ML20207A886
| ML20207A886 | |
| Person / Time | |
|---|---|
| Site: | 07109268, 07201023 |
| Issue date: | 02/28/1999 |
| From: | External (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20136H802 | List: |
| References | |
| SNC-96-72SAR, SNC-96-72SAR-RD, NUDOCS 9903050300 | |
| Download: ML20207A886 (19) | |
Text
-.
SNC-96-72SAR l
Revision D I
i SAFETY ANALYSIS REPORT FOR THE TRANSTOR* STORAGE CASK SYSTEM 10CFR PART 72 PREPARED BY:
BNFL Fuel Solutions, Corp.
ScoTTs VALLEY, CALIFORNIA FEBRUARY - 1999 9903050300 990225 DR ADOCK 071 268 6
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SAR - TranStor* Storage Cask Revision D L)ocket No. 72-1023 February 1999 l
TABLE 3.3-5 MECHANICAL PROPERTIES OF A-500, GRADE C FERRITIC CARBON STEEL Property (units)/ -20
+70
+200
+300
+400
+500
+700 i
Temperature ('F)
I l
Ultimate Strength' 62.08 62.0 62.0 62.0 62.0 62.0 62.0" 58.7" l
(ksi) 1 l
Yield Strength *
'50.0 50.0 50.0 45.6 44.3 42.9 40.4 36.0 l
i l
(ksi) l i
l 1
20.7 20.7 20.7 20.7 19.6 Design Stress 20.7 20.7 20.7
. Intensity'(ksi) l Modulus of 29.9E+3 29.8E+3 29.5 E+3 28.8E+3 28.3 E+3 27.7E+3 27.3 E+3 25.5E+3 d
Elasticity (ksi)
Mean Coeflicient of i
Thermal Expansion' 4.9E-6:
5.0E-68 5.42E-6 5.89E-6 6.26E-6 6.61 E-6 6.91 E-6 7.41 E-6 (in/in/ F) j Poisson's Ratio' O.29 l
Density' 490 lbm/ft' (0.284 lbm/in')
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l ASME Boiler and Pressure Vessel Code, Code Case N 71-16 Table 5 ASME Boiler and Pressure Vessel Code, Code Case N-71-16, Table 3.
]
Calculated as the lesser of S/3 or 2S/3 per ASME Code d
ASME Boiler and Pressure Vessel Code,Section II, Part D, Table TM-1.
ASME Boiler and Pressure Vessel Code,Section II, Part D, Table TE-1, Baumeister & Marks," Standard liandbook for Mechanical Engineers," 7th ed.
Extrapolated from specified values.
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Based on testing performed by SNC/BFS.
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SAR - TrinStor* Storage Cesk Revision D
' Docket No. 72-1023 February 1999 l
l 3.4 :
GENERAL STANDARDS FOR CASKS 1
3.4.1 CHEMICAL AND GALVANIC REACTIONS The materials used in.the TranStor. System (e.g., steel, concrete, etc.) will not experience significant chemical, galvanic, or other detrimental reactions. The only contact between dissimilar materials is on the inside of the basket which is coated and placed in an inert
- environment. All components open to ambient' air are made of similar materials with essentially equal potential in the Galvanic Series of Metals and Alloys. In addition, they are protected from the atmosphere by coatings.
1 i
~ Coatings used in the TranStor" basket are qualified via an extensive testing program. They are shown to not be susceptible to the chemical reaction with borated water so that there is no potential for generation of hydrogen gas in the basket. Nevertheless, the absence of hydrogen is assured by venting the air space in the basket and sampling the gas prior to seal welding the shield lid (as described in Chapter 8.0 of this report).
Coating Design Parameters are shown in Table 3.4-11.
l 3.4.2 POSITIVE CLOSURE The TranStor System employs a positive closure system that is composed of seal' welds at four locations: 1) Basket shield. lid to shell; 2) Basket structural lid to shell; 3) Basket structural lid to basket shield lid at the penetration ports; and 4) Basket drain and port cover plates to structural lid. The closure welds are shown in the drawings. Welded closure ensures that the' basket can not be inadvertently opened and eliminates the publem _ of seal deterioration during service. The basket shield lid-to-shell weld is helium leak checked to 4
ensure leak tightness of better than 10 sec/sec. Leakage greater than this limit shall be cause for weld repair.
The storage cask cover is bolted in place and has provisions for tamper indication. The cask is not ' subject to vibration loads that could cause the closure bolts to loosen or fall out. - No s inadvertent opening of the cover is possible.
/
3.43 : LIFTING DEVICES i
The TranStor" System has separate provisions for liAing the storagp cask,.the basket, and the transfer cask. The storage cask.may be lined from below using air pads or from above i
< using a transporter. _ lt should also be noted that both the top and bottom lia are not important j
L to safety since the cask is lined only a few inches. The TranStor storage cask lining p
components must _
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p SAR -TranStor* Storage Cask Revision D Docket No. 72-1023 February 1999 TABLE 3.4-11 DESIGN PARAMETERS OF COATINGS HASKET INTERNAL, CO ATING Coating Requirements Totally Inorganic Binder System Non-Reactive Inorganic Filler System No Volatile Organic Compounds Resistace to Chemical Corrosion Application Temperatures to 1000 F Qualification Standards Blistering ASTM D714-87 Flaking ASTM D772-93 Delamination ASTM D3911-95 Adhesion ASTM D5144-91 Radiation Tolerance ASTM D4082-95 Chemical Resistance ASTM D3912-95 Emissivity ASTM E408-71 Qualification Tests and Acceptance Standards Qualification Test Test Parameters isual xam Adhesion
- Endssivitf Gen ration Boric Acidimmersion:
4000 ppm boron Minimal Per Standards
>200 psig N/A
@ ambient temp.
120 hrs @ ambient Listed Below*
Boric AcidImmersion:
4000 ppm boron Minimal Per Standards
>200 psig N/A
@ elevated temp.
to 21l'F@3 F/hr Listed Below*
Heat Tolerance:
72 hrs @850 F N/A Per Standards
>200 psig
>0.77 in He atmosphere Listed Below*
Radiation Tolerance:
1.2 E10 Rads N/A Per Standards
>200 psig
>0.77 Listed Below*
gamma (1)
Following completion of test.
(2)
Visual Examination Standards Checking
- ASTM Method DB60 Cracking
- ASTM Method D661 Blistering
- ASTM Test Method D714 l
Flaking
- ASTM Test Method D772 Delamination
- No Guidance Necessary Peeling
- No Guidance Necessary Unusual Appearance
- No Guidance Necessary 3-39a
SAR - TranStor* Storage Cask Revision D Docket No. 72-1023 February 1999 TABLE 3.4-11 I
DESIGN PARAMETERS OF COATINGS (continued)
BASKET EXTERNAL COATING Coating Requirements Low Volatile Organic Compounds Resistance to Chemical Corrosion Impervious to Contamination Application Temperatures to 475 F
_ Qualification Standards Blistering ASTM D714-87 Flaking ASTM D772-93 Delamination ASTM D3911-95 Adhesion ASTM D5144-91 Radiation Tolerance ASTM D4082-95 Chemical Resistance ASTM D3912-95 Emissivity ASTM E408-71 Qualification Tests and Acceptance Standards Qualification Test Test Parameters sual xam Adhesion
- Emisshitf Gen ration Boric AcidImmersion:
4000 ppm boron Minimal Per Standards
>200 psig
>0.9
@ ambient temp.
120 hrs @ ambient Listed Belod2>
Heat Tolerance:
72 hrs @475"F N/A Per Standards
>200 psig
>0.9 in He atmosphere Listed Belod2>
Radiation Tolerance:
2.0 E9 Rads N/A Per Standards
>200 psig
>0.9 Listed Belod2) gamma
_ Hypothetical Fire:
4.5 hrs @530 F
< allowable Per Standards N/A N/A
-transport accident in He atmosphere cask Listed Belod2) pressure (1)
Following completion of test.
(2)
Visual Examination Standards Checkirg
- ASTM Method D660 Cracking
- ASTM Method D661 l
Blist'erlng
- ASTM Test Method D714 l
Flaking
- ASTM Test Method D772 Delamination
- No Guidance Necessary Peeling
- No Guidance Necessary Unusual Appearance
- No Guidance Necessary 3 39b
A SAR - TranStor* Storage Cask Revision D Docket No. 72-1023 February 1999
. Tables 4.1-1 through 4.13 summarize the results of the thermal calculations. The results are based upon a design basis heat load of 1.083 kW per PWR assembly and 0.426 kW per BWR assembly. The long-term component temperatures are reported for the full capacity baskets (26 kW) as well as for the reduced capacity configurations. The off-normal and 3
. accident data are presented for the full loading only, and the reduced capacity cask is always
. bounded. As can be seen from this ta e, t e conservat ve y ca cu ated temperatures are bl h
i l l l below the temperature specifications listed in Sections 2.0 and 4.2.
4.2 TECHNICAL SPECIFICATION OF COMPONENTS Temperature limits were established for all the materials used in the TranStor System.
l Specifically, these limits are for concrete, fuel cladding, steel, and coatings. The limits l
were established in accordance with the following codes and manufacturers l
recommendations:
Code or Standard Component 1
?
PNL-6364 and EPRI TR-106440 Fuel ASME Section III, Division 1 Steel ACI 349 and NUREG-1536 Concrete Manufacturer's Data Neutron shield and poison Qualification Test Coatings 4
i I
i The component allowable temperatures are shown in Tables 4.1-1 through 4.1-3.
l-Thermal parameters of coatings are shown in Table 3.4-11.
l I
{
SUMMARY
OF THERMAL PROPERTIES OF MATERIALS ii 4.3 l
The thermal properties used in the thennal hydraulic analyses are shown in Tables 4.3-1 through 4.3-8. The derived parameters (effective thermal conductivities) are discussed in 1
Section.4.4.
Lower bound values derived from the open literature, test data, and conservative calculations were used.
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4-6 b
.,__.________.~._._.___._-_.___.__._____.m_.._
-SAR - TranStor* Storage Ceak Revision D Docket No. 72-1023 February 1999 11.2.10 CASK DROP OR TIPOVER l
L 11.2.10.1 ~ CAUSE OF ACCIDENT There is no known credible event that would cause the TranStorm cask to tip over. The accident analyses (SAR sectionsl1.2.3,11.2.4,11.2.5, and 11.2.8) performed for the tornado wind and missiles, flood, earthquake, and explosions show that the margin of l-safety against overturning of the cask is greater than 1.1. Cask tipover is not credible l
because-l
'a):
the Technical Specifications presented in Chapter 12 restrict the cask lifl height to '
' no more than 18 inches, and '
b)E one side of the cask must be raised more than 5 feet higher than the other side to l
move the center of gravity over the corner and create the potential for tipover.
]
Despite the unlikelihood that the TranStorm cask would tip over, the following accident L
analysis addresses the consequences of the non-mechanistic cask tipover event.
j 11.2.10.2 ACCIDENT ANALYSIS l
L The accident analyses address the following parameters important to the cask overturning i
event:
i Dissipation of the energy from the cask overtuming through deformation of the i
- concrete cask, foundation pad and the sub' grade material.
l Structural integrity of the concrete cask.
e e Structural integrity of the basket, failed fuel cans and the fuel debns cans.
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11.2.10.2.1 Storage Cask :
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- During the hypothetical tipover accident, the concrete storage cask will impact the i
concrete foundation pad, which in tum is supported by the foundation subgrade material.
L The impact area will initially be along a narrow longitudinal strip of the cask surface.
I The concrete material in the cask and the foundation pad would both crack and crush thus l-
' dissipating a past of the impact energy.
L-A 2D model of the concrete cask was developed to assess the damage sustained by the L
concrete cask.' Plastic stress-strain relations were used to represent the concrete and l~
reinforcing steel materials. The model accounted for the stiffness of th'e foundation slab i
11-41
}
a
SAR - TronStor* Storage Cosk Revision D Docket No. 72-1023 February 1999 and the subgrade material. The methodology is based on Reference 11.8 and has been validated against full-scale cask drop tests impacting concrete slabs (Reference 11.9].
Three different cases were constructed to represent the variations in slab design t.nd subgrade conditions:
- 1. An 18" thick,3000 psi concrete slab on 24" engineered fill on top of bedrock with an equivalent subgrade modulus of 340 psi /in,
- 2. A 36" thick,3000 psi concrete slab on deep soil with a subgrade modulus of 480 psi /in, and
- 3. A 36" thick,4000 psi concrete slab on deep soil with a subgrade modulus of 288 psi /in.
j Static capacity calculations were performed to determine the deceleration forces experienced by the cask during impact. The static capacity method provides steady g-loads on the cask for a given drop height that was factored by a dynamic amplification factor. A multiplier for the gravity load in the cask is incrementally applied to allow concrete cracking and compressive yielding to develop with redistribution of the loads to the reinforcement and the subgrade support.
The results of the analyses, for all three site conditions considered, indicate that the cask tolerates the impact loads without significant distortion. The ovalizing deformations are not significant. Based on the static calculatiens, such deformations would be recoverable since the liner remains elastic. The cask sustains cracking and local crushing but has adequate reserve strength to allow the canister to be extracted after a hypothetical tipover accident.
Lawrence Livermore National Laboratory Report UCID-21246, " Dynamic Impact Effects on Spent Fuel Assemblies," evaluated the capability of fuel assemblies to withstand various drop orientations. The UCID-21246 evaluation concluded that typical fuel assemblies can withstand loading equivalent to 63g without exceeding the yield strength of the cladding. Therefore, the capability of the fuel assemblies bounds the postulated loads resulting from a hypothetical non-mechanistic cask tipover accident.
I1.2.10.2.2 Basket The TranStor baskets are designed by analysis to withstand the drop loads of 124g in the axial direction and 44g in the lateral direction. The hypothetical cask tipover accident analyses presented above resulted in basket loads (36g to 41g) that in alf cases were below the design value of 44g. The loads in the axial directions would result from a l
vertical drop of the cask. The thaximum cre'dible vertical drop is
- estimated to be 18 l
inches. The basket acceleration (33g) due to the 18-inch drop is bounded by the 124g l
design value.
11-42
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l SAR -TranStor Storage Cask Revision D Docket No. 72-1023 February 1999 11.2.10.2.3. Failed Fuel Cans As discussed in Section 3.4.4.4, the PWR Failed Fuel Can supports only its own weight and its stresses are insignificant.
As discussed in Section 3.4.4.4, the BWR Fuel Debris Can is structurally identical to the BWR fuel sleeve and, therefore, is bounded by the sleeve analysis.
L I11.2.10.2.4 Fuel Debris Cans The axial stress in the PWR Fuel Debris Can walls due to 124g acceleration is calculated t
to be 7.6 ksi and is pure compression. This stress is first evaluated against the ASME, I
Section'III, allowables for the Level D conditions. The controlling location is the single-
_ groove partial penetration weld at the bottom. After applying the quality factor of 0.4 for l
such weld with surface examination, the allowable stress is determined to be 12.6 ksi.
l.
Buckling of the PWR can shell is evaluated in accordance with NUREG/CR-6322. Both l-the tube and the plate buckling are evaluated. The respective allowable stresses are calculated to be 16.7 ksi for the tube and 143 ksi for the plate. Both of these stresses are above the' design compressive stress of 7.6 ksi.
As discussed in Section 3.4.4.5, the BWR Fuel Debris Can is structurally identical to the
~
BWR fuel sleeve and, therefore, is bounded by the sleeve analysis.
l.
11.2.10.2.5 Site Specific Analysis The cask tipover analyses described above were based on three typical site conditions.
The acceptability of a specific site would be established based on calculating the hardness j
of the foundation pad and the stiffness of the subgrade material. If the site-specific j
l l
hardness and stiffness values are within the range of values considered in the generic i
l analyses, the site would be deemed acceptable. Site-specific analysis would be l
L performed if the hardness and stifYness of the foundation and subgrade fall outside the l-range.
i 11.2.10.3 ACCIDENT DOSE CALCULATIONS l
i The cask'and basket are capable of withstanding the drop loads and there wou1d be no
~
radiological release or adverse radiological consequences due to the 18-inch vertical drop event. As discussed above, the cohcrete crushihg at the bottom would'stually decrease the dose rates at the air inlets.
t Il-43 V
L a
y
- SAR-TranStor* Storag Cask-Revision D Docket No. 72-1023 -
Febmary 1999 l
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s
11.3 REFERENCES
i j-11.1 D.R Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, TID-l l
' 26711-PI, Dept. Of Energy, Washington, D.C.,1976.
11.2 E. Elias, C. B.' Johnson, " Radiological Impact of Clad and Containment Failures i
in At-Reactor Spent Fuel Storage Facilities," Electric Power Research Institute,.
j Palo Alto, CA,1982.-
11.3 EPRI NP-440, " Full Scale Tornado Missile Impact Tests",1977.
11.4 EPRI NP-1217, " Local Response of Reinforced Concrete to Missile Impact",
1974.
1 11.5 ~ BC-TOP-9A, Revision 2, " Design of Structures for Missile Impact," Bechtel
- Power Corporation.
i 11.6' - Sabersky. et.al., Fluid Flow.-
11.7 BC-TOP-4A Revision 4, Seismic Analysis of Structures and Equipment, Bechtel Power Cogoration,1979.
)
1 11.8 EPRI NP-7751, " Structural Design of Concrete Storage Pads of Spent Fuel j
Casks",1991.
11.9. ' Y. R. Rashid, et al.,." Validation of EPRI Methodology for Analysis of Cask Drop l
and Tipover Accidents at Spent-Fuel Storage Facilities", Proceedings ofICONE-l 5, Fifth Intemational Conference on Nuclear Engineering, Nice, France, May 26-l 30,1997.'
l l
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l-i 1
1 l
11-45
~,
E?
ENCLOSURE 3 MATERIAL TESTING A) ANAMET Test Report, Laboratory Number 5003.001, Rev.1 B)' ANAMET Test Report, Laboratory Number 5003.364
~ C) ANAMET Test Report, Number 5003.364A 1
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j LABCRATORY CERTIFICATE i
/
ANAMET 8400 INVESTWENT SOULEVARD e NAYWARD. CAllFORNIA 94545 3811 = (5 0)887 8811 4
j January 26,1999 i
I LABORATORY NUMBER:
5003.001, Rev.1 i
i CUSTOMER AUTHORIZATION:
PO# 98-045 j
DATE SUBMITTED:
October 15,1998 f
REPORT TO:
Sierra Nuclear Corporation l
Atta: Boris Chechelnitsky 1 Victor Square i
Scotts Valley, CA 95%6 1
I l
SUBJECT:
i One rectangular tube section was submitted for mechanical testing. The sample was identified as Material: ASTM A 500, Gr. C,7" x 7" x 1/4", Canada.
TENSILE TEST (ASTM A 370-97a) 1 2
H Temperature
+70*F
+ 100"F
+ 100'F Dimensions of Specimen (in.)
{
Width l
Thickness l
Area (sq. in.)
l Tensile Strength (psi) j Yield Strength @ 0.2% offset (psi) l Elongation in 2.0" Gage (%)
i j
1 B
D Temperature
+300*F
+300'F
+500*F Dimensions of Specimen (In.)
Width Thkie=s Area (sq. in.)
4 Tensile Strength (psi) j Yield Strength @ 0.2% offset (psi) i Elongation in 2.0" Gage (%)
i i
i This report shall not be reproduced. except In fu!I, without the written apprwal of Fil Anamet I
, -. ___, 7;_ -
_7---
FTI ANAMET j
Lab. No 5003.001, Rev.1 I
HAYWARD. eALIFORNtA TENSILE TEST (ASTM A 370-97a) 4 1
8 j
j Temperature
+500*F
+600'F
+ 600*F i
Dimensions of Spechnen (in.)
j Width i
Thickness Area (sq. in.)
Tensile Strength (psi)
I j
Yield Strength @ 0.2% offset (psi) m Elongation in 2.0" Gage (%)
6 2
E i
l Temperature
+700'F
+700*F
+ 800'F Dimensions of Specimen (in.)
Width Thieles Area (sq. in.)
Tensile Strength (psi) m Yield Strength @ 0.2% offset (psi) l Elongation in 2.0" Gage (%)
l 2
i i
i Temperature
+ 800'F 1
l Dhnensions of Specimen (in.)
Width Thickness Area (sq. in.)
l.
Tensile Strength (psi)
Yield Strength @ 0.2% offset (psi) j Elongation in 2.0" Gage (%)
1 i
1 2
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/// ANAMET V
Lab. No. 5003.001, Rev.1 NAYWARD. CALIFOMNIA i
This testing was performed in accordance with the customer's authorization (10CFR21 applies).
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Submitted by:
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v Edward A. Foreman mic Quality Manager 1
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LABORATORY CERTIFICATE
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ANAMET FTI 3400 INVESTMENT BOULEVARO + HAYWARD. CALIFORNIA 94545 3819 * (510) 887 8811 j
i i
I February 1,1999 LABORATORY NUMBER:
5003.364 i
CUSTOMER AUTHORIZATION:
PO# 98-045, Rev.1 DATE SUBMITTED:
January 14,1999 REPORT TO:
Sierra Nuclear Corporation Attn: George N. Dixon l
1 Victor Square Scotts Valley, CA 95066 l
SUBJECT:
l One lot of coupons was submitted for tensile testing. The samples were identified as Material:
t l
1/8" Sheet, Ht# 402S5412 per ASTM A 570, Gr. 45.
i TENSILE TEST (ASTM A 370-97a) 3 i
1 2
4R l
Temperature 60*F 60*F 60 F 1
i Dimensions of Specimen (in.)
sq. in.)
j Tensile Strength (psi)
Yield Strength @ 0.2% offset (psi) l Elongation in 2.0" Gage (%)
i l
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l This report shall not be reproduced, enept in full, without the written approval of Ffl Anamet i
FT1 ANAMET Lab. No. 5003.364 HAYWARD. CAllFORNI A TENSILE TEST (ASTM A 370-97a) a 4
5 Temperature 100 F 100 F 100 F Dimensions of Specimen (in.)
Width Thickness Area (sq. in.)
Tensile Strength (psi)
Yield Strength @ 0.2% offset (psi)
Elongation in 2.0" Gage (%)
i fi 2
S Temperature 300'F 300 F 300"F Dimensions of Specimen (in.)
Width Thickness Area (sq. in.)
Tensile Strength (psi)
Yield Strength @ 0.2% offset (psi)
Elongation in 2.0" Gage (%)
6 2
2 10
.11
.12 Temperature 500*F 500 F 500 F
'500 F Dimensions of Specimen (in.)
Width Thickness Area (sq. in.)
Tensile Strength (psi)
Yield Strength @ 0.2% offset (psi)
Elongation in 2.0" Gage (%)
2
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ANAMET Lab. No. 5T3.364 4,
H AYWARD, C ALIFORNIA s
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TENSILE TEST (ASTM A 370-97a)
D M
E i
j
-Temperature 600 F 600 F 600 F l
Dimensions of Specimen (in.)
ickness Area (sq. in.)
l Tensile Strength (psi)
Yield Strength @ 0.2% offset (psi) m Elongation in 2.0" Gage (%)
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)
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E E
i Temperature 700'F 700'F 700*F Dimensions of Specimen (in.)
Wid*h 6
Thickness Area (sq. in.)
Tensile Strength (psi)
Yield Strength @ 0.2% offset { psi)
Elongation in 2.0" Gage (%)
3
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ANAMET Lab. No. 5003.364 H AYWARD. C ALIFORNI A i
I i
7 TENSILE TEST j
(ASTM A 370-97a) 18 19 20 i
Temperature 800 F 800 F 800 F i
j Dimensions of Specimen (in.)
Width l
Thickness 1
l Area (sq. in.)
l Tensile Strength (psi) l Yield Strength @ 0.2% offset (psi)
{
Elongation in 2.0" Gage (%)
I l
This testing was performed in accordance with the customer's authorization (10CFR21 applies),
i i
Submitted by:
i bAmdC,h Edward A. Foreman mic Quality Manager 4
.