ML19312C747

Summary of 670629 Meeting W/Util & B&W in Bethesda,Md Re LOCA Analysis for Spectrum of Break Sizes to Be Presented at ACRS Jul 1967 Meeting.Summary Table of Results & Addl Info on Cold Leg Breaks Encl

ML19312C747
Person / Time
Site:	Oconee
Issue date:	07/10/1967
From:	Grimes B US ATOMIC ENERGY COMMISSION (AEC)
To:	Long C US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7912190958
Download: ML19312C747 (5)

Text

{{#Wiki_filter:_______ _____. O.-.E".. o-UNITED STATES GOVERNMENT Memorandum To Files DATE: July 10,1967 THRU: C. Long, Chief, RPB #3, DRL FROM B. Grimes, Reactor Project Branch No. 3 Division of Reactor Licensing

SUBJECT:

Meeting with Duke Representatives to Discuss " Spectrum of Breaks" Analysis Dockets 50-26f/270/287 On June 29, 1967, R. Wascher and D. Montgomery, of B&W, and Ed Fiss, of Duke Power, visited the Bethesda offices to discuss the loss of coolant analysis for the spectrum of break sizes which is to be presented orally to the ACRS at the July meeting. C. Long and B. Grimes were present from the staff. A summary table of the results presented and additional infor-mation on cold leg breaks are attached. Some information was previously available on hot leg breaks but only qualitative information can be obtained from the figures presented (Fig. 14-41, 42). The top of the core is uncovered at a mass release of 310,000 lb and the bottom of the core at about 400,000 lb and the time to uncover the core can thus be estimated for the hot leg breaks from avail-able information. The following points came out of our discussion: (1) The analyses were performed assuming that the accumulators were initiated at 600 psi and discharged to the vessel as a function of the driving head available. One high pressure pump was assumed to operate after a 25 second delay. (2) The pressure transient was calculated without core 'ajection and the volume of injection water superimposed on the calculat-d inventory. (3) No heat release from the steam generators is assumed during blowdown (Westinghouse may assume heat is removed). (4) The steam-water separation model is different from Westinghouse's. Both companies use the FLASH code and use reference 10 of Section 14, PSAR for the steam separation model. Westinghouse, however, uses a single separation factor over the entire pressure range while B&W has incorporated a variable factor (as indicated by the experimental data). This area will require further investigation in the future. The result of the variable separation factor is to leave more water in the reactor vessel for smaller break sizes and to allow the pressure to remain high for a longer period of time. The effect is not signifi-f. cant in the large break sizes (3 ft2 and greater). O m Buy U.S. Savings Buds Regularly on the Payroll Savings Plan 79121907SP g

.a. o _By telephone communication on July 3, 1967, R. Wascher provided backup references for the steam separation factor as listed below and stated that Phillips was also incorporating a variable steam-separation factor in the LOFT calculational model (FLASH modified . to an IBM computer) to better predict the - experimental results.

References:

Phillips' monthly reports (1) August, 1966, (Ny-251-66A), p III-6 (2) October, 1966, p III-13 (3) January, 1967, p III-13 (5) on the solution to the steam bubble problem, B&W stated that the check valve hinge was to be on the outside of the support shield at the recommendation of the check valve supplier. We stated that this was not as desirable as a hinge on the inside since the hinge would not be visually inspectable during refueling. Attachments cc: D. Muller R. Tedesco C. Long R. Ireland HM. Rosen R. DeYoung V. Moore J. Newell B. Grimes l \\ l l

a ~ TABLE I SPECTRIDI 0F COOLANT LINE BREAKS Minimum Positive Quiet Hot Hot Peak Moderator Spot /' . Spot Temp. (Full-1 Break Level Sizg Coolant (ft. above ' Uncovered Re-Covered Hot Spot Poser - - ( f,t3 I, pop Core Bottom) (Seconds)_ ~ ._S ec ond s ) - (*F) Seconds)- ( l '+ act -6.8 4.0 17.5 1950 2.1 S.- hot -5. 4 - 6.2 20.6 1700 3.5 cold ~7.5 5.0 22.3 1740 L j d.3 j .f e -{,965- .'_1. 6 3 hot -2.3 17.6 33,5 cold -5.6 13.4 32 1320 S! 1 hot +4.7 790 1.42 cold +4.0 790 1 0.4 hot +12.1 1.4 cold +6.9 730 0.05 cold +12.3 +eo u 1] Hot' spot at about +3 ft. ~ 2/ Scram assumed. ~ ON (T ^ f .i .I l i l O .,j.. As - gg

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