ML20010A232
| ML20010A232 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/30/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8108110205 | |
| Download: ML20010A232 (4) | |
Text
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Duxe PowrifCihiks.4y:
mn POWEM UtIn. DING.
422 Socin Cutf acn STREET, CRAHISTTE. N. C asa4a.
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S WILLIAM O. PAR M ER, J R.
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STram PacDuction 373-4083 July 30, 1981 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413, -414
Dear Mr. O'Reilly:
Pursuant to 10 CFR 50.55e, please find attached Significant Deficiency Report SD 413-414/81-14.
V y truly yours, wA d, h William O. Parker, Jr.
RWO/php Attachment cc: Director NRC Resident Inspector Office of Inspection and Enforcement Catawba Nuclear Station U. S. Nuclear Regulatory Commission Washington, D. C. 20555 gh! ' 8 /,g c hh #
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REPORT NUMBER:
SD 413-414/81-14 REPORT DATE:
July 30,1981 s,
FACILITY: Catawba Nuclear Station - Units 1 & 2 IDENTIFICATION OF DEFICIEfCY t
During Code PT of some 1" socket welds, linear indicati6r.1 were detected in the base metal. Further investigation disclosed both linear and transverse indications which in some cases encroached on material spec-ification minimum wall thickness. These are covered on Duke P6wer Non-conforming Item Reports 10,311; 10,479; 10,637; 10,638; and 10,799.
INITIAL REPORT On June 30, 1981, Mr. J. Bryant of NRC Region II Atlanta, Georgia, was notified of the def'ciancy by Messers W. O. Henry and J. M. Curtis of Duke Power Company, Charlotte, North Car 611na 28242. This notification was a result of Potentially Reportable Item CA-81-26.
SUPPLIER AND/0R LGHPONENT The material in question is 1" Schedule 40 welded stainless steel pipe to ASME SA-312 TP304, Heat Number 490269. Pipe was manufactured by ARMC0 Incorporated and supplied to Duke Powt* by Guyon Alloys Inco.,v. ated of Charlotte, North Carolina.
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DESCRIPTION OF DEFICIENCY t %
Investigation of these indications disclosed two distinct types. These are as follows:
1.
Longitudinal - These are straight tight indications running intermittently 'oen the length of the pipe. The indication occurs from 1/16" to 1/4" away from the weld.and varies in sx appearance from a lap to a step (offset in surface). These 1
are visually detectable.
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2.
Transverse-Thesearesharp"W"shapedindicationstranve5Se g
to the centerline of the pipe and starting about 20 to 30 awcy from the weld. These are visually detectable.
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y REPORT NUMBQ:j SD 413-414/81-14 REPORT DATE:
July 30,1981 These indications were not dett ted by the arf 1C0 Eddy current test during manufacture. Samples.of these have been examined by art 100 and they attribute them to the following causes:
1.
Longitudinal - These probably resulted from scoring caused by a forming roll insert which was subsequently peened over during the weld bead finishing operation.
'2.
Trans' verse - Based on the regularity of these defects, they are concluded to be the result of a mill mark'or crack which was subsequently rolled over.
The depth of these indications was investigated by Duke Power and ARMC0 and the deepest were found to be:
Longitudinal =.0063" Transverse
=.0087" Both of the above represent'some encroachment on the material specification 2
-minimumwallthicknessof.116".
ANALYSIS'0F SAFETY IMPLICATIONS
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A check was made and none of this heat of pipe was found at Oconee, McGuire, or Cherokee.
A review of our records at Catawba indicate that we received approximately-2700' of this heat of pipe. Of this, approximately 1760' have not been installed.
According to our records, this pipe has been installed in Safety Related Systems with design conditions as listed below:
DESIGN NUMBER a SYSTEM CONDITIONS
'0F WELDS WL Liquid Wasta-35 psia b 200 F 14 WL - Liquid Waste:
65 psia @ 200 F 2
WL - Liquid Waste
.165 psia 0 200 F 52 WG Liquid Waste 165 psia 0 200 F 52 NB - Bt; rated. Water 165 psia 0 200 F 52 s
NB - Borated Water.
165 psia 0 250 F 4
F0 f Diesel Gen. Fuel Oil 210 psia 0 100 F 2
NV - Nuclear Volume Control 31E psia 0 250 F 2
0 NV - Nuclear Volume Control 615 psia 0 400 F 4
NI'- Safety Injection 715,.;ia 0 300 F 2
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REPORT NUMBER: SD 413-414/81-14 REPORT DATE:
July 30, 1981 Based on the number of welds involved, we estimate that approximately 800' of this pipe has been installed in the above systems.
All of this pipe passed a mill hydrotest of 2500 psig.
Based on the deepest defect found, this pipe would be good for at least 2300 psig based on Code requirements for pressure and temperature alone.
This it stainless steel pipe which from experience would inherently leak before breaking.
Based on the above, it is our judgement that any of the pipa used at Design o
Conditions of less than 315 psia at 250 F is acceptable for the intended service.
Due to the sharpness of these indications and their potential as stress raisers, we will further evaluate the suitability of this pipe for higher pressure and temperature service on a case by case basis.
CORRECTIVE ACTION All of the uninstalled pipe will be re-examined by ARMC0 and any found to have rejectable indications will be replaced.
A visual inspection will be made of the installed pipe in psteas having design conditions equal to or greater than 315 psia at 250 F.
Any visual indications found will be PT'd and if found rejectable, the pipe will be replaced.
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