ML20198G721
| ML20198G721 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/03/1997 |
| From: | Crosson J, Vecchio R LUCIUS PITKIN, INC. |
| To: | |
| Shared Package | |
| ML20198G719 | List: |
| References | |
| CON-96-4 M96244, NUDOCS 9709040286 | |
| Download: ML20198G721 (109) | |
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Report No. M96244 3 HOT ROLLED XM-19 STAINLESS STEEL CORE SHROUD TIE-ROD MATERIAL - CREVICE CORROSION INVESTIGATION NYPA NO. S94 62083, TASK NO. 96-4 GPUN NO. NB70401073 3-Prepared for New York Power Authority GPU Nuclear Corporation l 123 Main Street 1 Upper Fond Road D White Plains, NY 10601 Parsippany, NJ 07054 Attention: Messrs. William H. Spataro & Anthony Collado Pre ared by
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D lucius Pitkin D' 1.0 EXECUTIVE
SUMMARY
D As a result of the widely recognized susceptibility of Type 300 series austenitic stainless steels to intergranular stress corrosion cracking (IGSCC) in light water reactor (LWR) coolant environments, the New York Power Authority (NYPA) and GPU Nuclear Corporation (GPUN) instituted repairs to the core shrouds of their James A. Fitzpatrick (NYPA) and Oyster Creek (GPUN) boiling water reactor (BWR) nuclear power plants (NPP). Specifically, hot-rolled XM-19 O stainless steel tie-rods (herein referred to as XM-19) were usod to restrain the austenitic stainless steel shrouds within the reactor vessels in the event that the shroud circumferential welds would degrade to the point where load carrying capacity was compromised. To this end, tie-rnd systems were installed in the James A. Fitzpatrick NPP in 1995 during the 11'" refueling outage and in the Oyster Creek NPP in 1994 during its 15'" refueling outage. Within the reactor vessel, the threaded tie-rods are exposed directly to the BWR coolant. Since the tie-rods are threaded, a stress concentration and associated crevice condition exist in and around the thread roots. Service conditions are such, therefore, that stress-corrosion crack initiation and subsequent propagation could occur if, of course, XM-19 is susceptible in the H BWR coolant environment in this regard, Lucius Pitkin, Inc. (LPI) was requested j to provide engineering services for determining the resistance of XM-19 to l intergranular stress-corrosion cracking (IGSCC) in a simulated BWR coolant environment. Constant extension rate testing (CERl) of XM-19 was performed in t - simulated BWR reactor coolant at 550*F in order to determine the resistance of XM-19 to IGSCC. The simulated coolant (as specified in Appendix B, part 4.4.) was maintained at a dissolved oxygen concentration of approximately 10 ppm - which is in excess of the 3 ppm saturation point for rapid IGSCC to occur in Type 304 stainless steel. Contaminant levels were controlled so as to maintain a conductivity of 0.4-0.5 S/cm using sulfate additions. Coolant pH was
~3 maintained in the range of 6.0 to 7.0, corrected to 70*F. Chemical analyses, indeed, indicated that the simulated BWR coolant chemistry remained within specified tolerances throughout the test program.
Control tests were performed in air to provide a baseline for determining the load (strength) and ductility (elongation) ratios for the BWR coolant tested O specimens. Load versus time curves and elongation data were obtained for each CERT specimen tested in the BWR coolant. In addition to establishing the 1 preload levels for BWR coolant CERT specimen tests, the air results also g ,
OL Lucius Pitkin
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 Vc . provided the basis for calculating the coolant to air load (strength) and ductility ratios - both measures of resistance to IGSCC and, conversely the susceptibility, b _if any, of the XM-19 test specimens to IGSCC. After testing, all CERT specimens were examined visually end documented with 35_mm color photographs. In i addition, the test specimens were examined metallographically and in the ) scanning electron microscope (SEM) to determine specimen fracture ,' mechanisms., 07 Results for the CERT specimens tested in air revealed XM-19 to exhibit substantially higher yield and ultimate load (strength) levels .and lower elongations compared to Type 304 stainless steel. Since the air tests were performed at room temperature and the BWR coolant tests at 550 F, the air test ultimate load levels were adjusted to reflect the decrease in strength associated with increasing temperature. Based on review of allowable stress levels provided O in the ASME B&PV Code for the subject materials at the respective. test temperatures, a factor of 0.85 was applied to the room. temperature ultimate
- tensile load levels. Scanning electron microscopy of the air tested specimens revealed a rough fracture morphology characterized by microvoid coalescence, as is typical of ductile overload fracture.
O Results of the constant extension rate testing revealed that hot-rolled XM-19, as evaluated using threaded specimens under crevice conditions in a simulated BWR environment at 550*F, is no.1 susceptible to intergranular stress corrosion cracking. That is, the relative resistance of XM-19 to.lGSCC, as assessed by calculating the coolant to air load (strength) and ductility (el ngation) ratios, revealed that XM-19 exhibits the same load and ductility O capacities in simulated BWR coolant as it does in air. It was also evident from the -CERT program that sensitized Type 304 stainless steel is extremely susceptible to fracture in simulated BWR coolant. Moreover, the results of this
# 4 investigation indicated that a reduction in test strain rate from S x 10 sec to 5 x 108 sec4 'does not change the resistance of XM-19 to IGSCC. Finally, the O reproducibility of the results for the three different conditions of XM-19 evaluated herein attests to the' homogeneity of the XM-19 material and the reproducibility of the constant extension rate test conditions.
In order to verify the mode of the XM-19 and Type 304 CERT specimen fractures, all test specimens were examined visually, metallographically, and by scanning _ electron microscopy (SEM). Examination of the XM-19 CERT O_ specimen fracture surfaces revealed a rough fracture morphology characterized by microvoid coalescence, characteristic of ductile overload fracture. More importantly, the XM-19 specimens did not exhibit any evidence of intergranular O 2 i
D Lucius Pitkin
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 fracture. However, the Type 304 CERT specimen fracture surfaces exhibited an intergranular morphology, as is characteristic of intergranular stress corrosion D cracking. Clearly, by comparison, the XM-19 specimens were resistant to IGSCC in the same environment in which sensitized Type 304 stainless steel exhibited extreme sensitivity to IGSCC. ) J
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a Lucius Pitkin p
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244
2.0 INTRODUCTION
a As a result of the widely recognized susceptibility of Type 300 series austenitic stainless steels to intergranular stress corrosion cracking (IGSCC) in light water reactor (LWR) coolmt environments, the New York Power Authority (NYPA) and GPU Nuclear Corporation (GPUN) instituted repairs to the core shrouds of their James A. Fitzpatrick (NYPA) and Oyster Creek (GPUN) boiling water reactor'(BWR) nuclear power plants (NPP). Specifically, hot-rolled XM-19 3 stainless steel tie-rods (herein referred to as XM-19) were used to restrain the austenitic stainless steel shrouds within the reactor vessels in the event that the shroud circumferential welds would degrade to the point where load carrying capacity was compromised. To this end, tie-rod systems were installed in the James A. Fitzpatrick NPP_ in 1995 during the 11* refueling outage and in the Oyster Creek NPP in 1994 during its 15* refueling outage, as shown in Fig 1. 3 With regard to the shroud repair, it was reported that the most highly stressed (loaded) components are in-fact the threaded tie-rods which are loaded to a tensile stress of approximctely 32.5 ksi or 31% of the minimum specified yield strength of 105 ksi for XM-19 (ASTM: A479, Gr. XM-19). Moreover, within the reactor vessel, the threaded tie-rods are exposed directly to the BWR D coolant. Since the tie-rods are threaded, a stress concentration and associated crevice condition exist in and around the thread roots. Service conditions are such, therefore, that stress-corrosion crack initiation and subsequent propagation could occur if, of course, XM-19 is susceptible in the BWR coolant environment. it is well known that three critical factors are necessary for the initiation of J stress corrosion cracking (SCC). These factors are: 1) a susceptible material,2) tensile stress, and 3) corrosive environment. Most austenitic stainless steels are susceptible to stress-corrosion cracking in aqueous environments depending upon the applied stress, material microstructure, and water chemistry. Of these factors, the applied tensile stress generally has the greatest effect on the time required for the initiation and propagation of SCC. Increasing the stress level
- decreases the time for stress corrosion crack initiation. For example, intergranular stress-corrosion cracking of sensitized Type 304 stainless steel in 0.2 ppm dissolved oxygen (0 2) BWR coolant environment at 550*F occurs in less than 20 hr at a stress level of about 90% of the ultimate tensile strength.
5 Whereas,10'to 10 hr are required when the applied stress is close to the yield strength. A Typically, BWR coolant is high-purity, 6.0-7.0 pH water containing approximate!y 0.2 ppm dissolved oxygen. This oxygen concentration has been (J 4
o Lucius Pitkin
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Attn.: Messrs. W. H. Spataro & A. Collado M96244 shown to be sufficient to initiate IGSCC in sensitized austenitic stainless steels.
-Increasing the dissolved oxygen content to approximately 3 ppm can increase' g the rate of-cracking. Anions such as chlorides, sulfates, and carbonates can further exacerbate the propensity for IGSCC. Moreover, crevice conditions, such as those which could develop in the tie-rod threads, generally exacerbate the environmental effects which, in-turn, reduces the initiation time for IGSCC.
Prior to the installation of the NYPA and GPUN core shroud repairs, a 0- number of evaluations (Ref.1) were performed to determine the adequacy of
- XM-19 in the BWR coolant environment. For example, initial susceptibility of XM--
19 to IGSCC was assessed according to the requirements of ASTM: A262. Additionally, constant extension rate testing was performed on smooth ' specimens of XM-19 in simulated BWR coolant conditions at 550 F. Results of these tests (Ref.1) revealed XM-19 to be immune to IGSCC for the evaluated 0 - smooth specimen test conditions. However, these initial tests did not simulate the stress concentration / crevice conditions potentially present at the tie-rod thread roots. In this regard, Lucius Pitkin, Inc. (LPI) was requested to provide engineering services for determining the resistance of XM-19 to IGSCC in O simulated BWR coolant environment. NYPA and GPUN, in conjunction with LPI, developed a test program for the that purpose. To this end, LPI implemented a comprehensive constant extension rate test program with its subcontractor Babcock & Wilcox Research and Development Division, Alliance Research Center (ARC). O- Lucius Pitkin, Inc. maintains a Quality Control Program in accordance with the requirements of 10 CFR50 Appendix B " Quality Assurance Critoria for i Nuclear Power Plants," which was followed for the subject investigation, as applicable to the services performed. O O O 5
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A; Collado M96244 3.0 XM-19 CREVICE CORROSION CERT EVALUATION PROGRAM Lg: 3.1 Overview Constant extension rate testing (CERT) of XM-19 was performed in simulated BWR reactor coolant at 550*F in order to determine the resistance of XM-19 to IGSCC. The simulated coolant was maintained at a dissolved oxygen concentratiori of approximately 10 ppm - which is in excess of the 3 ppm 'O - saturation point for rapid IGSCC ' to occur in Type 304 stainless steel. Contaminant levels were controlled so as to maintain a conductivity of 0.4-0.5 pS/cm using sulfate additions. Water pH were maintained in the range of 6.0 to 7.0, corrected to 70*F. Load versus time curves and elongation data were obtained for each O CERT specimen tested in the BWR coolant. In addition, air tests were performed to provide a baseline for determining the strength and ductility ratios for the BWR coolant tested specimens. These ratios provide a measure of the susceptibility, if any, of the XM-19 test specimens to IGSCC.
-- After testing, . all CERT specimens were examined visually and-
'O documented with 35 mm color photographs. In addition, the test specimens were examined metallographically and in the scanning electron microscope (SEM) to determine the fracture mechanisms. Complete details of the test procedures and the test results are given in the following sections. 3.2 Materials As previously described, the XM-19 evaluation program was developed to determine the resistance of ASTM: A479, Gr. XM-19, to IGSCC in a crevice - environment, in this regard, specification SP-1302-52-118, " Crevice Corrosion n" Testing For Hot Rolled XM-19_ Material," was developed by GPUN for constant extension rate testing (CERT) of threaded (grooved) specimens machined from ASTM: A479, Gr. XM-19 bar stock, Jacketed with Type 304 crevice assemblies. In addition, since sensitized Type 304 stainless steel is known to exhibit IGSCC. in BWR coolant,- sensitized Type 304 CERT specimens were evaluated concurrently so as to provide control specimens to ensure that the test O environment indeed was capable of inducing IGSCC. A copy of specification SP-1302-52-118 is given in Appendix A. o- 6
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 O Three lots comprised of two heats of XM-19 and one lot /one heat of Type 304 stainless steel bar stock were submitted to LPl for evaluation, as described U in Table 1. The test material was taken from the same stock bars (heats) as those placed in service in the respective BWR's addressed herein. TABLE 1 TEST MATERIAL IDENTIFICATION _ LPI Bar Bar 3 ident. Material Heat No. Diameter (in.) Lenath (in.) Plant A XM-19 AJ5018 1.494 7-5/16 JAF NPP (PC 18) B XM-19 AJ5018 1.740 5-5/8 JAF NPP (CLI 427819) O C XM-19 A9098H 1.491 8-3/16 OC NPP D Type 304 L27527 1.245 4-1/2 Control Prior to machining, each bar was marked and stamped with the .O appropriate letter designation. In order to obtain sensitized Type 304 stainless steel, bar D was heat treated at 1250 F 110 F for 1 hr followed by furnace cooling. The time-temperature record for the sensitization heat treatment is given in Appendix B. CERT specimens from each bar were machined with grooves to simulate O the thread geometry according to the requirements of SP 1302-52-118 (Appendix A). Each specimen was stamped with its letter designation and a sequence number as follows A1, A2, ...; B1, B2,...; C1, C2,..., and D1, D2,.. .., etc. The dimensions of each CERT specimen were verified for conformance with the specified dimensions given in drawing No. 38-SKM-722 (Fig. 2). O Inasmuch as the shroud tie-rods are in contact with Type 304 austenitic stainless steel components, it was necessary to simulate a crevice env'ronment which incorporated bott, the XM-19 and Type 304 matenals. As such, crevice assemblies comprised of Type 304 austenitic stainlese steel packk.g material and jacket were fabricated for each specimen. It should be noted, that Fig. 2 specifies Type 304 stainless steel wool for the crevice packing material, however, O austenitic stainless steel wool is not commercially available. In lieu of stainless steel wool, Type 304 stainless steel 150 x 150 mesh (0.0026 in. diameter wire) screen material was used for the crevice packing material. That is, the screen O 7
o, Lucius Pitkin:
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' New York Power A0thority/GPU Nuclear Corpc April 3,1997 -
. Attn.: Messrs._W Hz Spataro & A. Collado .
- M96244 n wires were separated and bundled to form a wool-like assemblage for wrapping around the" specimen grooves.H Moreover, the fine diameter of the screen wires- ;
Lprovided,significa:ttly: greater surface area of Type 304 material relative to the 9- surface area of the XM 19 specimen grooves so as to enhance the ef'ect of the environment.4 The as-machined CERT specimens and crevice assemblies are shown in Figs. 3 throucjh 7. d;
-3.3 Test Procedures ,
3.3.1 Air Tests
-CERT specimens A1,= B1, C1, and D1- were tested ~ in air: at room 1 - temperature in order to obtain (1)- baseline _ ultimate _ loads and elongations for determining the BWR coolant to air load and ductility ratios,-and_(2) the specimen load at the onset of yielding for preloading.of the CERT specimens in the BWR -
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coolant solution (see .Section 3.3.2). . inasmuch as the CERT specimens are
. threaded, the actual smooth specimen tensile stresses .could not be obtained from the air test results. - Rather, since the air and BWR coolant specimens are O identical in . size and- shape, strength.. and ductility ratios were necessarily determined by a comparison of the ultimate loads and elongations.
Testing in air was rformed on ar 'nstron servo-hydraulic test frame at a loading rate of 0.003 sec'p' Load and strain were measured using a load cell.wi
'an; accuracy of approximately i1.0%-and a-1-inc-gage length extensometer 3 mounted r outside the specimen threads-(grooves). Fig. 8 shows the CERT ^
specimen air test set-up. Results of the air tensile tests are summarized in Table 2, As expected, the XM-19 exhibited substantially higher yield and ultimate load levels and. lower
- elongations compared to Type 304 stainless steel. Load-strain curves for the air
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test specimens are given in Appendix C.- e'
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a Lucius Pitkin ! g New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 O TABLE 2 AIR TENSILE TEST RESULTS O Specimen Yield Load (Ib) Ultimate Elongation (%) Ident.' Material (0.2% Offset) Load (Ib) (5/8 in. Gage) A1 XM-19 1500 1880 17 B1 XM-19 1390 1580 15 C1 XM-19 1590 1700 12 D1 Type 304 740 1120 28 7 Evaluation of the CERT specimen air test results is given in Section 3.4. 3.3.2 BWR Coolant Tests - , LPI provided ARC with ten threaded CERT specimens and associated crevice packing assemblies, as described in Table 3 and shown Figs. 4 through 7. TABLE 3 BWR COOLANT CERT SPECIMENS O Specimen ARC Test ident. Material Heat Frame A-2 XM-19 AJ5018 (PC18) SATEC 1 A-3 XM-19 AJ5018 (PC18) SATEC 2 A-4 XM-19 AJ5018 (PC18) CERT A-5 XM-19 AJ5018 (PC18) Not Used -- J- B-2 XM-19 AJ5018 (CLI 427819) SATEC 1 B-3 , XM-19 AJ5018 (CLI 427819) SATEC 2 C-2 XM-19 A90984 SATEC 1 C-3 XM-19 A90984 SATEC 2 D-2 Type 304 L27527 SATEC 1 D-3 Type 304 L27527 SATEC 2 3 The CERT program utilized dual 200 gallon feed-tanks which provided coolant solution to concurrently-operating autoclaves, identified by ARC as
" CERT" and "SATEC" test frames, in a once-through mode, as shown in Figs. 9 and 10. The dual feed-tanks and associated piping were constructed of austenitic stainless steel. Constant extension rate testing was conducted in the
' five-spccimen "SATEC" autoclave which is constructed from Alloy C-276. The one specimen " CERT" autoclave is constructed from Alloy 600. It should be noted that these materials have no effect on the simulated BWR environment. 9
D , Lucius Pitkin
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New York Power Authority /GPU Nuclear Corp. ' April 3,1997 -
- y Attn.: Messrs. W. H. Spataro & A. Collado M96244 l Schematic diagrams and photographs of the "SATEC" and " CERT" autoclave systems are presented in Figs.11 through 15.
O-Simulated BWR coolant solution was prepared in accordance with specification SP-1302-52-118, as follows:
. Conductivity - 0.4 - 0.5 pS/cm pH _.
6.0 - 7.0 0 Dissolved O2 - saturated at room temperature (-8 ppm) Chloride -
<5 ppb Sulfate -
sufficient to maintain conductivity and pH Temperature - ~550*F. In order to maintain the conductivity and pH within the specified ranges, a 3 sodium sulfate / sodium bisulfate solution was prepared such that the total sulfate concentration was ~100 ppb. Following initial feed-tank preparation, the test solution from both-feed-tanks was analyzed for conductivity, Cl~, and: SO42 , These analyses were repeated following each subsequent feed-tank preparation.
.in addition, both feed-tanks were analyzed for conductivity at least once every two weeks. The pH of the test solution in the feed-tanks was calculated from the 3- measured conductivity assuming that the only constituents in the water were Na*
and SO42. and that the sodium sulfate to sodium bisulfate molar ratio was 3.5:1. To maintain oxygen saturated conditions with a 6.0 .7.0 pH, the solution - inside the feed-tanks was covered with bottled CO 2-free air. - A small positive pressure was maintained to produce a dissolved oxygen concentration in the test 8'. solution of approximately 9-11 ppm. Had the test solution been exposed to air with CO2, the pH of the coolant solution would have been less than 6. Results of the chemical analyses performed on feed-tank and autoclave effluent coolant solutions are given in Tables 4 and 5. A plot of the calculated values for dissolved oxygen in the coolant solution (feedwater) during the entire test program is shown in Fig.16. Simulated coolant dissolved oxygen concentration and pH were calculated as a function of temperature and conductivity, respectively, as shown in Appendix D. S
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Co!! ado - M96244 TABLE 4 CHEMICAL ANALYSES OF FEED-TANK COOLANT O Feed tank 9- Feed-tank 12 - Conductivity cf SO4'8 Calculated Conductivity Cr SO4 calculated Date - (pS/cm) (ppb) (ppb) pH (pS/cm) (ppb) (ppb) pH-9/10/96 0.387 <5 110 6.55 0.367 <5 100 6.57 9/20/96 0.456- (a) (a) 6.49 0.458 (a) (a) - 6.49 n v (a)_ (a) 6.48 0.459 <5 79- '6.49 10/2/96 0.470 10/15/96 0.418 <5 77 6.53 0.410 (a) (a) -6.53 Note: (a) Measurements not required on the noted date based on tank Q_ usage f TABLE 5
' CHEMICAL ANALYSES OF AUTOCLAVE COOLANT EFFLUENT
'O "C ERT" "SATEC" Autoclave Autoclave cr soi 2 cr sot 2 Date (ppb) - . (ppb) (ppb) (ppb) 9/20/96 <5 96 <5 99 .O - 9/27/96 <5 73 <5- 73 10/11/93 <5 74 <5 71 10/18/96 <5 76 <5 70 (a) (a) <5 73 Cf 10/26/96 ' Note: (a) Test completed between 10/18/96 and 10/26/96. Clearly, these results indicate that the simulated BWR coolant chemistry remained within specified tolerances throughout the test program. Furthermore, C- a comparison of the feed-tank sulfate analysis results with the sulfate analyses of the autoclave effluent indicates that sulfate did not accumulate in the autoclaves during the test program. O 11
gL Lucius Pitkin
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New York Power Authcrity/GPU Nuclear Corp. April 3,1997 O= Attn.: Messrs. W. H. Spataro & A. Collado M96244 Prior to testing, the autoclaves were thoroughly cleaned and rinsed with O' .high purity water. The cleanliness of the autoclaves was verified by conductivity measurements. Following cleaning, specimen A-4 was inserted into the loading fixture in the " CERT" autoclave head, and specimens A-2, B-2, C-2, and D-2 were inserted into the loading fixture in the "SATEC" autoclave head. The autoclave heads were then bolted to their respective autoclaves and the -y autoclaves were filled with the coolant solution. Coo! ant solution was pumped through the' autoclaves at a rate of approximately 0.3 gal /hr. - Autoclave pressure , was maintained above the saturation pressure to insure that the autoclaves were completely filled v/ith test solution at all times. The autoclaves were then heated to approximately 550*F. 3 Once the specified temperature, pressure and flow rates were established, the specimens were preloaded to approximately 75% of the 0.2% offset yield load level, as shown in Table 6. It should be noted, that the specification indicated that the CERT specimens be preloaded to 90% of the yield stress. However, a true yield stress could not be determined due to strain hardening affects associated with the presence _of the thread root stress concentrations. o' Additionally, as shown in Appendix C,90% of the 0.2% offset yield load is 'well into the nonlinear regime of the load-strain curve. - Accordingly, preload levels were selected for each threaded specimen group as the point on the load-strain curves just at the' onset of nonlinear behavior. TABLE 6 Q CERT SPECIMEN PRELOAD LEVELS Specimen Yield Load, CERT Specimen Series 70*F in Air (Ib) Preload At 550*F (Ib) A 1500 1100 J- B 1390 1050 C 1590 1200
.D 740 -450 The CERT specimens were held at the indicated preload levels for 300 hr # so as to permit the development of a suitable crevice environment at the stressed thread roots, except for specimen series D which failed prior to the end of the 300 hr hold period. When, during the 300 hr hold,- the !aad on the specimens dropped below 90% of the specified preload, the load on the specimen was
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' New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. _H. Spataro & A. Collado - M96244 0,
increased to the specified value. f g - Following the 300 hr hold period, the specimens in the "SATEC" autoclave were loaded at a displace ~ ment rate of ~3.12 x 10'7 indsec, whereas the specimen in the " CERT" autoclave was loaded at a displacement rate of ~3.12 x 104 in./sec. These displacement rates corresponded to approximate strain rates of 5 4 x 1 0'7.sec 4 for specimens in the "SATEC" autoclave and 5 x 10 sec4 for the specimen in the " CERT" autoclave. Displacement controlled loading was lO_ continued until all specimens fractured. During the course of testing, the following parameters were continuously monitored by a computerized data acquisition system (DAS) which collected data every fifteen minutes (see Appendix E): O . Specimen load;
. Ram head / pull rod displacement;
. Autoclave temperature; and
.- Autoclave pressure.
During testing in the " CERT" autoclave, the displacement transducer 3 malfunctioned. Consequently, a dial gauge displacement indicator was attached to the " CERT" autoclave pull rod so as to provide continued displacement readings. Dial gage- readings did not reveal any changes in the " CERT" autoclave displacement rate.
- After the first four specimens in the "SATEC" autoclave fractured, the N
autoclave was cooled and opened, and the specimens were removed. The specimens were dipped in methanol to promote drying, given a cursory visual examination, and protectively packaged without further cleaning. The crevice forming Jacket was left in place on one half of each specimen. Subsequently, test specimens A-3, B-3, C-3 and D-3 were inserted into o~ the "SATEC" autoclave. Specimen placement in the autoclave was such that
- specimens from the same series were not connected to the same load train (i.e.,
Specimen A-3 was not connected to the same load train as Specimen A-2 in the previous test, etc.) in order to eliminate any bias in data due to position in the loading fixtures. The second test'in the "SATEC" autoclave followed the same procedures described previously for the first "SATEC" autoclave test. The test in O the " CERT" autoclave continued uninterrupted during, and between, the two CERT tests in the "SATEC" autoclave. O 13
e Lucius Pitkin
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New York Power Authority /GPU Nuclear Corp. April 3,1997 , Attn.: Messrs. W. H. Spataro & A. Collado M96244 The post-test procedures for the four specimens frcm the second test in the "SATEC" autoclave and the single specimen tested in the
- CERT" autoclave 3 followed those described a'c ove for the specimens from the first "SATEC" autoclave test.
3.4 Air Test Results Tensile results for the CERT specimens tested in air were previously D presented in Table 2. To reiterate, XM-19 exhibited substantially higher yield and ultimate load levels and lower elongations compared to Type 304 stainless steel. In addition to establishing the preload levels for BWR coolant CERT specimen tests, the air results provide the basis for calculating the coolant to air load (strength) and ductility ratios - both measures of resistance to IG3CC. Since the air tests were performed at room temperature and the BWR coolant tests at D 550 F, the air test ultimate load (strength) levels were adjusted to reflect the decrease in strength associated with increasing temperature. Based on review of allowable stress levels provided in the ASME B&PV Code (Section ll, Part D, Table 1A) for the subject materials at the test temperature, a factor of 0.85 was applied to the room temperature ultimate tensile load levels. These adjusted ultimate loads (strength) were used to calculate the load ratios for XM-19 tested C in simulated BWR coolant. Examination of the air tested CERT specimens (A1, B1, C1, and D1), shown in Figs.17 and 18, revealed the fractures to be similar and to have occurred through the 2"d or 3'd thread root. In addition, the specimen fracture surfaces were rough and irregular in appearance with no evidence of crack O branching - features characteristic of ductile overload fracture. Scanning electron microscopy of the air tested specimens, shown in Figs.19 through 22, invealed a rough fracture morphology cliaracterized by microvoid coalescence, as is typical of ductile overload fracture. g 3.5 Constant Extension Rato Test Results Load versus time plots for the two "SATEC" autoclave tests and the
" CERT" autoclave test are given in Figs. 23 through 25. Maximum load and time to failure results for each specimen group are summarized in Table 7. Ram head displacement rate versus time (pull rod displacement versus time for the " CERT" autoclave), autoclave temperature versus time, and autoclave pressure versus D time plots for each test are given in Appendix E. It is evident from Appendix E, that pressure and temperature remained constant during the course of testing and that pull rod displacements increased ur.;fo,mly up to the specimen fracture 14
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O Lucius Pitkin
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New York Power Authority /GPU Nuclear Corp, April 3,1997
- g Attn.
- Messrs. W. H. Spataro & A. Collado M96244 loads.
!O TABLE 7 CONSTANT EXTENSION RATE TEST RESULTS
! "SATEC" Test i "SATEC" Test 2 ' CERT" l
d d d ! (5 x 10sec ) (5 x 10'7 sec ) (5 x 10sec ) Specimen Time to Maximum Time to Maximum Time to Maximum O Group Fall (hr) Load (Ib) Fall (hr) _ Load (Ib)_ Fall (br) Load (Ib)
-A 368.3 1378 370.1 1410 891.7 1374 l
B 362.3 1323 359.9 1303 - - c 345.1 1363 348.4 1368 - - O D 198.2 414 159.7 449 --- --- It is clearly evident from these results, that the Type 304 stainless steel specimens fractured prior to the end of the 300 hr hold period, in that the Type 304 specimens were intentionally sensitized and fractured at a load significantly C below their ultimate load, demonstrates that the simulated BWR coolant was sufficiently aggressive to promote stress corrosion cracking and thus suitable for evaluating the resistance of XM-19. For the XM-19 specimens tested at a strain rate of ~5 x 10'7 secd , the O group C specimens failed first, followed the group B specimens and then the group A specimens in both "SATEC" tests. The maximum load attained by group A specimens was somewhat greater than that attained by the group B and C specimens, in fact, the CERT coolant exposed specimen failure loads ranked in the same order as the ultimate load results obtained in air, indicating little or no environmental effect on XM-19. O 8 Similarly, the group A, XM-19 specimen tested at a strain rate of ~5 x 10 4 sec reached nearly the same maximum load as the group A specimens tested at ~5 x 10'7 secoand a load greater than the XM 19 group B and C specimens. This latter result clearly indicates that there is no effect of strain rate on the resistance of XM-19 to IGSCC. Moreover, the reproducibility of the test results for the three XM-19 specimen groups attests to the homogeneity of the XM-19 0 material and the reproducibility of the CERT conditions. The relative resistance of XM 19 to IGSCC was assessed by calculating O 15
a Lucius Pitkin
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 O the coolant to air load (strength) and ductility (elongation) ratios. Results of such calculations are given in Table 8 and indicate that hot-rolled XM 19 exhibits the O same load and ductility capacity in simulated BWR coolant as it does in air. It is also evident that sensitized Type 304 stainless steel is extremely susceptible to fracture in BWR coolant. Had XM-19 been susceptible to stress corrosion cracking in the BWR coolant, then the XM-19 specimens would have exhibited significant reductions in both the load and ductility ratios. l J TABLE 8 l CERT LOAD AND DUCTILITY SUSCEPTIBILITY RATIOS Specimen Max Load in Coolant Elonastion in Coolant ident. Material Strain Rate Max LoaJ In Air Elongation in Air A2 XM 19 5x 10 sec" 0.97 0.88 D2 XM-19 5x10 sec" 0.98 0.93 D C2 XM 19 5x10 sec" 0.94 1.00 02 Type 304 5x10~' sec" 0.43 0.14 A3 XM 19 5x10 ' sec" 0.98 ' O.88 B3 XM 19 5x10 sec" 0.97 _f .00 C3 XM 19 5x10 sec" 0.95 1.00 J D3 Type 304 5x10 sec" 0.47 C16 A4 XM-19 5x10* sec" 0.96 1.12 In order to verify the mode of the XM-10 and Type 304 CERT specimen j fractures, all test specimens were examined visually, metallographically, and by O scanning electron microscopy (SEM). Prior to examination, the specimens were cleaned using benign cleaning techniques, that is, fiber brush scrubbing and ultrasonic agitation. Visual examination was performed using a binocular microscope up to a magnification of 25X. SEM examination was performed at an accelerating potential of 20 kV. J Visual examination of the CERT specimens, shown in Figs. 26 through 30, revealed the XM-19 fractures to be similar and to exhibit rough and Irregular fracture profiles and secondary cracking of the adjacent thread roots, as is chcracteristic of ductile overload fracture. In contrast, the Type 304 specimens exhibited relatively flat and granular fracture profiles, as is characteristic of stress i corrosion cracking. The Type 304 specimens also exhibited intergranular g secondary cracking in the adjacent thread roots. SEM examination of the XM-19 CERT specimen fracture surfaces revealed a rough fracture morphology characterized by microvoid coalescence, 16
O Lucius Pitkin New York Power Authority /GPU Nuclear Corp. April 3,1997 , Attn.: Messrs. W. H. Spataro & A. Collado M96244 ,g characteristic of ductile overload fracture, as shown in Figs. 31 through 37. More importantly, the XM-19 specimens did not exhibit any evidence of intergranular LO fracture. However, as shown in Figs. 38 and 39, the Type 304 CERT specimen fracture surfaces exhibited an intergranular morphology, as is characteristic of stress corrosion cracking. Clearly, the XM-19 specimens were resistant to IGSCC in the same environment in which sensitized Type 304 stainless steel exhibited extr,eme susceptibility to IGSCC. O Metallurgical evaluation of the CERT test specimens was performed to (1) , further assess the mode of fracture and (2) determine the nature of the , secondary cracking in the thread roots adjacent to the fracture surfaces. One-half of each specimen was thus sectioned longitudinally so as to intersect the fracture surfaces, mounted in plastic, polished, and electrolitically etched for metallographic examination. O The fracture profiles of the XM-19 specimens, shown in Figs. 40 through 43, were, except for specimen A4, irregular and typical of ductile overload fracture. Specimen A4 exhibited a slanted fracture profile also characteristic of ductile shear fracture. The slanted nature of the A4 fracture is attributed to the development of coincident fractures in adjacent threads which merpd at the O point of final fracture. in contrast, the Type 304 specimens exhibited intergranular fracture profiles with intergranular secondary cracks, shown in Fig. 44, as is characteristic of stress corrosion cracking. O Metallographic examination of the secondary cracking in the thread roots adjacent to the fractures, shown in Fig. 45, revealed blunted ductile tears in the XM-19 specimens and branched intergranular cracking in the Type 304 specimens, further demonstrating the resistance of XM-19 to IGSCC and Type 304's sensitivity to the coolant environment. O f O $7
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, Lucius Pitkin
............ g ~
New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244
4.0 CONCLUSION
S i O Results of the XM-19 constant extension rate test program revealed that hot-rolled XM-19 stainless steel material, as evaluated using threaded specimens under crevice conditions in a simulated BWR environment, is n21 susceptible to ! intergranular stress corrosion cracking (IGSCC). That is, the relative resistance of XM-19 to,1GSCC, as assessed by calculating the coolant to air load and ductility (elongation) ratios, revealed that XM-19 exhibits the same load (strength) !O and ductility capacities in simulated BWR coolant as it does in air, it was also evident from the CERT program that sensitized Type 304 stainless steel is extremely susceptible to fracture in simulated BWR coolant. i Furthermore, the results of this investigation indicated that a reduction in test strain rate from 5 x 10'7 sec to 5 x 10-s3 ,c adoes not after the resistance of O XM-19 to IGSCC, Finally, the reproducibility of the results for the three different conditions of XM-19 evaluated herein attests to the homogeneity of the XM-19 material and the reproducibility of the constant extension rate test conditions. O RSVAb52/M96244 Fmal Report O O-0 0 18
.O Lucius Pitkin
. . . . . . . . . . . . g_
New York Power Authority /GPU Nucleal Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 O'
5.0 REFERENCES
O 1 " CERT Testing of Type XM-19 in Simulated BWR Environment," Document No. 51-1235147-00, B&W Nuclear Technologies, Lynchburg, VA, December 20,1994. O-O O O O O' o- 19
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New York Power Authority /GPU Nuclear Corp. April 3,1997 l ! Attn.: Messrs. W. H. Spataro & A. Collado M96244 ! m. _m l j_. ( 304 SST SHROUD
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. . . . . . . . . . . . g_
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 m D I D i ? O A i11{tti< LUCIUS PliklN. INC Fig.4 Close-up photograph showirig the groJp A XM-19 CERT specimens in 9 the as-machined and crevice jacketed condition. Unjacketed specimen A1 (bottom) was tested in air. 3 D .
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............ g "' "
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New York Power Authority /GPU Nuclear Corp. April 3,1997
' Attn.: Messrs. W. H. Spataro & A. Collado M96244 m
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New York Power Authority /GPU Nuclear Corp. April 3,1997 g Attn.: Messrs. W. H. Spataro & A. Collado M96244
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3
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O Fig. 23 Load-time plot for specimens A2, B2, C2, and D2 tested in BWR 3 O coolant (550 F) at a strain rate of 5 x 10 sec O
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. . . . . . . . . . . . g_
New York Power Authority /GPU Nuclear Corp. April 3,1997 ' Attn.: Messrs.' W. H. Spataro & A. Collado M96244 y,_- 1500~ ,O x . -- _ O. 1000 Spec. A3 j g Epec.m g -WG g_ EbecDB 500 - w_ _- - _- O o ' ' - ^ ' - - - **
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O-i Fig; 24 Load-time plot for specimens A3, B3, C3, and D3 tested in BWR 4 O coolant (550 F) at a strain rate of 5 x 10 sec O O
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New York Power Authority /GPU Nuclear Corp. April 3,1997 O Attn.: Messrs. W. H. Spataro & A. Collado M96244
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l ~~ l New York Power Authority /GPU Nuclear Corp. April 3,1997 g Attn.: Messrs. W. H. Spataro & A. Collado M96244 , m . . . I g' ws: . , l 4 . I i j l l
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. . . . . . . . . . . g-New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spatarc & A. Collado
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O Fig. 38 Scanning electron micrographs showing the fracture surface of o specimen D2, after testing in simulated BWR coolant, to exhibit an intergranular morphology, as is characteristic of stress corrosion cracking. A small microvoid coalescence covered final fracture zone was also evident. O 1
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Fig. 39 Scanning electron micrographs showing the fracture surface of 3 specimen D3, after testing in simulateo BWR coolar.t, to exhibit an intergranular merphology, as is characteristic of stress corrosion cracking. A small microvoid coalescence covered final fracture zone was also evident. 9 e
D Lucius Pitkin g New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado
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J
) Lucius ............ Pitkin 8 New York Power Authority /GPU Nuclear Corp. April 3 1997 Attn.: Messrs. W. H. Spataro & A. Collado ) M96244 )
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o Lucius Pitkin
. . . . . . . g_j thi teR>
New York Power Authority /GPU Nuclear C arp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 O O ( tyg 7I 4g-qg ;,.,Aj -- ., 8 p 1 s 'h' N ' t 'f*, . . ..
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O Lucius Pitkin
~~
New York Power Authority /GPU Nuclear Corp. April 3,1997 g Attn.: Messrs. W. H. Spataro & A. Collado M96244 O o
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D Lucius Pitkin g lbf eNt New York Power Authority /GPU Nuclear Corp. April 3,1997 g Attn.: Messrs. W. H. Spataro & A. Collado M96244
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specimens D2 and D3, after testing in simulated BWR coolant, to be irregular with extensive intergranular branched cracks, as is characteristic of stress corrosion cracking, D-
~
J Lucius Pitkin g_
~~
New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 J < A3 D l i O D f 3 D3 ',"' d sN_ O Fig. 45 Photomicrographs (200X) showing the roots of threads adjacent to 3 the fractures of specimens A3 (XM-19) and D3 (Type 304) in the as-polished condition. Specimen A3 exhibits a blunted ductile tear, whereas specimen D3 exhibits branched and oxide filled secondary cracks, typical of stress corrosion cracking. J
D Lucius Pitkin
. . . . . . . . . . . . g_
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New York Power Authority /GPU Nuclear Corp. April 3,1997 Attn.: Messrs. W. H. Spataro & A. Collado M96244 3 0 D APPENDIX A 3 Specification For Crevice Corrosion Testing For Hot Rolled XM-19 Ma.erial Oyster Creek And James A. Fitzpatrick Nuclear Power Plants SP-1302-52-118 O O O e 9
. _ _ _ _ _ _ _ _ _ __ A
E SPECIFICATION SP-1302-52-lis OUAlfTY CLASSIFICATION "REOU1.ATORY REOUTRED* SPECIFICATION - FOR CREVICE COAROSION TCETING FCM HOT-ROften xx.19 MATERTAL OYSTER CRear NUCLEAR GENERATING STATION & JAMES A. FITEPATRICK NUCLEAR POWER PLANT 4 PREPARATION i b. M b shnoff '# DATE //-I-N
/#A. Coll o/S. D.
ENGINEERING APPROVAL d'l L - DATE bb f ( we aesw QA CONCURRENCE DATE'/N ' '
' A c ., MFV REV_ 2 i
A00010411 M 5
O lsumua b r b gf DOCUMENT NO. SP-1302-52-119 0 mts CREVICE CORROSION TESTING FOR HOT-POLI.ED XM-19 MATERIAL REV
SUMMARY
OF CHANGE APPROVAL DATE 1 Deleted proprietary note from cover sheet, Reference 2.3.1 was Revision 0. Deleted f[ j l/v1 g./ /- 7g Patent Pending from 4.2 and added "see p f O contract details for proprietary definition . o' . e g/gg In paragraph 4.3, 1.250 inches diameter was 3 ' J L inches. In Paragraph 4.4 300 hours was 7 O days, added att'.lc loading, ground and , [ thermal isolation requirements and testing of one additional spacimen at lower strain rate. /7' M8# g.y /, g M %/df684 Deleted pricing section 7.0. Revised 6.2.7. Added 6.2.11. 2 Reference 2.3.1 was revision 1. Revised 4.2 to specify that the
~&j lL~b 4 &
8Pocens tested in air sW be at rmm temperature and that l best treatment shall be ramped vs. Step change. Revise 4.4 to ' f fq/p[gg, l specify water chiey momtoring and flow rate requiremasts. g , %,m3 L Added stram rate requirements for specunens tested in air. ' mis lo 7 f. 3 - 9 'P revision captures the "as-built" conditions. l O O O N0036 (03-90) la e e
l SP 1302-52 Il8 Rev.2 May 1996 . Crve. Cor. Hot Pdd XM 19 Page 2 of 9 l 4 TABLE OF CON'IENTS l
)
F East 4 1 4 ' 1.0MPE...........................................................................................................................................3 2.0 CODES AND STANDARDS ....................... ......... .... ...... .......... .. ..... ... .. ... ... ....... ................ ..... ...... 3 1 1
- 2.1 Amnerican Society for Testing and Materials (ASTM) ... ............................................................ 3 2.2 Anmericas National Standards lastitute (ANSI) ................................................................. ........ 3 2.3asferenees....................................................................................................................................3 2
4 ~ 3 .0 GENERAL REQUIREMENTS .............. ... . . ....... .... .... .... ...... ..... .... ... .... .... . .... ...... . .. .. ... .... ... .. ... ... 4 3.1 Work to be Provided by the Contractor ..................-................................................................ 4 4 3 .2 Wo A 2 ba Pre h h . .. . . . . .. ... . . .. . . . . . . .. . . . . .. . .. . . .. .. . .. . . . .. .. . . . . . . .. . . . . . . . . . . . . . .. .. .. . .. . . . . .. . . .. . 4.0 DETAIL ED REQUIREMENTS . .. .. ............. .......... .............. .. .. . ... .... .. .. ... .. . .... . . . . . ........ .... . . .......... . 4
- 4.1 Description of Intended Use .... ..... .... ..... .......... ... ...... .... . .... .. .... . .... ... .. . . . ... .. ... ..... . . ....... ....... ._ ........ 4 1 - 4.2 Spechnes Preparation ...... .......... .. .............. ..... .... ........ ........ ... ... .. ......... .. .. .... .... . . . ............ ... ...... .. 4 4.3Maanrials......................................................................................................................................d 4.4 Testing and Evaluation of Tests ...... ... ... ......... .. ... .. ... . ........ ..... ... ...... ...... ... .. . . . ... .... . ..... .. ... ........ . ... 6 4.5C1.aming...................................................................................................................................7 4.6 Marldag & Identi5 cation A Traceability .................-......~...-...................... .......................... 7 5.0 QUALITY ASSURANCE ...... ................... ..... ... ..... .............. ... . ...... . .... ... ...... . ... .......... .................. 7
- 6.0 INFORMATION TO BE SUBMITTE D ..... ...................................... .........................................~. 8 6.1 with Proposal . .... , ...... ... . ........... ........_ _.. ...-. .------.--.~ .---- .. -. . ~..- -. .--- 8 6.2 A fter Aw ard of Contract .. . ........ ........ ........ .. ...... ... .... .. ... ..... ~... ......... ... . .. ........... ...... .... .. . . ..~... 8 t
4 =.n g 1 4 J I 2 I a 4 014/204 i 12/2/96 i
- - . - , - . ., ,n .-.- - ,. --
._ l i SP 1302 52118 Rev.2 ;
i May 1996 ; 1 Crve. Cor. Hot Rol'd XM l Pass 3 of 9 l i i i 1.0 SCOPE i . His specdication covers the requiranents for crevice conosion testing of hot-rolled XM 19 and
- -304 stainless steel mataruls. .
i Hot-Rolled XM 19 matsnal was used in Boder Water Ramotor (BWR) shroud repairs. %s 304
; stainless steel testing is for ocatrol purposes only. nis testing is to comply with the requirements
- of the U. S. Nuclear Regulatory Comunission (NRC) for purpees of demonstrating that hot-rolled ;
l . XM 19 in the thrusJed (crevice) condition will perfonn ==tishaardy in a BWR envisn==ar* ne i maeorial testing audined herein addneses Hot-Rolled XM-19 in servios at the Oyster Causk e !- Nuclear Generating Station operated by GPU Nucisar (OPUN), and the James A. Fitzpatnck ! Nuclear Power Plant, opermesd by the New York Power Authority (NYPA). i 2.0 CODES AND STANDARDS Unless speci5ed herom, tbs latut revision of the following codes and standards t. hall apply. l L Asserican Society for Testing and Materials (ASTM) . 2.1 i ! 2.1.1 A479-92 SP c=*ian A for Stainless and Heat-Rasistant Stasi Bars and Shapes for Use in Boders and Other Pressure Vessels. ! 2.1.2 G49 - Standard Practice for Preparation and Use of Direct Tension Stress-Coryosion Test Specimens. l 2.1.3 G78 - Standard Guide for Crevios Corrosion Testing ofIron-Base and Nickel , l Base Stamiane Alloys in Sea Water and Other Chionds Aqueous Environments 2.1.4 A380 - Cleaning and Descahng stainless Steel Parts, FM and Systems. l I- . i 2.2 ~American National Standards Institute (ANSI)
- 2.2.1 N45.2.1 Clemmng Requirements - 1973 edition l 2.3 References ,
f
- i. g GPUN Drawing 3B-SKM 722, Rev. 2, Tension Test Specimen for Crevice l f,3.1 CorrosionTestag ,
1 i i '. 014/204 a i 12/2/96
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SP 1303052118 Rev.2 May 1996 Crve. Cor. Hot Rol'd XM 19 Pass 4 of 9 3D GENERAL REQUIREMENTS 3.1 Work to be Provided by the Contractor a) Dmk- < = of test procedures b) - Preparation of test specimens. c) Providing test fhedities, tochas, 6xtures and testies apparatus, d) Performanos of tests. . e) Evaluation and Reporting of:sst resul:s in report form. f) Tachair=1 support (as required) in discussions and submittals to the NRC. l 1 3.2 Work to be Provided by Others a) Suhient bar stock of test materials (XM-19 HR and 304 SS), B) Providag test certi5ed metsnals docim==tatian of the supplied material u reqmrod. c) Field veri 6 cation of testag and source inspection as required. 4.0 DETAILED REQUIREMENTS
~
4.1 Desedption ofIntended Use The material testing progrwn required by this WM= is to demonstrate the resistance of XM-19 matenals to Interganuls Stress Corrosion Crackag(IGSCC) under creviced BWR environmental conditions. The crevun has bem created into the design of reactor internals repair in the form of machme-threaded joints. 4.2 Spechnen Preparation The sponmen design shall be such that the established crevice is not lost durmg the testing process. Reference 2.3.1 shows an Wahic type specimen wrapper design.
'Ihe Contractor may provide alternate specimen type subject to GPUN and NYPA approval.
'Ibe specunen shall ba cut (thermal cutting is prohibited) and whiaad from the supplied bars.
014/204 12/2/96
4 SP 1302 520118 Rev.2 May 1996: Crve. Cor. Hm Rol'd XM 19 Pass 5 of 9 All final machiand surfaces, includag threads, and grooves shall be accomplished with sharp tools and cutters that ha.w not been pronously used on carboc steel. Light sandag with approved abrasiw cloth may be used to obtain surface finish regarements. Final machining pass / passes shall be hmited to .010" metal rernoval. M made by rolling am nm sannitted. , All abrasin cleaning shall be performed with abrasin materials ihat am not contaminated with residues other than austenitic stainless and nickel chrome alloys. Cutting tools shall be properly cooled with suf!Icient fluid to proves overbesting of tools and specima materials. Cuttag lubrimats, tools, testing apparatus, fixtmos, workers and other equipment used in contact with the apari=== ce the testag fluid shall be con: rolled as to their anae==iamar levels.1hs following lunits apply to thoes ====anhia products which contaa the test specimen. CCNTAMINANT LIMITS ! Zinc,its alloys and/or compounds 50 com, max. Totalheave metals: 200 ppe, max. (Pb, Hs, Cd, Cu, their alloys and/or
="r==la)
Totallendable halosses. 100 ppe, max. (Cl , Br , F., etc.) Totalhalogsos: 1,000 ppa, max. -
- (Cl , Br , F , etc.)
Total sulfur and its compounds 1,000 ppm, max. When surfaces are found to be contammated by contam with product not meeting the - above limits, the surfaces hall be cleaned in accordance with a NYPA and GPUN approved Contractor procedure. Ibe Contractor and sub-tier vendors must use methods to prevent contammation of test matenals lhe practices of ASTM A 380 shall be followed. Gnndmg or centericss gnadmg, incidental weldmg, or repair weldmg of the test specunen is not permitted. A total of three heats of XM 19 material require testing. Two specunens of each heat shall be tested in BWR coolant envirc unent and one specunen per each heat shall be tested in air at room temperature as a control specimte. In addition, one specimen of sensidzed
- Type 304 stamless steel shall be tested in the test environment as a control to assure adequacy of the test mmronment to produce IGSCC.
014/204 12/2/96 . b A
_ . _ _ ._.. _ . _ _ _ _ _ _ _ _ _.q
- I i SP-1302 53 ils , {-
i Rev.2 May 1996 ! Crve. Cor. Hot Rol'd XM 19
- Page 6 of 9 4
j Sensitization of the Type 304 stainless steel shall be accomphshed by best treatmet at 1250 *10*F for one hour, followed by furnace cool. Heat treatment shall be ramped i; versus slap change. a j 4.3 Materials 1 2-
'!)s XM-19 materials were purchased ta ASTM-A479, hot-miled with special corrosion test A262 Pracnos A or E.
1
- h XM-19 as supplied by "Others" has buen previously subjemed to a load conditioning
!- at 80 Kai semes. A 1; i j The 304 stainians sesel materials were purchased to ASTM A479 with special coricei:n i test A262 Premios E. 'Ihs 304 stainises sesel was not load condieianad 'Ihis materialis in 2 the solution annealed aandian per ASTM A479. i~' . .
'Ihe XM 19 samples for specimen making will be supplied in one piece,1.5-inch diameter ,
[ ? by g-e- - ^ ", 6 inches long for each best of material. ; 1 i 'Ibe 304 stainless samples for the control apari=ma making will be supplied in one piece,
. %- - -- y 1.250 inches diamanar by 3 inches long.
Other materials are shown in Parerence 2.3,1. i
- - -j 4.4 Testing and,, Evaluation of Tests
'Ihs test medium shall be sinadated BWR reactor coolant at 550*F *10*F with a 8 to 10 ppm oxygen. r'ane==inant levels shall be cont:ntled to raminimia conductivity of the test ,
medmm in the range of.4 .5 pS/Cm using sulfate addition. Water cha-istry must be
- momtored and recorded, once a week for the first month of the testag (at the foodwater
[ 'and of5uset) and once a month thercafter for the longer duranon test to capture the j equilibrium of bulk water conditions. In addition to oxygen, chlorides and sulfataa shall be ;
- i. measured. Water pH range shall be 6.0 to 7.0, corrected to 25'C.
Flow rate to be_kept as slow as ramenankle actuevable while ==ia+=ialaa the required l - oxygen levels in order to simulate the oxygen differential in the crevice Flow rate to be L ' measured in ft/sec. across the specimen surface 3 c Test acceleration shall be accomplished by subjecting the specisnem to slow strain :ste 3 4 '
- testmg 'at a low strain rate of 5x10 sec until failure. One addinonal specimen, from at whichevec heat has sufficient 4 material, shall be subjected evai lower strain rate of 5x10 soci' until failure as a confirmanon that ths 5x10 to slow' stmin rate strain rate accur + sly detects the potennal failure marhaala= Elongation vs Timr,shall be 1
~
- recorde
- 8 for all test specimens Prior to straimag, the specunens shall be praenad*~=4 j for 300 hours in the' elevated temperature test envuonmcat and statically loaded to 9W. of L yield stress for material during the preconditxxung period.
014/204
- l. ^ 12/2/% -
lL L,- -.. .
, ,- , . , , , ~ , -, , , ~ ~ , - . - , . , , -
l SP-1303 52 Il8
- Rev.2 May 1996
- Crve. Cor. Hot Rd'd XM 19
- . Page 7 of 9 4
l Strain rate for the specimens tasted in air shall be in accordance with ASME range for g' i tensile tests. Lower bound rate shall be used. %e stenin rate achieved shall be stated in ! the final report. 4 Specimens shall be electrically grounded and thermally isolated fhun the envirnamaw j, 2 Following the test, specimens shall be an==iand using conventional light microscopy and 4 scana'as electron microscopy. De specansns will be examined fbr ladic=*ia== c(stress conosion crecidag on the firectus suribos and along the gauge section. A ramin== of two
- metallograpide mounts will be evaluated for each specimen. Contractor to supply wntion
!- evaluation, graphs and photographs of test reauks. i 4.5 Cleaning De completed specimens shall be cleaned per ANSI Nt,5.2.1, Claw B Clanalia==v prior to insertian into the autoclaves. 4.6 Maridag & Identincation & Traceability All XM 19 and 304 specunens saall be idatified and traced to their unique heat number for the material. All markings shall be done with low stress vibrating tools. Marking in the specimen sage sectionis not penrutted. All specimens shall be traceable to their bar stock where the specunen were cut from. He Contractor shall be responsible for u.amtaming a Quality Control System that would preclude the mixing of different matenals. 5.0 _ QUALITY ASSURANCE All work is clammirwi as " Regulatory Reqmred." ne Supplier Quahty Classi6 cation List requirements apply. Work shall be done under a Quality Assurance program which meetr 10CFR50 AWiv B or an - approved' program by GPUN and NYPA. All work shall be p.Jv...d. in md.c.c4 with standard laboratory t%m. Calibrabon of instruments shall be as required by the National Bunau of Standards / National Insatute Standards and Technology.- All fabrication of specimen and crevice corrosion testmg activities shall be controlled by the
~ Contractor.
014/204
. 12/2/96
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SP.1302 52118 s Rev.2 May 1996 Crve. Cor. Hot Rol'd XM-19 Page 8 of 9 GPUN shall be noti 6ed of any non conformance to this speci5 cation or to any contractor
. requirements approved by GPUN and NYPA.
GPUN and NYPA, or their agents, shall how complets access to the Contracids and
' Subcontractor's fhedsties to witness work and i@ in progress. GPUN and NYPA shall have complete access to all dstr, and records reisted to the thbrication, testing, and inspection of the 8Peonnes.
6.0 INPORMATION TO BE SUBMITTED . l : 6.1 With Proposal l 6.L1 Description of testing fhedity. 6.1.2 ' Referonos history list of similar work performed. 6.1.3 E-W and/or ahernatiw to the requirement of this at-harian 6.1.4 Schedule to perform the testag fhun Purchase Order ph to issuanos of Saal report. 6.1.5 CornAnarv== of quali5ed personnel to perform tests and evaluaes test results. 6.1.6 Qua'lity Assurance Program for infonnation. 6.2 After Award of Contract 6.2.1 Detail testms procedum and test looo diagram, for approval prior to start of . testag. , 6.2.2 Records of alltesting activities. 6.2.3 T@ Records on all test specimen matenals. 6.2.4 All calibration records for calibration instruments used during the performance of the contract. 6.2.5 Specunen detailed drawmgs for approval prior to start of fabtication. 6.2.6 Method of extracting / cutting material for specimm makmg 6.2.7 Technical evaluaten of testing results 6.2.8 Phciep.phs of testmg apparatus. 014/204 12/2/96
SP-1302 52118 Rev.2 May 1996 Crve. Cor. Hot Rol'd XM.19 Page 9 of 9 6.2.9 Certifkation ofIJboratory TF l =r!=== for information prior to start of testag. 6.2.10 All documentaten of materials tested (i.e., Material Test Reports). 6.2.11 DraA and Final T-hair =1 Raports (four copies for GPUN and four copies for , d NYPA). i l 8 e 014/204 12/2/96
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. . . . . . . . . . . . g_
New York Power Authority /GPU Nuclear Corp. April 3,1997
. Attn.: Messrs. W. H. Spataro & A. Collado M96244 0
,O - l O-APPENDIX C
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