ML20003E627
| ML20003E627 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 03/31/1981 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TAC-43514, TAC-43515, NUDOCS 8104070422 | |
| Download: ML20003E627 (10) | |
Text
{{#Wiki_filter:. 1 WISCONSIN Electnc pom cown 231 W. MICHICAN, P.o. BOX 2046. MILWAUKEE, WI 53201 March 31, 1981 Mr. Harold R. Denton, Director fi Office of Nuclear Reactor Regulation X @,N U. S. NUCLEAR REGULATORY COMMISSION g/,.. n p 3M .g ,];{gj ,h Washington, D. C. 20555 Attention: Mr. Robert A. Clark, Chief b c, M " Operating Reactors Branch #3 M II " " ',, c #. $ ! {-] u.s $$2" [.N/ Gentlemen: y d / I,'fip \\ \\ DOCKET N05. 50-266 AND 50-301 POSTULATED UNCONTROLLED BORON DILUTION AT COLD SHUTDOWN f0 INT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Our letter of December 23, 1980 provided results of our initial analyses concerning uncontrolled boron dilution, as requested by your letter of September 30, 1980. Subsequent to the December 23, 1980 submittal, telephone conversations on the subject were held with members of your Staff. The following is provided in response to these discussions with members of your Staff and clarifies and supersedes the information provided in our letter of December 23, 1980. The plant conditions of concern were: 1. Cold shutdown with the reactor coolant system drained to the " half-pipe" level (Gduced Reactor Coolant System [RCS] volume), and 2. Cold shutdown with no reactor coolant pumps running (an effectively reduced RCS volume). This analysis of the boron dilution event used conservative RCS volumes (i.e., reduced or effectively reduced RCS volumes for the applicable primary system flowpath). Mixing of the diluting water (boron free) and the RCS water was assumed to take place in the vessel downcomer and proceed in a " wave front" fashion through the rest of the RCS. Specific calculations were performed for each of the applicable primary flowpaths (i.e., reduced or effectively reduced RCS volume). These calculations detennined the baron concentration at the core inlet as a function of time and conservative (high) f boron dilution rates were derived from them. The dilution rates for the two l 810.4 0 7 0 Y.2.2_ g
Mr. Harold R. Denton March 31,1981 conditions of reduced RCS volume were compared and the most limiting condition (highest dilution rates) were used in the rest of the analysis. The most limiting condition was determined to be the " reduced RCS volume" where the primary system is on residual heat removal. This result is attributable to the higher recirculation rate of diluted water when on residual heat removal. The attached figures present the results of this analysis for the most limiting cases. Figure 1 shows the most limiting boron dilution rates l relative to the initial boron concentration for three charging flowrates. l The data in the limiting Figure 1 was then converted to a reactivity addition rate and is displayed in Figure 2. The conversion between dilution rate i (ppm / min) and reactivity addition rate (%ak/k/ min) was a simple dimensional convenian using a conservative (high) differential baron worth (%Ak/k/ ppm) derived from the nuclear design manuals for Point Beach Nuclear Plant, Units 1 and 2. The data in Figure 2 was then integrated to detemine the total reactivity addition for 15-minutes of charging flow. Figure 3 shows the total 15-minute reactivity addition for the limiting charging flows. Figure 4 shows the most limiting (lowest) shutdown margin for a given boron concen-tration as determined from the nuclear design manuals. A comparison of Figures 3 and 4 shows the shutdown margin remaining after 15-minutes of charging for each of the limiting charging flows. The comparison of Figures 3 and 4 is shown in Figure 5. Additionally, the time to criticality can be computed for a given charging flow with a by dividing the shutdown margin (Figure 4)given initial boron concentration oy the product of dilution rate (Figure 1) and differential baron worth (1%Ak/k/70 ppm). The results of the time to criticality calculations nre shown in Figure 6. Figure 6 shows that it is impossible to reach criticality by charging at 60 gpm for 15-minutes if the core is at least 1% shutdown prior to initiation of charging. However, for the other two limiting charging flows, the time to criticality is less than 15-minutes if the core is 1% shutdown prior to initia-tion of charging. In order to detemine a safe operating regime for any charg-ing flow, the minimum required shutdown margin at the three limiting charging flows for any initial concentration was computed. This is shown in Figure 7. The safe operating regime for the limiting charging flows is determined by the I region below and to the left of the intersection points. As an example: if the initial boron concentration is 1230 ppm, the minimum required shutdown margin for charging at 60 gpm is 1%, but the actual shutdown margin is 3.72%. Hence, criticality cannot be reached within 15-minutes. However, if the initial boron concentration were 1040 ppm and the charging rate were 180 gpm, the required shutdown margin would be 2.35% and the actual shutdown margin of 1.0% would be inadequate. Therefore, from Figures 6 and 7, it is concluded that a prudent practice would be to limit charging flow to 60 gpm (1 pump) and provide an alarm to alert the operator that charging has begun and a potential dilution event is in progress.
I Mr. Harold R. Denton March 31,1981 The above conclusion will be implemented by administratively (procedurally) limiting charging flow to 60 gpm (lock out two pumps while at cold shutdown) and by installing a limit switch on the valve for the reactor water makeup pump. The limit switch will activate an alann in i the control room on the alarm status board whenever the valve is not closed. The alarm light will have a message similar to "P0TENTIAL DILUTION IN. PROGRESS". This resolution will provide substantially more than 15-minutes warning to the operator. This is because it will take approximately five minutes for the wave front to reach the core inlet after charging has been initiated and the alarm has been sounded. The installation of the limit switch alarm and procedural changes will be implemented within 90 days of receipt of NRC concurrence with this position. j We would be pleased to respond to any questions concerning the material provided herein. Very truly yours, l r C. W. Fay, Director Nuclear Power Department Attachments Copy to:- NRC Resident. Inspector Point Beach Nuclear Plant 1 A 4 0 i e 5 +
BORON DILUTION RATE Figure 1 VS INITIAL BORON CONCENTRATION 22
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