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AR Nuclear 1 Leaker Fuel Rod Investigation, Preliminary Rept
	ML20030D297
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/07/1981
From:	Husser D; ARKANSAS POWER & LIGHT CO.
To:	;
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ML20030D293	List: 1CAN088108, Forwards AR Nuclear 1 Leaker Fuel Rod Investigation, Preliminary Rept.No Plans to Continue Investigation; ML20030D297;
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CONTENTS I Page I. Introduction 1 II.

Background

2 III. Radiochemistry and Sippino Data 3 IV. Manufacturing Data 9 V. Plant Operation 11 VI. Visual Examinations 12 VII. Diameter Data 19 VIII. Conclusions 26. _i.

I. INTRODUCTION This report provides a summary of the data evaluations available at this time (late July) of the ANO-l leaking fuel rods. This report is preliminary in that much of the data obtained during the PIE work conducted in June and July,1981 has'not yet been fully analyzed. Specifically, the diameter data has been reduced; however, detailed analysis of this data is still in progress. Insufficient work has been completed on the crud samples to allow any data on these samples to be reported. As a result, the tenta- ~ tive conclusions reached in this report may change as more data becomes available. A complete report on this project will be issued in the fourth quarter of 1981. l _ _ _

II. BACKGROUND The AN0-1 reactor experienced a sharp rise in the iodine concentration in mid through late September 1979 while operz. ting at 100% power. The initial indi-cation occurred on September '.:9,1979 after approximately 45 effective full power days (EFPD's) of operation in cycle 4. A fuel assembly sipoing program at the end of cycle 4 (January 1981) indicated a total of 24 fuel assemblies contained leaking fuel rods. In order to obtain additional information to determine the cause of the failures, a post irradiation examination (PIE) of selected assemblies in the spent fuel pool was conducted in June - July 1981. The results 'of an ongaing~ investigation into the cause of the f'uel rod failures are discussed in this report.- A number of conventions are used to describe the location within the core of a fuel assembly and of features or rods within the fuel assemblies. As these are used throughout this report an explanation of these conventions is provided. Core Location The core location of a fuel assembly is designated by a letter-n 2ber identifier. This letter-number corresponds to a row and column within the core. These desig-nations are shown on Figure 1 (see Radiochemistry and Sipping Section). Assembly Locations Each fuel assembly face is assigned a letter designator (A, B, C, or D). Face A is always the number plate side of the fuel assembly. The remaining sides are lettered in a clockwise direction looking down on the assembly top. The fuel rods are numbered from right to left across a given face. The fuel assembly is axially divided in seven spans beginning at the top of the fuel assembly. A span is the portion of the assembly between 2 spacer grids. The six intermediate spacer grids are also numbered beginning at the top of the fuel assembly. These.onventions are shown on Figure 2 (see Visual Examination Section)..

III. RADI0 CHEMISTRY AND SIPPING DATA A. Radiochemistry Radiochemistry monitoring of the ANO-1 reactor primary coolant for cycle 4 indicated that approximately 2 to 4 leaking fuel rods were present in the core prior to 9-19-79 (approximately 45 EFPD's into cycle 4). A sharp rise in the iodine concentration was observed on 9-19-79 and reached an 'i - librium value approximately two weeks later. Iodine values increased by a factor of approximately 10 during this time period. Iodine isotopic ratios indicated the defects were small when initially formed and slowly increased in size over the remainder of the cycle. This results from secondary effects within the leaker rods and is consistent with previous experience at other plants. Significant iodine spikes were observed during subsequent plant shutdowns. Such iodine spikes are normal occurrences in plants operating with leaking fuel rods because of the " pumping" action imposed on the leaker rod during power changes. The variations in iodine cc,centrations observed during the remainder of the cycle were consistent with the majority of the defects having been fonned in the September 1979 timeframe and the defects initially being very small. The number of defective fuel rods is estimated to be between 25 and 40. This estimate is based on the iodine concentrations observed during the cycle and the average power levels at whict the 24 leaker fuel nsemblies operated. This implies that most of the leaking assemblies contain only 1 or 2 leakinc fuel rods. Further substantiation of these estimates has been possible as a result of the re-insertion of 5 of the Batch 6 (once-burned) assemolies indicated as leakers. Radiochemirtry results from cycle 5 (adjusted for known power levels of these 'ssemblies) indicate l 5 to 8 leaking rods in the core, confinning the low number of leaking rods l in +ach assembly. I l 3-

~ B. Fuel Assembly Siooing As a result of the iodine levels during cycle 4, a fuel assembly sipping program was wnducted at the end of cycle 4 to detemine which assemblies contained leaking fuel rods. All 177 fuel assemblies utilized during the cycle were tested. Cesium 134 and 137 were used as the primary indicators for detecting leaking fuel rods. A total of 24 fuel assemblies displayed cesium levels indicative of one or more leaking fuel rods. Figure 1 shows the core locations during cycle 4 of these 24 assemblies. Of the 24 assen-blies identified as leakers, 9 were from Batch 4 (3 cycles of operation), 6 were from Batch 5 (2 cycles of operation), and 9 were from Batch 6 (1 cycle ofoperation). Based on the sipping results the following observations are made. 1. No batch dependence exists. e percentage of the leakers vs. batch Y range from 11% to 16% (see T ale 1). 2. There is a positive correlation of the leakers to power level. Eigh*y-three percent of the leaker assemblies had a relative power density (RPD)of 0.9 or greater and sixty-two percent had an RPD of 1.1 or greater (see Table 3). Thirty-eight percent of the assemblies with ] RPD's at the time of the iodine increase of 1.30 or greater were identified as leakers. This compares to 10% or less for all other RPD groupings. 3. There is a positive correlation with core location. Seventy-five per-cent of the leaking assemblies are contained in either the WX or ZW Quadrants (" west" side). Further, three of the six leaker assemblies on the " east" side of the core are likely candidates for " carry-over" leakers from the previous cycle (Batch 4 assemblies on the periphery of the core). 4. No significant burnup dependence is evident. Leakers were distributed throughout the burntip range (see Table 2). Twenty-five percent of the leaker assemblies with burnups of 19.8 to 21.4 GWd/mtU at 45 EFPD's were identified as leakers. This compares to 14% with burnu s of less e than 2 GWd/mtU and 17% with burnups between 11.4 and 13.7 GWd/mtu. It is believed that 2 to 4 of the leaker assemblies were " carry-over" leakers from the previous cycle. Taking this into consideration, the percentage of "new" leak 3rs for the higher burnup group would be approximately the same as the remaining groupings. t _..

Figure 1 NO-10:RE LCADLNG PLAN CYCE 4 FUEL TRANSFER CANAL ) x 1 FA Face Desi::natic 00XY 00XD 00iS 00XS 0:DCf D N \\\\( $UiO 00XR C A QJX7 oaf! DU OEL 00XI 01FG OCWQ I CD C14 C31 R-03 ONB 01EG 00hV 01G3 00H3 01FJ 00HD 01Di 00XB 01EN 00G2 B215 C43 B214 C32 B20V C33 B231 C57 B 'Jr 'O1I 00XF 01EP 00XS \\ 'V N C0fN 01C 00 3 01FN 00HR 01EA 00C 01EH 00X1 \\ D \\\\ \\ B216 s C13W:0Ys A04 B21P C13 B21N A05 B20X C16 B:0S ON4 A!Y3 s0 E3 00HX 1F3\\ 0017 01F1 A3iA 01Rt 00FU p12U 00Y0 03fC E C55 'B 02 C35 3219s C23 B2D! C03 B213 C6 B 0N C47 s (01E \\'Od{Y\\01FA 001C 01F3 b0XIN 01F4 CaIA 01G1 00X8 00XD 00WX OCWP 01G2 Ca13 F CS B217 A03 Q2hs s*C50 BCA C45 B209 \\'C34h B212 A06 B20Q C33 s 00XA 'D1'Fd\\ M1 01FD 00H3 01G0 00J0 @S 00HY 01FF 00H 01F9 OCHP 01FV 00X9 0 C50 B21S C22 B:0B C12 CIS 5:03 G5 B21K C40 00iE 00XV 01EC CaU 01EX OCH5 \\ 0004 1A41 00fr CGJG 01FJ 0016 01EQ 00Y2 00HQ __y W-H (C(1 C08 3213 Q7 B21R C61 C49 B21D C19 B20G C23 00XH 01FH 00J3N 01FK OdID 01FY OCHF 00WL 0019 01FR 00iV 01FL 0014 01FS 00XE ' C' B21T C17 B:0C CC6 C4 B207 C09 321F 'C42 g \\ 00XX @R CIFS COGX 01F6 Ns x \\' 01FC 00GW 01FE 00Y1 \\ 01Er 20J9 01EY OChN CCY4 001J - s\\ g h'N sxN s L C7 B21C A02 (213 gC3,8g s B:0Dg' C37 B20E C3 B20N A07 B231 C34 ' 0{2\\ 00X2 01FP \\ 00fN [0JF7 \\ \\ p\\ 01F5 THL 01F2 00Y5 . CC!C( 0 \\ 'X11G\\ J1FD M '\\\\ \\ '\\ \\ ' 21'Es'sC1'5N, g N C39 q:10 ' C32 3 321H sC11N BOOP C9 B20F C59 s \\'N g 00XP 01ED int \\ 01ES 00J5 \\ 01G3 CJfr 01ER DaIF 01FQ 00XL 01DI 00XQ N sxT ssN l B21Q gC04g' B211 s 01g B21U C01 B21J A08 3:0R - C22 B 0J A l CJJZ 01EK 00XG 01F2 33JH 01FU 001E 01G4 03Y6 01EF '00J6 \\ hN 0 B22L C53 B21G C46 B:Of C44 B:0L C51 B20K 00Y7 OGJ7 00XN 01Fr 21J 01FX 00X6 00GY NX3 p R-41 C25 CO2 C36 i 00XK 20XC XHK ?CX2 CN R l I Z 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 l l Fuel I.D. (Lt**= Batch 1;00G',CGI* 5 OGJ*= Batch 4;0CW*,00X* 5 00Ya-Batch 5:01E*,01F* 5 01G'= Batch Scurce I.D. (R=3econdary) or Control Ccep I.D. (C=CRA, A=APSR, B=BPRA) Note: All FA I.D.'s are prefaced by 'U vith the exception of Batch 1. Note: Detected Leaker Fuel Assemblies are slashed..

. _ _. _ _ ~ _ _ _ _ _. _ _ - _. _ i t i i. 4 TABLE 1 1 Total Number of Number of Percentage of Assemblies Leaker Assemblies Batch Within Batch Assemblies Within Batch I 1 1 0 r 4 56 9 16% 5 56 6 11% 6 64 9 14% y 1 ] TOTAL 177 24 13.5% 4 6 i i o l i, i i . { a----.--.-..-.--- ---

4 4 i TABLE 2 PERCENTAGE OF SUSPECT ASSEMBLIES VS. BURNUP i Number of Percentage Burnup at Total Leaker of Leaker 45 EFPD's Number of Assemblies Assemblies (GWD/MTU) Assemblies Within Buraup Range Within Burnup Range < 2.0 64 9 14; 7.6 - 9.1 32 2 6% 11.4 - 13.7 24 4 175 .i 13.7 - 19.0 29 2 7% f 19.8 - 21.4 28 7 25% f i 4 i I l ( l l l l l . l

TABLE 3 PERCENTAGE OF LEAKER ASSEMBLIES VS. POWER LEVEL Total Number of Percentage of RPD* Number Leaker Total Percent of Leakers Range of Assemblies Assemblies Leakers liithin Range 0.4 - 0.59 40 4 17 10 0.60 - 0.89 9 0 0 0 0.90 - 1.09 48 5 21 10 1.10 - 1.29 48 3 12 6 > 1.30 32 12 50 38 TOTALS 177 24 100 4 1

Relative Power Density at 45 EFPD.

l i l I I l !

IV. MANUFACTURING DATA The as-built characteristics of the critical components, i.e. fuel pellets and fuel rod clad, have been reviewed to determine if any data indicates a design / manufacturing / material dependency for the leaker rods. The results are discussed below. The discussion dots not include the one Batch 1 assembly used during cycle 4 since it.ias not a leaker. FUEL PELLET Dimensional Characteristics The only significant design change made within the three batches of fuel used in ANO-I cycle 4 was a change in the pellet der.sity and a corresponding diameter change. Nominal pellet density / diameter for batch 4 was 93.5% T.D./ .3700 and 94% T.D./.3695 for Batch 5 and 6. As-built dimensions for all three batches were typical of B&W production. Pellet lots contained in the leaker assemblies showed no tendency to group on either side of the nominal or to show greater than normal standard deviations. No single pellet lot was used in more than four of the leakers. Chemical Characteristics Pellet impurity, 0/U ratios, and absorbed gas content were checked. All values were within normal manufacturing ranges. Pellet Moisture Mean pellet moisture for all lots was 3 ppm or less. Standard deviations were typically 1 ppm or less. Fabricator The same pellet (CNFP) and powder (Appolo) vendor were used for all three batches. _g.

j i FUEL ROD CLA0 Dimensional Characteristics No designchanges crcured over the three batches of fuel in the clad design. Batch mean clad I.D. and 0.D. were within 2.0001 inch of nominal with samole variances of.0003 inch or less. Lot mean I.D. and 0.D. were within one standard ceviation of the batch means. As with the pellets, no pattern existed l for the lots contained in the leaker assemblies. No single clad lot was l contained in more than 4 of the leaker assemblies. Clad Comoosition/Imourities A total of 12 cifferent ingots were used to produce the clad lots contained i in the leaker assemblies. No unusual impurity levels were found in any ingots j and alloying agents were found to be in the normal ranges for all cases. 1 Fabricator The same clad vendor (Sandvick) was used for all three batches. The same ingot vendor (Wah Chang) supplied all ingots for the three batches. Conclusion The conclusion reached was that no evidence has been found to indicate that a manufacturing / materials dependency exists for the leaker assemblies. l i s i 1 k 4 i i ,, -, -,.... - - - - - -. ~ -.,,. -.

I i a j V. PLANT CPERATION i 1 A review of the plant operating history over the early part of the cycle was made. A number of notable items from this review were discussed below. l The plant had operated at steady-state 100% power for approximately 30 days prior to the increase in iodine. A computer analysis using the FLAME computer code was made of the startup immediately prior to the steady-state run. The data indicates no significant increases in the local power levels l (<lkw/ft max) above the normal operating levels during the startup. Based on j this analysis and the plant operating history prior to the increase in icline levels, it was concluded that the startup is unrelated to the leakers. l A review of the operating logs (both operator and canputer generated) for the time period immeciately prior to the iodine increase was conducted. This review indicates no significant rod movements or major system imbalances. l A core tilt existed at the time the iodine increase occurred. While its magnitude was small (s2.5%), its direction corresponds to the side of the core in which the majority of the leakers were found. The tilt resulted i in approximately a 4 to 5% higher relative power on the side of the core in which the majority of the leakers occured. The tilt, by itself, is not i unusual; however, its directional correspondence with the leakers indicates that it may represent a secondary but minimal factor associated with the l failures. I 4,-

F l 1 1 VI. VISUAL EXAMINATIONS A. Fuel Assemblies Visual examinations of fuel essemblies Table 4, were made during both the 4th refueling outage and the subsequent PIE. The examinations during the outage were made using standard underwater video equipment. To assure higher ~ ] quality visual examinations, a periscope was used'during the PIE work. The periscope examinations resulted in the idcntification of 3 fuel rods having throughwall defects. General observations made during the visual examinations of the leaker fuel assemblies are as follows: 1. The fuel rods exhibited four types of surface condition: (a) A dark brown / black uniform crud deposit (b) Lighter, more reflective areas which represent areas in which the crud had flaked off (loosely adhering flakes of crud were seen in some of these type areas) (c) White, highly reflective areas which appeared to be ); white deposits i (d) Mottled areas which were combinations of.(a), (b), and (c). 2. The rods exhibited a " typical" axial pattern (as observed during the PIE) begir.ning with brown / black crud in lowest span, getting progressively lighter / whiter through the center of the assembly, and becoming mottled in span 3. Span 2 was more uniform than span 3; however,.it still exhibited a mottled appearance. Span 2 also was darker than span 3. Span 1 was similar to span 2 except that it also contained 1 or sometimes 2 horizontal patterns of light-on-dark crud. The upper pattern was located near the top of the fuel column, while the lower

pattern was located across the lower third of the span and was generally the more predominant. 3. The early examinations ( during the refueling outage) on the assemblies differed slightly in the axial profile. The white / lighter areas extended ugward somewhat farther and the lower " flame" pattern was not as pronounced as the e,oer pattern. A darkening of some areas which appeared white in the earlier exam had occurred. Whether this occurred as a result of additional crud deposition in the spent fuel pool or dissolving of the white crud deposits could not be determined. Furthermore, some additional areas of cruci flaking (exposing the more reflective under surface) were observed in the PIE. 4. The general level of crud appeared to be low and similar in thick-ness to that observed previously at other reactors after 1 or 2 cycles of operation. This is substantiated by the relatively low specific activities and weights of the majority of the crud samples. 5. On a few assemblies, white crud deposits appeared to be thick end mottled in one or two of the top four spans. These deposits were icsalized and seldom occurred on more than one face of an assembly. They had the appearance of dripping or streaming candle wax over-laying a darker, apparently more uniform crud. Occasional streams of light orange deposits overlayed the thicker white crud. These patterns, however, were not common. 6. No significant rod bow (>50% closure) was observed except on rod A2 on 01E9. See discussion below on this rod. 7. Spacer grid cell damage was observed on two assemblies, 01F7 and OCJ5. A broken corner weld (one side only) was observed on grid 2 of OlF7 at the B-C corner of the assembly. Assembly 00J5 had cell 1 on face A damaged at grids 2 and 3. In each case the lower strap and s60% of the soft stop had shearud off. The soft stop (rod contact point) was atscnt in both cells..

i t In general, the fuel assemblies have a greater variation in crud patterns than previously observed at other reactors. However, their appearance was typical of previous observations with the exception of the extent of the whitish deposits. White crud deposits have been observed at other plants in association with known through-wall defects. In those cases the white deposits remained more localized and could be best characterized as a " plume" extending upward from the defect. The tendency for the leakers to cluster and the length of oper-l ation ('dik years) after the leakers were formed are possible reasons for the i extent of the whitish deposits seen at ANO-1. Sound assemblies away from the cluster of leakers were observed to have little or none of the highly reflect-ive white crud deposit. Visual Observations of Leaker Rods Three fuel rods with through-wall defects were /isually observed. These are Rod A2 in 01E9, Rod C13 in 01F7, and Rod D15 in 00J5. Figure 2 gives sketches of the areas of the three rods which exhibit through-wall defects and other anomalous areas. Photographs of these rods will be providcJ in the final report. The observed defects have several common characteristics. The rods each exhibit a blister type formation (s) on the central part of the rod in spans 3 or 4. Each exhibits a second area of interest somewhat lower on the fuel rod. In the case of 01E9 and 01F7, the lower defect appears to be a crack ur split in the clad. In the case of 00J5, the areas appear to be a bubble in the uniform white crud cover-ing span 5. In this latter case it is not clear that this bubble represents a through-wall defect. If it is assumed that the areas observed are the only defects on the rods, the upper defects on rod A2 and C13 in 01E9 and 01F7, respectively, are judged to represent the location of the primary failure. The lower defects on these rods are believed to represent secondary effects d;d to subsequent water intrusion into the rod. It is also possible that all of th0 abserved areas represent secondary defects and the primary defects either remained too small to detect vitually or were in a non-observable location (only 30% to 40% of the rod surface area is readily observable). 4

I Two other observations of note were made concerning the defects on A2 on 01E9 and D15 in 00J5. Rod A2 in 01E9 did exhibit rod bow as noted earlier. The rod bow occurred in span 4 and appeared to be maximum *t the location of the upper defect. Since the defect occurred at approximately center span, the coincidence with maximum rod bow is not surprising. Based on the observatiors made, the direction of the bow is in a plane perpendicular to the "A" face, i.e., the bow is inward toward the second row of rods. As a result of the direction of the bow, the amount of bow cannot he estimated from the photographs. The grid damage to 00J5 described previously occurred in the cell restraining rod D15. No relationship between the grid damage and the rod failure appears to exist. B. Burnable Poison Rod Assemblies (BPRAs), Two BPRAs were inspected during the PIE to determine if failure of individual poison rods could have resulted in local power peaks in the Batch 6 fuel assemblies. No defects or breaches in the cladding were found. BPRAs B20Y and 821E were examined in the PIE area using a standard black and v' lite video camera. These assemblies operated in fuel assemblies 01EV (core location D-5) and 01F7 (core location M-6), respectively, during cycle 4. Both of these fuel assemblies were identified as leakers in the sipping campaign. Each BPRA was viewed from two sides: sides I corresponding to fuel assembly faces B ano ^ on B20Y and faces B and A on B21E were viewed. i I All of the rods were covered with a dark, sooty, loosely adherent crud and many had thin axial scratches which obviously resulted from handling. In addition to the axial scratches, lighter areas were seen which resembled " chatter" or rub marks. These areas varied in size and shape, ranging from 'h to - inches in diameter and were circular or oval in shape. The oval type areas were occasionally oriented with their major axis ~300 from the vertical giving them a spiral appearance. The areas occurred more frequently and at more periodic intervals (as close as 'h" apart) on certain rods in the central three or four feet of the rods. These areas are prob-ably a result of flow differences in the guide tube / rod annulus resulting from changes in annulus size and local turbulence. -.

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Table 4 Visual Examinations of AN0-1 Fuel Assemblies Assembly No. Cycle 4 Outage PIE Exam Batch 6 ole 9 (Leaker) Yes Yes 01F6 Yes Yes OlF3 Yes Yes 01F7 Yes Yes OlEV Yes No OlEB Yes Na OlFW Yes No OlFP Yes No OlFC Yes No 01FU (Sound) Yes No OlEQ Yes No Batch 5 00XS (Leaker) Yes Yes 00XM Yes Yes 00X4 No Yes 00Y1 No Yes 00WY No Yes 00XJ No Yes 00WZ(Sound) No Yes Batch 4 00HG(Leaker) fio Yes 00J1 No Yes 00J3 No Yes 00H5 No Yes 00J5 Yes Yes 00JB (Sound) Yes No __, _ -

VII. DIAMETER DATA Note: The data discussed in this section is preliminary. No major changes ia the results discussed are anticipated for the final report; however, additional review and analysis of this data is in progress which could result in some changes, Rod diameter measurements were made.on 10 fuel assemblies during the leaking fuel examination. These included three batch 4, five batch 5 and two batch 6 assembl ies. Equipment used is described in Reference 1. The measurements con-sisted of a single orientation line-scan of the diameter of the fuel rod in a plane carallel to the face of the assembly. In most cases, the computer data acquisition system (DAS) was used to acquire and store the data. Table 4 lists all rods that were scanned. Note: Repeat scans of rods were frequently performed in or der to assure the repeatability of the data. In addition, data on randomly selected rods were acquired by both the computer and a X-Y chart recorder to provide addeo assurance of the repeatability of the data. l All diameter data were reduced by calibrating the raw d ta to a trace of a l three step calibration standard. Each diameter trace was digitized (approximately j every 50 mils for DAS data and 200 mils for charts). A distribution mean and standard deviation were calculated for each grid-to-grid segment of each rod. This data is still under review at this time. However, a number of results are available and are discussed below. The average creepdown over the center spans (2 through 6) for non-leaking fuel l rods can be summarized as follows: Batch 6 creepdown - 1 to 2 mils Batch 5 creepdown - 14 to 2 mils Batch 4 creepdown - 2 to 3 mils These values are somewhat lower than previously obtained data on Mark 8 fuel, especially for the batch 5 and batch 6 assemblies..

Previcas data indicates that creepdown generally ranges upwards from 1.5 mils even at low burnups, and can be as high as 3 mils after one or two cycles and 4.5 mils efter three cycles. The ANO-1 cladding creepdown is within the prev-iously observed data scatter but is somewhat below the previously observed mean values. In addition, data on other two-cycle fuel showed creepdown ranging from 2.8 to 3.3 mils. Also, several assemblies have shown over 2 mils of creepdown after just one cycle. Diameter profiles of the visually confirmed leaker rods are shown in Figure 3. Rod A2 in 01E9 exhibited two visible defects. The first was midway between grids 3 and 4 and is blister-like in appearance. Figure 3 shows that this defect caused the diameter to undergo a small increase, then a sudden decrease and a sharp increase (scanning down from the top of the rod). The " trough-to-crest" height of this peak is approximately 22 mils. The second defect was a vertical crack about 0.75 inch in length occurring below grid 6. This produced a very wide and tall peak approximately 20 mils in height and about 2.5 inches long. Another sharp peak of about 13 mils occurred midway between grid 6 and the lower skirt. In this latter case, no defect was seen in this area during the visual examination. There are other anomalies associated with this rod. Spans 4 and 7 (which contain the confirmed defects), as well as spans 1 and 2, exhibit an above average degree of diameter variation when compared to the relatively flat traces for spans 3, 5, and 6. Span 3, however, includes a 4 mil d'ameter decrease just below grid 2, which extends at least 2 inches axially. All of these areas were closely re-examined following the diameter scans, but nothing unusual w'as seen except for the two defects ~ and some peeling crud in span 4. It should also be noted that all of these features repeated well on all runs, including the DAS and X-Y recorder. The apparent lack of creepdown and ovalization in the mid-region of the rod indicates that this rod became defective in cycle 4. Rod C13 in 01F7 exhibited three visible defects, two blister-like defects between grids 2 and 3, and a possible hairline crack just above grid 6. The t'co blisters produced sharp peaks, 8 and 10 mils in magnitude (Figure 3). Similar peaks occurred just above grid 2 and just below grids 5 and 6. No defects were seen in these areas. --

The apparent hairline crack just above grid 6 produced no significant change in the diameter trace, probably because the defect was too close to the grid for the diameter fingers to reach. Like 01E9/A2, this rod showed a large amount of diameter variation. The only flat span, between grids 4 and 5, shows little ovalization or creepdown. Based on mean diameter data, this rod also apparently became defective early in cycle 4. The third rod with a visible defect was rod D15 in 00J5, (diameter trace not shown), which had a small hole just below grid 2. This defect was not detectable with the diameter scan due to its proximity to the grid. The diameter downscan, when it passed grid 3, indicated a gradual increase in diameter over several inches, and then a voltage outside the range of the computer /LST interface. This resulted in a tall plateau along this entire section of the rod. It is not known whether this is a true diameter or whether the fingers were cocked or " rode up'" on the rod. The rest of the scan showed an abnormally high diameter, except for span 3. The rod mean diameter neglecting span 4, was over 0.434 inch. Although the general shape of the trace showed reasonably good repeatability on a repeat scan, the values must be considered suspect. In addition, the orthogonal trace on rod A1 (not shown) has a relatively flat shape with a mean diameter of 0.430 inch. As a result of these facts, the DAS data on this rod is not considered to be reliable. This conclusion is further supported by visual examinations. The diameter traces for rods A2 of 01E9 and C13 of 01F7 have been reviewed for indicat-ions of pellet clad contact. Both the clad diameter and the distance between diameter " spikes" are inconsistent with that which would be expected in the case of pellet-clad contact. It is, therefore, concluded that pellet clad-contact did not occur in these rods. In addition to the three visually confirmed failed rods, there were several diameter profiles that showed unusual behavior. These are discussed below. Rod D15 in 01E9 had a sharp, 12 mil downward spike in span 2. The spike corresponded to a region of high ovality (about 10 mils) in this region. The rod was scanned twice, and showed good repeatability. Also, the orthogonal trace for Al correlated well. Thus, the spike and ovality are not thought to be artifacts, but are probably real. Rod D1/C15 in 01F7 had a similar-looking occurrence, also in span 2, although the downward spike was not as great. Rod B15/C1 in 00HG has larger than normal diameter variations in the bottom three spans. The traces repeated well and the orthogonal scans show good correlation..

These variations appear to be greater than expected from rod ovalization. In each of these cases, no defects or anomalous areas were observed in these areas. ~, l 450. FUEL ASSEMBLY NJ01E9 FACE A ROD 2 E [ $ 3 4 35. lE ._.- %d L A A yp ~- 420. I DOTTOM GS G5 G4 G3 G2 G1 TOP i 450. FUEL ASSEMBLY NJ01F7 FACE C 000 13 1 i 5 C3435 ~N L-~~~h M+ 1 hb 9 ju)% J s-- --w 420. DOTTOM GG G5 G4 G3 G2 G1 TOP AXIAL POSITION Figure 3 - Expanded-scale Diameter Traces on Failed Rods I l 1 +

Table 4 ANO-1 Diameter Scans Assembly Face / Rod Scan Dir. NJ01E9 D15 Up A2 Down A2 Down D1 Up A15 Up Al Up D15 Up NJ01F/ Al Up A15 Up B1 Up B15 Up Cl Up Cl3 Up C15 Up C15 Up 01 Up D15 Up NJ00J5 Al Down A15 Down B1 Down B15 Up Cl Down C15 Up D1 Down D15 Down D15 Down NJ00J1 Al Down A15 Up B1 Down B15 Up Cl Down D1 Up D15 Up NJ00XJ Al Down A15 Up B1 Down B15 Up Cl Down C1 Down C15 Up D1 Down D15 Up _ _ _ ~. -.... _... _ _ _. _.. _ _.. _ -.. _.. _... _... _. _, _. _.. - _. _.. _ _. _. _.. _.. _ _ _ _ _ _. _.

Table 4. (Cont'd.) Assembly Face / Rod Scan Dir. NJ00HG Al Down A15 Up A15 Down B1 Down B15 Up B15 Down Cl Down C13 Up D1 Down D15 Up NJ00WZ Al Up A15 Up B1 Up B15 Up D1 Up D1 Up D1 Up D8 Up D8 Up D15 Up D15 Up D15 Up NJ00WY Al Devin A15 Up B1 Down B15 Up C1 Up C15 Up 01 Down D15 Up D15 Down D15 Up NJ00XS Al Down A15 Up B1 Down B15 Up C1 Down C15 Down D1 Down D15 Up Table 4 (Cont'd.) Assembly Face / Rod Scan Dir. NJ00XM Al Down A15 Down B1 Down B15 Up Cl Down Cl Down C12 Down C15 Up C15 Down D1 Down D15 Up Note: Based on the conventions used, Rod 1 of any given face represents an orthogonal trace of Rod 15 of the counter clockwise fact, i.e., traces of Rods Al-D15, B1-A15, Cl-B15, and Dl-C15 are orthogonal traces of the corner rods. REFERENCE 1: T. A. Coleman, et al., Devclopment of an Extended Burnup Mark B Design, Second Semi-Annual Progress Report, January - June 1979, BAW 1532 - 2, D0E/ET/34213-2, Babcock & Wilcox, December 1979. j _.. -.

VIII. CONCLUSION No definite cause for the leakers at AN0-1 has been established. However, based on data obtained to date, the following tentative statements can be made. A brief discussion is given with each.

1. There are no indications that the leaking rods resulted from manufacturing related sources.

Manufacturing related rod failures, i.e., primary hydride failures, weld defects, etc., are typically seen early in the rod lifetime. After accounting for carry-over leakers, it is estimated that at least 50% of the leaking rods had success-fully operatec either one or two full cycles prior to developing t' ough-wall defects. The lack of any correlation between manufacturing related attributes and the leaker assemblies provides further evidence of the absence of a relationship. In addition, the "si ultaneous" origin of these defects which occurred after ~45 m EFPD's of cycle 4, is not consistent with past occurrences related to marafacturing related failure modes. These types of failures have more commonly beer. observed either "immediately" after startup or show up as a gradual increase :n activity over the early part of the cycle.

2. There are no indications that the leaking rods resulted from the pellet-clad interaction induced stress corrosion cracking mechanism (PCI/ SCC).

PCI/ SCC is associated with rapid power changes (ramps) resulting in high local powers of the fuel rods. No operatior;? event occurred around the time of the iodirie increase which would have resulted in a significant power ramp to the leaker assemblies. As noted in the Operational Data section, the startup -35 days prior to the iodine increase should not have resulted in any rods experiencing significantly higher power levels than they had experienced previously. No significant control rod (full or part length) movement occurred around the time of failure which could have induced a local power ramp. Rod diameter treces of the two batch 6 known leaker rods show no evidence of pellet clad contact. Such contact would be expected to be present if PCI/ SCC had in fact occurred. The low burnups ('2000 mwd /mtu) of the batch 6 leakers at the timo the defects occurred would hasc req-uired much higher power levels to induce PCI/ SCC. These factors and past experience indicate that PCI/ SCC was not the defect formation mechanism. -.. ~ _ - - - -

3. Areas to be considered Additional areas being investigated are : 1) chemical attack by some undentified agent and 2) enhanced local clad oxidation due to local crud buildup. Some combination of these could also have occurred, Local areas of thicker crud were observed during the visual inspections. The coloration of some of these areas was different from that generally observed, possibly indicating a different composition or chemical state of-the constituents in those deposits. The axial variations in crud patter.ns observed indicate some temperature and/or power (flux?) dependency of crud deposition. This could explain a possible power level dependency of the leakers. The on going work on the crud samples takte during the PIE work may provide additional data to verify these possibilities. 4 t a 1 l _.-..-_.-,-._.,,..-m., ..m-,7,..

n-t N

T e

l ARKANSAS NUCLEAR ONE-UNIT I 1981 REFUELING OUTAGE-END OF CYCLE 4 WET SIFPING TEST REPORT JANUARY 25-FEBRUARY 8, 1981 m-C ta e DATE: b - //~7/ PREPARED BY: i "G.P. h / PREPARED BY: s DATE: 8 27 P/ 4.R. Smith APPROVED BY: 4 %f G [ e Rav DATE: cf - // - F/ R.N. Du can APPROVED BY: /< f DATE: / /.I2/ B.J. feTig i i

e. h{ TABLE OF CONTENTS PAGE INTRODUCTION 1 SIPPING OPERATIONS 1 I SIPPING RESULTS 2 CONCLUSIONS 2 TABLE I ANO-I ASSEMBLIES IDENTIFIED BY WET SIPPING AS CONTAININGLEAKING FUEL RODS 3 TABLE II ANO-I LEAKING FUEL ASSEMBLY DISTRIBUTION BY FUEL BATCH 4 FIGURE 1 ANO-I SIPPING ANALYSIS Cs 5 j34 FIGURE 2 ANO-I SIPPING ANALYSIS Cs 6 l37 FIGURE 3 ANO-I SIPPIllG ANALYSIS I 7 131 FIGURE 4 ANO-I CORE LOADIhG PLAN CYCLE-4 8 ? v-APPENDIX A ANO-I SIPPING DATA LOG 9 e w: i

l i' s. s INTRODUCTION t,::= Each fuel assembly frcm the Arkansas NAnar One Unit I core was examined i for leaking fuel rods by Wet Sipping during the 1981 End-of-Cycle Four refueling outage. The Wet Sipping concept is based upon the fact that leaking fuel rods 1 within a fuel assembly expel measurable quantities of radioactive isotopes i when the temperature of the fuel assembly ' rises. By plac'ing a fuel assembly i into a closed volume of water, it is possible to allow the fuel assembly to

~

heatup by fission product decay heating. A change in water temperature in-side the sipping can cf thirty (30) to forty (40) degrees Farenheit is sufficient to cause fission products to be expelled into the water, if the i fuel assembly being tested contains leaking fuel rods, i ) Water samples were drawn from a sipping can containing a fuel assembly. The fission product isotopes that were measured during this sipping program included I131, Csl34, and Csl37 A baseline water sample was taken from each i sipping can immediately prior to inserting the fuel assembly. This baseline sa ple established the background activity level of the pool water inside each sipping can. Analysis of the water samples was done by usinga Lithium drifted Germanium Ge(Li) l detector and a multi-channel analyzer to determine the number of disinteg-l rations of specific er:ergy levels in the sample or baseline. Since the three isotopes being analyzed emit known energy gamma radiation, it was f.,

('_

'ossible to isolate those energy peaks on the multi-channel analyzer and l accurately determine the concentration of the three isotopes. A correction I for ba:kground activity was programmed into a Hewlett-Packard computer that was interfaced with the multi-channel analyzer, and calculations were made using nuclide abundance, half-life ar.d sample volume to yield isotopic j activity in terms of cicrocuries per milliliter of sample volume. Data for each fuel assembly were stored on magnetic tape and used to identify [ leaking assemblies through statistical analysis of the isotopic activities. I SIPPING OPERATIONS l l Wet -Sipping was perfor.ned in the reactor cavity as part of the fuel shuffle. The first fuel assembly was sipped at approximately 1130 hours on January _ 29,' 1981, and the last assembly was completed at 1130 hours on February 8, i 1981. The initial intention was to test one hundred twenty (120) fuel assemblies, distributed among the various batches as follows: 1 Batch 4 56 Assemblies Batch 5 SC Assemblies Batch 6 8 Assemblies i' Leaking assemblies were found in both Batch 4 and Batch 5. Discovery of a leaking assembly in Batch 6 predicated the decision to sip all one hundred, seventy-seven (177) fuel assemblies in the core.

(=;

n.. SIPPING RESULTS I Displayed in Figures 1, 2 and 3 are the histograms from ANO-I fuel wet sipping.These log-normal representations show the distribution of the ---.--,.,n.n-,,,-,-,,--,-,n..,ve-- n n.e r n,- ,,e-,w..,--m...,w,,,- n, w .,m w-e.w, _ _

7 concentrations for each isotope. ine plots of the data for both Csl34 and h Csl37 show little variation about the mean value for fuel assemblies that did not contain leaking rods. Segregation between assemblies identified as containing leaking fuel rods and those free of leakers was clearly evident by the separation in the isotopic concentration levels. The lowest Csl34 and Cs137 isoto;:ic concentrations for an assembly identified as i leaker (NJ00H0) were E and 9.7 times higher than the three-sigma leveP for the populations of nor.-leaking assemblies, respectively. The segregation between leaking and non-leaking fuel assemblies for 1131 was not as clearly evident. Fourteen (14) of the twenty-four (24) assemblies identified as containing leaking fuel rods by the Cesium isotopes had 1131 concentrations greater than three-sigma. Figure 3 shows that three of the remaining ten assemblies had concentrations below three-sigma but significantly separated from the rest of the population. The remaining seven assemblies (all Batch 4 assemblies - shown as dark squares) had Il31 concentrations distributed in the higher value range of the non-leaking assemblies. This is attributed to the fact that the :131 background activity of the cavity water was higher during the early part of the testing -than during later portions. Also the low release levels of 1131 frcm the Batch 4 assemblies due to relatively lcw decay heat levels contributt.d. This was caused by these assemblies having run at low power during Cycle four. Table 1 lists the assemblies that contained leaking fuel rods, the sipping sample number, cycle four core location and the concentration values for the isotopes analyzed. Cycle four core locations of leaking assemblies a e also shown on the core map (Figure 4). Table 2 details the distribution of the leaking assemblies according to fuel batch. CONCLUSIONS Based on the isotopic concentration data, twenty-four (24) assemblies were identified as containing leaking fuel rods in the ANO-I Cycle' four core. The sipping tests cor irmed that the high primary coolant activity levels r observed during plant operation were caused by leaking fuel rods within the core. Ci 2

a v A \\ - ~_ TABLE 1 {.l? / 'I ANO-I ASSEMBLIES IDENTIFIED BY WET SIPPING T AS CONTAINING LEAKING FUEL RODS IS0TOPECONCENTRATIONS(Ac/ml) ASSEMBLY SIPPING CYCLE 4 I Cs Cs SERIAL N0. SAMPLE NO. CORE LOCATION l31 l34 l37 NJ00J5 11 N6 2.668E-03 1.075E-01 9.376E-02 !!J00J1 33 M9 2.825E-03 1.262E-02 1.353E-02 NJ00HG 39 M7 2.590E-03 1.323E-02 1.062E-02 NJ00Y1 64 L10 9.658E-03 3.108E-02 3.404E-02 NJ00XJ 69 L6 1.377E-03 6.656E-02 7.001E-02 NJ00X4 147 F10 3.570E-03

1. i14E-01 1.038E-01 HJ00WY 153 F6 3.626E-02 1.569E-01 1.538E-01

'NJ00XS 186 D4 7.076E-03 4.538E-02 5.544E-02 NJ00H0 201 Bil 1.463E-03 1.236E-02 1.592E-02 ,JJJ00XM 216 N4 5.419E-03 1.893E-02 2.596E-02 (_;_JHZ 21 9 M14 3.060E-03 3.999E-02 4.534E-02 NJ00H2 222 M2 5.943E-03 9.918E-02 9.315E-02 NJ00J6 228 013 1.867E-03 1.9928-02 2.077E-02 NJ01E9 249 F5 1.422E-01

1. 504E-01 2.479E-02 NJ01FC 252 L7 4.412E-02 5.065E-02 7.409E-02 NJ01F7 268 M6 5.786E-02 6.700E-02 9.704E-02 NJ00J3 274 K3 1.427E-02 9.487E-02 7.122E-02 NJ01F3 283 E6 4.910E-01 4.227E-01 5.645E-01 NJ01F6 318 L5 2.571E-02 4.491 E-02

?.244E-02 NJ01EV 345 D5 2.192E-02 1.503E-02 2.296E-02 NJ01FP 357 M4 3.713E-02 4.462E-02 6.409E-02 NJ01EB 372 E4 1.856E-01 1.827E-01 2.479E-01 NJ00H5 409 H6 2.489E-03 7.875E-02 6.208E-02 NJ01FW 540 G2 3.782E-02 4.508E-02 8.004E-02 5 3

\\ s-i- .. ;i. n TABLE 2 ~ ANO-I i LEAKING FUEL ASSEMBLY DISTRIBUTION BY FUEL BATCH ~ k NO. OF ASSEMBLIES WITH % OF i SERIAL NO. NUMBER OF NO. OF LEAKING LEVELS GREATER TilAN 3 SIGMA BATCH WITH BATCH IDENTIFICATION ASSEMBLIES SIPPED ASSEMBLIES I CS CS LEAKERS 131 134 137 \\ j 1 NJ1A41 1 0 0 0 0 0 1 1 4 NJ00G-56 9. 1 9 9 16 NJ00H-NJ00J-i 5 NJ00W-56 6 4 6 6 11 j NJ00X-NJ00Y-i 6 NJ01-- 64 9 9 9 9 14 l TOTAL 177 24 14 24 24 14 } } i i 1 l 1 i 4 i

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ANO-1 CORE LCADING PLAN CYCLE 9 m., nyfiig 00XY 00X0 00HS 00X5 00XW A CCX7 00HM 00WU 01EL 00XT 01FG COWQ 00H3 00XR B CSC C19 C31 ] R- 03 20JB 01EG COWV 0163 00H8 01EJ 00HD 01EW 00XS 01EN 00GZ C B215 C93 9219 C52 B20V C38 820U C57 B20T COXF 01EP 20XS!0iEV 00HW 01EZ OCHS 01FN 00HR 01EA 00WZ OiEH 00Xi ] D B216 AC9 BaiP C13 B21N A05 B20X C16 820S 20J9 00YS OiEEl00HX OiF3i OCH7 01F1 00HA 01FM 00HJ 01EU 00YO 00HC E C55( ] C]5 ~~$ C23 82iM C03 8213 C26 820W C97 L I ~ 20WP 01G2 00.*E!OiESl00MYiO1FA 00JC 01FB, 00X9l 01F9 00JA CiG1 00X8~ 00XDl 00WX 2-- C28 B217 A03: ] B20A C95 B209[~ 3212 A0 B200 CBS 00XA 01FW 00H1 01FD 00H3 01GG 00J0 00WS 00HY 01FF 00dH 01F9 00HP OiFV 00XS 6 ] C50 821S G1 3203 C12 C18 8208 C05 821K C90 CCHE 00XV 01EC 00HU0:EXl00H5 . 0 WM 1891 00WT 00JG 01FJ 00H6 01EC 00Y2 00HQ H C08 S218 C07.521R! C61 C99 821D C19 B20G C20 OCXH CiFH 00J3 01FK C0JD 01FY 00HF COWL 00H9 01FR 00HV 01FL$0H4 01FS COXE K ~~ 92iT C17 S20C C06 C29 8207 C09 821F C92 00WR OiF8 00GX b'9[?J_Xjj03[ C27 B21C A02 00GW01FE_003 01ET 00JS 01EY OCWN 00Y4 00XX L C37 B20E ~~ B20N A07 920H CS4 00YSl03 3.g2 00x2 01 2 00HNlM F7}p 01F0 00Ji 01F5 00HL 01F2 n .s C39 C32; B21H 1 82'CP C29 B20F . CSS : 'a = ~ m ~~ 00XP 01ED 00m!01ES(00J501G500HT01ER 00JF 01FQ 00XL CiEli 00XQ N 8210-B211: B21U C01 B2iJ ACS B20R C22 820J i o 20J2 01EK 00XG 01FZ 00JH 01FU 00JE 01G9 00YS 01EF 00JG [ 0 82il CSS 921G C96 B20M C99 '820L C51 B20K 00Y7 00J7 00XN 01FT 00Xu CiFX 20XG 00GY 00XS P R-09 C25 CO2 C3G 00XK 00XC 00HK 00X2 00WW R 1 2 3 4 5 6 ,7 8 9 10 11 12 13 19 15. LEGEND: XXXX' IND CATES FUEL ASSEMBLIES CGNTAINING 9 LEAKIf;G FUEL RODS .4 hs FIGURE 4 .. F. .? *..'.. 8 '

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U V v ~ SIPPING O TA LOG h COUNTING FILE Ili MICR00URIES/HL E: ASSM. CAH TIME T-To. SLOT llo - N0 DATE-TIME (SEC.) LEVEL {MIE.- ). NO. I 131 CS 134 OS 137 ~ ~ - - - - - 1 1 ~ 2/ 2-848 300 3 5600 2.126E-03 1.050E-02 1,.521E-0? 1.601E 0^ 3 ? ?/ P-858 300 3 5610 2.12SE-03 1.08aE-0? j3 3 ?/ P-910 300 3 56?2 2.?14E-03 1.085E-0? 1.597E-0? NJ00J1 1 ?/ P-1046 300 3 5718 9 2.825E-03 1.?62E-0?

1. 353 E-0 ?

NJ01F9 ? ?/ P-1056 300 3 57?8 10 7.9?3E-04 1.088E-03 1,601E-03 NJ00HG 3 ?/ 2-1333 330 3 58n5 11 ?.590E-03 1.3?3E-0? 1.06?E-0?

a

? ?/'?-1355 300 3 5907 2.136E-03 1.117E-02 1.640E-0? NJ00XK 2 P/ 2-1612 300 3 6044 12 2.03IE-03 1.117E-03 1.' 6 4 0 E-0 3 ' !a 1 P/ P-1830 300 3 6182 1.858E-03 1.120E-0? 1.6??E-0? NJ01FD 1 P/ P-1843 300 3 6195 13 1.175E-03 1.1?OE-03 1.6??E-03 {n 2 ?/ P-1851 300 3 62G5 _ 1.989Er03 1.103E-02 1.640E O' NJ00HN 2 P/ ?-1900 300 3 621? 14 6.615E-04 1.103E-03

1. 640E -03

!B 3 P/ P-?008 300 3 6280 1.903E-03 1.104E-02 1.619E-0? FJ00XM 3 2/ ?-?O17 300 3' 6?89 15 3.547E-03

1. ?86E -02; 1. 674 E-0 ?
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.1 P/ P-?005 300 3 6?98 1.796E-03

1. 088E -02 1.589E 09

~~ 'a P/ P-?O33 300 3 6306 ?.01?E-03 1.091E-0? 1'.560E-0?

n 3

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J01FF 1

. / 0 - 3 1 /. 300 3 13n00 1G2 3.47U:-04 1.197E-03

.733E 0-

^ 19 3

1 2/ 8-3?3 300 3

13897 9.0?4E-04 1.175E-02 1.736E-0: 1?B ? ?/ 8-330 300 3 13904 9.33nE-04 1.159E-02 1,690E-0: 10RCO NJ01FF 1 ?/ O-314 300 3 133n8 162 7.1?4E-04 '1.175E-05 1.736E 13 NJ01EQ P- ?/ 8-339 300 3 13915 163 2.771E-04 1,159E-03 1,6903-0 153 2/ 8-347 300 3 13923 9,984E-04 1.202E-02 1.71?E-0 16 NJ01FL 3 2/ 8-358 300 3 13943 164 6.757E-04 1.?0?E-03 1.71?E-0 1a3 1 2/ 8'405 300 3. 13951 1.040S-03 1.192E-02 1.743E-0 ?/ 8-41? 300 3' 13958 1.1?7E 03 1.204E-02 1.76?E-0 'in PG - UJ01EL 1 ?/ 0-4?2 300 3 13960 165 4.989E-04 1.192E-03 1.743E-a ?ral 3 ?/ 8-4?9 300 3 13975 9.511E-04 1.194E-0? 1.7?4E-0: '?' NJG1FG 2 ?/ 0- 445 300 3 13991 166 1.1?7E-04 1.204E-03 1.76?E-O'

U v G sr.md.'m we r COUNTING FILE IK MICR00URIES/IG CE ASSN. CAN TDIE T-To. SLOT ~ --- -. {MIE. ), No. I 131 CS 134 CS 13] (SEC.) LEVEL ),, H0 N.0. DATE.. TIME 73 1 ?/ 8-452 300 3 13993 1.072E-03 1.170E 0? 1.7/?E-O' l5 NJ01FV 3 P/ 8-SPS 300 3 14031 1C 8.359E-04 1.194E-03 1.7?4E-03 3 UJn1FT 1 P/ 8-533 300 3 14043 166 6.619E-04 1.170E-03 1,74?E-03 3B ? P/ 8-541 300 3 14051 9.325E-04 1.183E-0? 1.745E-0? i1 NJ01FX ? 2/ 8-6?4 300 3 14093 169 4.013E 04 1.183E-03 1.745E-03 33 3 ?/ 8-63? 300 3 14101 9.164E-04 1.214E-02 1.719E-O' 1. NJ01FS 3 P/ 8-813 300 3 14?0? 170 6.693E-04 1.?14E-0! 1.719E.03 6n 1 2/ 8-OP0 300 3 14?09 9.?91E-04 1.146E-0? 1.656E 05 on P/ 8-841 3n0 3 14230 1,003E-03 1.174E-0? 1.716E.O." 7 NJ01EG 1 ?/ 8-850 300 3 14238 171 6.065E-04 1.146E-03 1.656E 03 'n NJn1FW ? P/ 8-859 300 4 14?48 17? 3.78?E-0? 4.500E-0? 8.00/E-0: pa 3 ?/ 8-911 300 3 14P60 9.P01E-04 1.189E-0? 1.710E-0! 3 NJ01EH 3 ?/ 8-931 300 3 14?ao 173 7.697E-04 1.189E-03 1.71nE n! iqa 2 2/ 8-943 300 3 14?92 " "1.053E-03 1.155E 02 1.7?1E-0: asn 1 P/ 8-954 3n0 3 1430? 9.643E-04 1.178E-0? 1.750E n: 6 NJ01ED 1 P/ 8-1005 300 -3 14313 174 3.483E-04 1.178E-03 1.750E-O' s/ 8-1014 300 3 143?? 6.921E 04 1.149E-0? 1.69nE-0 ,iin 59 NJ01FH ?- P/ 8-10?2 300 3 14330 175 ?.656E-04 1.155E-03 1.7?1E-O' 54n 1 2/ 8-1030 300 3 14338 1.053E-03 1.171E--0 2 1.697E-0

?

NJ01G1 3 ?/ 8-11?5 300 3. 14391 176 6.353E-04 1.149E-03

1. 68nn.0 55 MJ01EF 1

2/ 8-1134 300 3 14400 177 4.057E-04 1.171E-03 1.697E-0 o .}}

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