ML071800250
| ML071800250 | |
| Person / Time | |
|---|---|
| Site: | Catawba, PROJ0728  |
| Issue date: | 04/30/2007 |
| From: | AREVA NP |
| To: | Office of New Reactors |
| References | |
| ANP-10280NP, Rev 0 | |
| Download: ML071800250 (40) | |
Text
ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies April 2007 AREVA NP Inc.
(c) 2007 AREVA NP Inc.
U.S. Nuclear Regulatory Commission Disclaimer Important Notice Concerning the Contents and Application of This Report Please Read Carefully This report was developed based on research and development funded and conducted by AREVA NP Inc. (AREVA NP), and is being submitted by AREVA NP to the U.S.
Nuclear Regulatory Commission (NRC) to facilitate future licensing processes that may be pursued by licensees or applicants that are customers of AREVA NP. The information contained in this report may be used by the NRC and, under the terms of applicable agreements with AREVA NP, those customers seeking licenses or license amendments to assist in demonstrating compliance with NRC regulations. The information provided in this report is true and correct to the best of AREVA NPs knowledge, information, and belief.
AREVA NPs warranties and representations concerning the content of this report are set forth in agreements between AREVA NP and individual customers. Except as otherwise expressly provided in such agreements with its customers, neither AREVA NP nor any person acting on behalf of AREVA NP:
- Makes any warranty or representation, expressed or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this report, nor the use of any information, apparatus, method, or process disclosed in this report.
- Assumes any liability with respect to the use of or for damages resulting from the use of any information, apparatus, method, or process disclosed in this report.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page i ABSTRACT The U.S. Department of Energy is implementing a program to dispose of a portion of the nations surplus weapons-grade plutonium by reconstituting the plutonium into mixed-oxide fuel pellets and using the fuel in commercial light water reactors. Accordingly, the Department of Energy has contracted with Shaw AREVA MOX Services (formerly known as Duke COGEMA Stone & Webster, or DCS) to qualify the fuel for batch irradiation.
The qualification process includes irradiation of lead assemblies and post-irradiation examination of those assemblies to ensure that they perform as expected under irradiation. This report documents the examination of the lead assemblies after their first cycle of irradiation. Future reports will present the results of subsequent examinations.
The lead assembly design is denoted as Mark-BW/MOX1. Four lead assemblies were supplied to Duke Energys Catawba Nuclear Station, Unit 1, for irradiation starting in spring 2005. The lead assemblies were placed in high power but non-limiting locations that are expected to be representative of the batch peaking requirements. The first cycle of irradiation was completed in fall 2006, and the lead assemblies were examined at poolside after ultrasonic cleaning during the refueling outage. Consistent with previous plans, the examinations included measurements of fuel assembly growth, fuel rod growth, and fuel assembly bow, as well as fuel assembly and fuel rod visual exams. The appearance of the assemblies was normal; no damage was observed. Upon evaluation, all characteristics of the fuel assemblies were found to be within the criteria for reinsertion for a second cycle of irradiation, so the assemblies were reinserted into Catawba Unit 1.
The results of the examinations support the conclusion that the Mark-BW/MOX1 lead assemblies are performing safely and as expected.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page ii Nature of Changes Section(s)
Item or Page(s Description and Justification Rev. 0 all Initial release.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page iii Contents Page
1.0 INTRODUCTION
............................................................................................... 1-1 2.0
SUMMARY
AND CONCLUSIONS .................................................................... 2-1 3.0 METHODS, PROCEDURES, AND EQUIPMENT.............................................. 3-1 3.1 Visual Examinations ............................................................................... 3-1 3.2 Fuel Assembly Growth Measurements ................................................... 3-2 3.3 Fuel Rod Growth Measurements ............................................................ 3-3 3.4 Fuel Assembly Bow Measurements........................................................ 3-4 4.0 RESULTS .......................................................................................................... 4-1 4.1 Visual Examinations ............................................................................... 4-1 4.1.1 Fuel Assembly Examinations ....................................................... 4-1 4.1.2 Fuel Rod Examinations ................................................................ 4-1 4.2 Fuel Assembly Growth Measurements ................................................... 4-1 4.3 Fuel Rod Growth Measurements ............................................................ 4-2 4.4 Fuel Assembly Bow Measurements........................................................ 4-3
5.0 REFERENCES
.................................................................................................. 5-1 6.0 APPENDIX ........................................................................................................ 6-1
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page iv List of Tables TABLE 1-1DESIGN PARAMETERS FOR MARK-BW/MOX1 LEAD ASSEMBLY .......................................................................................... 1-3 TABLE 3-1EXTENT OF POOLSIDE EXAMINATIONS............................................. 3-5 TABLE 3-2NOMENCLATURES FOR FUEL ASSEMBLY FACES ............................ 3-6 TABLE 4-1FUEL ASSEMBLY GROWTH ................................................................. 4-5 TABLE 4-2FUEL ROD SHOULDER GAPS .............................................................. 4-6 TABLE 4-3FUEL ROD GROWTH............................................................................. 4-7 TABLE 4-4FUEL ASSEMBLY BOW ......................................................................... 4-9 TABLE A-1CATAWBA UNIT 1 CYCLE 16 CORE OPERATION HISTORY.............. 6-2
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page v List of Figures FIGURE 1-1GENERAL ARRANGEMENT OF MARK-BW/MOX1 LEAD ASSEMBLY .......................................................................................... 1-4 FIGURE 1-2LOCATIONS OF LEAD ASSEMBLIES IN CORE ................................. 1-5 FIGURE 4-1TOP ENDS OF FUEL RODS AS SEEN ON WEST FACE OF MX01 .................................................................................................. 4-11 FIGURE 4-2TOP END GRID AS SEEN ON WEST FACE OF MX01 ..................... 4-12 FIGURE 4-3THIRD SPACER GRID FROM TOP AS SEEN ON WEST FACE OF MX01 ............................................................................................ 4-13 FIGURE 4-4MIDDLE MID-SPAN MIXING GRID AS SEEN ON WEST FACE OF MX01 ............................................................................................ 4-14 FIGURE 4-5BOTTOM END GRID AS SEEN ON WEST FACE OF MX01 ............. 4-15 FIGURE 4-6BOTTOM ENDS OF FUEL RODS AS SEEN ON WEST FACE OF MX01 .................................................................................................. 4-16 FIGURE 4-7FUEL ASSEMBLY BOW, NORTH FACE............................................ 4-17 FIGURE 4-8FUEL ASSEMBLY BOW, WEST FACE .............................................. 4-17
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page vi Nomenclature Acronym Definition BPRA burnable poison rod assembly DOE Department of Energy DVD digital versatile disk EFPD equivalent full-power days GWd/MThm gigawatt-days per metric ton of heavy metal GWd/MTU gigawatt-days per metric ton of uranium LVDT linear variable differential transformer M5 designation for an advanced cladding alloy MOX mixed oxide - uranium dioxide and plutonium dioxide NRC U.S. Nuclear Regulatory Commission PIE post-irradiation examination
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 1-1
1.0 INTRODUCTION
The U.S. Department of Energy (DOE) is implementing a program to dispose of a portion of the nations surplus weapons-grade plutonium by reconstituting the plutonium into mixed-oxide (MOX) fuel pellets and using the fuel in commercial light water reactors. Accordingly, the DOE has contracted with Shaw AREVA MOX Services (formerly known as Duke COGEMA Stone & Webster, or DCS) to qualify the fuel for batch irradiation. A formal plan has been developed to guide the fuel qualification process (Reference 1).
The qualification plan calls for irradiation of four MOX lead assemblies for up to three cycles, as well as post-irradiation examination (PIE) of the assemblies to ensure that they perform as expected under irradiation. Poolside examinations are required after each cycle of irradiation, and hot cell examinations of selected fuel rods are required after the second and third cycles. This report documents the examination of the lead assemblies after their first cycle of irradiation. Future reports will present the results of subsequent examinations.
The lead assembly design is denoted as Mark-BW/MOX1. A detailed description of the design has been published (Reference 2). Figure 1-1 shows the general arrangement of the fuel assembly, and Table 1-1 provides selected design parameters (Reference 2, Table 5.1).
Four lead assemblies were supplied to Duke Energys Catawba Nuclear Station, Unit 1, for irradiation starting in spring 2005. The lead assemblies were placed in high power but non-limiting locations that are representative of the batch peaking requirements.
Figure 1-2 shows the locations of the lead assemblies in core during their first cycle of irradiation. In fall 2006, the first cycle of irradiation was completed. The assembly average and maximum rod average burnups are 22.0 and 26.1 GWd/MThm, respectively. The lead assemblies were in quarter-core symmetric locations, so the same burnups apply to all four.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 1-2 Prior to completion of the first cycle of irradiation, quantitative acceptance criteria were developed for fuel assembly and fuel rod growth. These criteria were chosen to help provide assurance that the lead assemblies could be safely irradiated for a second cycle. The criteria are discussed in Sections 4.2 and 4.3.
The lead assemblies were examined at poolside during the refueling outage after their first cycle of irradiation. Consistent with previous plans (Reference 2, Table 8.1), the examinations included measurements of fuel assembly growth, fuel rod growth, and fuel assembly bow, as well as fuel assembly and fuel rod visual exams.
Each of the examinations helped to provide assurance that the lead assemblies could be safely irradiated for a second cycle. The visual examinations were used to ensure the mechanical integrity of the fuel assemblies, including fuel rods and structural components. Fuel assembly growth measurements were used to ensure that a positive clearance will remain between the fuel assembly and the reactor internals during the next cycle of irradiation. The clearance between the top ends of the fuel rods and the upper end fitting is related to fuel rod growth. Measurement of this clearance was used to ensure that a positive clearance would remain throughout the next cycle of irradiation.
Finally, measurements of fuel assembly bow were used to ensure that the fuel assemblies could be readily loaded into the core during refueling and would allow for rapid and reliable control rod insertion.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 1-3 Table 1-1Design Parameters for Mark-BW/MOX1 Lead Assembly Parameter Value Pellets Fuel pellet material PuO2 and Depleted UO2 Fuel pellet diameter, in 0.3225 Fuel pellet density, % of theoretical density 95 Fuel pellet volume reduction due to chamfer and 1.11 dish, %
Rods Fuel rod length, in 152.40 Fuel rod cladding material M5 Fuel rod inside diameter, in 0.329 Fuel rod outside diameter, in 0.374 Active fuel stack height, in 144 Assemblies Distance from top of bottom nozzle to bottom of 159.85 top nozzle, inches Lattice geometry 17 x 17 Fuel rod pitch, in 0.496 Initial shoulder gap, inches 1.295 Number of fuel rods per assembly 264 Heavy metal loading per assembly, kg 463 Number of Grids Bottom end 1 Vaneless intermediate 1 Vaned intermediate 5 Mid-span mixing 3 Top end 1
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 1-4 Figure 1-1General Arrangement of Mark-BW/MOX1 Lead Assembly
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 1-5 Figure 1-2Locations of Lead Assemblies in Core R P N M L K J H G F E D C B A 1
2 3 MX01 4
5 6
7 8 MX02 MX03 9
10 11 12 13 MX04 14 15
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 2-1 2.0
SUMMARY
AND CONCLUSIONS Upon evaluation, all characteristics of the MOX lead assemblies were found to be within the criteria for reinsertion for a second cycle of irradiation. The assemblies were reinserted into Catawba Unit 1, and a second cycle of irradiation is currently in progress.
The results of the examinations support the conclusion that the Mark-BW/MOX1 lead assemblies are performing safely and as expected. The results support the eventual licensing of the Mark-BW/MOX1 fuel design for batch irradiation.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 3-1 3.0 METHODS, PROCEDURES, AND EQUIPMENT This section discusses methods, procedures, and equipment for the poolside PIEs.
Consistent with previous plans (Reference 2, Table 8.1), the examinations included measurements of fuel assembly growth, fuel rod growth, and fuel assembly bow, as well as fuel assembly and fuel rod visual exams. Table 3-1 compares the planned extent of examination with the actual extent. In each case, the actual extent equals or exceeds the planned extent.
It is often necessary to distinguish the four faces of a fuel assembly. The faces are often denoted by the compass directions (north, etc.) taken when the assembly is in reactor, but other nomenclatures are used as well. Table 3-2 provides a comparison of several different nomenclatures.
In accordance with standard practice, the fuel assemblies were inscribed with unique serial numbers (NJ13GE through NJ13GH) on the south faces of the upper end fittings.
Additional identifiers (MX01 through MX04) were inscribed on the north faces. This report primarily uses the additional identifiers, but some of the tables, such as Table 4-1 below, provide the equivalent serial numbers as well.
The results of the PIEs are given in Section 4.0.
3.1 Visual Examinations Visual examination is a qualitative survey of the periphery of the fuel assembly. It matches the plans for both fuel assembly and fuel rod examinations in Reference 2, Table 8.1.
Visual examinations were recorded with a video camera. The camera was lowered into the spent fuel pool and secured in position. The fuel assembly to be examined was placed in guide rollers and moved vertically with a hoist. The entire vertical length, from lower end fitting to upper end fitting, was examined. To provide more detailed images, the camera was placed so that the field of view was narrower than the width of the fuel
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 3-2 assembly. The length of each face was scanned twice to provide full coverage of each face.
The video signal was recorded on digital versatile disks (DVDs) for later review. For identification purposes, the video image was overlaid with text that identified the reactor, fuel assembly, fuel assembly face (north, east, south, or west), time, and date. The video record can be conveniently reviewed on a computer, and individual still images can be extracted and printed.
3.2 Fuel Assembly Growth Measurements Fuel assembly growth was determined by measuring the length of the fuel assembly after irradiation and comparing it to the length before irradiation. The method for measuring fuel assembly length uses a gage rod, sometimes known as a dipstick. The equipment includes [
]
[
]
[
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 3-3
]
The net fuel assembly growth is determined by subtracting the as-built length of the fuel assembly from the length after irradiation. The as-built length was determined by averaging measurements, taken when the fuel was manufactured, of [
]. The measurements are corrected for thermal expansion of [
].
Fuel assembly growth measurements might also be called guide tube growth measurements. Irradiation growth of the end fittings is negligible, because (1) these components have a small vertical dimension and (2) the fast neutron fluence at the end fittings is small compared to that in the active length, so the relative change in the vertical dimension is also small.
3.3 Fuel Rod Growth Measurements Fuel rod growth is not measured directly but is deduced from measurements of fuel assembly growth and shoulder gap, where shoulder gap is the clearance between the top end of a fuel rod and the lower surface of the upper end fitting.
[
]
[
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 3-4
]
The initial shoulder gaps were measured when the fuel assemblies were manufactured, so the change in shoulder gap can be determined by subtracting the as-built shoulder gap from the irradiated shoulder gap. Changes in shoulder gap are normally negative.
Fuel rod growth is equal to fuel assembly growth minus the change in shoulder gap.
3.4 Fuel Assembly Bow Measurements Fuel assembly bow is measured semi-quantitatively. [
]
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 3-5 Table 3-1Extent of Poolside Examinations Inspection Planned Extent Actual Extent Fuel assembly visual All assemblies All assemblies Fuel rod visual Peripheral rods on all All peripheral rods on all assemblies assemblies Fuel assembly growth All assemblies All assemblies Fuel rod growth (shoulder gap Two assemblies, two longest Two assemblies, at least 16 closure) peripheral rods in each peripheral rods per assembly, assembly plus qualitative evaluation of the remaining two assemblies Fuel assembly bow Two assemblies, two faces All assemblies, two faces per per assembly assembly
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 3-6 Table 3-2Nomenclatures for Fuel Assembly Faces Compass Face Engraved Fuel Rod Direction Number Identifier Positions North 1 MX_ _ A1 through Q1 East 2 (none) Q1 through Q17 South 3 NJ_ _ _ _ A17 through Q17 West 4 (none) A1 through A17
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-1 4.0 RESULTS This section presents the results of the poolside PIE. It also compares the results to the quantitative acceptance criteria for reinsertion when such criteria are applicable.
4.1 Visual Examinations A complete video record was made of all faces of all four lead assemblies. The record was stored in digital form on DVDs and for later review. The visual inspections indicated that the fuel assemblies are performing normally, that is, like low enriched uranium fuel assemblies. These inspections do not require mathematical analysis. Sample photographs from the video record are shown in Figure 4-1 through Figure 4-6. As is described in Section 3.1, the individual video images do not cover the full width of a fuel assembly, so each of these figures shows first the left side followed by the right side.
There is some overlap between the two images. To indicate the extent of overlap, the center (ninth) rod on the face is marked with 9 below each image.
4.1.1 Fuel Assembly Examinations The video record documents the appearance of the periphery of the assembly, including fuel rods, spacer grids, mid-span mixing grids, and end fittings. All grids were found to be in excellent condition, with very little corrosion and no mechanical damage.
4.1.2 Fuel Rod Examinations The video record documents the appearance of the peripheral fuel rods. All fuel rods appear to be in excellent condition, with light, uniform oxidation.
4.2 Fuel Assembly Growth Measurements Fuel assemblies are held in position by the lower and upper core support plates, and an axial clearance is provided between the upper end fitting and the upper core support plate to accommodate fuel assembly growth during irradiation. The clearance is taken up by the holddown springs. However, if fuel assembly growth was excessive, the clearance could be completely consumed, and there would be interference between the fuel assembly and core support plates. Interference is undesirable because it could
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-2 result in damage to the fuel assembly. The potential for interference is greatest under cold conditions because the coefficient of thermal expansion is greater for the reactor internals than for the fuel assembly guide tubes.
The fuel assembly axial clearance will depend on the fuel assembly design and will vary slightly from one reactor to another because of differences in the as-built dimensions of the internals. For a Mark-BW/MOX1 fuel assembly of nominal length, the minimum clearance at beginning of life was determined to be [0.000] inch. It is known that the fuel assembly growth rate decreases with increasing burnup (Reference 3, p. 6-25), so the allowable fuel assembly growth at the end of the first cycle of irradiation was conservatively chosen to be [0.000] inch, or half of the initial axial clearance.
Table 4-1 reports fuel assembly growth. Because of rounding, some results may appear to be in error by 0.001 inch.
4.3 Fuel Rod Growth Measurements Just as axial clearance is required for the fuel assemblies, it is also required for the fuel rods. Fuel rod growth during irradiation typically results in a reduction in the axial clearance between the top end of a fuel rod and the lower surface of the upper end fitting, or shoulder gap. Interference between the fuel rods and end fittings is undesirable because it could result in distortion of the fuel rods and damage to the assembly. As with fuel assembly growth, the criterion for reinsertion was that the shoulder gap remaining at the end of the first cycle of irradiation must be at least half of the initial shoulder gap, or [0.000] inch. This value is based on the minimum initial shoulder gap that is consistent with design tolerances rather than on the nominal value given in Table 1-1.
The fuel rod shoulder gap was measured directly as described in Section 3.3. Only MX01 and MX02 were measured, but the visual examinations indicated that the shoulder gaps for MX03 and MX04 were comparable to those for MX01 and MX02.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-3 Table 4-2 provides a summary of the shoulder gap measurements, adjusted to room temperature. Blank cells indicate that a measurement was not taken. The peripheral fuel rods are identified by a face (north, west, etc.) and a number (1 to 17), where the number is assigned by counting from left to right across the face of the assembly.
Alphanumeric fuel rod locations are provided in parentheses after the shoulder gap measurements. The shoulder gaps for some corner rods were measured twice because these rods are in two different faces.
The minimum and average measured shoulder gaps are [0.000] inches and [0.000]
inches, respectively, on the basis of the combined data for MX01 and MX02. The criterion for reinsertion was that the minimum remaining shoulder gap must be at least
[0.000] inch. Therefore, the fuel assemblies satisfy the criterion.
It will be noted from Table 4-2 that the shoulder gaps for fuel assembly MX02 are fairly tightly distributed, whereas assembly MX01 has some unusually large shoulder gaps, such as [0.000] inches for rod 12 on the south face. The large shoulder gaps occur where the fuel rods have been reworked, that is, where the first seal weld was unsatisfactory. Rework involved cutting off the upper end plug and weld, and welding a new upper end plug. The length tolerance for the overall length of the fuel rods had been chosen to accommodate such rework.
Table 4-3 lists the as-built and irradiated shoulder gaps for each measured fuel rod, plus the derived fuel rod growth, which is the decrease in shoulder gap plus the assembly growth. As in Table 4-2, duplicate measurements for corner rods are both tabulated.
4.4 Fuel Assembly Bow Measurements Fuel assembly bow was measured for the north and west faces of all four assemblies.
Measurements were taken in accordance with the process described in Section 3.4. A displacement of the fuel assembly to the left, relative to the tape, is taken as positive.
Note that the spacer grids are numbered sequentially, with grid 1 near the top of the assembly and grid 8 near the bottom.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-4 The results of the fuel assembly bow measurements are tabulated in Table 4-4 and plotted in Figure 4-7 and Figure 4-8. The maximum displacement is about [0.00] inch, which is reached on the north face of assembly MX03. This amount of bow is within the experience base for low enriched uranium fuel assemblies and was considered acceptable for reinsertion of the fuel assemblies for a second cycle of irradiation.
There does not appear to be a strong correlation among the fuel assembly bows. If the entire core had a significant bow in one compass direction, all four curves in Figure 4-7 and Figure 4-8 should be similar, but that is not seen. There could also be a systematic tendency for the lead assemblies to bow toward or away from the center of the core as a result of gradients in neutron fluence. In that case, pairs of assemblies on opposite sides of the core (MX01 and MX04, or MX02 and MX03) should have opposite bows, but that is likewise not evident. The lack of a strong correlation among the fuel assembly bows is reasonable in light of the small bow displacements.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-5 Table 4-1Fuel Assembly Growth Measurement Fuel Assembly MX01 MX02 MX03 MX04 NJ13GE NJ13GF NJ13GG NJ13GH
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-6 Table 4-2Fuel Rod Shoulder Gaps Assembly MX01 Face (NJ13GE)
North West South East Rod Number Shoulder Gap, inches Assembly MX02 Face (NJ13GF)
North West South East Rod Number Shoulder Gap, inches
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-7 Table 4-3Fuel Rod Growth Assembly MX01 (NJ13GE)
Rod Location Shoulder Gap, inches Fuel Rod As-Built Irradiated Growth, inches
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-8 Table 4-3Fuel Rod Growth (Continued)
Assembly MX02 (NJ13GF)
Rod Location Shoulder Gap, inches Fuel Rod As-Built Irradiated Growth, inches
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-9 Table 4-4Fuel Assembly Bow Assembly MX01 Face (NJ13GE)
North West Spacer Grid Number Assembly Bow, inches Assembly MX02 Face (NJ13GF)
North West Spacer Grid Number Assembly Bow, inches
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-10 Table 4-4Fuel Assembly Bow (Continued)
Assembly MX03 Face (NJ13GG)
North West Spacer Grid Number Assembly Bow, inches Assembly MX04 Face (NJ13GH)
North West Spacer Grid Number Assembly Bow, inches
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-11 Figure 4-1Top Ends of Fuel Rods as Seen on West Face of MX01 9 9
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-12 Figure 4-2Top End Grid as Seen on West Face of MX01 9 9
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-13 Figure 4-3Third Spacer Grid from Top as Seen on West Face of MX01 9 9
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-14 Figure 4-4Middle Mid-span Mixing Grid as Seen on West Face of MX01 9 9
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-15 Figure 4-5Bottom End Grid as Seen on West Face of MX01 9 9
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-16 Figure 4-6Bottom Ends of Fuel Rods as Seen on West Face of MX01 9 9
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 4-17 Figure 4-7Fuel Assembly Bow, North Face 10.000 MX01 9.000 MX02 MX03 8.000 MX04 7.000 6.000 5.000 4.000 3.000 2.000 1.000 0.000 1 2 3 4 5 6 7 8 Figure 4-8Fuel Assembly Bow, West Face 10.000 MX01 9.000 MX02 MX03 8.000 MX04 7.000 6.000 5.000 4.000 3.000 2.000 1.000 0.000 1 2 3 4 5 6 7 8
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 5-1
5.0 REFERENCES
- 1. DCS-FQ-1999-001, Rev. 3, Fuel Qualification Plan, September 2006.
- 2. BAW-10238PA, Rev. 1, MOX Fuel Design Report, July 2004.
- 3. BAW-10240(P)-A, Rev. 0, Incorporation of M5' Properties in Framatome ANP Approved Methods, May 2004.
- 4. Letter from James R. Morris (Duke Energy) to Document Control Desk (U.S.
NRC), January 9, 2007, Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke), Catawba Nuclear Station, Unit 1, Docket Number 50-413, Operating Report for Cycle 16 Operation with Mixed Oxide (MOX) Fuel Lead Assemblies, with attachment.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 6-1 6.0 APPENDIX This appendix provides information on operation of Catawba Unit 1 during the first cycle of irradiation of the MOX lead assemblies.
A report recently issued by Duke (Reference 4) provides boron concentration and full-core flux maps for various times during the cycle. Reference 4 includes the measured assembly relative radial power density for the lead assemblies at selected times during irradiation. The locations of the lead assemblies in core are shown in Figure 1-2.
Table A-1 summarizes the core operation history for Catawba Unit 1 Cycle 16. The cycle included one outage due to loss of offsite power (NRC event 42592), which lasted from May 20, 2006 to June 10, 2006.
AREVA NP Inc. ANP-10280NP Revision 0 Poolside Postirradiation Examination of MOX Lead Assemblies Page 6-2 Table A-1Catawba Unit 1 Cycle 16 Core Operation History Lead Start Date End Date Cycle Assembly Maximum Assembly Length Average Rod Average Cycle (EFPD) Burnup Burnup (GWd/MThm) (GWd/MThm) 1 Jun. 5, 2005 Nov. 11, 2006 499 22.0 26.1