ML20027D774
| ML20027D774 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/01/1982 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8211090410 | |
| Download: ML20027D774 (1) | |
Text
-..
A BALTIMORE GAS AND ELECTRIC CHARLES CENTER. P.O. BOX 1475
- BALTIMORE, MARYLAND 21203 ARTMum E. LUNOVALL, JR.
vier psets.ocen sumv Noventer 1,1982 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cannission Washington, D. C. 20555 ATISTICN: Mr. R. A. Clark, Chief Operating Reactors Branch #3 Division of Licensing SLBJECT:
Calvert Cliffs Nuclear Pour Plant thit No.1, Docket No.30-317 Report of Startup Testirig for Cycle Six GentIaren:
Startup Testing for Calvert Cliffs Unit 1, Cycle 6 was caTpleted on July 17, 1982. A strnrary of the results of those tests was submitted October 15, 1982 under a cover letter which incorrectly referenced Unit 2, Docket No. 50-318.
This letter supersedes and replaces the cover letter dated October 15, 1982.
Very truly yours, IMLTIERE CAS A'O IC CDP ##
J-ar
- ' A. E. Luhdv411
/
Vice Presidebt, Supply
/
AEL:MEB:fid Enclosure cc:
- 3. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC P. W. Kruse, CE gf R. E. Architzel, NRC/CC 7-
%1h410 C6 R
P
2..
BALTIMORE GAS AND ELECTRI i
l CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 1
ARTHun E. LUNDVALL. Jm.
ver Pacsiotwv Supply October 15, 1982 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Conmission Washington, D. C. 20555 ATTENTION:
Mr. R. A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No.
2, Docket No. 50-318 Report of Startup Testing for Cycle Six Gen t l ernen :
Startup Testing for Calvert Cliffs Unit 2,
Cycle 6 was completed on July 17,1982.
A s urrrna r y o f the results of those tests is enclosed.
Very truly yours, BALTIMORE GAS ELECTRIC OCMPANY t&vdh
- a pVice President - Shpply
. E. Lundvall, Jr./
AEL:MEB:fid Enclosure (40 copies) cc:
- 3. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC P. W. Kruse, CE kel
3
'x BALTIMORE GAS AND ELEC'IRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT UNIT I Docket No. 317 License No. DPR-53
SUMMARY
OF STARTUP TESTING FOR SIXTH CYCLE r
s
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p a
' Y
SUMMARY
OF STARTUP TESTING FOR CALVERT CLIFFS UNIT ONE CYCLE SIX I.
The following tests were conducted for the Startup of Calvert Cliffs Unit One for Cycle Six. All tests were conducted in a manner similar to Initial Startup (Reference i
1).
A.
CEDM/CEA Performance Test B.
RCS Flow Verification C.
Initial Criticality D.
CEA Symmetry Check
{
E.
' Critical Boron Concentration Measurements I
s
)
F.
Isothermal Temperature Coefficient Measurements G.
Group Rod Worth Measurements H.
Power Coefficient Measurements I.
Power Distribution Measurements
~
i
)
II.
The results of these tests and compar>
- predictions are as follows:
{i <
A.
The proper functioning of the CEDM's and CEA position indication was verifed through insertion and withdrawal of CEA's. All CEA's reached a 90% insertion I
in less than 3.1 seconds at hot, full-flow conditions. The slowest CEA (59) l reached 90% insertion in 2.94 seconds.
N, B.
Reactor Coolant System flow was verified to be consistent with previous testing.
C.
Initial Criticality was achieved at 1316 ppm Boron with CEA Group-5 at 45.0" withdrawn. Predicted value was 1329 ppm.
l D.
The CEA Symmetry Check verified that all CEA's were attached to their extension shafts. An evaluation of the quantitative reactivity change for dual CEA's yielded an azimuthal tilt estimate of
<6%.
Acceptance Limit
_10%.
was E.
Critical Boron Measurements - Table 1.
F.
Isothermal Temperature Coefficients - Table 2.
G.
CEA Group Worth Measurements - Table 3.
H.
Power Coefficient Measurements - Table 2.
1:
Power Distribution Measurements - Table 4.
a l
111.
All test rese!ts were within acceptance limits except for the Power Coefficient Measurerr.ent at 50% power. This measurement was repeated at 85% power with similar but slightly improved results and the full power measurement satisfied the acceptance criteria. Other measuremenits failed to confirm the existence of fuel temperatures which are suffici-nt to account for ?!.e disparity. Both BG&E and CE have carefully reviewed the test results and the differences between measurement and prediction are felt to be due to the measurement technique which cycles the center CEA in the highly depleted center fuel assembly. Alternate measurement techniques are being evaluated to improve the measurement.
The disparity in agreement between predicted and measured Power Coefficient does not obviate the validity of the safety analysis.
l 1
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TABLE 1 i
CRITICAL BORON MEASUREMENTS J
Measured Predicted 0
All Rods Out,532 F 1334 ppm 1347 i 100 ppm CEA Group 5, 4, 3, 2,1 1078 ppm 1075 t 100 ppm TABLE 2 ISOTHERMAL TEMPERATURE COEFFICIENTS AND POWER COEFFICIENTS ITC Measured Predicted Zero Power, CEA Group 5
+.132 x 10-4 ap/ F
+.113 t.3 x 10-4ap / F ct 102" Withdrawn 50% Power, CEA Group 5
.189 x 10-4 Ap/ F
.148 i.3 x 10-4 ap/ F at 102" Withdrawn 4
85% Power, CEA Group 5
.479 x 10 Ap/ F
.349 i.3x 10-4ap/ F ct 102" Withdrawn 100% Power, CEA Group 5
.577 x 10-4ap / F
.451 i.3 x 1C-4 ap/ F ct 102" Withdrawn POWER COEFFICIENT 50% Power, CEA Group 5
-1.331 x 10'4 ap/% power
-1.006
.3 x 10-4 ap/% power at 102" Withdrawn 85% Power, CEA Group 5
-1.212 x 10-4 Ap/% power
.907 t.3 x 10-ko /% power ct 102" Withdrawn 100% Power, CEA Group 5
-1.147 x 10-44p /% power
.875
.3 x 10-4ap /% power ct 102" Withdrawn
TABLE 3 CEA GROUP WORTH MEASUREMENTS Measured (%
)
Predicted (%
)
Group 5.
.440
.452.068 Group 4
.170
.181 i.027 Group 3
.678
.700.105 Group 2
.492
.491 t.074 Group 1
.836
.889 i.133 TOTAL 2.616 2.713.271 TABLE 4 POWER DISTRIBUTION MEASUREMENTS Measured Acceptance Limits 50 %
100 %
50 %
100 %
I F
1.680 1.596 1 1.73 1 1.65 x
F}
1.594 1.516 11.73 11.65 T
.0130
.0116 1.030 1.030 q
Radial Box See See Measurement varies from P:wcr Distributions Figure 1 Figure 2 prediction by less than 10% (i 15% for fuel assemblies on core periphery).
FIGURE 1
_Calvert Cliffs Unit 1, Cycle 6,50% Power Comparison of Measured Versus Predicted Radial Box Power Distribution Mrasured
@ 50.5, 34.5 MWD /T, Bank 5 at 103.5" Predicted
@ 50%,40 MWD /T, Bank 5 at 102" 1
2
% Diff Measured - Predicted
.7843 1.0764 100
.7770 1.0399 Predicted
.931%
-3.391%
3 4
5 6
7
.8563 1.1359 1.1286
.8548 1.1316
.8496 1.0986 1.0921
.8849 1.0963
.782%
-3.284%
-3.234%
3.521%
-3.119%
8 9
lo 11 12 13
.8761 1.1202
'.9806 1.2229
-1.0249
,9530
.8374 1.1195
.9635 1.2142 1.0088
,9501
-3.758%
.062%
-1.744%
.711%
-1.571%
.304%
15 16 17 18 19 20 14
. 8720 1.0836
.8202 1.2224
.8774 1.2171
.8231
.8374 1.0642
.8502 1.2388
.8711 1.2150
.8330
-3.968%
-1.790%
3.658%
1.342%
.718%
.173%
+1.203%
m 21 22 23 24 25 26 27 28
.8595 1.1245
.8258
.9375
.8769 1.1749
.8644 1.0396-
.8496 1.1195
.8502
.9514
.9360 1.1992
.8857 1.0822
-1.152%
.445%
2.955%
1.483%
6.740%
2.063%
2.464%
4.098%
29 30 31 32 33 34 35 36 1.1404
.9853 1.2317
.9004 1.1564 1.0417
.9352
.9008 1.0986
.9635 1.2388
.9360 1.1790 1.0044
.9698
.9342
-3.665%
-2.213%
.576%. 3.954%
1.954%
-3 581%
3.700%
3.708%
37 38 39 40 41 42 43 44 1.1327 1.2291
.8824 1.1780 1.0354 1.1395
.9377
.8796 45 1.0921 1.2142
.8711 1.1992 1.0044 1.1382
.9382
.9115
)
.7852
-3.584%
-1.212%
-1.281%
1.800%
-2.994%
.114%
.053%
3.627%
~
4%
46 47 48 49 50 51 d2 53
.8571 1.0304 1.2225
.8684
.9343
.9342 1.1163
.8386
.8849 1.0088 1.2150
.8857
.9698
.9382 1.1320
.8824 54 3.243%
-2.096%
.613%
1.992%
3.8D0%
.428%
1.406%
5.223%
1.0757 1.0399 55 56 57 58 59 60 61 62
-3.328%
1.1269
.9688
.8202 1.0571
.9040
.8813
.8390
.5497 1.0963
.9501
.8330 1.0822
.9342
.9115
.8824
.5677
-2.715%
-1.930%
1.561%
2.374%
3.341%
3.427%
5.173%
3.275%
..-.~.,,n....-
FIGURE 2
~
Calvert Cliffs Unit 1, Cycle 6,100% Power Comparison of Measured Versus Predicted Radial Box Power Distribution i
Measured
@ %.6%,260.6 MWD /T, Bank 5 at 105.0" Predicted
@ 100%,250 MWD /T, Banks at 102.C" 1.7434 1.0107 i
.7366 0.9766
% Diff
= Mecsured - Predicted
-0.915%
-3.374%
x100 Predicted 3
4 5
6 7
.8067 1.0709 1.0776
.8328 1.0927
.7948 1.0467 1.0466
.8538 1.0619
-1.475%
-2.260%
-2.877%
+2.522%
-2.819%
r 8
9-10 11 12 13 I
.8264 1.0703 '.9528 1.1926 1.0207
.9566
.8013 1.0753.
.9307 1.1889 1.0030
.9513
-3.037%
+0.467%
-2.319%
-0.310%
-1.734% -0.554 %
15 16 17 18 19 20 14
~.. 8281 1.0416
. 8128 1.2095
.8878 1.2263
.8463
.8013 1.0424
.8403 1.2304
.8807 1.2321
.8496
-3.2,36 %
+0.077% +3.383%
+1.728%
-0.800%
+0.473% F0.390%
21 22 23 24 25 26 27 28
.8094 1.0741
.8181
'.9509
.8999 1.2033
.9026 1.0819
.7948 1.0753
.8403
.9629
.9423 1.2264
.9127 1.1203
-1.804 %
+0.112 %
+2.714 %
&1.262%
+4.712 %
+1.920%
+1.119 %
+3.549%
29 30 31 32 33 34 35 36 1.0747
.9570 1.2180
.9229 1.1914 1.0915
.9961
.9640 1.0467
.9307 1.2304
.9423 1.2093 1.0521 1.0242
.9941.
I i
-2.605%
-2.748 %
+1.018 %
+2.102 %
+1.502%
-3.610%
+2.821%
+3.122 %
37 38 39 40 41 42 43 44 1.0811 1.1980
.8923 1.2060 1.0853 1.1996 1.0067
.9527
^
' 45 1.0466 1.1889
.8807 1.2264 1.0521 1.2034 1.0053
.9777
.7442
-3.191 %
-0.760 %
-1.300%
+1.692 %
-3.059 %
+0.317%
-0.139%
+2.624 %
j
.7366 46 47 48 49 50 al 32 33
~*
.8348 1.0255 1.2310
.9062
.9950 1.0032 1.1909
.9114
.8538 -
1.0030 1.2321
.9127 1.0242 1.0053 1.2212
.9567
@.0101
+2.276 %
-2.194 %
+0.089 %
+0.717 % +2.935 %
+0.209%
+2. 544 %
+4.970 %
0.4766
-3.317 %
55 56 57 58 59 60 61 62 1.0882 0.9714 0.8430 1.0988 0.9669
.9543
.9118
.6073 1
1.0619
.9513
.8496 1.1203
.9941
.9777
.9567
.6242 i
-2.417 %
-2.069 %
+0.783 %
+1.957 % &2.813 %
+2.452 %
+4. 924 %
+2. 783 %
1 i
1 1
i 1
REFERENCE i
i.
1.
Calvert Cliffs Nuclear Power Plant Unit 1. Startup Last Report, August 29,1975.
1 1
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