ML20211C716
| ML20211C716 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/13/1986 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 5211-86-2176, NUDOCS 8610220008 | |
| Download: ML20211C716 (5) | |
Text
M NUhIN[
GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054-1149 (201)263-6500 TELEX 136-48?
Writer's E'i'ect Dial Number:
Octcher 13, 1986 5211-86 2176 Office of Nuclear Reactor Regulation Attn:
J. F. Stolz, Director PWR Projects Directorate No. 6 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station Unit 1 (TMI-l)
Operating License No. DPR-50 Docket No. 50-289 Fuel Resintering GPU Nuclear letter to NRC of June 9, 1986 (5211-86-2103) provided a description of the resinter program and results for TMI-l inventory fuel planned to be used as reload assemblies for Cycle 6 and Cycle 7.
In response to your verbal request for further inforination concerning the resinter test results the attached table and figures provide the pellet lot average densification values as reported by our fuel vendor Babcock and Wilcox (B&W) for the two fuel batches (TMI-1, Batch 8 (91F) and TMI-2, Batch 4 (21B)). These data were obtained as discussed in the above-referenced letter. The values for rods "A" and "B" are from the two independent population samples taken for each fual pellet lot.
Figures 1 and 2 graphically illustrate the change ir, percent theoretical density data listed in Table 1, converted to change in density in grams per cubic centimeter for each sample.
Evaluation of the data by B&W showed that the densification characteristics obtained by the modified sampling plan were representative of the two fuel batches.
Predicted in-reactor behavior, using the B&W approved densification model (BAW-10083P, Rev.1, July 1977) with the resinter test results, was shown to be acceptable for licensing analyses. For all densification-related fuel rod analyses the predicted densification characteristics of both samples for each lot were comparad tr the characteristics assumed in the generic TACO-2 (BAW-10141PA, Rev.1, June 1983) fuel thermal analyses applicable to THI-l and were determined to be conservative.
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GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation
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1 5211-86-2176 October 13, 1986 If any further information is required, please contact us.
Sincerely,
. D.
1 Vice President and HDH:DJD:jh(4068f)
Dircctor, Unit 1 Attachments cc:
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Thoma R. Conte D. Fieno l
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Babcock & Wilcox a McDermott company Table 1 Fuel Contracts 660-021B and 660-91F Fuel Rods "A" and "B" Test Results Contract 660-021B 6
6 24 24 24 Hr Hr Hr Hr Hr Lot Rod Rod Initial Density Change 6-Hour Density Change 24-Hour No.Name ID Density Change Std.Dev. Density Change Std.Dev. Density (e.l,_
(m)
(%TD)
(%TD)
(%TD)
(%TD)
(%TD)
(%TD)
(%TD) 1 A
1288 A 94.582 0.6134
.1429 95.196 1.5041
.1535 96.0862 2 A 1588 A 94.093 1.1254.
.2829 95.219 2.2799
.3078 96.3733 3 A 3342A 94.427 0.9232
.1365 95.350 1.7670
.1498 96.1909 4 A 4056A 93.881 0.9466
.1469 94.827 1.6687
.1765 95.5494 5 A 6324A 94.582 0.9293
.1696 95.512 1.6897
.1869 96.2720 6 A 6436A 93.965 0.8608
.1054 94.326 1.6255
.1375 95.5904 7 A 8712A 93.672 0.8704
.1422 94.543 1.9795
.2037 95.6518 8 A 9408A 94.337 0.7100
.1227 95.047 1.6271
.2068 95.9642 9 A 11144A 93.899 1.1626
.0940 95.061 2.2021
.1246
-96.1010 s
1 B 1308A 94.604 0.6332
.1203 95.237 1.4240
.1470 96.0281 2 B 1589A 94.272 1.0912
.1601 95.363 2.0539
.1944 96.3256 3B 3365A 94.345 0.8423
.1055 95.137 1.6710
.1284 96.0156 4 B 4059A 93.887 0.9133
.2773 94.800 1.6706
.3613 95.5572 5 B 6395A 94.117 1.1534
.1444 95.270 1.9335
.1852 96.0503 6
B-6471A 93.936 0.6842
.1077 94.620 1.5072
.1456 95.4432 7 B 9362A 93.639 0.8605
.1269 94.499 2.0656
.1502 95.7043 8 B 9410A 94.444 0.7471
.1452 95.191 1.6617
.1885 96,1058 l _
9 B 11165A 94.491 0.7763
.1596 95.267 1.5919
.2177 96.0824 Contract 660 091F
~
l A 0041F 95.014 0.9514
.0691 95.965 1.5705
.0711 96.5345 2 A 1965F 95.559 1.0911
.1104 96.650 1.6765
.1144 97.2350 4 A 2728F 94.693 1.2334
.1331 95.926 1.8719
.1116 96.5644 5 A 3990F 94.706 1.1502
.1055 95.857
!.8769
.1044 96.5832 21 A 5478F 95.658 1.3418
.0933 96.999 1.8143
.1103 97.4720 22 A 6997F 94.926 1.7504
.1096 96.676 2.4339
.1117 97.3595 23 A 7390F 95.263 1.5424
.1097 96.806 2.2726
.1241 97.5358 24 A 9991F 94.740 1.2985
.0920 96.039 2.0009
.0956 96.7413 25 A 10282F~ 94.936 1.3264
.1375 96.262 1.9949
.1337 96.9307 1
B Ol35F 94.992 0.9687
.0805 95.961 1.5224
.0704 96.5148 2 B 4992F 95.448 1.0572
.2122 96.505 1.6699
.1992 97.1176 -
4 B 3036F 94.747 1.2165
.1629 95.963 1.8381
.2694 96.5850 5 B 4634F 94.927 0.9808
.0943 95.908 1.7017
.1069 96.6289 21 B
5497F 95.683 1.3103
.0995 96.994 1.7966
.0942 97.4799 22 B 6998F 94.790 1.8288
.1364 96.619 2.5874
.1733 97.3775 23 B 7391F 95.205 1.4696
.1333 96.674 2.2276
.1510 97.4323 24 B 10007F 94.858 1.2038
.0874 96.062 1.9266
.1187 96.7849 25 B 10289F 95.047 1.0922
.0821 96.139 1.7278
.0884 96.7748
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