ML20237G518

Evaluation of the Qualification of Spert Fuel for Use in NON-POWER Reactors

ML20237G518
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Issue date:	08/31/1987
From:	Office of Nuclear Reactor Regulation
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NUREG-1281, NUDOCS 8708240112
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NUREG-1281 L Evaluation of the  :

Qualification of SPERT Fuel  !

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,, NOTICE Availability of Reference Materials Cited in NRC Publications

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NUREG-1281 Evaluation of the Qualification of SPERT Fuel for Use in Non-Power Reactors M:nuscript Completed: July 1987 Date Published: August 1987 Division of Reactor Projects ill, IV, V and Special Projects Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 as ase, f

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ABSTRACT This report summarizes the U.S. Nuclear Regulatory Commission staff's evaluation of the qualification of the stainless-steel-clad uranium / oxide (1102 ) fuel pins for use in non power reactors.

The fuel pins were originally procured in the 1960's as part of the Special Power Excursion Reactor Test (SPERT) program. Argonne National Laboratory (ANL) examined 600 SPERT fuel pins to verify that the pins were produced according to specification and to assess their present condition. The pins were visually inspected under 6X mag-nification and by X-radiographic, destructive, and metallographic examinations.

Spectrographic and chemical analyses were performed on the U02 fuel. The re-sults of the qualification examinations indicated that the SPERT fuel pins meet the requirements of Phillips Specification No. F-1-SPT and have suffered no physical damage since fabrication. Therefore, the qualification results give reasonable assurance that the SPERT fuel cods are suitable for use in non power reactors provided that the effects of thin-wall defects in the region of the upper end cap and low-density feel pellets are evaluated for the intended operating conditions.

NUREG-1281 iii

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l CONTENTS .

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Page l; ABSTRACT ................................................. ,..... ,, jjj 1 INTRODUCTION ..............................................,,,,,. 1 i

2 QUALIFICATI0i1 0F SPERT FUEL PINS ...............................- 1 j 3 CONCLUSIONS ..................................................... 3 f

APPENDIX A REQUALIFICATION OF SPERT PINS FOR USE IN UNIVERSITY REACTORS i

1 NUREG-1281 y

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1 ' INTRODUCTION Since the U.S. Nuclear Regulatory Commission ruled (51 FR 6514, February 25, 1986) to limit the use of highly enriched fuel in domes U c non power reactors, some universities are considering converting their non power reactors to use stainless-steel-clad, low-enriched, uranium / oxide (U0 2 ) fuel pins. These pins were manufactured in the 1960's for use in the Special Power Excursion Reactor Test (SPERT) program. The serial numbers of the 600 SPERT fuel pins that were examined by Argonne National Laboratory (ANL) cover virtually the entire range of serial numbers of the 9000 pins produced in the qualification program.*

These 600 pins have never been used in a reactor and have been in air-conditioned storage at Purdue University since 1974. However, since there is no record of the storage conditions between 1965 and 1974, it was necessary to verify that the SPERT fuel pins have not been damaged since fab *ication.

The results of the ANL qualification program should be applicable to the entire production run of SPERT pins, except for pins that have been operated in reactors or stored in water or under other conditions significantly different than the storage at Purdue. In these cases, examinations for corrosion of the cladding, both surface and intergranular, may be needed. Additional examination require-ments for pins that have been used in reactors may need to be addressed on a case-by-case basis, depending on operational history.

I R. E. Carter of the U.S. Nuclear Regulatory Commission coordinated the NRC evaluation of ANL's qualification program. R. R. Hobbins of EG&G, Idaho National Engineering Laboratory (INEL) under contract to the NRC, performed the technical review of the ANL report.

2 QUALIFICATION OF SPERT FUEL PINS The SPERT fuel pins originally were procured according to Phillips Specification No. F-1-SPT and Phillips Drawing No. SPT-E-1166. The component materials were required to meet applicable ASTM standards, and extensive acceptance tests and inspections were required for components and the firished pins. All pins were to be inspected for dimensions and surface condition, helium-leak tested to ensure the integrity of the welds (the pins were filled with helium at the time of welding), and gamma scanned to check the fuel zone length and detect the presence of any foreign materials in the fuel zone. However, it appears that all fabrication, inspection, and acceptance records have been discarded.

Therefore, the purpcses of the qualification program were to verify that the pins are those procured to Specification No. F-1-SPT and that the pins have suffered no physical damage since fabrication.

All 600 pins were checked for straightness and visually examined under 6X mag-nification for nicks, scratches, and/or other damage to the cladding surface.

• The ANL report, originally written for the Department of Energy (DOE), was submitted by DOE to the NRC in December 1986 and is included as Appendix A to this report.

NUREG-1281 1

Thirty rods were measured to check diameter and roundness. All pins appeared to be in excellent condition and met the dimensional and surface condition requirements of the specifications, except (possibly) for the diameter in the end cap welds. On the average, this diameter is 0.0041 in. (0.10 mm) larger than the maximum dimension for the pin diameter given on the specification drawing.

Sixty pins were selected randomly among the representative groups of serial numbers for X-radiographic examination of the upper and lower end cap welds.

Defects were found in the upper end cap welds on six pins. The X-radiography examination found the minimum wall thickness in the defects to vary from 0.005 to 0.015 in. (0.13 to 0.38 mm) [ nominal cladding wall thickness is 0.020 in.

(0.51 mm)]. Metallographic examination of one of the weld defects revealed it probably was caused by a gas bubble. Although this particular defect was not connected to the interior volume of the fuel pin, radiographs of other pins showing similar defects indicate that some of the defects are probably connected to the interior volume. These defects would not have been discovered at the time of fabrication because X radiography was not specified.

Thin-wall defects tend to produce stress concentrations at the defective location. The effects of such stress concentrations should be evaluated for the intended use of the fuel pins. Factors such as differential pressure across the wall of the fuel pin during normal operation and under postulated-accident conditions, fuel-handling practices, and corrosion control should be considered. For some uses, it may be advisable to perform 100 percent X-radiographic inspection to eliminate pins with thin wall defects.

In addition to the pin whose weld defect was examined metallographically, the internal pressure, void volume, and fill gas composition were measured in five pins chosen for destructive examination. All six pins had a positive pressure of fill gas, ranging from 0.6 and 3.3 psig. For comparison, the specification for fill gas was 1 psig of helium. The fill gas was predominantly helium, but a sizable amount (up to 16%) of hydrogen also was found. Trace amounts of water vapor and nitrogen were measured, although one pin had about 1 percent nitrogen and a few milligrams of water. The hydrogen is responsible for the overpressure in the pins. The hydrogen probably resulted from the reaction of water vapor with the fuel and the cladding. Less than 2 mg of water is re-quired to produce the amounts of hydrogen measured in the fill gas. The specification allowed up to 75 ppm water in a fuel pin, which corresponds to about 60 mg. The presence of hydrogen in the fill gas has no deleterious ef-fect because its thermal conductivity is nearly the same as that of helium.

The other minor deviations in composition and pressure relative to the specifi-cations have no significance for the use of these pins in non power reactors.

The entire stack of 60 fuel pellets was examined from two pins, and the top 6 pellets were examined from two other pins. With three exceptions, all pellets examined had only minor surface chips and were judged to meet the pellet surface-condition requirements of Specification F-1-SPT. Three pellets from one pin each had a significant piece (0.2, 0.2, and 0.7 g, respectively) spalled off the entire length of the pellet. The missing material was contained in loose fragments and powder collected af ter all the pellets were removed from the pin. The length, diameter, and weight of each of the 132 pellets removed from the four pins were measured and the pellet density was calculated based on solid, right, cylindrical geometry. Excluding the 3 chipped pellets, 16 pellets NUREG-1281 2

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were found with densities outside the specification of 9.97 g/cm 3 minimum den- l sity and 10.1 g/cm3 deviation from the mean. Four pellets at the top of one pin were found with a density of about 9.52 g/cm3 . Excluding these four pellets and the three chipped pellets, the mean pellet density was 10.078 1 0.055 g/cm3 .

Twelve pellets in one rod had densities more than 0.1 g/cm3 above the mean den-sity, the largest of which was 0.15 g/cm3 higher than the mean. With 3 the excep-

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tion of the four pellets with a relatively low density (9.52 g/cm ), deviations  !

of this magnitude from the specification for pellet density have no safety l significance for the use of the SPERT fuel in non power react rs. f l

It is assumed that the pin with the four low-density pellets at the top of the l fuel stack was purposely loaded in this manner and that the use of pellets with j nonconforming densities was properly approved. Depending on the reactor power levels, low-density fuel pellets tend to run at higher temperatures, are subject  ;

to densification, enhanced fission product release, and can promote exagg g ted cladding collapsu and pellet-cladding mechanical interaction. The prestni.u of low-density fuel pellets in other fuel pins and at other stack locations cannot be ruled out with the current limited data base on fuel pellet density. The effects of low-density pellets should be evaluated for the intended use. Addi-tional pellet density measurements may be needed to ensure that low-density pellets are an unlikely occurrence.

Three pellets, one from each of three rods, were sectioned and examined metal-lographically. The microstructure were similar in the three pellets and were relatively fine grained (5 to 10 pm) UO2 with some porosity and, possibly, some U074 present. The structures were fairly typical of as-fabricated, unirradiated U02 fuel.

Analyses of uranium isotopes, total uranium, and impurities in the U02 fuel were performed. Spectrographic analysis for 20 elements revealed an impurity content of <185 ppm, which is only about 5 percent of the specification level; however, a number of possible significant elements were not analyzed. An upper limit value of the oxygen / uranium ratio of 2.04 was calculated, based on the measured uranium content, measured impurity content, and the assumption that the remaining sample weight must be oxygen. An additional impurity content of 1200 ppm, which would be well within the specification, would result in an oxygen / uranium ratio of 2.02, which is the specified upper-bound limit.

Metallographic examination of the fuel cladding showed the cladding to be within specification for wall thickness; to be seamless, as specified; and to have a microstructure typical of 304 stainless steel with some evidence of normal car-bide precipitation, but no evidence of intergranular attack or corrosion from either the inside or outside surfaces. Chemical analysis showed that the metallic constituents of the stainless steel were all within the specification with the exception of cobalt, which was 0.084 wt% compared to a maximum of 0.05 wt% allowed by the specifications.

3 CONCLUSIONS The staff concludes that the ANL examinations give reasonable assurance that the SPERT fuel pins were fabricated in accordance with Phillips Specification No. F-1-SPT and that they substantially met the acceptance criteria when fabri-cated. Furthermore, the examinations show that storage for more than 20 years has not caused deterioration to cladding or pellets that would significantly NUREG-1281 3

affect safety in the use of these fuel pins in low power reactors. Therefore, these fuel pins are acceptable for use if the operating conditions do not cause undue stresses in the cladding. At high reactor power levels, there might be some concern because of the presence of thin-wall defects and low-density fuel pellets, but these factors should be evaluated for the intended fuel use on a case-by-case basis. The deviations from such specifications as the internal pressure of the pin and fuel oxygen / uranium ratio are minor and without sig-nificance from a safety standpoint. The absence of intergranular attack or l corrosion of the stainless-steel cladding during storage and the basic confor- I mance of the stainless-steel cladding to the specifications, suggest that cor- I rosion is an unlikely failure mechanism provided there is reasonable water chemistry control,  !

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1 NUREG-1281 4 l

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Distribution Category:

i Nuclear Converter Reactor Fuel Cycle Technology: Base Technology (UC-83)

ANL/RERTR/IM-8 I

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ARGONNE NATIONAL LABORATORY 9700 South Cass Avenue Argonne, Illinois 60439

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l REQUALIFICATION OF SPERT PINS FOR USE IN UNIVERSITY REACTORS by J. L. Snelgrove, R. F. Domagala, and L. R. Dates L RERTR Program December 1986 NUREG-1281 APP A

l Requalification of SPERT Pins for Use in University Reactors i

J. L. Snelgrove, R. F. Domagala, and L. R. Dates RERTR Program Argonne National Laboratory  ;

Argonne, Illinois 60439 l i

ABSTRACT A series of nondestructive and destructive examinations has been per-formed on a representative sample of stainless steel-clad UO2 fuel pins pro-cured in the early-to-mid 1960's for the SPERT program. These examinations were undertaken in order to requalify the SPERT pins for use in converting university research reactors from the use of highly enriched uranium to the use of low-enriched uranium. The requalification program included visual and dimensional inspections of fuel pins and fuel pellets, radiographic inspec-tions of welds, fill gas analyses, and chemical and spectrographic analyses of fuel and cladding materials. In general all attributes tested were within or very close to specified values, although some weld defects not covered by the original specifications were found.

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i NUREG-1281 APP A A-iii

Table of Contents Page

1. INTRODUCTION ......................................................... I

2. VISUAL AND MECHANICAL INSPECTIONS .................................... 2

3. EXAMINATION OF WELDS ... ............................................. 2

4. EXAMINATION OF FUEL PIN MATERIALS .................................... 5 4.1 Fill Gas Analysis ............................................... 5 4.2 00 2 Pellet Condition and Density ................................ 9 4.3 Metallographic Examination of UO2 Pellet ........................ 16 4.4 Metallographic Examination of 304 SS Cladding (Tubing) . . . . . . . . .. 16 4.5 Chemical and Spectrographic Analysis of 304 SS Cladding ......... 16 4.6 Uranium Analysis of UO2 Pellet .................................. 19 l 4.7 Spectrographic Analysis for Impurities in UO2 Pellet ............ 19

5.

SUMMARY

.............................................................. 19 REFERENCE ........................................................... 21 ,

I APPENDICES ,

A. Phillips Specification No. F-1-SPT and Drawing No. SPT-E-1166 ... 23 B. Requalification Plan for SPERT Pins .............................. 39 C. Inspection Data Sheets and Reports l 1

C.1 Fuel Pin Dimensional Inspection Data Sheets . . . . . . . . . . . . . . . . 43 l l

C.2 Weld Radiographic Inspection Reports ........................ 46  !

I C.3 Fill Gas Analysis Reports .................................. 58 I C.4 Fuel Pellet Inspection Data Sheets .......................... 63 ,

C.5 Cladding Chemical and Spectrographic Analysis Reports ....... 74 C.6 Fuel Pellat Chemical and Spectrographic Analysis Reports .... 77 ,

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NUREG-1281 APP A A-v 1

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List of Figures

.P, age, I

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1. Etched Section of Upper End Cap Weld'of Pin No. 7097 '

Showing Defect ................................. .................. 6

2. Photograph of Defective Pellet No. 20 and Typical Pellet No. 6 f rom Pin No. 8321 ................................................ 10.

3. Typical Microstructure of UO2 in Fuel Pellets ..................... 17

4. Typical Microstructure of 304 SS C1 adding.......................... 17 l 1

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List of Tables I. Distribution of SPERT Pin Serial Numbers .......................... 3 II. Se rial Numbe rs of Pins Radiographer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 i

III. Pins with Defects at Upper Weld ................................... 4 IV. Volume and Pressure of Fill Gas in SPERT Pins ...................... 7 V. Components of Fill Gas in SPERT Pins ......................t....... 8 VI.~ Dimensions and Weights of Pellets in Pin No. 2619 . . . . . . . . . . . . . . . . . 11 VII. Dimensions and Weights of Pellets in Pin No. 8321 ................ 13 VIII. Dimensions and Weights of Top Six Pellets in Pin No. 0396 ........ 15 IX. Dimensions and Weights of Top Six Pellets in Pin No. 7097 ........ 15 X. Results of Analysis for Major Constituents of Cladding .. .. . . . . . . . 18 XI. Results of UO 2 Analyses ........................................... 20 1

NUREG-1281 APP A A-vi

Requalification of SPERT Pins for Use in University Reactors

1. INTRODUCTION In response to the U.S. Nuclear Regulatory Commission rule limiting the use of highly enriched uranium in domestic non-power reactors, several univer-sities are considering converting their reactors to use stainless steel-clad, low-enriched UO2 pins produced in the early-to-mid 1960's for use in the Special Power Excursion Reactor Test (SPERT) program.

More than 9000 SPERT fuel pins were procured according to Phillips Speci-fication No. F-1-SPT, which incorporates Phillips Drawing No. SPT-E-1166. The specification and part of the drawing are reproduced in Appendix A. The component materials were required to meet applicable ASTM standards, and extensive tests and inspections were required for components and the finished pins. In particular, all finished pins were inspected for dimensions and surface condition, helium leak tested to assure the integrity of the welds (the pins were filled with helium at time of welding), and gamma-scanned to check the fuel zone length and to detect the presence of foreign materials in the fuel zone. In the intervening years it appears that all f abrication, inspection, and acceptance documentation has been discarded. Since it is known that the pins were accepted by Phillips, it is presumed that they met the requirements of the specifications, except, possibly, in some minor ways.

In the absence of the original records and because it is impossible to ascertain all handling and storage conditions of the pins, it is necessary to requalify the pins for their proposed use in selected university reactors.

The basis for the requalification program is the presumption that all pins originally met the requirements of the specifications. The requalification program is intended to verify that the pins are indeed those procured to Spec-ification No. F-1-SPT and that the pins have suffered no physical damage since fabrication.

The original requalification plan is shown in Appendix B. It is an expanded version of a plan suggested by R. R. Hobbins, EG6G Idaho, and trans-mitted verbally to ANL by K. R. Brown, EG&G Idaho. The nondestructive exami-nations were intended to verify that no pin has suffered physical damage. The destructive examinations were intended primarily to verify that the pins being inspected did indeed conform to Specification No. F-1-SPT. Sample sizes were consistent with standard sampling procedures. As the inspections progressed some minor additions were made to the inspection plan when needed to adequately characterize the condition of the pins.

The 600 pins which were inspected came from Purdue University (West Lafayette, IN), where they had been stored in an air-conditioned environment since their receipt in 1973 or 1974. These particular pins are intended for use in the Critical Experiment Facility at Rensselaer Polytechnic Institute (Troy, NY). The inspection results should be more generally applicable, however, since the pins inspected cover virtually the entire range of serial numbers of pins from the production run.

NUREG-1281 APP A A-1

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i The visual and mechanical inspections of the fuel pins were performed by the Mechanical Inspection group of the AhL Support Services Division (SSD),

and the group of radiographic SSD. inspections were performed by the Nondestructive Testing {

Meta 11ographic examinations and density determinations were l

performed Division.

by the RERTR group in the ANL Haterials and Components Technology, All other destructive examinations were performed by the ANL Analytical Chemistry Laboratory (ACL). i This report presents only the results of the requalification inspections.

An evaluation of the meaning of the inspection results in relation to the intended use of the fuel pins was not part of the task assigned to ANL.  !

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2. VISUAL AND MECHANICAL INSPECTIONS The 600 SPERT pins arrived at ANL from Purdue University on September 9, 1986, and inspection according to the plan shown in Appendix B began on September 10.

The pins were distributed over the serial number range 0001 to i l

9002 and, therefore, are believed to cover the whole production run. The dis-tribution of serial numbers is shown in Table I. It should be noted that two pins cisplayed five-digit serial numbers--00013 and 00040. It is assumed that an extra zero was erroneously added, and these pins have been listed as Nos. 0013 and 0040.

All 600 pins were checked for straightness and were examined under 6X magnification for nicks, scratches, and/or other damage to the cladding sur-face. Thirty pins were measured to check diameter and roundness. All pins appeared to be in excellent condition and met the dimensional and surf ace con-dition requirements of the specifications except, possibly, for the diameter in the weld area which, on the average, is 0.0070 in. (0.18 mm) larger than the maximum dimension given on Drawing No. SPT-E-1166. It should be noted, however, that the maximum diameter shown on the drawing is that of the tube.

There is no indication on the drawing or in the specification that this dimen-sion was intended to apply to the weld. The measured cladding tubing outer diameter was 0.4656 1 0.0007 is. (11.83

• 0.02 mm), and the measured veld outer diameter was 0.4726 0.0015 in. (12.00 1 0.04 mm). Copies of the original dimensional inspection data sheets are contained in Appendix C.1.

3. EXAMINATION OF WELDS Sixty pins, whose serial numbers are listed in Table II, were selected at random from within the groups shown in Tatle I for X-radiographic examination of the welds. Each of the two welds on each pin was radiographer at 0 and 90 degrees. A third radiograph was taken at an intermediate angle when needed to determine the extent of suspicious areas. A stainless steel compensation block was used to assure a constant thickness of material across the diameter of the pin. Regions of decreased density, indicative of bubble-type defects, were found at the upper end cap weld of each of six pins. The minimum thick-ness of weld material between the def ect and the outside environment and the size of the defect for three of the pins have been estimated from measurements on the radiographs. The results are listed in Table III. Subsequently, the upper welds of the five pins chosen for destructive examination (Nos. 0396, 1

1 NUREG-1281 APP A A-2 1

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Table I. Distribution of SPERT Pin Serial Numbers Serial Number No. of Pins Range No. of Pins Radiographer 0001 - 0999 148 15 1000 - 1999 97 10 2000 - 2999 73 7 3000 - 3999 18 j e I

4000 - 4999 52 > 9 5000 - 5999 16s 6000 - 6999 15l 7000 - 7999 90f 8000 - 9002 91 9 Serial Number Pin for Destr.

Range No. of Pins Examination 0001 - 0632 120 0396 0633 - 1992 120 1382 1993 - 4467 120 2619 4468 - 7195 120 6921 7196 - 9002 120 8321 NUREG-1281 APP A A-3

Table II. Serial Numbers of Pins Radiographer 0007 0008 0072 0075 0081 0150 0396a 0437 0529 0568 0583 0739 0837 0866 0882 0901 1192 1379 1382a 1385 1388 1398 1499 1564 1571 1987 1998 2018 2032 2064 2074 2520 2619a 2625 2892 4333 4337 4357 4401 4408 4458 4493 5178 5746 6720 6921a 7080 7088 7093 7097 7162 7167 7182 7188 7198 8050 8195 8257 8321a 8399 8449 8533 8536 8542 8682 aUpper end cap weld only, following disassembly of pin. t Table III. Pins with Defects at Upper Weld Minimum Wall Approx. Defect Size,a in.

Pin Number Thickness,a in. Width Length 0583 0.015 b b 0882 0.005 0.025 >0.440 l 1571 0.010 b b 4401 0.007 0.020 >0.445 4408 0.015 b b 7097 0.005 0.020 0.075 aAs determined f rom the radiographs.

b Not determined.

NUREG-1281 APP A A-4

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1382, 2619, 6921, and 8321) were radiographer. No defects were found. Copies-of the radiographic inspection reports are contained in Appendix C.2.

In order to better characterize the nature of the defects in the upper end cap welds, pin No.-7097 was chosen for metallographic. processing of a transverse section of the' upper weld. The pin top was sectioned at the lower end of'the weld; the location of the defect, determined from the radiograph, was marked in ink on the piece; and the piece was mounted in an acrylic (clear) polymer for processing. The sample was carefully ground, with inspec-tion at the end of each minute, until the first evidence of the defect was ob-served--after ~90 minutes of grinding and the removal of ~0.040 in. (~1.02 mm) of solid material. Af ter photographing the defect at this stage of proces-sing, the grinding was continued for an additional 0.001 in. (0.03 mm), photo-graphs were taken, and the sample was polished until a total of 0.042 in.

(1.07 mm) [ believed accurate to *0.0005 in. (*0.01 mm)] of material had been removed. Examination of'the sample during the polishing process indicated that the maximum size of the defect had been reached. . Following more photo-  ;

graphs the sample was etched, and the etructure was recorded.

Figure 1 shows the etched sample. The weld material was typical of a cast (and not heat-treated) material, and the base (end cap) had a structure typical of 304 SS. It appears that the defect resulted from a gas bubble, based on its shape. Measurements taken from the photograph of Fig. I show the minimum thickness of weld material to be ~0.005 in. (~0.13 mm), consistent with the data from the radiograph. Although the defect in pin No. 7097 was located near the center of the weld zone and was not connected to the interior volume of the pin, a reexamination of radiographs of the other pins showing similar defects indicated that some defects are probably connected to the interior volume.

This type of defect, discovered through radiography, would not have been detected at the time of fabrication unie a the minimum thickness of weld mate-rial were so small as to allow He to pass through. The 100% He leak test required by Specification No. F-1-SPT should have eliminated all leakers. It was also required that a sound metallurgical bond be formed between the tube i and the end caps. There is no evidence that this requirement was not met.

4. EXAMINATION OF FUEL PIN MATERIALS 4.1 Fill Gas Analysis Five pins, as indicated in Table I, were initially chosen for destructive examination. The pressure and species of fill gas and the void volume in each pin were determined by the ACL. A sixth pin (No. 7097), which had an indi-cated thin wall in the weld area as discussed above, was subsequently submit-ted for fill gas analysis. The results are given in Tables IV and V, which ,

are taken from the ACL reports in Appendix C.3. All of the pins had a posi-tive pressure of fill gas, in all but one case greater than the maximum (1 psig) given in the specification. The fill gas was predominantly He, but a sizable amount of H2 was also found. The H2 concentration decreases as the serial number of the pin increases (presumably as the fabric'ation progressed).

Trace amounts of water were detected in the gas of all of the pins, but the gas from pin No. 8321 contained as much as a few milligrams of water. (Note NUREG-1281 APP A A-5

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that the fuel in a pin could contain up to 60 mg of water and not exceed the allowable moisture content, 75 ppm.) The presence of N2 in Pi n No. 8321 sug-gests that the fill gas was contaminated at the time of welding. The other f

unique feature of pin No. 8321 is its considerably reduced void volume rela-tive to the other pins. Thegeometricvoidvolumeoutsidethefuegpelletsin apin(baseduponthedimensionsofthedrawing}"isvoid" 6.65 per

• 0.75 cm . The fuel pellets themselves are only ~92% dense (~6.5 cm pin). The fact that the measured void volumes of the pins are larger than the geometric void outside the fuel pellets indicates that the fuel pellets were partially permeable to the He backfill gas. It appears, therefore, that at least some of the pellets in pin No. 8321 were less permeable to He than the average pellet, possibly because of the extra water present in this pin.

4.2 UO2 Pellet Condition and Density Following completion of the fill gas analyses, the tops were cut from the six pins in the plenum (spring) region. All pellets were removed f rom pins Nos. 2619 and 8321; the top six pellets were removed from pins Nos. 0396 and 7097. The fuel pellets were serially identified in order of their removal, with the number 1 being assigned to the topmost pellet. All of the pellets removed, with three exceptions, had only minor surf ace chips and were judged

( to meet the pellet surf ace condition requirements of specification F-1-SPT.

I Pellets Nos. 4, 5, and 20 from pin No. 8321 each had a significant piece

(~0.2, 0.2, and 0.7 g, respectively) spalled of f the entire length of the pellet. The missing material was contained in the loose fragments and powder collected af ter all pellets were removed f rom the pin. Figure 2 shows pellet No. 20 and a typical pellet (No. 6). It is extremely unlikely that the damage occurred to pellets Nos. 4, 5, and 20 during disassembly of the pin; it is I impossible to determine if the damage occurred during assembly or during sub-sequent handling.

The length of each of the pellets removed was measured twice with a cali-brated micrometer, and the diameter of each pellet was measured in three loca-tions with the same micrometer. In addition each of the pellets was weighed.

It should be pointed out that the extent of measurements of pellets was con-siderably greater than required by the original requalification inspection plan because of the anomalous results for pin No. 8321 discussed in the previ-ous section. The results of these measurements are given in Tables VI-IX.

Copies of the original inspection data sheets are contained in Appendix C.4.

Accuracleo are estimated to be i0.0002 in. (10.005 mm) for dimensional mea-surements 'and i0.002 g for weight measurements. The active fuel length and the total fuel weight for pins Nos. 2619 and 8321 were well within specifica-tions. The calculated fuel pellet volumes and densities assume a cylindrical pellet with no chips; therefore, actual densities are slightly underestimated.

Pellets Nos. 1-4 from pin No. 2619 are very similar and have significantly lower weights and densities than the other 128 pellets examined. It is assumed that the pin was purposely loaded in this manner and that the use of pellets with nonconforming densities was properly approved. Excluding the four low-density pellets in pin No. 2619 and broken pellets Nos. 4, 5, and 20 in pin No. 8321, the average pellet density was 10.078 i 0.055 g/cm . The weights and densities of the pellets in pin No. 8321 were generally higher than those of the pellets in the other pins. The densities of 12 of the pel-lets in gin No 8321 exceed the average density by more than the allowed 0.1 g/cm . All other pellets, except the four low-density pellets discussed NUREG-1281 APP A A-9

Fig. 2. Photograph of Defective Pellet No. 20 (Left) and Typical Pellet No. 6 (Right) from Pin No. 8321.

[Each Scale Div. = 0.5 mm (0.020 in.)]

NUREG-1281 APP A A-10 l

l I

I Table VI. Dimensions and Weights of Pellets in Pin No. 2619 Pellet Wt., Ave. Diam., Ave. Len., Vog., Densigy, No. g in. in. em g/cm 1 13.150 0.4200 0.6093 1.3832 9.507 2 13.234 0.4200 0.6119 1.3892 9.526 3 13.164 0.4198 0.6086 1.3802 9.538 4 13.211 0.4199 0.6112 1.3870 9.525 5 13.656 0.4202 0.5976 1.3579 10.056 6 13.730 0.4202 0.5995 1.3624 10.078 7 13.678 0.4202 0.5995 1.3620 10.042 8 13.731 0.4200 0.5985 1.3588 10.105 9 13.730 0.4200 0.5971 1.3555 10.129 10 13.664 0.4200 0.5986 1.3590 10.054 11 13.641 0.4200 0.5981 1.3578 10.047 12 13.787 0.4200 0.6021 1.3669 10.087 13 13.653 0.4200 0.5993 1.3606 10.034 14 13.767 0.4202 0.5991 1.3612 10.114 15 13.709 0.4200 0.5999 1.3621 10.065 16 13.692 0.4202 0.5991 1.3611 10.059  !

17 13.624 0.4202 0.5981 1.3591 10.025 18 13.710 0.4202 0.5976 1.3578 10.097 19 13.697 0.4202 0.5977 1.3582 10.085 20 13.641 0.4202 0.5983 1.3595 10.034 1 21 13.693 0.4202 0.6001 1.3636 10.042 22 13.612 0.4200 0.5969 1.3550 10.045 23 13.609 0.4200 0.5981 1.3579 10.022 24 13.820 0.4202 0.6014 1.3665 10.114 25 13.699 0.4202 0.5983 1.3593 10.078 26 13.717 0.4201 0.5975 1.3568 10.110 27 13.568 0.4201 0.5966 1.3549 10.014 28 13.654 0.4201 0.5978 1.3580 10.055 l l 29 13.711 0.4201 0.6007 1.3645 10.048 30 13.767 0.4201 0.6020 1.3675 10.067 l 31 13.668 0.4201 0.5988 1.3601 10.049 32 13.626 0.4201 0.5977 1.3577 10.036 33 13.719 0.4201 0.6003 1.3634 10.062 34 13.681 0.4201 0.5986 1.3596 10.063 35 13 607 0.4201 0.5972 1.3566 10.030 36 13.655 0.4201 0.5981 1.3583 10.053 37 13.729 0.4201 0.6007 1.3642 10.064 38 13.693 0.4200 0.5991 1.3600 10.068 39 13.650 0.4200 0.5987 1.3595 10.041 40 13.595 0.4200 0.5973 1.3560 10.026 41 13.586 0.4200 0.5965 1.3541 10.033 42 13.681 0.4200 0.5982 1.3579 10.075 43 13.635 0.4200 0.5976 1.3568 10.050 44 13.549 0.4200 0.5957 1.3524 10.018 45 13.642 0.4199 0.5991 1.3597 10.033 NUREG-1281 APP A A-11 l

1 8

Table VI. Dimensions and Weights of Pellets in Pin 'No. 2619 (Cont.)

Pellet Wt., Ave. Diam., Ave. Len., Density, No. Vog.,

g: in. in. cm g/cm3 46 13.630 0.4199 '0.5973 1.3552 10.057

'~

47 13.580 0.4196 0.5977 1.3543 10.027 48 13 607 0.4199 0.5971 1.3549 10.043

-49 13 650 0.4200 0.5977 1.3570 10.059 50 13.627 0.4200 0.6008 1.3637 9.993 51 13.608 0.4201 0.5986 1.3598 10.008 52 13.627 0.4193 0.6023- 1.'3628 10.000 4 53 13.719 0.4200 0.6011 1.3645 10.054 l-54- 13.607 0.4200 0.5970 1.3554 10.039 l 55 13 670 0.4201 0.6004 1.3634 10.026 56 13.662 0.4200 0.5993 1.3607 10.040 57 13.627 0.4201 0.5974 1.3567 10.044 58 13.736 0.4201 0.6001 1.3629 10.079 59 13 689 )

0.4201 0.6002 1.3630 10.043

^

60 13 597 0.4200 0.5970 1.3553 10.033 Sum 818.071a 35.9664 Average 13.666b. 0.4200 0.5994 1.3612 10.053 b Std. Dev. 0.057 b 0.0001 0.0033 0.0073 0.029b aNot including loose powder. and fragments weighing 0.09 g removed from tube.

b Excluding pellets Nos. 1, 2,13, and 4.

l i

i NUREG-1281 APP A A-12

l Table VII. Dimensions and Weights of Pellets in Pin No. 8321 ,

Pellet Wt., Ave. Diam., Ave. Len.,

Vog., Densigy, No. g in. in. em g/cm 1 13.635 0.4200 0.5963 1.3538 10.072 2 13.663 0.4200 0.5959 1.3529 10.099 l 3 13.637 0.4200 0.5956 1.3521 10.086 4 13.476 0.4200 0.5992 1.3606 9.904 5 13.425 0.4200 0.5986 1.3590 9.878 6 13.615 0.4199 0.5968 1.3540 10.056 7 13.582 0.4200 0.5962 1.3536 10.034 8 13.697 0.4200 0.5985 1.3586 10.082 9 13.601 0.4199 0.5961 1.3525 10.056 10 13.731 0.4199 0.5994 1.3603 10.094 11 13.604 0.4200 0.5973 1.3560 10.033 12 13.676 0.4199 0.5977 1.3563 10.083 13 13.990 0.4199 0.6043 1.3711 10.204 14 13.732 0.4197 0.6006 1.3618 10.083 15 13.836 0.4197 0.6014 1.3635 10.147 16 13.776 0.4198 0.6005 1.3620 10.114 17 13.834 0.4199 0.6019 1.3655 10.131 18 13.712 0.4198 0.5982 1.3568 10.106 19 13.799 0.4199 0.6009 1.3637 10.119 20 13.058 0.4200 0.6029 1.3685 9.542 21 13.775 0.4199 0.6018 1s3655 10.088 22 14.031 0.4199 0.6059 1.3750 10.204 23 13.983 0.4199 0.6046 1.3720 10.192 24 13.928 0.4199 0.6025 1.3674 10.185 25 13.844 0.4199 0.6017 1.3654 10.139 26 13.713 0.4199 0.5984 1.3581 10.097 27 13.724 0.4199 0.5986 1.3580 10.106 28 13.963 0.4199 0.6038 1.3702 10.191 29 13.746 0.4199 0.5998 1.3611 10.099 30 13.730 0.4200 0.5995 1.3607 10.090 31 13.690 0.4200 0.5976 1.3566 10.091 32 13.557 0.4200 0.5952 1.3513 10.033 33 13.662 0.4200 0.5983 1.3583 10.058 34 13.524 0.4200 0.5943 1.3491 10.024 35 13.639 0.4200 0.6007 1.3637 10.002 36 13.579 0.4200 0.5945 1.3496 10.062 37 13.535 0.4200 0.5947 1.3501 10.026 38 13.580 0.4200 0.5950 1.3508 10.053 39 13.627 0.4200 0.5961 1.3533 10.069 40 13.699 0.4198 0.5986 1.3578 10.089 41 14.026 0.-4197 0.6064 1.3748 10.202 42 13.817 0.4197 0.6013 1.3634 10.134 43 13.922 0.4198 0.6033 1.3683 10.175 44 13.719 0.4197 0.5997 1.3595 10.092 45 14.008 0.4199 0.6056 1.3739 10.196 NUREG-1281 APP A A-13

Table VII. Dimensions and Weights of Pellets in Pin No. 8321 (Cont.)

Pellet Wt., Ave. Diam., Ave. Len.,

Vog., Densigy, No. g in. in. em g/cm 46 13.993 0.4198 0.6048 1.3718 10.201 47 13.845 0.4198 0.6012 1.3635 10.154 48 14.040 0.4200 0.6061 1.3760 10.203 49 13.683 0.4200 0.5983 1.3580 10.076 1

50 13.839 0.4200 0.6032 1.3691 10.108 51 13.910 0.4200 0.6021 1.3666 10.178 l

52 14.026 0.4199 0.6054 1.3737 10.210 53 13.739 0.4199 0.5989 1.3587 10.112 54 13.809 0.4198 0.6014 1.3642 10.123 55 14.040 0.4198 0.6049 1.3722 10.231 56 13.686 0.4198 0.5979 1.3562 10.091 i 57 13.690 0.4198 0.5980 1.3560 10.096 l 58 13.741 0.4197 0.5987 1.3572 10.125 l 59 13.997 0.4198 0.6057 1.3738 10.188 l 60 13.647 0.4199 0.5969 1.3545 10.075 Sum 824.785a 35.9982 Average 13.769 b 0.4199 0.6000 1.3615 10.113 b 0.150 b 0.057 b Std. Dev. 0.0001 0.0034 0.0074 aNot including loose powder and fragments weighing 1.21 g removed from tube. l b

Excluding pellets Nos. 4, 5, and 20. 1 l

l 1

NUREG-1281 APP A A-14

1 I)

Table VIII. Dimensions and Weights of Top Six Pellets in Pin No. 0396 Pellet Wt., Ave. Diam., Ave. Len.,

No. g Vog., Densigy, in. in. em ,_ g/cm 1 13.682 0.4198 0.6009 1.3630 10.038 2 13.694 0.4198 0.6012 1.3638 10.041 3 13.704 0.4198 0.6020 1.3651 10.039 4 13.708 0.4198 0.6016 1.3645 10.046 5 13.595 0.4199 0.5968 1.3541 10.040 6 13.707 0.4198 0.6025 1.3666 10.030 Sum 82.090 3.6049 Average 13.682 0.4198 0.6008 1.3629 10.039 Std. Dev. 0.044 0.0000 0.0021 0.0045 0.005 Table IX. Dimensions and Weights of Top Six Pellets in Pin No. 7097 Pellet Wt., Ave. Diam., Ave. Len.,

No. g Vog., Densigy, in. __

in. cm g/cm 1 13.719 0.4203 0.6030 1.3710 10.007 2 13.729 0.4203 0.6038 1.3728 10.001 3 13.679 0.4204 0.6010 1.3667 10.008 4 13.743 0.4200 0.6021 1.3669 10.054 5 13.693 0.4204 0.6010 1.3670 10.017 6 13.710 0.4204 0.6034 1.3724 9.990 Sum 82.273 3.6141 Average 13.712 0.4203 0.6024 1.3695 10.013 Std. Dev. 0.023 0.0002 0.0012 0.0029 0.022 NUREG-1281 APP A A-15

above, meet this criterion. Although the sample size is too small to deter-mine if the densities of pellets from pin No. 8321 are anomalous, the fact that this pin exhibits other anomalies makes one suspicious. Excluding all of

{

I the'pelletsinpinNo.8321andthefourlow-densigypelletsinpinNo.2619, the. average pellet density was 10.048 i 0.029 g/cm 4.3 Meta 11ographic Examination of UO2 ' Pellet Three pellets (pin No. 0396, pellet No. 6; pin No. 2619, pellet No. 30; and pin No. 8321, pellet No. 2) were selected for metallographic examination and were cut. perpendicular to the long axis at approximately the midpoint.

The samples were mounted with the cut surface in the plane of polish and were processed for metallographic examination. The samples were etched to bring out the microstructure of the pellets. A typical microstructure is shown in Fig. 3. In brief, the structures of the three pellets were similar and con-sist of a very fine grain size of UO2 with some porosity evident and the pos-sible existence of some U 490 , which cannot be positively identified using only the light m literature {croscope. The structures are consistent with those shown in the 4.4 Meta 11ographic Examination of 304 SS Cladding (Tubing)

Small pieces of the 304 SS cladding (tubing) were cut perpendicularly to the long axis from each of the pins from which the UO2 pellets were taken for metallographic examination. The pieces were taken from near the top of pins Nos. 0396 and 8321 and from near the center of pin No. 2619. The samples were mounted in a clear acrylic and ground on successively finer abrasive grit papers. After the 600-grit treatment, photographs were taken at exactly 100X so that accurate measurements of the tube wall thickness could be made. Wall thickness measurements were made at 90-degree increments around the circumfer-ence of the tube, and all thicknesses were well within the limits of 0.020

• 0.001 in. (0.51

• 0.3 mm) given in Drawing No. SPT-E-1166.

The samples were then polished and etched. The etched samples displayed, without exception, a typical 304 SS microstructure. Some evidence of normal ,

carbi6e precipitation was visible but no evidence whatever of intergranular '

attack or corrosion from the inside or the outside of any sample was observed.

No evidence of any weld it: the tubing was observed, confirming the tubing to be seamless. A typical sample of the tubing microstructure is shown in Fig. 4.

4.5 Chemical and Spectrographic Analysis of 304 SS Cladding Approximately six grams of 304 SS cut from near the center of the clad-ding of pin No. 2619 was submitted to the ACL for chemical analysis. The results are given in Table X. Copies of the original ACL reports are contained in Appendix C.S. All data are in accord with the original specifications as well as with those of ASTM A269(-74) except for the Co level. The original specification called for 0.05 wt% Co maximum; the first analysis showed 0.11 wt% Co while a careful reanalysis to eliminate interference by other elements yielded a value of 0.084 wt%. Because of the cost and uncertainties associated with such analyses, no determination of boron content was made.

NUREG-1281 APP A A-16

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Fig. 3. Typical Microstructure of UO2 in Fuel Pellets.

(From Pin No. 0396, Pellet No. 6.)

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(From Near Center of Pin No. 2619.)

NUREG-1281 APP A A-17

Table X. Results of Analysis for Major Constituents of Cladding l

Quantity,

! Constituent wt%a Co 0.084 Cr 18.60 Cu 0.17 l Fe 68.9 l

l Mn 1.06 Mo 0.20 Ni 9.56 aEstimated accuracy: Co 10% of amount present; Others 5% of amount present.

i' Note also that no analysis was conducted for C or Si, with l maximum allowed quantities of 0.08% and 0.75%, respectively.

1 NUREG-1281 APP A A-18

4.6 Uranium Analysis of UO2 Pellet Samples from each of five pine were submitted to the ACL for U isotopic and total U content analysis. The results are shown in Table XI. A copy of the original ACL report is contained in Appendix C.6. Included in the table are calculated values of the oxygen-to-uranium (0/U) atom ratio based upon the measured U and impurity levels. The calculated O/U ratios are upper limits  !

since analyses were not made for all impurities. An additional impurity con-tent of only 0.12 wt% would reduce the calculated average 0/U ratio to less than 2.02, as required by the specification.

4.7 Spectrographic Analysis for Impurities in UO2 Pellet A portion of pellet No. 30 from pin No. 2619 was subjected to a spectro-graphic analysis at the ACL. The results are also listed in Table 31. Copies of the original ACL reports are also contained in Appendix C.6. The impurity j level for the elements analyzed is <185 ppm with an accuracy of 3-10% of the I amount present. This level of impurities is only ~5% of the total impurity level allowed by the specification, but, of course, no analyses were conducted for a number of specific elements. <

5.

SUMMARY

In order to requalify a large group of SPERT fuel pins for use in certain university research reactors, 600 pins have been examined to verify that they ,

are the pins described in the specification and to assess their present condi- )

tion. The serial numbers of the pins which were examined were distributed j over the entire range of serial numbers of pins produced. l l

The results of the requalification examinations leave no doubt that these i SPERT pins were produced according to Phillips Specification No. F-1-SPT.

Most of the attributes tested were within or very close to specified values.

l Except that pieces may have spalled from a few fuel pellets, no evidence was found of any deterioration of the pins since fabrication.

The external condition of the pins was excellent. All six of the pins g destructively examined contained a positive preseure of fill gas which was )

predominantly He but contained a significant amount of H2 . During radio-graphic inspection of the welds, which was not required by Specification i No. F-1-SPT, small gas bubble-type defects were found in the upper end cap welds of six of the 65 pins inspected. The remaining weld thickness was as small as 0.005 in., but there is no evidence that these defects affected the i' He leak tightness of the pins or the soundness of the metallurgical bond be-tween tubing and end cap. Meta 11ographic examination of the cladding showed l it to be in excellent condition, with no evidence of intergranular attack or corrosion from within or without. Three fuel pellets with pieces spalled from them were found in one pin (No. 8321), which appears to be somewhat anomalous in several other respects.

NUREG-1281 APP A A-19 1

Table XI. Results of UO 2 Analyses Uranium Analysis Pin Pellet Isotopic Analysis, wt% Total U, 0/U No. No. 2330a 234Ua 235gb 236pa 238ge wt% Ratiod 0396 6 0.0009 0.0255 4.809 0.0481 95.116 87.92 2.040 i 1382 6 <0.0005 0.0245 4.802 0.0483

' 95.125 87.85 2.053 2619 30 <0.0005 0.0250 4.805 0.0479 95.122 87.91- 2.042 6921 6 <0.0005 0.0256 4.818 0.0463 95.111 87.93' 2.038 8321 2 <0.0005 0.0257 4.803 0.0434 95.127 87.97 2.030 Average <0.0005 0.0253 4.807 0.0468 95.120 87.92 2.040 Std. Dev. --

0.0050 0.007 0.0021 0.007 0.04 0.008 l

uncertainty: 0.0005 wt%.

b Uncertainty: 0.001 wt%.

uncertainty: 0.002 wt%.

d Oxygen-to-uranium (0/0) atom ratio, based upon impurity content of 0.02 wt%.

Impurity Analysis Amount,a Amount a Impurity ppm Impurity ppm Ag 2 Mg 10 ,

A1 9 Mn 2 Ba <2 Mo <2 ]

Be <0.5 Ni 10  !

Ca 38 Pb <3 Co <2 Sn <10 Cr 13 Sr <0.5 Cu 9 Ti <0.5 Fe 66 V <2 Cd <0.5 Zn 3 aEstimated accuracy: 3-10% of amount present.

NUREG-1281 APP A A-20

ACKNOWLEDGMENTS Many persons participated in planning and performing the inspections discussed in this report, and their contributions are gratefully acknowledged.

The authors especially thank D. R. Schmitt for helping with many administra-tive and supervisory details, R. B. Massow for helping plan cost-effective radiographic inspections, and L. E. Garrison for advice on quality assurance matters.

REFERENCE

k. B. E. Schaner, " Meta 11ographic Determination of the UO2-U49 0 Phase Diagram," J. of Nucl. Mat. 2, No. 2, 110-120 (1960).

I i

1 NUREG-1281 APP A A-21

SPECIFICATION FOR l FABRICATION, INSPECTION AND PACKAGING OF URANIUM DIOXIDE FUEL RODS SPERT Specification F-1-SPT Phillips Petroleum Company Atomic Energy Division Box 2067 Idaho Falle, Idaho August 9, 1963 i

i NUREG-1281 APP A A-23

FABRICATION, INSPECTION AND FACKAGINO OF URANItM DICKIDE TUBL RODS SPERT SPECIFICATION T-1.SPT APPROVAL PAGE Prepared By:db1 Date: b M, /P /3 Checked By: ((. bl  % Date: /1, i j g /f L4 g -

7 , -

Approved By: IO Date: /L J /b l40 By: h Date: 5 ]/(o 3 By: /I Date: g/ f[4.3 By: erm Date: /1// F u v - '

By: Dates l By: Date:

Revisions l

1. Prepared By: Date: =

l ApprovedBy/ Dates i

2. Prepared By: Date:

ApprovedBy/Date:

3 Prepared By: Date:

Approved By/Date:

NUREG-1281 APP A A-25

FABRICATION, INSPECTION AND PACTAGING '

0F URANIUM DIOXIDE FUEL RODS SPERT SPECIFICATION F-1-SPT TABLE OF CONTElfrS l

1 SECTION DESCRIPTION FAGE' 1.0 Scope . . . , . . . . . .............. 4 ,

i 2.0 References ...... ............. k 3.0 Description of Work . .............-. k

,. 4.0 Materials of Construction . ........... 5 50 Fabrication . . . . . . . . . . . . . . . . . . . 8 6.0 . Tests and Ir.spections . . ............ 8 7.0 Cleaning ........ ..... ....... 11 8.0 Fackaging and Shipping .. .......... 11 90 Information Required from Vendor ........ 12 10.0 Responsibilities . ............... 15 11.0 Items Furnished by Buyer ........... . 13 NUREG-1281 APP A A-26

I 1

FABRICATION, INSPECTION AffD PACKAGING l OF URANIUM DIOXIDE FUEL RODS SPERT SPECIFICATION F-1-SPT 1.0 SCOPE These specifications cover the requirements for fabrication, inspection, cleaning and packaging for shipment of uranium dioxide fuel rods, for use at the United States Atomic Energy Commission's National Reactor Testing Station near Idaho Falls, Idaho.

2.0 REFEREFCFS 2.1 Reference Documents 2.1.1 ASTM A269-62T, TP-304 - Specifications for Seamless and Welded Austenitic Stainles's Steel Tubing for General Se rvice .

2.1.2 ASTM.A276-62, 30k - Specifications for Hot-Rolled and Cold-Finished Corrosion-Resisting Steel Bars.

2.1 3 ASTM-A370-61T - Methods and Definitions for Mechanical Testing of Steel Products.

2.1.4 ASTM-A313 Chromium-Nickel Corrosion-Resisting Steel Spring Wire.

2.1 5 ASTM A371-62T - Corrosion-Resisting Chromium and Chromium-Nickel Steel Welding Rods and Bure Electrodes.

2.2 Schedule of Drawings The following drawing is included as an integral part of this specification:

Drawing Number Title SPT.E-1166 Spert Fuel Rod Details and Assembly

3.0 DESCRIPTION

OF WORK 3.1 Each fuel rod fabricated shall consist of slightly enriched, sintered UO2 pellets, encased in a stainless steel tube espped on both ends with a stainless steel cap. There shall be an aluminum oxide (Alp30 ) insulator between the U02 fuel pellets and stainless steel end cap at the bottom end of the fuel rod and an aluminum oxide (Alp 30 ) insulator between the U02 fuel j pellets and the stainless steel pad at the upper end of the fuel rod. Cas gaps to accommodate fuel expansion are provided both at the upper end and around the UO2 fuel pellets.

3.2 To assure tube integrity requirements, the following tests and in- i spections in accordance with Section 6.0 of this part shall be per. l formed by the seller: Flattening Test, Hydrostatic Test and Eddy l Current Test.

I NUREG-1281 APP A A-27 l l

l

SPECIFICATION F-1-SPT 3.3 The weld used to seal the end caps to the tube of each fuel rod shall make a sound metallurgical bond with both the tube and and cap components.

3.4 Each fuel rod assembly shell have an identifying number. This number shall be placed ou the end cap at the spring end as shown on drawing SFT-g-1166. The character size and the numbering system shall be specified by the buyer prior to f abrication.

3.5 chips and cracks on sach fuel pellet f abricated for ass 3mbly into fuel rods shall be controlled by the seller, and pellet defects exceeding the limits stated in Section 6.0 shall be rejected. and p9g, assembled into rods.

3.6 All parts and assemblies shall be fabticated in strict accordance with best standards of commercial practice.

3.7 These11er shall furnish the buyer two (2) copies of all shop drawings at least fif teen (15) days prior to f abrication.

3.8 Notwithstanding c: hor provisions of these specifications, the buyer way, at his option when requested in writing, vaive certain minor deviations from requirements of the specifications and drawinge where the f ailure to meet any specific requirement either alone or in combination with other failures shall not in the opinion of the buyer significantly reduce the ef ficiency or performance of the fuel rod assembly, Acceptance by the buyer of a fuel rod with one or more such deviations f rom the specifications shall not be construed to mean the buyer approves or shall approve similar deviations in items not yet delivered under the contract. If such deviations allowed by the buyer under this provision result in less costs to the seller than would have been incurred had all the re- l l

quirements of the specifications and drawings been fully met, then the Subcontract price shall be adjusted downward by en amount l I

corresponding to such reduced costs and the Subcontract shall be modified in writing accordingly.

4.0 MATERIALS OF CONSTRUCTION 4.1 Tubing 4.1.1 All tubing shall conform to ASTH designation A-269-62T,

" Seamless and Welded Austenitic Stainless Steel Tubing for General. Service, Crade TP-304" and with the supple-mental requirements specified by this specification.

4.1.2 The tubing shall have the following chemical composition limitations in addition to those specified by ASTH-A-269-62T, TP-304:

Cu 0.50% Maximum Co 0.05% Maximum Ho 0.50% Maximum B 0.005% Haximum 4.1.3 Dimensional tolerances shall be as shown on drawing SPT-E-1166.

NUREG-1281 APP A A-28

. . . . . . . .. . . .. .. . . . . . . . .. -~

l SPECIFICATION F-1-SPT 4.1.h Tube finish shall be as stated on drawing SPT E.1166.

k.1 5 The steel from which the tubing is manufactured shall be made by the electric furnace process.

i 4.1.6 All tubes shall be bright annealed. The annealing shall be performed to produce maximum corrosion resisting qualities of the annealed material.

I k.2 End Caps and Pads 4.2.1 The material used for fabrication of the end caps and pads shall conform to ASTM designation A-276 62, " Hot Rolled and Cold Finished Corrosion Resisting Steel Bars,"

Type 304, annealed, and with the supplemental require-ments specified by this specification.

4.2.2 The material used for fabrication of the end caps and pads shall have the following chemical composition limitations in addition to those specified by ASIM-A-276-62, Type 301s.

Cu 0 50% Maximum Mo 0 50% Maximum Co 0.05% Maximum B O.005% Maximum 43 Fuel Pellets 4.3 1 The specifications on total U-235 loading per pellet and per rod shall be furnished by the buyer prior to award of the contract. The U-235 enrichment vill not be less than 2% nor greater than 5%.

b.3 2 The oxygen-to-uranium atom ratio in the UO2 shall be 2.00-2.02.

433 The total thermal (at 2200 m/sec) neutron cross section of all impurities shall not exceed 100 x 10-5 c 2/em3. The total impurit'ies shalGot exceed 2500 ppm. Specific inaxima for individual impurities shall not exceed the following

~

limits:

NUREG-1281 APP A A-29

SPECIFICATION F-1-SPT Element 14aximum ppm Fe 1,200.0 Cr 500.0 Si 500.0 N 500.0 Al 300.0 Ni 300.0 Mo 150.0 C 100.0 Ca 100.0 W 50.0 Ti h0.0 F 25.0 Pb 20.0 Mg 20.0 14n 20.0 Sn 20.0 Zn 20.0 Cu 10.0 Co 6.0 In 3.0 B 15 Cd 1.0 Ag 0.5 Total Rare Earths 0.6 k.3.4 The total moisture content shall ng exceed 75 ppm.

435 The density of the finished pellets shall be 9 97 g/cm3 minimum. The density shall not deviate by more than +

0.10 g[cm3 from the mean density.

4.4 Insulatore k.k.1 The insulators shall be made from Norton Alundum AkO2 or equivalent (minimum purity of 98.5% vith a specific gravity of 3.75 + 0.10).

h.5 Springs 4.5.1 Springs shall be made from a chromium-nickel corrosion-resisting steel spring wire conforming to AST14-A313-55 The vire shall not be coated with any foreign metals suchaslead,cipTer,etc.

4.6 Welding f4aterials 4.6.1 The material used for velding of the fuel rods shall con-forn to ASTil designation A371-62T, " Corrosion-Resisting Chromium and Chromium.!!ickel Steel Welding Rods or Bsre Electrodes," AWS-AST!4 Classification !! amber ER-308 Weld 14a terial .

NUREG-1281 APP A A-30

,x . .. . . . . . . . . _ . . . . . . . . . . . . .

SPECIFICATION F-1-SPT 50, FABRICATION 51 Gene ml 5 1.1 All parts and assemb).ies shall be fabricated in strict accordance with best standartis of commercial practice.

52 Fuel Rod Assembly  ;

5 2.1 rinal veld of the end caps to the tubing shall be per-formed in a helium atmosphere. The space between fuel pellets and tubing shall be filled with Bureau of Mine's 1 quality belium gas at a pressure of one (1) psig maximum.

I 5.2.2 The seller shall supply the buyer in writing, for the buyer's approvar, the procedures to be used in the velding operations. This information shall be supplied at least fifteen (15) days prior to fabrication of fuel rods.

53 Fuel Pellets 531 Fuel pellets assembled in the fuel rods shall have a minimum stacked weight of 22.56 g/in. The active fuei length per rod shall be 36.000 + 0.062 in.

6.0 TESTS AND INSPECTIONS 6.1 Genersi 6.1.1 The seller shall allow the buyer's representative free access to the seller's plant areas at reasonable times where fabrication, inspection and testing are being con-ducted under the contract. The seller shall provide the buyer's representatives all reasonable assistance necessary to evaluate the seller's confoz1 nance to the contract.

6.1.2 A minimum of three (3) copies of all test and inspection records shall be supplied to the buyer prior to or at the time of shipment.

6.2 Tubing 6.2.1 Chemical Composition and Tensile Tests i

)

Stainless steel materials in the condition used for fabri-cation, shall be certified to the buyer as to the chemical composition and tensile properties. The tensile properties i for the tubin6, determined in accordance with ASTH.A-370-61T, using the 0.2 percent offset method for determining the yield strength, shall meet the following requirements:

NUREG-1281 APP A A-31 l

SPECIFICATION F-1-SPT Ultimate strength: 75,000 psi minimum Yield strength: 30,000 psi minimum Percent elongation in 2 in: 45% minimum 6.2.2 Flattening Test A section not less than 2-1/2 in. long shall be flattened cold between parallel plates to a final size of three times the vall thickness. Any crack or break in the metal after flattening shall result in rejection of the lot.

6.2 3 Hydrostatic "est i

l Prior to final dimensional inspection, all tubing shall l be hydrostatically tested at a pressure of 1100 psi. I Tubes shoving any evidence of leakage or damage shall be rejected.

6 . 2 . 16 Eddy Current Test Each tube shall be subjected to 100% Eddy Current inspec-tion and to be acceptable must be found free from cracks, pits end other defects having a maximum depth of 10% of the vall thickness.

63 Fuel Rods 6.3 1 All subassembly components shall be statistically inspected I and only those complying with specificaticus shall be as-sembled into fuel rods.

632 All finished fuel rods shall be 100% inspected for dimen-sions and surface conditions.

633 Each fuel rod shall be given a helium leak test after com-pletion of all manufacturing operations. The test shall be carried out in a chamber evacuated to a maximum pressure ierons of mercury. A leak rate greater than 1 x of 10-gooem2g/see shall be cause for fuel rod rejection. The exact procedure to be used shall be submitted by the , seller to the buyer for the buyer's approval. Fuel rods failin6 the test may be reworked and subjected to a retest, if all other requirements are met, and the buyer grants approval, in vriting, to the seller to proceed with the rework.

6.3.4 All finished fuel rods shall be gamnn scanned and twe (2) copies of each of the scan traces furnished to the buyer.

The buyer must approve in vriting the gamma scan technique.

NUREG-1281 APP A A-32

SPECIFICATION F-1-SPT 6.4 Fuel Pellets 6.4.1 The total area of all chips on any single pellet shall not exceed five (5) percent of the cylindrical surface area of the pellet. l 1

6.k.2 The area of the single chip shall not exceed 0.03 sq. 1 in. on the cylindrical surface area 7~ ,

6.4 3 No cylindrical surface chip shall exceed 0.010 in in depth.

6.k.h On the cylindrical surface of any pellet, any two (2) chips, in their. closest proximity, shall not be closer than the maximum dimension of the smaller chip (the maximum dimension taken on the cylindrical surface, and not along the edge of the pellet). ,

6.k.5 The total area of chips on each end of the pellet shall not exceed ten (10) percent of the pellet end area. The portion of edge chips on the cylindrical surface shall meet the requirements of 6.h.2, 6.k.3, and 6.k.4 above.

6. k . 6 No longitudinal crack shall exceed 0.25 in. and no other cracks on any surface shall exceed 1/3 the circumference of the pellet.

6.k.7 Uniformity of uranium-oxide loading in each fuel pellet and in all fuel pellets in each fuel rod shall be con-trolled by the seller through application of quality control procedures to the production processes. The seller, upon request by the buyer, must furnish data in support of this specification, i

6.k.8 For the purpose of inspection under Section 4.3.1 of these specifications and to implement financial responsibility pursuant to Article VII, Section 10, and Appendix 1, the buyer will determine the U-235 loading of individual pellets and/or rods in one or more of the following methods:

6.4.8.1 chemical analysis of UO2 88mples as required by Section 9.5.

6.4.8.2 Comma scanning of completed rods.

6.4.8.3 Seller's measurement.

NUREG-1281 APP A A-33

SPECIFICATION F-1-SFT 6.k.9 Prior to assembly into rods, sampling of fuel pellets shall be made and the fuel pellets destructively ex.

amined to assun that the requirements of Sections 4.3.1 through k.3.5 and 6.k.1 thmugh 6.4.7 an met.

The sample size of each lot in the sampling procedure shall be such that the " Lot Tolerance Percent Defective" for each lot does not exceed three (3) percent with an associated risk ofTo5. A '" defective pellet" is defined here as a pellet which does not comply with one or more of the specifications established by the referenced sections.

70 CLEANING 71 Finished Fuel Rode 7 1.1 The seller shall take all precautions necessary to main-tain a high standard of cleanliness during fabrication to ensure that no foreign materials are present in the finished units.

, 7 1.2 The finished fuel rod shall be completely free of dirt,  !

l scum, scale, pencil or graphite marks '

[ contamination (ontheoutsidesurfaceh, grease, uranium or other foreign materials. All rods shall be free fmm denta, scrutches, or f,ouges in excess of 0.003 in. in depth.

7 1.) All oil and grense shall be removed by use of a satis-factory degressing agent, and all surfaces shs11 be thoroughly rinsed with water. The composition of cleaning

, materials shall be controlled to minimize the presence of l contaminants which n;sy accelerate corrosion, contribute i

to parasitic absorption of neutrons, reduce mechanical integrity, impair heat transfer, or promote swelling or blistering of the fuel rods. Use of materials containing a halide ion shall not be perinissible.

7 1.4 Surfaces of each finished fuel rod shall be smeared and counted for radioactive contamination. The alpha count from surface activity shall be less than twenty (20) dpm per 100 cm2 , and the beta-gamma count shall be less than one thousand (1000) dpm per 100 cm2 ,

8.0 PACKAGING AND SHIPPING 8.1 Fuel Rode 8.1.1 The seller shall design and supply shipping containers required to transport and deliver the completed fuel rods.

NUREG-1281 APP A A-34

SPECIFICATION F-1-SPT i

8.1.2 The containers shall be designed to prevent any distortion or damage to the fuel rods.

8.1'. 3 The containers shall meet all the applienble federn1, state and local regulations for shipments of this type.

8.1.4 The containers shs11 meet the necessary AEC Nuclear Safety requirements.

8.1 5 The seller shall be responsible for packing the rods in a clean and dry condition and shall take all necessary precautions during packing to protect the mds from damage during shipment.

8.1.6 Loaded shipping boxes shall be carefully closed and latched and shall be provided with a distinct seni prior to ship-l ment from the seller's premises.

I L 90 INFORMATION REQUIRED FROM VEITDOR 91 Prior to fabrication of the fuel rods by the seller under this contract, the seller shall provide the buyer in writinE, the manner by which the seller proposes to determine pellet UO2 and U-235 content, along with a detailed description of the manner by which the sclier proposes to verify that the tubing, fuel

, pellets, components and final assembled fuel rods shall meet specifications with a 95% reliability. Included in the descrip-tion should be sampling, analytical, and quality control pro-cedures, a statement as to the estimated absolute accuracy, developmental and production data in support of the precision estimate, and data showing that the methods to be used are free fmm any systematic error (bias).

92 As required by Section 6.1.2, a minimum of three (3) copies of all test and inspection records shall be supplied to the buyer by the seller.

93 As required by Section 6.2.1, the fuel rod material shall be certified to the buyer by the seller as to the chemical com-position and tensile properties (for stainless steel parts only).

9.4 As required by Section 6.3.4, all finished fuel rods shall be gamma scanned and two (2) copies of each of the scan traces furnished to the buyer. The buyer must approve in writing the gamma scan technique.

95 rne seller vill obtain fot the buyer three (3) five gram samples and corresponding chemical analysis from each U02 batch. These samples will be held at the seller's plant. From time to time during the course of the Subcontract any or all samples so held may be called for by the Buyer. At the completion of the Subcontract, samples not called for and in possession of the Seller will be considered part of the Seller's scrap.

1 NUREG-1281 APP A A-35

_ - - - - - . - - - - - . - - _ _ _ _ - - - _ _ _ - - _ - - _ - - _ - - - - - - - - _ - - - _ _ _ _ _ _ _ - - - - - - - - - - - - _ _ - - - - - - - _ - - - - - - - - - - - - - - - - - -a

SPECIFICATION F-1-SPI 9.6 As required in Section 3 7, the seller shall furnish the buyer two (2) copies of all shop drsvings at least fifteen (15) days prior to fabrication.

97 As required in Section 5 2.2, the seller shall submit to the buyer for approval the procedures to be used in the velding operations. This infor1 nation must be supplied at least fifteen (15) days prior to fabrication of the fuel rods.

10.0 RESPONSIBILITIES 10.1 The seller shall assume the responsibility and cost of con-version of UF6t o UO2 to the specifications required for compliance with Section 4 3 10.2 The seller shall assume the responsibility for and cost of reprocessing to U 3 08, UF4, UF6, or uranyl nitrate crystals all scrap generated in implementing the contract.

11.0 ITEMS FURNISHED BY BUYER 11.1 The uranium in the forin of UF6 with the proper isotope en-richment shs11 be supplied by the buyer along with irotope analyses to the seller f.o.b. Oak Ridge, . Tennessee, and in such quantities and at such time as to permit conversion according to specification and compliance with delivery schedules, j

1 l

l NUREG-1281 APP A A-36

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Appendix 5 Requalification Plan for SPERT Pins l

i l

i NUREG-1281 APP A A-39

l REQUALIFICATION INSPECTION PLAN FOR SPERT PINS 1.0 NONDESTRUCTIVE EXAMINATION i

1.1 Visual Inspection (100%)

Each pin shall be visually inspected for evidence of damage and for condition of the cladding surface. Each weld shall be visually inspected for evidence of cracks. The location and description of dents, scratches, gouges, or pits in excess of 0.003 in. in depth; cracks; discoloration; or other anomalies shall be noted.

1.2 Dimensional Inspection 1.2.1 Straightness (Bow) (100%)

Each pin shall be inspected for straightness. The amount of bow shall be recorded if it exceeds 0.032 in.

1.2.2 Diameter, Roundness (5%)

Five percent of the pins shall be selected at random for diametral measurements. Two measurements shall be made (separated by l[f 2]fl[f1]90*) at the following distances from the bottom of the pin: 7-3/8 in., 19-3/8 in., and 31-3/8 in. (all with tolerance of *1/8 in.). The measure ments shall be recorded.

1.3 Inspection of Welds (10%)

Ten percent of the pins shall be selected at randon. The circumferential welde joining the upper and lower end caps to the tube shall be inspected by x-radiography for cracks and fissures which might allow leakage of the cover gas. If any defective weld is found, a determination of the extent of additional inspection required will be made based upon the results of all inspections.

2.0 DESTRUCTIVE EXAMINATION The lot of pins shall be divided into five equal sublots, ordered according to serial number. One pin shall be selected at random from each sublot for destructive examination.

2.1 Presence of Helium Cover Gas (5 pins)

The pressure and species of the gas in the pin shall be determined.

NUREG-1281 APP A A-40

2.2 Meta 11ographic Examination (pins from first, middle, and last oublots)

A cross sectional sample from the fuel zone shall be examined to determine the thickness and condition of the cladding, the diameter of the UO2 Pellet, and the grain structure of the UO2 P*ll't*

2.3 Fuel Pellet Density (5 pins)

The density of one UO2 . fuel pellet from each pin shall be measured.

2.4, Chemical and Spectroscopic Analysis 2.4.1 Tube (pin from middle sublot)

A quantitative analysis of the constituents of the fuel tube shall be made to verify that the material is Type 304 SS. In addition to the normal constituents of Type 304 SS, the amounts of Cu, Mo, and Co shall be reported.

2.4.2 Fuel Pellet 2.4.2.1 A total uranium and a uranium isotopic analysis shall be performed on a sample f rom one fuel pellet from each of the five pins.

2.4.2.2 A spectroscopic analysis for the following impuritites shall be made on a sample from one fuel pellet from the pin from the middle sublot: Ag, A1, Ca , Cd , Co , Cr , Cu , Fe , Mg , Mn , Mo , Pb , Sn , Ti , Zn .

I

, NUREG-1281 APP A A-41

Appendix C Inspection Data Sheets and Reports C.1 Fuel Pin Dimensional Inspection Data Sheets l

~1 J

t NUREG-1281 APP.A A-43

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Appendix,C Inspection Data Sheets and Reports C.2 Weld Radiographic Inspection Reports I

l l

n f

l NUREG-1281 APP A A 46

QUALITY ASSURANCE DtVISION - Nondestmetive Testing ,

RADtOORAPHIC TECHNDOUE 5tECORD 1980PECTION REOUIREMEWTS Ra#1 k OfVISION: (f l PERSON: /. O,[8 5 [Oi"1) l JOS NO.: f/f - /qy/y lesyECTION CDOE: ACCEPTANCE CR4 RIA: M ATERIAL TYPE: $$ 7"

.f*8 /#07" dey. 7 848- beAV MATL. THICKNESS: $,e b, PART N AME: ypfg gfg) l JCP # - l DWG.NO. SpT-f *//Q "

PAFif NUMBER (SI:

PART DESCRIPTION. IDENTIFICATION OF PART AREA (S) TO DE INSPECTED & SPECIAL INSTRUCTIONS:

(row nwiedel, wohl type, wetjf joint. EPecific part stes, etc.):

• A se.e.pfa m C n tsv7A : cnets and %5s's8res whiiA m,ph7 A fleev 1s* K ge. of TAs s one p,, j, y f,yg,aq 7-l is a rsr r snd sap welk 1-1 is loww e.ed lap ml)

ATTACHMENTS: DSKETCH O DR AWING O OTHER:

FOR OAD/NDT USE ONLY PART 10ENTiflCATION: gpspgcTaog DAyg:9)p/gg, sHnY real roos 7-I

• T .a wsebs PROCEDURE:pbygg/gf f 7 OC040 C. l SOURCE SIZE: mm O lR 192 l l $OURCE &TRENGTH:

FOCAL SPOT SIZE: 7,S" mm l KV: JQ l MA: $

%X RAY MACHINE:J f d S M A/ 4Af EXPOSURE TIME: [d PENETROMETER (S)/ SHIM ($): */p SS[,fp" FILM LOCATION STATUS ' DATE pp: g ** f SCREENS: .0t%* f//) N PAfM FILED WITH QAD/NOT FILM TYPE (S): M-$ )Cobg SUBMITTED TO CUSTOMER FILM SIZEtS): I')t jp' SUBMITTED TO MATL. ' REVIEW RETURNED TO OAD/NDT I NUMSER OF FILMS: d[

VIEWING TECH.t M SINGLE D COMPOSITE SENT TO CENTRAL STORAGE gACCEPT O UNACCE M O OTHER 4/DR NO,.

INSPECTION RESULTS:

etc.* . .

COMMENTS MR.6.t blMimasks NO fitters.T '); poTI: ;T-l s/tL b 90*Vitsu wnu Tromuses. reg,g QS,*f y (sik*7167) 1 a.n l>ft o

8 c*> $1 e esot a suo e l DS7 7 awthh; RADIOGRAPHER isionaturel // aj u _1/, / j)g CERT. LLvtL: % DATE: <f [

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INTE RPRETER taignaturel CERT. LEVE L. DATE:/

QAD17 61 ??D l

NUREG-1281 APP A A-47 l l

OUALITY ASSURANCE DIVISION - Nondestructive Testing NDT 400 RA0lOGRAPHic TECHNIQUE RECORD

' AGE

/ Of /

INSPECTsON AEOUlREMENTS DivaSION. Ap l PE RSON: ), Ogh (997) l JOB NO.: ) = ) g $f]

INSPECTION CODE: ACCEPTANCE CRITERIA: MATE RIAL TYPE: g y-

[ 00//v0 7 M6.'.2 $se bE,fe M ATL. THICKNESS: yg pQ PART N AME: $ py( 7 p p gf l JCP S l OWG. NOa $p7. p .//g PART NUMSER(Sl: Su C. .,,, ,,73 PART DESCRIPTION,(IDENTIFICATION OF PART AREA (Si TO DE INSPECTED Si SPECIAL INSTRUCTIONS.

(r m.i.. i. M m ...r.M w . c.e.cP.n.r... m.:

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% Ac.c.ep%se, &s%in 1 Crask', s n} p,;, peg gf,j ,,,*ggggy,4 Ica Eage. of The e,erec gas si u,ae c.

[a= / th 44gCP 4 0,4[ MJO T-a. is lower & t,Ap we,l)

ATT ACHME N TS. OSKETCH D OR AW!NG D OTHE R:

FOR QAD/NDT USE ONLY , ,

PART IDE NOTIFICATION

INSPECTION DATE: 7/yM" 5fJR7 7utl A4s T-/ t 7-J wc.ds PROCEDURE: ges}p f A.,,7 0 tR.192 l CC040 l SOURCE STRENGTH. C. l SOURCE SI2E: mwn XX RAY MACHINE: a50 5W Rw FOCAL SPOT Size: 3, g mm l Kv: / y o l MA: p EXPOSURE TIME: [p , k # PENETROMETER (Sl/ SHIM (S): 88 g g $g / , {g

• gy p: ga FILM tOCATION STATUS A SATL SCRE ENS: . 00A.* F/a P6 Pa.o r. FILE D WITH OAD/NDT FILM TYPE (SL F6f - } R. ,la f SUSMITTE D TO CUSTOMER SUBMITTED TO MATL. REVIEW FILM SIZE (Sh 3

• W 3 o '#

NUMBER OF FILus: Y RETURNE D TO OAD/NOT VIEWING TECH.: }{ SINGLE D (X)MPOSITE SENT TO CENTRAL STORAGE INSPECTION RESULTS: k ACCEPT [UNACCEPT O OTHER 1/DR NOa f 9 7g /

COMME NTS (masks. letters, etsf P ,

p,a sv.* cusQ Nf: uMatf7 i Fw-SN M17 7 (Str ~ fpg 3Cjnygj, 7 anoT1 7 7017 O <N)

WE WhLE Tilt $!" Alle INkoceT1b by O'o fe#

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INTE RPRE TE R (venaturel E 7[' CE RT. LEVE L:M DATE: [76 UAO 99 t#1H NUREG-1281 APP A A-48

ouAuTY ANURANCE DIVISION - Nondestructive Testing PAGE NoTaco Rapt 00RAPHIC TECNeel0UE RECORD f OP /

tesePECTION MEOUIREMENTS M [

Division: Ap lPERsVN: L 03fu (n97) l m NO; l /(,- p e y a NsPECTiON cOoE: ACCEPTANCE CRITERIAi MATERIAL TYPE: gg /-

Soo/vot 4sv 7 See, he/ q* MATL.TwiCKNESs:Su g, PARTNAME: $ pg( 7 p;y lKP# l DWG.NO.: $py.p -f/gg PART NUMBE R(S): Sea C. v.it,s PART DESCRIPTION,40ENTIFICATION OF PART AREAtSi 70 SE INSPECTED Si SPECIAL INSTRUCTIONS:

trow materet, weld type, weld ioaret, specific part area, etch

% A ce.e p%c,g, Q,$g%iA t C ngg, g n} p,,'gy, gg g),,[fm*,g.pggj,4 g baEage of The e,e rer gas s's unAt 8 7-) A u e ed say wt.f)

'l-A is c e w ) LA p w e,l)

TT ACHMENTS, OSKETCH D DRAWING O OTHE R: ,

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FOR OADMDT USE ONLY _ ,

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PART IDENTIFICATION: INSPECTION DATE:7/Af2.M

• j

$94T Fuel Psits T-/ t 7-J We,LJs PROCEDURE: #00Nve[ Av.7 O th-te2 OC040 C. l SOURCE st2E: aun l l SOURCE STRENGTH:

R X. RAY MACHINE: 450 $ & Rag FOCALSPOTSIZE: 35 mm l Kv: 1F6 l MA: P EXPOSURE TIME: b ln,, PENETROMETER (S)/ SHIM (S): # le $5'/ . So "

FILM LOCATION STATUS RAM,,

SF D: yy#

SCREE NS. . 0 0 A,

• F/s P6 PA.er L8 0 *'* 0^D*DT FILM TYPE (S): Pt - } Re JA SUBMITTED TO MATL. REVIEW FILM SIZE (SI: E

• 1( t o &

NUMBER OF FtLMS: RETURNE D TO OAD/NOT VIEWING TECH.: X SINGLE D COMPOSITE SENT TO CENTRAL STORAGE INSPECTION RESULTS: D UNACCEPT O OTHER* I/DR NO.:

KACCEPT COMME NTS tar.enks, tiners. etc,*i: $ Ajefy; wg(L rareansy4 mpgeh 4 g 08, f#'

bok Ne*r (kmMN MD TtN Vlt M of 3-1 Nil b, $p # l$7l,

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INTE RPRETE R ingastures UE *h CE RT. LEVE L: DATE: g[fs m t, ..t NUREG-1281 APP A A-49

i

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OU ALITY AS$URANCE DIVISION - Nondestructive Testin$

NoT 4oo RADIOGRAPHIC TECHNiOUE RECORD l PAGE

/ or /

INsPECriON REOuiRaMENTS h 9dN[

~

oivisiON: Ap l PE ASON: ), OAfgg ( 87 ) 9 7 ) l49NO.:)ff-fgYhj INSPECTION COOE; ACCEPTANCE CRITERIAi MATERIAL TYPE: gy *f*

Soo/voY esv.2 54c hele [ MATL. THICKNESS: f'gg Ohg, l PART N AME: S py( 7 ppy lM# l 0WG. NO. gpy.y //g PART NUMBE RIS): gee, C.,me,,fg PART DESCRIPTION. IDENTIFICATION OF PART AREAts) TO BE INSPECTED Si SPECIAL INSTRUCTIONS:

trew meterial, wetd type, weld joint, specific part eree, etsj:

-W A ct.effkase, C,r{h,vig 1 C m k's g ) p,,'g m , y ),, j ,y, p gg, 4 j "A C 4 D6 OtPCP gA5 16 WtlA6 $a h } ls et e *y Lef W tA I*A [5 HeF 8- t,Ap we,l ATTACHMENTS: OSKETCH D C R AWING D OTHER:

FOR QADMDT USE ONLY _ , j PART IDENTIF # CATION: INSPECTION DATE: fgg[ * ]

$ridt7 Fuel PsAs T -1 & 7 -J w e,Il s PROCEouRE: dooAd Av.7 nwn D IR-192 l DC040 l $OURCE ST RENGTH: C. l $0URCF.f'ZEs ]

RX. RAY MACHINE: a5o 5 W b FOCAL SPOT SIZE: 35 a.= l Kv: 1F6 l MA: P

1. PENETRAMETERISUSHIMtS): # l g $5 / . 50 "

EXPOSURE TIME: [p p Tm ,

FILM LOCATION STATUS ,g A T,,[,,

SFD- Mp Pb fA s t r* "L ' ^

SCREENS: . CO.t

• fh3 SUBMITTE D TO CUSTOMER FILM TYPEtSI: r=j - ? Ro daf FILM SIZE (Sl; $*gga* SUBMITTED TO MATL. REVIEW NUMBER OF FILMS: y RETURNED TO QADMDT VIEWING TECH.: X SINGLE D COMPOSITE SENT TO CENTRAL STORAGE INSPECTION RESULTS: .- % ACCEPT )(UNACCEPT D OTHER : t/DR NO.: /W41 COMMENTS Ima s. fittera. etc.*l:

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'NUREG-1281 APP A A-50

~. _ _ .

l OVALITY ASSURANCE DivistON - Nondestructive Testing RADIOGRAPHIC TECHNIOUE RECORD INSPECT 80N REQUIREMENTS [ M k l /h /[

Division. Ap l PERSON. J , pgpg g (gg97) l JOS NO 1/ /[e- 16 Y /jll sNSPECTION CODE: ACCEPTANCE CRITERIA: MATERIAL TYPE: gg"/*

300//voY M6 v. 2 See $e/oV MATL. THICKNESS: ggg 8Q PART NAME : - $ py 4 7 pgy lJCP# l 0WG NO.: $py.y-//g/ '

PART NUMBE n(S): Su c, ,,,73 i PART DESCRIPTION. 4 IDENTIFICATION OF PART AREAls) TO BE INSPECTED & SPECIAL INSTRUCTIONS.

tese material, wsW type. weW sonat. specific part etes. etc.):

Y A CLif hYnssc. (hgisrs"A R Cysy U gnl f,hgypgg g f f m*,g g,y ggj, y

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^ Ap 4 DE Le rty* g5 s'g yfgggg g,

[- / / g C ,' ar-s4[ %fL T-4.is wer u d sap we.l)

ATT ACHME NTS. OSKETCH O DR AWING D OTHE R:

FOR CAD /NOT USE ONLY / /

PART DENTIF* CATION: INSPECTION DATE: f[$f(([

$ff47 fuel Ps/is T-/ 9 7 .1 w ells PROCEDURE: gepokr%g 7 D IR.192 l O CO-60 l SOURCE STRENGTH: C. l SOURCE S12E: .mm M X RAY M ACHINE : A50 5% Rav FOCAL SPOT Si2E: 35 ** l "V: /F0 l MA: &

1. PE NETRAMETE R(S)/SHIMISI: 88 0 0 ST / . 60 "

EXPOSURE TIME. [ pfjh SF D; ya FILM LOCATION ST ATUS DATE SCREENS. . c 0 4 F/s P6 PA ., e FILE D WITH OAD/NDT FILM TYPE (St. M-} yo ,fg SUBMITTED TO CUSTOMER FILea $1?EIS1: 3

• g i o '/ SUBMITTE D TO MATL. REVIEW NUMBER OF FILMS: h RETURNED TO CAD /NDT VIEWING TECH.: X SINGLE O COMPOSITE SENT TO CENTRAL STORAGE INSPECTION RESULTS: XACCEPT k UNACCEPT Q OTHER : 1/DR NO.: /75"OJ COMME NTS (masks. Mers. etc.*L ,

h'. "

, Zbg # ff$~g>3 5 (.\ukti Tnown]Ans. g,pps **)

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CERT. u m ;. u -- DATE:h oA1E: '/-

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NUREG-1281 APP A A-51 m

l OUALITY ASSURANCE OfVf880N - Nondestructhe Test'Eg NOT400 PAGE j OP f RA0lOCRAPHic TECHNIOUE RECORD INSPECTION REQUIREMENTS M DivlSION- Ap l PE RSON; j, ppfg4 { g39/) l JD0 NO.: ) /(. ~ l 6 Y /,ll INSPECTION CODE. ACCEPTANCE CRITERIAI l MATERIAL TYPE: $$ "f" Soo//voT /2s.v.2 See 6 e/o V* MATL. THICKNESS: ggg 8g PART NAME. Spy 47 ppy l KP W l DWG. NO.: $pf.y -//g PART NUMBE RIS): S c. w,,73 ,

PART DESCRIPTION. IDENTIFICATION OF PART ARE A(S) TO BE INSPECTED & SPECIAL INSTRUCTIONS: l i,.. m.i.n.i. io m.. ..oim. .P.ca,e P.n .. . .ic.): '

~*

Aee ep% ace. c,Nti.el'a t CncEs A n/ F,Esms wad 4 d,gW 4II. w l'* E^hC. & The e,srer aso'sunAtyft. l 5-) s's u er ed Laf WtI T-4.is e < 4 ssp we,l ATTACHMENTS: OSKETCH O DR AWING O OTHE R:

FOR OAD/NDT USE ONLY .

PART IDE NOTIFICATION:

INSPECTION DATE:)P/Mg Stie7 Fuel Ps/is T-/ t T-J we,tl3 PROCEDURE: goo' h o'y A.,.7 O IR 192 l 0 CO 60 l SOURCE STRENGTH. C. l SOURCE SIZE: mm R X RAY MACHINE: A50 $ 4 pag FOCAL SPOT SIZE. 3, g snm l KV: fy0 l MA: p EXPOSURE TifAE: h/ Ale PENET R AMETER(S)/ SHIM (S); 88 gg $g/ , $g "

SF D: yy# FILM LOCATION STATUS DATE SCR EENS: . Q Q A

• 7/[3 Ph fagp FILED WITH OAD/NDT FILM TYPE (SI: M-} g, ,/, f' SUBMITTED TO CUSTOMER l FILM SIZEIS): 3

• X 10 SUBMITTED TO MATL. REVIEW NUMBER OF FILMS: t/ RETURNED TO OADMDT VIEWING TECH.: #,1( SINGLE O COMPOSITE SENT TO CENTRAL STORAGE l INSPECTION RESUL1S- YACCEPT O UNACCEPT C OTHER : 1/DR NO.:

COMME NTS Imssks. filters. .tc.*I: '

Mik No (G m N.5)

C 7/11 ~

l *Self l t er 1 I I t 1A.

I >t45 J- /f/7 5- . e 0 5-y

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CERT. LEVEL: g DATE: Mh INTERPRITE R (s.gri.tur.)

I"[ 7' CE RT. LEVEL: DATE: (( #[*

OAD 09 89 714 NUREG-1281 APP A A-52

OVALITY ASSURANCE DIVISION - Nondestructwo Testmg NOT 500 PAGI R ADIOGR APHIC TECHNIOUE Rf CORD / OF /

INSPECTION REQUIREMENTS ,M h[

DIVtSION: Ap l PE RSON: J, ppfg ( g)9f) l JOO NO : f ff- f o kg INSPECTION CODE: ACCEPT ANCE CRITE RIAI MATERIAL TYPE: ${ f"

,[OO/NOT 44,n,2 $ge, h g /e g* M ATL. THICKNESS: $e,e 04 PART NAME. $ py4 7 pfg l KP W l DWG. NO,: $py= p //g/

PART NUMBE R(5): 5,,,, g g fg PART DESCRIPTION IDE NOTIFICATION OF PART ARE A(S) TO BE INSPECTED & SPECIAL INSTRUCTIONS:

(esw material, weld type, weld joint. specific part ares. etc1:

YAC68[A Ae,e., belitr[A C % E5 An fs gyles Wfi Q , f*4/ Q

/ca E*3c of The cerer gas ei y, wee 1/e.

[- ) 5 M Cr d nc Lef %)L I*e1 l5 lbHtr t. Lap we,l ATT ACHME NTS OSKETCH O DRAWING O OTHE R:

FOR OAD/NDT USE ONLY . ,

PART IDENTIFICATION:

INSPECTION DATE: 7M%

SPIR 7 Fuc,/ Ps/is T-/ t 7-J wet /s FROCEDUPE: ggg A ,,7 O IR-102 l 0 C0-60 l $OURCE STRE NGTH. C.l$0VRCEst2E mm R X RAY MACH 6NE: A50 54 FOCAL SPOT SIZE; 3,6 mm l KV: /F0 l MA: P EXPOSURE TIME: [, 9 7 ,, PENETR AM E TE R(SI/ SHIM (S): 88 go $5/ . 60 "

spo; g /r FILM LOCATION ST ATUS DATE SCREENS. . c o A

• F//3 P6 FA,er '

FILED WITH OAD/NOT FILM TveE(SI: p*f - p go ,/3 f SUBMITTE D TO CUSTOME R F LM SIZEIS): 1,

• x i o # SUBMITTED TO MATL. REVlf W NUMBER OF FILMS. y RETURNED TO OAD/NOT VIEWING TECHa ,hi( SINGLE O COMPOSITE SENT TO CENTRAL STOR AGE INSPECTION RESULTS COMME NTS (mask s. htters. etc *l-p(ACCEPT k UNACCEPT C OTHER . l/DR NO.: /TSA g,

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NUREG-1281 APP A A-53

1

(

OUALITY ASSURANCE DIVISION - Nondestructive Testing RADIOGRAPHIC TECHNIOUE RECORD  !

INSPECTION REQUIREMENTS d4g) NNg OlVISION. Ap l PERSON: j, ggg { gg9% l JOS NO.! )/[,= l g $ f,g INSPECTION CODE: ACCEPTANCE CRITERIAi MATERIAL TYPE: gg f*

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PART IDENTsF4 CAT 10N:

INSPECTION DATE: f/J7/((.

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INSPECTION DATE: f/#//f[

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lNSPECTION RESULTS: '% ACCEPT D ONACCEPT COMMENTS (m.sks,fitte,s, ses. ): 7~t wick rm vigw. _Sh Ne' Cs.nj pont f NB$ ( t*W e F fp *) w ALL W "***'s To g ,og " S' 0 S83 5~ >o80 -fdtioS~B.3 f 7/89 Anb ds/JW CERT. LEVEL: r7 DATE: g/ / RAoioGRAeNER ii.ea.iv<et ~ / g / ,,, s/_ /[E CERT. LEVEL # DATE: f[h INTERPRETER teannatur.) OA P l? 19.97) NUREG-1281 APP A A-56 1 I l OUALITY ASSURANCE DIV1810N - Nondestructive Testing PAOI 1 #v07400 RADIOGRAPHIC TECHNIQUE RECORD / OP / 4 INSPECTION REQUIREMENTS M/ [ 'pvE Ti" IPER$a t a tts (snz) I =Noanc-se m j INSPECTION CODE ACCEPTANCE CRITERIA- MATERIAL TYPE: g7 l 800/N07 4s v. 2 Su 6c/o/ M ATL. THICKNESS:See a wa. PART N AME . __$pf47.pjg ,_ j KP # l DwG. NO.: $p7.p //gg PAR T NUMBE RISI $gg C.,,,,,,,,7 ) a644 M

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$438 AKSSI M /I R DiOGRAPMU b hev$e Q q f Q CERT LEVEL: m DATE: yp/ / sNTE RPRE TE R to.gnewel h, CERT LEVEL: [ OATE: [M[fg V cap le st ??t l NUREG-1281 APP A A-57 Appendix C Inspection Data Sheets and Reports C.3 Fill Gas Analysis Reports l ) i 1 l i i l i l l l NUREG-1281 APP A A-58 1 i ANALYTICAL CHEMISTRY LABORATORY Argonne National Laboralery Agonne,IL cosas REPORT OF ANALYTICAL RESULTS Sample Meterist: $ PERT Fuel Pins Date Received: 9/17/86 10/1/06 Submitted by: R. Domagala Date Reported: g73jg Your Number ' Our Number 86-2024 See attached p , f l 'I l NOTE: Samples will be discarded one (1) month after date of report unless otherwise arranged. When making future inquiries regarding this work. you must reference OUR number (s) above. For further information about the resulta reported here, please calt D. Graczyk at 2 4460 , Copies To- R. Domagala D. Green Analyst (s): H. Goodspeed / Snelgrove H. Goodspeed D. Graczyk T. Wiencek D. Graczyk R. Heinrich T. Engelkemeir /vaa cm . NUREG-1281 APP A A-59 'C s 5 4 4 4 5 3 4 d g ea sog 2 0 0 0 0 0 0 e nd h y r i e t rf t 2 a a

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F e cn os i n poeae dni e 8 8 1 8 4 6 E y nup smsti . _ Md R b af et oncn i 9 9 0 9 9 7 e rah oie o 1 d eah r ccf g V e n r us t oe ch esur f o i t an t wnst m a i t i i r . rs i ,: psn 1 2 3 4 5 6 edeee nh s a . 0 0 0 0 0 0 t epi r ucnl wd . o - - - - - - evmru uoe id N 4 d oeas esiudtf ue se mTvs 2 r nqr r 0 e usa aie u 2 ard er sAld l v O - w rrP s ues o 6 sau p e .l ct rh c 9 ead s i r set e mgns .h peaihi r u - aed s rclt w ll t ren ge o ga s . olS pi o i h re o vi fi spuh enw N 6 2 9 1 7 1 f - eit psot hi 9 8 1 2 9 2 d cca o t pt r u 3 0 3 6 9 6 0 7 3 l dP nel onTi pe emrl ma o 1 2 8 ht ol nuh V ASS sr T afAipt Y ' * * * ' 2Ccn) o3a =3U7 33 rC wt0e- 3 3e o ANALYTICAL CHEMISTRY LA90MATORY Argonne Nationel Labarstery Argonne.IL 80430 REPORT OF ANALYTICAL RESULTS Sample Watertal: SPERT Pin Fill-Gas Date Received 9/24/86 10/1/86 Submitted by: D. Graczyk for R. Domagala Date Aaported: 10/3/85 Your Number Our Number 86-2024 See attached page. I l NOTE: Samples will be discarced one (1) month after date of report unless otherwise arranged.When making future inquines regarding this work, you must reference OUR number (s) above For further ardormation about the results reported here. please calf D. GraczYk at 2 4460 R. Domagala R. Heinrich Analyst (s): T. Engelkemeir Cop 6es To: 4 Snelgrove H. Goodsoeed T. Wiencek T. Engelkemeir D. Green D. Graczyk /vaa CMS as tapet 1 NUREG-1281 APP A A-61 i I 2 1 0 0 e s h a 5 8 0 1 6 0 t g , 0 0 1 0 O 0 0 2 0 0 2 o e C t yh 0 5 0 0 3 l t < 0_ < 0 <- < 0 gl naf 0 0 iuo v s ein v o n(i 5 4 4 4 4 i t 0 0 0 0 0 1 prc r 0 0 0 0 0 0 ee A ht l 0 0 0 0 0 0 c al < < < < < ( a woc e d t n meg e 6 0 5 0 5 0 6 0 5 0 6 osn rni n 0 0 o , 0 0 0 0 0 f er p0 d u 0 m o < < < 0< <0 < 0 0 0 snd ao gcd C - e d l f n e 1 1 2 1 1 l oi t 0 0 0 0 0 1 i a a O f et 0 0 0 0 0 0 cb ic C t 2 i e 2 eno h e d 2 T n ,, t d s 3 4 5 7 5 4 i a R I N 0 1 0 f vw 0 0 O T f 1 oe n A o 0 0 0 0 0 t ,i R n1 p O s t e2 Bi s n 2 2 3 t 3 e A sa e 0 0 0 2 n8h L yG c co in n _ t l - r T al e* 2 0 0 0 3 0 _ R nl P 0 0 r pi tai 0, 2 i t 2 S F eH 0 0 e r t < 3 4 5 < t If M on u m 0 0 0 3 a on E i l 0 wf e H sF o 0 0 0 l ,se Ct V a rr lT uap _ L uR 4 3 5 4 2 7 tl _ A sE cug C eP a iicn IRS 0 0 0 0 0 0 - T e f t e _ T. e 2 2 5 2 2 o rb 1 H a _ A 8 6 6 9 6 7 ep) _ N v s A 3 8 9 8 9 8 4 9 5 4 nm 9 9 it I a _ a r t g 4 3 3 3 2 2 n .i erl 0 0 0 0 0 0 sol epi , 2 2 2 t r pv am B e w 2 3 1 0 3 5 r r e ef 6 0 0 5 4 3 et 1 1 1 b a a w , t 1 2 3 4 5 6 of n ops . 0 0 0 0 0 0 a o - - - - - - yeh N 4 a r r 2 r u 0 m tuep 0, na 2 O - , 6 H t 8 ea rl obd o f st ie . N 6 2 9 1 7 s nae 9 8 1 eeml 1 2 9 2 udi p r 3 3 6 9 0 3 l nt m u 0 1 2 6 7 8 aos a o V ces Y

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o es s -scoo e p nt ru ra e g g N f et o u r er S e f l e - o te i t r r er c r I T e t o 7 _ N - N dr ee8-n - t a e t i r 7 ( r f9 rt p p s m W e r _ s i s e 5 e ya s l t _ O & 4 d a j .(M a O@ CO OC i P e  : y s t o a E G M C = f o s _  ? 2 s,. 4' 2CXmme~nb > ] > >aNm g / 4 ifI' ll i jl I i s. a sM M )s J. _ s - i e M W [- " s iI' o i . a L Z r ( & , ee n 4 .e d' # 4Q t e Z t . c d ) , M g V 4* A 4 ,& )' y ._ e  : &M k i p F T a .~ 2 1 (' O e r r A< (g u [ L S f f Agb . =# T A. .e R O P E C r ar S n A.,. j d iM e R S o s C s A i S I m w JL. I S Y a t e ,_ s 4 L C S g ' A g a N s y Wy J, A e l b m n a A ev L P c e h M ~ A }' a a _ C l ll ' _ I M n e P e t e n e fe _ E ' ' , e ._ H s me e .e e N " ' ' " e. e. e F _ C ' " t e G s e e e te e t e * , o w O S 1 N N v t t t M. ' K R I 8 a s .e r e r e R ( P " "

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. i r t t t n N E i e n ie = o - 1 r v u ?. s s r u T R O i r p i o e N == twm me N - I' I o a - n Y o Y P E R - I e re r " e g E T e=* f of o k A r o / S - ' or or G r tos n a-o T t I m. e td N r L U S r F e c <'t . 8 - s i T S E d r af cg a 3 w e - e v t e v d E t ss OO u Q# O R O@ i r s n y t D e c e 7-9 oiOe wM<n zC::r, > o"U m 3 h t - 2sNC l Appendix C Inspection Data Sheets and Reports C.6 Fuel Pellet Chemical and Spectrographic Analysis Reports I l NUREG-1281 APP A A-77 ANALYTN:AL CHEMISTRY LABORATORY Arpenne Nattenal Leberatory Argonne,lt 80438 REPORT OF ANALYTICAL RESULTS Sample Matertal: Spert Fuel Pins Date Received: 10/16/86 Subrnitted by: R. F. Donagala Date Reported: 10/23/86 Total U Your Number Our Number ISotop1L Analysis. Wt S Wt i b U 233* U 234' U 235 U E36* U 238' 0396/6 87-0026 01 0.0009 0.0255 '4.809 .0.0481 95.116 87.92 1 1382/6 -02 <0.0005 0.0245 4.802 0.0483 95.125 87.85 2619/30 -03 <0.0005 0.0250 4.805 0.0479 95.122 87.91 6921/6 -04 <0.0005 0.0256 4.818 0.0463 95.111 87.93 6321/2 -05 <0.0005 0.0257 4.803 0.0434 95.127 87.97 a uncertainty = 0.0005 bcertainty=0.001

• Uncertainty = 0.002 NOTE: $amples will be discarded one (1) month after date of repon unless otherwise arran$. When makin0 future inquiries regarding this work. you must reference 004 number (s) above. For further information about the reeutts reported here, please call r_ Rauh at3 7399 Copies To: R. Donagala Analyst (s) A. Essling J. Snelgrove E. Raub D. Green K. Jensen

/le E. Rauh cea rea. File NUREG-1281 APP A A-78 ljl1 4lllI I l ;l 4 9-l* 4 /- / /, d e C *s. c t e e e s a t r a L Z e t n o n M Z 3 4 ( 4 g a. f M V c M 2 e 6 l 6 / T f 6 c. 2 e 9 S e 5 W C 4  : 9, n o T r 3 a o i R C 1 $ t a O <f c P o - E R C o r < S t t 2 - S I 3 S Y e d e L A C 3 S f S dj N e A 6 e 3 M E m L 8 P < D o

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e , t e t e ' e a c e r I N p A e t t e t B - N A o M o <A n , e ' E rr I m ee r e t m te a r e d e T o f. 7( L 0 1 " t e == t r t t t e m L , t r M n - - f e t x e o p L m e u , 7 T S W a t A 4 M E F t u e m I s n g A ao s T A M t I m t 5 T L s G l a l e N e C g; i i I e I io L - r r o. - R t e on e r n u u e F e  ? t e v t [ t e r r 1 O s e g M M = T e r , n n l . t C d p I o e ta A u 0 e o i R t t 3 e 5 o s D E l r e = U C inr wo ou n N - m 1 N / il p i C - 0 1 a T R m A a t m 1 r / r / r s e e a u 6 ou 5 0 y s = D f o 2 a e p tn er =r E f o f Y

• Y *2 m e g e T A o r o

s a c o o M r os _ r r o t. o 3 t I o N 0- N 0 T, s r r e e a e t t T E der tacf o t . 3d - t p p e = 6 r 6 e E o f e . . r 2 g t e . c a 0 0 u2 O00 a OO @ a ir a y t D a 7- 7-8 6 o 2CMmOe NcN > u y >ENW llll1l, DISTRIBUTION FOR ANL/RERTR/TM-8 Internal: a A.'Schriesheim R. F. Demagala (6) C. E.-Till' G. L. Hofman P. I. Amundson L. A. Neimark L. Burris D. R. Schmitt D. W. Cissel L. M. Stefanski L. G. LeSage H. R. Thresh R. A. Lewis T. Wiencek 1 J. F. Marchaterre. L. E. Garrison ] R. J. Teunis D. W. Green / D. C. Wade R. B. Massow j R. W. Weeks ANL Contract File A. Trave 111 (35) ARL P7 tent Department J. L. Snelgrove (2) ANL Libraries (3) L. R. Dates . TIS Files (6) External: DOE-TIC, ' for distribution per UC-83 (66) Manager, Chicago Operations Office, DOE l Director, Technology Management Div., DOE-CH C. Benjamin Alcock, The University of Toronto Paul C. Shewson, Ohio State University l Applied Physics Division Review Committee: Paul W. Dickson, Jr. , EG&G Idaho, Inc. E. Linn Draper, Gulf State Utilities Michael J. Driscoll, Massachusetts Institute of Technology Robert L. Hellens, Retired William E.-Kastenberg, University of California-L.A. Daniel A. Meneley, University of New Brunswick Warren F. Miller, Los Alamos National Laboratory l NUREG-1281 APP A A-80

u. ucaAueOuLaToav COMM .ON 1 wOai NUM.im ,,, ., rwC. , v., uA. , ,

geonM == E'i 2E SISLIOGRAPHIC DATA SHEET NUREG-1281 SEE INSTRUC S ON TME RivtRst

2. TITLt AND SUS t 3 LtAvtBLANK Evaluatior f the Qualification of SPERT Fuel for Use in Non-Powe Reactors 4 DATE REgi COMPLETED MONTn ViAR l

*^"'"" July J l987 gAf t REPORT 188U(D YEAR 'MOJN I 1987 Augusy

7. # BAFORMING ORGANt2ATION NAME AND 8 LING ADDRESS linss u mela Coast 6 PROJECTg8K/ WORK UNIT NUMSER Division of Reactor Pro cts III, IV, V & Special Projects /

Office of Nuclear Reacto egulation om GaANT NUM eR U. S. Nuclear Regulatory ission Washington, D. C. 20555 4 10 SPONSORING ORGANi2ATION NAM AND MAILING ADDR trairivselecopei Ile Tvet OF REPORT Technical Same as 7. above. [*M ,_ ,, ,,o, C o. , R io ,,,,,,,,.. ,.,, a

17. SU6LtMENT AR Y NOYkB )

13 A381R ACT (200 worse er sesst This report summarizes the U. S. Nuclear R fatory Commission staff's evaluation of the qualification of. the stainless-steel-clad , inum/ oxide (U0g) fuel pins for use in non-power reactors. The fuel pins were g lly procured in the 1960's as part of the Special Power Excursion Reactor Test SPER program. Argonne National Laboratory , (ANL) examined 600 SPERT fuel pins to i fy th the pins were produced according to specification and to assess their pre nt condit' . The pins were visually inspected under 6X magnification and by X-radi raphic, des etMve, and metallographic examinations Spectrographic and chemical analyse were performe n the U02 fuel. The results of the qualification examinations indicat4 that the SPERT el pins meet the requirements of Phillips. Specification No . F T and have suffered physical damage since fabrica-tion. Therefore, the qualifica on results give reaso le assurance that the SPERT l fuel rods are suitable for use n non-power reactors prol ded that the effects of thin-wall- defects in the regigh of the upper end cap a 'd w-density fuel pellets are evaluated for the intended perating conditions. i T \ 14 DOCUMENT ANALYSIS e KirWORD ESCRIPT ORS 16 Ava LAtiLIT Y SPERT program SPERT fuel. rods Jnlimited non-power react s 16 SECURITY CLAS5tFICATION ITnn engel D lDENTiplGR$/OPtN 8ND ftRMs hClassified g ,Re.,,, JnMassi fied R O,, Ages if N is PReCE

• U. $. Co ut R ape hi P81IkT I NG 0871CE 11997-191-68) ? t 6319 6

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