ML20028C619
| ML20028C619 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/31/1982 |
| From: | Czajkowski C BROOKHAVEN NATIONAL LABORATORY |
| To: | Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| CON-FIN-B-5176 BNL-NUREG-31743, NUDOCS 8301110160 | |
| Download: ML20028C619 (27) | |
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- BNL-NUREG-31743 INFORMAL REPORT LIMITED DISTRIBUTION i
EVALUATION OF FAILED REACTOR COOLANT PUMP INTERNAL BOLTS FROM THE H. B. ROBINSON NUCLEAR POWER STATION *
. I Carl Czajkovski August 1982 ,
Brookhaven National Laboratory Corrosion Science Group Department of Nuclear Energy Upton, New York 11973 i
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- Research carried out under the auspices of the U. S. Nuclear Regulatory Conant s sion.
8301110160 020731 PDR PDR RES e
TABLE OF CONTENTS IA12.
o List of Figures 11 Abstract iv 1.0 Introduction' 1 2.0 Visual / Photography 1 3.0 SEM/EDS 2 4.0 Optical Microscopy / Meta 11ography 4 5.0 Discussion / Conclusions 4 6.0 Acknowledgements 5 7.0 References 6 9
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LIST OF FIGURES .
Flaure Pagg,
- 1. Photograph of a*rchive bolt 77
- 2. Photograph of shank portion of bolt 8
- 3. Photograph of threaded portion of bolt 9
- 4. Photograph of bolt head 10 -
- 5. SEM l'hoto of fracture face 11
- 6. _SEM photo of pit 12
- 7. SEM photo of initiation site 12
- 8. SEM photo of fatigue striation 12
- 9. SEM photo of fracture face 13
- 10. SEM photo of transgranular area 14
- 11. SEM photo of transgranular area 14
- 12. SEM photo of transgranular area 14
- 13. SEM photo of fatigue striations 14
- 14. EDS scan of base metal 15 ..
115. EDS scan of fracture face 15
- 16. EDS scan of fracture face 15
- 17. EDS scan of fracture face 15
- 18. EDS scan of fracture face 16
- 19. EDS scan of fracture face 16'
- 20. EDS scan of fracture face 16
- 21. EDS scan of fracture face 16
- 22. EDS scan of fracture face 17
- 23. EDS scan of fracture face 17
- 24. EDS scan of fracture face 17
- 25. Optical photomicrograph of shank bolt 18
- 26. Optical photomicrograph of head bolt 18
- 27. Low magnification photo of cold work area 18 v
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4 Figure Page 28.- Higher magnification photo of cold work area 18
- 29. Optical photomicrograph of cold work area 19
- 30. Photomicrograph of pit 19
- 31. Photomicrograph of pit 19
- 32. Photomicrogratih of ' pit 19
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Abstract A metallographic failure analysis was performed on two cracked bolts on the diffuser adapter to casing adapter plate from Reactor Coolant Pumps of the
. H. B. Robinson Unit *2 nuclear power plant. The observations included transgranular cracking and pits . on the. shank of one bolt and the head of another. SEN evaluation of the fracture surface disclosed areas of probable fatigue interaction. The report concludes that the bolt f ailure was due to a stress corrosion cracking (SCC) mechanism caused by probable chloride contamination and fatigue enhancement.
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1.0 INTRODUCTION
In April 1982, during the 10 year inservice inspection of reactor coolant pumps at the H. B. Robinson plant, the utility discovered that various diffuser adaptor to ca' sing adaptor bolts had failed in service. In May 1982, a bolt which had cracked in the thread area was sent to Brookhaven National Laboratory (BNL) for examination (1). The report concluded that the bolt faile.1 by a stress corrosion cracking mechanism probably caused by high tensile stresses in the bo?*, and probable chloride contamination.
r In June 1982, three additional bolts were sent to BNL from the H. B.
Robinson plant for examination. The work was done by a subcontract issued to BNL from the Franklin Institute under P.O. #C-67718. This report describes the results of this examination.
The analysis of the bolts was to be a metallurgical investigation of the i
failure mechanism and encompassed the following methods of evaluation; a) Visual / Photography ,
b) Scanning Electron Microscopy (SEM) and Energy Dispersive Spectroscopy (EDS) c) Optical Microscopy / Meta 11ography.
r 2.0 VISUAL / PHOTOGRAPHY t 4 The first bolt examined (Figure 1) had no visual cracks and was later ;
t determined by discussion with A. Herth (USNRC-Region 2) to be an archive I specimen if additional testing was needed. It was identified by the packing 1 designation as Pump: Capscrew 21. The bolt was 4 inches long and was .0625 ,
inch in diameter.
i The second specimen received (Figure 2) was just the shank portion of a bolt with a fracture on one end and the appearance of mechanical severing on the opposing end. This specimen was identified as PUMP CAPSCREW "B".
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I The . third bag examined had two specimens inside. The first specimen (Figure 3) was a portion of the threaded . area of a bolt with the same appearance of mechanical severing on one end. The second specimen was a bolt head with a ' thin metallic sheath surrounding it (Figure 4). This bolt head had fractured at the bolt head / shank juncture. This bag was identified as ,
PUMP: CAPSCREW 13/14. j l
l The outside of the three plastic bags were surveyed by BNL Health Physics ,
personnel with thA following results: (at contact) l l
, Specimen I.D. 21 "B"? 13/14 Beta-Gamma 600 mR/hr 1.1 R/hr 2 R/hr
, ' Gamma 200 mR/hr 250 mR/hr 800 mR/hr 3.0 SEM/EDS The fracture f ace of the specimen identified as PUMP CAPSCREW "B"? was cut from the bolt shank and viewed in the SEM. Figure 5 is a low magnification photograph of the fracture f ace. The fracture was relatively flat with only one area of ridging and was transgranular in appearance. One area of pitting was noticed during the examination (Figure 6) with the pit ;
lying on the plane of the tracture surface. The ridge area was examined l (Figure 7) and had the appearance of some intergranularity present on the shank side of the fracture face. The examination also disclosed one area of pos sib 1'e fatigue contribution (Figure 8) which was seen in an area almost diametrically opposite the fracture ridge.
t The fracture face of the bolt head (identified as PUMP CAPSCREW 13/14) l was also examined by SEM. It also had a very flat appearing fracture surface (Figure 9) and was generally transgranular in nature (Figures 10, 11 and 12). ,
No pitting was evident in the evaluation of the fracture surface. Figure 13 is an SEM photograph of the apparent area of fracture initiation which had ;
definite fatigue wavefront characteristics evident.
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Since. decontamination had' been performed on these . bolte prior to SEM evaluation, EDS examination for contaminants was omitted. An analytical SEM technique for stress corrosion cracking environment determination (2) was performed on the fracture surfaces of both bolts examined. This technique
. produced data generated by exomination of Type 316 stainless steel fracture surfaces.. The. technique indicates whether the stress corrosion cracking
, occurred by environmental interaction of the stainless steel with either chloride or hydroxide solutions. The examination entails the measurement of Cr/Fe ratios after EDS analysis. Classification of these ratios is then based on the observations that in chloride solutions, the corrosion product is chromium rich (Cr/Fe 0.6-0.9) while in hydroxide solutions, the corrosion d
produce is iron rich (Cr/Fe 0.4-0.6).
- Figure 14 is an EDS scan of the base material at 35 kV. The Cr/Fe/Ni ratios are in reasonable agreement with those of a Type 304 austenitic stainless steel. (Note: the use of a higher kV accelerating voltage provides a more accurate determination of the materials intensive properties.)
Figures 15,16,17,18, and 19 are EDS scans across the fracture f ace of PUMP: CAPSCREW 13/14 (the bolt head fracture). The Cr/Fe rai:io for these scans ranged from a low value of .957 to a high v slue of 2.10. Figures 20, i 21, 22, 23, and 24 are EDS scans across the fractuce face of PUMP CAPSCREW B7.
This fracture f ace had Cr/Fe ratios ranging from 'J.839 to a maximum of 2.027.
i The ratios observed on these two specimens are significantly higher than those previously reported (1). These greater values in Cr/Fe ratios are probably due to the fracture faces having a more prolonged contact with the corrodent solution, than the previously examined bolt which cracked in the i
thread area.
These high Cr/Fe ratios indicate the possibility of chloride induced I g stress corrosion cracking as the mode of failure.
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4.0 OPTICAL MICROSCOPY /METALLOGRAPHY Additional characterization of the cracking phenomenon was accomplished by cutting cross sections from the two fractured bolts and examining them metallographically. These samples were made by cutting transversely to the fracture face approximately mid-cross section of the bolt. The first section -
examined (Figure 25) was from the shank fracture area af ter ASTM A-262 was performed. It can be seen in the photomicrograph that the structure is that .
commonly seen in austenitic stainless steel with no evidence of sensitization.
There was virtually no evidence of significant cold work on the specimen.
The second specimen exam ned (Figure 26) was the area adjacent to the i
bolt head failure fracture face. The structure of the material af ter ASIM A-262 etching also shows no evidence of sensitization. This specimen showed some areas of significant cold work (Figures 27, 28, and 29). Various areas of pitting were also found on the bolt head cross section (Figures 30, 31, and
- 32) which is indicative of chloride contamination.
5.0 DISCUSSION / CONCLUSIONS i
It has been observed that chlorides will cause pitting as well as j
transgranular cracking in austenitic stainless steels (3,4) at higher temperatures. Since these bolts were from the same pumps which supplied the first bolt for examination (1); the conclusion that chloride contamination is contributing to the cracking is consistent.
The following conclusions can then be drawn from the failure analysis observations:
- 1. The bolting material is of the austenitic stainless variety (probably Type 304).
f l 2. The bolting material is in the non-sensitized condition. -
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- 3. The transgranular characteristics of the cracking, with pitting in evidence, indicates chloride contamination. This is also
! substantiated by the very high Cr/Fe ratios encountered on the fracture surfaces.
- 4. Since evidence of fatigue was observed on both fracture faces; it is reasonable to assume that fatigue interaction contributed to the bolt e
failures by a f atigue assisted stress corrosion cracking mechanism caused by probable chloride contamination.
6.0 ACKNOWLEDGEMENTS .
The author wishes to thank the Franklin Institute for funding the analysis. In addition thanks are due L. Gerlach, R. Sabatini, P. Knisely, and especially Dr. J. R. Weeks for his constant support.
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7.0 REFERENCES
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- 1. Czajkovski, C. J., BNL-31530, July 1982.
- 2. Poulson, B., Gartside, H., Br. Corr. J., 1978. Vol. 13, No. 2.
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- 3. Anderson, P. A., Duquette, D. J., Corrosion, Vol. 36, No. 8, August 1980.
- 4. Leckie, H. P., Uhlig, H. H., Jour. of the Electrochen. Soc., Vol. 173, No. 12, December 1966.
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( PUMP:CAPSCREW " B "? )
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6 i LNUREG -31743 . , , l ORMAL REPORT . LIMITED DISTRIBUTION 1 _s i 1 EVALUATION OF FAILED REACTOR COOLANT PUMP INTERNAL. BOLTS FROM THE H. B. ROBINSON NUCLEAR POWER STATION I CARL J. CZAJK0WSKI j DATE PUBLISHED - OCTOBER 1982 CORROSION SCIENCE GROUP DEPARTMENT OF NUCLEAR ENERGY BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK 11973 i {j._. , ,,. ' {' Prepared for the U.S. Nuclear Regulatory Commission
;J ; ?; -
Office of Nuclear Reactor Regulation
,1 j ' , ,a 1 Controc No. DE ACO2 76CH00016 n
.% ?
- k. hw - Ja. g .
y IhTERIM REPORT
#h er po6* [HearcN a or knocek DJl*Med k :
Accession No. l l Contract Program or Project
Title:
Franklin Institute Subject of this Document: Evaluation of Failed Reactor Coolant Pump Internal Bolts s from the H. B. Robinson Nuclear Power Station Type of Document: Informal Report
- Author (s): cari czajkowski Date of Document: July 1982 Responsible NRC Individual A. Herdt (Region 2) and NRC Office or Division: Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Suite 3100-101 Marietta St., N.W.
Atlanta, George 30303 This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes, this document should not be considered final. l Brookhaven National Laboratory Upton, New York 11973 , Associated Universities, Inc. for the U.S. Department of Energy Prepared for U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under Interagency Agreement DE-AC02-76CH00016 FIN 85176
. _ . _}}