ML19208D383
| ML19208D383 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/30/1979 |
| From: | Meyer R EMVGA, GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML19208D381 | List: |
| References | |
| GA-A15465, NUDOCS 7909280343 | |
| Download: ML19208D383 (110) | |
Text
{{#Wiki_filter:;, - s G A-A15465 FORT ST. VRAIN IN-CORE INSPECTION REGION 35 AND REGION 13 CORE SUPPORT BLOCK by R. J. MEYER HMTIL JUNE 1979 1052 303 7909280343
'Y GENERAL ATOMIC COMPANY
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l G A-A15465 ; c e 2 e i j l FORT ST. VRAIN IN-CORE INSPECTION
! REGION 35 AND REGION 13 ia CORE SUPPORT BLOCK >
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R. J. MEYER < 5 5 c. C
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IBMBE l L p l a [s GENERAL ATOMIC PROJECT 1900 ) JUNE 1979 1052 304 {
- GENERAL ATOMIC COldPANY
- - - - - - - - - - . - - - - - . - - ~.
ACKNOWLEDGMENTS The author wishes to thank several individuals for their assistance in preparing this report: Karen Leadley - data reduction Mike Dolphin - summary and data for RT-518, Sections IV and VT Leigh Sovier - interpretation of photos and videotapes Roko Bujas - observations made at FSV site 1052 305 i
TABLE OF CONTENTS ACKNOWLEDGMENTS
- 1.
SUMMARY
AND RESULTS . . . . . . . . . . . . . . . . . . . . ... 1 1.1 Region 35 Excluding Core Support Block . . . . . . . . ... 1.2 Core Support Block Inspection in Regions 35 and 13 . . ... 3 1.3 Other Regions' Inspections . . . . . . . . . . . . . ... 3
- 2. INSPECTION OF REGION 35 (RT-513) . . . . . . . . . . . . . . ... 5 2.1 Core Visual Inspection Before Block Removal . . . . . . ... 5 2.2 Region 35 Element Removal and Inspection . . . . . . . .. 6 2.2.1 Plenum Elements . . . . . . . . . . . . . . . . ... 7 2.2.2 Fuel and Reflector Elements . . . . . . . . . . ... 7 2.2.3 Core Support Block . . . . . . . . . . . . . . . ... 9
- 3. INSPECTION OF REGION 13 CORE SUPPORT BLOCK . . . . . . . . . .. 11
- 4. IIOT CELL INSPECTION . . . . . . . . . . . . . . . . . . . . ... 12 4.1 Keyed Plenum Element - Column 6 Layer 1 RT-518 Block #6 . .. 14 4.2 Top Reficctor - Column 6 Layer 2 RT-518 Block #15 . . . ... 14 4.3 Fuel Element - Column 6 Layer 4 RT-518 Block #29 . . . ... 14 4.4 Control Ft.el Element - Column 1 Layer 4 RT-518 Block #42 .. 15 4.5 Side Reflector - Column 17 Layer 6 RT-518 Block #51 . . ... 15 4.6 Fuel Element - Column 6 Layer 7 RT-518 Block #59 . . . . . 15 4.7 Fuel Element - Column 3 Layer 9 RT-518 Block #74 . . . ... 16 4.8 Bottom Control Fuel Element - RT-518 #80 . . . . . . ... 16 4.9 Bottom Control Reficctor - Column 3 Layer 10 RT-518 Block #106 . . . . . . . . . . . . . . . . . . . . . . ... 17 4.10 Bottom Reflector - Column 3 Layer 12 RT-518 Block #99 . ... 17 4.11 Unscheduled Inspection of Block #83 . . . . . . . . . . ... 18
- 5. ANALYSIS OF Tile DARK STAINS . . . . . . . . . . . . . . . . .. 19
- 6. CONFORMATION OF CORE BOUNDARIES - RT-518 SECTION IV . . . . ... 20 1052 306 ii
TABLE OF CONTENTS (cont.1
- 7. CORE FMPPING RESULTS - RT-518 SECTION VI . . . . . . . . . . . .. 21
- 8. EXTRAPOLATION TO OT11ER REGIONS AND CORROBORATION OF FLUCTUATION TIIEORIES . . . . . . . . . . . . . . . . . . . . . .. 22 APPENDIX A - GA REQUEST FOR TEST RT-SI8, ISSUE 2 . . . . . . . . . .. 90 1052 307 iii
LIST OF TABLES A. Core Visual Inspection . ... . . . . . . . . . . . . . . . . .. 23 B. Stains . . . ....- - - - . . . . . . . . . . . . . . . .. 24 C. Rubbing . . ... .. .... . . , , , , , , , , , , , , , , ,, 25 D. Interface Marks . .. .... - - - - . . . . . . . . . . . . .. 26 E. Block Visual Inspection .... . . - . . . . . . . . . . . . .. 27 1052 308 iv
LIST OF FIGURES
- 1. Region 35 element map and RT-518 removal sequence . . . . .... 28
- 2. Surface damage criteria drawing . . .. .. . . . . . . . .... 29
- 3. Typical cask camera photo . . . .. . .. . . .. .. . . .... 31
- 4. Fuel element in llSF - block 29 .. . . . . . . .. . .. .... 32
- 5. Fuel element in llSF - block 29 - face 2 . . . .. . . . . .... 33
- 6. Top reflector in llSF - bicek 15 . . . .. . . ... . . . .... 34
- 7. Region 35 - top view . . . . . .. . .. . . . . . . . .. ... 35
- 8. Top reflector - block 15 - face 1 . . .. . .. . . . . . .... 36
- 9. Typical surface markings . . . .. .. . . . . . . .... 37
- 10. Interface marks - control fuel layer 4 . . .. .. . . . .... 38
- 11. Region 35 core support block . . . . .. . . .. . .. . .. . 39
- 12. Region 13 core support block . .. . . . . .. . . . . .... 40
- 13. RT-518 supplementary data sheet . . .. . ... .... .... 41
- 14. Top reflector - block 15 - bottom surOc4 . .... . . .... 42
- 15. Keyed plenum element - block 6 .. ... . . ... .. . .... 43
- 16. Keyed plenum element - block 6 .. . . . .. . .. . . .... 44
- 17. Keyed plenum element - block 6 . . .. . . . ... . .. .... 45
- 18. Keyed plenum element - block 6 .. .. . . . . ..... .... 46
- 19. Keyed plenum element - block 6 - contact pad ... .. ... .. 47
- 20. Keyed Plenum element - block 6 . . . ... ..... .. .... 48
- 21. Keyed plenum element - block 6 - closeup of keyway . . .. ... 49
- 22. Keyed plenum element - block 6 - inlet port . .... . . .... 50
- 23. Keyed plenum element - block 6 - shiny areas .... .. .... 51
- 24. Keyed plenum element - block 6 - shiny areas ... . . . .... 52
- 25. Top reflector - block 15 - top surface and dowels . .. . .. . 53
- 26. Top reflector - block 15 - bottom surface and sockets . . .... 54
- 27. Top reflector - block 15 - stains and rub marks . . .. . .... 55
~1052 309 v
LIST OF FIGilRES (cont.)
- 28. Top reflector - block 29 - small stain face 6 . . . . . . . . . . 56
- 29. Top reflector - block 29 - scrapes face 6 . . . . . . . . . . . . 57
- 30. Top reflector - block 29 - stains face 4 . . . . . . . . . . . . 58
- 31. Control fuel element - block 42 - interface lines . . . . . . . . 59
- 32. Control fuel element - block 42 - dowels and top surface . . . . 60
- 33. Control fuel element - bicek 42 - bottom surface . . . . . . . . 61
- 34. Control fuel element - block 42 - face 4 . . . . . . . . . . . . 62
- 35. Side reflector - block 51 - stains, rub marks, interface marks . 63
- 36. Fuel element - layer 7 - block 59 - face 2 . . . . . . . . . . . 64
- 37. Fuel element - layer 7 - block 59 - face 2 closeup . . . . . . 65
- 38. Fuel element - layer 7 - block 59 - bottom . . . . . . . . . . . 66
- 39. Fuel element - layer 7 - block 59 - dowels . . . . . . . . . . . 67
- 40. Fuel element - layer 9 - block 74 . . . . . . . . . . . . . . . . 68
- 41. Fuel element - layer 9 - block 74 . . . . . . . . . . . . . . . . 69 ,
- 42. Fuel element - layer 9 - block 74 - scrapes on face 4 . . . . . . 70
- 43. Fuel element - layer 9 - block 74 - dowels . . . . . . . . . . 71
- 44. Fuel element - layer 9 - block 74 - sockets . . . . . . . . . . . 72
- 45. Bottom control fuel - block 80 - face 3 . . . . . . . . . . . . . 73
- 46. Bottom control fuel - block 80 - face 1 . . . . . . . . . . . . . 74
- 47. Bottom control fuel - block 80 - face 6 . . . . . . . . . . . . . 75 48 Bottom control fuel - block 80 - interface marks . . . . . . . . 76
- 49. Bottom control fuel - block 106 - stains . . . . . . . . . . . . 77
- 50. Bottom control reflector - block 106 - scratches and chips . . . 78
- 51. Bottom control reflector - block 106 - face 4 closeup . . . . . . 79
- 52. Bottom control reflector - block 106 - face 5 . . . . . . . . . . 80
- 53. Bottom control reflector - block 106 - bottom . . . . . . . . . . 81
- 54. Bottom reflector - block 99 - face 1 . . . . . . . . . . . . . . 82
- 55. Bottom reflector - block 99 - bottom . . . . . . . . . . . . . . 83
- 56. Bottom reflector - block 99 - closeup face 4 . . . . . . . . . . 84
- 37. Bottom reflecter - block 83 - alcohol squirt . . . . . . . . . . 85
- 58. Bottom reflector - block 83 - after evaporation of alcohol . . . 86
- 59. Bottom reflector - block 99 - in liSF . . . . . . . . . . . . . . 87 vi -
LIST OF FIGURES (cont.)
- 60. Bottom reflector - block 15 - taking sample of stains . . . ... 88
- 61. Bottom control fuel - block 80 - after scraping . . . . . . ... 89 1052 5\\
vii
- 1. SISBIARY AND RESULTS 1.1 Region 35 Excluding Core Support Block During the refueling of region 35, a visual inspection of the hexagonal fuel and reflector riements was performed to determine if any .lamage had occurred during cycle 1 operation. Each element was videotaped and photographed. Core components adjacent to region 35 were inspected using the fuel handling machine (FIB 1) TV camera. Com-ponents observed and videotaped included the thermal barrier, top edge of the core barrel, permanent side reficctor, keyed plenum elements in adjacent regions, and orifice valves in regions 18, 34, and 36. Following the removal of all hexagonal fuel and reflector elements frm region 35, the top of the core support block was inspected with the FIB 1 TV camera.
With the region removed, the camera was traversed axially the full height of the core to observe the surfaces of the permanent side reflec-tor, the elements of regions 18, 34, and 36, and the vertical gaps between elements. A relative profile of the vertical walls surrounding the empty region was obtained using the FIBf head as a displacement probe. Ten preselected elements plus one other element from region 35 (Fig. 1) were moved to the hot service facility for further observation. In the hot cell, all surfaces of the eleven elements were videotaped and photographed using telephoto lenses with zoom. Some additional non-destructive inspection was performed on several elements in the hot cell. Ethyl alcohol was sprayed on two elements to enhance the surface finish. Several elements were scraped lightly to obtain samples of surface deposits for later chemical analysis. 1052 312 1
The principal results of the inspection were as follows: The core components and reactor internals observed prior to unloading region 35 were in good condition. No sign of damage of any kind was observ ed . The orifice valves in regions 18, 34, and .56 were stroked full open and full closed and operated smoothly. The gaps within and between region s were observed to be unifom and the top of the core is level. Dark stains were observed on the faces of most of the fuel and reflector elements removed from region 35. The general appearance of a typical stain was as if liquid had trickled down the face of an element and left a dark residue. Fiany elements had several stains c a cach face. Several samples of the residue were obtained by scraping the stained area. A ganma spectrographic analysis showed the residue composition was primarily iron and silicon. Other elements present in significant quanti-ties were aluninum, copper, and silver. The scraping confirmed that the stains were surface markings only and had not etched the graphite to any visible degree. Flany elements had surface marks on the vertical faces which are best described as resembling scratches. Flost of these were clearly shallow marks. A few of the marks at first appeared to have some depth to them, but they were shown to be only a surface condition by spraying ethyl alcohol on the element surface and observing the evaporation pattern. This is an accepted industry technique for visually enhancing cracks in graphite. The results showed clearly that the marks were not cracks. For differentiation from other types of surface marks these will be referred to as scratches throughout the balance of the report. Blany element surfaces and the plenum element keys had indications that contact between adjacent elements had occurred and that there was some relative motion at these contact surfaces. Horizontal lines appeared on all cides of mest control elements and on the sides of many standard elements facing the control column. These lines are the result of contact 1052 M 2
and relative motion of a top (or bottom) edge of a vertically offset element against a face of an adjacent element. These types of indications will be referred to as rub marks throughout the balance of the report. Traversing the side reflector wall with the fuel handling machine used as a displacement probe resulted in the conclusion that the side reflector wel; pofile is straight and no elements are displaced. The presence of surface rub marks appears to confirm that some relative motioa takes place between adjacent elements. From the appear-ance of the marks or the pattern of occurrence throughout the region, no definite conclusions can be made about the nature of postulated motion during fluctuations, since some motion and rubbing may occur during normal operation (without fluctuations) . The principal conclusions from the rubbing marks concerning core motion are that elements at all levels rub cgainst adjacent columns and result only in a surface burnishing of the faces in contact. There was no evidence of any physical damage to core ccuponents that could be related to reactor operation. 1.2 Core Support Block Inspection in Regions 35 and 13 TV 171spection of the core support block in regions 35 and 13 showed the surfaces exposed directly to coolant flow had different re-flectivity than surfaces in contact with hexagonal elements. The darker appearance is thought to be indicative of a change in surface finish caused by oxidation or abrasion due to particulate matter in the primary coolant. Several marks were observed on the core support block surfaces. After careful TV inspection, it was concluded that the marks were shallow scratches and stains. 1.3 Other Regions' Inspections During the refueling, regions 17, 10, 21, 28, and 5 were also inspected. Two photographs were taken of each element as it was withdrawn 3 1052 314
into the fuel handling machine. For each of these regions, two layers were also inspected with the FIN TV camera. No new types of markings or damaged element were discovered as a result of these inspections. It is concluded that the detailed inspection of the eleven elements from region 35 is representative of all regions involved in the refueling. 1052 315 4
- 2. INSPECTION OF REGION 35 (RT-518)
The visual inspection of s.cre components and reactor internals in and around region 35 was carried out according :o a GA Request for Test RT-518 Issue 2 dated February 12, 1979 (Appendix A). The inspection was performed beginning on Starch 2, 1979, and ending Starch 12, 1979, by Public Service of Colorado personnel with several General Atomic engineers acting as advisors and coordinators. The purpose of the RT was to inspect for evidence of fluctuation related motion and to ascer-tain whether there has been any damage to or deformation of core compo-nents as a result of fluctuations. Since several fluctuation theories postulated movement of columns and regions, a close scrutiny of the fuel and reflector element surfaces might show evidence of rubbing, impact, or marks made by elements leaning against each other. Inspection and acceptance criteria were developed from QC records of the elements before initial loading and GA Dwg. 90-R1801-202 which is a manufacturing damage criteria drawing. This drawing illustrates typical scratches, chips, and gopges that might occur during manufacturing (Fig. 2) . None of the observed surface marxings during the in-core inspection exceeded the above acceptance riteria and thus would not have been documented during fabrication of the alements. 2.1 Core Visual Inspection Gefore Block Removal The FHot TV camera was used to inspect the top of the core, the control rod guide tubes and orifice valves in regions 18, 34, and 36 and some reactor internals to the extent they could be seen. The internals observed were portions of the thermal barrier, the top edge of the core barrel, the permanent side reflector and spacer clocks, and the core barrel-to-side reflector keys. The TV camera was slowly s 1052 316
panned in the vicinity of region 35 while the condition of the components was studied on the monitor in the FIIM control room. The inspection was recorded on videotape. Orifice valves in regions 18, 34, and 36 were stroked through their full travel, while GA engineers ..atched for any erratic movement. The valves worked smoothly without
- ticking or vibrating. Inspection of the core components resulted in no damage being observed. All plenum elements were i place, the valves were properly seated and gaps within and between regions were uniform.
The thermal barrier core barrel and side reflector were judged to be in good condition. A tabulation of the inspection criteria and results s is given in Table A. 2.2 Region 35 Element Removal and Inspection As each element was withdrawn from the core into the FC1, it was held in front of a TV camera located in the Film cask and rotated slowly so all sides could be videotaped. The cask camera has 7:1 zoom capability and this was used frequently to study surface markings on the elements. In eddition, two 35 mm black and white photos were taken of each element for later study (Fig. 3) . Before unloading each layer, the FliM TV camera provided close up viewing of the element top surfaces and dowels. No cracked or chipped dowels were observed during the entire inspection. No dents or crushed areas were observed on any dowels. The top surfaces of many blocks showed small shallow scratches probably caused by the FIIM grapple head during handling. In general, the surfaces were clean with no evidence of damage. The top edges of coolant holes were free of any chips. On block 83, a half ler.gth lower reflector in column 3, some faint marks were observed on the top surface and were described as "possible cracks" This element was later inspected in the hot service facility and judged to be free of cracks after ethyl alcohol was applied to the surface to enhance 1052 317 6
visite. lity of any cracks. Further discussion of the hot service faci-lity inspection appears below. During the videotaping and taking of 35 mm photographs in the FIN cask, the following observations were made: 2.2.1 Plenum Elements Shiny areas were noted on the edges of the male keys and on the raised contact pads on each face. These surfaces are coated with chromium carbide to reduce friction and wear if rubbing con-tact is made. 'The shiny areas suggest that light slidiag contact between plenum elements had burnished portions of the carbide coat-int. The coating itself was intact with no evidence of spalling. No evidence of impact was observed. The elements, being of low alloy steel (2-1/4*. chrome l'. moly) showed some discoloration probably due to the levels of moisture experienced in the reactor. Some light surface stains were seen on some faces of the keyed elements. The general appearance and condition of all plenum elements was very good. 2.2.2 Fuel and Reflector Elements The faces of the hexagonal graphite fuel and reflector elements were marked by dark stains (Figs. 4 - 6) as if a dark viscous liquid had dripped down the sides of the elements. The marks appeared to be several millimeters wide and usually ran the full height of the element. The staining was frequently observed on top reflector elements and on some upper layer fuel elements (Table B). The frequency with which stains were observed and the darkness of the stains themselves diminished at mid-core but then increased again in the bottom reflectors. The heaviest staining was seen on the upper reflectors. Although the stains appeared to be surface marks only, TV camera inspection limits the depth perception of the observer. An important clue to the depth 1052 318 7
of the marks was visible in close up pictures using the zoom capability of the TV camera lens. Jhc surface machining marks left during manu-facturing were often visible through the stain. This indicates that no etching of the surface had taken place and that the marks were surface residue only. A tabulation of the location in the region of each element face on which stains appear is given in Table B. The numbering of the element faces and the relative location of elements in region 35 is illustrated in Figures 1 and 7. Stains were seen most frequently in column 1, tl.c control column. Column 2 was generally free of stains. Some stains did appear on fuel elements in the lower layces of the fuel (7, 8, and 9) in columns 3, 4, and 5; but few stains were observed on upper layers in these columns. In general, it was not possible to establish a consistent pattern of staining throughout the region. There was no continuity of the paths of stains between elements since the liquid evidently could run down the face of one element (without contacting the face of an adjacent element) and then flow horizontally at the lower edge of the face before continuing down the next element. In some cases, the liquid appears to have run down the face of one element, jumped the gap, and continued down the face of an element in an adjacent column. In several instances, the pattern of vertical stains discussed above was disrupted midway down the face of an element by the top edge of an adjacent offset element (Fig. 8). The top edge of the adjacent element leaning against the stained element caused the staining liquid to run horizontally and disperse. Observation of this phenomenon served as further evidence that the marks were surface stains only and were not material defects or cracks due to impact. Other marks observed during the block inspection were light scratches, shallow surface scrapes, and some areas where rubbing between faces of adjat ent elements had occurred (Fig. 9). The evidence of 1052 319 8
rubbing between elements is of particular interest since explanations of core temperature fluctuations have postulated movement of fuel and reflector elements. The elements and specific faces where evidence of rubbing was observed are tabulated in Table C. Although it seems from the table that 'he rubbing marks were most frequently seen on sides 3 and 6, this is biased by the camera angle during photographing. These two sides were always directly facing the camera, allowing a more detailed examination of surface markings. A more significant observa-tion is that the side reficctor elements columns 17, 7, and 9 have more rub marks than the fuel element columns 3, 4, 5, and 6. This suggests that reflector columns may have experienced either higher rubbing forces or more frequent rubbing (or both). A particular type of rubbing mark has been labeled " interface marks". They appear on an element face as a single horizontal line and are most frequently observed on control column elements (see Table D). The control column is vertically offset in a region and the interface marks are the result of contact with the top (or bottom) edge of an adjacent element in an offset column. The marks are clearly surface rubbing marks and not surface indentations from impact. It is likely that the interface marks were the result of columns leaning together for extended periods during operation. As expected, the control elements show these marks on all faces (Fig. 10) whereas the standard elements have marks only on the side facing the control column. Interface marks were also observed on several faces of reflector column elements not adjacent to the control column, particularly column 17. Horizontal interfaces between permanent side reficctor blocks were the source of the marks on adjacent hex side reflectors. 2.2.3 Core Support Block Following the removal of layer 12 hex bottom reflector elements, the top surface of the core support block was viewed with the FIB! TV camera. The most striking observation was a visible pattern of the
; 0 1 [,l t, a o .
9
coolant flow path. The portions of the core support block top surface that had been directly exposed to helium flow appeared much darker than surfaces covered by solid reflector material (Fig. 11). The coolant from the control column impinges directly on the center of the core support block and is ducted radially outward through six slots cut in the bottom reflector elements. The dark appearance of the core sup-port block surface is thought to be the result of surface oxidation or abrasion due to particulate matter in the primary coolant causing a change in surface roughness and thus light reflectivity. Another possibility is that the marking was a dust pattern but the absence of dust collections anywhere else in the region tends to discount this explanation. Later viewing of the videotapes brought about some con-cern over some marks that to some viewers looked like hairline cracks on the surface of the support floor. Disagreement that existed over the nature of these marks led to a second, more thorough TV inspection of the support block surface. After close scrutiny of these faint marks, observers agreed that they were the edges of light stains on the surface of the block. No chipped edges or any evidence of structural damage was observed during the inspection, and it was concluded that the core support block is in sound condition. 1052 321 10
- 3. INSPECTION OF REGION 13 CORE SUPPORT BLOCK On May 1,1979, at the request of the NRC, region 13 was unloaded and a visual inspection made of the top surface of the core support block. The reactor viewing device (TV camera) was employed and video-tapes were recorded. The support block appeared cican and no cracklike features were identified. Two small chips of no structural consequence were noted. The same dark pattern of areas exposed to primary helium flow was observed similar to that seen in region 35. The general con-clusion is that the support block in region 13 is structurally sound and without visible degradation (Fig. 12).
1052 322 11
- 4. Il0T CELL INSPECTION Ten elements were selected for inspection in the hot service facility (ilSF). They included one keyed plenum element, five fuel elements, and four reflector elements. The particular elements were chosen to provide a variety of physical types and on the basis of material strength records. Since there was interest in possible structural damage, an effort was made to choose elements fabricated from graphite logs with lower than average tensile test elements.
The elements inspected in the llSF are as follows. Location RT-518 IYP" Block # Column Layer Keyed Plenum 6 1 6 Top Reflector 6 2 15 Fuel 6 4 29 Control Fuel 1 4 42 Side Reflector 17 6 51 Fuel 6 7 59 Bottom Control Fuel 1 8 80 Fuel 3 9 74 Control Reflector 1 10 106 Bottom Reflector 3 12 99 Each element was thoroughly inspected and the condition of the surface feat-res was documented according to RT-518, which requires that data shec:s (Fig. 13) and Table E be completed for each element. k03-12
Drawing 90-R1801-202 (Fig. 2) and the procedures of RT-518 (Appendix A) were used as a damage criteria guide during the inspection. The drawing was originally used during Quality Control Inspectio.i of the elements during fabrication to standardize the acceptance of elements which had small chips and surface scratches. The inspection procedure followed for each element in the hot service facility was as follows: With the FIB 1 positioned over the hot cell, the element was lowered until the bottom of the element was just clear of_ the refueling sleeve and visible to the observers stationed outside the hot cell window (Fig. 14). The sottom surface o- the o ement was observed with the aid of close range 7 x 35 field binocu-lars. Particular (s.phasis was placed on close inspection of the dowel sockets. A minimum of two black and white photos were taken of the bottom of the element. A 35 mm single lens reflex camera was used with either a 100-300 mm zoom lens or an 80-210 mm zoom. Kodak TRI-X (ASA 400) and Kodak PLUS-X (ASA 125) film was used. No flash was utilized due to possible reflections of the hot cell window. The existing bank of lights in the hot cell provided adequate lighting. In addition to the photographs, two remote TV cameras with zoom and pan capability were placed inside the hot cell and used to transmit pictures to the r!BI control room where videotapes were recorded on 90 minute cassettes (Type KC). Each element was lowered into the coil and rotated in order that each face could be photographed and videotaped. The element was then set on the floor of the hot cell and the FIB 1 grapple head withdrawn to permit inspection of the top surface and dowels. Close up photos and videotapes were also taken of the top surface. A summary of ti.e observations for each element inspected in the ilSF is presented below. 1052 324 13
4.1 Keyed Plenum Element - Column 6 Layer 1 RT-518 Block #6 The metal plenum elements appeared structurally sound and showed no evidence of damage from impact. The edges of the male keys and the raised contact pads had small shiny areas that indicated some rubbing had taken place between adjacent elements (Fig. 15). The keys and pads are plasma sprayed with chromium carbide to reduce friction and wear. The co,'ted areas appear to be in gooc. shape with no sign of chipping or spalling. Light stains were observed on all faces of this element includi g the top surface which appeared to have several puddles of residue in it (Fig. 16). The stains were evic ant ly the result of a liquid which dripped on the element from above and the.. dried and left a visible residue. No evidence of corrosive action was visible and the liquid did not appear to have etched the surface of the element (see Figs. 17 - 24). 4.2 Top Reflector - Column 6 Layer 2 RT-518 Block #15 The top and bottom surfaces were clean and no damage of any kind to the dowels and sockets was visible (Figs. 25 and 26). All six sides of the element were stained with dark lines. The stains were several millimeters wide and usually ran the full length of the element. A discon-tinuity in the stain pattern was seen on face 1 (Fig. 8) where midface contact was made by the top edge of an adjacent vertically offset element. Several faces showed evMence of rubbing with adjacent elements. There was a pattern of surface burnishing on these faces that one could expect from face to face contact accompanied by relative lateral movement of the elemer.a (Fig. 27). The element was free of chipped edges or cracks. 4.3 Fuel Element - Column 6 Layer 4 RT-518 Block #29 Dark stains were observed on all faces of this element. On face 6, the stain was only one inch long and was located near the center 1052 325 14
of the face (Fig. 28). On the same face, a 2" x 10" (Fig. 29) surface scrape was visible. Its origin could not be determined for certain, but it probably occurred during fabrication. The top and bottom surfaces of this element including dowels and sockets were free of any chips, cracks, or signs of impact damage. No surface burnishing was seen indicating that rubbing contact with adjacent columns was minimal (Fig. 30). 4.4 Control Fuel Element - Column 1 Layer 4 RT-518 Block #42 Light stains were observed on three faces and a small chip was barely visible on the edge between faces 1 and 2 (Fig. 31). It is surmised that the isolated chip occurred during fabrication. Dowels and sockets were in excellent condition (Figs, 32 and 33). A single horizontal line was visible on all faces corresponding to the one-quarter block offset of the control column (Fig. 34). Other marks were characterized as light surface scratches. No damage from impact or rubbing was seen. 4.5 Side Reflector - Column 17 Layers 6 RT-518 Block #51 Light stains and surface scratches were noted on faces 3, 4, 5, and 6. A single horizontal line was visible on faces 3 and 4 (Fig. 35). These lines correspond to an interface between permanent side reflector blocks directly adjacent to this element. Several faces had signs of surface burnishing indicating some degree of rubbing contact with adjacent elements. These rubbing marks appear as machining marks that have been hignlighted by face to fact contact between adjacent elements. In no case did the rubbing abrade the surface enough to remove the machine tool marks. 4.6 Fuel Element - Column 6 Layer 7 RT-518 Block #59 Face 2 had four dark vertical stains which ran the full height of the element (Figs. 36 and 37). Face I had a single long stain 1052 326 1
similar to those on face 2. Some ligh. scratches were noticed but no evidence of impact damage was seen. The top and bottom of the element were clean and in good condition. On the bottom surface, a pattern was made by the recessed fuel plugs in the element directly below. The fuel plug locations appear as lighter colored dots on the darker bottom surface (Fig. 38). No chips or cracks were noted on any of the surfaces. The dewels and sockets were likewise free from any visible damage (Fig. 39). 4.7 Fuel Element - Column 3 Layer 9 RT-518 Block #74 Several faces had sery light stains and irregular surface scratches. The stains were the same type as the dark stains noted on elements in higher layers but the marks are very faint (Fig. 40). Some evidence of rubbing with adjacent elements was visible in the form of shiny areas on the faces (Fig. 41) . The most distinctive marks on this element were a series of scrapes on faces 2 and 4 (Fig. 42). The best explanation tion of these marks is that they were made during element handling as the element was scraped against a storage rack inside the FIIM. The dowels and sockets were in good condition and no chips or cracks were noted anywhere on the element (Figs. 43 and 44). 4.8 Bottom Control Fuel Element - RT-518 Block #80 Dark stains were present on all faces except face 1 (Fig. 45). Long vertical scratches on faces 5 and 6 appeared to have been made during fuel handling. The diagonal scratch on face I was probably made during fabrication (Fig. 46) . Some faint evidence of rubbing was seen on faces 1, 4, and 6 indicating some relative movement between this element and those adjacent to it (Fig. 47). As expected for a control column element, all six faces were marked with a horizontal line corresponding to the 1/4 block offset (Fig. 48). Aside from the surface markings noted, the element was structurally in good condition. No cracks or chips of any kind were observed. 1052 327 16
4.9 Bottom Control Reflector - Column 3 Layer 10 RT-518 Block #106 Dark vertical stains were observed on faces 2, 3, and 5 (Fig. 49) . All faces had light scratches and scrapes which probably were made dur-ing fuel handling or fabrication (Figs. 50 and 51). Some small chips could be seen near the top edge of the element between faces 4 and 5 (Fig. 52). The dowels and sockets were in good condition. The bottom of r'e element had a shallow gouge which had been made during fabrication. Evidence of this gouge was visible on the core support block where there was a discoloration corresponding to the location of the gouge (Fig. 53) . 4.10 bottom Reflector - Column 3 Layer 12 RT-518 Block #99 The dowels and sockets of this element were found to be free froa any chips, cracks, or dents. There was a small chip on the corner edge be-tween faces 5 and 6. Dark stains were observed on faces 1, 5, and 6. Light scratches, barely visible, were noted on all faces (Fig. 54). The bottom of the element had a darker area corresponding to the portion of the element that hangs past the edge of the core support block (Fig. 55). In general, throughout the inspection, it was noted that surfaces exposed directly to helium flow, including gap flow, had taken on a darker appearance. A pos-sible explanation is that oxidation or abrasion due to particulate matter in the primary coolant causes a change in surface finish which alters reflec-tivity. On face 4, two marks were observed that had the appearance of small cracks (Fig. 56). To ascertain the depth of these marks, ethyl alcohol was sprayed on the surface and the evaporation process observed. The alcohol dried evenly and did not accent the marks. It was concluded that the marks were only shallow scratches since even a small crack in graphite will show up well after an alcohol application. This procedure is a widely used method for detecting small cracks in graphite. The alcohol seeps into the crack and evaporates more slowly than the liquid 1052 328 17
on the surface. In this case, the inniform evaporation demonstrated that no crack was present. 4.11 Unscheduled Inspection of Block #83 Inspection of an additional reflector element from column 3 layer 10 was performed after TV camera viewing in core resulted in some disagreement over the nature of the marks on the top surface. The block was set on the floor of the llSF and sprayed with ethyl alcohol to highlight any possible cracks. No evidence of cracks was observed although several Iight scratches and stains were seen upon close viewing. It was con-cluded that these scratches and stains were the marks that had appeared to be hairline cracks when viewed through the Film TV camera. Although not originally scbcduled for close inspection, block 83 was checked over and photographed in the sama manner as the other ten elements. No damage of any kind was observed. (Figs. 57 and 58). 1052 329 18
- 5. ANALYSIS OF Tile DARK STAINS During the llSF inspection of the 11 elements from region 35, samples were taken of the dark residue observed on the faces of many blocks (Fig. 59) . The samples were obtained by holding a small metal dish with the manipulator arm and scraping the stained area with the edge of the dish (Fig. 60) . This method also confirmed that the residue had not etched the graphite (Fig. 61). The residue samples were subjected to gamma spectrographic analyses. A high concentration of silicon and iron was detected with lesser amounts of aluminum, copper, and silver.
The high iron concentration was expected considering the water ingresses into the PCRV that have occurred. The silica is believed to have come from the Knowool insulating materials used in the core. The aluminum compositions are probably also derived from the insulation. Most other metallic components present in the analyses such as copper can be traced to alloys of reactor components or components in the water system. The only metallic composition found in the sample which is not available from metallic components is silver. A 100 ppm concen-tration of silver was detected and it is believed to have been released from the fuel . 1052 330 19
- 6. CONFORMATION OF CORE BOUNDARIES - RT-518 SECTION IV The Film grapple head was used to traverse the boundary of region 35 in order to obtain a profile of the void left by the removal of the region. No abnormalities were found. The side reflector walls were continuous and straight and no elements were offset. Accurate measure-ments were difficult due to the insensitivity of the FIN sensors and FIN tube deflection. The indication by the probe of interfaces between blocks was verified by the pick up position established during unloading.
Although the data charts indicate that the walls are straight but not quite vertical, the Film tube deflection is thought to account fcr this discrepancy. 1052 331 20
- 7. CORE MAPPING RESULTS - RT-518 SECTION VI An attempt to confirm the relative positian of each element in the region was made by tabulating the block pick up positions as indicated by the FIB 1. Increased deflection of the Fibt grapple head as the tube was more fully extended resulted in indicated block locations that were not sufficient ly accurate to permit a consistent reconstruction of the region element by element.
1052 332 21
- 8. EXTRAP01.ATION TO OTilER REGIONS AND C0xROB0 RATION OF FLUCTUATION THE0;; IFS _
During the refueling of regions 17, 10, 21, 28, and 5, two photo-graphs were taken of each element as it was withdrawn into the fuel handling machine. A review of these pictures shows that the stains, scratches, and rub marks and other surface discolorations observed are similar to those on the elements of region 35. In no case were any new types of markings observed on elements from other regions. For each region, the Film TV camera was panned across the top of two layers, enabling close inspection of the dowels and top surface of each element. No damage to dowels or the top surfaces was seen. The conclusion is that the detailed inspection of the eleven elements from region 35 provided an accurate representation of the condition of all the elements involved in this refueling. Iluctuation theories postulating movement of core elements were supported by the observation of the rubbing marks on many of the elements. Also the horizontal lines corresponding to the control column offset are indications that columns lean against each other and rub to some degree. In general, no pattern of rub marks throughout the region was identified that could suggest the mechanism by which the columns move. No conclusion can be drawn as to whether element movement is more fre-quent or more severe during periods of fluctuations. The inspection has verified that core elements are structurally undamaged and that movement of columns and regions takes place during operation. 1052 333 22
Table A Core Visual Inspection Componcnt Criteria inspection Results*
- 1. Thermal Barrier No bowed or buckled plates; Nothing unusual; no distortion or surface thermal barrier in damage. Seal sheets between good shape cover plates.
- 2. tipper edge of Barrel upper edge shape is No distortion visi-core and top re- un i form. No distortion at ble on upper edge flector keys key and barrel interface. of barrel; keys OK Key assembly and bolting arrangement is intact. No distortion at key and re-flector block interface.
- 3. Upper Plenum No tipped or displaced ele- All gaps appear Elements ments, uniform color and uniform; no dis-appearance. Gap uniformity placed elements between (1) plenum ele aents in a region, (2) plenum ele-ments between regions and (3) plenum elements and permanent side reflectors
- 4. Control Rod No distortion; fully engaged All components OK; Guide Tube, with plenum elements. No no wear marks ob-region ori fice wear marks at valve / plenum served valves RIS, R34, element interface.
and R36
- 5. Side Spacer No tipped or displaced ele- Spacer blocks OK Blocks ments. Uniform color uni-form gap between (1) spacer and core barrel, (2) spacer blocks and side reflector, and (3) spacer blocks.
6 Permant Side No tipped er displaced Gaps are uniform; Reflector Blocks blocks; uniform gap between no damage observed adjacent reflector blocks and reflector blocks and spacer blocks.
- Full inspection recorded on videotape.
1052 334 23
Table B Stains Column 01 07 02 03 04 05 06 17 09 Face Face Face Face Face Face Face Face Face "Y"# 432165 432165 432165 432165 432165 43216 5 432165 432165l432165 1 XX XXX XXXXXX XX 2 XXXX XX X X X X XX XX XXXXXX 3 X X X X X X X X XXX XXX X 4 X X X* XX XX XXX X ? X XXXXXX X y 5 XXX XX XX XXX X X X X X u 6 X X XX XX X XXX XX X 7 XX X XX X XX XX X X X X 8 XXXXXX X X XX XX X X X X X 9 XX X XX X XX XX X X X X 10 XX X XXX X 11 j 12 l X XXX
-. > Possible Chip h Location of stain N
u U LT1
Table C Rubbing Column 01 07 02 03 04 05 06 !? 09 Face Face Face Face Face Face Face Fa c.- Face "Y*# 432165 432165 432165 432165 43216 5 432165 432165 432 65 4 3 2 1 ti 5 1 XXXXXX 2 X X X XXX XX X XX X XXXXX 3 XX XX X 4 XX X X X X X X X X X ,, 5 X X X X X X X X X X 6 X X X X X X X X XX X X X 7 X X X X X X XX XXXXX X X 8 X XX X X X X X l X XX X X 9 X X XX X XXXXX X XXXXX XX X 10 X X 11 12 CX Location of rubbing Ln N U U Ch
Table D Interface Marks Column 01 07 02 03 04 05 06 17 09 Face Face Face Face Face Face Face Face Face "Y*# 432165 432165 432165 432165 432165 432165 432165 432165 432165 1 2 X X X X X X 3 , X 4 XXXXXX X y 5 XXX X X X X 6 XXX X X X X 7 X XX X X X 8 XXXXXX 9 XXX 10 X X X 11 12 X Location of interface marks CD L9 N LN U N
TABLE E ELEMENT NO. 42 BLOCK VISUAL INSPECTION CORE LOCATION R35-1-4 COMPONENT CRITERIA INSPECTION RESULTS*
- 1. 00WELS & SOCKETS OF FUEL / NO CRACKS OR CHIPS. 00WELS & SOCKETS OK.
REFLECTOR BLOCK. GOOD CONDITION NO CHIPS OR CRACKS.
- 2. PADS ON PLENUM ELEMENTS. N0 INDICATION OF IMPACT, RUBBING OR DETERIORATION.
NO CRACKED OR CHIPPED U EDGES.
- 3. KEY AND KEY SLOTS OF PLENUM ELEMENTS.
- 4. FUEL / REFLECTOR BLOCKS. NO CRACKED OR CHIPPED SMALL CHIP DN EDGE BETWEEN FACES 2 & 1 EDGES. NO INDICATION OF LIGHT STAINS ON FACES 3,4,5.
IMPACT OR RUBBING. NO HORIZONTAL LINE ON ALL FACES DISPLACED BLOCKS. SHOWS 1/4 BLOCK OFFSET.
*lNCLUDE DESCRIPil0N OF EXACT NO DAMAGE FROM IMPACT OR RUBBING LOCATION FO R SPECIFIC RESULTS.
LC. (51 rO
'W v
N
FUEL COLUMNS i COLUMN 1 7 2 3 4 5 6 17 9 SEQUENCE NO. FOR BLOCK REMOVAL 1 2 3 4 5 6 7 8 0F REG 10N 35. KP KP KP KP KP KP KP KP 9 1 1 1 1 1 1 NKEYE0 PLENUM p 10 11 12 13 14 15 i 16 17 R R R R R R R R 18 2 2 2 2 2 2 19 20 21 22 23 24 25 26 R R R R R R R R R 3 3 3 3 3 3 2 27 28 32 30 31 29 33 34 35 R R F F F F R R F j LAYER # 4 4 4 4 4 4 3 36 37 38 39 40 41 45 R R F F F F R F 5 5 5 5 5 5
/
4 47 48 49 43 44 50 51 52 53 R R F F F F R R F 6 6 6 6 6 6 5 54 55 56 57 58 59 60 61 62 R R F F F F R R F 7 7 7 7 7 7 6 67 68 63 64 65 66 69 70 71 R R F F F F R R F 8 8 8 8 8 8 7 ; 72 73 74 75 76 77 78 79 INDICATES BLOCKS R R F F F F R R NHSF F 9 9 9 9 9 9
~
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Fig. 10. Interface marks - control fuel layer 4 1052 349 3s
GOUGd ON BOTTOM REFLECTOR APPEA,lS AS SURFACE MARK STAIN (TYP) h __ COOLANT PASSAGE O E O !!? O RE ACTO R O . R E F. 0IR. e O 5,:: o O og!!iNI / 00WEL SOCKET
/ AREAS ' DARKENED 37.35" Fig. 11 Region 35 core support block 1052 350 39
t NORTH REACTOR REF NOTE: NO VISIBLE BURNOFF DIRECTION ON EOGE OF HOLE NOTE: GROUND COLUMN 2, UPPER HALF DARKER GREY p (NOT ORESSED)
/THAN LOWER HALF DARK VERY LIGHT STREAK
~~
O LIGHT LIGHT STR EAK s
- OBSERVED IN WHITE 3 5 0UT OF 6 HOLES)
O seec 6 MAR 4 O CHIP Q \l \ " (LOOKS DRESSED)
~
O , O v 3o NOTE: VERY CLEAN LOOKING WHITE STREAK MAY 1,1979 CORE SUPPORT BLOCK VISUAL INSPECTION VIA TELEVISION CAMERA Figure 12 - Region 13 Core Support Block 40 Ju 351
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DOCUM EN-~ PAG _: 3U _ _3 _ A \ O. 79o 9220sys NO. OF PAGES Y REASON: N PAGE ILLEGIBLE: HARD COPY FILED AT: PDR OTHER C BETTER COPY REQUESTED ON / / O PAGE TOO LARGE TO FILM: C HARD COPY FILED AT: PDR CF OTHER C FILMED ON APERTURE CARD NO. 1052 353
APPENDIX A GA RT-515 A RT-518 POT PJT REE Ref REQUEST FoR TEST DATE Feb.12, 1979 ISSUED 2- -79 REQUESTER M. B. Dolphin SYSTEM 13 PURPOSE /0 EJECTIVE To visually inspect core components in and around region 35 for evidence of fluctuation related motion. To ascertain whether there has been any damage or defonnation to core components as a result of fluctuations.
"A" REVISION CHANGES:
DESCRIPTION OF TEST
- 1) Specification callout, pg.1 See Attachment I. - 2) Clarifies and amplifies SAR
\
q 3) Revises HSF inspection procedure to avoid two fuel blocks in the HSF at one time.
"s d' . s . , , .2 Dr/K REQUIRED See Tables A, B & C.
/ AITIICIPATED RESULTS/ ACCEPTANCE CRITERIA No evidence of fluctuation related motion is expected. Acceptance of blocks will be in accordance with Drawing 90-R1801-202 and Attachment II. REF SOP OR ABNORMAL CONDITIONS S0P-1304 13- H-19 Specification, Issue E 50P-1602 SCHEDULE REQUIRE?.ENTS SAR & APPROVAL SHEET ATTA GV pg WORK ASSIGNED BY/ M '2- f TO M Fuet.H+vagasM,9 Aces Per< soy 4e DATE COMPU'TED BY Distribution: Requester L.D. Johnson G. Lipsey W. Franek R.D. Phelps GA-SD : D.W. McEachern W. Hawkins C. Collard R. J. Meyer P. M. Anderson K. E. Asmuss?u D. Scott F. Mathie E. Hill j } } ')- }}4 D. W. Ketchen 90
,.,,.,,,..n---in. - - - - - - -
SAR is in Support of FON and is enclosed as Page 2 of RT-518A
, sat FCN even thou;;b the SAR is a separate UncontroIIed Doctr.cnt.
(CHECK WITH DOCUEla CCCER FOR LATEST ISSUE) [ D Li 1;c)S CENERAL ATOMIC COMPANY o eq p ; FORT ST. VRAIN NUCLEAR CENERATING STATION O h SAFETY ANALYSIS REPORT o S j< (0]_ _ _a TITIATING DOCUMENT: RT-518A YES NO
'ATEGORY: PLANT CHANGE U@ DOCUMENT CUANGE ONLY CLASS I @ MADiTDIANCE SAFE SHUTDOWN COOLING R@
-AILUBE MODES AFFECTED U$ TEST h
~ ~
D'. GE R E B XI E KED AFETY SIGNIFICANT CHANGE >2 NREVIEWED SAFETY QUESTION U E4 ECH SPECIFICATION CHANGE U@ SAR CHANGE U@ PPLICABLE FSAR OR TECH SPEC SECTIONS REVIEWED: /..d O. 4. S 7 4. 7./.
. ASIS FOR SAFETY EVALUATION: (Add additional Sheets if Required):
=his test involves no plant changes. List is Class I since it involves the jovement of irradiated fuel elements from the reactor to fuel storace wells ng
-ppropriate procedures, safeguards and protective equipment. Hot service facility peration will be in accordance with 50P 16-02. Since only one fuel block will be n the HSF at a time, the maximum expected air discharoe temperature will be 1100F.
his is assuming'the air flow through the HSF is about 340 acfm, ambient inlet air
. emperature is 800F and the average fuel element temperature is 5600F. The temp-rat"re is expected to be less than stated, and unable to support combustion. Cal-ulmions were based on a power factor of 2.
(See attached sheet for conclusion.) S SAN DIEGO SAFETY ANALYSIS /LICEN5ING REVIEW REQUIRED? YES @ NO S SAN DIEGO SAFETY ANALYSIS / LICENSING REVIL LE N PERFORMED? YE @ NC O A SAA 2-2 ~19 ,'?. o th 9-1-79
*ITIAIOR/ D!.TE/ LICLNSING/DATE 3" Sy /).J.)h na h C ENGR. REVIEW / DISPOSITION: I# # "" A ' 'W kEO n JLJ + -
M h.
~g . [ .h 2.-12-7 9 ENG'R/DATE ' e .
If 2 4-79
/
m FORM: SAR 4/77 1052 355
Page 3 of RT-518A The relative power factor is equal to the power density of a block divided by the core average power density. The hottest block to be inspected is anticipated to have a power factor of 0.8. The maximum expected dose rate on the first day outside the viewing window is 7.8 m rad /hr. This is with the fuel block five feet from the inside of the viewing window. During inspection keep blocks four feet from inside of viewing window to maintain 10 m rad /hr. on first day. This can be relaxed if more days of decay are allowed before observation in the HSF. A maximum gama dose rate of 34 m rad /hr. could be seen on the first day after shutdown; with the fuel block one foot from the inside of the viewing window. This dose rate decreases to 4.3 m rad /hr. after 40 days. 1052 356 92
ATTACHMENT I I. Preparation for RT-518A A. Insure the fuel handling machine (FHM), reactor 50 m viewing device (RVD), FHM viewing device and FHM 35 m camera are fully operational and calibrated where required. B. Insure that hot service facility (HSF) and HSF cameras are operational and that reactor isolation valve is installed on east penetration. C. Verify installation of reactor isolation valve and that spacer blocks have been placed in fuel storage well (FSW) number two, column two. D. Verify video tape is operational to monitor removal of blocks. E. Verify installation of isolation valve on region 35 and that removal of control rod and orifice drive has been accomplished. F. Verify that a refueling sleeve has been installed in Region 35 and HSF. G. Verify operability of computer printout for tangential and radial positions of the FHM for core mapping. H. Verify that an adequate core shutdown margin has been established for refueling Region 35 and Base Count Rate data has been taken. I.. Install a stripchart recorder in the Fuel Handling Centrol Room to measure grapple head tangential, radial and vertical positions. Refer to drawing ELJ142-0027 and ELD 142-8151 for interface with present analog system. J. Verify new keyed plenum element 5.01, with scratcher pad, is located in HSF. Ref. FCN 4536. II. Core Visual Inspection A. Lower FHM Grapple Head /RVD into refueling region 35. B. Adjust the FHM Grapple head /RVD for optimal viewing of the core components described in Table A and report the inspection findings based upon the criteria gTven for each component. C. Adjust t6> FHM Grapple head /RVD for optimal viewing of the core orifice valves of regions 18, 34 and 36. Perform the following inspection for each valve:
- 1. Stroke valve full open and observe travel for any urusual movement or binding.
- 2. In full open pcsition, inspect valve internals if possible.
- 3. Stroke valve full close and observe for any unusual movement or binding.
- 4. In full close position, inspect side walls of inner valve cylinder for wear marks.
III. Core Region 35 Block Removal and Inspection A. General description of test: During this operation, Table B will be used as a check list of each block while in the core, in the FHM or in the HSF. Table C 1052 357 93
will be used for visual inspection of walls and gaps surrounding region 35. If possible, use the same data sheet for the sama block in all locations of inspection. The viewing devices provided will examine the following components: RVD: Dowels, plenum element pads, key and key slots of plenum elements and fuel / reflector block top. FHM Viewing Device: Plenum element pads, key and key slots of plenum elements and fuel / reflector block sides and edges. HSF Viewing Device: Top, sides and bottom of any block (See Section V). The unloading procedure is described in the next subsection and the sequence shown by Figure 1. Blocks and surrounding area will be examined at each level of region 35 before removal. The sides of blocks will be viewed in the FHM after removal from the core. At this time, 2 pictures will be taken 1800 apart automatically by the FHM viewing device. The video tape will be used during all viewing segments. Dowels on each block will be examined with the RVD camera as required in the following procedure. Ten blocks will be stored in the FHM and later placed in the HSF for closer examination as described in Section V. CAUTION: Do not use emergency stop to examine blocks while computer is in the program sequence. If further viewing is desired, wait until the end of a procedure step and manually retrieve block desired for viewing. This will prevent ccmputer sequence mixups. B. Procedure for Block Removal and Inspection
- 1. Start automatic mmoval of metal plenum elements by initiating step 201 of region 35 block removal program data tape 35-01.
Stop program during step 209,
- 2. Manually inspect top of region 35 level 2 per Table B.
- 3. Initiate step 210 and stop during step 215. When complete, manually inspect blocks 10, 11, 12, 13, 14 & 15 dowels while in FHM.
- 4. Initiate step 216 and stop during step 218. When complete, manually inspect blocks 16, 17 and 18 dowels.
- 5. Manually inspect top of region 35 level 3 per Tab 17 9
- 6. Initiate step 219 and stop during step 222. When complete, manually inspect blocks 19, 20, 21 and 22 dowels.
- 7. Initiate step 223 and stop during step 225. When complete, manually inspect blocks 23, 24 and 25 dowels.
- 8. Initiate step 226 and stop during step 226. When complete, manually inspect block 26 dowels.
1052 358 94
- 9. Manually inspect top of region 35 level 4 per Table B.
- 10. Initiate step 227 and stop during step 232. When complete, manually inspect blocks 27, 28, 29, 30, 31 and 32 dowels.
- 11. Initiate step 233 and stop during step 234. When complete, manually inspect blocks 33 and 34 dowels.
- 12. Initiate step 235 and stop during step 235. When complete, manually inspect block 35.
- 13. Manually inspect top of region 35 level 5 per Table B.
- 14. Initiate step 236 and stop during step 237. When complete, manually inspect blocks 36 and 37 dowels.
- 15. Initiata step 238 and stop during step 242. When complete, manually inspect blocks 38, 39, 40, 41 and 42 dowels.
- 16. Manually inspect top of region 35 level 6 per Table B.
- 17. Initiate step 243 and stop during step 244. When complete, manually inspect blocks 43 and 44 dowels.
- 18. Move FHM to fuel storage well No. 2. Unload blocks by initiating program step 251.
- 19. Return FHM to region 35.
- 20. Initiate step 301 and stop during step 305. When complete, manually inspect blocks 45, 46, 47, 48 and 49 dowels.
- 21. Initiate step 306 and stop during step 309. When complete, manually inspect blocks 50, 51, 52 and 53 dowels.
- 22. Manually inspect top of region 35 level 7 per Table B.
- 23. Initiate step 310 and stop during step 312. When complete, manually inspect blocks 54, 55 and 56 dowels.
- 24. Initiate step 313 and stop during step 318. When complete, manually inspect blocks 57, 58, 59, 60, 61 and 62 dowels.
- 25. Manually inspect top of region 35 level 8 per Table B.
- 26. Initiate step 319 and stop during step 322. When complete, manually inspect olocks 63, 64, 65 and 66 dowels.
- 27. Hove FHM to FSW No. 2. Unload first part of blocks by initiating program step 351.
- 28. Load spacer blocks 2 thru 10 in FHM section 4 and spacer block 1 in section 5 our of FSW No. 2 section 2 by initiating program step 360.
- 29. Complete unloading of biccks in FHM to FSW No. 2 by initiating program step 371.
1052 359 95
- 30. Return FHM to region 35.
- 31. Initiate step 401 and stop during step 401. When complete, manually inspect block 67 dowels.
- 32. Initiate step 402 and stop during step 403. When complete, manually inspect blocks 68 and 69 dowels.
- 33. Initiate step 404 and stop during step 405. When complete, manually inspect blocks 70 and 71 dowels. e
- 34. Manually inspect top of region 35 level 9 per Table B.
- 35. Initiate step 406 and stop during step 406. When complete, manually inspect block 72 dowels.
- 36. Initiate step 407 and stop during step 409. When complete, manually inspect blocks 73, 74 and 75 dowels.
- 37. Initiate step 410 and stop during step 410. When complete, manually inspect block 76 dowels.
- 38. Initiate step 4i1 and stop during step 412. When complete, manually inspect blocks 77 and 78 dowels.
- 39. Initiate step 413 and stop during step 414. When complete, manually inspect blocks 79 and 80 dowels.
- 40. Move FHM to FSW No. 2. Unload blacks by initiating program step 421.
- 41. Initiate step 434 to relocate spacer blocks 1 thru 5 in FHM.
- 42. Return FHM to region 35.
- 43. Manually inspect top of region 35 level 10 per Table B.
- 44. Initiate step 451 and stop durir; step 453. When complete, manually inspect blocks 81, 82 and 83 dowels.
- 45. Initiate step 454 and stop during step 456. When complete, manually inspect blocks 84, 85 and 86 dowels.
- 46. Initiate step 457 and stop during step 459. When complete, manually inspect blocks 87, 88 and 89 dowels.
- 47. Manually inspect top of region 35 level 11 per Table B.
- 48. Initiate step 460 and stop during step 462. When complete, manually visually inspect blocks 90, 91 and 92 dowels.
- 49. Initiate step 463 and stop during step 465. When complete, manually visually inspect blocks 93, 94 and 95 dowels.
- 50. Manually inspect top of level 12 per Table B.
1052 % 0 96
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51 . Initiate step 467 and stop during step 473 to relocate spacer blocks 6, 7 and 8 and remove blocks 96, 97 and 98. Make manual visual inspection of dowels.
- 52. Initiate step 475 and stop during step 482 to relocate spacer blocks 5, 9 and 10 and remove blocks 99, 100, 101 and 102.
Make manual visual inspection of dowels.
- 53. Initiate step 483 and stop during step 483. When completed, manually inspect block 103 dowels.
- 54. Initiate step 485 and stop during step 487 to relocate spacer block 4 and remove block 104. Make manual visual inspection of dewels.
- 55. Initiate step 489 and stop at step 491 to relocate spacer block 3 and remove block 105. Make manual visual inspection of dowels.
- 56. Initiate step 493 to reiocate spacer block 2 and remove block 106. Make manual visual inspection of dowels.
- 57. Manually make visual inspection of region 35 core support and items required by Table C. Separate entry is required for gap "A" as shown by Figure 2 since it is next to Power Channel VI.
. Core Conforcation at Boundaries of Recion 35 A. The purpose of this portion of RT-518A is to measure possible block displacement or excessive gaps between blocks. Measurements are required in eight separate areas of region 35 as designated by Fig. 2. B. Set recorder for s10 in/ min. and 0 to 1 inch full scale. (Thereis adjustable gain provided in present system; therefore, meter full scale must be checked for input.) Proceed with the following:
- 1. Move FHM grapple head to area #1 (Figure 2). Use location computer indicated as tangential and radial coordinates where metal plenum eierent was picked up. These locations were established in Section III.B of this RT.
- 2. Move grapple head radially against surface until a 0.4 inch radial deflection is monitored on both recorder and digital readout. Start recorder.
- 3. Move grapple vertically, at approximately 2 inches per second down face of area #1. Observe digital readout to prevent exceeding maximum displacement of head. (With interlock O.6 inches.)
Repeat step if needed to find optimal deviation required of head.
- 4. Label recorder printout for scale, speed, area, run and date.
- 5. Repeat steps 1 through 4 for areas #2 through #6.
- 6. Repeat steps 1 through 4 for areas 7 and 8 exceot both tangential and radial deflection is monitored in step 2. (Maximum displacement of haid with interlock is 0.6 inches).
97 1053 001
Block Inspection in Hot Service Facility (HSF) A. Verify proper operation of camera in HSF and monitor and controls in fuel handling control room. Use Table B for documenting observations of abnowlities. B. Blocks will be observed at four different positions:
- 1. Bottom of block as it leaves guide tube.
- 2. Rotating block +150* and -190' while it is directly in line with camera.
- 3. Set block on floor to check dowel pins.
- 4. Pick block up, rotate 180' and set back on floor for dowel pin observation.
C. Bring blocks out manually in the following sequence:
- 1. Remove spacer block S2 from column 4 of FHM and deposit ,
in HSF below FHM cn center line.
- 2. Remove block 99 from column 5 and inspect per subsection V.B.
except set block on spacer block instead of ficor.
- 3. Return block 99 to column 5 of FHM.
- 4. Remove block 106 from Column 3 and inspect per subsection V.B, except set block on spacer block instead of floor.
- 5. McVe spacer block S1 from column 3 to column 4.
- 6. Return block 106 to column 4 of FHM.
- 7. Move spacer block S2 off to south west side of HSF.
- 8. Remove block 59 from column 2 and inspect per subsection V.B.
- 9. Return block 59 to column 3.
- 10. Remove block 51 from column 2 and inspect per subsection V.B.
- 11. Move block 51 north west of HSF.
- 12. Remove block 42 from column 2 and inspect per subsection V.B.
- 13. Return block 42 to column 3 of FHM.
- 14. Remove block 29 from column 2 and inspect per subseciton V.B.
- 15. Return block 29 to column 2 of FHM.
- 16. Move block 42 from column 3 to column 2 of FHM.
- 17. Move block 59 from column 3 to column 2 of FHM.
98
- 18. Remove block 80 from column 3 and inspect per subsection V.B.
- 19. Return block 80 to column 2 of FHM.
- 20. Remove block 74 from column 3 and inspect per subsection V.B.
- 21. Return block 74 to column 3 of FHM.
- 22. Put block 80 back in column 3 from column 2 of FHM.
- 23. Move block 59 to column 3 from column 2 of FHM.
- 24. Return block 51 to column 2 of FHM.
- 25. Move block 59 to column 2 from column 3.
- 26. Remove block 15 from column 1 and inspect per subsection V.B.
- 27. Return block 15 to column 3 of FHM.
- 28. Move block 8 from column 1 to column 3 of FHM.
- 29. Move block 7 from column 1 to column 3 of FHM.
- 30. Remove block 6 from column 1 and inspect per subsection V.B.
- 31. Return block 6 to column 3 of FHM.
- 32. Remove block 5 from column 1 and replace with new scratcher pad block located in HSF.
- 33. Move block 6 from column 3 to column 1 of FHM,
- 34. Move bicck 7 from column 3 to column 1 of FHM.
- 35. Move block 8 from column 3 to column 1 of FHM.
- 36. Move block 15 from column 3 to column 1 of FHM,
- 37. Move spacer block S2 below centerline of FHM.
- 38. Move block 106 from column 4 to HSF.
- 39. Return spacer bicek S1 from column 4 to column 3 of FHM.
- 40. Return block 106 from HSF to column 3 of FHM.
- 41. Return spacer block S2 from HSF to column 4 of FHM,
- 42. If no further inspection of 10 blocks or region 35 is necessary, continue with refueling of region 35.
. Core Mapping By use of the computer printout, the locations where each block is picked up will be recorded for comparison with the theoretical 1053 003 99
locations. In this way a map can be made of actual care block pickup location to verify uniformity of blocks in region 35 for each level. 1053 004 100
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LAYER 11 AND 12 REFLECTOR BLOCKS IR NO. BLOCK TYPE S/N 1R DESCRIPTION 4-19-71 1 16 2 50 1/16"x 3/8" CHIP ON VERTICAL CORNER 2* 16 2 44 REJECTED (3/32"x 13/8" CHIP DN VERTICAL CORNER) 3 22 1 118 1/16"x 3/8" CHIP ON LOWER CHAMFER 4* 22-1 96 REJECTED (1/4" x 1" CHIP ON UPPER CHAMFER) 22 1 4 5/16" x 11/2" CHIP DN EDGE 6 22 1 35 CRUSHED AREA ON 00WEL AND COOLANT HOLE 7 16 2 43 1/16" DEEP GOUGES IN SIDE;WAS BLENDE0 8 16-3 19 POROUS MATERIAL SHOWING ON ONE CORNER 9 21 1 29 1/16"OEEP GOUGE ACROSS ONE FACE 10 22-1 144 CHIP ON CORNER I 22-1 156 TWO CHIPS ON UPPER EDGE 12 21 1 23 SMALL POROUS AREA 0N ONE SIDE 13 22 1 213 CHIP DN UPPER CORNER 14 16 3 7 SCRIBE L.NE 2"00WN FROM TOP ALL THE WAY AROUND 15 22 1 150 CRUSHED AREA ON DOWEL (SHOP BLENDED) 16 22-1 215 CHIP BETWEEN COOLING HOLE AND TOP PICK UP HOLE 17 21 1 41 MECE OF MATTER STUCK TO WEB BLOCK 18 16-1 41 CORNER HAD BEEN CHIPPED AND BLENDEu 19 22-1 182 CHIP ON TOP CORNER 20 22 1 109 CHIPS ON TWO TOP CORNERS 21 22 1 167 CRUSHED AREA ADJACENT TO COOLING HOLE 22* 16-1 52 REJECTED (DOWEL LOCATION INCORRECT) 23* 21-1 16 REJECTED (00WEL LOCATION INCORRECT) 24 22 1 73 GOUGE ON SIDE 1" x 1/32" x 2" 25 22-1 72 CRUSHED AREA JN DOWEL 110 1053 0 9
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