ML19350A234
| ML19350A234 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 01/15/1981 |
| From: | Pratt W BROOKHAVEN NATIONAL LABORATORY |
| To: | |
| Shared Package | |
| ML19350A226 | List: |
| References | |
| NUDOCS 8103130177 | |
| Download: ML19350A234 (150) | |
Text
{{#Wiki_filter:. . e 9 O BROOKHAVEN NATIONAL LABOR ATORY MEMORANDUM oArc: January 15, 1991 To: R. A. Bari rnoM W. T. Pratt S'JBJ ECT ; Some Very Preliminary Results of a Short-Tem Analysis (3 week study) of Hydrogen Combustion during Degraded Core Accidents in the Sequoyah Nuclear Plant in the Presence of Glow Plugs. INTRODUCTION AND SUM!%RY At the request of the NRR Containment Systems Branch (through the Peactor Systems Branch) in evaluation has been perfomed on the consequences of H2 burning during a wide range of degraded core age dents in a PWR ice condenser pl ant. Use is made of the MARCH computer codell to predict the contairrnent response. A major aim of our analysis was to assess the potential benefits (in tenns of contairment loadings) that might result from the installation of ignition sources (alow plugs) in an ice condenser plant to ensure H2 burning , at low concentrati n levels. In connection with our analysis, we were specif-ically reauestedl2 to assume that the installation of glow plugs would lead to the following combustion behavior: A. Hydrogen combustion would occur at either of two concentrations, namely, from 10% to completion and from 8% to 4% (both with oxygen , concentration > 6.5%) . In addition, we were also requested (2) to restrict our analysis to 75% Zr-steam reaction and assess the influence of the following input assumptions:
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B. Burn duration. C. Flane propagation between cells. D. Hg source tem. Comparison is made with a studyI3) conducted at TVA related to the in-stallation of glow plugs in the Sequoyah Nuclear Plant. Sequoyah is a four-loop PWR with an ice condenser containmer.t. The following conclusions of the TVA study are pertinent to the present work:
- 1. TVA was not able to identify any accident scenario that became worse due to the operation of the igniters (p. 9-2, Volune 2).
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, , R. A. Bari January 15, 1981
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- 2. Al though the rate of H2 release predicted for various accidents is very sequence-dependent, TVA considered that the ignition system should be effective for a wide range of accidents and associated re-lease rates (p.1-4, Vol me 2).
Implicit in the first of the above conclusien, is the assmption that the H2 will eventually burn (due to the presence of random ignition sources) and that it is obviously better to ignite it at low concentrations rather than al-lowing H2 to build-up to higher concentrations, in this context we were also unable to identify an accident scenario that became worse due to H2 ignition at low concentrations as opposed to ignition at higher concentrations. We are, however, unable to support the second of the above conclusions. The TVA analysis consisted of a series of scoping studies based on only one accident seouence, namely, an 520. The MARCH code was used to provide the steam and H2 release rates from tha primary system. The release rates were then used as input to the CLASIX(4) computer code (dev' loped by Offshore Power Systems) to predict the containment response. TVA found from their CLASIX analysis that H2 burning at low concentrations (those given in Table 1) could be acco'modated by the Sequoyah contaiment assuming the 5 D 2 steam and H2 release rates. The basic question is: Are the S2 D release rates typical of a wide range of degraded core accidents, hence confiming the effectiveness of the ignition system for a wide range of potential accidents? From our analysis of a wider range of accidents, we are unable to con-fim the typicality of the S D2 release rates. In fact, the TVA S 2D release rates represent a very specific accident sequence in which no passive ECC (as well as active) water was injected into the primary systs. This was incon-sistent with the fact that the primary system pressure fell below the set point necessary for UHI injection. This is an input option to the MARCH code dis-cussed more fully in the following section. The release rates used by TVA therefore represent the minime amount of water that can be released frm the primary system before core uncovery and the start of H2 production. The majority of accidents considered at BNL involved far greater steam re-lease than that considered by TVA. Minimizing the steam release maximizes the cuantity of ice available to mitigate the consequences of any H2 burns in the lower compartment. The stesn partial pressures in the lower compartment will also be minimized, which in turn makes it easier for the H2 tn attain low burning concentration. A key element of the TVA analysis requires burning of the Hp as it is released in the lower compartment. To achieve this,10w steam partial pressures are necessary together with a fresh supply of 02 fra the upper compartment. High steam partial pressures in the lower compartment can inert the atmosphere resulting in the H2 burning downstream of the ice in the upper compartment. Also, any interruption of the return air supply from the upper to the lower compartment muld prevent H2 combustion in the lower compartmet due to 02 starvation. It is these basic differences between our analysis and the TVA study that lead us to the conclusion that the present TVA strategy for burning H2 at low concentrations may not be effective for a wide range of degraded core accidents. In the following section we briefly describe b the BNL analysis. _ _.,. ._
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R. A. Bari Janumry 15, 1981 BNL t%RCH Analysis As a starting point to our analysis we obtained from BCL a MARCH input deck (5) for an 5 2D sequence in Sequoyah. This input deck was run at BNL and the output is presented in Figures 1-10. In addition to the specific recuests(2 7 noted in the previous section, we also selected a ntsnber of other input parameters (Table 1) that could significantly impact the accident pro-gression and its consequences. It was requestedL28 that we analyze a wider range of accident secuences and Table 2 summarizes the accidents considered. With seven accident sequences under consideration and six critical input as-sumptions, a full sensitivity study was clearly unrealistic in the time frame available. Representative values were therefore selected for the six input variables (Table 3) and used to generate a base case for each of the accident sequences. For selected accident sequences we then varied some (but not all) input parameters. Table 4 summarizes the cases run at BNL and gives some in-dication of the ice remaining at the start of significant H2 production. De-tailed output for the cases is presented in Figures 1-140. Results beyond 75% Zr-steam reaction are included for infonnation purposes only and are not used in this study. Note that in Case 1, H2 was assumed to burn from di down to 0%, and that for all other cases the H2 burn characteristics of Table 1 were used. The major differences between our assessment and the TVA study are related to the quantity of ice remaining during H2 generation and the mole fraction , of steam in the lower compartment. An inspection of Table 4 shows that there are several accident scenarios in which the ice is completely melted before H2 generation. A comparison of the detailed output (Figures 1-140) for the various cases also shows significantly lower steam mole fractions in the lower compartment of the S2 D sequence when compared with the other accidents. This is illustrated most dranatically if one compares the steam mole fraction in the lower compartment (Voltane 1) for the BCL 2S 0 case (Figure 3) with the results for a TLMBS case (Figures 123 or 133). The lower steam mole fraction in the S2 D case allows similar rates of H2 generation to reach a flammable concen-than for tration those cases much with earlier (andsteam higher therefore moleburn smallerFor fractions. quantities of Hg)her a case with hig steam mole fractions when the H2 finally does reach a flansnable concentration, the total quantity of H2 present is much larger, which result in a significantly more energetic burn. High steam mole fractions can also completely suppress burning in the lower compartment leaving the H2 to accianulate and burn in the upper compartment. It is for the above reasons that we predict higher pressurization of the containment building for certain cases (as seen in the figures) when burning at low concentrations than was calculated by TVA. Consequently, we are unable to confinn that, by ensuring H2 burning (by use of glow plugs) at low concentra-tions in an ice condenser plant, contairinent loadings will be acceptable for a cide range of potential degraded core accidents. When communicating (6) the above results to NRC, the following two ques-tions were raised regaring the BNL analysis:
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R. A. Bari January 15, 1981 r
- 1. UHI in MARCH is modeled as water addition to the bottom of the core when in f act the water is injected to the top of the core. How does this impact the predicted H2 generation?
- 2. If ice remains in the chest, does MARCH neglect heat transfer to the spray droplets in the upper compartment?
With regard to the first Question it should first be noted that the di-rection of UHI injection is only of importance to the 5 D 2 seguence. For all other accidents *, the UHI occurs prior to core uncovery and all subsequent ECC (both passive or active) is injected to the bottom of the core as modeled in MARCH. However, if we consider the 52D sequence, the BCL case (Case 1) avoids the problem by preventing UHI injection (although the primary system pressure falls below the set point necessary for injection) after the core reaches its mel t temperature. At BNL we allow UH1 depending on primary system pressure, not core temperature. Supplying water from below during core uncovery (MARCH model) maximizes H2 generation rates. However, flooding from above (actual UHI) will produce steam in the upper region of the core and hence produce. H2 at a greater rate than if we assume no UHl. We consider that Case 1 (minimtri H2 generation rates) and Case 2 (maximian H2 generation rates) bracket possible H2 ge:.aration rates for the 5 D2 sequence. We again emphasize that the direction of UH1 is only a problem for the S 02 sequence with an equivalent break area of 2 inches diameter. All other cases were modeled correctly. For example, an 51 0 sequence with a 3 inch diameter break involves UH1 prior to core un-covery and accisnulator injection at core uncovery. With regard to the second Question, MARCH does indeed neglect heat trans-fer to the spray droplets in the upper compartment if (and only if) ice remains in the chest. H2 burns in the upper compartment (if ice remains) may there. fore be conservative because the hept) sink associated with the water droplets is ignored. At a recent TA meetingt7 we presented the effect on H2 burning of spray operation. We sumarize our presentation below to give an indication of the effect of considering heat transfer to the water droplets:
- 1) Adiabatic H2 burn, ap = 64 psi,
- 2) Similar burn in presence of spray, tp = 32 psi.
However, the MARCH results may not be conservative in other regards. MARCH instantaneously equilibrates the pressures between two cells so that th2 pressures presented (Figures 1-140) during H2 burns do not represent an l adiabatic burn in an individual compartment. The pressure pulse is shared ' ovenly over both the upper and lower compartments. Again, we emphasize that this question applies only to those cases in which ice remains at the point of H2 generation. An inspection of Table 4 will indicate those cases in I which H2 burning may occur in the presence of ice.
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*With the exception of the TMLB' sequence. In this case, UHI and Accumulator j injection occurs after head failure.
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R. A. Eari January 15, 1981 We must emphasize that this is a very preliminary study carried out in only 3 weeks. 'we were not able to investigate the effect of burn duration or the H2 source tem. We consider that MARCH predicts a H2-steam release mix-ture that is weak in tems of H2 concentration. This is because as the H2 is generated in the core, it is mixed with the entire quantity of steam in the primary systen. For a four-loop plant with a single break in one locp, one would expect the H2 to mix (apart from diffusion) with steam only in a direct route fro 9 the core exit to the break point. If we consider mixing only be-tween the core and break (neglecting the steam content of the other 3 ioops), it is possible that the H2 Concentration released to the Contaiment (as pre-dicted by HARCH) could be increased by a factor of 2.5. The role of secuence-dependent diffusion of hydrogen in the primary system requires further inves-tigation. Finally, we 'ere also unable to examine the effect of the air return system (except comAtt. fa il ure - TNLB S, TMLB ' , and AB) . If combustion is to be sustained in the lower compartment, a fresh supply of 02 f rcm the upper cornpartment is essential . Any interruption in the air return will suppress burning in the lower compartment leaving the H2 to accmulate and burn in the upper compartment. REFERENCES
- 1. R. O. Wooton and H. I. Avci, "*RCM (@ltdown Accident Response Charac-teristics) Code Description and User's snual," NUREG/CR-1711, BMI-2064, October 1980.
- 2. Private Communication, R. A. Bari (BNL) and C. Tinkler (NRC) .
- 3. "Sequoyah Nuclear Plant - Core Degradation Program - Hydrogen Study Vol-urnes 1 and 2," TVA, September 1980.
- 4. A brief description of the CLASIX code is provided in Reference 3.
- 5. In this short-tem study, we were unable to critically review this input deck. It is our understanding that this deck also provided the basis for the TVA analysis and, perhaps, related studies at Sandia National Labora-tory. The MARCH code itself is undergoing review at BNL as part of our TA progre. Thus, our many reservations, which were connunicated to NRC, ap-ply here as well . In addition, in this short-term study, R. D. Gasser made a very preliminary independent assessnent of the ice condenser heat trans-fer performance for a few accident seouences and found that the results were co9sistent with MARCH code predictions.
- 6. Telephene Conversation: W. T. Pratt (BNL) and C. Tinkler (NRC); W. Butler, J. Meyer and J. Long of NRC also participating, on December 31, 1980.
- 7. "TA Role in Resolution of Issues Important to the Z/IP Mitigation Feature Progra," Meeting held at NRC on October 28, 1980.
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R. A. Bari January 13, 1981
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TABLE 1
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INPUT PARAMETERS h2 BURN CHARACTERISTICS e BUD: CONCENTRATIONS: 10'e0% 8% ~ 4% e BURN OURATION e FLAME PROPAGATI0t! BETWEEN CELLS PRIMARY SYSTEM K) DEL e ECC OPERATION (PASSIVE AND ACTIVE) AFTER CORE REACHES MELT TEMPERATURE e BREAK FLOW MODEL: e FLOW FROM STEAM SPACE e FLOW FROM WATER REGION l l
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R. A. Bari 7 January 15, 1981 TABLE 2 ACCIDENT SE0VENCES CONSIDERED SEQUENCE C OMMENTS . 5D2 SMALL BREAK LOCA (2 INCH DIA EQUIV. BREAK) WITH FAILURE OF ECC SYSTEMS. . 5D1 SMALL BREAK LOCA (5 INCH DIA. EOUIV. BREAK) WITH FAILURE OF ECC SYSTEMS. SH2 SMALL BPEAK LOCA (2 INCH DIA. EQUIV. BREAK) WITH FAILURE OF ECC !W RECIRCULA110L. 5H1 SMALL BREAK LOCA (5 INCH DIA. EQUIV. BREAK) WITH FAILURE OF ECC IN RECIRCULATION. AB LARGE BREAK LOCA WITH FAILURE OF ELECTRICAL POWER TO ESFs. TMLB' EXTENDED LOSS OF ALL AC POWER AND FAILURE OF THE AUXILIARY FEEDWATER. TMLBS EXTENDED LOSS OF ALL AC POWER AND FAILURE OF THE AUXILIARY FEEDWATER WITH INDUCED-LOCA THROUGH FAILURE OF THE REACTOR COOLANT PUMP SEALS. l
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. . R. A. Bari January 15, 1981 P TABLE 3 INPUT PARAMETERS FOR BASE CASES H2 BURN CHARACTERISTICS e H2 BURN FROM 8% to 4% CONCENTRATION e 6 SECOND BURN DURATION e NO BURN PROPAGATION BETWEEN VOLUMES e NO ADDITIONAL H2 SOURCE TERM PRIMARY SYSTEM MODEL e INJECTION OF ECC AFTER CORE REACHES MELT TEMP. e STEAM BREAK LOCATION l
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R. A. Bari January 15, 1981
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TABLE 4 CASES CONSIDERED ICE LEFT* START CASE No. COMMENTS H2 GENERATION (LB) 1 52D BCL DECK 1.8x106 2 52D BASE CASE O 3 5 2D BREAK FROM WATER SPACE. POWER RESTORED AT 89 MIN. 1.8x106 4 52D Hp BURN FROM 10% to 0%. BREAK FROM WATER SPACE. POWER RESTORED AT 89 MIN. 1.8x106 5 SID BASE CASE O 6 SID BREAK FROM WATER SPACE 1x106 7 52H BASE CASE O 8 S2H BREAK FROM WATER SPACE O 9 51H BASE CASE 0 , 10 S1H BREAK FROM WATER SPACE 8x105 11 AB BASE CASE 6x105 12 TMLB BASE CASE 1.4x106 13 TMLBS BASE CASE O 14 TMLBS POWER RESTORED AT 450 MIN. i
- INITIAL ICE INVENTORY 2.45x106 LB.
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, R. A. Bari January 15, 1981 r SE0VOYAH MARCH ANALYSIS CASE 1 - FIGURES 1-10 CASE 2 - FIGURES 11-20 CASE 3 - FIGURES 21-30 CASE 4 - FIGURES 31-40 CASE 5 - FIGURES 41-50 CASE 6 - FIGURES 51-60 CASE 7 - FIGURES 61-70 CASE 8 - FIGURES 71-80 CASE 9 - FIGURES 81-90 CASE 10 - FIGURES 91-100 CASE 11 - FIGURES 101-110 CASE 12 - FIGURES 111-120 CASE 13 - FIGURES 121-130 CASE 14 - FIGURES 131-140 THE FOLLOWING UNITS ARE USED IN THE OUTPUT PRESSURE - PSIA ! 1 TEMPERATURE *F 1 VOLUME NO.1 IS THE LOWER COMPARTMENT. VOLUME NO. 2 IS THE UPFER COMPARTMENT. l l
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l l l BUARD NOTIFICATIOT1 (McGuire 1-2) Atomic Safety and Licensing Board Panel Ato,ic Safety and Licensing Appeal Board Panel ' Docketing and Service Section Dr. John M. darry Diane B. Cohn, Esq. Dr. Richard F. Cole Robert M. Lazo, Esq. J. Michael McGarry, III, Esq. William Larry Porter, Esq. Jesse L. Riley Mr. David E. Smith Dr. Emmeth A. Luebke ACRS Menbers Mr. flyer Bender Dr. Max W. Carbon Mr. Jesse C. Ebersole Mr. Harold Etherington Dr. William Kerr Dr. Stephen Lawroski Dr. Harold U. Lewis
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