ML19305E121
| ML19305E121 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 04/04/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Weigand J GULF STATES UTILITIES CO. |
| References | |
| NUDOCS 8004220770 | |
| Download: ML19305E121 (1) | |
Text
UNITED STATES pn r 49 NUCLEAR REGULATORY COMMISSION NSIC 3"
7, REGION IV CENTRAL FILES E
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611 RYAN PLAZA oRIVE. SUITE 1000
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j ARLINGTON, TEXAS 76012 O
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April 4, 1980
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In Reply Refer To:
RIV Docket Nos. 50-458/IE Bulletin No.79-03A 50-459/IE Bulletin No.79-03A i
'(
I Gulf States Utilities Attu:
Dr. J. G. Weigand, Vice President Operations and Technical Systems
[
Post Office Box 2951 i
Beaumont, Texas 77704 l
Gentlemen:
[
Enclosed is IE Bulletin No.79-03A, which requires action by you with regard to your power reactor facilities with an operating license or a construction permit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
l Sincerely, f
I
/
W K. V. Seyfrit
[
l Director v
l
Enclosures:
1.
List of IE Bulletins Recently Issued I
b 8004220 l.
i SSINS No. 6820 Accession No.:
UNITED STATES 8002280644 NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION ND ENFORCEMENT WASHINGTON, D. C.
20555 IE Bulletin No.79-03A April 4, 1980 Page 1 of 3 LONGITUDINAL WELD DEFECTS IN ASME SA-312, TYPE 304 STAINLESS STEEL PIPE Description of Circumstances:
IE Bulletin No. 79-03 required the licensee to determine if ASME SA-312, Type 304 pipe manufactured by Youngstown Welding and Engineering Company is in use or planned for use in safety-related systems.
Since the issuance of IE Bulletin 79-03 on March 12, 1979, subsequent findings indicate additional information and clarification is needed to resolve the SA-312 issue.
t It has been determined that conventional ultrasonic testing (UT) and radio-graphic testing (RT) techniques (as required by ASME Section III) are not adequate to detect centerline lack of weld penetration (CLP).
Conventional radiography and UT examinations may detect the presence of CLP under special i
conditions, but neither can be considered reliable enough to detect CLP even when significant percentages exist.
Based upon the above and previous findings during inspections at Youngstown it has been determined that the Youngstown Welding and Engineering Company did comply with the ASME Code requirements, but that the Code NDE require-ments are deficient.
Consequently any manufacturers' SA-312, Type 300 Series,
.tstenitic stainless steel fusion welds may contain undetected CLP. This
- roblem is generic to all welded SA-312/A-312 material and is not restricted to material manufactured by the Youngstown Welding and Engineering Company.
l The NRC has verified that the CLP condition also exists in the SA-312 and/or A-312 fusion welded pipe manufactured by ARMCO's Advanced Materials Division, j
the SWEPCO Tuba Corporation and Crucible's Trent Tube Division. These com-panies are known to have supplied SA-312 and/or A-312 material for nuclear l
applications and are now included within the scope of this Bulletin.
Several licensee's responses to the IE Bulletin 79-03 were inadequate. The responses were inadequate because they were based on the purchase order NDE requirements rather than the information requested in the Bulletin. An actual example of an inadequate response was as follows:
Radiography of a circum-ferential weld seam revealed CLP in the longitudinal seam of a section of t
SWEPCO fusion welded pipe.
The licensee did not believe the case was reportable if the orginal NDE requirements for the SWEPC0 pipe did not require volumetric examination.
This CLP problem is considered by the NRC to be a significant deficiency which requires extensive evaluation and could result in repair or replacement of l
l pipe and/or fittings.
April 4, 1980 IE Bulletin No.79-03A Page 2 of 3 The information requested in this revised Bulletin is to be provided without regard to the purchase order NDE requirements or any subsequent NDE perfo The information requests in this Bulletin supersede fcr or by the licensee.
the requests for information in the IE Bulletin 79-03.
The NRC staff position on this issue and any other case where defects or deficiencies are discovered in safety-related components is as follows:
Regardless of the circumstances under which potential deficiencies or potent defects in safety-related components are discovered th d requirements the appropriate Federal Regulations. Although the ASME Code rules an ify may be used when appropriate to evaluate defects or deficiencies and to just be used and accept the existence of a defect or deficiency, the Code can not as justification for not reporting the defect, deficiency and circumstances to the NRC when that defect or deficiency has been identified by the NRC as a When the licensee, his agent or vendor discovers a potential generic problem.
defect or deficiency that may be a generic problem, or a si the situation to the NRC.
For those power reactor facilities that have the subject pipe installed, the action identified in this Bulletin is limited to identifying the specific applications and providing information related to the structural integrity of Additional guidance related to NDEs and/or precau-f tionary or corrective actions will be provided in a later Bulletin revision i the piping components.
necessary.
Revised action to be taken by Licensees and Permit Holders:
For all power reactor facilities with an operating license or a construction permit:
Determine whether SA-312 or A-312, Type 300 Series fusion welded pipe is in use or planned for use in safety-related systems subject to design 1.
For the stresses greater than 85 percent of the Code allowable stresses.
purpose of this check the actual wall thickness of the pip of the piping products are satisfied using 85 percent of the maximum allowable stress at the design temperature.
For those piping components using greater than 85 percent of the allowable stresses, identify the application of the piping including the 2.
system, pipe location, pipe size, pipe configuration (elbow, tee), design pressure / temperature requirements and the manufacturer.
For those facilities under construction and where access permits, the ends of all safety-related SA-312 and A-312 fusion welds should be etched 3.
Identify the manufacturer and the degree of to determine if CLP exists.
CLP as a percentage of the pipe wall thickness.
IE Bulletin No.79-03A April 4, 1980 Page 3 of 3 4.
For facilities with an operating license, a report of the above information shall be submitted within 120 days of receipt of this Bulletin.
5.
For facilities with a construction permit, a report of the above information shall be submitted within 120 days of receipt of this Bulletin.
Reports should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the NRC Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, D.C., 23555.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
c.
IE Bulletin No.79-03A April 4, 1980 i
RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
5 80-02 Inadequate Quality 1/21/80 All BWR licenses with Assurance for Nuclear a Construction Permit Supplied Equipment (CP) or Operating License (OL) 80-03 Loss of Charcoal From 2/6/80 All holders of Power Standard Type II, 2 Inch, Reactor Operating Tray Adsorber Cells Licenses (OLs) and Construction Permits (cps) 80-04 Analysis of a PWR Main 2/8/80 All PWR reactor facilities Steam Line Break With holding Operating Licenses Continued Feedwater (OLs) and to those nearing Addition Licensing 79-01B Environmental Qualification 2/29/80 All power reactor of Class IE Equipment facilities with an Operating License (OL) 80-05 Vacuum Condition Resulting 3/10/80 All PWR power reactor In Damage To Chemical facilities holding Volume Control System Operating Licenses (OLs)
(CVCS) Holdup Tanks and to those with a Construction Permit (CP) 80-06 Engineered Safety Feature 3/13/80 All power reactor facilities (ESF) Reset Controls with an Operating License (OL) i Enclosure.
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