ML19261A836
| ML19261A836 | |
| Person / Time | |
|---|---|
| Site: | Atlantic Nuclear Power Plant  |
| Issue date: | 01/30/1979 |
| From: | Haga P EECOPS |
| To: | Baer R Office of Nuclear Reactor Regulation |
| References | |
| FNP-MNE-886, NUDOCS 7902080219 | |
| Download: ML19261A836 (24) | |
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, . ". m s . ' '~ g FNP-MNE-886 Offshore Power Systems cono Aomim, twr.< .
- w. oot-/2a //ca U ; - E 0 00, J . ; y, '+ , F ba ia 32211 7el v LGu;OG January 30, 1979 Mr. Robert L. Baer, Chief Light Water Reactors Branch No. 2 Division of Project Management U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20852
Dear Mr. Baer:
RE: SANDIA MEETING OF DECEMBER 6, 1978 (DOCKET NO. STN 50-437) Enclosed is a copy of a trip report prepared as a result of our December 6, 1978, meeting with your consultant G. R. Hadley of Sandia Laboratories on the subject of exchange of sump water with the basin water surrounding a Floating Nuclear Plant following a postulated core melt through accident. Mr. Gordon Chipman of y. er Staff had planned to attend the meeting but was recalled to Washington the morning of the meeting. As a result of the meeting, we believe that the Offshore Power Systems and Sandia analysts concur that t.ie Offshore Power Systems and Sandia models would yield comparable results if the same inputs and volume modeling were employed. Differences in calculated mixing times result principally from input assumptions. Sandia did not feel qualified to j"dge the relative validity of the Offshore Power Systems' aS. Jmptions and those supplied to Sandia by the Nuclear Regulatory Commission for the March, 1978, Sandia calcula-tions. A meeting with appropriate members of the NRC Staff to discuss the input assumption to the sump water-basin water exchange calculations may be appropriate. The basis for the Offshore Power Systems' input assumptions is set forth it. Appendix C to the Offshore Power Systems' comments on RDES-III, June 30, 1978. We have also enclosed a copy of an Offshore Power Systems' letter report describing the Offshore Power Systems' 30-volume sump water-basin water exchange model. Additionally, there is a plot of the results obtained with the model in 7902080 M(
t 4 Page Two January 30, 1979 the format suggested by comments in Mr. Hadley's letter to you of September 5, 1978. All of the enclosed material has been transmitted to Mr. Hadley by Offshore Power Systems. Since ely, flll ./ 'l P. B. Haga, hief Engineer Mechanical and Nuclear Engineering leb cc: V. W. Campbell A. R. Collier Enc.
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b OffshoreNowerSystems LETTER NO. title-SRE-1765
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D. H. Walker
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REPORT FORM MEETING TRIP DATE OF REPORT 1/26/79 SUBJECT OF MEETING OH PURPOSE OF TnlP Mixing between Sump Water in Platform and Basin Water Followino Postulated Core Melt-Throuj)tLAccident LOCATION OF MEETING OR COMPANY VISITED ( Irgrgf r Ig JESS) Sandia Laboratories, AGENDA LETTER IDENTIFICATION DATE OF F T / TRIP ATTENDEES iNnicATEseAn1 Time NAME COMPANY DlVislON NAME COMPANY DlVislON D. H. Walker OPS H. J. Stumpf OPS G. R. Hadley Sandia DISTRIBUTION NAME / ADDRESS
SUMMARY
OF MEETING / TRIP In the OPS comments on RDES-III (6/30/78), OPS presented P. B. Haga, II-6 analysis which showed that mixing between contaminated T. ft. Daugherty, I-6 sump water within the platform and basin water outside the platform occurred at a substantially slower rate A. S. Candris, II-6 than that employed in the f1RC RDES-III anal3 sis. (These R* A* Bruce' II-6 analyses are appendix C of the comment letter). The OPS analysis was sent by flRC to Sandia for review by fl. A. Capo, II-6 G. R. Hadley. Mr. Hadley's comments are contained to a letter to flRC of 9/5/78. OPS performed additional analysis to address some of Mr Hadley's comments. OPS sent the results of our additional analysis and evalua-tions to fir. Hadley on 10/23/78 for his review and to provide a basis for the discussion contained in this report. Results of our discussions at the meeting in the areas of Mr. Hadley's comments are presented below. (Cont. on next page) AUTHOR SIGN ATURE O ft_diL L "OM F O R M 609 S H E l. I 1 O F
MNE-SRE-1765 January 26, 1979 Page 2
- 1. Exchange between Basin and Interior of Platform due to Currents ia the Basin beneath the Platform Mr. Hadley's initial analysis (3/78) of exchange between the platform interior and the basin assumed the iaterior of the platform was one large compartment. This analysis showed exchange caused by eddying within the platform as a result of outside currents past a hole in the platform would be of the same magnitude as exchange induced by wave action. OPS examinations of the platform design showed that the region beneath the reactor vessel is subdivided into 5 compartments and that 3 of these, includ-ing the assumed holed compartment, were further subdivided and baffled by bulkheads. Thus OPS felt eddying within the platform caused by a current beneath the barge would not propogate beyond the first holed compartment.
Wave pumping action however can propogate to all compartments. After examining compartmentation and the degree of baffling in our design, Mr. Hadley agreed that wave pumping action would likely be the dominant mode inducing exchange with basin water for the FNP platform design.
- 2. Mr. Hadley noted in his comment letter that differences in parameters between those used in his analysis and those employed by OPS were the principal reason for the longer exchange times calculated by OPS. Mr. Hadley had no basis for judging which set of parameters were representative for the postulated FNP core melt through. This area requires resolution with NRC.
The basis for the input parameters selected by OPS are contained in the OPS comments on RDES-III of 6/30/78.
- 3. In his comment letter, Mr. Hadley suggested a graphical form for presentation of calculated exchange results that would permit a more complete evaluation.
We agree with Mr. Hadley and the additional analysis were plotted in the format he suggested in our letter to him of 10/23/78. These results yield the functional form suggested by Mr. Hadley and show that dilution to 50% of initial concentration occurs more rapidly than the subsequent dilution. As a result of our meeting, I consider Sandia comments on the OPS exchange analysis resolved in the sense we have reached agreement on each of the points. We agreed also that using the same inputs and volume modeling, OPS and Sandia calculations would probably yield comparable results.
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] Mf1L-SRE-1756 D.ii.tygu.y Offshore PowerSystems From H. J. Stumpf f
E xtension 2113 oate January 22, 1979 (Week #406) subject Sump Water - Basin Water Exchange Model
, I To :L-0; H. Walker f
The attached material describes the 30-volume mathematical i model used by OPS to calculate the rate of exchange of ' released sump water with basin water. Included are the water volumes in each of the 30 volumes, the equivalence between the volumes of the previous 5 volume model and the present one and the flow between tanks as a fraction of the total flow per cycle into the barge.
/ .
[ Mw i H. J. Stumpf, Manager fiuclhar Safety Engineering leb Attachment i o i I t t L 7 8
., l MATHEMATICAL MODEL FOR CALCULATING THE EXCHANGE OF RELEASED SUMP WATER WITH BASIN WATER I.
Introduction:
Reactor coolant, refueling water storage tank contents, containment spray and melted ice collect in the FNP sumps following a postulated LOCA. This collected sump water is used for long-term cooling of the core during the post accident recirculation phase and as a source of water for long-term operation of the containment spray system. In the unlikely event that a LOCA were to lead to core melting with reactor vessel melt through by the molten-debris, a flow path for sump water to the reactor vessel cavity does exist. In about half of the postulated core melt sequences, continued operation of the ECCS pumps is possible. Water pumped into the reactor vessel for these sequences could, of course, drain through the melt hole into the reactor vessel cavity and any connected volumes. Interaction between the core melt debris and the concrete at the bottom of the cavity can eventually lead to melt through of the base mat and the plate beneath it, resulting in core debris falling on the bottom of the platform. Similarly sump water could dr ain from the cavity to the volumes below eventually filling those compartments connected to the compartment beneath the reactor vessel cavity. The amount and distribution of sump water in the reactor vessel cavity and the compartments beneath it depend upon the sequence of events following the hypothetical core melt accident. For example, if the ECCS pumps are shut down prior to melt through of the reactor vessel and the concrete pad beneath the
reactor vessel and the hull are subsequently breached by the molten debris, the compartments beneath the reactor vessel and perhaps the reactor cavity itself will most likely fill with seawater which enters the hole in the hull under about 34 feet of hydrostatic head. Alternatively, if the ECCS pumps continue to operate af ter reactor vessel, concrete pad and hull melt through, the reactor vessel cavity and the compartments beneath it will contain a large fraction of sump water. It is clear that the initial concentration of sump water in the reactor cavity and the compartments beneath it can vary over a wide range, depend-ing upon the particular hypothetical core melt scenario that is postulated. The sump water-basin water exchange model does not attempt to determine the initial sump water concentrations but assumes that these values are known. The following sections provide the details of the model. II. Mathematical Model: The sump water-basin water exchange model consists basically of volume elements, representing the various compartments, with single or multiple interconnecting flow paths. The maxin.um amount of fluid that can be in any volume element depends upon its location and whether the volume is vented. A volume may be completely filled with fluid, filled with fluid to the water level in the basin if the volume is winted, or tilled with fluid until it is in hydrostatic equilibrium with the air trapped in the compartment if unvented. The flow in and out of the compartments is assumed to be slow enough so that'the system is in hydrostatic equilibrium and pressure drops due to the flow are negligible. A. Geometry: 1 In Reference 1 a model was described that consisted of five interconnected volumes. Three of these volumes (numbered 1, 4 and 5) were further com-partmentalized by girders and bulkheads (see Figures 1 ano 2). In
, -3 utilizing this model it was necessary to assign coefficients to each of the volumes to describe the mixing process. In the case of those volumes containing girders and bulkheads it was difficult to assign values to these mixing coefficients with very much confidence. As a result of this difficulty it was decided to utilize a model which considered all thirty compartments which made up the five volume model considered in Reference 1.
Figure 3 is a plan view of volumes 1, 4 and 5 of Figure 2 which shows the various compartments formed by the girders and bulkheads. The letters shown in Figures 2 and 3 correspond to the same locations. Volumes 2 and 3 remain the same for the five volume and thirty volume models. Figure 3 indicates the remaining twenty-eight volumes of the thirty volume model, the number assigned to each volume appearing in a small circle in the figure. The corners of each of these volumes is shown as a large block dot. For example, the corners of volume element 1 are iettered WXYZ. Table 1 shows the correspondence between the five volume and the thirty volume models. Table 2 indicates the maximum volume of fluid in each of the thirty volumes for a basin water level at the 90 foot elevation on tne plant (34 foot dreft). The flow paths between the various volumes are indicated in Figure 3; openings in the girders a e indicated by rectangles (for example, between volumes 19 and 20), two foot diameter manholesareindicatedbythesymbol(h)(forexample,betweenvolumes 7 and 8).
B. Flow Model A very simple flow model is used to descr:be the mixing between connected volumes. It is assumed that the hole in the barge occurs in volume 1. The flow entering volume 1 from the basin will then be split into three paths, that is into volumes 2, 4 and 10. The flow split is proportional to the free surface area along each pathway. For filled volumes, such as volume 1, the flow into the volume equals the flow out of the volume. For volumes that are not filled, the fluid volume stored in the element during inflow is proportional to its free surface area. The flow between all volumes is treated in this fashion. Figure 4 is a schematic of the thirty volume model. Each volume has an indicator showing whether it is full of fluid, filled to the level of the water in the basin or filled to a level where it is in hydrostatic equilibrium with the trapped air in the volume. Table 3 lists the flows between volumas per unit inflow for volume 1. To describe the nixing between volumes consider a volume K which has a single inflow path from volume (K-1) and a single outflow path to volume (K+1), (voluua 8, for example, is such a volume). Figure 5 is a schematic diagram of volute K. In Figure 5 Vg = the fluid volume in volume K Ck = the concentration of contaminants in volume K F g ,), g = fraction of the total flow of basin water into the barge (v) that flows from volume K-1 into volume K. (F g is defined in a similar way) i
, -b S
K = the concentration of contaminants in the small volume of fluid that flows from volume K into volume (K+1). (Sg_) is defined in a similar way) a g, p) = a mixing coefficient which indicates the fraction of the fluid in volume (K+1) which mixes with or replaces part of the fluid that flowed into volume (K+1) from volume K. (a g _), g) is defined in a similar way) It should be noted the 0 < a < 1 for all a's. A superscript is used to define the number of the cycle being calculated assuming a cylic inflow and outflow with a fixed period. The amount of contaminant in volume K at the end of cycle il is given by IYK~fK, K+1v) C +F g, y )v SyI During the inflow part of the cycle an amount of contaminant F il K-1, Kv Sg_) ft is added to volume K and an amount of contaminant Fg, g,3v Sg leaves volume K. The fluid which enters volune (K+1) from volume K mixes with that of volume (K+1) so that a fraction a g, g ) is replaced by the fluid in volume (K+1) with concentration C
). The fluid which entered volume K from volume (K-1) also mixes with the fluid in volume V, and a portion, a g _), g, is replaced by the il fluid in volume K with concentration Cg . Therefore during the outflow por-tion of the cycle an amount of contaminant equal to Fg,g,)v{(1-ag,gy))
Il SIl g + a g, g) Cg )} is added to volu..e K and an amount of contaminant cqual to F y, _), gv {(1-a g_ ) , g)S _) +u g_), g C } leaves volume ". The concentration of contaminants in volume K at the end of cycle (fl+1) is {V g -Fg,gz} v tl Cy +1 + F g gq vS11 g+1 and must be equal to the sum of the contaminant in volume K at the end of cycle ti and all inflows and outflows during the cycle. Performing the algebra the contaminant in volume K at the cnd of cycle (fl+1) is i
11 ti il il Cg+1 = Cg
-F_),g va g g _), g {Cg-Sg _)}
{Vg-FK, K+1 "} The small volume F g, g_) v which flows between volumes K and (K+1) has a new concentration of contaminant in it and mixes with the fluid in volume K before the next cycle begins. Using a mixing coefficient S g, g,) defined in a manner similcr to that for the coefficient a the new concentration of contaminant in the small fluid volume flowing between volumes K and (K+1) is given by S[I = {(1-ag, g ))S +a g, gy) C
)) (1- sK, K+1}
- OK, K+1 Fluid volumes with multiple flow paths are treated in a similar fashion.
1 'l Table 4 lists the equations tv C +1 g and S'g+1 for all thirty vo'.ames. The values of the a's and s's must be chosen in order to completely defiiie the equati ms. Where the flow path between volumes consists of a large opening in a girder the values of u and B should be relatively large (<,ay S 0.5). For volumes where the cuanecting path is relatively , small (2 foot diameter man hole) and the flow is small, the values of a and 6 should be relatively small (say s 0.1). The particular choice is a matter of judgment and a range of values should be used to determine the sensitivity of the dilution time to chcnges in the values of a and 8. The calculation is started by assigning initial values to all C gand S.g He aqiadons for all thirty volumes are then solved sequentially for e6ch cycle until a desired average concentration is reached. The dilution time is then equal to the product of the cycle time and the number of cycles.
- FLOODED COMPARTMENTS AFTER ' ~
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EQUIVALEllCE BETWEEll FIVE AND THIRTY VOLUME MODELS Five Volume Model Thirty Volume Model Volume 1 Volume 1 and Volumes 4-16 Volume 2 Volume 2 Volume 3 Volume 3 Volume 4 Volumes 17-24 Volume 5 Volumes 25-30 TABLE 1 i
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MAXIMUM FLUID VOLUME: illIRi r VOLUME 110 DEL (34 Foot Draft) Volume Number Maximun Fluid Volume (FT ) 1 3646.5 2 8148.8 3 6413.0 4 5076.2 5 932.0 6 2080.4 7 782.2 8 782.2 9 1564.4 10 3646.5 11 5076.2 12 932.0 13 2080.4 14 782.2 15 782.2 16 1564.4 17 2021.0 18 1451.8 19 1451.8 20 2021.0 21 2097.0 22 2097.0 23 2097.0 24 2097.0 25 2944.9 26 5095.2 27 2500.1 28 2500.1 29 2944.9 ' 30 5095.2 TABLE 2
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8= %,,, v % ,,, / ( M, - V % ,- ) 9e = n,,,e v a,,, , l C de - v (ni,,a + 6z,ii )) es= m,,, v a,,,,/ ea , s e,,,, 9 %, ,, / ( gi - v s, ,<) . e,= q ,, v a,,,,/ ces - v. s ,.) -
- l 6, = Egiav'i./vlc !
0r = q a V %, a / ( 47 -vl6,,,s+6,,zs'6,,c))' ,
\
e ,= 5, ,s v s ,,e / ( s - 9 Es , )
* . i
, TA BLE 4 ( C oW Y) : i c-il i
! ' i
&,,, v %,,, /N, - v 5,,,. )
~
e, = i !
;j ;i 8e s, z. ,
v <,, z. / ( v.-
, z v 6.,,, ) ;
Pz,= Q , v %, ,, / ( f, - v. 6,, ,, ) , i ll1 l i
&=%v %,,, lVn '
63 = b v %,., /(es- v 44 ) ; I j
& = 6,y V az3 z< / 64 ,.' .
8s = 5,zs v d,,,zc/ l6s - v (6x za r6z,)) 8 , 8s=5 8u v azc,zal via ., . e, = 5,,u v % z,/( 6, - v. 67, za ) ; : .
;i
& = Eue v % zs/ (sc- 9 Ee,z,)
- i 8,= 6a,,, 9 % / ( 4 ,- v 5 ,3.) '
I 0o"&, son'Az9,3.l V3a ' n+1 a - t . 6 = h*C I 0626/ I I 2 de/
'( I ~K' z) 53 A/
+
a x,, z C, ) (/ - p,, , ) + g,,, C,d+ / {':
, i I
~ i q*' = ( ( u - sz, ., ) s " r a ,, c," )(i - A,2 ) + A., C I ,.
.(' = ( ( I - a ,1 ) s," + a,,, c")( i- A, , ) + ,d,,, c,"* '
;l f' = (( / - x,,, ) 5," + x4, y c")(/A c ) < ,4,, C' . :
s'"' = ((i % ). s" qe c" Xi- s ) + 4, c"*' ,
~ , ,
i\ >
\
5-, 7
= ((1 - x,,., ) 57 + dg7 c D-47)+4.s7c-7 4 3 ,
i. ni ~ ~ nei g l~ Y ,0 )
- 8
- 1 7, & g
~
f, 8 1, 6 7 ;(l
^ i , .i f""= (( i- de,s ) S,'+ % C,~)(/- 48,,) + (Js,, C~" g .I. .;
'{
1 ilt.
0 e e *
) OM , e a' .
s af, y , y . . pp .- .- --
- Y l ~ W,, , o o I, 10 ,o I
,, , o , ,o T --
- ~ ~ ~
s;'" = ((i- a,.,,, ) 5,," + ;I[ a.. .. c " )(i- A..,,;) .+ 4,,1c,\"y S,,""
= ((I- %, ,2 ) S," + ^ , ,, c," )(i- A,, ,, ) + A, ,, f,f[. , . l s;" = c(i- a,, ,D s,," + ,
a.. ,, c,~ )('- A , ,y ) + i,,3 C,f'l0 s,,~" - ((1 - x,s is ) S," + %, ,, c,~ Xi-A., is ) + A,, ,i c,Y l C' = ((1 - %,,s ) S + %.,.cc" Xi- A,,,, y pr, ,i c,~" l l;~ s,:" = ((i- x,g,J 5,:
- a,8,. c" x i- Ag ,. ) + Ag ,. c,
- S~
'l. ,
I y 4, ,1 , h, ,9 0, i~ /b4 ,,1 h f l 4,,9 ;
~ ^' ~
q^'"
, = ( ( \ - %, ie )s, <- %, ie c,e 2 0 - A ,,,e) + A,,sc '
q,^'"= ((1- %.., ) 5," + %,,, C;;' )(1- 4,;) + As,il c,$' ' l l . s 3 w - < , ,,.. > s + n ,, u c ( i - A ,, .. ) 1 4 ,. .. h,~ * i;1; 4 " "- c ( u - < ,c,) s " + x . ., z.C : Xi,a.,>+s.,,c'i.:i:
^
sd ((i - %,z2 ) s~ + %,z, c^'z .)(i - A,,zt b 4,,e c',*'! - 5;"= ((i %,zJ s~ - x,,,,3 c~3 )(1- o,,,,,b an 4,,,, c.~f'; , o a ner g4 l ~~ 25,24 24 Z ,, E 4 24 S~ f z3,24 2 }, t + 3 -- S ,c,2, - (lu - s a, t s ) S~c + ^ ,,,u-
~ ~< 1-z C2 s )(I - A r,2 c ) + A,, rsc,, i ,
i t Sz c Yl~ 6tt,ls ) Sz &W b iztc.Cz"sh(I-bezis)+iizia0Yc
@ (( -x,gz,) s "+ %z, c " W- Ag2a + 42, c ~c *'
~
f~ S""= U >- air ,is ) su + an .iec;;' ) D - A r. m 31 h ts C
~
'.l.
6,,"= (O - dz e,c,) 5 ~,+ %, c" a z,)b- Ae, ,, 24 4,e, q c ~e"! ! E e 1 . af h 30 49, ao J ,., t,, So ) + 29, 3o 29
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