ML20140F770

Topical Rept Evaluation of Nedo 10859, Steam Vent Clearing Phenomena & Structural Response of BWR Torus. Portion of Rept Re Structural Response & Stress Analysis Unacceptable. Viewgraphs Encl

ML20140F770
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Site:	Quad Cities, 05000000
Issue date:	09/12/1974
From:	US ATOMIC ENERGY COMMISSION (AEC)
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References
FOIA-85-665 NUDOCS 8604010156
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Text

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~N TOPICAL REPORT EVALUXfION Report No.: NEDO 10859 (Non-proprietary)

Report

Title:

Steam Vent Clearing Phenomena and Stmetural Response of the BhR Torus Report Date: April 1973 and Errata and Addenda Sheet, May 21, 1973.

Originating Organization: General Electric Company Reviewed By: Operating Reactors Branch No. 2 SLBNARY OF TOPICAL REPORT i

The report presents an analytical model that mathematically describes the process of relief valve _ opening, the clearing of the water out of the vent, and the subsequent pres'sure oscillations in the wetwell and the toms stmetural response due to the expanding air expelled from the vent. A parametric variation is perfomed which demonstrates the effect of such parameters as vent submergence, valve opening time, mass flow rate through the valv6, and reactor pressure. In addition, analytical results are presented for the pressures generated in the suppression pool as a function of distance fr a the vent exit for single and multiple valve openings and for the resulting toms structure loads, deflections and stresses. The experimental data were derived from a series of nine tests perfomed on the Quad Cities Unit 2 plants.

l The results of a test program consisting of five single valve tests and four multiple valve tests perfomed in October 1972 on the Quad Cities Unit 2 plant are reported. The instmmentation employed to detemine the pressure response consisted of ten transducers in the toms at various distances from a vent exit, and one transducer on a vent pipe just above the water line.

The values for the highest pressure amplitude (characteristically the second peak in the oscillations) are compared with the analytical predictions.

Structural response instmmentation consisted of 7 displacement sensors and clevci strain gages, many of which failed during tests. The comparison of the data obtained from the tests with that obtained from the structural analytical model is of little significance based on the small amount of test data obtained from structural instrumentation.

SLEM\RY OF REGULATO tY EVALUATION The analytical predictions shown in Figure 4-13 and 4-15 envelope the measurements of the maxicum positive amplitudes of the pressurt oscillations with the exception of the maximun negative amplitudes which frequently exceed the theoretical values for the single valve tests. All the measurements indicated show a substantial degree of scatter. It is significant to note that the multiple valve tests show l a larger degree of scatter than the single valve tests. '

. The model generally represents a valid and sufficiently complete l method of generating a pressure loading prediction for relief valve j action; however, the analysis .results presented in the report still

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contain some unexplained anomalies. For example, a comparison between Figure 4-13 and Figure 4-15 indicates that at a distance of 5 ft.

from the vent exit, the theory incorrectly would predict a higher positive pressure amplitude for single valve opening than for multiple valve opening. Furthemore, the limiting behavior of pressure in Figure 4-15 as the distance from the vent nit, goes to zero which does not appear to be correct since limiting behavior should approach that of Figure 4-13. It is expected that the phenomenon of pressure wave .

addition is also subject to substantial randomness which might well  !

explain the scatter in Figure 4-25. Similarly, the starting con-ditions of each test would have to be reviewed to detemine uhether the initial conditions were identical. In view of the scatter in all the test results, it is our opinion that a detemination of adequacy

' of the model to detemine'a universally applicable forcing function would have to be supported by larger data base to include other i Bh M ! ark I plants.  ;

A suitable forcing function must also consider the projected number of valve openings over the life of the plant. Such a projection, necessary for detemining the fatigue life of the plant, should include some correlation for including the attenuation from adjacent valves. The projection should be based on a breakdown over the anticipated number of occurrences; e.g., turbine trip, MIS, test requirement, etc. The figure in Section 5.3.4 that depicts less than five relief valve openings a year is considered unrealistic.

The analytical model of the entire torus-ring header system that uses bar members to represent torus segments is inadequate for dynamic analysis of the structure. This method of analytical modeling is not considered appropriate for detemining stresses in such critical areas as the pipe penetrations.

Stresses due to dynamic effects in the vicinity of pipe penetrations could not be calculated because the analytical model was not designed to yield detailed results in all torus bays. Furthemore, measured strain data which were used for comparison with analytical results are not reliabic due to faulty instrumentation. On the basis of the above discussion, we find that the portion of the report conceming structural response and stress l analysis is unacceptable and should not be used as a reference in future I work relating to the Mark I structures.

REGUI.ATORY POSITION As emphasized above in our evaluation, the data base confiming the analytical ma for the forcing function is rather limited in view of the scatter that exists in the data. The verification of the model can therefore not be considered con-clusive fur application on other torus structure designs based on the Quad Cities tests alone. The model predicts certain anomalous results such as Figure which shows that the maximun colma pressure does not increase with reduced valve opening time. Such a result would also need experimental verification.

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The verification of the analytical model for the forcing function should be extended further by tests perfomed on other plants where the configuration and design of the relief valve vents and the torus are significantly different from the Quad Cities Unit 2 toms. Such testing would verify the model for variation in some of the parameters listed in Table 4-1. In addition, differences in the stmetural characteristics of the toms are expected to influence the pressure amplitudes that are measured in the suppression pool in view of the large deflections with which the torus shell responds to the pressure amplitudes. ,

Experimental stress analysis should be emphasi::ed for the investigation of stress and strain conditions in the critical area. Strain and deficction measurements had not provided reliable data for analysis because of instrumentation malfunction. Therefore a test program should be established that provides a better experimental data base for stress and strain at pertinent and critical areas of the torus. In addition, effects of cumulative damage and usage factor due to previous tests and operations should be given consideration in detemining the fatigue life of toms structures based on the steam vent charing phenomena associated with operation of primary system relief valves.

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