ML20125C069
| ML20125C069 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/24/1979 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20125C067 | List: |
| References | |
| IEB-79-05C, IEB-79-5C, NUDOCS 8001030242 | |
| Download: ML20125C069 (27) | |
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SMUD SACRAMENTO MUNICIPAL UTILITY District C 6201 s street, Dex 15830, sacramento, California 95813, (916) 452 3211 October 24, 1979 T U.S. Nuclear Regulatory Commission h ' T1M..b
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Attention: Mr-. R. H. Engelken, ~@ '6 Director, Region V .2 - E Office of Inspection 5 Enforcement ,/ 1990 North California Boulevard .J/ l Walnut Creek Plaza, Suite 202 -
. l Wdinut Creek, California 94596 . ':P' i
j Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1 ; I
Dear Mr. Engelken:
l l In the letter to you dated August 27, 1979, the District i provided an analysis titled " Analysis Summary in Support of an Early l RC Pump Trip". l l The attachment to this letter carries a revision to Section III of that analysis. Sincerely yours, l hA, h [A l bohn J. Mattimoe Assistant General Manager l and Chief Engineer Attachment 90002244 sno,nno 26 n .., a (
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r . Un%7.00A D'D?TS III. 31tPACT ACST.SS".D'T OT A RC Titi? Tr.TP 0 :
- f. . Introdurrion So:ne Chapter 15 cvents are characterized by a ' primary syst em response similar to the one follouing a LOCA. The Section 15.1 i
events that result in an increase in heat rcroval by the secondary ' system cause a primary system cooldoun and depressurization, nuch l like a small brech 1.DCA. Therefore, an assessucnt of the conse-quenecc of' an imposed IC pu=p trip, upon init.dation of the lov RC pressure EST/.S, uns ncdc f or these events. . l 3 B. Gencrcl Ansentment of Pu .n Trin in Non-T.0CA Eventn ! l that. Several concerns have been raised with regard to the eff cet nn early pu p trip rou3d hcvc en non-LOCA events that exhibit LOCA characteristics. Plcnt recovery would be core dif ficult, dependence. , on natural circulation rode while achieving cold shutdcun uo'uld be highlighted, nanual fill of the steam gencretors would be required, cnd so on. Boucver, all of these draubaclis can be accccoodated since tilc o , l none of thc= vill on its own 1cca to unacceptabic consequences. restart of the pumps is reco==cnded for plant centrol and coo 3down "once contro11cd' operator action is assumed. Out of this scarch,
' thtcc nejor concerns have surf aced which have cppeared to be sub-stantial enough as to require analysis: f
- 1. A pump trip could reduce the time to systen fill /repressurinct. ion or safety valvc opening following an overcooling transient. If the tine availabic to the operator for controlling EPI flow and the rargin of rubcooling vere substantially redueca by the pump trip to where timely and ef f ective operator action could be '
quentienchic, the pump trip veuld beco=e Icss desitahlc. the
- 2. In the event of a large s cam line break (caxinum overcoolin;)
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blevdown nay induce a steam bubbic in th,c RCS which could impair ) es-nctural circulation, with severe consequences on the core, l l pccin11y if any degree of return'to poect is experienced. EOL l i
- 3. /. nere general concern exists uith a large stcan line breah at conditions and whether or not a return to power is experienced followin;; the RC pu=p trip. If h return to critical is experienced, l natural circuhtien floe nay not be suf ficient to remove heat and to aveid '* '""""
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' Ov;crbcating evchts uore not considered in the impact of the F.C pump trip since they do not initiate the low'RC pressure EgTAS, and LNerefore, there would be no coincident pump trip. In addi-
. tion, these events typically do not result in an c=pty pressurizer Reactivity ,
or the formation of a stcan bubbic in the primary system. In addi-transients were also not considered for the same reasons. ' for tion, f or overpressurization, previous analyses have shown that the worst case conditions, an RC pump trip will mitigate the pressure ric e. This results from the greater than 100, psi reduction in
- pressure at the RC p' ump c>:it ,uhich occurs af ter trip.
C. Annivnic of Concerns and Renults
- 1. System neprennuriration In order to resolve this concern, an analysis was performed '
for a 177 FA plant using a MINITPJ.P model based on the case l Figure 3.1 shows the noding/ flow path, j set up f or TMI22, l scheme used and Tabic 3.1 provides s description of the nodes' and flow paths. This case assumed that, as the result of a i c=all steam line breah (0.6 f t, split) or of some co:abination l of secondary side valve f ailure, secondary side heat de:nand This increase vas increased f ro:a 100% to 138% at time scro.' in secondary side heat demand is the smallest which results k in a (high flu >:) reactor trip and is very similar to the vorst modcrate frequency overcooling event, a failure of the steam pressure regulator. In the analysis, it was accumed
' that follouing HPI actuation on low RC presourc ESTAS, main feedwater is ramped down, MSIV's shut, and the au>:lliary feeduater initiated with a 40-second delay. This action was taken to stop the cooldoun and the depressurization of the system as soon as possibic af ter IIPI actuation, in order to ,
minimize the time of refill and repressurication of the system. Both HPI pumps were assumed to f unction. The calculation was performed twice, once assuming two of the four EC pumps running (onc loop), and once accuming RC pump trip right after HP1 initiation. The analysis shows that the In system behavec very similarly with and without pumps.
' both cases, the pr,essurincr' refills in about 14 to 16 minut es f rom initiation of the transients, with the natural circula-16 90002246
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I tion cacc rdfilling about one ninute beforc thc cacc vith tuo of four ptcps running (Sce Tigures 3.2.3.3). In both cacec, the cystem is highly subcooled, f rom a ninimum of 30*T to 120*r
' and increasing at the end of 14 ninutes (rcier to rigure 3.4).
It is concluded that an EC pump trip following IIPI actuation will not increate the probability of causing a LOCA through the prescurizer code caf etics, and that the operator will have to the came 1 cad time, an uc11 as a Icrge narnin of subcooling, Although no case control IIPI prior to saf ety valve opening. 1 with all EC pumps was made, it can be inf erred f rom the one 1oop case (with pumps running) that the nubcooled margin vill The
~ be slightly Inrger f or the all pu=pn running ense. ,
pressuriner will tahc longer to fill but should do co by ~16 ninutes irto the trancient. Tigure M shows the coolcut tcaperaturcs (hot Ict, cold leg, and core) as a function of time for the no EC pumps case. ,
- 2. Effect of Stem Tui$ e on hturn3 Circu3ction Cooling For this concern, an analycis.vas perforced f or the sa=c assuming that
- ncncric 177 FA plcnt as cutlined in Tart 1, but 2 ns a result of an unnitigated large SLB (12.2' it. DER), the excessive cooldown vould produce void fornation in 'the primary
- cystem. The intent of the analysis was to also show. the As in extent of the void formation and where it occurred.
the case analy cd in Tart 1, the brech was sy==ctric to both
- generators such that both cou3d blou dm a equally, naximicing break on cach t.he cooldova (in this case there vas a 6.1 f t.
loep). There van no 1:51V closure curing the transient on cither ntcan gtnerator to naxi=isc cc.oldoun. Also, the tur-bine bypass ryctem' uas accured to operate, upon rupture, , until icolatien on ESTAS. ESTAS van initiated on lou gC precsure and also actuated IIP 1 (bo(b pumps), tripped RC pumps (chen applicabic) and isolated the HT1'IV's. The ATW I
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was initiated to both generatorc on the Iou SG prescurc l cignni, with eininum delay ti=c (both pumps operating) . This analysis was performed teicc, once accusing all RC pumps running, once vith all pumps being tripped on the llPI actuation (af ter ESTAS), with a short (s5 second) delay. In ; both cases, voids ucre formed in the hot legs, but the dura-90002247
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" tion and site ucre smaller for the casc' with no RC pump
' trip (ref er to Figure 3.7). Although the RC pump operating case had a higher cooldoun rate, there was less void forna-tion, resulting f rem the additional system eixing. The coolant tc peratures in the pressurfacr loop hot and cold legs, and the cerc, are shown f or both cases in Figurcs 3.5, 3.6. The core out1ct pressure and SG and pressurizer lev'cis versus time are given f or both cases in Figures 3.S.
3.9. This analysis shows that the system behaves
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similarly with and v,thout i pu=ps, although caintaining The EC pump flou does secc to help citigate void formation. of pres-pump flow case shous a shorter time to the start surizer refill than the natural circulation case (Figurc 3.9), although the ti=c dif ference does not seem to be very large. l Since the volume of the hot leg locp above the lovest point in the . candy cane portion is about 63 cubic feet, these steam fgreations . have the potential for blocking natural circulation in the het leg loops. As a result of these findings and since TRAP had not been prograt=cd to closely follev this specific condition, an additional TRAP case was run. It is based on the un=itigated'12.2 ft sLcam line break with RC pump trip, since this case represented the bound-s , ing event f or steam formatien. This case included a nore detailed' noding sche:c and conservative bubbic rise velocitics (5.0 f t/sec) to the upper regions of the hot legs such that the ef f ect of stcan formation on natural circulation in the loops could be observed.
^ The noding and flow path schc=e used in this codel is shoun in Figure 3.10. Tabic 3.2 provides a description of these nodes and flow paths. Figure 3.11 details the hot Icg - candy canc -
upper steam generator shroud noding and f1ou path model superimposed over a scaled figure of those regions. The flow path positions and sizes vere carefully chosen to allev for countercurrent stcan and liquid flow at the top of the candy cane. This codel is consistent i with that used f or the small breah LOCA analyses described in Sec-tion 6.2.4.2 of Ref. 5. The results of this analysis shoucd stcas forcation only in th: pressuri ct loop (ref er to Figure 3.12). These steam volumes are conservative since they include all of the steam that was calculatcJ ns being entrafued as bthbles in the If quid. The additional stena volumes calculated for this loop, compared with those shown in Figure 3.7, are due to the additional hailing and steam separation 90002248
t that occurs in the candy cane as the liquid flou rates are reduced by steam formation and aided by metal heating.,The lack of steam forma- ~ tion in the non-pressurizer loop 'E' is attributed to a correct ion in the metal heat transf er and metal heat capacitics calculated for ' the hot legs. The previous analysis crroneously included half of the steam generator tubes, haced on the calculations from the ECCS CRAFT model. Since the TRAP code already accounts for the tube actc) in its steam generator model, this represented an unnecessary concer-vatism and it was deleted from the model for this case. This case showed that the natural circulation flow was temporari) reduced. This flow reduced in the pressuriner loop to 45 to 100 lb/sec f rom 250 to 360 seconds (ref er to rigurc 3.13), uith flou steadily increasing af ter this time period. The flou in the non-pressuri:cr loop remained relatively unchanged at about 10091b/se (ref er to Figurc 3.14) . Core flou was maintained f rom 1000 to 2030 lb/see and no void formation occurr'ed (ref er to Figures 3.15 and 3.16). The steam bubbic was collapsed, natural circulation fully restored, and a grc'ater than 50 F subcooled margin a,chieved in the pressuriner loop (refer to Figure 3.16). Both steam generators and the pressurizer established 1cyc1 and the system pressure was
\ turned around from the HPI flow by 14 minutes into the transicnt (ref t to Figures 3.17 and 3.18).
- 3. Effect of Ecturn to Power There was no return to power exhibited by any of the EOL casce analyzed above. Previous analysis experience (ref. Midicud TSD' .
Section 15D) has shown that a nC pump trip will mitigate the consequences of an EOL return to power condition by reducing the cooldown of the primary system. The reduced cooldetm substan-Lially increases the suberitical margin which, in turn, reducco or clininates return to power. D. Conclunionn and Su=nnry A general assessment of Chapter 15 non-LOCA events identified three areas that varranted further investigation for impact of a RC pump trip on ESPAS low RC pressure signal.
- 1. It was found that a pump Leip does not significantly shorten the time to filling of the pressurizer and approximately the same time interval for operator action exists.
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- 2. Tor the maxi;num overcooling case analyzed, the RC pump trip increased the amount of void f'ormation in the hot Icg ' candy canc' of the pressurizer loop; however, natural circulat' ion was not completely blocked. The steam bubble was collapsed and full natura) circulation was restored. Core cooling was naintained throughout the t'ransient and no void formation occurred in the core.
- 3. The suberitica] return-to-power condition is alleviated by the RC l pump trip case due to the reduced overcooling cffcct. )
i Eased upon the above assessrient 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 signa], for all 177 FA louered loop plants. .Although there were no specific analyses perf orced for TECO, the conclusions drawn f ro:a the analyses f or the lowered loop plants are applicabic. l 90002250 l l
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!! ODE liffMitETI DESCRIPT70!l Reactor Yessel, Lower Plenum 2
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4,10 Primary, Steam Cencrator Tube Region
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Pressurizer 15 16,24 St eam Cencrator Dosmcomer 17,25 Steam Gencrr *r Lower Plenum Secondary, Ltcan Generator Tube Region 18-20,26-28 21,29 Stccm Riscro Main Stcan Piping 22,30 23 Turbinc Containment 31 : O M11:ITRAP2 PATil DESCRIPT10:1 DESCRIPTIO: PATil IRIMBER # Core 1 l Core Lypass 2 Upper Plenum, Reactor Vessel 3 4,11 - s Hot Leg Piping Ilot Leg Piping and Upper S. G. Shroud 5,12 6,7,13,14 Pricary, Steam Gencrctor RC Pumps 8,15
- Cold leg Piping 9,16 Downtoeler, Reactor Vessel ,
10 Pressurizer Surge Line 17 18,19,26,27 Steam Generator Do.mcomer Secondary, Stcam Generator 20,21,28,29 Aspirator 22,30 Stcan Riser, Stcan Cencrator 23,31 Main Steam Piping 24,32 Turbine Piping 25,33 34,35 Break (or Leak) Path IFI 36,37 AF1.' 38,39,43,44 Main Pced Pumps 40,41
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1111 ITRAP2 'l:0DP. 'DP.SCRIPTIO:1 DP.SCRIPTION 1:0DE !?Ul!BER Reactor Vensc1, Louc'r Plenum 1 - Reactor Vessel, Core 2 Reactor Vessel, Upper Plenum 3 4,30 llot Leg Piping (including ' Candy Canc') 32,33 ' Candy Canc' and Upper S. C. Shroud 5-7,11-13 Primary, Steam Generator Tube Region S,14 Cold Leg Piping
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}!ain Steam Piping 22,30' 23 Turbine .
31 Containment a l!I??ITRAP2 PATH DESCRIPTIO:! , DESCRIPTIOI? PATil !!LTBER 1 Core 2, Core Dypass 3 Upper Plenum, Reactor Vencel 4,11 llot Leg Piping 5,12 Upper Steam Generator Shroud 45,'46,47,48 Top of !!ot Leg ' Candy Cane' 6,7,13,14 Primary I! cat Trancfcr Region, S. G. 0,15 RC Pumps 9,16 Cold Leg Piping 10 Downcomer, Reactor Vecsci 17 Pressurizer Surge tine 10,19,26,27 Steau Generator Downcec:cr and Plenum 20,21,28,29 Secondary llcat Transfer Region, S. G. 22,30 Aspirator 23,31 Steam Ricer, Steam Generator 24,32 liain Steam Pibing 25,33 Turbine Piping 34,35 Breah (or Leak) Path 36,37 !!PI 3S,39,43,44 AFU 40,41 liain,Pecd Pumps - l 42 tPl 90002252 l Tabic 3.2
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