ML20084N774

Followup to AO Rept Re Correlation of Fuel Failures, Identified by Wet Sipping Tests to Calcualted Violations of GE Pciomr

ML20084N774
Person / Time
Site:	Dresden
Issue date:	06/20/1975
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20084N756	List: ML20084N769 ML20084N774 ML20084N777
References
383-75, NUDOCS 8306090068
Download: ML20084N774 (17)

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• 7 ';. ." CNeago tilincin G'JG09 E S Ltr. #333-75 Dresden !!uclear Power Station R. R. (1 I'. orris, Illinois 60450 June 20, 1975 Mr. Jc=cs G. Keppler, Regional Director Directorate of Regulatery Operations-Region III U. S. !!uelear Regulatory Co::niscion 799 Roo:cvelt Road Glen Ellyn, Illinois 60137 SUBJa',T: POLLC'.?-UP UCT iT TO /C:0R!'JiL 00CU'RE'CE E' TITLED "CORRTIJ.TIO I OF FliEL FAIUBES !.T D:RSCM 3 It';-3;TIP13 'N UET SIPPE:G TECTS TO CALCU13.TZD VIOIEi'ICKS OF GE PCIC:Ot" ,

Reference:

NRC Exit Interview of May 20, 1975' Please find attached the above-::entioned report, provided per !!RC request of May 20,1975 O

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,Mr. Jc=e2 G. Kcppl Juna 20, 1975 TITLE Fuel Failures Identified at D3-E003 by Wet Sipping Teste and Comments Regarding the PCIGH!. .

SUM *.ARY l

724 assemblies were wet sipped out of core and total of 113 defective assemblics were identified. General Electric agreed they were defective as indicated by the fuel contract and were discharged. Twenty-seven high exposure as.aemblies were also discharged and a total of 140 new assemblies were inserted in the core for cycle 4. All the defcetive assemblics were 7X7 fuel enriched to 2.13 w/o U-235. The average fuel failure rate was 15 6%. The core was sipped at an average rate of 40 assemblics per day. Table 1 is a listing of the identified failures, their core locations and exposures.  ;

' DISCUSSION Figure 1 is a coro map indicating the location of the lenkers. Figures 2 to 4 graph three power distributions (equilibrium xenon) typical of the preconditioned shape (2227-Figure 4 (a)) and the shape at 6:57 a.m. on 10-31-74 (1432-Figure 4 (b)). Icnon transients, depending on core location, will increase the bottom peaks by O to 25%.

Failures that don't appear to be related to 10-31-74 are reviewed as follows:

(a) None of the Cycle 2 edge assemblies, including those moved to the center for Cycle 3, failed - Figure 6.

(b) There were three assemblies from cells that had 3 out of 4 failures at EC::-1 that were moved to uncontrolled locatigns on the cdge for Cycles 2 and 3.

None of these three has failed yet.

(c) Pour edge assemblies failed during Cycle 3 One,DD0209, was classified as a suspect 1caker at ECC-2.

(d) Of So Cycle 3 assemblies that trere reconstituted at EOC-1, six failed.

All but one may be attrlbuted to 10-31-74.

No GEB (7X7) or DD3 (8X8) anscsblics were classified as leakers. The average exposure of the GEB's was about 4000 IGD /T, and of the DD3's about 2000 IGD /T.

Initially, one GE3 (058) and two DDS's (008 and 011) sipped as lenkers. The three were recipped twice and found to be sound. To resolve any questions concerning these assemblies, five other assemblies, initially sipped at approx-imately the same time and classified as leakers, were recipped. Again all five

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U CJ were four.d to be defective. Of the 52 GE3's in the core, 29 exceeded the PCIOM.i. Seven of these did so by more than 2 W/f t, and were among the most severy v"intienn. The differencen fro.1 the original core 77.7's int -oduced in the GES's inclucc: different fill gas, lower crposure, thicker cladding, smaller pellet diar.eter, and shorter pellets with chamfered edges.

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Figure 1 indicates that about 80% of the assemblics on the periphery (one assembly removed) of cells that experienced major rod movements (D7, C6, C8 and symetric locations) failed. Figure 7 shows the local power dintribution at about 15,oco w D/r for a controlled and an uncontrolled D3 2.13 w/o asscmoly.

A 2.13 w/o Gd asse=bly is included to compare the local factors of pins A7 and G1, which are about 2 % higher for the D3 assemblics.

An analysis was done with a FLARE-type code to detemine the k'rl/ft of nodes that exceeded 8 kU/ft on a pin. The study was done at equilibrium xenon for 12-inch nodes (a correction factor was applied to account for transient xenon). The results are su arized in Figure 8. Only original core fuel is included, and rcwcr changes were assumed to be instantaneous. Some comments on the results follow:

(a) The failurca do not appear to be related to previous cycle operaticn.

(b) 22 Failures of 433 assemblies (5) were at less than 8101/ft on 10/31/74.

Thus, none of these was assumed to be related to the October 31, red movements.

(c) 5 of 74 assemblies (75) failed when the envelope (or 8 kW/ft, which ever was Ereater) uas violated by 1 kU/ft or less. The failure rate increased rapidly as the step change above the envelope increased.

(d) The effcet on fuel failures of more gradual increases in power, coak periods, exposure, and length of time fuel remains " preconditioned" requires more data than is currently available.

CONCLUSIC"S ..

1. The fuel rod failurcs related to rod movements on 10/31/74 were probably caused by a pellet-clad interaction mechanism involving highly localized strain leading to cracking of claddins having a 1cw strain-to-fracture capability. Some cracking could also have been pro.noted by a stress corrosion phenomenen.

2. GE's PCIOMR, based on the assumption that a minimum tensile stress is recuired to cause such cracking, were in part substantiated: the evidence appears to support the 8 L*/ft threshold and allows some marcin above a " preconditioned" shape.

3 Based on past nipping experience and cn the observed care with which sipping operations uere conducted, the sipping program for D-3 E00-3 was judged to be very successful, with an estimted effectiveness of at least 90%.

TRbLE l

. O o Defective Fuel Assemblica Ident11.1d at Dresden-3, End-or cycle 3

. Assembly Core Excosure

. Number Iocation (f6/D/t )

DD 001 09-30 12,686 021 13-28 13,018 025 13-38 13,420 036 - 13-34 13,008 037 31-48 13,576 053 47-34 12,990 ,

064 51-30 12,814 073 09-34 12,891 079 45-32 13,015 081 53-20 12,882 089 11-30 12,805 090 13-32 13,027 093 47-24 13,439 102 13-30 '

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107 47-32 13,o44 111 09-38 12,580 120 39-2,0 13,321 121 -

4W26 13,100 127 09-?9 12,906 128 51-34 12,928 129 43-38 13,368 132 09-32 12,790 134 47-20 13,'298

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. O Exposure Kas.ere.b1:/

Nur.ber Incc tion (EdD/t) _

142 47-42 , 13,292 151 01-30 11,531 161 31-12 13,731 162 ,45-06 11,671 163 11-36 13,061 173 49-32 12,966 175 13-20 13,327 181 49-36 13,101 188 13-42 13,294 191 13-24 13,569

'196 47-30 13,044 200 49-30 12,923 204 51-28 12,925 209 47-06 11,342 214 '21-20 13,327 229 29-42 ,,

12,822 233 47-38 13,437

. 270 47-28 1'3,114 286 09-36 10,563 287 09-22 10,622 295 07-24 12,653 296 23-30 12,633 300 17-56 11,936 301 53-36 12,966 l

319 05-26 11,945 L

O O Issembly Core Exposure Number Iocotion (IdD/t) _

331 51 12,536 332 25-38 12,287 343 31-20 12,978 350 43-30 12,317 351 43-26 9,465 364 09-42 12,385 378 11-40 12,741 401' 51-42 11,244 .

406 07-26 12,958 424 27-32 11,941

.425 19-06 11,774 431 51-36 10,501 433 09-44 .11,332 436 45-36 12,788 440 53-26 12,619 450 07-32 -

12,678 -

455 51-26 10,568 -

457 35-24 12,303 460 43-34 12,679 465 11-16 - 12,858 474 17-26 9,442 ,

475 39-28 12,550 480 15-50 '12,904 483 13-44 10,353 ,

487 35-32 12,149

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/.'e semb ly Core Exposure Humber Incation (?OID/Q 488 07-36 12,530 ,

, 491 17-28 12,671 493 .

53-24 12,678 499 .51-22 10,652 511 07 40 12,594 518 53-22 12,663 529 11-18 12,939 531' 07 44 11,798 ,

537 27230 11,944 542 11-22 12,820 544 07-22 12,636 566 47-26 lo,088 573 07-38 .22,022 587 25-24 12,309 613 07-30 12,863 617 11 44 .. 12,897 .

618 09-40 10,593 .

. 623 53-38 12,667 624 45-26 12,789 633 49-44 12,949 639 13-26 lo,075 646 13-36 10,060 652 13-40 10,467 663 49-16 12,865 669 33-30 11,945 l 688 49-22 12,802 1

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Exposure Assembly Ku.ber Loc a tion (f tlD/t )

693 13-22 10,502

. 698 47-22 10,503 699 49-40 12,791 700 15-36 12,764 705 05-34 12,099 706 09-26 10,585 710 09-24 12,519 714' 51-40 10,627 716 15-26 12,778 -

721 17-14 10,356

.730 51-20 10,653 745 47-40 10,492 750 53-40 12,648 752 51-24 12,542 j .

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Average exposure of 113 defective assemblies - 12,294 EdD/t.

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