAB'LE .Dr' MODIFICATIONS FOR "CSB TYPE'' MODEL I.
| |
| A. - Revisions to Volumes (See Table la) I Volumes 1 to. 6 divided into:
| |
| . . 3 .I*
| |
| Volume:* No.
| |
| . l, Volume .. (ft )
| |
| . 135.06:
| |
| Height (ft)
| |
| . 6.2917 .
| |
| Eleva ti on (£ t).
| |
| 618.2083' .
| |
| ,.,
| |
| 2- . ' 140'..87" . 6.2917 &la:.2083 ,
| |
| *3 135:,06 *.6~2917' 618.2083 ......
| |
| .* .. .'
| |
| ,.*:.*.
| |
| . 1'35.06 6.2917 618.2083 4
| |
| 5 6
| |
| 140 .. 87
| |
| .135.06 6.2917 6.2917 61&.2083
| |
| . 618. 2083 I 614.8724 24 25 6J;.263.
| |
| *. 69.073.
| |
| 3.3359 .*
| |
| 3 .. 3359: 614~8724 . .1.
| |
| *. '63~637 3:.3359 ... 614.8724 . '
| |
| . 26,
| |
| *-1.-
| |
| ,,.
| |
| . 63 *. 63-T 3*.3359 . .. 614.8.724 .
| |
| . 2.7
| |
| .' . 614:~.8 72l~- .. ..*****
| |
| '
| |
| 28: . :. '69.073' .* 3*.3359:
| |
| 3'~3359:. 614.8724-.
| |
| 29
| |
| -* \
| |
| I.
| |
| ,.. *;I,:;
| |
| *.,:::';.,'.;:;~.;;:**
| |
| *",_.:,1:-*.,*,
| |
| ***1***
| |
| .
| |
| -.'
| |
| ~ '- : . -.
| |
| ....
| |
| ,., ~ :*. . -
| |
| "
| |
| - *.*.,.. :.
| |
| - . ,-_
| |
| -*-*- :' *-
| |
| ,,;.' .. * . -. -_
| |
| **1*
| |
| I
| |
| *I.
| |
| 1*
| |
| ...
| |
| .4-** 3. 6-z.-
| |
| .,
| |
| | |
| . .-.~-*.. *.
| |
| .. *. > 1 I
| |
| . _':- I
| |
| : * ,TABI,E* 4.3~26 (cont.)
| |
| * I ** *
| |
| . :* . . ..
| |
| CONSUNERS POWER I . PALISADES PLA:t-il'
| |
| * TABLE OF* MODIFICATIONS FOR "CSB TYPE' MODEL I . B- - Revisions to Junc.tions (See Tab le lb)
| |
| I J"unction Number
| |
| -From*
| |
| Vol
| |
| * 12._ . -*Area ..* Elevation*
| |
| Vol ** _ (ft 2 ) . (f~)
| |
| L/A
| |
| -1 (ft . ) .
| |
| Irreversible Loss Coeff *. *
| |
| * Forward. K. .
| |
| . ~.
| |
| I *1 2.
| |
| l' 2 ..
| |
| 2
| |
| :3.~
| |
| .. .*
| |
| 11.404
| |
| ';ll.404 .
| |
| 620.0417 620~.0417 0.59391 0.5939!:
| |
| : 0. 301366<
| |
| 0.301366 .* .
| |
| 0 .301366
| |
| ,o *.30i366 ..
| |
| ' ,: - : -..
| |
| I 3
| |
| .4
| |
| .3 5
| |
| 4.
| |
| 4 10.218 11.404 620.625 620.0417
| |
| . 0.60409*.
| |
| 0:59391 0.301366 0~*385131 0.3013.6.6
| |
| .0.301366 0.301366 I :6
| |
| : 5. 6 1
| |
| 5
| |
| .6-11.404
| |
| . 10.218 620.0417 6200625 *
| |
| . 0.59391 0.60409 0.38513L 0.385131 7 1 20 20.155 624.5 0.13856 . 1.09331 0.55614 I 8 2 20 20.155 624.5 0.13856 1.09331 *. 0.55614 9 3 ..20* 20.155 624.5 o*.13856 1.09331 0.55.614 : ..
| |
| I 10 4 20: 20.155 . 624.5 0.13856
| |
| .. 0.13856 .
| |
| 1.09331 *. 0.55614' .. ..**
| |
| ~
| |
| ,,. ;._.,*,
| |
| '
| |
| S' 20, .. : 20.155 625.5 1.09331 *. 0.55614 I ~ 6 20* ... 20.155 624.5 614.8724 0~13856'.
| |
| 0.60238 1.09331 0.57336 0.55614 0.56152 13 24 7 12.87 I 14 .25 8 12.406 614.8724 614.8724 0.60238 0.60238 0.57336 0.57336 0.5.6152 0 .561:52 15 26 9. 12.87
| |
| *I. 16
| |
| . lT.
| |
| 27 28* ..
| |
| 10 .... -12.87 tL* ..
| |
| . 614.8724 12 *.406* . 614.8724 0.60238 1.60238.
| |
| 0 *.57336
| |
| *
| |
| * 0.57336 .
| |
| 0.56152 O~:S6152: .- .....*' -
| |
| . ... ..
| |
| 1*
| |
| . .
| |
| 18 .29.:.. 12: 12.87' 614~8724- 0.60238 0.57336' . 0.56152 48 1 . 24-* -* 13~666 618.2083 0.21833 0.48365. 0.48876' I *. 2 25 . _14.852 618.2083- 0.21248
| |
| * o *.42001 0.42452 49 . . . -:~ ;
| |
| *. 50 . *3 26 * * *
| |
| * 13'.666 :.,* ... 61s.208J .* . 0.21833 .. 0.48365 0~48876'
| |
| *,,.* ... * .* \*. *' - . ~ .. ./"' -.* . -. . -
| |
| . *51 . 4, .. *'13~666:*. 618.2083 0.21833 0.48365 . .. 0~48876 .*
| |
| .I:: 52: ,5, .. 2a * ** .
| |
| * 14.asz*" * - 61s.2083 *
| |
| * 0~2124s. 0~42007 .* *.
| |
| ..
| |
| 0~42452.
| |
| . .
| |
| : ;,' *.* ...'.-*:
| |
| . 6: 29 , :.- . 13.666.
| |
| * 61s-.2oa3 0~2'1833 o*.48365 * *: *o.48876
| |
| . *.** -..
| |
| 24.** . 25* . 1.51324 614.8724 1.66333 *1.12831 . 1.12831 .
| |
| 25 26
| |
| * 1.70224 614 *. 8724 1.58996 1. 08197" 1.08197 55 I !~
| |
| ,
| |
| : 26. 27 0.79954 614. 8724 . 2.2532 1.31182 1.31182 28 27: . . 2.88824 614.8.724 1.34873 0.81280 . 0.81280
| |
| . **29. 28 1.51324* 614.8724 1.66333 .* 1.12831,.. 1.12,831
| |
| . -- -~:~ : I 24* 29 .2.88824 614.8724 . 1.34873 0.81280 o*.81280 I -:*'
| |
| . :* -~ *_, ..
| |
| **.' *... *-
| |
| | |
| --*~*: ...
| |
| (cont~)
| |
| . CONSUNERS POWER PALISADES PLANT TABLE OF MODIFICATIONS FOR 11 CSB TYPE" MODEL I.
| |
| I C -*Revisions to "Projected Areas" and Lever Arms X'-direction **Pressure Differential
| |
| . ",.
| |
| 2 . 523.7.124
| |
| . ' .
| |
| y;...direction, .Pressure Differenti.al A:rea *Lever,
| |
| .. 2 New* .Cft )*
| |
| *.I .
| |
| , ..
| |
| | |
| lcf-- .-.,-.~. - - *-.--~*-:----* ..:-..--:.-:.-~__ ,- ___.:.:_ __;_ -*-*:';.__.__._ _ _ _
| |
| . . . .* * *. Figure* 4.3-ai: .
| |
| . . . \
| |
| * --->.:_,_.:....:._ __ _- __ ._ .._: _____. -:_,-..-.....:..:._::.....,:..__..;,_. ___ *..
| |
| : . :* .* *. *,: ': .*
| |
| Baltimore Gas And Electric .* *
| |
| * 1;'
| |
| l.... * .i Calvert Cliffs Units 1 And 2 Reactor Cavity Subcompartment Model J:
| |
| ,,\..
| |
| '*.
| |
| ; SCHEMATIC SECTION SHOWING VOLUME NUMBERS
| |
| ,* . *-
| |
| I- .~ ' .' ' .* ' : ~,
| |
| ..
| |
| *.** *- - :. ; .. :- .
| |
| .37'(UPPER CONTAINMENT):.*.
| |
| I:*. .:;*,.":,
| |
| *: '
| |
| . - - ------ --*- - - -*-
| |
| 35 I:'"
| |
| . NEUTRON SHIELD t:::::==============!==================:=::iEL.~.292
| |
| . .. : __ -_;* :1 . .
| |
| \ ...'
| |
| *.*34 EL. 44.0 (SEAL EL,VATION)_ .*~
| |
| * 1* 36i . . -:{+l *.* .* . '
| |
| . ,::I * . ,* * ,
| |
| ...* * . ARMSi *
| |
| ,. ~-:
| |
| MOMENT: * * .
| |
| . . _- *, .
| |
| ,,.
| |
| I.
| |
| .l'J 16.
| |
| Ir
| |
| '*.
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| I :
| |
| :.:. ._***...
| |
| ll 1**;
| |
| -~* :_**.
| |
| 1--_._-1---+--l---+--il---t--il---+---ll---+/-----I.
| |
| 22 19 20 21
| |
| .r
| |
| ~..: 17 5 (TANGENT LINE OFRVI LEVEL3
| |
| __.EL.aL1~~~0*
| |
| 1.*;
| |
| * : .* . . <:*::*....- -..-.. . ..._;- _. _.-._-.-.. ,:-.__,._-*.-. .*-.*-*.-::..___,. ___--;.,_. _..__**_*._.. _*. _..___
| |
| IJ .:_/** .*.** _*'t<~::*::,~i}'~S:*~.:i....:.*:t,.,;, *. '* *-* ~. ..
| |
| .. _. ___ .------ ...:---~~=--~=~-*--*__-:::::.::_-:::-::-:**::::-:-:-::::::-.=:::::.::::.;::__ : __*.: .*:..--:::::_::.:..*. .:.:..-*---*- ---*- **-*~--**
| |
| -.-*-**--****** -- . -* .. -- ,...-_
| |
| . ., ---*-*-**--, - . ----
| |
| **-* *-- ***- *-* - . -- . . --* ...-*-**--
| |
| **---*-***-**-****,"-** ---* ---- **-*-**n-
| |
| --' **-**** - -- . **--**-*,*
| |
| - -** - **--* ,.,_. * .... *-.--,*-****--*-* * ** ., * ***
| |
| | |
| \
| |
| \ !
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| I
| |
| :'*:*, -.*-*
| |
| ~,.. . .-** ' , .- ,:- :" .**~ "
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| * i-
| |
| * Flgure.*
| |
| *: ** * . . :~,_- '
| |
| *4.3-a2 * * . *. : **
| |
| . \J1;;~:1~"
| |
| '-. Baltimore Gas And Electri*c Reactor Cavity
| |
| * Subcompartment Model I Calvert Cliffs Units 1 And 2.
| |
| / SCHEMATIC ELEVATION SHOWING* I
| |
| : '
| |
| VOLUME: NUMBERS
| |
| ' . . ':: . >~ ~ '* - .
| |
| ' . __ * . _ : '
| |
| * t
| |
| '' .;*** ,.,:-
| |
| *.. -..
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| *;. '. 2*'_;.. '
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| _.. *:
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| ' j i '
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| . *; .*.
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| '(* -
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| -I ,.- * * *
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| . .*
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| r ...
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| l '
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| I
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| \.'
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| .* I L. .i I .
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| \.. __
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| ' J .
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| ''
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| , .*. . -. -' ' ..:~-. . .
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| '.* . ' *. ''* ,:*
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| | |
| .. -*-** --*--* __ ::..__, - --'.*~* _____..:__... ___ ,___ .____________ ..,:..__ *---*-** -*--*-ff*.;..*-----*--*-----__:,.. _______________ ,_~---: _._, ______ ,_;_ .,..... ----** *-- .. --**- - - . -* .-.... *... , ....,...... .-*-
| |
| ~
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| **----~---
| |
| . . .. . .
| |
| . .
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| I ~ *_ ::----F-igure .-J....-53-- - - --- -
| |
| ---------------~
| |
| MILLSTONE 2 I Reactor Gavity Subc_ompartment Model
| |
| * SCHEMATIC SECTION SHO\'\/ING I . VOLUME NU~JIBERS I *- .. *
| |
| .**.*.* *-*** *:*.::::-*
| |
| _ . -*-. __*.. * -* 3{,(UPPER CONTAINMENT) .
| |
| I .--~- ..::~. _. .:.. -1 '***
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| : * ..
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| *.-*::
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| *;'
| |
| ...
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| *' _..
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| ,-* ..
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| . **.-':e . ~* '* -* .., . . *- ..-. ''*' ..
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| I
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| *,-. ' : ** ***,.: *'<'
| |
| **.*. _*-,_... *...
| |
| *. ** * . .':'*
| |
| ....,* ..
| |
| .. 31 NEUTRON SHIELD I
| |
| I
| |
| .. (+I ; .
| |
| I MOMENT.
| |
| ARMS.
| |
| *-,.
| |
| . **:.~*-..:.....; _____ ..
| |
| I EL. +~.O EL. 5. 333
| |
| - "~,,-._._-**
| |
| MOMENT ARMS*
| |
| I *, t SU I ..; l
| |
| ' ...... '
| |
| I 13 14 .. *.*IS'. . I~ IT rs- - LEVEL2 I
| |
| I ,.,...
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| .*r
| |
| '" ".".,
| |
| ~ . .
| |
| 1----¥---""'--l--+-_._+---+--+--1--+---+--+/-"----t ~1:! 3.87S{TANGENT LINE I . 22 OFRVI 23 , 24 19 21 I LEVEL3 I . . __ __,___ _-..1.._ ___.__ ___.,____ _.....__ _ _ EL.-~ls
| |
| . ! . .* *--
| |
| (BOTTOM OF
| |
| * CAVITY)
| |
| I '*. .
| |
| *
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| .'
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| ,*_..
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| *
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| .r '. -
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| - *.-:
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| "'* . ..
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| . ..::,
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| .--- -----~- _ :_ _ ---- --~~------ _:__* * --~-~__:__: __:__:_::~- ~-~:-p; ~-- ~1-~~-~~_:~~:Z::-==-=*=-*-~;~:--=:_-~:-- _ ;_'.~=:--~~:.;:-~:*.~~_:~_-:: :__ :::_:~.-:=::::~_.;;_:_=: ____ _: ~-___ -.::- *.
| |
| | |
| :*""*
| |
| :;_
| |
| --***----". .*----p . ~-- --*---~--- -* -*
| |
| FIGUBE 4.3-84 SCHE~JUl.TiC ELE'Vl\T~Or'i SHO\l\HNG:
| |
| VO t...C u~l]l:-
| |
| 1tia t':. f'lUMBERS
| |
| *1
| |
| .,._.
| |
| '.
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| ..... ....
| |
| ...,.
| |
| 33
| |
| | |
| ..- *-*- .....--**-------*--.-* _____ _.:...... .:.:. ........ ___ ____
| |
| .., __. ..
| |
| :,_,,_~~--*-**.:. -;~* .___ ..:.._.*.~- *-**~,--..:_ *--** .. *-***---*-*--------****------*,* **::""':f~ .,:;..;**.*.* *****-**-...**-'--*-* ----:-**** .,.., ... ~-*:* . ****~:-:*- -. --*
| |
| *:* ...
| |
| ...
| |
| -..
| |
| I *.'
| |
| *(**
| |
| I Figure 4.3-85 CONSUMERS POWER I PALISADES
| |
| 'ffi *,
| |
| I I
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| *1 i I I !
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| I!* lI I
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| iI I * ; i ;.. * : : H l ; ~ I ---~-.-
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| ju i i !
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| II !
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| * 1 I L"
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| --*------,- ' ' ' !' I : I' ' I '- : -. ' - _ ;- * - ' - -i: . ' I I I , : . --'--*------'----. : , - t i . -,- , , ! .
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| ** :
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| -i~- I *: {~ '. ,*.: 34 .
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| +--_ _...___ _ _ _ _ _~-~~.---~.-+--BOTTo:vt:OF**ev---1 --:-
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| --, 41>---.-* __ _;_lir4-;-. 4k---- *!---~+-+~~-~-r---f.---J-
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| -.-:-* ~ ~~n~~~ 1~~
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| -- *---~.:.---------*----*-**-**
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| , __ . *--.~**-*~--._~-.-.- . -- *-----------*---------
| |
| ~-':"'",-...--~- ....--";*:-*;:~-~*-**--r***-.- . "7"'"~'*--:;<""'":'"*--***;---.-**-.-,-;,*- rr**.**,.-*-~_.,,,.._;-:-'-*-*-*;*-;i.-i;-rw.,..,,-;,..""''"':t:''-*-.-;;:--:...-::~.-1;::*--_,..-::*~-;-:--'::.~-.~---;-.'':"* ~-*'T>r.';'",,..~..,M~,-;>.~'.,~*~,:~"':*>;",~*;c~;~*-:<71-;. '"~"-<'*""'*.-:-;".""l'";**"';""""
| |
| | |
| Figure 4. 3-8 6 CONSUMERS POWER I
| |
| PALISADES fLOr.V :r~ *To PENEnZAT10A;).s:.
| |
| _ ---NO N~oTf20N $.HIELD~-
| |
| . , - '" ' _,: - .. -
| |
| <\~r-*;.,t£1~n IV/~o..r~ Pra.t:.t
| |
| --:,q.con~IZJ'\1L~-pawcr el1;!1cr
| |
| '. '*. '*** ~~*,,. \1 . -
| |
| | |
| I
| |
| *1 * . FT~*"CALBOUN
| |
| _ '. . . ._ .: . .. _O~P.,P~Il~~ . . _ ... _,. <., _ _._, __ , _ ,. .
| |
| UN!T'"l REJ~~CTOR CAViTY SUBCO~.i~PARTi\~ENT rJrODEl SCFlEriliATIC 'SECT!ON SHOVVH\!G _ _ VOLU!ViE NUrv1BERS I
| |
| I*
| |
| I I .34 I
| |
| I
| |
| ,- .
| |
| I*
| |
| I
| |
| .-~-
| |
| *I:
| |
| i*
| |
| | |
| FT. CALHOUN UNIT 1. REACTOR CJ:\VoTY SUBC,.O.MPART.r~ENT r~10DEL, scHErVlATIC ELEVATIONSHO~VING. voturlt1E* NUftriBERS . . I
| |
| .-
| |
| | |
| .I.
| |
| I I
| |
| . . ' . ~** _;~
| |
| I
| |
| *'I I.
| |
| ';.
| |
| ,,_, ..
| |
| ..
| |
| I /
| |
| Vent Flow-Top Plate
| |
| -*Head-I I -* Shield Tank -
| |
| ' -~ :** '
| |
| I BottOm Plate*
| |
| Pool I
| |
| I* ... *,.
| |
| **I .*. '.**.:
| |
| I**
| |
| ., FIGURE 4.3-89 SHIELD TANK CROSS SECTION ARRANG:EMENT I . ~: ;:_~ .:~C .. *-..*-*- '.._f.-~~'':.l?_. .. . . , ' *. ' ..
| |
| .. **----***- , ... _.. * * - - - - - - . - .-~*~*-.. *--~ .... -.;..... , .** ~-*. *****----.* **---... ~ - !P':
| |
| | |
| Fi~re* 4.3-90 MILLSTONE 2
| |
| '
| |
| NEUTRON STREAMING SHIELD AREA OPENING VS. TIME
| |
| . :-:
| |
| t*
| |
| | |
| I 4.3.3.6 Steam Generator Compartment Analvsis I The steam generator compartment was modelled to obtain the blowdown spatial pressure-time history response to detenninethe differential I
| |
| ,, pressures on the steam generator. Postulated ruptures in the steam generator inlet and outlet pipes were evaluated.
| |
| ,_ Figures-4.3.42 and 4.3.43present the nodal model for the generic*
| |
| - analysis, while the node and flow path infonnation is given in -
| |
| I Tables 4.3.l and 4.3.2. The Millstone 2 steafll generator compartment
| |
| 'I served as the basis for this generic model.
| |
| Using the generic mass and ener-gy data (Tables 4.3.9A through 4.3.
| |
| -lOB) .and the model described above, the steam generator compartment I'
| |
| pressure responses were computed for the steam generator inlet and
| |
| - out-let pipe breaks. Pressure- response histories for the 1000 square inch hot leg break are in figures 4.3.45 through 4.3.50 and
| |
| 'I in Figures 4~3.51 through 4.3.56 for the 1414 square inch suction leg, break. In the hot leg break analysis 50% of the blowdown was
| |
| _, :
| |
| ___ ____ ---~--------~-----_:___ -- .,
| |
| t ,**. . . :. . .. ; . ' . **.*-
| |
| I.
| |
| I .** .....
| |
| I I
| |
| 'I
| |
| | |
| I assumed to go* into node 6 and. the other 50% into* node 7; for the suction leg break 45~~ of the blowdown was assumed into node 9 and I
| |
| ,55% into node 8. These percentages were determined based on the
| |
| *location of the pipe break and the projection of blowdown from the break into the surrounding nodes.
| |
| '1:,.
| |
| Tables; 4.3 ..16A and:* 4.3 *.168 ,present maximum- calculated pressureo differentials across the steam, generator . as well as time*of'occ~rrence
| |
| .:,
| |
| ..
| |
| .*.*.~*****..
| |
| \
| |
| for*this generic analysis.
| |
| Generic* analysis pressure-time histories were provided for evaluation t
| |
| of' component supports.
| |
| .. ' .
| |
| . *.-.
| |
| . . . - . -
| |
| Section. 4.3-.J ..T discusses pl ant. *spec.ific analys~s: and~ presents. *
| |
| --- . . . .
| |
| **-...:.~--*---*---. -_ *-* :__-~-".___ .......:.:~--- - . - .
| |
| --- ,..~,..._ *-~*""'**. -**---~- ----:::-.----;- *--*--.*~-- --*----*- ';-- -- . .---- ----
| |
| 4.3.3.7 Application of .Subcompartment Pressure Analysis This. section explains how the generic steam generator compartment .*
| |
| -----analysis" was appTied" to* the plant specif;-c: analyses~ -:-~-
| |
| . . ~ .-:- . , .~ . . .
| |
| : l * . -~- ,; ..-
| |
| ....-~- _.,:;_ -*-/.;_-~ '
| |
| A::comparison of:*<steain generator compartment parameters. is= made in.
| |
| Table 4.3. lT. The plant civil arrangements can be seen in the.
| |
| .
| |
| Figures stated. in Section 4.3.2'. The. Millstone 2. compartment was.
| |
| -.'...
| |
| . .
| |
| :* - ....
| |
| . - .~ . :.*; . -_:: . . ; . :*
| |
| **~hosE!n 'as;:~he.-bad-~ for:*dai~g'the generic, ~~-alysi~>
| |
| ..
| |
| . :. . .
| |
| *,,. .'.':::.
| |
| . *,;: ... . _, . '~-
| |
| ,,'-' ....
| |
| .. , *.-.
| |
| - .* . . -. -
| |
| ' --~ . .--. ~-* : : .
| |
| .... ,- .
| |
| ..
| |
| .Millstone 2 and Calvert Cliffs* 1 and z*have very similar layouts.
| |
| The Millstone upper compa.rtment walls e~te~d- higher-up around the-.
| |
| steam generator than do those for Calvert Cliffs *. *The effect of I-higher shield walls surrounding the Millstone.steam generator is to I
| |
| *
| |
| * include- additional pressure differentia*ls across th~ upper portion
| |
| -,,
| |
| . -- ... -----. -~ ---* -*--*--- --- -~*-*--------*-----~ ...."'"'--*-----~~_,. ______..,...._.....,._, ...,.-.,.--* ----,-* ...
| |
| ~ ~.*-~.*---~-:..
| |
| | |
| .. ** l' . . ..
| |
| t - * * - * * * : - * * ' ' * ,_- * .._~ * .' :- *
| |
| *of this component* versus Calvert Cliffs. In one. corner* .of the I compartment the primary shield wall extends. further bey~nd the.
| |
| *I reactor coolant pump in Millstone versus Calvert Cliffs.
| |
| analysis of the - suction. leg break was performed on the other side The t
| |
| - .
| |
| of the compartment where* the layouts are alike and pressures would' -:.:.*,
| |
| *. be: greater* (due* to more limited* space}.. The differences on ~he* one II *.. *.. . *, ; co~ner of the compartment have inccm.seq~~ntial.' *effe~ts on:. the re~~it~::l;~;>: * . . *'::<<<**.
| |
| . *, ':., . ., * -:. *~: \~* -~ ~ : _. ._-, .-*' *. . . - .~:* ' :* .>~~. -<_:*:..._~ _.,-* ' ' .:.. -~-*{:~_;*.: -; - *-~-: '/' *:' . *: . ~. ~-_. .f< . '.:i\:: . :.;< ..'-~-*:* .~;- .. '. _ : ~ _'.~--~~-~--:~,!*:' -~;.:_,-~'.-~-~::::*.:_*_~**. .~~*:*;~~f:~i'.: . .~~~'.~<;:~~~}-~-(£~'.:,;~!.):*:\::~-/~~~-.:~.~~:~~-~~-::-
| |
| 1*
| |
| . '
| |
| : . The conclusion* i's that the generic. (Millstone 2): steam generator:*,/-"/'.:;:')'<; *:;*/c>:::",-:,
| |
| . :.., '.
| |
| ~- ( :' ;'
| |
| *. :.'*
| |
| compartment model. is directly applicable to Calvert Cliffs.
| |
| * S.inc~
| |
| t
| |
| ,, :
| |
| the generic mass and energy releases* are also- those for Millstone*
| |
| and Calvert 4.3.3.6 are val id.* for these* plants.
| |
| Cliffs*~
| |
| . ..
| |
| the generic
| |
| -. .
| |
| an~lysis
| |
| .
| |
| and results of Section.
| |
| **. -,. . ,' . : *>_" -
| |
| . .*'
| |
| ' ~ .. -
| |
| ..
| |
| '' .:.: *_..-:.
| |
| .
| |
| ..** *.
| |
| 'I
| |
| '
| |
| ,* ... *-*,*
| |
| *.. * - .
| |
| ' . ' .*. '":.* . :- - . : ...
| |
| *While' the .Pal isades,*~team-generator compartment* configuration is:_, .... '*
| |
| like the generic:, adjustments were _made. to the generic model to more closely reflect the Palisades plant. The generic model I nodalization- scheme was left as is (see Figures 4.3.42 and 4.3.43).
| |
| I . . * * *.!*-
| |
| -.
| |
| <!
| |
| .
| |
| * Changes to node vo 1~mes; amL vent areas were* made. in the fallowing way~
| |
| *',-.
| |
| **
| |
| *'' .
| |
| I *..:~~~The .generic model. ste~m* generator .. comp_artrnent. total net*** val ume was
| |
| .......... ,,.:.
| |
| 11 . .. . computed., . The
| |
| .. ,. : :~* .
| |
| Pa-lisades
| |
| . . . -
| |
| .
| |
| steam
| |
| .. .. . .
| |
| generator compartment total . .
| |
| net
| |
| ;~j;,,?,ii:~S ~~e~~~~~j~tr~~gl~i~~~01~f1~~t~;t!;j~~~~~t:$~1~i~~~it,;~wz1jff,'~f t*'Y*
| |
| 1 t ... * ,,*.. .'.:'..' volu~ *n~mb,~r: of T~bl~'.4~,i~.Ti~:.-* *(l~~e;~:*2".~tid~:l',~olumes of nodes 1~2s. *.
| |
| '.i:'
| |
| I
| |
| ,
| |
| :
| |
| " *.* .
| |
| .
| |
| *, **''. ~ ..*
| |
| '
| |
| , .: :. . .- *--.**. - ..... . -* .* *'._~*. - . :._ . . .
| |
| and 30~35.were each mult.iplied:; by the- P,alisades*normalfzed volume value to give. node volumes for<the Pali'sades analysi~. * -
| |
| I Generic; model vent areas out of the 1 stea~
| |
| .
| |
| gerier~tor .
| |
| compartment
| |
| ... '
| |
| were changed for the Palisades analysis. -The total vent area. out I . *....... *. ,*
| |
| *-'.*. ' , : r ,' . ,*.*
| |
| ......
| |
| :.-:*
| |
| .. .~ .. :
| |
| | |
| *' ~ *I : *
| |
| . '
| |
| This was also done for the Palisades *compartment-, .and the Pa.lisades total vent area was. divided by the generic analysis vent. area to result in a normalized vent area of o*.a1* (See Table 4.3.17). Each-
| |
| -vent. area out of the. *g~neric analysis* steam* generator compartment -
| |
| * ;__ 1-~ ' : * *
| |
| | |
| ,, . normalized. vent area was: calculated~: These normalized volumes and .
| |
| '* ;._.
| |
| ..
| |
| *:*:.
| |
| '....
| |
| .**
| |
| . . '
| |
| I areas .. are stated in Table 4.3.17.
| |
| ,,
| |
| I
| |
| .
| |
| Then, as was *done for Palisades, the generic mode*l compartment interior node volumes were multiplied by the Fort Calhoun normalized: volume**
| |
| **.and each vent area*. out of the: generic
| |
| . . .
| |
| compar~mentwas
| |
| . ' *.
| |
| multiplied:
| |
| .
| |
| by the .Fort .Calhoun normalized area. The; Fort* Calhoun steam generator I . *,** - - compartment code *input model was created using these- nocie vo1:umes .
| |
| ,:* .* . -- *:~- . .. .. : -,_...
| |
| * and, the:;*vent areas.*. The.:nodalfzadon sche~e- of.*Figure~
| |
| ',,, 4.3.43 remained the same *.
| |
| '
| |
| '
| |
| \ ;
| |
| '
| |
| The pressure analyses. were accomplished using the hot leg break.and suction leg break data of Tables 4 *.3.13A and 4.3 *.138 and. Tables 4.3.14A and. 4.3.148 ,. respectively*. Pressur~ respons-e. his tori es. for**
| |
| ~ **the. hot leg break are in Figures 4.3.69 through:
| |
| . *' . .
| |
| 4.* 3.74 while.* the
| |
| "-,_._ **-;, _, ,. --~:-'.*-~' .* ... ~,., .. :
| |
| , ' ~:* ** * * ** : - .' * * - * - :-;** = * *
| |
| ,, '''-.
| |
| I Fort Calhoun suction leg break pressure:*responsetransients are in Figures 4.3.75 through 4.3.80. Steam generator maximum pressure.
| |
| ii **/
| |
| differentials are in Tables 4.3.19A and 4.3.19B.
| |
| *1 . . Steam generator*
| |
| . . . . ,**
| |
| d~fferential
| |
| "<-.***.**
| |
| pressure sealing factors were determined
| |
| . * : . . -.*. .
| |
| *.
| |
| * and sp'~ci *f~ ed for;, eval u~tfon of' steam: gen:~~ator .**supports* fa~: each *. . .
| |
| '..-.*
| |
| . . .
| |
| I* plant specific., a*nalysis~
| |
| * These. scal_ing *fac~o;s **~ere ~~~~~t~d from,
| |
| ..,results of the generic and the piant specific analyses *by usi~g the I .;.:.
| |
| method .ci~~cribed-'belo~.;_*_ .:scaling i~~to:rsc:were:ca1*~~1-;ilt~d: for* ~t1~* . . ;* .*** *.
| |
| tl '* . *'.:*
| |
| h~r;,io~*~~i.,:'* ~~a~ ~erti ca~- di*r~~~;:~;~*'\;~~Pi~*~:'.*W:~J:~f~~ii''.b:~,;-**~:~~~-~~~ i~;.\., . *: **
| |
| **. , , .. - :.
| |
| . ~ .. '
| |
| , . ; hot leg 'pipe. b-~ea.k cases-. **
| |
| , I\/-,.
| |
| *. -* :.:*. : .. ~ ~ '* ._.,-, ~*" ', *:.< *.. ,.*
| |
| -- :*.".
| |
| * h ....
| |
| * .. *'
| |
| .~:
| |
| ,_ ..., ....
| |
| *There are four levels of nodes along .. the height. of the steam**
| |
| I *. generator as shown fo Figure 4.3.42. From the subcompartment pressure I .,;
| |
| analysis a maximum differential' pressure.- across. ' . ..
| |
| the steam generator.* .
| |
| l .. i , . .. . . was o~tai ned for e~ch of t:efour node 1~vel s ~ ,;!h*~_,~rimu~;pre~~~re ...* < .*..*
| |
| :, -'~""--* ----.-* -- ~'-?c~:,.~,~---.---~-."~:--.. ~*--*-~ -~~-:~~...::~,~~_.:,~.:~.:,.,~~*::o::*~~.:c::=cc~c::;:_c~~-~~;-.:~~~~'-*~,-~;.;~-~~;;*~.,~,~~;::~-~-~~~!'";:~:__, .: c____ :~-~:;:~:~c
| |
| | |
| .-,,:'
| |
| . -;
| |
| differentials for each of the levels were weigt:ited by nod~l h~ight on the steam generator and summed to yield an overall maximum horizontal differential pressure. Far each break on each plant this value.was divided by its counterpart determined from the generic analysis' to produce: the scaling factor~ An. analogous' approach:* was,
| |
| . ~-,.
| |
| direct.ion* scaling factors-.,
| |
| .
| |
| . Tabla 4;.3.20 *. ~ The Millstone and. Calvert: Cliffs*
| |
| . '
| |
| . *-*:
| |
| '19'0 ~~-c~.~?e their ~~a1yses are one and~ the:: same.' as. the: gen~ri~'()nes~-
| |
| ...
| |
| These seal fog* factors were provided for: evaluation *of* the
| |
| .
| |
| generator
| |
| ' . ~
| |
| supports ._1;.* * ***
| |
| | |
| TABLE 4.3. l
| |
| ---*
| |
| MTLLSTONE 2 I CAL~ERT CLIFFS t,2
| |
| "--***
| |
| * .
| |
| *-------S*T-E*A ~~G £NE~ A'lnJ~*,.e~?-~ R-T-Ht~T"'=A 'I l\t'tS:t NJOE OESCRt~TIJ~ .
| |
| s*---------*-w-. . -~- ~-
| |
| N')OE \/".11..UME O!SCIHPT ION f
| |
| *** _ ~U~B!R- H',T-***"l'-* .. - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - -
| |
| -~---t.:..._~+ 2113 :ct&**--- -tt.-***~~.,.._ro-.~59*!'--1.,... r..-------
| |
| 1A *. ~* *. l.t 2:sQ *Et.:: .,:s FT rn -:s9! ..-r
| |
| " . ! * . ~*tt8~t2* E~tj FT T~ .:3y;-*---~~-----"---'----
| |
| U .1s9o:s2 l!L *. :5Q3 FT TO 2:s ,,.
| |
| -Hi~-.i.*.1-.--~ b-f-~9-3 !L *:5~3 FT TO 2::>
| |
| .. &. 1SAS:99 [~. 2:s' FT TJ 20:0 FT
| |
| ___..,, ~?:s*~*e,. . !t ~.~,,.. l'n 20'cir,.**,. . .---------.. -.. .-. -.--~--~~
| |
| 11*1.* 8 ll&s*:11 . . EL 2:.~* FT TO. 2n:o i::'1'... . . '. --
| |
| ~ 9 t3R*~f-l !L 2~.5 ,T TO 20:r-l''...,~--------~---
| |
| tO 'H&s:33 !'L z~.>> ,T. TJ 20:0 ~ir* ..
| |
| ---H- - 5,,-t : 4 q . !t 2. 5_, .. T_ _ _ _ _ _ _ _ _ _ _ __
| |
| T--'filf-'J.__.2Hn.--.~o.-.*.....
| |
| ._L~!i-*---~'- *U
| |
| = ~!~:~-~!-~
| |
| tsq9:1r
| |
| ~-~~;;~~~;-~s!-**~~-~,~~~~-----~---*-
| |
| !L 20:-0 FT TO ~5~5 FT .
| |
| -:9t--+s-** --~-oc;2*i-q11 !L 2-~~,.;-;-J1s-;-s-;r-
| |
| * . . t &* 1 l.t ~
| |
| * O5 EL. c0 : 0 F T T0 '.3 5 *: 3 F T
| |
| ---* 1 '~l.lS-~-t-'J !L 20:0 FT T~:s-r-**.- - - - - - - - - - - - - -
| |
| t8 . ~~&s:11 EL 20:0 FT TO !s:s FT
| |
| ~~ *-~**tq*~*-~~- .. ,t,~4-lit.i 1.. !t-'2'tr;*o--J>~*-~-s~;5-.-,-T----------~----.,-*,
| |
| * ~o rnc * .19 £L. 3;*:s FT' .T~ 5c:b. FT . . ..
| |
| -------n*--*------11n~:1 q.:_. !~!;:;s-F:r-t~s'.a-:~:--;:T'- ----- --c---c:--.-~-*--**--*-.. *-*;
| |
| *f\
| |
| ' ~2 . 5'1l~3U .* . EL 3;::s FT TO 5o:b FT I
| |
| ---~~ ?3-------------as2*.21 !t 3~~c;'--N-ttt-c;o-;-b;': *-*--/
| |
| .*.. .. ff. ... .. . ;;: ~!; . . ~-- ------~~;~~:~~*~~~~ ~;.~~ :~ ~;-,.:---*-* ~*~* .............
| |
| -.,, ~1* *l;-21 PIP£ . TU~N£t. -.-:-*1
| |
| .i\ . 18 1 t &~90 ,I~! TUNt-.IEL 1 *~
| |
| *---!t--
| |
| . JO fl lB s-:,.4~
| |
| 559.&S'*
| |
| R~AC ~ ~R--e-"4V-tT EL so.& FT Trl &3.Q F:T
| |
| _ . **1 L12 7-*1t---:--*-:..,.-5-;9*:bB- .
| |
| -J*J 4Qb:'63
| |
| * f,8*2*-:-3'2
| |
| [t8'"Su:~*tf*'"--nt'..:fi1-:t1"1"!t"'-----------.-~-,--*,.*-***
| |
| £L s*o:& J".T
| |
| !t-:-"S~,.T T*:l*
| |
| r~ &1:0 F*f a:l!'o--r-,-------------'--
| |
| : 1. '1---~ §
| |
| ~U
| |
| ~*E.*
| |
| ~A2:l~
| |
| !4lJ &:-q 3 i:,ot)Ooo:on EL so:& ~T T1
| |
| !L 5 0:,, FT T:J--b~3~;-f'ro-r...
| |
| CO~TAIN~E'.NT' VOLU~[\
| |
| &3:o ;r r-------------
| |
| *~* . - . ' -*. . .. '. .
| |
| :...___:_*.~-*--=...:...._- ~ .-.:,.~;~** -.~--*~
| |
| ______________
| |
| ..*.**'* * ->. -....
| |
| -* ...*,,__.
| |
| **.*** .. - ..- . * .- ... * -
| |
| :-*. *. - .* --,-----'*'
| |
| ...... *.. *_---;
| |
| *--~--'--......:.._...:._-'-- ;...__------:-~-:-_..;.--..;._---~*--
| |
| I
| |
| | |
| * - - - - *----------T_A.8LE 4._.3_._2_.*- - - - - - - - - - - - - - *
| |
| * _ *_ _ _*_. t---
| |
| ~ILLSTONE 2 I CALVERT CLIFFS lJ2
| |
| ..
| |
| --*--------<<s~TEA~ GENERAT-OR-COMP-ARTMEN"f-A~"At;YS~l-41:S~-----------,**-
| |
| FL.Ow PATH DESCRIPTION . ~_i FROM TO HEAD LOSS K
| |
| ~i~r~~~~E--V~~~~E
| |
| *---ttt!llO
| |
| * AREA 1110-.--No-.--f-T*-."2.,__ _F*f *o--t LIA FRICTION I<
| |
| FOPWARO REI/ERSE GfOt..iM~K'-_.,.6EQM-1<:-----1
| |
| '.I'.
| |
| '~
| |
| -----1)-'fOs----tt-4-.
| |
| 0410 *
| |
| --~s-------st.-J-i.
| |
| io f20.s1
| |
| * .-1-J-:r-*-
| |
| .otsoo '
| |
| .i-o-o
| |
| .100 Se:S45
| |
| ~soo s.54 ... 5----l-
| |
| .998 - *
| |
| --<ttr09 4 9 36.7!-0 .* 1866 elOO .sto--~1~ *. 4-l:Ot-----ji(
| |
| - 0509* 5, 9 36 *. 10 e 1870 ,*. 100 .878* i.257* . '.
| |
| --oft"o5o-Es 5 a .15.0.--r-1 *. ut+69- .100* .921> i *. *2*r.----~-1 101 l 10 17 lBT.98 *0834* *100 .022 -.022*.
| |
| ---09-16 9. 1.6 f-le75. .2"t84 *. 10-0 *. 60-7 ..* 00-0----:-...-~
| |
| oa1s a is.. 1aa.46 *. 0832. .i-oo* .022 .oJo
| |
| ---ocrto 9 i-o 12"re57 .1"63J-* .100 .41a .396 0908 9 8 124.57' .1633 .100 .418 .396
| |
| --+r1-16*-1-"t ""t6 i:ss-;35..-.-1120--
| |
| * too .39ts .35-".-----i lSlb* 15 16. 88e3~ .1720 .100 e398 .354
| |
| _ _,O-to-2 l 2 -a-.-28*---i--.-~26s*- .ttto 2i-2S-o 2.zsn----.,_,, ____
| |
| ,.---1 0203 z 3 a.2a i *.. 0241 *. 100 2.2so 2.2so
| |
| ---o-b,-402 4 2 36.-S r;
| |
| * 0 ifO*l .10 6
| |
| * 41il
| |
| * 8ft2i>------!"'~~
| |
| 0502 .S 2 36 *. 58* - eO'tOS - *. lOO. * .466; e.867 '
| |
| --~:g;~-* :: .i ;:~~~~!, - -~g~~: :1~~ .-:..r:~ :.1~i -I._
| |
| ---0-1*36 l. 3& --4s1-*.-3:(t.--.-.,ooJc-----..1:(}0 i..-000. *,. .soo,.---._-.-., . . .*:-,:*-<;.*-
| |
| ,
| |
| 0236 2 3& ... 73 .. 15.. . . *. 0189* . . . ., *. 100
| |
| * leOOO'* e50.0
| |
| --0-JJo---*1- 36 36u.o4' . *Ot}*Je * .:t-<H) .1 *. 0-00 * *..so 110~ 11 4 130.l~ 10681 .100 .~19 .021
| |
| -~-----.*-**obO't , ** - - 6* **--*-*-*-~'+ ---*----:----* J06
| |
| * 0 J* -.**-*<<*
| |
| * 0~33 --* ***---**~---.-100----9 62"7 1*879--~---- ***
| |
| * 01os 1* s l06e03 .oas2* .100 i.002 .a&4,
| |
| --~1*-zos 1-2 s 70.79
| |
| * l-332-
| |
| * l Otl l. tSS
| |
| * 94-1-----
| |
| ---i.m . i oe;fc~--6 1
| |
| t, "10 .
| |
| 1 i~tt 89'-.-3-7
| |
| <:m~
| |
| .. : .05:7*
| |
| .* *. :~it :m . . Ji~:-.
| |
| ..*,t<ttr .a*t 9 ---*_-..,, .
| |
| *7'&~-----
| |
| 0712 T. 12*:* *-sa *. i.9*' .:-* *. o9a5 *.*'*-.1.00*:
| |
| * _*.*.1as .,798.
| |
| ---o-a-t2 *8 lZ: *9..-cl.. e70054* .*,11)0 .660 .55....- - - - -
| |
| 1011 10 11 110.d~ .0733 *~100 . ,632. ~632*
| |
| --fl-QtJ*2c 6 2b h-69* , "f6&-3
| |
| * l-QO 1485. 193'"19"->>---....,.,.-,-1 0627 6* 27 : ... 4<.,72.- ,.6009 . .100 .491 . ..963.
| |
| --f}Tl't~ 1- . . 2-1 1t.~*Tc;*-~*-. . e.6009=-- e 100 * * *:49*t .-963***-->>. - -
| |
| 0728 r: *.: '2.a-: *.
| |
| * J*.*01+;.*."
| |
| * i.2975 . : .-1:00 ., .4as *,.... *-.~_939,- :. * -*
| |
| --..12-28 l-2 28 . * *. 3*.-84-.'-h:723& *: *..i-o-o e48*1 e-94Q.9-*--*-,*-...._;,1
| |
| * ....
| |
| ***.-_
| |
| 2629 26-' * "29* * -* . 4'e*lS . . le.391_0 .- : .100 l.ooo *. soo .~ _
| |
| ---~1*29--z-7
| |
| * 29. :: h~2C-----h:5692 .,litO. l:-e--0-0-.0. .S<>n---------1 2e29*_. - 2a 2i:; ** *. 7.69';. * .7533 .*,100 i.ooo * .* soo
| |
| --i:.-1tt8' * . 11 18 162-e~"f~
| |
| * U-963 *}CH> 1 {H}4f * &3-:J-----t
| |
| . 0613 6 13 114.~3- .1371 .100 , *. oos ..* 044*
| |
| --0-7-1-lf' 7 1*4 l 1:4*9:3-3 e.-1-37'1 .1-0-0 .--0&8 . .-()4'*'~---,::--1 1219- 12 .* 19 70. 78 .* 2215 .:100 .020*. . .011 . *. . :
| |
| ---l-81-J 18 1-3* l*.;lil 57'---.-12'+6- **l.O:t>----.'872 * .. e90-3-*-,--'-------- -
| |
| l J l tt. lJ 14* 113*. 51
| |
| * 1 03 5
| |
| * 100 . .
| |
| * 239 .
| |
| * 2 3 9- .
| |
| -~14*15 lit 15 79*.-10 a0669 .to-o .-tl4-l. *. 1e-s-------
| |
| ___ _ _ _ _ _ _ _ _ _ __.:.___ _ _-=..!_ _ _ _ _ _ _ _ _ _ _ ___:_:_.
| |
| 4- . 3*. ~ '1..-- *------------~ -=--"
| |
| | |
| . 1------....*
| |
| ..; _* FROM' . TO TA8LE
| |
| * 4.3.2 (CONT.)
| |
| HEAO- Loss: K'
| |
| -1**\f't:ow---rtotUM E--v-oi:trr-tE:
| |
| I PATH NOUE NODE AREA L/A FRICTION FORWARD .REVERSE
| |
| '--''-NO. NO. No-.--F*joo-2---F*fo-0-. GEOM K BEOM-1<~_---~
| |
| --t-~g r-~--rs 19--1s r:- ~~---
| |
| i tri-----s~-.-45:-.
| |
| ~r:~~ - - .:~m U<Jb*3---:-*
| |
| =~~~
| |
| * 1 tt-o
| |
| :~:~
| |
| ---.---oe*oi--..;.....~.
| |
| :~:~*-----
| |
| ssfit-s----
| |
| i *t-1110 ' 17 18 98 .* 17 .0827 .100 .632 .632
| |
| -* -* ' t836--l8 36 s*te-tt'f .0419----i-o-o
| |
| * t .11*1 l
| |
| * lf-lu3------
| |
| 1336 13 36 12.16 .oS78 .100 1. 8"72 'l. 736
| |
| ~36 36 1"4 15* *'
| |
| 36 36.
| |
| l-Z-.-t6 21..19
| |
| .0578'
| |
| *. 036T
| |
| ,.100
| |
| *. 100:
| |
| l .~8-1-Z 1 *. 867 1.1-36
| |
| : l. ll9 1136 t7 36 2s.1e .o-368 .1*00 1.as-1 t .6*ij4 II so.s.r+- .. .0063
| |
| '*
| |
| 1936 19 36 .100 ''
| |
| le613 **'
| |
| ' i .010.
| |
| '
| |
| 142"1 14 21 . s i .-:sJ ' .* l-94-7 el (}O .3tt8 .38~
| |
| *zo
| |
| '
| |
| 1320 13 51.33 .1947 .100 *. 308* ~380 2-2 z-..95--z-.494 0 , i-oo 1.3~ l .4-3~
| |
| _J
| |
| * l'r22 1325'
| |
| ---is2z--15
| |
| '1-4' 13 25 2'2 2.95 39*~5 2.4940
| |
| .*""2230
| |
| .1ou
| |
| * t11cr--
| |
| 1,395
| |
| .4*04 1.432
| |
| .652 1725 17 25 39 *. 95 .2230 .100 .404 .652
| |
| * too i .25-7 --
| |
| rr~~:
| |
| 15 2-3 --tJ-9~9-z ,-t-709 1.0&5 17 24- 13.92 .1709 *. 100 1,065 1.2s1
| |
| .... _,*
| |
| .too ,so*o .so-o
| |
| --t 1623 1624
| |
| -ztr2*1~-*2~
| |
| 16 16
| |
| --2'1 2-3 24 35.S-8 35.88
| |
| 'If"11r-r---.*z2r2
| |
| .1?2b5
| |
| .2265 .100
| |
| .ttJO
| |
| .-SGO
| |
| .s.-s
| |
| .soo
| |
| * s-q.s- . *-
| |
| . 2122 21 22 44 *. 18 ' .1674-
| |
| * 100 ,.316 .422
| |
| *--~02~---*20 25 tt't--.-1a*-----.-::t&7'r .~100---.-:H t>- .422:* -
| |
| ..
| |
| &_2223, 22 23 ~-'+ .1 a .* 1546
| |
| * 100* *. 353 -.2tj5
| |
| - -- 2s2~--zs- 2~- "4-.-1 ti
| |
| * l-546 ii*OO .353 .2es 2324 23 24 65,69
| |
| * l 565. .100 .244 .244*
| |
| .... ' .. 2 3' ~ - *-*-*--3 b '*** .-*- *--~U.__, 3 (1 .. *11* .-12 7 s ******------* ***** l Q,0-' *- *-- *1
| |
| * 4 9 s**-----1. 4 9 2 ,..._ ____ ,_,_ -~*** **
| |
| -a-~-~:~:
| |
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| TABLE 4.3.78
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| - - , .:.;. ' * ** . - . * *' - * -~'o. .*:.:. *~* ' ' ., * .... ,, ' ..... .* ..
| |
| * - *.. " .. _.. . " '. :,._;*," . . . , *. . ..... *".* ........ " ,. ...
| |
| * I
| |
| . *.... -
| |
| *-----*--~-------*----------*-*------*:- *--*
| |
| . ~ .. ~- :*. .* ,...*. *. . .
| |
| *:~-~-~ -~ ..._...._:~~ ~l-.-'-<'*
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| ,\
| |
| .. .. ;
| |
| .* .. ....;.. * ...... * ..: **
| |
| ' "
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| .. \~., *** ... *' . ' ,
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| . ' **'*, ~: ~.. . : ' .... : . *:* ' : .
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| : *, .
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| "'
| |
| | |
| 1
| |
| # *.. * *. '_..,., _ _. _ _ _ _;__r _ _ _ _ :_
| |
| *. . *-*----------*-----**--------F oRT- CAL:Ho::s~~ss ::: ::f.Rsv RELEAsE 4
| |
| - -- -" *.* * * - - - .-- ***~*------~--:...-...--------"--..:..- RATE s FOR* 1608 SQ. I Ne. HOT LEG* ** ****** .. ,. _____,_ ___ ..________ ~ ..-****-- *****---*-.:*
| |
| / ****----- -----~------------~~~~~g~I~~y~~~~:l~ TL~~g~ ~~;~~A~~~~LE*--*---,-*---------~------**----~'--1-.
| |
| .--*---------------**----*-*--*--**--.-----*--- *-* * * * *. . . _. . --* .-. * -'*-* *-----**- * -* --- ---- - - *- . . - * ---** *---* ----*-*-- -*- * *---** * **1
| |
| * <.FLOw FROM s.G. SIDE> . * . * . **
| |
| 1----~ **---*--*-* --.-* -~-*-- CSE~~~~s )-*-****-*---~~~~s~~ r~ ** * * *- - -* *- -~~i~~t:r . . . -~~~~~~s~~ I~- -.* .. -* .. - *-* *-* * * *- .
| |
| - -------------~-0~00000---*"----*-:--*-*-:*--*-o *. o-- .. :.~.~-~----**--616.70 **-****--*-**--- **'---~---o. --~-:. __:_.__ *****-
| |
| . * .00100 **.. 2~86.o . . 6.l6eZO 1531873.. *.* *. .* *
| |
| *I**
| |
| -*-.---:--*____.. _:._,...:...-00200-----:-:.__ .* 4-936 *. 0.--- -****--*-616.20* :***--.-~304-lS63.,*---~--------~-- ---~-------*-- -*.
| |
| *..*;ooJoo * *. .. 1012.* 0 .. * .- * &1s-.so *
| |
| * 43S't9Ja ..,
| |
| -~------------.-Oo4oo--*--:---~-.:..s64-2e:o:.:.:.... ---** -**-:~.61s. 20 .... ,...:~---~~--s3*1&ssa- *.... - ~:......... .... -*;_**:--*:c: . :.:
| |
| * * ** * * *_. *1*. "
| |
| *. *oosoo .. . . . 102i.o.o* . . . . 614".90 * ~-C' 62.78129.,. * . ~. ~i:*--
| |
| **--:~~;~g**---------. -~~~!g:~*-: ---~- -:t~:-~~ -~-~-*---~-;~~~!~!: .* ,.c. __ _;*~---'-* ,~,~~-:-+1;::~,
| |
| ------------*----------~-.. oosoo .. --------*--l.Jl1to.o -------------613. - ---- -* -8062704-.. - ----------*----* -
| |
| **--**-~---~--~--:~~~~~.
| |
| I 0 12 QQ
| |
| ____ t:i~~:~ . _____ :ti::~ - ___ :~~g;::
| |
| l 918 \) I Q . 61J15 Q . l l 7 b () 9 J 0 I
| |
| * * * * --1-** * . *. .
| |
| _______ _; __________ .01400 .. -------22030 .. 0 . . -----613.50 ., .. 135154-05. -* -.- .... -
| |
| *------* :-~~:~~C--~~---~--~-~;.~-~-~,:~- ~---~~--- **~--~:t~:*:~.:.
| |
| ..*. 02000 . 29450,0 ' . . 61,3",30
| |
| "~--~-~~!!i;!~
| |
| . l806lb85...
| |
| :. . . --~~--~-------*'**-;
| |
| . .. ' *-:~.
| |
| -~---**** -~--*--**-------*~-~--~: ~~~~~- .. *~ . . ,. ~~,;~~~~:.~ "'. ,_______.:. . :~ i:~~- - -_-.. ~~;:;~i: :. .. . . . . -* **-**-~'.., :_
| |
| *-------*-------~-*--*----*..: .* 02000. . .:..~ ... :____ 35,0-10 *. 0 ' ... ,. 7 **** 61..3.--1.0 21495286. .: **'' : '; .
| |
| .* . lto2aoo
| |
| * 3557'0 *. o* .-.**
| |
| * 613 *. oo.
| |
| * 2180441.o. -** *. _ .'k;'f.
| |
| -~---~- *--. ...: --* - .. - .... : *_. 03 ~a o
| |
| ------*~.. "'--***-*"*---.*-- .03~00
| |
| ,,03200.
| |
| . :-*. -:-,:-3"35:?*0-~.:o~
| |
| 324-Io *. o
| |
| .. J24lO.O
| |
| - - . - - *: .612 *. 9 o
| |
| .. E>l2 **9o
| |
| .. - bl2 *. 9u
| |
| .. - 205444 oa *.
| |
| 19900863.
| |
| 19864089,
| |
| * * .: ~ . *** *
| |
| * 1
| |
| ..
| |
| ------------~::.:.~~:~~ - *.. 04000:
| |
| ----- ----~-i;~;~:g
| |
| . 3563_0*:~_0_ .*
| |
| **-----~:~_i:*~g_
| |
| . 6'1:3~30
| |
| -----***--*~~-~~~:~~=:
| |
| 2'1851 . 679_. __ *
| |
| *-*-----*-----1.,
| |
| - ~.~*
| |
| ---~F~fmr~~=---niutrF:~-i~~-~tfHr~--~~i~nm~v~:-~f~~;0~11f~
| |
| * *. assoo _4oa9o.o *
| |
| * blJ.20. 25073748. - , .
| |
| ------~-*0600.0- --------3990.o.,o .... ---..c-*----&13.oo .... - .:.~-
| |
| .. .. ',.ObSOO 37940**. 0
| |
| - - - - - - - - *.01000 **- ,*....* ~:35190.0:::~~.. -~.;;.~;..,~~~-61.2' *.40
| |
| : *. *.*
| |
| * 612 *. 70
| |
| . 24458.700 *- . ..
| |
| 232.45838..
| |
| . 21550356.
| |
| * .
| |
| ----------- --- .
| |
| . ' _._,_;.,.:~; ,: .
| |
| ..* 1*
| |
| . _,,01soo.**. * **' 3*2soo.o~: * :.;>612*20, ..
| |
| * i.9e9*6s.oo, :._. .* .. ),':,,*;:~, *
| |
| ....* *:<' '>:: *. :~:~~~---~-~--*'-:-*~tit~:"~-~'. . . :. ;: :_ -~>-::~::tf::-~~- . . : * . : . ~:. ~ :1;~!~-~*:*.. ::;;**:~-- _::_'.:;,*1::.'
| |
| ----------'"---*~* .*. 0.900.o.*._.:_ _,__ * ..__ Jl.o oo *. o: .:.~.:.. __;,. __ :_~__ 6:lt.~ 60 *_ .. --~--~.:.lB95960 a....... :. ___ . .: _.;. .__ ~_..:._ --~--**
| |
| . 109500 ..... - . 30860 *. o ~- _.;* . 611.40. ' 18867804, . *> *; - :,*.......
| |
| - - - - - - -.....10000 _____:.,:__3oe10,.o: ..... ;., . :_:*~-_.611 *. 10-....~.*--*.18827991*'--~~-.~"-~~-~__:,__; ~-*
| |
| .11000 30690 .* 0 . ' . . 610. 20* . *, 18727038. . '.
| |
| _ _ _ _ _ _ _._-_ .* 1200.a . _* _______ Jo4so. a. _______*, _____ 609.20 .-.~--~ iasso l4o. ........... .
| |
| * 13 ooo 3o39o* a *6os
| |
| * l o . *
| |
| * i e4 a o15 9 ~ ,. * * ,,..
| |
| * _ _ _ _ _ _ __,__.*_14000 ----~-
| |
| * Joszo.o ... __ .:_ ___ :_____ 607..00 ....... 18525640. . ** ___- --*****-~*** ..
| |
| * ' r
| |
| * 0 0
| |
| .* ,:* ~i~CONT INUED) ** _** - -~---_- . :.~,__-,:,-~, .. *:~-w~---~::*1 ~--
| |
| --------------------------=----------*--*-*--- .. '**,'
| |
| . +. . .;.. Jt 6
| |
| | |
| . ' - . .' . . . . '. . . ~,-
| |
| , .~--* -*---*--.----"'- - . --
| |
| -~~-,-***-----------~---~*---**~~----'---*----.- , ---,...,.-*'.~~----.... --
| |
| . , *.* ** . '. . -
| |
| * TIME . -. FLOW RATE .. - .. ENTHALPY ENERGY RATE. .
| |
| - . _ ___...:.-~csECONOS). ____ :..... (L~/SEC>* _____* ---C8TU/L8) -------(BTU/SEC> - ------- _,, _________ ,,_ - -- -
| |
| --1
| |
| ~-1 *.*
| |
| --1
| |
| ~I _ -=_
| |
| -1
| |
| | |
| TABLE. 4.3.14A.
| |
| '0Rt CALHOU~ MASS ANn E~E~GV ~!LEASE.*
| |
| ------------.;n~""J"a ~--Qa*-;-s Q*:-r~7"s-uc*r1*0-~ CE G GUILLOTINE B~EAK AT SG OUTLET ~JZZLE
| |
| - - - - - - - - - - - - o i r - - q c s . ASY'fi;! ET Rt c.-i:o*A 0 S-EVAl~u At I J,~
| |
| ( F~Q~ FROM PUMP SIOEl
| |
| =---------- _
| |
| :.- .
| |
| . ,*
| |
| | |
| . .
| |
| . TABL.E: 4~3.14A'
| |
| ---------'~-
| |
| .. - .. .....
| |
| -~
| |
| . . . .
| |
| . : __:,: :.. *
| |
| < :.
| |
| I '*. . *.****
| |
| I '.... * .". < ' *; **.::, ,.. ' .. :*** *- ". . ;' ,,. '.; **. ~* *',. *,
| |
| '*.:'. *.
| |
| , ....;..*
| |
| ,, -"-
| |
| - ...
| |
| *~ --.~ -----~- -*----:-~----~---------- ......... ---~- ...-.--.~**-,..*--** --.-* . ~,..- ~- ... - ~ -* *----- ------- ~------ ~- ~-.,,. ----------:: - .. ~- --,-.-----**-~------------ ..... --~--~-- ---~--- ....
| |
| | |
| . --~* -.
| |
| 1 -: *;. ' * ' * ~
| |
| T--.-- -
| |
| '
| |
| , . *.
| |
| . TtME 'LO~ RATE ENThALPY E~ERGY RATE*
| |
| 1--
| |
| --------c~s!~n~o-s-,---c-cs7s~r-----c-aTU"1l-Sl ___TarJTs-c:c1 o*. ou-0-0-0 _* o:o.* * - s.n:--o.o - , .. o:..
| |
| -* *- . 1.
| |
| ~
| |
| .- -*. ooto_o.
| |
| -*;~LL ~ 0.2 Q0'.. ..* - '*
| |
| *. 21_119:0 . . :sao:20:-
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| * S.QO ::-o: -. ** *---
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| _ *-* *.
| |
| * _*. ,-. .~,:--.~*o.oaoo: * .
| |
| - &S~b: *.O. - *_':- .; **.'~>>_.- 539:-*b Q:
| |
| . *.. s2-?"~u: .- " .__ - . 5"39'.:-ro.--_. _*
| |
| "- cl5:l7&,l 8 .: - - **. -::<<:_.;,*~'-'f,->:_-..'{_:2 . ;~*:;
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| .-a1.n::s.ss_~ *. * ---* .. ;.*, *"'*;.---,1-:-.*~: ~
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| 4" .. ::* *-.,.
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| |
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| *
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| --_:... :-: -.--,::_-~'!~~'oi;oo. * * , , *.~*::''. *_.; CJo,;1:'<>* ,._. *_ -.:-.:;' :*_**; s3e*:*s*o *-. ..: <- 50&-s&1c,. *. :: :**:::*-</[,.'.;*.~*;::::':::;-~'1"*~*-
| |
| -~.__:_ __ ,_~.,-~_o_~-cnt~- _ 10130:0 * . Sl&:.1 o. . . ss~*ssr-3.. * . -.* , :-:\ --*
| |
| :' .~-()-70 o-
| |
| * 537*:1 o* 5'9lo s 3 t *.
| |
| 1--------.-<,!)-o~vo
| |
| . . ~- ,. 0 '> Oll .
| |
| 1io3o :o_:
| |
| 111n*:~o 1 2 u5 o: o
| |
| * sn-:so.
| |
| - S'.\ 7 : 3. O 62.e>~5*00-;,_
| |
| ob ~ 9 '3 8 S*.
| |
| .-
| |
| * .. *
| |
| *1
| |
| . :';;-' **
| |
| 1
| |
| - - - - - - - - . .- ._ o~trnrn 13"2*0-u-:-*o -s'3T:~~o 70"~To1ro-.
| |
| _*_-*. ::~t~:~~ _ -- }:~:r~~::~-o..-_ -
| |
| *-:-.- .u:&oo - _*_ 1ae3*0 *. --
| |
| ~-::~":-~-
| |
| *s3b.so-.
| |
| .- ~;~;i~~**:~
| |
| 101.01Qufl.'***-"*.
| |
| - .*-_* -_: ~,- ._'._,*_.: __-,*:_ ,_:. - *'_:_-.-;_*. -*_~;-_*;_._-1:.- .:*-_:_* . :*
| |
| l~~~~~~-'-~--A ~~~~~--'-'--'------
| |
| - . :._:- ;_* :. :'::,
| |
| _. ,_,:_**.,*,*:_ *.D3oa.rr ,
| |
| *. _- .*---:~.oJ.200- *..
| |
| -"2'7'Blo::o.-. '-:* .- ~ ---537:._20* _ -
| |
| * _ 27-9bo *. o -. . - 537*.30 tii9-s*o.21& *. - .... * ; < .r,;*
| |
| 150?290~.. , * ....... . .
| |
| ;: .*
| |
| _-"-<*1
| |
| ---* --.. ------~--:*7_~-.~.:>.3,!lO o-~~--~~~~~-~- 2.7Qbu:;-.o~----:. ~~---.:*~*-:537~;3 o*- ---~~ -~1 s*o ~29c 9 ;*--:-~ . _~ - _>,. _: ~7:,*f
| |
| -. . * , ,_ ........~3.&oo -. _ -*- z79.10 *. o... * *'*- .. 537 .. uo -. tU9*9e.s-3u *. -.- .. -- ::*.. . _.-.-
| |
| . _:_,_ . . ,:*.-':_~: ~~os.s-o-cr .. _ *: ~1 .. 2 a-zw~~-- .- :.- _._ .~.' :* -.sJ:;.;s- o_*
| |
| * _ .-~*,*:* *:_.,_o:q.oo.o--..*__ -_._. . _ 2 qo.,o *. o_., -*. ._--:- "5-37. 7 O: _
| |
| * *. rs-r-g--43*7
| |
| ._.t5 &lb 3 1&-*... *::
| |
| s-~. _... ::'. .....*.::'..'~,>:(:-.*.*::?t:,
| |
| ::_< .._,:.*_*.:<, :::
| |
| ....-
| |
| - - - - - - - .-.-~--1vrnro l1'7Q"O-: o.
| |
| " -. *_.- :* . .. *
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| * ll ooo* * * ,* * . 33 l' r; o:o * ..- -*<.:*.. _:-..* ss33 9q*~lJ-: q o*
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| -.*. . rn*-.,*ir6'97 *. - _
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| *_
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| * t 1 ao1 ~ e;-. *
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| . -" . _:- :.
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| *' *
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| *~ * *
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| .. t2n-oo-
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| .. *:13.ooo _*. * .... *.. .322. 10: 33a~o-:tr- : . - s:-cro-:2*0
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| . * :-.
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| * s.ao:20.
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| 1eor:re~a6. -.
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| t74J22*su *. .
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| - - - - ----;-tito v.o --_---:--~:=;--3:r2r;-o: o*----.::-~:-~sao-:3 o*-- -,--r&se u3 7 S'~---*-.-_ ~,: .
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| , .-. *:, - - *--.. . : * .. --*.=* ~. --, . . . -' .. *-... . . - ---:.
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| .-= .,_.:*. * -*. :-
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| - :.
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| -~**:.* .' . *-*. ..,.-...
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| o **
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| 1*.
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| .:~
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| - . -*.**-*-~**.:.-~.J.,* ... ~: . --- ..~:-:. ... *.-.\t C0 .*,"J T"VJU. - .. -
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| Eol - *.- .* *.,*-~ **
| |
| -
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| **.*- .. **-
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| .* ......
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| *_: **,.: . -.
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| .:*, --'**'* .* >
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| - ' --* -* - .
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| ..* * .. ,.* ,_.' . . , *'"_* .' **:1.*.~.'-: *.~'*a-;~ .,:_.,*: ~ ~*{ ** ''*, :.~' *~ *' ' ... "'* _. .-,** . * -.~.*=~~* .. ~' . - ~, _.:.; .-'; . * * '- ... ~~*~**~.\4'
| |
| '.~***: ****::~-!.- . **~-*. '* -*** *- -**.-" ~:. "'. '. :-, . . . ~.. .. " ... ':.. . ..
| |
| | |
| ,..;;_~~~-=---.:.--...-.....-'-~------'--~--'~_..;_:~_.;;~~;_;_.;:;._;,;..,,;;;.;...;-""..,;,.....;..-.:..~---;_;..-"-'~-
| |
| -: *.- -,_,_ :,,_~*: * *~:<_::\;r;A-BLE:'--: 4j~_l4B~ _:_:,:.: :: 'c:c*J~;r~~,::* *
| |
| -'-------'--'-'---- , _..:. .;___-~-\~-----*-::::-:-'-<----,
| |
| .~-
| |
| ***-'-c:::-*--.--~.;,-:--_.;..::~;"::::;;-~---.-
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| ".*:: ... ~- -- ~-
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| . - : ' . , -. ~' ' .
| |
| -1
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| |
| --;1fo:-s* o----111rs9 at2*.-_------*--*--
| |
| s o1-: 2 o .- *1s1osss2.
| |
| -----~irr:3*1r n*1&*oos~*....;;.- . -------
| |
| __L_- - t71.~UR&~~
| |
| 1 1T~ f o. 5 & *.
| |
| 1 I
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| |
| . - .
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| ' ' ' I I - *. ~" ."
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| |
| ,. *.. , *'*.
| |
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| .l .
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| |
| . . . ' .
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| |
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| .-. (
| |
| '***. ' :,:_."1
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| . . . * :.', .-1
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| :. .; -: *:.
| |
| . ~-.., - '
| |
| _. ---.*-:. '*.'*
| |
| *. - _,., .
| |
| . , --.*1"
| |
| ' _1 *
| |
| ; :6, 555 . . ..
| |
| 32 . !
| |
| :.* ,.'
| |
| .
| |
| .
| |
| '.
| |
| .* .... *
| |
| , ~ .- .. ' :'
| |
| . -.- *~
| |
| ** J ' - - *
| |
| . . ~.:: ;,
| |
| *-*
| |
| ' '-.
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| ."
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| | |
| *-* .. ~
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| .. -.:. .: . .
| |
| I * ....... .
| |
| ...... *.:.-.:*-*:
| |
| . *TABLE 4.2.16A, I MILLSTONE 2/CALVERT CLIFFS 1, 2 SG COMPARTMENT ANALYSIS I MAXIMUM DIFFERENTIAL PRESSURES ACROSS THE SG FOR THE ,1000 SQ. IN. HLG
| |
| * I NODES MAXIMUM DIFFERENTIAL . **TIME OF.
| |
| PRESSURE (PS ID) . * *. OCCURRENCE (SEC)
| |
| (FROM-TO)
| |
| I ''*'
| |
| *;...- ,,*.
| |
| .**;
| |
| --
| |
| ' ..
| |
| ./'
| |
| .
| |
| r:., -.
| |
| ;.:; ..:::.. -~
| |
| 0~060..
| |
| :*.::
| |
| . 6* - g '* '' ~- ..
| |
| -:* ~~ . *'.*
| |
| I
| |
| *..
| |
| .. - .
| |
| '; ' *.
| |
| . *.*.. 0~060 7 - g* . l1 ~03 5.12. 0.075 .
| |
| I 13 - 16.
| |
| 14 - 16 4.46 0 .. 029 I 20- 23 3*.45. 0.082.
| |
| 0.04T 21 - 24
| |
| * 2.a1 I 30 - 33 .. . . 1.67
| |
| *:' ..
| |
| 0.142 *-.**: ..
| |
| l'o06 0.058 I 31 - 34 6 - 36 . 13'.27 *a.060 I 7:... 36 13.27
| |
| .. 6.97 0.061 0.089
| |
| . 8 -.36 I .9' - 36
| |
| - *...... :.''
| |
| ..__-.:.' :-.. ..
| |
| ~: ,-:.- .. ..*. 0.083
| |
| .-*.*' .. **:
| |
| . . . ..
| |
| .' . . .*. . ~* ~.' .*..*. 0~092 .**.
| |
| I*
| |
| * 10* - 36' .
| |
| .
| |
| '
| |
| . :
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| |
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| |
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| |
| . *... -, .. . *,. -: .,,*:.*:
| |
| *, ... :_.,: .. *.
| |
| . ' '
| |
| I
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| ': .:... . .
| |
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| |
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| |
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| |
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| |
| ' .** ''--*
| |
| *. ,.: *.:* '. .: -_** . _..:._ -,
| |
| .
| |
| ... . . ., . . .
| |
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| |
| :*.
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| |
| * ... * .
| |
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| |
| ' *- ...
| |
| *- .. : ;_"... *.
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| *_ .....
| |
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| |
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| |
| .. ----~--~*,..._.. ...-...... _,,_....-----~-~----*~---'"-------*---------****-**---~------ .. --*-------**-..-*----**-----**.-*- -*-***-*-~~-------*--, ....,..--. *~, .....,. .. ___, _______ ., _ __...~ .......-~**,,~-....._,.~~---~
| |
| | |
| : ~* , -,
| |
| - ...
| |
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| |
| **1.
| |
| ' '*.
| |
| TABLE 4.3.168 I MILLSTONE 2/CAL VERT CUFFS 1 ,
| |
| * 2 SG COMPARTMENT ANALYSIS MAXIMUM DIFFERENTIAL PRESSURES ACROSS THE SG FOR THE 1414 SQ. IN. SLG I
| |
| . ~***
| |
| MAXIMUM DIFFERENTIAL TIME OF.
| |
| .PRESSURE * (PS ID) OCCURRENCE (SEC)
| |
| .. ,.
| |
| 24.03 0.024 9-* 6 18.20 0.025
| |
| :,_;
| |
| "'
| |
| : g. T .,*,,
| |
| ,.. '.;*
| |
| 6~92 0.04l "
| |
| "
| |
| 16 13.'
| |
| -**1 16:; 14*
| |
| 3".00 0~088'
| |
| ~** '* . .'-
| |
| | |
| .. - .. *, I
| |
| ~** *~ .... - .... - - ......... - - *:- *.
| |
| *. ,*
| |
| ' ..
| |
| . *.,* .
| |
| . . . .* ** ..
| |
| .* **.**' , .
| |
| ' *,;'
| |
| -' .... ~ .:* ' -
| |
| . . .,_. ! . '
| |
| ....
| |
| :* .. I
| |
| '. *:, :~ . *; .. '.,
| |
| , '.
| |
| ' ...*: '***--*-"
| |
| I 1,
| |
| ... ..... *.. :
| |
| i
| |
| *-.:
| |
| -*: . :..-
| |
| *'.'*:* : .*.. ; ., :*
| |
| PALISADES
| |
| .. . .. * - . ***FORT CALHOUN
| |
| . . . . . .
| |
| . . _.: .
| |
| *. .
| |
| ... *. .
| |
| .'
| |
| * *. !
| |
| *\'.'*
| |
| . 51.5' *: :.: ,,: .
| |
| '.r ~ :.:-: *' * .
| |
| : 62. 5' .: *, ..
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| 5' . 23 O'
| |
| *"
| |
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| |
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| |
| ' .. ' . " ' ~
| |
| ...
| |
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| |
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| |
| r,.*: .
| |
| . . .* ... '* *. *.>.><:::
| |
| :**_****,* . ** "l * *.*
| |
| NORMALIZEO VO~UME *. *** * 'SIMILAR
| |
| **;...... -* .. *.
| |
| TO :* .
| |
| 0.45"' ' ::
| |
| MIL~STONE .. * *. : .. ,!
| |
| ' *. : . ~; ... :
| |
| .. ,.....*....* **>> ,, ' **. ~
| |
| NORMALizfo;vENT:AREA ....>. ':'.. . *SIMILAR TO I ' * . : : .. }
| |
| *- *-*- '.;:*.' .. **:,.,*
| |
| ; *. *":-.*.**
| |
| .. * * . ** .. ..... / . . , . MJLLSTONE .. *.;.
| |
| '* ,.,
| |
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| |
| c
| |
| ._***",
| |
| . :~.
| |
| *.
| |
| :* : -
| |
| . .*.. *E.XCLUD.ES. c6~lANT PUM~'cbMPARTMENTS.
| |
| . -. -- . .-. .* .- .. *.- - - . :* '* ,._ ,. .. - - ' *.
| |
| <
| |
| -
| |
| .. *., . . . . . , *1
| |
| .:-." ..
| |
| | |
| '.,,r * *, *
| |
| * 1*
| |
| TABLE 4.3 *. 18A I PALISADES I
| |
| ,,
| |
| SG COMPARTMENT ANALYSIS MAXIMUM DIFFERENTIAL PRESSURES ACROSS THE. SG. FOR THE. 1000 SQ. IN. HLG NODES MAXIMUM DIFFERENTIAL **TIME OF*
| |
| . <I\
| |
| . (FROM-TO). PRESSURE (PSID) .
| |
| * OCCURRENCE (SEC) . . ; *...
| |
| -
| |
| ~- --~-: -~~.-:f-~-'
| |
| 6 - 9 11.41 0.060 T - 9 11.43 0.060 13 - 16 5*.05 0.076 . ,.,
| |
| ---_14_ .::-rs-----'- --- --=--__:* --*-*-~ - __
| |
| ~-----
| |
| *--:-.* ~~4. 55 _ _ _ _ - _ --~-- ______._____ Q'.;029 20 - 23 .
| |
| . *_ .:;_
| |
| 3 *. 3T 0'.083. ..
| |
| **1-
| |
| .. ~- . ;' :: ..
| |
| .-, :**. .'.*
| |
| '*.,*. -__.*.
| |
| 2:*.ag*: 0~041 l
| |
| ;
| |
| 30 - 33 T*. 58 0.144-
| |
| ,
| |
| 31 - 34*
| |
| 6:- ;..*~35::-------
| |
| 1.15 14 *.io:
| |
| 0.058
| |
| _ o.059 I*'
| |
| .
| |
| * *** ** c-~c 2t1t~ 36c7::C.;fc;i , Cf,~*.7i~~.~~~-'1:1J/fc.;~ic;f-~~: ;';;.;.~ .*c;,f~o~~~*~* ,:~~*/C;~~;;;
| |
| . 1{~ 36 .. . , ' ' i.60 *.* **. .*... .* . . 0.091 *. *
| |
| * g* - 36 7~J3 0'.085 **:. -_. ' --
| |
| . 10.' - 36*
| |
| ...
| |
| " .7'~65' . 0.094* . *1*.
| |
| * *. >j *
| |
| :.., *-.. ---
| |
| ;**....
| |
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| |
| ~
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| I I
| |
| **.- ..
| |
| ;I 4* ;.J'2.tS
| |
| | |
| ':*-*
| |
| I TABLE 4.3.188 I PALISADES SG COMPART,MENT ArrnL YSIS MAXIMUM DIFFERENTIAL PRESSURES I ACROSS THE SG FOR THE 1414 SQ. IN. SLG I NODES MAXIMUM DIFFERENTIAL TIME OF OCCURRENCE (SEC)
| |
| (FROM.-TO)_
| |
| * PRESSURE (PSID)
| |
| I .; .- - - i:--*.
| |
| ': .
| |
| . -* *' .-
| |
| _:.
| |
| I **a-* 6 14.05
| |
| ...
| |
| 0.025 24.55 0.025 I 9 - 6.
| |
| 9 - 7 18.80 0.026 I 15 - 13
| |
| - .' - ...
| |
| 7 .12
| |
| :.7 .55 0.041 0.030 "16 - 13 . ~
| |
| 'I . 16 - 14 22 - 25 23 - 20 6.33 4.60 4.84 0.026 0.041 0.038
| |
| .I 24 - 21 32 - 35 3.12 1.89 0.090 0.054
| |
| .1. 33 - 30 2.46 0.095 34 - 31 . .. 2.72 0~096 I
| |
| ,, ...
| |
| : ..,_
| |
| *'
| |
| .. ,-*.:. :- *; .~ ~* .-.; .:*:;_
| |
| 6 -*36 1-: 36.
| |
| -. -. - *_ :__ *_z,. . . - ~- *-
| |
| 9.98 .
| |
| 9.97
| |
| ;.;.-:*--- r ... _., - ~:- . *::,_:-;. _ ~-~--- . .' . , -~--
| |
| 0.101 0~086
| |
| . .; -
| |
| :*.o:~.032
| |
| .
| |
| 8-- 36* "16~00 I .. 9- 36 . 26'.35 .. ** 0.027 10 :..;. 35*. 10.05" . 0.100 I . - " .**_,,.__ .,.
| |
| I I
| |
| 1* 4-.;. ,.,.., . .
| |
| ****----*-**--*-~~--~*-*~*~***-** -* * **** ----..,..-.-~.-----~--**--------*,.----*******-**---**--**--***--********* -*******---*:***-*** , * -****--*~*-~* :--*--**-**--* -~*r- ---- ~-~*-*<"***-- ***-.**--***..,.**** ,--.***--....,.,. __ ,. ____ *..-**~-*** *-*-:-~--- .....*;"*' ..-~- *r*,*,*
| |
| | |
| FORT CALHOUN SG COMPARTMENT ANALYSIS MAXIMUM DIFFERENTIAL PRESSURES ACROSS THE SG. FOR THE lf:08 SQ. IN .. HLG
| |
| | |
| .........-'.'* *,** .;_..
| |
| .. :'.
| |
| I
| |
| .. . *. - *.
| |
| .. .
| |
| . .... -~:.: ~ '. . _. .'
| |
| . '. '**
| |
| TABLE 4.3.198 -*. ,*'. : .
| |
| '*I . *SG COMPARTMENT ANALYSIS FORT CALHOUN I I MAXIMUM DIFFERENTIAL PRESSURES ACROSS THE SG FOR THE 905 SQ. IN. SLG
| |
| . ' '
| |
| I . . NODES*. . ~*.MAXIMUM. DIFFEREtffIAL . TIME* OF
| |
| ,, , ..
| |
| .
| |
| --
| |
| .
| |
| (FROM-TO)
| |
| . .
| |
| . >8".-6: .. '.
| |
| .
| |
| :.*\' ,.
| |
| . PRESSURE ( PSID)
| |
| . ' _- :. ~ .
| |
| ... ~~-
| |
| OCCURRENCE (SEC)
| |
| . ,.' .'* .. ..
| |
| *, ,.** '.* ~. . .
| |
| *,.; *.*:
| |
| ., **,*.
| |
| I "=**..:.
| |
| :.,_. *.,*; .,
| |
| ;;..
| |
| ..
| |
| : 9. ~ 7 12~03. 0~009 I 15 - 13 4.05 ..
| |
| . .5.31 '0.018 0.021 16 - 13 I '16 -14.'
| |
| *
| |
| * I >* : * ~' ",
| |
| -
| |
| .4.47*.* .*
| |
| ,~ ,
| |
| 0.017
| |
| . 22 -*. 25'.
| |
| ' .*
| |
| .
| |
| .
| |
| . . . .*. *.. * .- 0.029 I
| |
| . ~ .. _,
| |
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| |
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| |
| : 23. _:,20
| |
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| |
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| |
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| |
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| |
| :* r '' . . i I
| |
| * 24 -. 2T .*. *., 2';.35.:'
| |
| 1.15* .
| |
| . *o-.049 0.107 32 - 35 t '33**-.. 30 . > : J.41 0.08.l
| |
| .. O;.OST 34.- 31 I . '* ..
| |
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| |
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| |
| 0'~025:.
| |
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| |
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| |
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| |
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| |
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| NODALIZATlotJ SKETCH SECTION VIEW
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| *,,,,..,,,
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| EL 50.59' ...
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| _2QT0_ 25
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| STEAM EL.,35.5':-
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| 13TO 19
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| REACTOR VESSEL
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| FIGURE 4.3.43 STEAM GENERATOR COMPARTMENT NODALIZATIQN SKETCH TOP VIEW ELEVATION - 305' TO - 0.5937'
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| ... *. ELEVATION - 0.5937' TO 2.5'
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| E lEVATION. 20~0' TO 35.5' l 1
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| I ELEVATION 35.5'. TO *sa.593''.
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| |
| f ,' : *
| |
| ' .;
| |
| ' ~ *:
| |
| I I
| |
| 1:
| |
| I
| |
| ! ':
| |
| . FrnURE 4.3.44 I"
| |
| .',. ' .. ~- . .. CEFLASH~4 RJ:ACTOR COOLANT SYSTEM NODAL MODEL
| |
| ........ *~ . * . ~.:*:'illiit. ':. *. 1-;.*_..,
| |
| -n..-*filt~tiii*
| |
| ' .......... ' I '
| |
| * _.. <9iit
| |
| \*,
| |
| * liiiii',:o . .~o:liijiiFJSl_. iliiiit :.._ *
| |
| ( *
| |
| | |
| ~
| |
| I Legend for Figure 4.3,44 t' 1. Reactor vessel downcomer.
| |
| : 2. Reactor vessel lower plenum.
| |
| : 3. -5. Reactor core.
| |
| 1:.
| |
| ,.
| |
| .
| |
| : 6. Fuel alignment plate region.
| |
| : 7. Reactor vessel exit plenum .
| |
| 8 *. CEA shrouds.
| |
| g*. Reactor vessel upper head.
| |
| I 10. Reactor outlet pipe.
| |
| : 11. Steam generator inlet plenum.
| |
| a 12. -16. Steam generator tubes
| |
| ,, 17. Steam generator outlet plenum.
| |
| : 18. Pump suction pipe.
| |
| : 19. Pump discharge pipe.
| |
| * 20.* Pump suction pipe.
| |
| t 21. Pump discharge pipe.
| |
| : 22. Reactor outlet pipe.
| |
| t 23. Pressurizer.
| |
| : 24. Steam generator inlet plenum.
| |
| t 25. * -29. Steam generator tubes.
| |
| : 30. Steam generator outlet plenum.
| |
| t 31. Pump suction pipe (2).
| |
| : 32. Pump discharge pipe. (2).
| |
| : 33. Steam generator secondary side.
| |
| I 34. Steam generator secondary side *.
| |
| --
| |
| 35 .. Containment~
| |
| 1*
| |
| I When a circumferential pipe rupture fs .
| |
| represent the severed* *pipe.
| |
| postulated~. two nodes are used to I
| |
| ,
| |
| . r I
| |
| | |
| . . '. .. ' . ~* . .'* . -
| |
| : : :.*.. ::.
| |
| ']
| |
| :-:-~1:.
| |
| '
| |
| * FIGURE. 4.3.45
| |
| ** ...
| |
| STEAM GENERRTOR COMP~RTMENT ~N~LYSIS 1000 SQ. IN. HOT LEG GUILLOTINE.BRE~K
| |
| :f
| |
| ~BSOLUTE PRESSURE OF NODES 1,2,3~4,5,s *
| |
| ,,
| |
| ::'I
| |
| - *',* .
| |
| ":'
| |
| .*
| |
| 30.00 '*-
| |
| *.. * ... *. *:.- .. *. **.*-*
| |
| --:-,
| |
| *. 8i\I*
| |
| . ~
| |
| . .. - .. . *.
| |
| - ,,.*,* , ... -* ' .. , .. : .. :
| |
| . *-'*. *2.S.00 *.**;.,. .
| |
| ;.'****
| |
| .~ ',..
| |
| .. .. *.*.
| |
| . .. ..
| |
| ..,
| |
| 2.8 .o 0
| |
| :..**.
| |
| 2.7 II 0 0
| |
| . :I
| |
| --2.s.o-o ,I'.
| |
| 2.5 .o*o -
| |
| 19.00 18.00
| |
| . 17 itOO
| |
| -~ .. * ..*. - ... '
| |
| . 16 .oo
| |
| ..' 16 .oo ... ._. -. ~- .,. .:
| |
| 14:.00u-r-~-t-~-+~--1-------1~--.,,t--~t--~-t-~-:t--~-t-~-1
| |
| *o: *o 0 0 0
| |
| : 0. o*
| |
| . 0 0
| |
| 0
| |
| .. 0
| |
| +
| |
| .. '
| |
| 0
| |
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| |
| Iii.
| |
| - co*
| |
| *... 0'
| |
| --*J;...~.ti6 *:*:*
| |
| | |
| . -:
| |
| .. . ~ ' .
| |
| '**:.*:. ...
| |
| .**.: *... :
| |
| I.
| |
| ' " .
| |
| '*,. **-*. '..".*'. . .. ' .* - . - *....
| |
| *. - . ~ . _. ....... -" -FIGURE:. 4.3.46 .**
| |
| .
| |
| 'I
| |
| ' *. ~ ..:. *
| |
| ,, *-
| |
| .. **
| |
| *. ':.*.
| |
| STERM GENERRTOR COMPRRTMENT RNRLYSIS 10 0 0 SQ *.
| |
| * IN m HOT LEG GUILLOTINE BRERK
| |
| ..~, RBSOLUTE PRESSURE OF NODES 7~8~9~10~11~12.
| |
| I .**_.*..
| |
| ....... .-.* ...
| |
| ~ ,. . ' .. .
| |
| 1* 3'0'.00
| |
| .I!
| |
| ,. ' 2.8*00
| |
| *I 27 .oo 2.6' ia 0 0
| |
| : .. ,.
| |
| '**2.5 *. 00 11*
| |
| ... ,:'". ;.':
| |
| *:.' .. ~:: -. *,\ ,-.
| |
| 2..4.00 a:*'
| |
| i H'
| |
| ~-
| |
| w m\
| |
| 2.3 .:oo
| |
| 'I n::: 2.2. II 0 0
| |
| ::l
| |
| (/)
| |
| ~* 2.1~00
| |
| 'I 0:::
| |
| a..
| |
| *
| |
| * co*.ao
| |
| .. ;._ . : :~;;~_*:::~* .:F:~.i:.~\;~~1\_\ :*:. ~:.
| |
| :I \<19:'~00
| |
| : . ~-. :; ~. ~- ...... '
| |
| 18 aO 0 I*
| |
| .,,
| |
| ('., ,:**:,_*.
| |
| *:
| |
| *. .*15 "0 0
| |
| ,,
| |
| 14.00
| |
| *. **
| |
| * I
| |
| .- .-.. II II*, ".
| |
| I ._,.*
| |
| : o. ,''
| |
| , ,
| |
| 'TIME.'SECONDS .
| |
| I "
| |
| *. :-
| |
| ---
| |
| . *-",''
| |
| ',
| |
| | |
| -::":i,._ ;~**.-~:;,.
| |
| . FIGURE 4. 3.47
| |
| * .:**-'*-*-*~ ** -:.*,..,**;:* :.~* ""'° "*** *c*.-~ *-.-~-* *
| |
| .* .
| |
| .*.***.
| |
| *.
| |
| ;11*
| |
| .. - .**:* *: .:;_*****;..
| |
| .
| |
| :_::_
| |
| _.,*.
| |
| *
| |
| *.* *.rt' STERM GENERRTOR COMPRRTMENT RNRLYSIS ... ~
| |
| 1000 SQ~. IN. HOT LEG GUILLOTINE BRERK
| |
| ..
| |
| '
| |
| RBSOLUTE PRESSURE.OF NODES 13~14~15~16~17~*18 I
| |
| ~
| |
| _.,
| |
| > '.I
| |
| . .:. . **.I
| |
| . i
| |
| ... ' ' . .
| |
| ,j~ff.'
| |
| 2.9=0 0 .:* . *.: . .. :"' ..' .*.. *** . *., .*
| |
| ,
| |
| ; .'*
| |
| * *
| |
| * w * *~*** .,.;* ,' ... *' **' .*, ... . '\ .,- .
| |
| *c.s.on ,. *'*
| |
| . .. .. *~:*
| |
| . 2.7.
| |
| !I' 0 0 G+-
| |
| .
| |
| .
| |
| _* ..... .
| |
| . . . . . . *,
| |
| **~* ~:~~~: £_6._o.o_ --~- _ .c o: I.
| |
| .*
| |
| ~- 2.4.a,001 1~- 2._3 ~ 0 O.Gt-w I
| |
| .. *
| |
| * * ... Jili; I~ 2. 2. a 0 0 of-:
| |
| ''.:)
| |
| . (f)
| |
| :*. __ -'---~:--2;i ~.o*o
| |
| ~ . -~':_~-~c~; ~-~e.~~(/()
| |
| .
| |
| **.!
| |
| . *. ~-*~*- 'tGI~sf:-~~~;~=~;J;:;i;NE<f{~~4~1ts; \.fkl*~:
| |
| _". ;_I
| |
| . *. . * ....
| |
| 1Ta00
| |
| -:1* .
| |
| ~~*"
| |
| . '-; **~'
| |
| .. ' -.
| |
| . . .. . * :. *.. <.;.. ..
| |
| J.. 6.0:0
| |
| *.*
| |
| * 15.wO 0 14 I! 0 0 qM-~~I.---2;----+-2;---25-....---c!;;----"--!ch
| |
| ...
| |
| *.** .***Ji** ,. ~ ...
| |
| * o o a a a o o
| |
| 0
| |
| ...
| |
| a
| |
| ..
| |
| .~* .*~
| |
| a
| |
| . . -~
| |
| a.
| |
| ***
| |
| o 00
| |
| *. .
| |
| a*
| |
| 0
| |
| ..
| |
| *1
| |
| * 0 ~: ?'"
| |
| *-----------------=.::...:.=--=-=,.::..;;.:.."'-=-'"-----------,...-----' .TIMEJiSECONDS 4"*3-. 178
| |
| *.; ' .. *. **
| |
| I ,_.
| |
| .....
| |
| * t'
| |
| ,. . . . . ..
| |
| '.: *~.. '
| |
| ..
| |
| L
| |
| | |
| =*
| |
| i*-- FIGURE 4.3.48 .
| |
| 1:.
| |
| :I STERM GENERRTOR COMPRRTMENT RNRLYSIS 1000 SQn IN. HOT LEG GUILLOTINE BRERK RBSOLUTE PRESSURE OF NODES 19~20~21,22~23~24 I
| |
| j . ,._ .
| |
| 30.ooJ
| |
| 'I 2-9 .oo°t I 2.8 .oo I I I ,_.--'
| |
| 2.7 *. 001 2.6 .ooot I .I .
| |
| I 2-5. ooot
| |
| '
| |
| )I:--* I!Hcr 2.4.00G-j- I
| |
| .
| |
| a- !~ 2.3 .001 *l I I
| |
| I~ 2.2. *. 00 1 1 f .
| |
| 1 ~ 2.1.000j ~
| |
| a.... :
| |
| j 2.0 .ooo+- 1
| |
| * I l.
| |
| 19 0 0 o+- I .'t;~' ' ' ., ., j.3 .;cf .
| |
| I II
| |
| .,,..~ ~ I
| |
| . -. I 18 .,_Q 0 (}!-
| |
| I -* .
| |
| ..... ..:.** ',_
| |
| . *.. -.* ! . . *.: -* ~--:
| |
| ~::::J
| |
| :1*. .* ..-::.*:*_ . . ' .**-* .. *
| |
| *f) .. ;_
| |
| 15.00 I 14 0 0 0:>-~-__.,__-1-----1---4---4----1-----2:;*-~*-
| |
| II ~
| |
| !'
| |
| *1 i I
| |
| a 0
| |
| 0
| |
| **
| |
| 0 0
| |
| ..
| |
| (\j C)
| |
| C)
| |
| ..
| |
| ...r a
| |
| a
| |
| (.D
| |
| ..
| |
| 0 0
| |
| co*
| |
| **
| |
| o 0
| |
| 0
| |
| ***
| |
| I
| |
| .
| |
| 0 .-f I ! TIME., SECONDS
| |
| | |
| - I FIGUP-E 4.3.49
| |
| *' ~1
| |
| * _,-
| |
| :1 STERM GENERRTOR_ COMPRRTMENT RNRLYSIS 1000 SQ11 IN. HOT LEG GUILLOTINE BRERK RBSOLUTE PR~SSURE OF NODES 25~26~27328~29~30
| |
| ,,
| |
| I 35 .OOGr *.1
| |
| .,,,.,_
| |
| 34 .ooo+- . :.
| |
| .,
| |
| '' . ~
| |
| .... ' .
| |
| - ' ._,.
| |
| 33 .oo 32.00 I
| |
| ---
| |
| I'
| |
| '~ ....... ,..,
| |
| -----* ------=-- 'II
| |
| - '
| |
| ---~---
| |
| *- ., __
| |
| - -- - - - ----
| |
| -
| |
| :I' ~--* .
| |
| 1*
| |
| 18.00 17 110 0 16 Ii 0 0 15 .. o0 {I 14.00 H-~+---i~--+~-t-~--t-~--t-~-t-~-+-~-t---t a a a a
| |
| a a
| |
| a a
| |
| a j
| |
| .
| |
| a .0 a a
| |
| .. ru ....t- - U>
| |
| *-*
| |
| 00
| |
| * a a
| |
| * TIME.?JSECONDS
| |
| ~
| |
| * i,.,
| |
| | |
| *I'* FIGURE 4. 3.50 STERM GENERRTOR COMPRRTMENT RNRLYSIS 1000 SQ. INas HOT LEG GUI~LOTINE BRERK I .-.
| |
| RBSOLUTE PRESSURE OF NODES 31J32.J33~34~35~36
| |
| ,,I' I '
| |
| 30 *. 000-:-
| |
| ,-,
| |
| 2.9 .o 0 I~ .**
| |
| * ;T' *
| |
| ; *. *,,,'*.-:
| |
| ' . ,* ...
| |
| 2.8. 0 0
| |
| *I, 2.7 a 0 0 G-j .*. iI i I l:,7 2.6asOO°r .*.
| |
| *
| |
| ~11 2.5.00l*
| |
| 2.4 ~ 0 0 1.,, 1cL H
| |
| U) a.. 2.3 .ooJ. , .. * '* . .. *;
| |
| ',
| |
| ..
| |
| '
| |
| .
| |
| .oo+
| |
| S\
| |
| w 1
| |
| 1 n:::
| |
| !~ 2.2.
| |
| ,..-'\
| |
| I~ 2.l 0 0 11 I '
| |
| 1R: 2.0 .o 0 i I ,.
| |
| ...*
| |
| .. *:*:.-: .
| |
| I *. 19'.0 0 I 18.00 lTaOO
| |
| .., ..
| |
| **~
| |
| I '16. 00
| |
| .,, 15~00
| |
| '*,-.*_*,.**
| |
| . . '.::: -:' *:~:~***
| |
| .. , *.*-*.,
| |
| .. , .-.
| |
| ";*:: .. *. .
| |
| '* .. *
| |
| . - ..
| |
| ~ - '
| |
| **- ,I- .'
| |
| ._, .. _ *-
| |
| : 1. 14.00 H---1r---t-~--t-~-t-----i~-+-~-+-~-t--~1--'--~'
| |
| 0 0 0 0 0 0 0
| |
| 0
| |
| * 0
| |
| (\J
| |
| * 0
| |
| ..
| |
| ..q-0
| |
| (.0
| |
| * 0 co
| |
| **
| |
| 0 0 .,
| |
| I 0 TIME.!! SECO~N~DS~-.,-----...--- _ _
| |
| .-+
| |
| I .- .: ' .
| |
| . .
| |
| .
| |
| - ... .
| |
| . .
| |
| ,* . .
| |
| *.
| |
| .
| |
| .
| |
| .
| |
| :
| |
| .
| |
| .
| |
| . ' . .
| |
| - .. . . : . ~~ :.:_:
| |
| . : .. . .. ~ *: -
| |
| ' .
| |
| - .._
| |
| *A-.~.ICll
| |
| | |
| --*-- **
| |
| -- -"------~--- --~ - *- -~ *--:- -..._~.._ *:-~- : .... *- - ~:- _- *-:.*.,- - -. : :. _:.,:_ ~ : ::*:. ;:...:_ --:_--:---: - ** - *** - : . - : - .:.--;::.:;:.~- *.....!.;! '..... ----.**-:-~;*-~_-:......__ *- . . . . . . . -- ______ ....:.:.*--*-------*-*~.:---*--'---*~* ~---~*..!:.=~-~ *.;,,.....,..::,_~;,.~~* _:,,.:..__._.
| |
| .*. ..J',;..;_;.--~~-...-.:.0..-.....:........ __ ~-~--*....:..'..:~.:_,,.; __ ._*, .. ;;. ...... - .
| |
| FIGURE 4.3.51 **:1**.
| |
| STERM GENERRTOR COMPRRTMENT RNRLYSIS
| |
| . ,,,
| |
| \__,_, .
| |
| 141~ SQ. IN. SUCTION LEG GUILLOTINE. BRERK RBSOLUTE PRESSURE OF NODES 1~2.~3~4~5~6
| |
| . 2.5 *. o0
| |
| . *-.. *****
| |
| **.* ' -.. ' . . . . .... ' ....~.
| |
| < ._, .
| |
| ... ... '
| |
| 2..4~00 . *,,_.
| |
| 2.3.00 2.11100 er ..
| |
| H' (j) a..
| |
| II\
| |
| 2.0. 0 0 w
| |
| 0:::
| |
| ::::::>
| |
| -*- -----(]). CJ) -19 . . .... 0" *I;)- _.
| |
| l.!J
| |
| ~~c~._,___
| |
| :--~~ ~~-.ts~o=o-
| |
| .
| |
| *
| |
| :I 17.00
| |
| -,-=.co.o~ - '- *. ~cr:£i; 16.00
| |
| *. I ~ .- . --.
| |
| 15* *. oo
| |
| **-
| |
| * .....
| |
| ...... * .....
| |
| ,:,:.
| |
| *:
| |
| :.
| |
| ,-.***
| |
| ... . * *. ;
| |
| -_,.'.'-''
| |
| .*.. *.* ...*.. .*...
| |
| 'fl .
| |
| ,, ~
| |
| 14
| |
| * 0 0 tt---+---+----t-...,.-,..-1r--+----t----r---+---+----1
| |
| .
| |
| 0 0
| |
| 0
| |
| **
| |
| . O*
| |
| o.
| |
| ...r
| |
| *..
| |
| q 0
| |
| <.O*
| |
| Ill 0
| |
| 0 co*
| |
| ..
| |
| . o.
| |
| 0 0
| |
| ..
| |
| I\
| |
| 0 *. . ~-- ..
| |
| . TIME.!'.' SECONDS *
| |
| . .. .. -. ..
| |
| .
| |
| | |
| _ ... ------.:...'-~~-" *-*~*'-'-**'*'-'**;'-""-'c- -- '-"-'."~c **'-'- 0""'**-*'*-*~'"'--'*''-'-*---"~'-*'"'**'*'-"-''""'''"'.2.=,,.~.~ -~'-'-.;.~oc.:.*.~--~'' *'*-*- "''". . k . "'*'-"*-;-"'"**-**~~-~~~*~**_.,,- *-~
| |
| -**-*--- .. ~:c..;.....
| |
| . **--L .. ;:;.*. :"'
| |
| I **.FIGURE 4.3.52 : *._*.* ..
| |
| I STERM GENERRTOR COMPRRTMENT RNRLYSIS 1414 SQ. IN. SUCTION LEG GUILLOTINE BRERK
| |
| *j RBSOLUTE PRESSURE OF NODES 7~8~9~10~11~12.
| |
| j a **:~
| |
| 45 *. oo 44.00 *,.-* ., .:-;;*.
| |
| I 43.00
| |
| . 42..00
| |
| .;::, *-'*;
| |
| **'.-*
| |
| . ~-
| |
| *.
| |
| a
| |
| ~; ~'
| |
| 41.00 40*00 39.00 38.00 I\~.*
| |
| 37 ... 00 36.00 I
| |
| I .
| |
| --*!
| |
| I 35.00 i
| |
| . 34 *. o 0 331100~
| |
| * * * *r'
| |
| ,
| |
| er I H 32.... 00
| |
| ~ ~t:~~~~ ... *. .. . . . . .* * * . ..
| |
| .
| |
| .,-~
| |
| \ '
| |
| ~~
| |
| ~-
| |
| ~
| |
| 2.9
| |
| * o o 2.8.00 2.7.00 2.6.oo-
| |
| ~I - ~
| |
| r l- .
| |
| ~
| |
| f.
| |
| -
| |
| I
| |
| _,:.
| |
| 2.5.00 . ,<>-*: ::: .>/~
| |
| I,_,,_
| |
| 2.4.00 2.3 0 0II 2.2.. 0 0 I 2.1 *. 0 0
| |
| . 2.0. 0 0 ;;:*.\*
| |
| ,,
| |
| I 191100 18 *. 00
| |
| *17.00 16 .oo 15.00 i' ;
| |
| "
| |
| ,.
| |
| I 14~00Q----~---~--~--~---+~---~--~-----
| |
| a 0 a 0 0 a*
| |
| a C) 0
| |
| * 0 c\.J
| |
| **
| |
| a
| |
| .....r
| |
| * a U)
| |
| .. ':*.
| |
| a
| |
| .co
| |
| .. o.
| |
| 0
| |
| *
| |
| ..;*
| |
| TIME.' SECONDS l ~-~--~-. . ... ' *. . ~ l~ '";. . "*
| |
| L - - _ ... _. _ _ . _ _ ; _
| |
| . "_ _ _ ; '4-.:..,_*_..._.'- -
| |
| | |
| - -* ** ........... ,_,., .. -- '"" .. ...
| |
| FIGURE 4*. 3.53
| |
| :1*
| |
| -------------.----.Ii STERM GENERRTOR COMPRRTMENT RNRLYSIS 1414 SQ. IN. SUCTION LEG GUILLOTINE BRERK RBSOLUTE PRESSURE OF NODES 13~14~15~16~17~18 I
| |
| 'I 30 .oo I
| |
| 2.9. 0 0 I 28 00 II
| |
| *a 27.00
| |
| -. -2.s. o*o
| |
| _,_____ ___ _
| |
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| I FORT CALHOUN STEAM GENERATOR COMPARTMENT ANALYSIS 905 SQ. IN. SUCTION LEG GUILLOTINE BRERK I ABSOLUTE PRESSURE OF NOOES13.14.15.16.17.18 I
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| 'I FORT.CRLHOLJN I STERM GENERATOR COMPARTMENT ANALYSIS 905 SQ. IN. SUCTION LEG GUILLOTINE BRERK ABSOLUTE PRESSURE OF NOOES25.26.27.28.29,30 I
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| | |
| *1 I APPENDIX A I SELECTION OF A FLOW MULTIPLIER FOR MASS AND ENERGY RELE.Ci.SE CALCULATIONS I Recent blowdown experiments performed by various tests (References A.1, A.2 and A.3) have indicated that use of a combination critical flow
| |
| * iI .
| |
| correlation predicting the blowdown mass release rates is required. This*
| |
| is due ta differences in the flow process when the.fluid stagnation conditions are subcaol ed and saturated. Al 1 of these test data demonstrate -
| |
| * the influence of some degree of non-equi 1ibrium between the phases for ii subcao1ed and very low quality f1uid conditions. But for the remainder of the. saturated regime only equilibrium state prevails.
| |
| II The combined Henry/Fauske and Moody correlation described in Reference 3.7 reflects these influences by the assumptions used in its derivation.
| |
| However, the test data mentioned above has shown that the mass flow rate from the vessel through a short length of pipe is over-estimated by the corr.bined Henry/Fauske and Moody correlation throughout the whole blowdown period. * *:**
| |
| For the actual reactor system following a postulated pipe rupture this over-estimation in the subcooled and low quality saturated blowdown may be -i-~
| |
| amplified since the existence of upstream geometr-y may enhance the phase mass and heat transfer, and bubble formation processes. Upon reaching the throat, the phases are closer to equilibrium than existed in experiments which had no upstream geometry. In the saturated blowdown, a much less appreciable slip value, expected in the reactor system, may. result in lower flow rate than the prediction of *Moody's theory. Furthermore, blowdown tests performed by Sozzi and Sutherland (Reference A.4) have revealed that critical flow rate decreases with increased throat diameter regardless of flow regime. Non-ideal nozzle shapes of ruptured geometry along with a larger break area in the postulated ruptur_es will result in further decreasing the* blowdown rate. * ';** .;-.*
| |
| Comparisons of pressure vessel fluid pressure data from LOFT-Test Ll-2 (Reference A. 2) with CEFLASH-4 show that CEFLASH-4 pressures during the early phase* of blowdown agree well with LOFT measurements when the Henry/
| |
| Fauske correlation in conjunction with a 0.7 flow reducing multiplier was used. Reported values of the .Moody flow multiplier for a large number of published saturated blowdown experiments are summarized in Reference A.5.
| |
| The Moody multiplier has always been found to be less than unity. The
| |
| * fact that it is approximately equal to 0.7 is probably due to the over-e~timation of phase slip ratio.
| |
| * Based dn CEFLASH-4 verification against available data and realistic assessment of break flow rates in the reactor system, the combined Henry/
| |
| Fauske and Moody correiation with a flew multiplier of 0.7 provides a reasonab1e prediction of critical flow rate from subcooled and saturated fluid stagnation state. .:
| |
| .:.**..,.
| |
| | |
| ...... *'
| |
| *. . .
| |
| .,
| |
| | |
| ==REFERENCES:==
| |
| | |
| I
| |
| .: ~.
| |
| A.1 Hall, O.G., "A Study of Critical Flow Prediction for Semi-scale*
| |
| M00:-1 Loss-of-Coolant Accident Experiments," Tre~-Nureg-1006, December, 1976. I A.2 Robinson, H.C., "Experiment Data Report for.LOFT Non-Nucl°ear*Test Ll-2 ,. 11 Tree-Nureg-1026 ,. January, 1977.
| |
| Hutcherson,. M. N., . 11 Cantri bution to the- Theory of* Two-Phase Bfow-I A.3 . Down Phenomenon, 11 ANL/RAS.. 75-42, November,. 1975. * . .. . * * *. *** .
| |
| * A.4 *.
| |
| * Sozzi, li.L., and Suther'land, W.A., "Critieat Flo;:, Of Saturated an~ * *. * .
| |
| . . . ** j~~~~o~~~ ~a ter at High Pressure," G. E: Report .NEDD-13418, .*..... **. .*.****.*.. / ;.;:~1 5
| |
| A.5 Ardron, K.H. and Furness, R.A., 11 A Study of the Critical Flow
| |
| *Models Used in Reactor Slowdown Analysis," Nuclear En$ineering and Design 39, 1976, P 257-266~
| |
| ._.'
| |
| ..
| |
| .- : . .
| |
| *.**:
| |
| .
| |
| -.
| |
| *, '., .,..
| |
| " ...* ,*' -* *...
| |
| -;;
| |
| :*.
| |
| ;*.
| |
| *.: ,*;
| |
| **** .. *.. ::* . ~ *..
| |
| 'J '
| |
| *' I
| |
| \, "~
| |
| '**
| |
| ,.
| |
| I
| |
| | |
| I l I 4.4 BLOWDOWN LOADS Hydraulic blowdown loads refer to the thermodynamic and hydrodynamic I induced forcing functions that occur throughout the primary reactor system during a postulated Loss-of-Coolant Accident. These forcing I functions consist of the space-time distribution of fluid pressures, flow rates and densities.
| |
| I The transient pressures act directly on the adjacent structures. In I addition, changes in the-flow rates and fluid densities result in transient drag forces which also act on adjacent structures.
| |
| I The plants represented
| |
| .
| |
| by the RCS Asymmetric Loads.Evaluation
| |
| '
| |
| Owners' Group are Calvert Cliffs, Millstone 2, Palisades and Ft. Calhoun. In I order to obtain the blowdown loads forcing functions for these plants, a single generic plant was analyzed. In addition, modifications to I this generic analysis for specific plants were performed as require*d.
| |
| The following discussion pertains to the decompression (pressure I loads) analysis and to the drag force analysis.
| |
| I 4.4.1 PRESSURE LOADS The transient pressure, flow rate and density distributions have been I computed with the CEFLASH-48 computer code according to the methods documented in Reference 3.9. These calculations are valid for both I the subcooled and saturated portions of the decompression.
| |
| I The CEFLASH-48 computer code is based on a node-flow path concept in which control volumes (nodes) are connected in any desired manner by I flow areas (flow paths). A complex node-flow path network is used to model the primary reactor coolant system (RCS).* The CEFLASH-48 modeling procedure has been compared* to a large scale experimental I b1owdown test with exce 11 ent agreement (Reference 3. 9.
| |
| I I
| |
| I 4.4. l
| |
| | |
| I 4.4. 1.1 Summary for Reactor Vessel Internal Pressure Loads I
| |
| Calvert Cliffs was selected as the generic plant to be used in the blow-down loads analysis for the*RCS Asymmetric Loads Evaluation. Two breaks I
| |
| at full power were identified for the generic analysis. These were a double-ended guillotine break at the RV inlet nozzle and a 135 sq. inch I guillotine break at the reactor vessel outlet nozzle (see Section 4.2).
| |
| I Analyses for Mi 11 stone 2, Pa 1i sades and Ft. Ca 1houn employed the generic plant (Cal.vert Cliffs) blowdown loads model. I The break sizes, opening times and locations for Millstone 2 and Palisades are identical to those determined for the generic plant, Caivert Cliffs.
| |
| I
| |
| -----..,------Also-,- the- reactor vessel --volumes are *verr-simi-lar -(within 2%)_ to~ _th~_ generic
| |
| ---~plant-;-- ~r-hus-,--the---resu-1 ts-from- the--generi-c plant analysis are di.rectly I applicable to Millstone .2 and Palisades~
| |
| I The Ft. Calhoun break size is different than that for the generic plant and the reactor v~ssel volume is less. The use_of the larger geheric plant vessel volume for Ft. Calhoun is conservative (see below). The break I
| |
| sizes for Ft. Calhoun can be adjusted by the ratio of the reactor vessel volumes of the generic plant to Ft. Calhoun. This is explained further I
| |
| - -- ----- ~
| |
| in Section 4.-4. l-.3 ~-
| |
| -----==--~--=--~~-=-----== =~=:.=-=----~--- - -:.-
| |
| -~-----------"________-----~-~-~~ ~~:-~-=~~-~~---~~:-~~~==~--- --f~---=__-_-:_-_--:~ ==---~~=-=--==:----=---===----=-_=---:=-----~--:..~-----=-=----:-_--"'-=:~=~-~---=---=--- --=-
| |
| 4.4.1.2 Generic Plant Analysis I
| |
| As indicated above, Calvert Cliffs was chosen. to be the generic plant for the blowdown loads analysis in the RCS Asymmetric Loads Evaluation. I This selection was based on the fact that the predicted subcooled decompression ( i niti a-1 pressurizer pressure mi nus the i sentropi c saturation I
| |
| pressure) for Calvert Cliffs is greater than or equal to the ~ubcooled de-compression for the other plants. -Also, the sizeable geometric dimensions I
| |
| . for.Calvert Cliffs indicate that these blowdown loads will be representative or greater than those for the other plants included in this study (larger* I pressure differences across components will. result from the longer pressure wave travel times). I 4.4.2 I
| |
| --------------- --------- ... ***-***-***-*-**-*
| |
| | |
| I T~o guillotine breaks were d~fined, one at the reactor vessel I inlet nozzle and one at the reactor vessel outlet nozzle. A suinmary of the break parameters is given in Table 4.4.1.
| |
| Operating conditions and certain geometrical data is I presented in Table 4.4.2 for the plants represented by the generic model.
| |
| I 4.4.1.3 Plant Specific Analyses I
| |
| A procedure was developed to obtain plant specific 'hydraulic loads from the I generic plant CEFLASH-4B computer model. The plant specific pipe break area was. adjusted _by the ratio of the reactor vessel volumes of the generic plant I to the specific plant. This factor is a measure of the time for the pressure
| |
| *to drop to a given value for systems of different initial fluid volumes and I break sizes. The plant specific hydraulic loads were computed using the corrected pipe break area with the generic plant CEFLASH-4B model. The equation for computing the corrected break area is given below. The basis for I this representation is to obtain an equivalent decompression in the generic model for the appropriate plant specific break area ~nd vessel* volume.
| |
| I
| |
| *I Areacorrected = (A/V)plant x Vgeneric (1) specific plant I
| |
| The plant specific pipe break areas and break opening times are I summarized in Table 4.4.1. The RV inlet breaks defined in Table 4.4.1 are all double-ended for each plant. Ft. Calhoun has 24 in. diameter I cold legs and 32 in. diameter hot le~s compared to 30 in. and 42 in.
| |
| diameter pipes, respectively, for the other plants.
| |
| I I Due to the ~imilarities of the Millstone 2 and Palisades vessel volumes with Calvert Cliffs (generic plant) (see Table 4.4.2) additional CEFLASH-4B computer cases need be run only if the break sizes or I loc~tions were different than those determined for Calvert Cliffs.
| |
| I I 4.4.3
| |
| | |
| I The break sizes, locations and opening times for Millstone 2 and Palisades are identical to Calvert Cliffs (Table 4.4.1). Thus, the existing I
| |
| generic plant CEFLASH-48 results can be applied to Millstone 2 and Palisades. I The Ft. Calhoun corrected inlet break area was calculated according to I the procedure described above. From Equation (1) and Table 4.4.2:
| |
| I Areacorrected = (A/V)Ft. Calhoun x VCalvert Cliffs
| |
| = (905 in 2/3014 ft 3) x 4595 ft 3 I
| |
| = 1379 in 2 I
| |
| The corrected break area was used in the generic CEFLASH-48 model with
| |
| -a 23 nisec break opening ti'!1e as_:specified.___ I Likewise, the Ft. Calhoun corrected outlet break area was calculated using Equation (1) and Table 4.4.2 to be 305 sq. inches. This* break area was I
| |
| used iri the generic CEFLASH-48 model with a 20 msec break opening time.
| |
| -I 4.4.1 .4 Results of the Slowdown Loads AnaJysis I
| |
| ------- I ~ ~-
| |
| Double-Ended Inlet Break Results I
| |
| A representative absolute pressure result from the generic plant double-ended inlet break case is shown on Figure 4.4.l. This figure represents I the volume node closest to the broken nozzle . The pressure in the annulus rapidly decompresses during the first 120 msec and then fluctuates at about 1450 psi a with reducing amplitude.* (The isentropic saturation pressure of the sid~ is 1468 psia. The strong initial decompression wave travels through the reactor vessel until the isentropic saturation pressure is reached in the outlet plenum. Then, the pressure throughout the reactor vessel ceases to drop rapidly.
| |
| 4.4.4
| |
| _J
| |
| | |
| I Figure 4.4.2 shows the peak delta pressure across the core support barrel (inside-outside) which occurs at the nozzle centerline elevation.
| |
| I The magnitude of the initial delta pressure pulse decreases substantially for locations down the annulus.
| |
| I I
| |
| A plot of the pressure difference around the core barrel (difference I between two annulus no4es 100°*apart.) is presented on Figure 4.4.3.
| |
| The pressure difference around the CSB (and on the inside of the reactor I vessel), the so called asymmetric load, is less than 80 psid after 200 msec.
| |
| A polar plot showing the absolute pressure for each of the nodes at the I nozzle centerline elevation is provided on Figure 4.4.4. Figure 4.4.4 shows the pressures starting to equalize at 25 msec. The core axial I de1ta pressure is given on Figure 4.4.5.
| |
| I 135 Sq. Inch Outlet Break Results A representative absolute pressure plot from the 135 sq. inch outlet I break case is shown on Figure 4.4.S. This case was run to a transient time of 1000 msec since the break size is relatively small and results I in a slow rate of subcooled decompression. Delta pressure rgsuits across t~~_core qarre1 (inside-outside) are provided on Figure 4.4.7.
| |
| I It is seen from this plot that the magnitude of this load is relatively small compared to the double-ended cold leg break results shown on Figure 4.4.3.
| |
| I It is seen from Figure 4.4.8 that the outlet break results in a symmetric decompression around the annulus (difference between two annulus locations I 180° apart). This figure is representative of the other pressure differences at other azimuthal as well as axial locations. This result is expected since the decompression wave must travel through the core I barrel internals to reach the lower plenum from ~here the wave propagates uniformly up through the annulus. The core axial pressure difference is I given on* Figure 4.4.~.
| |
| I I
| |
| I 4.4.5
| |
| ---------------- -*********** . ., **--- .
| |
| | |
| RESULTS OF THE PLANT SPECIFIC ANALYSES Results for Millstone 2 and Palisades*
| |
| The generic plant inlet and outlet break results are applicable to the Millstone 2 and Palisades plants and are described above.*
| |
| Results for the Ft. Calhoun Inlet Break.
| |
| Figure 4.4.*10 shows the pres~ure difference across the core support
| |
| .barrel (inside-outside). This figure provides a comparison of the Ft. Calhoun and generic plant analysis results of the peak delta pressure across the CSB. The two cases predict identical results through the first the* core barrel (differe-nce between two* aimu*lus- nodes 180°* apart) is given in Figure 4.4.11 for both Ft. Calhoun and the generic plant. The two cases exhibit similar results through the first 25 msec. The core axial delta pressure is compared on Figure 4.4.12. I Results for the Ft. Calhoun Outlet Break I
| |
| at the nozzle centerline elevation. The symmetric decompression around the annulus is typified by Figure 4.4-15. This expected phenomena was I
| |
| explained above for the 135 sq. inch outlet break. The core axial pressure difference is given on Figure 4.4-16.
| |
| I I,
| |
| I I
| |
| I 4.4.6 I
| |
| | |
| I I 4.4.2 DRAG LOADS I During a rapid blowdown strong rarefaction pressure waves travel through the reactor primary system resu*lting in .large pressure gradients I across various reactor internal components. These pressure gradients, in turn, result in an acceleration (deceleration) of the primary circuit
| |
| : 1. fluid which causes an increase (decrease) in the associated component*
| |
| drag load. The loads resulting from the depressurization are discussed I above.* This section is concerned with the drag loads.
| |
| 4.4.2.l CEA Shroud Drag Loads I
| |
| During a blowdown the flow from the upper guide structure and into the I hbt leg nozzles undergoes a rapid change in magnitude and, possibly, direction. These give rise to transient drag loads on the individual I *CEA shrouds and to a tota1 load on the upper guide structure (UGS).
| |
| These loads add to.the transient pressure loads (which for the case of I the CEA shrouds consist of an inertial component).
| |
| I 4.4.2.l.l Summary for CEA Shroud Drag Loads I The procedure for the analysis of drag loads was to select a generic plant (Calvert Cliffs) and to determine the crossflow drag factors I for that plant. The drag factors on the UGS were determined from a flow model experiment. The experimental data was scaled to represent the actual forces on a reactor UGS. The sea 1i ng factors consisted of I geometrical scale factors as well as* the transient momentum parameters for the hot leg nozzles as computed with the CEFLASH-48 code.
| |
| I The results of this generic analysis were related to each individual plant.
| |
| Where necessary, appropriate modifications were performed to account I. for specific plant features.
| |
| I I
| |
| I 4.4.7
| |
| | |
| 4.4.2.l .2 Description of Upper Guide Structure I Plan views for the shroud arrangements in the*upper guide structures are shown for Calvert Cliffs (Figure 4.4.17), Millstone 2 (Figure I
| |
| . 4.4.18), Ft. Calhoun (Figure 4.4.19) and Palisades (Figure 4.4.20).
| |
| * It.is seen that the UGS shroud arrangements are quite similar for -
| |
| I Calvert Cliffs and Millstone 2. The layout for Ft. Calhoun is similar in concept to Calvert Cliffs but smaller in overall diam~ter I (indi~id~al shroud diameters are the iame, however); For Palisades, the overall* diameter of the UGS i*s similar to that for Calvert Cliffs. I The indi_vidual shrouds are different, however, being of a cruciform design. Additional information on the various upper guide structure~ I is given in Table 4.4.3.
| |
| 4.4.2.l .3 Upper Guide Structure Drag Factors I
| |
| - - - -The dr_ag_ factors -fo-r- :ca-1 vert cH ffs riave been deve lope a- frorri geometr1ca lly similar experimental data as normalized drag force per unit axial length of CEA shroud at several discrete axial elevations. Forces have been normalized with respect to vW 2 (momentum parameter) of the scaled_
| |
| reactor outlet nozzle. A description of the procedure employed to
| |
| -
| |
| I obtain th~se drag factors is given in Section 6.1 of Reference 4.4.l.
| |
| The drag factors have been developed in order to give crossflow loads on individual CEA shrouds and, by appropriate summation, on the entire I
| |
| ~-~==~~=--~~-' ----upper guide ~structure.-~- ~ * - - - . :_ - __
| |
| - - - -- - - -- - - -------::---- - - - - - - - - - --:---*---*- =-=--- ---=:---- -----
| |
| __________ **- - -
| |
| For the additional plants represented by this study th2 drag factors for I' the generic plant have been modified to account for differences in the geometry and number of the shrouds and the flow area of the respective I hot leg nozzles.
| |
| I
| |
| .1 4.4.8 I
| |
| * TABLE 4. 4.1 BREAK PARAMETERS .
| |
| lill1 CALVERT CLIFFS MILLSTONE PALISADES ET. CALHOUN INLET BREAK BREAK TYPE GUILLOTINE GUILLOTINE
| |
| * GU ILLOTI NE GUILLOTINE LOCATION RV NOZZLE RV NOZZLE RV NOZZLE . RV NOZZLE S"IZE CIN 2) .
| |
| -
| |
| 1414 1414 1414 905
| |
| :::::.
| |
| .::..
| |
| OPENING TIME CSEC) On023 0.023 0.023 0.023
| |
| .:)
| |
| OUTLET BREAK BREAK TYPE GUILLOTINE GUILLOTINE GUILLOTINE GUILLOTINE LOCATION RV NOZZLE RV NOZZLE RV NOZZLE RV NOZZLE SIZE CIN 2) 135
| |
| .. 135 135 200 OPENING TIME CSEC) 0.020 0.020 0.020 0.020
| |
| *'
| |
| | |
| I
| |
| , I- : .
| |
| 'i :
| |
| I,
| |
| : *r
| |
| : li,I
| |
| : !:ii
| |
| '. , .. 11 TABLE 4.4 2 I
| |
| '11
| |
| ' "
| |
| !'
| |
| ''! i;:'
| |
| i'
| |
| ' I j: ,*' PLANT PARAMETERS.
| |
| '1!i ' '.:
| |
| ITEM I 1GALVERT MI LLSTO'NE PALISADES Fr. CALHOUN
| |
| * I 1*11 .
| |
| ,.Qi'L I FFS I,
| |
| GEOMETRICAL DIFFERENCES ! I UPPER GUIDE STRUCTURE PLATE No YES UGS DESIGN' CRUCIFORM SINGLE&DUAL CONTROL Rons SHROUDS CORE LENGTH (LEF TO UEF) 141.2 IN, 146,3 IN,
| |
| __.
| |
| 0 CORE BARREL LENGTH 314,5 IN, 307.25 IN.
| |
| CORE BARREL OD 152,75 IN, 122.6 IN.
| |
| REACTOR VESSEL ID 172 IN. 140 IN.
| |
| COLD LEG ID 30 IN, 24. IN I Hor LEG ID 42 IN, 32 IN.
| |
| THERMAL SHIELD No YES THERMAL SHIELD LENGTH NIA 164 IN ..
| |
| VOLUME IN REACTOR VESSEL 4640 FT3 3014 FT3 POWER LEVEL 2530 MWT 1591 MWT PRESSURIZER PRESSURE 2015 PSIA 2250 PSIA TCOLD(°F)/P~~~NTROPIC (PSIA) 535.5/891 547/973 THOT(°F/P~~~NTROPIC {PSIA) - 582/1305 607/1570
| |
| | |
| - .. - ~ . . ,._ l@t ~ . . l(ilt . . 119 ~ IDt . . ,~ . . - * - - F
| |
| *"/;"
| |
| TABLE 4.4.3 COMPARISON OF PLANT.UPPER GUIDE STRUCTURES
| |
| ..
| |
| HEIGHT OF PLANT UGS DES IG~HS) . CONIBOL BOD 8BB8NGE~ENI SHROUDS EXPOSED TO CRQSSFLOW CALVERT CLIFFS SINGLE & *DUALS 20 DUALS/45 SINGLES 99.84"
| |
| "" MILLSTONE 2 SINGLE &DUALS 12 DUALS/57 SINGLES
| |
| .::.
| |
| _,
| |
| 99.84"
| |
| _,
| |
| FT. CALHOUN SINGLE &DUALS 12 DUALS/29 SINGLES 99 8"4''
| |
| I PALISADES CRUCIFORM 45 117.5"
| |
| | |
| I FIGURE 4.4.l GENERIC PLANT ANALYSIS I/
| |
| -DOUBLE-ENDED RV INLET BREAK AT 60° I
| |
| ,-
| |
| ABSOLUTE PRESSURE IN THE ANNULUS NOZZLE CENTERLINE ELEVATION AT 60°
| |
| '11 2.0 c0 I: 0 t-----t-----+----+-----+----1
| |
| ...* -~* ~-~~~- ----: ~ ~c~~~ *. >~="~-- -*c~ccccccccc:c::::' _ .*
| |
| 1600 .o '\ "' . . t
| |
| ~* I'~,~~ I*
| |
| w" I
| |
| Cc::
| |
| ~ 12.00.01-----t---=----+---~.__---1-~-~1
| |
| . C/)
| |
| C/)
| |
| w a:::
| |
| I
| |
| ,:-~~~~~:::'-:-;-:::~::-::-=-::;=--~~~~-~~:-::---- -;:-=-~~-=~~-
| |
| .
| |
| - - -
| |
| - .,. -- --* ..,_ - --
| |
| 0 =_-: ;:~ ~ :_ -~ = -- ~- - -- - - - - - -
| |
| - --
| |
| --
| |
| ~
| |
| -
| |
| -
| |
| - -- -
| |
| .._._ _- ... -
| |
| ____ f
| |
| --- --
| |
| --
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| 800 aO -
| |
| ,~~
| |
| 400 .o I
| |
| I\
| |
| 0 0 0 0 0 C)
| |
| I .;I*
| |
| 0 0 0 0 0 0 C)
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| ...-i n
| |
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| |
| * C\..I (Y')
| |
| II 0
| |
| ""<t-A II TIME} SECONDS I 4.4 .12.
| |
| 11-
| |
| | |
| I FIGu RE LJ 4 2 I GENERIC PLANT ANALYSIS I I DOUBLE-ENDED RV INLET BREAK AT 60° I PRESSURE DIFFERENCE ACROSS THE CORE BARREL NOZZLE CENTERLINE ELEVATION AT 60° t
| |
| '*I 12.00eaO
| |
| 't 800.0
| |
| )'
| |
| t 400 1110 1:. -
| |
| ( /)
| |
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| v
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| |
| '
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| *I*
| |
| -800e0 I';
| |
| -12.0 0 ,.QC>
| |
| a 0
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| .0 0
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| |
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| co a
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| II 0
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| ...,<..o
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| * 0 0
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| (\j (Y)
| |
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| 0
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| "'<t-
| |
| *
| |
| 'I TIME) SECONDS
| |
| ;I:
| |
| 4 .4 .13
| |
| | |
| FIGURE 4.Ll.3 I
| |
| GENERIC PLANT ANALYSIS DOUBLE-ENDED RV INLET BREAK AT 60° I
| |
| PRESSURE DIFFERENCE AROUND THE CORE BARREL NOZZLE CENTERLINE ELEVATION C6o 0 ~240°)
| |
| 't I*
| |
| t 800 aO 1~
| |
| ,_....
| |
| I C/)
| |
| 0...
| |
| ....
| |
| 4-00 110 I w
| |
| ec:::
| |
| ::=i C/)
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| C/)
| |
| It w
| |
| u::::
| |
| o.o 0...
| |
| c::r.
| |
| 1-
| |
| *I'
| |
| - ____
| |
| -~1-Cl _
| |
| _c __
| |
| __J l....!-l__
| |
| _
| |
| *--*------
| |
| -- - ----
| |
| -~
| |
| --= ___ _:___-~: -_- _:__ -- - - --- ___ ,,_
| |
| ----- - ----*- --- - - --- * -*--- -- - - -- - - - -- - ------ ------ - - - - - -- -- -
| |
| -400 .. 0 t
| |
| ,~
| |
| -80 0 .. o
| |
| :I*
| |
| -12.0 0 II 00 0
| |
| a a
| |
| a a
| |
| 0 0
| |
| 0 0
| |
| a a
| |
| ,
| |
| ..
| |
| 0 0
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| a
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| * 00 a*
| |
| *
| |
| (.0
| |
| ~
| |
| II
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| "'¢
| |
| ('J ll
| |
| ('J
| |
| ('I')
| |
| II 0
| |
| "<:I'"
| |
| * .t TIME) SECONDS I 11*
| |
| 4.4.14
| |
| | |
| -*-*-* 5 MSEC
| |
| -**- .. -10 MSEC
| |
| ;----:20 MSEC
| |
| ' i~=~~- *.-.*. ----25 MSEC 2400 .*
| |
| .,f!.~* *' r. ,*
| |
| . ~ **
| |
| I Ii:;:;. --*'* **.I''
| |
| *--*.
| |
| : .*, .... . . _.
| |
| ~
| |
| FIGURE i4.4,4
| |
| . ,,, ABSOLUTE PRESSURE IN THE ANNULIJnTIHE NOZZLE CENTERLINE
| |
| ! ELEVATION FOLLOWING ADOUBLE-ENDED INLET BREAK i AT 60° FOR CALVERT CLIFFS FOR VARIOUS TIMES AFTER RUPTURE
| |
| ' . . - - - * - - * - - - -..------------
| |
| '.: : *~ '.:.;!: ,~ ;;"'~.* ;"r '. * ' ;*,. t ,, .,.,
| |
| * 4 _ll. 1 c;
| |
| | |
| ----:1
| |
| *~
| |
| FIGURE 4.4.5 I*'
| |
| GENERIC PLANT ANALYSIS DOUBLE-ENDED RV INLET BREAK ,, i CORE AXIAL PRES SU RE DIFFERENCE _
| |
| ~
| |
| ;,\,
| |
| ,,
| |
| 'I
| |
| _...
| |
| 100a00 t
| |
| (/)
| |
| Ci...
| |
| I' w"
| |
| r:::c:::
| |
| :::::>
| |
| U)
| |
| (/)
| |
| 0 110 0
| |
| ~ (\) I . ~ /\ -"- / ' - '- . ----.. i w
| |
| CZ:::
| |
| I \( - *
| |
| ~ -~_; ~.~- ~ ~* --;_== ~ , ~~~~;_;_ccc~~~ ~ .c ______ ~ -1 0..
| |
| ---- - - . __ ce c _ c * - - -
| |
| __. ~----==----==-----=-----=---=-----=-==-=-----==-~~= ~-~ ~~
| |
| ~ -100 .oo ,.
| |
| \
| |
| I
| |
| . -~OOaOO~~~-r-~~~-+-~~~f-:-~~~~~~1 1:
| |
| -300 .ooo I
| |
| 0 0 0 0 0 0
| |
| 0 0
| |
| 0 (X) 0 0
| |
| (.0
| |
| ..-j 0
| |
| °'<t"
| |
| (\j .
| |
| 0
| |
| (\j (Y) 0 0
| |
| °'<t" i 0
| |
| Iii
| |
| * a
| |
| *
| |
| - -
| |
| a
| |
| --- -- ,,---
| |
| 4.4.lfi
| |
| .I
| |
| | |
| ',,
| |
| I FIG uRE 4 4 6 I
| |
| GENERIC PLANT ANALYSIS I
| |
| 135 SQ. IN. RV OUTLET NOZZLE BREAK AT o0 .
| |
| ABSOLUTE PRESSURE IN THE ANNULUS NOZZLE CENTERLINE ELEVATION AT o0 I
| |
| I;
| |
| ,.,
| |
| ' ' .
| |
| .
| |
| 2.400.0 I
| |
| I 2.000uO ~""\ I I
| |
| e *~ ,,,--- - -....
| |
| ,,
| |
| -------.....,,
| |
| 1600.0 - ~
| |
| ,,
| |
| c:::i:
| |
| ........
| |
| en 0..
| |
| w" 12.00 nO 0:::::
| |
| :::::>
| |
| en en w
| |
| *I 0:::::
| |
| 0..
| |
| I* 800110 I 400.0 _,
| |
| I
| |
| ~.
| |
| 'I 0 0 0 0 0 0
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| (",()
| |
| Ill 0
| |
| 0 0
| |
| R 0 ,..-.j I TIM~, SECONDS I 4.4.17
| |
| | |
| FIGURE 4.4.7 GENERIC PLANT ANALYSIS 135 SQ, IN. RV OUTLET NOZZLE BREAK AT o0 PRESSURE DIFFERENCE ACROSS THE CORE BARREL NOZZLE CENTERLINE ELEVATION AT o0
| |
| *I 1200.0~~-~~~~~~~~~-1 t 800 0 11 --------1--------1---....,.--+-------l----
| |
| I I
| |
| t-~
| |
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| |
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| |
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| |
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| |
| ~ -~§- -=:_~c==_ ~~- ~--~ ~=7_~ -:~ =:_ ~~ -~--=-- - ~--= :_:._:- ~~---= -=- --_ -=---~~ -_:':____-_
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| .,
| |
| 0 0 0 C) 0 0 o_ 0 0 0 0 0 0 (\j "'<t" (0 co a Ill Ill II Al II: Ill a .-!
| |
| *r IMEJ SECONDS 4.4. lR
| |
| *1
| |
| | |
| , ._,
| |
| .
| |
| FIGURE 4.4.8 I
| |
| .,, GENERIC PLANT ANALYSIS 135 SQ, IN. RV OUTLET NOZZLE BREAK AT o0 .
| |
| PRESSURE DIFFERENCE AROUND THE CORE BARREL NOZZLE CENTERLINE ELEVATION co 0 - 180°)
| |
| 1*
| |
| I 12.00 .. o I
| |
| I' -- .~
| |
| I' 4 00 aiO --iI t -
| |
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| |
| o_
| |
| I I
| |
| I
| |
| ......
| |
| ... Maximum pressure drop lS 3~3 psi.
| |
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| |
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| |
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| |
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| |
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| |
| 0 .. 0 I i I
| |
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| |
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| |
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| |
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| |
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| |
| *1. ~ -400110 -
| |
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| |
| - -800 zO -
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| ......,*
| |
| I TIMEJ SECONDS
| |
| 'l ------------'--------*--- - - - - - - - - - - -
| |
| 4.4.19
| |
| -.,,_.__-=---==--- -*---*--*-**-..*-- .
| |
| | |
| - - - - - - - -
| |
| I ,__,.
| |
| FIGURE 4.4.9 GENERIC PLANT ANALYSIS II 135 SQ, IN. RV OUTLET NOZZLE BREAK AT FULL POWER
| |
| --*-**--r----------,-
| |
| CORE AXIAL PRESSURE DIFFERENCE
| |
| '
| |
| 300.00r~----.----.------.-----,----__,
| |
| i I I:
| |
| ,1,_
| |
| 2.00~00r------1-----r-----1-----+-----1
| |
| .......
| |
| - - - --- - - - - - - -
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| -2.0 0 0 0 i----r----1-~....;.....__-1-----+----I II I
| |
| j,
| |
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| |
| I C>
| |
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| |
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| |
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| |
| 0 II:
| |
| * Ill
| |
| = fl
| |
| ._,
| |
| II TIME) SECONDS 4.4.20
| |
| - - - - - - - - -* *-*-* .. *-*
| |
| | |
| FIGURE 4.4.10 FT, CALHOUN P~NT SPECIFIC ANALYSIS RV INLET BREAK AT 60°
| |
| ., I PRESSURE DIFFERENCE ACROSS THE CORE BARREL NOZZLE CENTERLINE. ELEVATION AT 60°
| |
| ***-*"""'*"""-* -----
| |
| ..............
| |
| FT, CALHOUN
| |
| -- - CALVERT CLIFFS)
| |
| I I MILLSTONE AND PALISADES
| |
| -- .. ---- *-. - - -
| |
| 12.0 0,. 0 i-***---- ---*--*- *-. * - - * *-- -*-* ....... *-- ... .. .
| |
| I:
| |
| ., 1 iI l: -,
| |
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| |
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| |
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| |
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| |
| -- --*--
| |
| ~*
| |
| 8 00 sO --*:-** .. *-*--
| |
| i 400z0 Ii-~- - ----+---*-*-*-* - ~-* ------1 **-**--
| |
| \1 ' I 11 1
| |
| /\ ~ ! [ I
| |
| ~-\--~~-...............~1+-~rr~-- ,~~~
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| * I
| |
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| |
| *-12.00n0~'-----'-~-----*---- -------**--******.L.________ j I
| |
| 0 0
| |
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| |
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| |
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| |
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| |
| .,..., 0J ('f) v 0
| |
| Ill
| |
| * II Ill II: Ill TIME) SECONDS 4.4.21
| |
| | |
| - FIGURE 4.4.11 FT. CALHOUN PLANT SPECIFIC ANALYSIS RV INLET BREAK AT 60° PRESSURE DIFFERENCE AROUND THE CORE BARREL NOZZLE CENTERLINE ELEVATION AT 60° I~
| |
| FT, CALHOUN CALVERT CLIFFSJ ..
| |
| MILLSTONE AND 1 12.00 .o, PALI SADES -
| |
| .t
| |
| )._,
| |
| 800 110
| |
| -------------~
| |
| -
| |
| ---
| |
| ------- ---
| |
| I
| |
| -
| |
| C /J c...
| |
| 400 110 I
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| I: JI ll ll I:
| |
| 0 TI_ME_.1_ SECONDS i 4.4.22
| |
| * I
| |
| 'I *,
| |
| .. FIGURE 4.4.12 FT. CALHOUN PLANT SPECIFIC ANALYSIS RV INLET BREAK CORE AXIAL PRESSURE DIFFERENCE I) FT. CALHOUN CALVERT CLIFFS, I 300a00 ---*1*--
| |
| MILLSTONE AND PALISADES I,
| |
| I I:
| |
| ,, 2.00 sOO I 100t100 ~* -*
| |
| JJ
| |
| (\
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| TIML SECONDS
| |
| *1 ------*' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - '
| |
| .....
| |
| 4.4.23
| |
| | |
| FIGURE 4.4.13 FT. CALHOUN PLANT SPECIFIC ANALYSIS RV OUTLET BREAK AT o0 ABSOLUTE PRESSURE IN THE OUTLET PLENUM
| |
| ,.., 'nr n L 'r u *.J * '-'
| |
| j I! I I
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| ----*- -*----*----** -* *-*---.. ----------. ----*-* ---------*---------------*-* *--** - - -*- - -------------------1**
| |
| . 4.4.24 . .
| |
| | |
| FIGURE 4.4.14 I FT. CALHOUN PLANT SPECIFIC ANALYSIS t RV OUTLET BREAK AT o0 PRESSURE DIFFERENCE ACROSS THE CORE BARREL II NOZZLE CENTERLINE ELEVATION AT o0
| |
| ,,)
| |
| I -.
| |
| 1200.0 I
| |
| I I. I II .
| |
| I I
| |
| 800.G
| |
| !
| |
| I:
| |
| I, I
| |
| I
| |
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| |
| ,__ 400.0 I l
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| 0 1* TIML SECONDS I ----*
| |
| ~:
| |
| --- --- ..... *-- - ..
| |
| 4.4.25
| |
| | |
| FIGURE 4.4.15 FT. CALHOUN PLANT SPECIFIC ANALYSIS I RV OUTLET BREAK AT oo .,,
| |
| PRESSURE DIFFERENCE AROUND THE CORE BARREL '-..J NOZZLE CENTERLINE ELEVATION co 0 -1so 0 )
| |
| I 1-
| |
| .I --
| |
| 1200.0 I
| |
| ''
| |
| I I
| |
| soo.o I I I
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| TIML SECONDS I
| |
| 'I
| |
| '~
| |
| 4.4.26 1.
| |
| *--'
| |
| ---------- - -- -------- - -----
| |
| | |
| I FIGURE 4.4.16 FT, CALHOUN PLANT SPECIFIC ANALYSIS 1 RV OUTLET BREAK AT o0 CORE AXIAL PRESSURE DIFFERENCE I
| |
| I, 300.00 I I i I
| |
| I I
| |
| '
| |
| II
| |
| ,'
| |
| 1:
| |
| 200.00 i I
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| D I TIME, SECONDS I
| |
| I 4.4.27
| |
| | |
| I
| |
| .. ... .
| |
| I'
| |
| .... ~~ '.. *..
| |
| . ..
| |
| *~*:.n*
| |
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| |
| {
| |
| . .,.,'I ..
| |
| ...,. .. .,.___ OUTLET.
| |
| NOZZLE;*'--... ' ' . - .*. '**- '1* . -:: .*
| |
| l f!j!?!"''o/-'* ''"". . . ..
| |
| sI NG LE SHROUD '* *.' .
| |
| DUAL SHROUD ........ :-. ; .. *..
| |
| ,.
| |
| IL .
| |
| \:J.Oo
| |
| ~ ' ., ... * ... ;*.,r .... '
| |
| .,....
| |
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| |
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| |
| . . . . . . . *~oO** s:JOQ o0~* ... c~tr*~t~
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| ~.~ .,._,.,,.~:;*w:~*
| |
| ..
| |
| I I! '*~ FIGURE 4.4 .17 :I
| |
| ~lL.~-~; . * * * .
| |
| *.-''.*.t-.. ~.. :
| |
| . CALVERT CLIFFS UPPER GUIDE STRUCTURE
| |
| , . . *. ,'* . . . . ~'CEA SHROUD ARRANGEMENT . . **I
| |
| '~G::f+/-tM : * * . ~~ .
| |
| -~~1F'-.~f"'"'r-****
| |
| .. ...*,*'.('<'':;<'.'.'""'
| |
| ~ ..*
| |
| **....
| |
| ':~f-
| |
| {?. :.**
| |
| ~Li;~;;t*.***: .
| |
| I 4.4.28
| |
| *:1
| |
| | |
| --------------~ ----------
| |
| I I
| |
| I i..---- OUTLET ~
| |
| 1- NOZZLE
| |
| '.I SINGLE SHROUD ii,
| |
| :I *. 0000 I
| |
| I 0 o0 o <;::jOQ o0 o0 I 0 o0 o 9JO~ o0 o0 I 0 0 V0"0 0 0 0 0 I
| |
| I 00000
| |
| -1 I FIGu RE 4 4 18' I I MILLSTONE 2 UPPER GUIDE STRUCTURE
| |
| 'I, CEA SHROUD ARRANGEMENT I
| |
| I I
| |
| | |
| ./:(' ---
| |
| .1*
| |
| .- ..
| |
| * I
| |
| ;.
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| '
| |
| i~-2~:**~~.- :. . . ~* .
| |
| *;i_*: ~,:.; :~:;: ~* *.
| |
| *-* .*. ~**
| |
| ..,, ... - . ..,, .. ,"*:*
| |
| -;~'!rt'*'~~-~-******'\.**-:**,.
| |
| OUTLET*
| |
| ~ ..,, .. ,.,:*...: NOZZLEi
| |
| ~~;,
| |
| I
| |
| --SINGLE SHROUD
| |
| ** ... , ,_, ..., *.;
| |
| I \
| |
| 1.. ;.
| |
| . . .
| |
| * . :*. *:. *1~,
| |
| '
| |
| ~~~-~~.:a.,*".;,*,
| |
| . ....
| |
| ~
| |
| ~-~L_;f/.
| |
| ::F;:*
| |
| _;ttti~L2~~:---~-- ----- -- ---
| |
| GO 0~ 0. . 0 *
| |
| .. ,/'I''I
| |
| .,.r**oo-02j?-
| |
| -
| |
| iftl'~~*-~ 1'""' '"''-'~""
| |
| '.~t{''\~>**: *;' ' '
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| ~" ' ..
| |
| " * *:. .-,:. "" - '
| |
| .~ .** .... *
| |
| '
| |
| . . _ **- .. . : . - -..-: .... :..'_
| |
| '
| |
| -~-. ~-*._c-~" -"*-"*:-.,:;_~ ~*
| |
| *.. . ....... *. ;,....
| |
| (***-,1*_*
| |
| '> ...***:*
| |
| -~:,;-:
| |
| ';.:_;'-:._:. **.
| |
| :h.;-.:. :'
| |
| *: ;~: ' .. *. . . .
| |
| ~~;.~~~-~~~:J.~'.~;-~ ... 00000 0000 I
| |
| *.* 0 Q* 0 0 I
| |
| * c**~r**.:. . ~::." o,,,,
| |
| _-,__ - - 'l'
| |
| .. .. , / ( )
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| ~;~~~~;;~;;:,'~-~~~-_':[h::--~~4~~
| |
| .%"). 0 :"
| |
| ~G .
| |
| ©.i..~~
| |
| *:*.'":' ,. ~.: "1*<.~ ,~*:~
| |
| \*;'.~*"::;.~ -£
| |
| : :
| |
| 4.4.30 I
| |
| | |
| ... .;.. *.
| |
| ' - - - . OUTLET; ---i
| |
| 'NOZZLE*
| |
| ---*
| |
| , * * ~ , * *', * ~ ** r "<..,.. *"''
| |
| *:i. *-
| |
| *-:''. :;*~ ... *..... ,~-
| |
| . . * ' * * *** ~* *;!.-.,.. ..~ .~-~- *.*:;"' . ***'. '
| |
| .***.:.:. _ 1 FIGURE 4.4 .20 PALISADES UPPER GU IDE STRUCTURE CEA SHROUD ARRANGEMENT --.-_ . '*
| |
| . *... ,.
| |
| tl_/I ~1
| |
| | |
| I 4.5 REACTOR VESSEL, RC PIPE, Arm RCS SUPPORTS I
| |
| ,. DESIGN BASIS The analysis described herein was performed to evaluate.
| |
| the response of the reactor coolant system (RCS) major components to forces associated with design basis pipe ruptures. The design basis pipe breaks for this analysis I are defined in.Section 4.2. Associated forces for each of these guillotines include pipe tension rel~ase forces at the break location, subcompartment pressurization I forces as described in Section 4.3, and internal asymmetric hydraulic forces acting.on the vessel and internals as 9escribed in Section 4.4.
| |
| I 4.5.2 METHOD OF ANALYSIS Dynamic analysis of the RCS was performed using lumped
| |
| .I *parameter mode 1s which include details of the reactor vessel (RV) and internals~ steam generator (SG) and inter-nals, reactor coolant pumps (RCP) and interconnecting I reactor coolant piping. - -
| |
| ,, The pipe break tension release forces, asymmetric sub-compartment pressurization forces, and asymmetric reactor internal hydraulic forces were applied as simultaneous time-hi story forcing functions.
| |
| ,-,
| |
| I Anon-linear ti:ne-history dynamic analysis was performed for a three-dimensiona1 mathematical model specifically .
| |
| detailed for each break in order to generate mass point I response of the components, support and pipe nozzle loads, and time-history motions as subsystem connection points.
| |
| Millstone was selected as the model to be used in the I generic analysis, but Millstone RCP dead weight vertical hangers \*1ere not credited with pipe rupture load carrying capa_bility. For each postulated break, *assessments were I made for Calvert Cliffs, Palisades and Fort Calhoun. These assessments are explained in Section 4.5.7.
| |
| II 4.5.3 INSTABILITY ANALYSIS OF SUPPORTS An elastic and/or plastic analysis of each component support I region was performed for two purposes. The first was to
| |
| , determine the non-linear load displacement relationship for -
| |
| inclusion in the RCS model described in Paragraph 4.5.4.
| |
| The second purpose was for evaluation of the acceptabi1ity of the computed loads for each component support region.
| |
| This evaluation is discussed in Paragraph 4.5.8.
| |
| I 4.5.3.1 Detailed Finit~ Element Models . .
| |
| The three-dimensional elastic plastic analysis I of the component support regions has been performed with the MARC non-linear general purpose finite element program (Ref. 3.10). The finite element I ~odels used in the analysis must be sufficiently
| |
| | |
| 4.5.3.1 Detailed Finite Element Models (Continued)
| |
| I detailed to provide an accurate load displacement curve and instability load but simple enough to I
| |
| provide a reasonably efficient solution with the MARC program. A typical model of a reactor vessel support on an inlet nozzle is shown in.two viev1s I in Figures 4.5.1 and 4.5.2. The model provides for the determination of the load displacement relationships not only at the support but at the nozzle/vessel intersection and at the nozzle/pipe I
| |
| intersection.
| |
| Models with an. appropriate degree of detail were I
| |
| developed for each different RCS support region.
| |
| The material properties used in the analyses were de.termined from laboratory tests already performed.
| |
| I.
| |
| 4.5.3.2 Load Displacement Relationships I
| |
| Each support region model was loaded statically in the direction of load expected during the RCS
| |
| -structural ana-lysis. _ The load was increased until I'
| |
| the deformation increases* without bound. ___ The overal 1 behavior of the region was determined for 1*
| |
| ,,
| |
| input to the RCS structural analysis as a non-linear , ,
| |
| support stiffness.
| |
| 4.5.3.2.1 Load Carrying Capability of Reactor Vessel Supports
| |
| .Reactor Ves.sel support characteristics hav..e been determined for all plants under consideration per
| |
| *1
| |
| ===~=----~~-=~~~=*~-=:-=~:===*=:-
| |
| . paragraphs 4.5.3.1 and 4.5.3.2 of the evaluation plan. These support characteristics are indicated
| |
| * *~ ---~~~c:m=-the-b0ad_O_e_~ curves for the Generic Plant J _
| |
| --~on-F'-ig~ _zi.::;::5~4~.~~~-~====================-:__::
| |
| .
| |
| : a. RV Nozzle Loads
| |
| -~ -~-- -~: -~I~
| |
| Load capability is defined as the maximum moment acting on the pipe safe end or el bow which sat-isfies ASME Code, Appendix F elastic limits.
| |
| I Finite element analysis has been used to determine a stress intensification factor for piping elbows' 4.5.3.3 Instability Analysis The detailed stresses and strains for each loading ~
| |
| up to instability were obtained from the analysis -
| |
| described in Paragraph 4.5.3.2. This information as well as the instability loads (the loads at
| |
| -which deformation increases without bound) were 1*
| |
| stored for 1ater use, in evaluating the effect of the loads computed by the RCS structural analysis.* 1*
| |
| '--\*S* 2...
| |
| I
| |
| | |
| I I 4.5.3.4
| |
| * Steam Generator and Pump Supports Support regions where predicted loadings are assumed to be within the elastic loading range I have been evaluated on a conservative, elastic basis. The assumption of elastic behavior is verified by comparing elastic load limits to I calculated loadings. These comparisons are shown in Section 4.5.8.
| |
| I 4.5.3.4.1 Load Carrying Capabilities of Steam Generator and Pump Supports 4.5.3.4.1.1 Generic Analysis of Steam Generator I And Pump Supports All generic plant steam generator and RC pump supports I have been evaluated on an elastic basis. Load capa-bilities have been determined for all supports in order to evaluate the structural adequacy of these I supports when subjected to the loads calculated in the RCS dynamic analysis. Load deflection characteristics of these supports have also been conservatively calcu-I lated on an elastic basis. The calculated load capa-bilities are listed in Tables 4.5-4,5,6 and were determined as follows:
| |
| * I* a. Steam Generator Lower pads, lower stop; lower keys, and upper keys I Design Loadings are less than or equal to 90%
| |
| Loadings at Yield. Load Capability for these supports is defined as Design Loads/0.9, and I apply to both the component support and the foundation structure.
| |
| : b. Steam Generator Holddawn Bolts I Load Capability is defined as loadings ta cause yield based on ASME Code material I properties.
| |
| : c. Steam Generator Snubbers I Load Capability is reported as actual test loads.
| |
| I
| |
| '-*'
| |
| : d. Steam Generator and Reactor Coolant Pump Nozzle Loads Load Capability is defined as the maximum I moment acting on the pipe safe end or pipe elbow which satisfies ASME Code, Appendix F elastic limits. Finite element analysis has 1* been used ta determine a stress intensification factor for piping elbows.
| |
| I y.S*.J'
| |
| | |
| I 4.5.3.4.1.2 *Millstone 2 The generic support analysis is directly applicable I to Millstone.
| |
| 4.5.3.4.1.3 Calvert Cliffs I The generic support analysis is directly applicable to Calvert Cliffs. I 4.5.3.4.1.4 Palisades ~
| |
| The.Palisades *support system is substantially different . *.
| |
| from the gen~ric design. A plant specific analysis was performed for the Palisades supports using the
| |
| * same analytical methods as applied to the generic 1
| |
| plant. In addition, the load carrying capability of the supporting foundation structure was evaluated on an elastic-plastic basis. This data was used, 1*
| |
| where applicable, as the load limiting component.
| |
| 4.5.3.4.1.5 Fort Calhoun I The Fort Calhoun support systemlsSU-0-stanti-a-i-ly---- __
| |
| different from the generic design. A plant specific analysis was performed for the Fort Calho~ri supports I '
| |
| using the same analytical methods as* apnlied to the Palisades plant. 1*
| |
| 4.5.4 MODELS Condensed struc;:t1:1ral models of the major compone~ts of the RCS and component internals were developed from deta1led representa~-:
| |
| I ti.ans_ of _ea*c.*h component by incorporating *response characteristic9
| |
| ===========~~~~---_,and.ma-in-tatning interface response compatibility. For each . I*
| |
| ~---:-a11-=-~Jys:i*s:-,-~a~m_0a-e::l~o:f~~~~e=RCS~,n~ludiog r_-e_~~tor vessel, steam '
| |
| generator\ ' *reactor=* co 0~1~~fr1t~p:umps ; :~ana;~'fnt;*e~c 0-n n'e,G:t-:'.i,n 9.=P~tp_jJlfl~-- _
| |
| ~:~a ~~P i~~e~ i 1 ~~~~o~~~~~ ~-c~~~~ i- ~~~~~~~~~~r;~e-~i ~~!ii:~~~~{faL*.*:1;~
| |
| depending on the component to be evaluated. However, a mass representation of other RCS components is included for each model.
| |
| 4.5.4.1 Models for the Reactor Vessel Analysis Design basfs pipe breaks for thi~ a~~lysis are defined in Section 4.2 as the RV Hot Leg (Outlet) nozzle guillotine and the RV Cold Leg (Inlet) nozzle guillotine. For each of these breaks, a detailed model was developed using lumped mass parameter techniques as ~etailed below.
| |
| L\-5-L-f
| |
| | |
| I 4.5.4.1.l .Generic RV Outlet Nozzle Guillotine Analysis I ' .
| |
| The three-dimensional model of the RCS constructed for this analysis contained total RCS mass and I stiffness definition, with pipe break discontinuity of the pipe at the RV nozzle safe end on the #1 hot leg (Figure 4.5.5). The RV internals were modelled
| |
| .'I in detail, taking into account the three-dimensional non-linear aspects of the connections between elements such as the fuel assembly, core shroud, core support barrel (CSB), and upper guide structure (UGS), and I RV as well as hydrodynamic coupling effects of the CSB-RV and CSB-shroud interfaces. The.internals model used for this analysis was reduced from the I more highly detailed model used in the analysis of the internals themselves (Section 4.6.2). The reduced model of the RV internals, showing its co-I linear elements and non-linearities, is presented in Figure 4.5.6. In addition to parameters outlined above, lump mass parameters of the RV shell and
| |
| ,.
| |
| both SG's were included in the model. The non-I linearities of the RV gapped horizontal supports and vertical support pads as well as the lower stop for each SG were also modelled. The resulting model consisted of 70 mass dynamic degrees of freedom (d.d.o.f.), 8 non-linear RV internal interfaces and 5 non-linear RV support locations.
| |
| I 4.5.4.1.2 Generic RV Inlet Nozzle Guillotine Analysis I The details of the mathematical model analyzed (Figure 4.5.7) were identical to those for the RV Outlet Nozzle Guillotine Analysis, except I that the pipe discontinuity was modelled at the lA loop RV inlet nozzle safe end. The model contained 70 mass d.d.o.f., 8 non-linear internal I interfaces, and 5 non-linear support locations.
| |
| 4.5.4~1.3 Generic RV Analysis for ECCS Motion I For each RV analysis design basis pipe break the RCS models outlined above were revised to provide lurnµ.mass parameters at all RCP's and piping loops, I and d.d.o.f. 's at ECCS nozzles. RV shell and SG mass and gapped support point motions resulting from the RV asymmetric load analyses were applied 1* on a time-history basis as forcing functions to the rest of the RCS to obtain motions at the ECCS nozzle interfaces. Each of these models* was linear I and contained 70 mass d.d.o.f. s.
| |
| 1 I
| |
| I 4* 5 *5
| |
| | |
| 4.5.4~2 Models for Steam Generator Support Analysis I
| |
| Design basis pipe breaks for this analysis are defined in Section 4.2 as the SG outlet nozzle I
| |
| guillotine and the SG inlet nozzle guillotine.
| |
| For each of these breaks, a detailed model was developed using lumped mass parameter techniques as detailed below.
| |
| 1 4.5.4.2.1 Generic SG Outlet Nozzle Guillotine Analysis The three-dimensional model of the RCS constructed for this analysis ~ontained total RCS mass and stiffness definition, with the pipe break discon-
| |
| * tinuity of the pipe at the lA loop SG outlet nozzle (Figure 4.5.8). Lump mass parameters of the RV, I both SG's, lB, 2A, 28 RCP s. lB cold leg piping 1
| |
| and #1 hot leg piping are included. Steam Generator
| |
| #1 was modelled with a high degree of detail in prder to calculate its response and movement fol~
| |
| I
| |
| ------:____.__ __________________ lowing this break._ The detail includes the non-llnearfties-of-the--lower:stop and_ k~ys and all four vertical pads. The internals of ~SG #1 were I
| |
| also modelled, and included a gross tube bundle mass and stiffness as well as tube bundle to shell interface details. The detailed model of SG #1 for this break is presented in Figure 4.5.9, which I
| |
| shows the colinear elements of the SG tube bundle and shell as well as the support non-linearities-The resulting model consists of 68 mass dynamic I
| |
| degrees of freedom (d.d.o.f~) and 7 non-linear support locations. I
| |
| ~~~~~~~~;:--:::::::::::~~~~~,__:4.5.4.2.2 -Generic SG Inlet Nozzle
| |
| =_--,_ -0 : _ _-__- ~ _---:.-- -===---= -~-=--=- --*-- _:__~ ~- ---=--'---Anac:rJ:S'-i':s~~-;,_._,,"'-;.-:C--='=~,__-=-______ -
| |
| Guillotine I
| |
| ____ _
| |
| ... .... .*** .* . . . *. /~~g~~;~fiI~) t~;:~a~~~~friiff~~!! :i~~~~~~a~~ *. .~ f
| |
| -o_
| |
| Outlet Nozzle Guillotine. For this analysis, discontinuity of the piping was represented at the SG #1 inlet nozzle safe end, and mass repre-sentation was also included at the lA RCP and lA cold leg. SG #1 contained the same detail as I
| |
| the model for the SG Outlet Nozzle Guillotine, e~cept that the lower support keys were modelled as linear supports (See Figure 4.5.11). This I
| |
| model contained 76 mass d.d.o.f. s and 5 non- 1 linear support locations. I
| |
| : 4. 5. 5 FORCING FUNCTIONS 4.5.5.1 .Reactor Vessel Support Analysis I For each design basis pipe break in the RV cavity.,
| |
| a blowdown loads analysis (Section 4.4) and a cavity _
| |
| I L\ .5.,f; I
| |
| | |
| ,. 4.5.5.1 Reactor Vessel Support Analysis (Continued)
| |
| I pressure analysis (Section 4.3) were performed in order to generate internal asymmetric loadings and differential cavity pressure respective1y.
| |
| I These forces and the pipe tension release force at the postulated break were used to calculate the three-dimensional time history forces applied I to the exterior and internals of the RV. Forcing functions for a typical RV support analysis are shown in Figure 4.5.12.
| |
| I 4.5.5.2 Steam Generator S~pport Analysis For each design basis pipe break in the steam I generator compartment, a subcompartment pressurization analysis was performed using the procedure:~ and models discussed in Section 4.3. Resulting pressures were I used to calculate asymmetric forces on the SG. These forces and the pipe tension release force at the postulated break were used to calculate the three-I dimensional time-history forces applied to the exterior of the SG. Typical simultaneous three-dimensional forcing functions for an SG support I analysis are shown in Figure 4.5.i3.
| |
| 4.5.6 COMPUTER CODES I The physical definition of each model was supplied to the STRUDL computer code (Reference 3.2), which generated the condensed stiffness matrix as well as pipe and linear support load influence I coefficients. The matrix, along with the mass.definition, gapped support definition, damping, appropriate hydrodynamic coupling effects, the three-dimensional time-history forcing functions as I discussed and developed in Reference 3.1, and the pressure loads calculated from the subcompartment pressurization analysis as discussed in Section 4.3, was supplied to the DAGS computer code (Reference 3.4) which calculates support loads* and* time I history motions. The time history motions and the STRU_DL-generated influence coefficients wer~ supplied to the bAGS post-processor code FORCE (Reference 3.4),-which calculates I maximum pipe nozzle loads and support loads.
| |
| 4.5.7 RESULTS OF ANALYSIS I The results of the analyses described above include time histories of .component maximum support loads for support evaluation and I time histories of motion of components and piping for subsystem analysis of vessel internals (Section .4.6), CEDM (Section 4.8),
| |
| and ECCS piping (Section 4.9)!
| |
| I The results of the generic analysis was related to specific plants in either full or sealed form. Where necessary pl ant specific verifications and/or analyses were performed.
| |
| 1*
| |
| I
| |
| | |
| 4.5.7.1 Results of the Generic Reactor Vessel Analysis I
| |
| Generic re~ctor vessel support loads, RV nozzle loads, 1*
| |
| and RCP nozzle loads are summarized in Tables 4.5-1, 4.5-2~ and 4.5-3 respectively for both pi~e breaks analyzed. I Time-history motions of the RV and both SG s were 1 also generated from these analyses and were used as forcing functions to develop motions of the ECCS* I nozzle at its connection with the RCP discharge 4.5.7.2 pipe.
| |
| Results of the Generic Steam Generator Support Analyses I
| |
| Generic steam generator support loads, SG nozzle loads and RCP nozzle loads are summarized in Tables;4.5-4, I
| |
| 4.5-5 and 4.5-6 respectively for both pipe breaks analyzed. These loads are shown in comparison to load capabilities as developed in Section 4.5.3. I 4.5.8 tVALUATION OF COMPONENTS AND SUPPORTS 4.5.8.1 Acceptance Criteria I
| |
| The reactor vessel support 1oads resulting from the I RCS Structural Analysis, Section 4.4.8.1, have been evaluated by comparison to the instability analysis results. The initial conservative acceptance criterion I
| |
| was the ASME Boiler and Pressure Vessel Code Section III, Division 1, *Appendix F, Article F1324. This criterion states that the violation of the pressure boundary will not occur if the applied loads do not 1.
| |
| :._- -
| |
| exceed 70% of the plastic instability load.
| |
| *~-=~~~** ~ ~_;_ ~---=-~~_:_~-=-= ~~ ..=::.:~~==_:-~_sea-s_e:s~n-eE'e=tes:.uj-ts_ m~y~n-ol~clear:Jy~s_atis~f.x-:-t::b-i-S-=-:_ - -- - I _
| |
| --_-:..-...=-
| |
| criterion, stru-ttural aaequa-cy: a-na_ ~ preS:scu'r=*e:--:b:o1;1r:id:a,~y~.-~~=*
| |
| integrity are also demonstrated by examinatirin~'Jof the , .. . ,.
| |
| effects* of the additional strain on component;supports and piping. Where necessary, these effects are discussed in 4.5.8.2.1, Generic Plant RV Supports Evaluation. ,.
| |
| These acceptance criteria have also been applied to the RV shell and nozzle intersection, and to the reactor coolant pipe near the supports and component nozzles.
| |
| The steam generator and pump support loads resulting from the RCS Structural Analysis have been evaluated by comparison to the elastic analysis results.
| |
| I 4.5.8.2 Evaluation I
| |
| *The maximum 1oad experienced by the nozzle. regions of the the reactor vessel for each design basis pipe break in reactor cavity was evaluated. The results of the I
| |
| RCS structural analysis was compared to the results of the elastic-plastic analyses of Section 4.5~3.
| |
| I I
| |
| | |
| .
| |
| I I *4.5.8.2 Evaluation (Continued)
| |
| The integrity of the reactor vessel was evaluated by comparing the computed elastic-plastic behavior to I the instability load or to strain limits according to the acceptance criteria of Paragraph 4.5.8.1.
| |
| I The maximum load experienced by the support and nozzle regions of the reactor coolant piping was evaluated for each design basis pipe break. The I evaluation process is similar to that discussed above. The integrity of the reactor coolant piping was evaluated by comparing the computed elastic-plastic behavior to *the instability load or the I strain limits according to the acceptance criteria of Paragraph 4.5.8.1.
| |
| I The maximum load experienced for each RCS support was evaluated for each design basis pipe break in the steam generator compartment. The evaluation process I was similar to that discussed above. The integrity of the reactor coolant system supports was evaluated by comparing the computed elastic-pastic behavior I to the instability load or to strain limits according to the acceptance criteria of Paragraph 4.5.8.1.
| |
| 4.5.8.2.1 Generic Plant RV Supports Evaluation I The resulting loads from generic RV support analysis are compared to the acceptance I criteria for the supports in Figures 4.5.3 and 4.5.4.
| |
| RV and RCP nozzle loads are compared to their acceptance criteria in Tables 4.5-2 and 4.5-3.
| |
| I For the RV Outlet Nozzle Guillotine, all RV support and RV and RCP nozzle loads satisfy the initial con-servative acceptance criter_ia of ASME Code Section III.
| |
| I For the RV Inlet Nozzle Guillotine, RV support loads exceed this criterion by 5~L (See Figures 4.5.3 and 4.5.4).
| |
| For this case, however, it is clear from the load-
| |
| ,.
| |
| I deflection curves for each support that there is a considerable amount of additional strain capacity.
| |
| Therefore, the supports are adequate to sustain the calculated load. For this postulated rupture, the RV nozzle loads meet the initial acceptance criteria, and the RCP discharge nozzle loads exceed the elastic I analysis criterion by 1ess than 2~~ ~ The pressure retaining integrity and geometric stability of the primary piping are not impaired.
| |
| * I 4.5.8.2.2 Analysis Plant Specific Evaluation ~ RV Supports I 4.5.8.2.2.1 *Millstone 2 The Millstone 2 plant was .used as the basis for the I generic RV support ana lys..i~ ~ _with the exception that 4*5 *9
| |
| | |
| I 4.5.8.2.2.1 Millstone 2 (Continued) I the generic cavity pressure loads were calculated by applying a factor of 1.1 to the Calvert Cliffs cavity pressure loads. The Mi 11 stone cavity pressures have
| |
| .I been shown to be lower than those used for the generic RV supports analysis. Therefore, the generic results are directly applicable to Millstone.
| |
| I 4.5.8.2.2.2 Calvert Cliffs I The Calvert Cliffs-RV, RV support system and RCP p1p1ng are identical to Millstone's, the RCP has greater potential load carrying support than Millstone, and I
| |
| the cavity pressure loads applied to the generic analysis are 1.1 times greater than Calvert Cliffs cavity pressure loads. Therefore, the generic results are conservative I
| |
| for Calvert Cliffs.
| |
| 4.5-.8~2.2.3
| |
| * Palfsades I piping are similar to Millstone's, but the load-deflection I The Palisades RV, RV and SG support system and RCP characteristics of the RV supports and foundation (Figures
| |
| * capability, made it necessary to perform a plant specific I 4.5.14 and 4.5.15), which show reduced load carrying analysis for the controlling RV Inlet Nozzle Guillotine case. In this analysis, which used models and methodology similar to those already discussed, the load carrying capability of the 1B & 28 RCP supports was utilized, but 1*.
| |
| credit was taken for neither the 2A loop RCP supports, 1~~~-~-~-~-'c::"::;:_~-~~-~ ~-, ._,.,-;- ~=-=---""=---~:;.~~-~=-=* -=:!~!!~o[P~~--~n!~:0f~A~t~~~1_n~-~~~I~~~~~~is~~e ~~~d~~~a f~:l ~~:d _ I 1
| |
| - ~ -- - -- --- -~ -'~sp'ecifi-taJ:ly_;Jor~fta-:l~i~-a'd~s~wer-*e~1rp~~1-=-~a~ to~gettig_r--fdth~..:--:*=--- . :.:
| |
| generic RV i nternaT-and~ plpe-t-ensTon -*re i-e-a:se_:-"l-oa:as~~---'- - : -~ c"=
| |
| -**---- --*** .. R~sul ts,* as summarized and compared in Tab 1es 4. 5-7 ,8,9,10 and Figures 4.5.i4 and 4.5.15, show that all support and I
| |
| nozzle loads generated by this plant specific analysis meet the acceptancei criteria for this plant. These loads ,..
| |
| include a11 RV support loads, a11 RV and RCP *nozzle loads and all applicable RCP support loads.
| |
| * The results of the generic analysis for the RV Outlet Nozzle Guillotine are conservative for Palisades and I
| |
| still meet Palisades plant specific acceptance criteria.
| |
| Pal.isades specific ECCS time history motions were also I
| |
| generated for this bre_ak, to be used as input forcing functions to the ECCS analysis reported on in Section 4.9. I I
| |
| L-/-~-/0 I
| |
| | |
| *1*
| |
| 4.5.8.2.2.4. Fort Calhoun I A comparison of the Fort Calhoun plant RCS parameters to those of the generic plant show that results of neither the generic RV support analysis nor the I elastic-plastic instability analysis of supports are applicable to the Fort Calhoun plant.
| |
| I Based on experience gained from analyses heretofore completed and the aforementioned capabilities of the RV supports, it is reasonable to believe that the results of the actual analysis will show that the supports are I adequate to sustain the loads from each postulated break.
| |
| 4.5.8.2.3 Generic Plant SG Su~ports Evaluation I The results of the generic SG support analysis (4.5.7.2) and elastic analysis of supports (4.5.3.2), summariz-ed I _in Tables 4.5-4,5,6 were compared. All support and pipe nozzle loads generated by the SG support analysis are within their respective calculated load capabilities.
| |
| I 4.5.8.2.4 Plant Specific Evaluations - SG Support Analysis-I 4. 5.8.2.4.1 Millstone 2 The Millstone 2 plant was used as the basis for the I generic SG support analysis; therefore, the gen~ric results of the SG supports and SG nozzle loads are directly applicable.
| |
| I 4.5.8.2.4.2 Calvert Cliffs The Calvert Cliffs SG, SG support system and RCP piping I is identical to Millstone's. Therefore, the generic results of the SG supports and SG nozzle loads are directly applicable .
| |
| I . The Calvert Cliffs RCP support system includes a horizontal snubber, a vertical snubber and a horizontal seismic I support- strut for each pump that the Millstone *RcP*s do not have. Since it has been shown that the generic RCP nozzle loads meet the acceptance criteria without the aid of any other RCP support, these generic results I are conservative for Calvert Cliffs.
| |
| 4.5.8.2.4.3 Palisades I System geometry, forcing functions, and thos~ parameters which affect distribution of applied loads to each of I the supports are essentially the same for Palisades and the generic plant. Consequently, generic SG support reactions and SG* nozzle loads. are directly appl i cab 1 e to Palisades. However, the Pali~ades SG support (and I
| |
| I LJ
| |
| * S *II
| |
| * I 4.5.8.2.4.3 Palisades (Continued) nozzle) load carrying capabilities were found ta be I different than the generic plant. Therefore, the plant specific load capabilities (Tables 4.5-12, 4.5-13) I generic SG support and nozzle loads were compared to and ~ere found to be acceptable. The Palisades RCP support system contains vertical supports capable of carrying significant load. Therefore, because the generic model is without pump supports, the generic I
| |
| RCP nozzle load results are conservative for Palisades.
| |
| They are compared_ to Palisades specific load capability I in Table 4.5-14 in order t_p show that they also meet the acceptance criteria.
| |
| 4.5.8.2.4.4 Fort Calhoun I A comparison of Fort Calhoun plant RCS parameters to those of the generic plant show that results of neither I the generic SG support analysis nor the elastic analysis of.supports are applicable to the Fort Calhoun plant. A Support load capabilities for this plant are summarized I plant specific analysis for Fort Calhoun is in progress~
| |
| in Figures 4.5.15, 4.5.17, and Table 4.5-11.
| |
| Hardware design modifications for the SG accident
| |
| ,1 support system have been made, and a plant specific analysis for Fort Calhoun which incorporates these modifications is in progress. Load capabilities for I the SG and RCP support systems are summarized in Table 4.5-11. Based on experience gained from analyses herein reported and the capabilities given above plus I
| |
| preliminary investigations, it is reasonable to believe th~t this _ana~ysis_ will show the adequacy of the support
| |
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