ML20039F398

Forwards Effect of Change in Flow Maldistribution Factor on DNB for B&W 205 Fuel Assembly Plants. Rept Shows Effect of New Flow Factor on DNBR

ML20039F398
Person / Time
Site:	05000561
Issue date:	02/06/1978
From:	Taylor J BABCOCK & WILCOX CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML111090060	List: ML19208A315 ML19208A325 ML19250B014 ML19250B445 ML19250B480 ML19250B482 ML19254C975 ML19254G119 ML19254G128 ML19255K396 ML19255K397 ML19257E274 ML19257F047 ML19257F050 ML19260B823 ML19260E912 ML19260E913 ML19260E914 ML19261C469 ML19262E467 ML19262F230 ML19263D836 ML19263F605 ML19263G068 ML19268C086 ML19268C087 ML19269F130 ML19271A085 ML19271A172 ML19273B051 ML19273D308 ML19274A409 ML19274E085 ML19275B428 ML19275B444 ML19275C327 ML19275C328 ML19275G904 ML19275G918 ML19275H308 ML19275H317 ML19275H339 ML19275H341 ML19275H375 ML19275H401 ML19275H405 ML19275H493 ML19275H655 ML19275H660 ML19276D594 ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8201120416
Download: ML20039F398 (13)

Text

{{#Wiki_filter:~ j l s Babcock &WilCOX eower ceneration croup P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 February 6, 1978 Mr. Steven A. Varga, Chief Light Water Reactors Branch #4 Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

1) B4W 1etter dated December 20, 1977, J. H. Taylor to S. A. Varga, "VMFT Experimental Results" l

Dear Mr. Varga:

The reference letter reported experimental results regarding the VMFT minimum flow maldistribution factor which affect the information presented in Topical Reports BAW-10025, BAW-10025P, BAW-10026, and BAW-10026P. In subsequent telephone conversations with W. Hodges, G. Kelly, and T. Cox, it was determined that the results of analyses must be submitted to show the effect of the new flow factor. The attached report, "The Effect of a Change in the Flow Ma1 distribution Factor on DNB for Babcock 6 Wilcox 205 Fuel Assembly Plants," dated January 30, 1978, has been prepared to show the effect of the new factor on DNBR. We trust that the information presented is adequate to permit issuance of the BSAR PDA without delay. Please advise promptly if you have any questions. Ver truly yours, YhmM/ N James H. Taylor' Manager, Licensing JHT:dsf Attachment cc: O. D. Parr (NRC) R. B. Borsum (B4W) 7603S0278 l 8211120416 810403 l PDR FOIA MADDEN 80-515 PDR L Tin fWfree ADicem h.

THE EFFECT OF A CHANGE IN THE FLOW MALDISTRIBUTION FACTOR ON DNB FOR BABC0CK & WILCOX 205 FUEL ASSEMBLY PLANTS INTRODUCTION Recent B&W submittals to the NRC (References 1 & 2) have reported that the minimum flow maldistribution factor, as experimentally obtained from our vessel model flow tests, should be reduced from 0.99 to 0.965. Reference 2 also explained that the overall effect of this change on the minimum DNBR calculations will be negligible when the thermal-hydraulic analysis is performed using a crossflow analysis (LYNX 1, 2, BAW-10129,10130) rather than a closed channel analysis (CHATA, TEMP, BAW-10110,10021) as was used for the BSAR-205. Subsequent discussions with the NRC have indicated that additional in formation, i.e., confirmation, is required to justify the minimal effect of the flow maldistribution factor on the minimum DNBR. Therefore, B&W has performed additional analys.es, as described in the following sections, which address the NRC concerns and conclusively shows that the flow maldistribution factor has an insignificant effect on the minimum DNBR of B&W 205 fuel assembly plants. DISCUSSION B&W has completed a study comparing CHATA/ TEMP and LYNX 1/ LYNX 2 computer code results in evaluating the reduction of 2% flow in the interior region of the core and a reduction of the minimum flow factor from 0.99 to 0.965 for the 3800 MWt plant. Consistent with design procedures cu'rrently used at B&W, a maximum design 112% power case defined in Chapter 4 of BSAR-205 was used as the basis for this study. The same design procedures, hot channel factors, and power peaking conditions associated with a maximum design conditio a were used in both the CHATA/ TEMP analysis and in the LYNX 1/ LYNX 2 analysis. ___----_o

o The most significant dif ference between tha closed channel and crossilow analysis methods is the inherent difference resulting from the treatment of coolant mixing. Any flow perturbation introduced at the inlet to the closed channel is maintained throughout the length of the channel, whereas the crossflow analysis results show that flow recovery occurs within a short distance of any local flow upset. ANALYSIS RESULTS Figure 1 illustrates the axial flow distribution in the hot bundle for a maximum design condition for the two methods of analysis. The closed channel analysis predicts a reduction in bundle flow of 3.1%, resulting from the reduction in maldistribution factor from 0.99 to 0.965, while the cross-flow analysis demonstrates an initial reduction of 2.5% flow which decreases to less than 0.5% difference by X/L = 0.3 and stabilizes at that value. Figure 2 illustrates the bundle enthalpy rise for the two methods of analysis. The cross-flow analysis shows a negligible enthalpy effect from the 0.965 minimum flow factor, consistent with the mass velocity distribution shown in rigure 1. Figures 3, 4, and 5 show subchannel parameters, including MDNBR (BAW-2). It can be seen from Figure 5 that the reduction in flow maldistribution factor from 0.99 to 0.965 has the effect of reducing the predicted MDNBR by 0.0d when the cic sed channel analysis is used and by 0.01 when the crossflow analysis is used. It is believed by B&W that the conservative MDNBR predictions using CHATA/ TEMP (.08 reduction in MDNBR compared to.01 for crossflow) are not realistic. This is shown by comparing the results from the crossflow codes to those obtained from the closed channel model. Although the closed channel analysis is very sensitive to the reduction of the minimum flow factor from 0.99 to 0.965, the crossflow analysis demonstrates that flow redistribution minimizes this ef fect. -

ANALYSIS WITH UPDATED CHF CORRELATION As per the NRC's request, an additional analysis was made using.the BXC-2 CHF correlation (an interim critical heat flux correlation) which is currently being used by B&W as a preliminary evaluation tool for use in analyzing HDNBR performance of Mark-C fueled cores. Experimental data to date (not complete and therefore, the results of this study are subject to change) support an MDNBR of approximately 1.15 as the critical heat flux ratio required in design at a 95/95 tolera' ace level. The basis for this analysis was the same as the closed channel versus crossflow comparison with one minor exception. The BXC-2 critical heat flux study included a design update which reduced the instrument guide tube sleeve OD from 0.480 to 0.465 inches to be consistent with the control rod OD. The results of this analysis, shown in Table 2, indicate that the reduction in maldistribution factor from 0.99 to 0.965 results in a negligible reduction in MDNBR. B&W has committed to use the reduced flow maldistribution factor in future analysis at the FSAR stage in all affected applications (Reference 2). CONCLUSIONS From the results of this study, it is concluded that FSAR analysis will show a negligible change in MDNBR resulting from the use of a 0.965 maldistribution factor and that all design criteria will be met. _ 3-

1 TABLE 1 l Closed Channel and Crossflow Comparative Results of Reducing the Minimum Interior Flow Factor from 0.99 to 0.965 j CHATA LYNX 1 1 Nbthod of Analysis TEMP LYNX 2 Base Case (112% Power) Maximum Design Maximum Design R x L Peaking 1.55 1.55 CHF Corre,lation B&W-2 B&W-2 Design Limit DNBR 1.30 1.30 MDNBR (FF = 0.99) 1.439 1.623 MDNBR (FF = 0.965) 1.364 1.613 A MDNBR (Reduction) 0.08 0.01 l

TABLE 2 MDNBR Predictions Using the Interim Mark-C Critical Heat Flux Correlation (BXC-2) for the 3800 MWt Maximum Design Case LYNX 1 Method LYNX 2 Base Case (112% Power) Maximum Design R x L Peaking 1.55 CHF Correlation BXC-2 Design Limit DNBR 1.15 MDNBR Predicted (FF = 0.99) 1.23 MDNBR Predicted (FF = 0.965) 1.22 A MDNBR (Reduction) 0.01 s I j

References:

1. Amendment 22 of the BSAR (January 16, 1978) 2. Letter, J. H. Taylor, B&W, to S. A. Varga, NRC, (December 20, 1977)

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NRCsonM 195 u.s. NUCLEAR 5:EcVLAToRY CoMMISSlo DOCKET NUMIED 0; * ~7'EP/C N NRC DISTRIBUTION Fon-PART 50 DOCKET MATERIAL TO. FROM: oATE oF ooCUMENT Babcock & Wilcox 2/6/78 Mr. Steven A. Varga Lynchburg, Va. n,7,,,ca,y o James H. Taylor 2/7/78 2TEETTEn ONoToRizEo PROP INPUT FORM NUMBEn oF COPIES RECEIVED CoRio4NAL EfJNCLASSIFIED OcoPr j ssweO oESCRIPTION ENCLoSU RE Rept. entitled, "The Effect of a Change in the Flow Ma1 distribution Factor on DNB for Babcock & Wilcox 205 Fuel Assembly Plants"... PLANT NAMZ : RJL 2/7/78 (1-P) (11-P) ./2rr Ake <1 (JAe rou s h/76 g, Exct h /APMo MMeMS q3FrTy FOR ACTION /INFORMATION ENVIRONMENTAL / ASSTOYFD AD! VA>Y4tt o ASSIGNED AD: V. MOORE (LTR) / BRANCH CHIEF: /Mk BRANCH CHIEF: ,_/' PROJECT MANAGER: [ max D DROJFcT MANAGER: LIC. ASST: 'A J f.Tc. ASSTr l J (4l/L Sed / M 8/86 B. HARLESS INTERNAL DISTRIBUTION / REG FILES 9VRTFMS SAFrTY PLANT SYSTEMS SITE SAIETY & / NRC PDR R_ MATTSON TFDESCO ENVIRCN ANALYSIS ICE SCHROEDER RENAROYA DENTON & MULLER OFT n T_ATNAR cRUTCHFIELD _GOSSICK C STAFF ENGINEERING IPPOLITO / 9ANAtten WNTOMT F. R09A ENVIRON TECH MTDC 90SNAW ERNST cace S TMhT TL OPERATTNG REACTORS BALLARD nnvn P AWT.T CWT STFrLO YOUNGBLOOD / 6,MAldM / FTMF5MUT PR03rCT MANAGEMENT REACTOR SAFETY SHAD SITr TECH SKOVHOLT / ROSS / BAER GAMMILL f2) P. COLLINS / HOUSTON /' NOVAK BUTLER ~ ROSZTOCZY GRIMES SITv ANALYSIS VELT2 CHECK VOLLMER MrLTINES / f// MDBG8f BUT dH MR AT & I J,_ COLLINS SALTZMAN RREGER Rt!T9FRG EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: vs? Y sn. TIC NSIC 7S0380278 _ REG V ( J. HANCHETT ) / 16 CYS SENT CATEGORY ,4 TO ACRS 1 {. m}}