ML19257B591
| ML19257B591 | |
| Person / Time | |
|---|---|
| Site: | Crane, Davis Besse  |
| Issue date: | 09/08/1978 |
| From: | Luken R BABCOCK & WILCOX CO. |
| To: | Domeck C TOLEDO EDISON CO. |
| References | |
| TASK-TF, TASK-TMR BWT-1698, NUDOCS 8001170687 | |
| Download: ML19257B591 (9) | |
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Babcock &Wilcox TELEC0PY power ceneratien cicuo P.O. Box 1260. L nchburg, Va. 24505 September 8, 1978 BWT-1698 File:
T1.2/123 m
i Mr. C. R. Domeck -
Nuclear Proj ectEngineer
- Toledo Edison Company 300 Madison Avenue Toledo, OH 43652
Subject:
Toledo Edison Company PRESSURIZER PERFORMANCE DURING REACTOR TRIPS Davis-Besse Unit 1 B5W, REFERENCE NSS-14
Dear Mr. Domeck:
Attached per your request is a report describing the dynamic performance of the pressurizer during reactor trips at Davis-Besse Unit 1.
Very truly yours,
- c/
RCL/hj R. C. Luken Attachment Project Manager cc:
J. D.'Lenardson w/a For A. H. Lazar J. C. Lewis Senior Proj ect Manager D. J. DeLacroix M. Malcom/4 w/a E. C. Novak/1 w/a bec:
(with attachment)
Ivan Green W.H. Spangler
.R. W. Winks A. H. La:ar Records Center F. R. Faist R. C. Luken 1916 158
~
The qqec::x & w; com cemeany i Estamiisnee tes7
~
-8001170 @ 7 [
Babcock &WHcox ATTACHMENT TO BWT-1698 DYNAMIC PERFORMANCE OF THE PRESSURI2ER DURING REACTOR TRIPS AT DAVIS-BESSE 1 I.
INTRODUCTION
_During the ?' actor trip transient at Davis-Besse 1 on November 129, 1977, tue' pressurizer level indicator went off scale.
This incident and suosequent reactor trip transients have rai' sed a
- concern that the pressurizer will empty completely during a reactor trip from full power with simultaneous loss of station power.
The reactor trip transients to date have' occurred at partial power levels with either all RC pumps running or all four RC Pumps tripped.
The purpose of this report is to present the results of calcula-tions indicating the minimum pressurizer level reached during the November 29, 1977 transient.
Addi'tionally, this report will present a calculational technique for predicting minimum pressuri:er levels following a reactor trip transient and account for either tripped or running RC pumps.
Actual reactor trip transient test data from Davis-Besse 1 has been used to support the calculational technique.
II.
SUMMARY
The minimum pressurizer level that occurred on the November 29, 1977 reactor trip transient with loss of all four RC pumps is calculated to have been 32 inches below the low level tap.
A fluid reserve' equivalent to 43 inches of level existed in the pressuri:er before makeup flow increased the volume of reactor coolant.
Minimum main steam pressures were 610 and 730 psig for the two steam generators.
A calculational technique has been developed for predicting changes in pressurizer level during reactor trips which agrees very well with observed reactor trip transients at Davis-Besse 1.
The method has been used to predict the final minimum pressuri:er level for two possible transients (both from 100% power):
a reactor trip with simultaneous trip of all RC pumps, and a reactor trip with all RC pumps operating.
For the first transient above, the pressuri:er level will decrease only 100 inches, provided that main steam pressure will not decrease
_ If main steam pressure decreases to 700 psig the below 950 psig.
- pressuriser would become empty.
For the reactor trip transient with all RC pumps running, the pressuri:er level will decrease below the lower level tap if the main steam pressure drcps to 950 psig.
Since a minimum main steam pressure of 980 psig is anticipated on future reactor trip transients, the predicted minimum pressurizer level will be a few inches above 1~916 159
Babcock &Wilcox Page 2 the zero' indication and nearly 80 inches ab~ove the bottom of the pressurizer.
If steam pressure decreases to 840 psig on this transient, the pressuri:er would become empty.
Two graphs have been developed (Figures 2 and -3) which relate minimumT@lhtransients.
to minimum pressuri:er level for the two different reactor t These graphs can be used to predict pressurizer performance during any large transients at Davis-Besse 1.
III.
ANALYSIS OF NOVEMBER 29, 1977 TRANSIENTS The following reactor trip transients have been analyzed to determine a realistic primary system cooldown profile for analyzing and predicting pressuri er performance:
TABLE 1 Initial RC Pumps Date Power Level Running Comments 2/24/78 74 yes Trip initiated by the failure of a flowmeter AP transmitter.
4/2/78 75 yes Turbine trip test with unsuccess-ful runback of reactor power.
8/2/78 40 yes Reactor trip due to divergent oscillations while in tracking mode.
11/29/77 40 no Reactor trip and station black-out causing loss of RC pumps.
The response of the ICS and plant was adequately similar for these four transients to be able to characterize the relationship between T
and RC pressure following the trip of the reactor.
Figure 1 dfl$1aysthisrelationship.
This curve was utilized in predicting minimum conditions in the reactor coolant system for calculating minimum values of level in the pressuri:er.
The objective of our analysis was to compare the predicted change in pressuri:er level with measured changes in level and verify that the mathematical model was sufficiently accurate to predict pressur-i:er level changes that dropped below the lower level tap.
The mathematical model used to represent the contraction of the RC system during these transients utili:es the following equation:
Total mass of fluid in the RC system = M, =
Equivalent Volume of Hot Fluid Specific Volume of Hot Flula 1916 160 Eauivalent Volume of Cold Fluid
+
Specific Volume or Cola Flula Cont'd
Babcock &MAlcox Page 3
+
Liouid Volume of the Pressurizer Specific Volume of Pressurizer' Fluid The equivalent volume. of hot fluid consists of upper half of each steam generator, one half of the reactor vessel and all the hot leg piping.
Similarly the equivalent volume of cold fluids consists of the other half of both steam generators, the lower half of the reactor vessel, and all the cold leg piping.
the sum of the hot and cold fluid volumes is equivalent to the total reactor coolant system volume excluding the pressurizer.
The calculational technique requires the determination of the initial and final pressures and t-emperatures of the reactor coolant system, an evaluation of the specific volumes for those conditions plus saturated conditions within the pressurizer, and the difference in pressurizer
. volume due to the calculated contraction of the constant mass in the RC system.
Table 2 below, presents a comparison of calculated pressurizer level changes with measured level changes at selected time intervals in the four reactor trip transients.
TABLE 2 Comparison of Measured and Calculated Chncges in Pressurizer Levels During Reactor Trip Transients at Davis-Besse 1 Measurel Calculated Date of a Level A Level Time Elapsed Rx Trip
- inches
- inches
- seconds 191 184 60 2/24/78 4/2/48 162 167 45 8/2/78 196 206 90 11/29/77 139 132 170 11/29/77 184 181 240 The test data from the November. 29, 1977.. reactor trip was examined to find the minimum RC pressure and temperatures that probably occurred while the pressurizer level was off scale and the values were determined to be the following:
At clock time 22:48:50, minimum RC pressure was 1625 psig
(+50 psig due to oscillations).
The corresponding value of hot leg temperature was 562.5F whereas the cold leg temperature was off-scale (below 520F) and was calculated to Ebe 508.5F. T
-for Loop 2 was determined to.be 535.5F and the Loop 1 and 2 sEXIm
- pressures indicated 610 and 760 psig.respectively.
These values were used to specify the final specific volumes required
} h b 'l 6 }
Babcock &VMcox Page 4 in the equation and revealed that the change in pressuri:er level was 224 inches.
Since the initial pressurizer level at instant of reactor trip was 192 inches, then the final pressurizer level was 32 inches below the lower level tap.
There was another 43 inches of water re-maining in the pressurizer at this time.
IV. PREDICTED PRESSURIZER PERFORMANCE AT 100% FULL POWER The extent of reactor coolant volume contraction following a reactor trip is primarily governed by the wetted surface area of the tube bundle and by the steam pressure maintained within both once Through Steam Generators.
It is also affected by the flowrate of reactor coolant through both steam generators, that is, all pumps running.versus all pumps tripped.
. Figure 2 was developed for the situation of a reactor trip from full
- power plus loss of all RC pumps.
The minimum T will be controlled bythesteampressureineachsteamgenerator.a5fselectingdecreasing values of T*YIvels were predicted.and corresponding values of steam pressure, minimu pressurizer
,The intent is to be able to predict the total change in presserizer level that will occur as T changes from a normal 582F to a known or anticipated minimum templfature.
Figure 2 shows that T*Yfansienthas to decrease to 534Fi o empty the pressurizer t
for this reactor trip (no RC pumps running)~ and that this require.
(a minimum stream pressure in each steam generator to be equal to 665-psig.
'By controlling steam pressure _ab9ve 800 psig during this transient, the pressurizer level can remain above the lower level tap.
The blowdown con all the main steam safety relief valves has been adjusted. by Toledo Edison Company at the Davis-Besse 1 plant._early in 1978.
The values of minimum steam pressure after a recent reactor trip transient indicate hat the performance of the steam pressure relief system is greatly in-proved ever that observed during earlier reactor trip transients.
If the initial power level had been 100% on the November 29, 1977 transient then the calculated minimum pressurizer level would have been 58 inches below the lower level tap.
Since the initial power level was only 40%,
the amount of contraction in the RC system was only -32 inches.
Both of these calculated values are less than predicted (by application of Figure 2), and demonstrate the conservatism of the method.
The dependence of the contraction of reactor coolant on initial power level is exhibited -
in Table 3 below:
Table 3 Ill b-RC Contractions for Reactor Trips (With Station Blackout) From 40% and 100% Power Levels Power Level: -1 40 100 Initial RC Pressure - psia 2138 2138 Initial T ot -F 592 605.5 h
Babcock &Wilcox Page 5 Initial Level - Inches 192 192 3
Initial RC Volume - Ft 11,264 11,264 Initial RC Mass - Ibs.
496,969 493,437 Final RC Pressure - psia 1640 1640 Final T ot - F 562.5 562.5 h
508.5 508.5, Final REold - F Final T aass - ths 496,969-493,437 Final Pzr. Volume - Ft 122 37 Final P:r. Level - Inches
-32
-58
-Figure.3 was similarly developed for a~ regular reactor trip from full
~ power (all pumps running).
This transient is more severe than the previous situation in that the forced convection of reactor coolant quickly removes all stored heat in the primary system.
Below a T value of 550F, T cold leg temperature, and saturation temperafufe
- ava, in the steam generators are almost all equal.
Thus, much greater care s umst.be exercised in maintaining steam pressure to avoid emptying the
..pressuri:er.
An expected main stean pressure of 980 psig should occur, as has been demonstrated on the August 2, 1978 reactor trip, and the pressuri:er level will remain above the lower level tap.
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