ML19338D110
| ML19338D110 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/12/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009190476 | |
| Download: ML19338D110 (4) | |
Text
r-TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II September 12, 1980 Director of Nuclear Reactor Regulation Attention:
.t. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Cosgission Wasnin6 ton, DC 20555
Dear Mr. Schwencer:
In the Matter of the Application of
)
Docket No. 50-327 i
Tennessee Valley Authority
)
50-328 Enclosed is the material you requested concernin6 the material test reporte for the critical section of the containment steel in the Sequoyah Nuclent Plant. is a table of plate yield strengths for the unit 1 and unit 2 co.:tainment stecl.
- is a statement defining the critical section of steel for each l
containn:ent. Enclosure 3 summarizes the nr.terial analyses for the critical section.
The mill test reports on the critical section will be provided under separr.h cover on or before September 15, 1980.
l Very truly yours TENNESSEE VALLEY AUTHORITY
-k L. H. Mills, Manager Nuclear Regulation and Safety Sworntoanosubscribe(berorer.e g
this M day of L unwie 1980
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Enclosures 8009194 i
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An Equal Opportunity Employer
n ENCLOSURE 1 SEQUOYAH CONTAINMENT VESSELS UNITS 1 AND 2 PLATE YIELD STRENGTH ***
Plate No.
Standard Thickness Tests Mean Y.S.
Deviation R-s 2 - 2s I - 3s Minimum Y.S.
(inches)
(R)
(s)
~
1/2 11 ~
47.3 1.27 46.1 44.8 43.5 45.7 1/2 119 47.2' l.92 45.3 43.4 41.5 40.6 7/16 48.3 1.40 46.9 45.5 44.1 45.9 9/16 5
48.2 1.28 46.9 45.6 44.4 46.7 5/8 47 49.2 1.61 47.6 46.0 44.4 45.9 11/16 12 47.8 1 35 46.5 45.1 43.8 46.1
_a 3/4 17 46.4 2.13 44.3 42.2 40.0 41.6 15/16 1
48.9 48.9 1
53 46.6 2.41 44.2 41.7.
39.3 40 9 1.1/16 15 47.0 3.59 43.4 39.8 36.2 39.3 1 1/8 8
47.1 3.44 43.7 40.2 36.8 40.9 1 -- 1/4 -
83 45.5 2.'26 43 3 41.0 38.8 38.1 1 3/8 19 43.7 2.82 40.9.
38.1 35.3 38.9-1 1/2 85 46.1 2.63 43.5 40.8 33.2 37.5
. Data for cylindrical containment shell plates only.
Data includes tests on material-used for shell plates, stiffeners,
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. pad plates, and dome plates.
All strength values in KSI,
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ENCLOSURE 2 As part of TVA's review to determine the maximum pressure cap eity of the Sequoyah steel containment shell an examination was made of all areas of the containment boundary, including the shell plate, equipment hatch, personnel locks, penetrations, vacuum relief valves, and anchorage to determine the section (critical area) that could limit the shell's capacity to withstand internal pressures above the present 12 PSIG design limit without significant yieldinS and/or leakage. This examination revealed that the 1/2" cylindrical shell plate between elevations 782 and 791.5 was the critical area of the containment boundary.
TABLE 1 SEQUOYAH l'UCLEAR PLANT (UNIT 1)
TEST DATA FOR 1/2" CYLINDRICAL SHELL PLATE BETWEEN ELEVATIONS 782 AND 791.5 Tensil Test No. of Plates Yield Strength Tensil Strength % Elongation 1
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ENCLOSURE 3 L
The shell plates for' the Sequoyah containment vessel meet the requirements
.of ASME specification SA-516, Grade 60. This specification requires a minimum yield strength of 32 KSI. Tensile' testing. requirements for this specification are-orovided by ASME specification SA-20.
Paragraph 11 of SA-20 specifies that one tension ' test shall be taken from a corner of each as rolled plate.
e The corner is the position of. minimum yield strength resulting from chemical segregation-in the plate steel. Therefore,' this test represents the minimum yield strength of the as rolled plate. As many as.four shell plates were cut from each as rolled plate. Table 1 provides the tensile test results for the 1/2" cylindrical shell plate-for unit 1.
The results for unit 2 are similar with a minimum yield' strength of 45.7 KSI.
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