ML20147F813
| ML20147F813 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/15/1988 |
| From: | Toro Diana Diaz, Gordon G GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML113111187 | List: |
| References | |
| 87-178-037, 87-178-37, NUDOCS 8803080045 | |
| Download: ML20147F813 (20) | |
Text
{{#Wiki_filter:. .p .; NUCLEAR ENERGY SUSINESS OPERATIONS GENERALOitictnic '""*"'"'s^' FUEL & PLANT MATERIAL? TECHNOLOCY FINAL REPORT 2 I
;. LABORATORY EXAMINATION OF RECIRCUIATION LINE-l DECONTAMINATION FIANGE FROM MONTICELLO NUCLEAR POWER STATION !
/, WORK PERFORMED FOR NORTHERN STATES PO'ER) i I
i January 15, 1988 ! l I I
- 3 ;
Prepared By: s " t T.P. Diaz l Plant Materials Performance i I Approved By: b7f G.M. Gordon, Manager { Fuel & Plant Materials Technology i l i l I TPD8715 j
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i l K3 807 (REV 10/81) 8803080045 880229 I PDR ADOCK 05000263 l S DCD ! = l
1 y&pMT TRANSEIITAL No. 87 178-037 DISCIALMER OF RESPONSIBILITY This docu=ent was prepared by or for the General Electric Co=pany. Neither the General Electric Co=pany nor any of the contributors to this docu=ent: to A. Makes any warranty or representation, express or i= plied, with respect the accuracy, co=pleteness, or usefulness of the infor=ation contained in this docu=ent, or that the use of any infor=ation disclosed in this docu=ent =ay not infringe privately owned rights; or B. Assu=es any responsibility for liability or da=a5e of any kind which =ay result fro = the use of any information disclosed in this document, h 9 b c I 1 I
F&PMT TRANSMITTAL No. 87-178 037 TABLE OF CONTENTS . 2151
1.0 INTRODUCTION
................................................... 1 2.0 OBSERVATIONS AND CONCLUSIONS................................... 1 3.0 VISUAL AND DYE PENETRANT EXAMINATION........................... 1 4.0 METALLOCRAPHIC EXAMINATION..................................... 2 5.0 HARDNESS MEASUREME. TIS.......................................... 3 1 6.0 CHEMICAL ANALYSIS.............................................. 3 1 1 3 I 1 l _1_
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I F&PMT TRANSMITTAL NO. 87-178-037 f
1.0 INTRODUCTION
This report su==ari:es the results of laboratory examination perfor=ed on a portion of 2 inch dia=eter Tyge 316L decontamination pipe received from Northern States Power Monticello plant. The speci=en consisted of the upper portion of an 8 inch long, 2 inch dia=eter line connecting the decontamination flange to the recirculation pipin5 The socket veld between the 2 inch line and the recirculation pipe was found to be leaking durin5 hydro tests conducted at 550 F, and 1,000 psi. The pipe had been in service less than 3 years when,the leak was detected. 2.0 OBSERVATIONS AND CONCI.USlQJM, o The crack length was about 2-1/4 inches on the CD and 3/4 inch on the ID. o Optical metallography and SEM fraccography revealed that the fracture mode was transgranular. o There was no evidence of base =aterial sensitization o There was no evidence of damage to the base material due to veld repairs or cold work. o The crack initiated at the veld fusion line on the CD surface. , o The cracking =echanism har been attributed to high cycle fatigue.
- 3. VISUAL AND DYE pD7ETRANT EXAMINATION The specimen received consisted of the socket veld and the top four inches of pipe. Figures 1 and 2 are photographs of the as received specimen. A crack i about 1 inch on the CD and 5/8 inch on the ID was visible with the unaided ,
eye. Some staining /screakin5 was visible on the CD of the pipe and weld 1 h
I . F&PMI TRANSMITTAL NO. 87 178 037 probably due to corrosion durin5 the leak. A slight oxidation stain was also visible along the crack on the ID surface. Liquid penetrant examination of the CD and-ID was perfor=ed as shown in Figures 3 and 4 The CD indication was about 2-1/4 inches long and followed the weld fusion line. The ID indication was about 3/4 inch long. The lon5er indication visible in Figure 4 is due to the gap between the pipe and socket fitting beyond the veld. After visual and liquid penetrant examination, the specimen was sectioned transversely about 1/2 inch from the fusion line and then axialy to re=ove specimens for optical metallography and Scanning Electron Microscopy. Figure 6 is a close up photograph of the SEM specimen showing a dark brown oxidation layer on the fracture surface close to the OD and becoming lighter in color towards the ID. . 4.0 METALLOGRAPHIC EVALUARQ1{ The sectioning plan is illustrated in Figure 5. Speci= ens 1 and 3 represent the ends of the crack and specimen 2 is representative of the through wall t portien of the crack at a location equidistant from the crack ends. A fourth , speci=en for optical metallography was sectioned 180 from the crack center. The SEM speci=en was pried slightly open before the photograph of Figure 5 was taken. Figures 7 throu5h 13 show the optical metallography results. The crack originated at the CD closely following the fusion line and then propagating into the base metal. The crack mechanism is clearly transgranular and the base =ecal =icrostructure is typical of annealed 316L thin walled piping. There is no evidence of grain boundary sensitication and the grain structure was revealed only after heavy etching. A "banding" effect resulting from the extrusion process prior to annealing and repeated preferential etchins was visible, but the annealed structure showed no evidence of grain t deformation due to cold work, nor van there any visible da= age to the base material (i.e. burn through) as a result of a reported weld repair. No cracking was detected in specimen 04, 180 from the through wall crack. i 2-g . . _ _
. _. ~. _ _ _ _ .
l . F&PMT TRANSMITTAL NO. 87-178 037 SEM evaluations of the fracture surface (Figures 14 and 15) provide additional evidence of the transgranular cracking mechanism. The above findings lead to the conclusion that the observed cracking was the result of high cycle f t.cigue . Crack initiation occurred at the veld fusion line which acted as a i stress riser at the pipe OD. l 5.0 HARDNESS MEASUREVENTS Hardness messurements using a 200 gram load were conducted on speci=en #2 near the through vall portion of the crack. The results shown in Figure 16 I
- indicate that the base material meets current require =ents for annealed Type 316L pipe (Rockvell B 92) . The hardness ceasure=ents ran5ed from Rockwell B-87 to -89.
6.0 CHEMICAL ANALYSIS A chemical check analysis was performed on a decontaminated sa=ple by an outside laboratory. The results, which are co= pared o the ASME SA312 and CE ,
"Nuclear Grade" requirements in Figure 17, indicate that the pipe material >
=eets specification.
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Check ASME SA312 316 Nuclear i Elenent Analysis Tvee 316L M C 0.014 0.035 Max. 0.020 Max. Cr 16.90 16 - 18 - Mo 2.52 2.0 - 3.0 . Ni 13.40 10 15 - P 0.023 0.04 Max. 0.035 Max. Si 0.56 0.75 Max. - S <0.005 0.030 Max. 0.005 Max. Mn 1.77 2.00 Max. - N 0.065 - 0.060 - 0.120 Figure 17. Comparison of Check Analysis, ASME 312 Type 316L chemical co= position and additional requirements of CE 316 Nuclear Grade uterial 4 t' 17 - _ _ . _ _ . . . _ . _}}