ML20084R183

Forwards Rept Re Shutdown Margin Tests Performed on Reactors in May 1973.Tests Demonstrated Adequate Shutdown Margin & Indicate Satisfactory Reactivity Worth of Control Rods Tested

ML20084R183
Person / Time
Site:	Quad Cities
Issue date:	08/03/1973
From:	Brian Lee COMMONWEALTH EDISON CO.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8306140821
Download: ML20084R183 (10)

Text

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N .gf Address Reply to: Post Office Box 767 /. t, N Chicago, Illinois 60690 /i p I.,h. "* [i og 's G 8 ]gg _--j l August 3, 1973 .h,h D

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.mri If #ve.:, Mr. J. F. O' Leary, Director ,7/yg#Y,'/ Directorate of Licensing U.S. Atomic Energy Commission Washington, D.C. 20545

Subject:

Possible Inverted Absorber Tubes in Quad-Cities Control Rods, AEC Dkts 50-254 & 50-265

Dear Mr. O' Leary:

Pursuant to telephone conversations on July 23-25, 1973, with the Directorate of Regulatory Operations, Region III, Commonwealth Edison is submitting this report concerning shutdown margin tests performed on the Quad-Cities reactors in May of 1973. The tests demonstrated adequate shutdown margin and indicate satisfactory reactivity worth of the control rods tested. The May tests were conducted to verify shutdown margin in the areas of the core which appeared to be most reactive, and to investigate reactivity differences between symmetric core locations. Section 4.3.A.1 of Appendix A to Operating Licenses DPR-29 and DPR-30 specifies a minimum shutdown margin of 0.25% 4K with the strongest operable control rod withdrawn and all other operable control rods fully inserted. To demonstrate compliance with this requirement, nine two-rod criticals were performed on the Unit 1 core. A summary of the results of those tests is attached as Attachment 1. A shutdown margin well in excess of 0.25% 4K was demonstrated in each case. Two locations:in the Unit 2 core, including the most reactive, were also testad. The shutdoan margins on Unit 2 were demonstrated to be slightly greater than those on Unit 1. The variation between the two cores is due to fuel reactivity variation with core exposure. I y! g \\)y, \\ ' .y G 607G 8306140821 730903 PDR ADOCK 05000 P COPY SENi RI'GION J

8 Commonwealth Edison Com ) .) siy Mr. J. F. O' Leary August 3, 1973 On the basis of examination of these shutdown margins in the most reactive parts of each of the Quad-cities cores, it is concluded the effect of any inverted control rod absorber tubes was insignificant, and the reactors continue to operate safely and within all limits imposed by the Technical Specifica-tions. Very truly yours, 0 e_- E Sc m C A c. 41 1 Byron Lee, Jrs Vice-President cc Mr. Boyce H. Grier Regional Director Directorate of Regulatory Operations - Region III l l

ATTACit/.ENT I SPECIAL TEST sum!ARY UNIT 1 LOCAL REACTIVITY MEASUREMENTS HAY 1973 TworodcriticaltestswereperfIrmedonQuadCitiesUnitI reactor to investigate; a) the magnitude of the shutdown margin and b) the magnitude of a suspected reactivitynsymmetry. The critical tests were performed on Unit i reactor with an exposure of 3400 MUD /T on May 2-6, 1973. Figure 1 summarizes the two rod critical positions, the corresponding reactor water temperature and the measured positive periods. Core reactivity values were determined from positive period measurements, negative period measurements and suberitical multiplication data. Reactivity values become increasingly less reliable as the reactor becomes more shutdown. Subcritical multiplication data adjusted to a measured negative reactivity from negative period data is valid only in aiding the formulation of a rough worth shape curve. Figure 2 illustrates the gross core reactivity drif t and rod worth shape change over the 0-3400 MWD /T lifetime of Unit 1. The same two control rods (G7 and C6) were withdrawn in both cases. The roles of the two rods were interchanged, however. Figure 3 compares core reactivity versus rod position for three symmetric rods to investigate the suspected power. symmetry between Local-Power Range Monitor string 24-09 and symmetrical counterparts. Te.s t results indicate a reactivity difference of.237.oK for symmetric rods F-3 and C-6 at position 20, with corresponding adjacent rods fully withdrawn. 6 O 4

The most limiting shutdown margin check was with control rod F-4 at position 18. Unit I rehetor was supercritical on a 280 second period with a reactor water temperature'of 113'F. Calculated values of core reactivity, Figure 4, indicate Unit 1 to be shutdown significantly more than.257. o K and probably more than 1.0% th K with F-3 fully withdrawn and F4 6th e.eered. Determination of an exact value of shutdown reactivity is nearly impossible because of the uncertainty of the calculations as the error bars show. Figure 5 and Figure 6 show the results of the remaining 2 rod critical tests. These criticals are less' limiting and Unit i reactor appears to be shutdown by much more than 17 a K with either G-8 or J-ll withdrawn at 150*F. Thus, Quad Cities Unit i reactor appears to be shutdown with one rod fully withdrawn by about 17. o K in the worst case at ll3*F. ~0 Assuming a temperature coefficient of 8 x 10 -f1 h, the reactor would be shutdown by.577. 4 K at 60*F. A stuck control rod, if one were to occur during operation, would not jeopardize shutdown capability if it were stuck at position 06 or less. If a control rod were to become stuck at position 08 or greater, a shutdown would be necessitated to either; 1) remedy the stuck rod or 2) demonstrats the shutdown margin with the stuck rod considered inoperable, by fully withdrawing the strongest operable rod and a second strongest operable rod to l critical in a manner similar to that used in previous shutdown margin tests. S 4 [' e .S S e m. , Q. -~- r

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