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Latest revision as of 18:20, 17 March 2020
| ML18078A673 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/12/1979 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML18078A672 | List: |
| References | |
| NUDOCS 7901220111 | |
| Download: ML18078A673 (92) | |
Text
{{#Wiki_filter:nEVALUATION OF THE REACTOR COOLANT SYSTEM CONSIDERING SUBCOMPARTMENT
..... PRESSURIZATION FOLLOWING A LOCA FOR SALEM UNITS NO. 1 AND 2 11 790:1.22 C\ \ \
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!ABLE OF CONTENTS Section Title l.O Introduction 2.0 ~~J Subcompartment RCS Breaks 3.0 Conversion of TMD Pressures to Forces 4.0 Steamline Break 5.0 Reactor Coolant Loop Piping Evaluation 6.0 R.G.S. Equipment Supports 6 .1 Steam Generator and Reactor C.oo l ant Pump Lower Supports 7.0 Interior Concrete Structures 7.1 Introduction 7.2 Evaluation Criteria for Subcompartment Pressure ' !'
7.3 Analytical Model -and Method of Analysis 7o4 Results and Conclusions
**a.a References
LIST OF TABLES
- Table 1
2 Title Containment Geometric Data Break Mass and Energy Flow 3 Ho-t Leg Break Releases 4 Peak Pressures 5 Areas for Force Calculations 6 Peak Forces Acting on Steam Generator 7 Peak Forces Acting on the Pressurizer 8 Steam Generator/R.C. Pump Lower Supports
"'* - .?5 -:A.-.. . =~ .;.,;:w
-ea . ewe* ~;**i 6 *+ :-y* **e;:r iN.;~.~1rm rz= 0 mrav"*' LIST OF ILLUSTRATIONS
*
- Figure Title 1-3 Reactor Containment 4-17 Br~ak Compartment Pressure Transients 18-35 Pressure Differentials*Across the Steam Generators and Pressurizer .
\
- 36. Axial Force on Steam Generator 37 Vertical Force on the Steam Generator 38 Moment to Overturn. the Steam Generator
- 39 Axial Force on the Pressurizer 40 Vertical Force on the Pressurizer 41A Moment to Overturn the Pressurizer
. 418 Reactor Coolant Loop Model 42-47 Interior s*tructure 48-51 Pressure Time History in Subcompartments 52A Summary of Reinforcement 528 . Accumulator Compartment Wall 53 Sample Deflection Plot c
1.0 INTRODUCTION
- To assure the safety of the Salem ruptures must be considered. This report presents an evaluation of the reactor coolant system and the concrete for the loads induced by a loss-of-coo~ant accident.
Nuc_lea~ Plant the possibility of pipe
* ... 1$ .:!S.%1 C9~PdJ4.SJ.J. ~*-..*~ . .l,,;,53'~-.Sn ... .5¥J.- ... ~f;,#.-...J@-J.4.;}§!_ .... !~. 1.1 _IQ F-:?'f"l.J ~* . ...$(
2.0 PNJ SUBCOMPARTMENT RCS BREAKS An analysis has been performed utilizing the latest version of the TMD computer code. An 18 node containment model was used to calculate the pressure differentials across the containment structures, steam gener-ators and the pressurizer for a spectrum of RCS breaks.' The nodal boundaries used are illustrated *in Figures 1 to 3. The reactor coolant system breaks analyzed were double ended. hot and cold leg breaks. These break releases represent a significant c~nservatism since existing pipe restraints limit break sizes. The nodalization used is similar to that utilized on other Westinghouse plants recently analyzed and reviewed by ~he NRCr the only significant difference being the division of node 4 into two nodes, 4 and 18. This additional nodalization was necessary because of a restriction between these node boundaries.
- The geometric data used is given in Table L The mass and energy releases used are given in Tables 2 and 3.
Figures 4 to 17 give the break compartment pressure transients for the various breaks analyzed. Table 4 gives the maximum calculated pressure for each node. Figures 18 to 35 show the pressure differentials across* the steam generators and pressurizer for the various breaks. The maxi-mum equipment pressure differential is always less than 7.5 psi.
. ~-. *:- ..
- 1*1.1.*
31.co:. CCON.VERSION OF TMD PRESSURES TO FORCES "T:r:ans:f.or.matton :of :the .pressures into corresponding forces and moments
- a:c;:t,in;g *Dn "the :prjmary :components must be made in order to ass~ss the iimp:ac:t xif +/-he :trarrsJ.ent sub compartment pressures on the supports *
.riiyuras 1 :t:IL3 3tmw. "the IMO mode 1. Tab 1e 5 presents the appropr i a.te ~ ilr:eas <im!f ~he .:other.geometric data necessary for the trans-ffiDrmtii':t:"i:orrs.. IATil. ttmarr:sfDrmation data are consistent with TMD data.
IA 1TMD ;pns:t q>roaes:snr ::cmv:erts the pressures from TMD into elemental fflnrme:s :to the a:mp"JiE'.i :to :ttre structura 1 mode 1 of the component. The
- ca:nor:tftna:tre ~*y:stem J..ESEi :1cas its positive x-axis directed away from the tlmmik ":lm:ra:t:inn :thrru..mh :the appropri.ate primary component,* its y-axis wmttii:aaT;ty JlPWilr:d,, itml 'ii:ts :z-axis established by the right-hand rule.
Tfhe ffJJrniam:em+/-:a.":l <BQ.UB':biDn .1.5.ed to calculate forces is
=i=:x = ~x ms B
~
'F,X "ts :the f:on::e 'in *the x coordinate direction
- P i3 +/-hE fTMD) :pr:essure on the element being considered.
~x is the :pr:cj:e:c+/-inn of the area of the element with its normal
'.VEC'+/-or in +/-he x-.d i rect ion
~ is :the i!OJ;ile 111e.-asured counterclockwise from the break loca-
- tiDTI (*rnrn:a.t'iv:e x-axis) to the element centroid *
.:.P. SS:inii7l:ar ~iDn -:U; ;written to account for the vertical force com-fPDTIE!~ crai1mmf ti?:}' fP~ on area.with vertical normal vectors:
fF =fm\. JI .
The*asymmetric distribution of vertical force contributes to a moment
- abou.t _the .z..:.axis in accordance with the equation:
-Fy*R cos e where M2 . is the moment about the z axis.
Fy is the *vert i ca 1 (y) force on the e1ement. R is the radius from the component- center line to the element centroid. e is as defined previously The resultant horizontal force, vertical force, and moment time his-
- tories acting on the steam generator are presented in Figure 36, 37 and 38 for the hot leg break in element 4 case. When all possible combina-tions of all the loop compartment breaks were investigated, it was found that the peak horizontal for"~e acting on the steam generator was 314 kips. This peak occurred at 0.0251 seconds for both the hot leg break in element 4 case and the hot leg break in element 18 case.
The resultant horizontal force, vertical force, and moment ti~e histo~ ries acting on the pressurizer are presented in Figures 39, 40 and 41a for the hot leg break in element 2 case. When all possible combinations of all the loop compartment breaks were i.nvestigated, it was found that the peak horizontal force acting on the pressurizer was 141 kips. This peak occurred at 0.00813 seconds. Table 6 presents the peak horizontal forces for the appropriate breaks for the steam generator loads. Tab-le 7 present the peak horizontal forces for the appropriate breaks for the pressuri~er loads
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4.0 STEAMLINE BREAK The region immediately surrounding the steam generator for the Salem Unit~* i~ not conducive to asymmetric pressurization due to steam line breaks because of ~he openness of the design. The steamline exits the secondary.shield ~all at an elevation above the steam generator and not at the side of an enclosed steam generator as in some designs. Conse-quently, a. rupture in the vertical run parallel to the steam generator would be on the opposite side of the secondary shield wall as the steam generator and would cause no steam generator asymmetric pressurization. There would be little or no side force'and a very small vertical flow exerted on* the steam generator from asymmetric pressurization as a result of the steam line rupturing at the top because the Salem steam generators are not inclosed at the top~ The steamline break loads calculated from a* design that included an enclosure *surrounding the steam generator and attached steam lirie were conservatively used to verify the adequacy of the Salem steam generator supports. The peak horizontal loads were approximately 1000 kips for the side break (vertical run) and approximately 200 kips for the break at the top *. The 1000 kips ~rresponds to a peak differential pressure of less than 10 psi if the load is assumed to be uniformly distributed over one side of the steam generator.* The peak vertical load, due to the break at the top, was calculated to be approximately 800 kips. This is equivalent to a peak differential pressure of approximately 30 psi
- S.O REACTOR COOLANT LOOP PIPING EVALUATION The reactor coolant loop (RCL) piping was analyzed for the effect of
~symmetric press~re loads acting on the Steam Generator (S~) due to LOCA. * *A conservative forcing function was used for the analysis. The forc~ng f~nction *cons*isted of a ramp up to a peak load. of 500 kips in 0.001 seconds and' remained .constant thereafter (i.e., ramp-plateau).
This forcing function enveloped the force-time curve developed later. (See ,sect*ion 3.o.) . The RCL pipe stresses were calculated using Equation 9 of. the ASME Code Secti.on III. The resulting pipe stresses due to the ss*subcompartment pressure loads were found to be insignificant when compared with the.other faulted conditio~ pipe stresses due to dead-weight, pressure, Design Basis Earthquake and LOCA loop hydraulic forces. The faulted condition stress*limit of 3.0 Sm was satisfied with the additional pipe stress due to the Steam Generator subcompart-ment. pressure loads. Asymmetric pressure loads acting on the pressurizer are reacted almost entirely by the pressurizer supports. The pressurizer surge line is also very flexible and therefore there are no significant stresses developed in the reactor coolant ...
~
loop piping from the pressurizer load-ing. The loop piping stresses are controlled almost entirely by the hydraulic forces on the loop piping itself and all other loadings such as asymrue- . tric loads on the steam generator are insignificant. The mathematical model of the. rea~tor coolant loop is shown in Figure 4lb. The complexity of the reactor coolant loop/supports system required the use of a computer code to obtain the displacements, forces, and stresses in the piping and support members. WESTDYN, the computer code used for piping system analysis, is capable of performing an elas-
. tic analysis of redundant piping systems subjected to thermal, static and dynamic loads * .& 1.!P :. I ,a IP.;:zt4 J¥ *'+:fr .. J!i§4...s&l.M t?W<&Jifi&
. It i~ concluded from this ev~luation that the reactor coolant loop piping meets the faulted condition requirements of ASME Section III and is. capable at withstanding the additional pipe stresse~ resulting from
_ asymmetric pressure loads on the Steam Generator and Pressurizer due to LOCA"
6.0 R.C.S. EQUIPMENT SUPPORTS 6.1 Steam Generator and Reactor Coolant Pump Lower Supports The supports were analyzed for the effects of asymmetric pressure loads_ combined with LOCA loads using computer program WESAN. Table 8 gives maximum member stresses in members of the steam generator and reactor coolant pump supports expressed as a per-centage of permissible stress limits for the faulted condition *
. Of the break cases c*onsidered, only the governing (maximum) member stress is given for the columns and frame members. The permis-sible stresses, as defined in the ASME Boiler and Pressure Vessel Code Section III and Subsection NF, are below the limiting values for all members. Member 31 on the reactor coolant pump support h*ad a stress percentage of allowab.le of *99%, however due to the conserv.atism with which the stress allowables were determined, being close to the allowable stress is not an ind~cation of being close to failure. A significant margin exists prior to the
- expectation of failure, therefore the supports are stable and adequate for all loading conditions.
Preliminary analysis on the Reactor Vessel Supports, Steam Generator Upper Lateral Support and the Pressurizer Supports indicates that the structures are adequate for the applied loading conditions. Final analysis is in progress and the results will be issued via an addendum to this report
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7.0 INTERIOR CONCRETE STRUCTUR~S
7.1 INTRODUCTION
This section of the report dears with the evaluation of the adequacy of the containment interior concrete structures due to the subcompartment pressurization. In the event of an accident
-condition, i.e.,"the postulated loss-of-coolant accident from any
*one of the primary loop breaks in the steam generator or reactor
*coolant pump compartments, the pressures in these compartments rise rapidly. The affect of this pressure.on the interior con-crete structures is mainly from the differential pressures across the partitions that comprise the interior ~oncre~e.
The containment interior concrete structures provide support to the floors, piping and equipment, and also provide radiation shielding to personnel during plant operation. The major features of the structures are (a) Prima~y shield structure, formi~g the reactor cavity, {b) Secondary shield structure, forming the steam generator and pump compartments, (c) Operating floor slab, (d) Refueling canal and (e) Removable missile shield slab above the reactor. The primary shield wall is a 4-9.5 foot thick reinforced concrete structure that completely surrounds the reactor vessel and pro-vides biological shielding. It provides support to the reactor vessel, and .laterar restraints to the steam generators and reactor coolant pumps. It is located in the center of the containment, and extends vertically from the foundation slab to the operating floor. Radiation shielding, protection of the reactor coolant system and support for* the polar gantry crane are provided by the secondary shield wall (crane wall). The reactor coolant system is enclose*d by this 3-foot thick continuous reinforced concrete structure from
- the foundation slab to the op~rating floor.*
~~~~---.--...~~-------__;;.----__;,;~--=====~~
.... * * *
- 1*****>."J'**.-*<i-*
*; ...* .* *. . .. -~ - .
The operating floor consists of a 3 to 5-foot thick reinforced concrete slab that covers the reactor coolant system compart-ments.. Four steam generators, pressurizer and various pipes penetrate the floor. The floor also provides lateral restraint to the steam generators. The refueling canal connects the reactor _cavity by way of the fuel transport tube to the spent fuel pool. The floor and wall of the canal are massive concrete structures which, along with water, provide the equivalent shielding of 6-foot thick concrete. The floor is 4 1/2 feet thick * . Structural drawings of the interior concrete structures are as fol lows: Salem Dwgs: 1. 201167 A 8709-6
- 2. 208058 A 8811-3
- 3. 208059 A 8811~1 \,
- 4. 208060 A 8811~5 Se 208063 A 8811-1
- 6. 208064 A 8811-1 Note: These drawings are contained in Reference 4 Appendix A
7 .2 EVALUATION CRITERIA FOR CONCRETE INTERIOR STRUCTURE To evaluate the structural integrity of the interior concrete
*str*ucture due to pressure differential, the following load com-
~inations for abnormal condition are considered.
with the following load definitions: D = Dead loads or their related internal moments and forces. L = Applicable live loads or their related internal moments and forces.
= Loads under thermal condition generated by a postulated
.~:*.
break and inc1uding T0 (thermal effects and loads during normal operating or shutdown conditions).
= Pipe reactions under thermal conditions generated by a postualted break and including R0 (pipe reactions during normal operating or shutdown conditions).
= maximum differential pressure load across a compartment generated by postulated break.
= loads generated by operating basis earthquake (OBE).
= Loads generated by safe shutdown earthquake (SSE).
~.
Yr = Loads on the structure generated by the reaction on the broken pipe during a postulated break. Ym = Missile impact loads on the structure generated by or
*during a postulated break.
Yj = Jet impingement load on a structure generated by a postu-lated break. For the load combinations where D or L reduces the effect of the pressure and other associated accident loads, the corresponding coefficients are taken as 0.9 for dead load and zero for live load. Appropriate dynamic load factors are used for the accident loads,
. Pa , Y.J and Yr in the three *load combinations.
Since the peak loads from cross-wall differential pressure along with other dynamic loads from the postulated accident diminish in a few seconds and the thermal loads. on the structure from the accident will not become effective until a much later time, the .load Ta in the load combinations above will degenerate to the* value T0
- Westinghouse SSDC l.19(l) *document indicates that catastrophic failure of the reactor vessel, steam generators, pressurizer, reactor coolant pump casings and piping leading to generation of missiles is not postulated. Components within the reactor coolant accident boundary whose failure may result in postulated missiles
- are instrument wells and thimbles, nuts and bolts, control. rod drafts shats and/or housings, and pressurizer heaters. Because of the localized effect of some of these postulated missiles that are designed to be contained in a local region or because of the small amount of the kinetic energy associated with some of these mis-siles, the effect of the postulated missile are small and are neglected in the evalulation.
- In load combinations (2) and (3), local sectfon strengths and stresses may be exceeded under the concentrated loads Yr and Yj' provided there will be no loss of function of any safety-rel~ted system *
- 7.3. ANALYTICAL MODEL AND METHOD OF ANALYSIS The analytical model used in the evaluation of'the structure is based on the finite element approach, using program NASTRAN( 2),
and supplemented by post-processors. This finite element model, as shQwn in Figures 42 thru 47 is an integral of all concrete _walls and slabs within and including the crane wall, above the foundation slab.* To redu*ce the size of this complex and detailed model, symmetry about the center line of the east-west containment was employed so that only the southern half of the interior con-crete structures were actually modeled. Proper boundary condi-tions were applied at the plane of symmetry to generate both symmetric and asymmetric models thereby accounting for any loading that is not in the nature of symmetry. The coordinate system of the model is x-along south, y-vertical up and z-along west with the origin at the intersection of the con-tainment centerline and **the plane of elevation 77' 11 11
- The model consists o.f 905 quadrilateral pi°ate elements, 184* triangular plate elements and has approximately 5850 degrees of freedom. All elements are isoparametric, and nodal displacements/rotation and element forces/moments can be calculated. As previously mentioned in the criteria section all loads associated with compartment pressurization during an accident condition are considered. Dead loads are calculated from a given concrete density and the element geometry while live loads are applied at the nodes. Thermal induced loaqs are considered as a uniform temperature rise throughout the structure. Equivalent static 11 g11 loads are applied to the model to account for the seismi~ effects. Accident pres-sures, jet forces and equipment support reactions are applied as equivalent.static loads with appropriate* dynamic load factors for each one of them *
*- .. - . -*"" --~--.:--*4**----
Acddent pr:-essure loads are of primary interest in this analysis * . Figure 48 shows a typical plot of pressure differential across a
- concrete wall immediate to a break in a hot leg. Figure 49 shows
_-a _ similar plot for a wall away from the same hot leg b.reak. Two corresponding plots for a cold leg break are given in Figures 50
- and.S-1. Sin_ce a static analysis method was employed, the maximum
*pressu.re differentials* were used in the NASTRAN input with dynamic
. _load_ .factors of 1.2 for all hot leg and 1.1 for all cold leg breaks. The value of 1.2 was arrived from the curve in the book
. by Biggs, {3) with a rise time of tr = 0.035 seconds .and natural period of T = 0.04. seconds. The value of 1.1 was calcu-lated from the same curve for a rise* time of 0.2 seconds and a natural period of 0.04 seconds.
After the flexibility analysis by NASTRAN, a post processor is used to combine the element forces/moments of various loadings cons*idered for all the loading combinations~ Then a second post-processor is used to calculate the required reinforcement in all elements of wa'lls and slabs. This post processor uses the ultimate strength design method for reinforced concrete. The results of the presen~ analysis are compared to the reinforcement as specified on the design drawings to show the adequacy of the structure.
/
I
7.4 RESULTS AND CONCLUSIONS It is found that the containment interior concrete structures are adequate to sustain the accident pressure loads, based on the evalua.tion criteria set forth in Section II, in the event of reactor- coolant loop breaks in the subcompartments. The only
. exception is the local load ~ffect in the concrete slab of the operating floor because all of the steam generator upper support loads are not available at the time of this evaluation.
Shown in Figure 52A and 528 is a sample of tabulated computer out-put to compare the calculated required reinforcement in the con-crete with what has been provided in the existing design. In pl~ces, the calculated reinforcement may exceed the reinforcement
.availa~le in design in certain elements due to the concentric application of loc~l loads~ Engineering calculations were per-formed to average the force/moment in these immediate areas.
A sample deflection plot is shown in Figure 53. T.his is the cross section view of a N-S sect ion from the symmetric model. Deflec-tions from dead load and accident pressure indicate that good flexibility analyses were obtained from the NASTRAN code. L.~_~-_-----------------~
- 8. 0 REFERENCES
- 1. Westinghouse System Standard Design Criteria 1.19, "Criteria for Protection Against Dynamic Effects Resulting from Pipe Rupture, 11 Westinghouse Proprietary Class 2, Revision 0, March 1978, West-inghouse Electric Corporation, Pittsburgh; PA.
- 2. MSC-NASTRAN Level 15.5, The MacNeal-SchwendJer Corporation.
MSC-51 Version, September 8, 1978.
- 3. John M. Biggs, "Introduction to Structural Dynamics," McGraw-Hill, Inc., New York, 1964.
- 4. "Dynamic Analysis of the Reactor Coolant System for Loss of
*Coolant Accidents: Salem Nuclear Generating Stations I and II" December 1, 1978, NS~TMA-1996 . ;b 40 w 4 s:r ¢ Xi) : .... uµ .. s.: , a _.J A #.P- ... ,.>.Z ; ,q; ca;_ .J. iALtt a .; 2
TABLE 1 CONTAINMENT GEOMETRIC DATA TMD Node Volume (ft3 ) 1 19000 2 14400 3 27900 4 29900 5 27900
.6 29400 7 25700 8 34200 9 40600 10 38800 11 5700
. 12 5700 13 37000 14 32800 15 52900 16 52900 17 2068000 18 29900 i
~-**
TABLE 1 (Continued) SALEM NUCLEAR GENERATING STATION REACTOR CONTAINMENT SUBCOMPARTMENT DATA EQUIV. INERTIA EQUIV. HYDRAULIC MINIMUM MAXIMUM LENGTH LENGTH DIAMETER AREA AREA FLOW PATH K F LI _gq DHEQ AMM AMAX 1-2 0.19 0.0095 - 9.44ft 8.01 ft 23. 95ft 1094.0ft2 1548.8ft2 2-3 0.262 0.0095 18.40 17.15 21.50 1044.3 1548.8 3-4 .* 506 0.0095 23.02 18.85 19.67 757. 1377 .2 (1) 4-18 1.13* 0.0095 31.34 28.54 .14 201.8 1377.2 (1) 18"-5 *506 . 0.0095 23.03 18.85 19.67 757
- 1377.2 (1) 5-6 0.215 0.0095 23.84 20.91 24.56 1044.3 1353.
--11 .
6-1
-17 3-17 1.23 1.3 1.36 1.37 0.0095 0.0095 0.0095 0.0095 21.42 5.57 14.31 14.22 19.16 5.01 8.23 7.95 5.78 1.80 4.77 8.42 72.4 12.9 93.9 162.1 1372.8 14,940 14,940 14,940 4-17 L4 0.0095 8.58 5.44 6.~4 81 14,940 (1) 18-17 .L4 0.0095 8.58 5.44 6.54 81 14,940 (1) 5-17 1.37 0.0095 14.22 7.95 8.42 162.1 14,940 6-17 L39 0.,0095 7.10 5.15 6.32 81. 1 14,940 1-7 1.3 0.0095 7.58 4.68 3.03 33.3 1098.1 7-14 1.21 0.0095 2.93 0.733 2*. 29 105.1 1098.l 14-17 1.4 0.0095 2.49 1.008 5.24 102.7 14,940 6:..s 1.28 0.0095 7.42 4.46 6.48 45.0 1168.0 8-13 1.15 0.0095 3.83 0.935 7.44 152.6 1171. 8 13-17" 1.39 0.0095 4.39 1.370 10.88 211.6 14,940 4-9 L24 Oa0095 6.59 4.35 6.37 45.0 *1805.0 (1) 18-10 1.24 0.0095 6.59 4.35 6.37 45.0 1805.0 (1) 9-15 1.03 0 .. 0095 5.61 1.519 3.24 359.7 1805.0
TABLE 1 (Continued) SALEM NUCLEAR GENERATING STATION REACTOR CONTAINMENT SU~COMPARTMENT DATA EQUIV. INERTIA EQUIV. HYDRAULIC MINIMUM MAXI Ml.JM LENGTH LENGTH DIAMETER
- AREA AREA FLOW PATH K F LI .J:m DHEQ AMM AMAX.
15-17 1.31 0.0095 5.16ft l.447ft ll.63ft 338.7ft 2 14,940ft2 10:..16 1.03 0.0095 5.61 1.519 3 *.24 359.7 1805.0 16-17 . L31 0.0095 5.16 1.447 11.63 338.7 14,940 7-9 Oo72 0.0095 87.29 84~07 16.64 329.3 505.3 9:-10 0.27 0.0095 93.39 74.64 12.86 236.5 33L5 10-8 1.8 0.0095 94.50 87.26 15.27 329.3 590.3 8-7 l.,03 0.0095 26.90 14.10 8.29 130.l 590.3 14-15 0~0095 95.5 95.5 20.23 451.1 451.1 0.0095 117 .4 117...4 20.23 451.1 451.1
- 13. 0.0095 100.0 100.0 20.23 " 451.l 451.l 3-14 0.0095 84.90 81.48 20.20 428.6 451.l 11 1.19 0.0095 14.11 9.27 8.48 97.9 1805 10-12 1.,19 0.0095 14.11 9.27 8.48 97.9 1805 1,2-17 1.4 0.0095 7.07 5.33 2.51 . 52.2 14,940 12-17 1.4 0.0095 7.07 5.33 2.51 52.2 14,940 12-15 1.4 0.0095 3.46 3.04 2.95 42.2 3,415 12-16 1.4 0.0095 3.46 3.04 2.95 42.2 3,415 3-11 L25 0.0095 4.87 2.59 6.46 50.5 1071.3 5-12 L.25 0.0095 4.87 2.59 6.46 50.5 1071.3 2-11 1.22 0.0095 4.63 2.49 8.23 37.4 572 6-12 0.66 . 0.0095 13.86 8.75 11.85 37.4 11)163.
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TABLE 2
. SHORT TERM BLOWDOWN COLO LEG DEG - INLET TEMP *-544 S\Jt't1ARY **BREAK MASS FLOW AND ENERGY FLOW TIHE(S)* HASS FLOW(LB/S) ENERGY FLOW(9TU/S) "AVG ENTHALPY(BTU/LB)
.00000 9.SOOOOOOE+03 S.1269600E+06 539.68
.00100 2.9666790E+04 . 1.585222GE+O? 534.34
.00201 4.0341319E+04 2.15576~6E+07 534.38
.00300
- 4.7292569E+04 2.5272171~+07 534.38
.00401 . S.13555SSE+04 2.7i09437E+07 534.36
. ~00501 5 .46530J1 E+04 . 2.9202010E+07 534.32
.00601 5.6291837E+04 3.0074307E+07
- 534.26
.00701 5.709?976E+04 3.0501515£+07 534. 18
.OODOO* 5. 731572liE+04 3 .05*11493E+07 534.09
.00901 5. 7119/.,35E+04 3.05C0:69c+07 533.93
.01001 . 5 .66375C9E+04 3.023i'96l~E+07 533.69
.01101 5.59334CiE+04 2. 93B'>0.!t5E+07 533.80
.01200 5.5247761E+04 2.9l~C3342E+07 533.75
.*01301 5.4503331E+04 2. 9090483E.+07 533.73
.01400 5 .3i3l,6875E+04 2.8741303E+07 533.76
.. 01501 5.331CCOSE+04 2.84535t.OE+07 533.82
.01603 5.2950440E+04 2.;827C547i:+07 533.91
.* 01702 5.277C~02E+04 2.8179426E+C7 .*;.* 534.00
.01801 5.2754332E+04 2.8175356E+07 534.08
.* 01903. 5.2858107E+04 .*. 2.8234001E+07 534.15
.02002 5.3023612E+04 2.8325097E+07 . 534.20
. *02102 5.3234459E+04 . *.. 2.8439936£+07 534.24
*02200 .... 5.3466532E+04. 2s8565871E+07 534.28
.02303 5 .3714269E+04 .. 2.869?311E+07 534.30
- c0240Q 5.3956454E+04 2.8830635E+07 534.33
.* 02505 5.4212332E+04 2.8%C984E+07 534.36
.02601 5.44480.SSE+04 2.9015732E+07 534.38
.02702 5.4681409E+04 2.9221481E+07 534.40
. n028Q4 5.4911461E+04 2.9345501E+07 534.42
.02904 5.5129347E+04 2.9463501E+07 534.44
.03003 5.5335714E+04 2.9574l300E+07 534.46
..03102 5.5539019E+04 2.9684793E+07 534.49
.. 03200 5~5737229E+04 2.9791916E+07 534.51
.. 03306 5 .*5929617E+04 2.9895947E+07 534.53 e03401 5.6109120E+Q4 2.9993176E+07 534.55
..03500 5.6280454E+04 3.0085995E+07 534.57
.. 03601 5.6449272E+04 3.0177543E+07 534.60
.03701 5.6608138E+04 3.0263324E+07 534.62
.03800 5.6761247E+04 3.0347309E+07 534.65
.,03901. 5.6955331E+04 3.0471290E+07 535.00
TABLE 2 (Continued).
-~04001 - 5.7269953E+04 : 3.064392SE+07 535008 .04101 S.7656602E+04 * . 3.0853823E+07 535.13 .04201 5 .8075l163E+04 3.1079767E+07 535016 .04301 .S.850515SE+04 3.1311344E+07 535.19
- 04401 . 5.892l332E+04 3.1535556E+07 . 535.21
.04501 S.9320544E+04 3.1750407E+07 535023 .04601 6.3634541E+04 3.4316400E+07 538.85 .04700 7.95667o5E+04 4.26435931:+07 535.95 .04800 7.7726402E+04 4.1695644E+07 536044 .04900 8.0215430E+04 4~2993834E+07 535.98 .05001 8.0361150E+04 . 4.3070354E+07 535.96 .05101 8.1357361E+04 4.3623686E+07 536.20 .05201 8.2793402E+04 4o4389343E+07 536.15 .05301
- 8.30444B2E+04 4.4491091E+07 535075
- 05401 7. 9564071 e+04 . 4v2612590E+07 535.58
.05501 . 8 .0271996E+04 4.3029.S10E+07 536.05 .05601
- 8.1231675E+04 4.351t3654E+07 . 536.04
.05702 8.2403089E+04 4.4167075E+07 535.98 .05802 8.2107841E+04 4.39C6645E+07 535072 .05901 8.2391149E+04 4.41722SOE+07 536.13 .06002 8.4055816E+04 4o507451JOE+07 536025 .06102 8.4874937E+04 4.5498522E+07 536.07 .06202 8.4939713E+04 4.5526324E+07' 535.98 .06301 8.4846055E+04 4.5475601E+07 535.98 .06401 8 .. 4936107E+04 . 4.SS56161E+07 536.04 .06504 8.5254547~+04 !t.56985C0;;+07 536.02 .06602 8.5209319E+04 4.5664637E+07 ,. 535.91 .06702 . 8.4787522E+04 4.543o617E+07 535 .91 .06802 . 8.4931443E+04 4.5526872E+07 536.04 .. 06902 . 8.5359472E+04 4.5760620E+07 536.09 .07002 8o58C0114E+04 4.6041882E+07 536.12 .,07102 8.61817o8E+04 4.6200564E+07 536.08 *07203 8.6362700E+04 4.6293757E+07 536.10. .07303 8.6593759E+04 4.6423590E+07 536.11 .. 07404 8.672%97E+04 4.6493194E+07 536.07 .* 07501 8.6664177E+04 4.6452127E+07 536.00 .07603. . 8.6473291E+04 4.6350647E+07 536.01 .07701 . 8.6541939E+04 4.6390084E+07 536.04 .07804 8.66468130E+04 4.6445776E+07 536.04 .07902 8.6772C22E+04 4.6513130E+07 536.03 .,08000 8.63~1437E+04 4.6559071 E+07 536.02 .08105 8.691426DE+04 4.65858171:+07 536.00 .08201 8.693203tlE+04 4.6593096E+07 535.97 .08301 8.6823136E+04 4.6528552E+07 535.90 .08405 8o6470445E+04 4.6334585E+07 535.84 .08501 8~6248120E+04 4.621744SE+07 535.87 .08604 8.6188126E+04 4.6182932E+07 535.84
TABLE 2 (Continued)
- *08703
.08803
.08903
.09003
.09100
*09207
.09302
.09402 *-*.
8.6013969E+04 .. 8.5859198E+04 8.5840264E+04 8.5694045E+04 8.5419078E+04 8.5222317E+Q4 . 8.5019145E+04
*8.473771-5E+04 4.6084447E+07 4.6001745E+07
. 4.S9a9739E+07 4.5904662E+07
- 4.S754D76E+07
.4.5647741tE+07 4.5533616E+07 4.53S0167E+07 535 .. 78 535.78 535 .. 76 535.68 535.65 535.63 535.57 535.54
.09503 8.4591554E+04 4.5301321E+07 . 535.54
......... .09605 8.4520122E+04 4.5259933E+07 535.49
.09702 8.4407010E+04 4.519b470E+07 535.46
.09806 . 8.4363.157E+04 4.5171301E+07 535.44
'.09904 8.4337431E+04 4.S155015E:t07 535.41
.10006 8.4329226E+04 4.S148437E+07 535.38
.10204 8.4337130i:+QI, 4.5147633E.+07 535.32
.10404
- 8.42C650DE+04 4.5114026':+07 535.25
.1(16(), ~.4119976E+04 4.501fi7"iOE+07 '5"i.1'5
.10604 8.3955618E+04 4.4924163E+Q7 535.09
.11006 8.3899711E+o4 4.4838934E+07 535 .. 03
.11201 8.3964362E+04 4.4919316E+07 534 .. 98
.11403 8.4056578E+04 4.496301CE+07 534.91
.* 11602 8.4097144E+04 4.497844SE+07 534.84
.11802 8.4129106E+04 4.4989533E+07 534.77
.12006 8.4230813E+04 . 4.5038735E+07 534 .. 71
.12201 8.4429354E+04 4.51li0391E+07 534 .. 65
- .* 12404 8.46~BS99E+04 4 .. 5274324E+07 534 .. 60
.12607 8.4941925E+04 4.5403690E+07 534.53
..,12811 8.5145649E+04 4o5506006E+Q7 534.45
.13008
- 8.5320055E+04 ~ 4.5592714E+Q7. 534.37
.13207 8.5SC~675E+Q4 4.5687139E+07 534.30
*13408
- 8.5731095E+04 . 4.5799747E+07 534.23
.13609 8.5970882E+04 4.5921497E+07 534.15
.,13808 8.6202351E+o4 *4.6038561E+07 534.08
.14008 . 8.6413482E+04 4.6147133E+Q7 ... 534.00
.14209 8.6619274E+Q4 4.62473392+07 533~92
.14401 8.6795341E+04 4.633443SE+o7 533.84
.14608 8.69617138E+04 4.6415772E+07 533~75
.14808 8.7094774E+04 4.6479276E+07 533.66
.15002 8.7193454E+04 4.6524516E+Q7 533.58
.15205 8.7260375E+04 4.6552293E+07 533.49
.15409 . 8. 72~ti!l34E+04 4.6559483E+07 533.1.0
... 15607 8.7287495E+04 4.6551077E+07 533 .. 31
.15eos 8.7272~6E+04 4.6535755E+07 533.22
.16007 8. 7258463E+04 .
- 4.6521154E+07 533.14
.16208 8.725J444E+04 4.6510172E+07 533.07
*.16408 . 8. 72 ~0267E+04 4.6498175E+Q7 532.99
.,16611 8.7213813E+04 . 4.6477410E+07 532.91
TABLE 2 (Continued)
.16807 8. 7163091 E+04 4.6443890E+07 532.84
.17005 8.7084311E+04 4.6395328E+07 532.76
.17202 8.6983057E+04 * *4.6334995E+07 532.69
.17408 8.6854780E+04 4.6260071E+07 532.61
.17601 8.6714169E+04 4 .6179117E+07 532.54
.* 17805 8.6539577E+04 4.6079761E+07 532.47
.18002 8.6329322E+04 4.5961745E+07 532.40
.18204
- 8.6096770E+04 4.5832244E+07 532.33*
.18403 8.SS57879E+04 4.5699859E+07 532.27
.18600 8.5623957E+04 4.5570126E+07 . 532 .21
.1~802 8.5369156E+04
- 4.5429188E+07 . 532.15
.19003 8.;5090251E+04 4.5275347E+07 532.09
.19202 8.4833540E+04 4.5134363E+07 532.03
*19406 8.4593894E+04 4.50020513E+07 531.98
.19603 8.435970SE+04 4.4873242E+07 \
531.93
.19802 8.41133447E+04 4.4774896E+07 531.87
.20006 8.4032968E+04 4.4691204E+07 531.83
.20509 8.385732SE+04 4.4538031E+07 531.72
.21004 8.4011389E+04 4.46645COE+07 531.65
.21sc1 8.4363720E+04 4.4846246E+Q7 531.58
.22007 8.4807831E+04 4.5076633E+07 531.51
.22507 . 8.5232560E+04 4.5296344E+07 531.44
.23012 8.5616797E+04 4.5494115E+Q7 531.37
.23510 8.S923865E+04 4.5650540E+07 531.29
.24016 8.6152424E+04 4.5764925E+07 531.21
.24509
- 8 .6303290E+04 4.SS40610E+07 531.13
.25008 8.6423271E+04 4.589459BE+07 531.04
.25502 8.6470317E+04 4o5912302E+07 530.96
.26002 8.6417673E+04
- 4.5875924E+07 530.86
.26512 8.6256230E+04 4.5781866E+07 530.77
.27007 8.6019512E+04
- 4.5648362E+07 530.67
.27506 8.5726600E+01+ 4.5405419E+07 530.;59 .
- 28002 8.5395036E+04 4.5302387E+07 530.50
.28505 8.5040406E+Q4 . 4.5107676E+07 530.43
.29010 8.4705346E+04 4.4924192E+07 530.36
.29502 8.4444056E+04 4.47E:0949E+07 530.30
.30003 8.4235191E+04 4.4693032E+07 530.26
.30503 8.4264926E+04 4.4679901E+07 530.23
.. 31009
- 8.4399729E+04 4.4749.>-!31 E+07 530.21 031501 . 8.4667792E+04 4.4890434E+07 530020
.32012 8o50315SOE+04 4.S081617E+07 s30.1a
.32503 8.5385963E+04 4.5267637E+07 530. 15
.33010 8.56820S6E+04 4.5422046E+07 530.12
.,33508 8.5865964E+04 4.5515390E+07 . 530.07
.,34019 8.5936584E+04 4.5548477E+07 530.02
.34505 8.5913760E+04 4.5531871E+07 529.97
.35019 8.5832577E+04 4.5484482E+07 529.92 I
I e ..
- .35505 8.5731292E+04 TABLE 2 (Continued) .
4.5426833f+07 529.87
.* 36010 8.5625320E+04 4.53669Q3E+07 529.83
..36505 - a.s514111c+04 4.5304534E+07 529.79
.* 37002. 8*.5390123E+04 4.523535l1E+07 529.75
.*37504 8.5245221E+04 4.5155071E+07 529.71
. *;.38005 8.5097514E+04 4.5073422E+07 529.67
.38503 8.4963440E+04 4.4999294E+07 529.63
*.39013 8.48577G9E+04 4.4940359E+07 ~ 529.60
,.39513 8e4:?04927E+04 4.4909<J47E+07 529.57
.40004 8.480~l,6S:;+04 4.4909522E+07 529.54
-.40505 8.487638GE+04
- 4.4943350E+07 529.52
.41010 8.4994445E+04 4.5003797E+07 529.49
,.41506 8.5118753E+Q4 4.506741SE+07 529.47
.* 42013 8.5219014E+04 4.s11eo11e+o1 529.44
'.42505 8.526!t604E+04 . 4.5139345E+07 529.40
.43005 8.5236M1E+04 4.S121222E+07 529.36
- .43511 8.5125910c+04 4.5059053E-i07 529.32
*.44013 8.4961C64E+04 4.4968565E+07 529.28
. ; .44519 8.4Ci35516E+04 *4.4899963E+07 529.26
.45009 8.4756623E+04 4.4856102E+07 529.23
*.45510 8.45o4491E+04 4.4762220::+07 529.20
. -... 46012 8.4441036E+04 4.4684310E+Q7 529.18
.. 46516 8.4310392E+04 4.461304SE+07 529.15
.* 47005 8.41e2606E+04 4.4543.461 E+07 529.13
*.* 47505 8.4C~5130E+04 4.4479405E+07 529.11
.* 48011 8.4C02782E+04 4.44451C~E+07 529.09*
.* 48506 8.4039:3t.SE+04 4.4464053E+07 529.08
- .,49007 8.4102951E+04 4.4496177E+07 529.07
... 49511 8.4153770E+04 4.4521676E+07 529.05
.50013 8.4233692E+04 4.4562779E+07 529.04
.. 51014 8.4352637E+04 .4.4622342E+07 529.00
.,52017 8.43::!~333E+04 4.4636229E+07 528.95
.53008 8.437SC91F+04 4.4626G92E+07 528.91
.54011 8.4212453E.>>04 4.4535621E+07 528.85
.. 55012 8.39372HE+C4 . 4.4335361E+Q.7 528.79
.. 56001 8 .3639112E+04 . 4.4250643E+07 528.75
.57005 8.3t.03~03c+o4* 4.4203412E+07 528.72
.58010 8.35611<;0E+04 4.4173551E+07 528.70
.59017 8.356S940E+04 4.41C0~66::+07 528.67
... 60005 8.3616142E+04 4.4203653E+07 528.65
.61008 8.3630!.05E+04 4o420J634E+07 528.62
.62004 8.3553425E+04 4.4164395E+07 528.58 .
*63007
- 8.3424072E+04 4.409352uE+07 528.55
.64001 8.326~037E+04 4.4006745E+07 528.51
.,65011 8.3095374E+04 4.3914933E+07 528.49
- .66002 8.2972551E+04 4.3848002E+07 528.46
.67006 8.2914367E+04 4.3815921E+07 528.45
TABLE 2 (Continued)
.68002 8.2910983E+o4 4.3813023E+07 528.43
.69014 8.2905588E+04 4.3803932E+07 528042
.70011 8.2e62832E+04 4.3735099E+07 528.40
.71005. *8.279516SE+04 4.3748314E+07 528.39
.72004 8.2704208E+04* 4.3699205E+07 528.38
.73006 8.2584379E+04
- 4 .363501 ZE+07 528.37
.74019 8.2462827E+04 . *
- 4.3570110E+07 528.36
.75011 8.2364652£+04 4-.35178ME+07 528036
.76010 : . . 8.2291312E+04 4.3479031E+07 528.36
.77001 8. 221, 7739E+04 4.3456202E+07 528.36
.78004 8.2229975E+04 4.3447237E+07 528.36
.79003 8.2197644E+04 4.3430541E+07 528.37
.80018 8.2117324E+04 4.33u:JS49E+07 528.37
.81001 8.2CD6973E+04
- 4.3331037E+07 523.38
.82006 8.10?.'.l459E+04 4.3275020~+07 528.40
.83020 8.1806127E+04 4.3227072E+07 528.42
.84009. 8.1729137E+04 4.3ia;oo~;:+o1 528.44
.85002 8.17C0349E+04 4.321919!>E+07 523.43
.86002 8.1'101069E+04 4.32J570.JE+07 528.51
.87011 8.2001242E+04 4.3341174E+07 528.54
.88019 8.2074635E+04 4.3382777E+07 528.Se
.89010 8.2142618E+04 4.3421797E+07 528.61
.. 90003 8.21726l>2E+04 4.344Q'.j';~!+07 528.65
.91009 8.219197CE+04 4.345493</e+Q7 528.70
.92023 . 8.2242299E+04 4.34~5722~+07. 5;s .. 1s
.93009 8.2263925E+04 4.35011G5£+07 5c:a.eo
.94002 8.,2246366E+04 4.3lt96337~+07 528.85
.,95025 8.2256954E+04 4.3507095E+07 528.92
.96008- 8.2293310E+04 4.3531754E+07 528.98
.97009. 8.22B1111E+04 4.3530713E+07 529.05
.98001 8.2231270::+04 4.3510271E+Q7 529.12
.,99008 8.219602SE+04 4.3490416E+Q7 529.20
*1.00003 ... 8 .. 218107SE+O:. 4.3497811E+07 529.29
**V:.
/_
r ... . I _ .:.-'.A: .¥.. ,.*** M* ( , * , ** ~fi .4&
- ca. _.::;.z; a C&CWWWN!AM &
14'.#WA ;;_ ~~*.E&C&il...¥9.P.. .,K§ 14£6. '- . .E4 Ci. ?S. .¥ S. - .PA..
TABLE 3. HOT LEG BREAK RELEASES TIME {sec) MASS ENERGY
. 0-. 9.3750E+03 5.8335E+06 1.0lOOE-03 5.5087E+04 3.4119E+07 3.0lOOE-03 7.9703E+04 4.9325E+07 4.0lOOE-03 7 .8060E+04 4.8261E+07 7.0200E-03 6.7104E+04
- 4.1413E+07 9.0lOOE-03 6.4921E+04 . 4.0104E+07 l.3010E-02 6.7063E+04 4.1445E+07 3.9000E-02 7 .3665E+04 4.5653E+07 4.6010E-02 7.6558E+04 4.7449E+07 4.7010E-02 8.3708E+04 5.1930E+07 4.BOOOE-02 7.9944E+04 4.9548E+07 4.9010E-02 8.3571E+04 5.1808E+07 5.lOlOE-02 8.2752E+04 5.1289E+07 5.3000E-02 8.3052E+04 4.1464E+07
. 6.lOlOE-02 7.9698E-+04 4.9380E+07 6.3020E-02 8.1442E+04 S.0470E+07 6.5020E-02 8.0335E+04 4.9790E+07 6.SOlOE-02 8.1702E+04 5.0642E+07 7.1030E-02 8.1540E+04 S.0546E+07
- 7.3000E-02 7.4010E-02 7.SOOOE-02 8.5020£-02 8.9030E-02 9.3010E-02
- 7. 9443E+04 8.2200E+04
-8 .1408E+04 8.0270E+04 7 .9714E+04 7.9600E+04 4.9239E+07 5.0975E+07 5.0452E+07 4.9727E+07
.4.9372E+07 4.9290E+07 9.6050E-02 7 .9762E+04 4.9386E+07 9.9050E-02 7.9915E+04 4.9473E+07 l.1507E-Ol 8.0404E+04 4.9736E+07 l.2501E-Ol 7 .9716E+04 4.9279E+07 1.5510E-Ol 7 .3877E+04 4.5592E+07 1.7003E-Ol 7.1882E+04 4.4340E+07
. l.9001E-Ol 7 .1161E+04 4.3848E+07 2.1019£-01 7.1253E+04 4.3826E+07 3.1006E-Ol 6.7553E+04 4.1184E+07 3.5006E-01 6. 7145E+04 4.0788.E+O?
4.2017E-Ol 6.5554E+04 3.9622E+07 6.8026E-01 6.2077E+04 3.7088E+07 L0002E+OO 5.8637E+04 3.4954E+07 2.0002E+OO 5.* 0525E+04 3.0421E+07 3.. 0002E+OO 4.2150E+04 2.*5800E+07
- Run terminated. at 3.0 sec.
- Run terminated at 0.5 sec.
A
. :~ * .. TABLE 5 '*1 AREAS FOR FORCE CALCULATIONS CENTRO IO HORIZONTAL VERTICAL ., TMD ANGLE
- HEIGHT AREA RADIUS AREA
.. (ft. 2)
COMPONENT ELEMENT {DEGREESl {ft.) -1fh1 (ft. 2) STEAM GENERATOR 3 o.o 12.474 296.8 2.52 55.57 4 180.0 12.474 296.8 2.52 55.57 17 -111.14 STEAM GENERATOR 18 180.0 12.474 296.8 2.52 55.57 5 o.o 12.474 296.8 2.52 55.57 17 -111.14 STEAM GENERATOR 2 o.o 12.474 296.8 2.52 55.57 3 180.0 12.474 296.8 2.52 55.57 17 -111.14 STEAM GENERATOR 5 180.0 12.474 296.8 2.52 55.57
- !}
6 o.o 12.474 296.8 2.&2 55.57
-:':'"* 17 -111.14 PRESSURIZER 1 o.o 10.46 173.2 1.76 26.9 2 180.0 10.46 . 173.2 1.76 26,9 17 -53.8
. . *~."~'
,,.,-*I** , . *. '*, .... " 1"'~
ijtp;j ff&fi* d# TABLE 6 PEAK FORCES ACTING ON THE STEAM GENERATOR (LOOP COMPARTMENT BREAKS)
* - PEAK BR~AK TYPE* HORIZONTAL TIME OF & TMD BREAK FORCE PEAK FORCE COMPARTMENT (KIPS) (SEC)
HOT .LEG IN 2 268. 0.01023 COLD LEG IN 2 191. 0.0132 HOT LEG. IN 3 211. 0.0134 COLD LEG IN 3 153. 0.0145 HOT LEG IN 3 262. 0.0186 COLD LEG IN 3 182. 0.0198 HOT LEG IN 4 314. .0.0251 . COLD LEG IN 4 223. 0.0203 HOT LEG IN 6 275. 0.0208 COLD LEG IN 6 192. 0.0241 HOT LEG IN 5 248. . 0.0165 COLD LEG IN 5 176. 0.0187 HOT LEG IN 5 257. 0.0207 COLD LEG IN 5
- 179. 0.0229 HOT LEG IN 18 314. 0.0251 COLD LEG IN 18 223. 0.0220
*FOR TMD. ELEMENT 3 AND TMD ELEMENT 5 THERE ARE STEAM GENERATORS AT BOTH BOUNDARIES. CONSEQUENTLY THERE ARE TWO ENTRIES FOR EACH BREAK FOR THESE TWO ELEMENTS
- TABLE 7 PEAK FORCES ACTING ON THE PRESSURIZER (LOOP COMPARTMENT BREAKS)
TIME OF BREAK TYPE PEAK HORIZONTAL PEAK & TMD* BREAK FORCE FORCE COMPARTMENT (KIPS) (SEC) HOT LEG IN 1 139 0.01069 HOT LEG IN 2 141 0.00813 COLD LEG IN 1 106 0.0168 COLD LEG IN 2 102 0.0116
TABLE 8 STEAM GENERATOR/R.C. PUMP LOWER SUPPORTS MAXIMUM MEMBER STRESS STEAM GENERATOR REACTOR COOLANT LOWER SUPPORTS PUMP LOWER SUPPORTS COLUMNS FRAME COLUMNS FRAME BREAK MEMBER RATIO MEMBER RATIO MEMBER RATIO MEMBER RATIO HOT 72 25.8 9 95% *41 26.3 40 49.8 LEG COLO' 79 18.8 .30 89.6 41 . 57 .6 31 99% LEG NOTE: For models and member numbers~ refer to Reference 4; Figures 3.2-1 to 3.2-11.
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