ML20150F301
| ML20150F301 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/20/1979 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20150F295 | List: |
| References | |
| 1-91, IEB-79-05C, IEB-79-5C, NUDOCS 7910010394 | |
| Download: ML20150F301 (27) | |
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Docket No. 50-346 License No.-NPF-3 Serial No. 1-91 September 20, 1979 1 i t l .' 4 1 t b i ATTACID1ENT B
; IMPACT ASSESSMENT OF A RC PUMP TRIP ON NON-LOCA EVENTS i
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}<c Y* S III. IMPACT ASSESS!:E:!T or A RC PUt? TI:IP 0 : NON-LOCA EVEt:TS .
A. Introduction .
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Some Chapter 15 cvents are characterized by a ' primary system response similar to the one following a LOCA. The Section 15.1 events that result in an increase in heat removal by the secondary system cause a primary system cooldoun and depressurization, ruch like a small break LOCA. Therefore, an asressment of the conse-qucnces of an imposed RC pump trip, upon initiation of the low RC pressure ESFAS, was made for these events. B. General Assessment of Pump Trip in 1:on-LOCA Events f a Several concerns have been raised with regard to the effect that an carly pump trip would have on non-LOCA events that exhibit LOCA characteristics. Plant recovery would be more dif ficult, dependence. on natural circulation mode uhile achieving cold shutdeva vo*uld be highlighted, nanual fill of the steam generators would be required, and so on. 11oucvcr, all of these draubacks can be accomraodated since none of them vill on its own Icad to unacceptabic. consequences. Also, restart of the pumps' is recommended for plant control and cooldown
'once controlled operator action is assumed. Out of this scarch,
',three najor concerns have surfaced which have appeared to be sub-stantial enough as to require analysia:
- 1. A ptuap trip could. reduce the time to system fill /repressurization or safety valve opening follouing an overcooling transient. If the time available to the operator for controlling HPI flow and the margin of subecoling ucre substantially reduced by the pump trip to where timely and effective operator action coulti be questionabic, the pump trip would become less desirnble. *
- 2. In the event ofga large steam 31ne break (maxinum overcooling), the blowdown may indhee a steam hubb1c in the RCS ubich could impair natural circulatipn,,
uith severe consequences on the core, es-N pecially if any degree of return'to power is experienced.
- 3. A more general concern exists "ith a large steam line break at EOL conditions and whether or not a return to power is experienced j
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following the RC pump trip. If a return to critical is experienced, natural circulation flow may not le suf ficient to remove heat and to avoid core damage.
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Ov;crhcating' event's were not considered in the impact of the RC pump trip since they do not initiate the low RC pressure ESFAS, and therefore, there would be-no coincident pump trip. In addi-tion, these events typically ado not result in an empty pressurizer or the formation of a steam bubble in the primary system. Reactivity-
-- transients ucre also not considered for the same reasons, In addi-tion, for overpressurization, previous analyses have shown that for the worst case conditions, an RC pump trip will mitigate the pressure rise. This results from the greate,r than 100 psi reduction in ,
pressure at the RC pump exit which occurs after trip. C. Analysis of Concerns and Results .
- 1. System Reoressurization i
In order to resolve this concern, an analysis was perf ormed for a 177 FA plant using a !!INITRAP model based on the case set up for TMIJ2, Figurc 3.1 shows the noding/ flow path scheme used and Tabl,c11 provides s description of the n' odes" and flow paths. This case assumed that, as the result of a small steam line breah (0.6 f t. split) or of some combination of secondary side. valve failure, secondary side heat d emand was increa' sed from 100% to 13S% at time zero. This increase in secondary side heat demand is the smallest which results in a (high flux) reactor trip and is very similar to the vorst moderate frequency overcooling event, a failure of the steam pressure regulator. In the analysis, it was assumed that following IIPI actuation on low RC pressure ESFAS, main f ecduater is ramped dotm, MSIV's shut, and the auxiliary feeduater initiated with a 40-second delay. This action uas taken to stop thc cooldoun and the depressurization of the , system as soon as possible af ter IIPI actuation, in order to , minimize yhc time of refill and repressurization of the system. So.th IIPI pumps were assumed to function. The calc 61a\gion was perfortjed twice, once assuming two of the four RC pumps running (one loop), and once assuming RC pump trip right 'after IIPI initiation. The analysis shows that the g system behaves very similarly eith and without pumps. In
' both cases, the pr,cssurizer refills in about 14 to 16 minutes from initiation of the transients, with the natural circula-
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tion case refilling about one minute before t'he. case with two of four pumps running (See Figures 3.2,3.3). In both cases, the system is highly subcooled, from a minimum of 30*F to 120*F and increasing at the end of 14 minutes (ref er to Figure 3.4). It is concluded that an RC pump trip following'IIPI actuation
"' vill not increase the probability of causing a LOCA through the pressurizer code safetics,'and that .the operator vill have the same lead time, 'as well as a large margin of subcooling,'to control llPI prior to saf ety valve opening. Alth'ough no case with all RC pumps was made, it can be inf erred from the one loop case (with pumps running) that the subcooled margin will be slightly larger for the all pumps running case. The pressuri:cr will take longer to fill but shouldd$soby16 minutes into the' transient. Figure lishows the coolant temperatures (hot icg, cold leg, and core) as a function' of time for the no, RC pumps case. ,
- 2. Effect of Steam Bubhic on Natural Circulation Cooline, For this concern, an cnalysis uns perf ormed f or the same
. generic 177 FA plant as outlined in Part 1, but assuming that 2
as a result of an unmitigated large SLB (12.2 f t. DER), the excessive cooldown vould produce void formation in the primary
. cystem. The intent of the analysis was to also show the extent of the void forcation and uhcre it occurred. As in the case analyzed in Part 1, the break was symmetric to both generators such that both would blow down equally, maximizing the cooldoun (in this case there was a 6.1 f t. break on each loop). There was no 11SlV closure during the transient on
, , either steam generator to maximisc cooldoun. Also, the tur-bine bypass system was assumed to operate, upon rupture, .
until isolation on ESFAS. ESFAS was initiated on lou RC pressure at d also actuated IIPI (both pumps), tripped RC pumps (when pplicable) and isolated the 11FWIV's. The AFU sias initiated to both generators on the low SC pressure cinnal, uith minimum delay time (both pumps operating) .
\ This analysis was performed twice, once assuming all !!C l s -
pumbs running, once with all pumpr. being tripped on the llPI actuation (after ESFAS), with a short (s5 second) delay. In both cases, voids were formed in the hot legs, but the dura-
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g ' tion and size were smaller for the case with no RC pump trip (refer to Figure 3.7).Although the RC pump operating case had a higher cooldoen rate, there was less void f orma-tion, resulting f rom the additional system mixing. The coolant temperatures in the pressurizer loop hot and cold 1 cgs, and the core, are shown f or both cases in F'igures 3.5, The core otitlet pressure and SG and pressurizer 3.6. 1cvels versus tiSe are given for both cases in Figures 3.8, 3.9. This analysis shows that the system behaves similarly with and without pumps, although maintaining RC pump flow does seem to help mitigate void formation. The pump flow case shous a shorter time to the start of pres-
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.surizer refill than the natural circulation case (Figure 3.9),
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' although the time difference does not seem to be very large.
Since.the volume of the hot-ltg locp above the. lowest point in the candy cane portion-is about 63 cubic feet, these steam f 9rmations have the potential for blocking natural circulation in the hot leg loops. As a result of these findings and since TRAP had not been programmed to closely follow this specific condition, an additional 2 TRAP case was rwn. It is based on the unmitigated 12.2 f t steam line break with RC pump trip, since this case represented the bound-ing event for steam formation. This case included a more detailed noding scheme and conservative bubble rise velocities (5.0 f t/sec) to the upper regions of.the hot legs such that the effect of steam formation on natural circulation in the loops could be observed. The noding and flow path scheme used in this model is shown in Figure 3.10. Table 3.2 provides a description of these nodes and flow paths. Figtare 3.11 details the hot leg - candy canc - upper steam generator shroud noding and f1ow path model superimposed over a scaled igure of those regions. The flow path positions and sizes' were care (ully chosen to allow for countercurrent steam and liquid flow at t(ctopofthecandycane. This model is consistent s with that used fors the small break LOCA analyses described in Sec-tion 6.2.4.2 of Ref. 5. The results' of this analysis showed steam formation only in the pr ssurizer 1oop (refer to Figure 3.12). These steam volumes are j
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conservative since they include all of the steam that was calculated as being entrained as bubblen in the liquid. The additional steam volumes calculated for this loop, compared with those shown in Figure 3,7, arc due to the additional boiling and steam separation
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_that occurs in the candy cane as the liquid flow rates are reduced by } steam formation and aided by metal heating.; The lack of steam forma- $~ . tion in the non~ pressurizer loop 'Id 'is a'ttributed to a correction in the metal heat transfer and metal heat capacities calculated for
- . the hot legs. The previous analysis crroneously included half of the steam generator tubes, based on the calculations from the ECCS ,
CRAFT model. Since the TRAP code already accounts for the tube metal-in its steam generator model, this represented an unnecessary.conser-
, vatism and it was deleted f rom the'model for this case. , This case showed that the natural circulation flow was temporarily reduced. This flow reduced .in the pressurizer loop to' 2
e 45 to 100 lb/sec from 250 to 360 seconds (refer to Figure 3.13), with flow steadily increasing af ter this time period. The flow in the non-pressurizer loop remained relatively unchanged at about 10CD 1b/sec (refer to Figure 3.14). Core flow was maintained from 1000 to 2000 7 lb/sec and no void formation occurred (refer to Figures 3.15 and 3.16). The steam bubble was collapsed, natural circulation fully ' l restored, and a greater than 50*F subcooled margin achieved in the pressurizer loop (refer to Figure 3.16). Both stcam generators and the pressurizer established level and the system pressure was turned around from the HP1 flow by 14 minutes into the transient (refer to Figures 3.17 and 3.18).
- l 3. Effect of Return to Power j~ There was no return to power exhibited by any of the BOL cases analyzed above. Previous analysis experience (ref. Midland FSAR,
- . , Section ISD) has 'shown that a RC pump trip will mitigate the '
consequences of an EOL return to power condition by reducing the i cooldown of the primary system. The reduced cooldown substan-tiallyincr\asesthesubcriticalmarginwhich, inturn, reduces or eliminates return to power.
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D. Conclunions and Summary \ A general assessmant of Chapter 15 non-LOCA events identified three 3 areas that warranted f urther invest li ;ation for impact of a RC pump trip -p r on ESFAS low ' RC pressure signal.
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}' l. It was f ound that a pump t'ip does not significantly shorten the time to filling of the pressurizer and approximately the same time interval i for operator action exintn. d
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- 2. For the maximum overcooling case analyzed, the RC pump trip increased the amount of void f'ormation in the hot leg ', candy canc' of the
. pressurizer loop;-however,' natural circulat' ion was not completely blocked. The steam bub.ble was coll'apsed and full natural circulation 1, , .-
, was restored. Core cooling was maintained throughout the transient and no void formation occurred in the core.
- 3. The suberitical return-to-power cond'ition is alleviated by the RC ,
pump trip case due to the reduced over. cooling effect. Based upon the above assessment and " analysis, it is concluded that the consequences of Chapter 15 non-LOCA events are not increased due to the addition of a RC pump trip on ESFAS low RC pressure signali for all 1/7FAloweredloopplants. Although there were no specific analyscs performed for TECO, the conclusions drawn from the analyses for the lowered loop plants are applicable. e h 4 '
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.. lH1TI:AP2NODEDESCRIPTION-NODE NUMBER DESCRIPTIO!!
1 Reactor Vessel, Lower Plenum 2 Reactor Vessel, Core 3 Reactor Vessel, Upper Plenum 4,10 llot Leg Piping and Upper S. G. Shroud
. 5-7,11-13 Primary, Steam Generator Tube Region 8,14 . Cold. Leg Piping 9 Reactor Vessel Downcomer 15 Pressurizer 16,24 Steam Generator Downcomer 17,25 Steam Generator Lower Plenum 18-20,26L28 Secondary, Stea= Generator Tube Region 21,29 Steam Riscrs 22,30 . 1:ain Steam Piping 23 Turbine
,31 Containment MINITRAP2 PATil DESCRIPTION 1
PATil NUMBER DESCRIPTION 1 Core 2 Core Bypass 3 Upper Plenum, Reactor Vessel 4,11 llot Leg Piping 5,12
- llot Leg Piping and Upper S. G. Shroud 6,7,13,14 Primary, Steam Generator 8,15 RC Pumps 9,16 Cold Leg Piping 10 Douncomer, Reactor Vessel 17 Pressurizer Surge Line i 18,19,26,27- Steam Generator Douncomer 20,21,28,29 S,ccondary, Steam Cencrator 22,30 .
Aspirator 23,31 ' i Steam Riser, Steam Generator T- . 24,32 Main Steam Piping 25,33 Turbine Piping 34,35 k. Break (or: Leak) Path 36,37 4 11PI 38,39,43,44 AFU
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. .. MINITRAP2 NODE DESCRIPTION NODE NUMBER DESC'RIPTION 1 Reactor Vessel, Lower Plenum
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2 Reactor Vessel, Core . 3 Reactor Vcssel, Upper Plenum 4,10 Hot. Leg Piping (including ' Candy Cane') 32,33- ' Candy Cane' and Upper S. G. Shroud 5-7,11-13 Primary, Steam Generator Tube' Region 8,14 Cold Leg Piping. 9 Reactor Vessel:.Dotmcomer 15 Pressurizer 16,24 ' Steam Generator Downcomer 17,25 , Steam Generator Lower Plenum 18-20,26-28 Secondary, Steam Generator Tube Region
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Steam Risers 22,30 Main Steam Piping 23 Turbine. . 31 Containment MINITRAP2 PATH DESCRIPTION PATil NUMBER DESCRIPTION 1 Core 2 Core nypass 3 Upper Plenum, Reactor Vessel 4,11 llot Leg Piping 5,12 Upper Steam Generator Shroud 45l46,47,48- Top of Ilot Leg ' Candy Canc' 6,7,13,14 Primary ifcat Transf er Region, S. G. 8,15 RC Pumps 9,16 Cold Leg Piping i 10 Downcomer, Reactor Vessel 17 Pressurizer Surge Line i- 18,19,26,27 k Steam Generator Douncomer and Plenum 20,21,28,29 V. Secondary lleat Transf er Region, S. G. 22,30 - Aspirator 23,31 \SteamRiser,SteamCencrator 24,32 - Main Steam Piping 25,33 , Turbine Piping 34',35 Break (or Leak) Path 36,37 IIPI - i 38,39,43,44 \ AFU 40,41 ' \ Main,1 feed Pumps 42 LPI . Table 3.2 i -@n -
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