ML19323D181
| ML19323D181 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/08/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 8005210218 | |
| Download: ML19323D181 (1) | |
Text
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REGloN IV CENTRAL FILES I I #'
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611 RYAN PLAZA DRIVE, SUITE 1000
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May 8, 1980 In Reply Refer To:
RIV Docket No.
50-382/IE Bulletin No. 80-11 Louisiana Power and Light Co.
ATTN: Mr. D. L. Aswell Vice President of Power Production 142 Delaronde Street New Orleans, Louisiana 70174 Gff'tlemen:
Enclosed is IE Bulletin No. 80-11 which is forwarded to you for information.
No written response is required.
Should you have any questions regarding this matter, please contact this office.
Sincerely,
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Karl V. Seyfrit Director
Enclosures:
1.
List of Recently Issued IE Bulletins e
c 8005210Gj%
ENCLOSURE 1 SSINS No.:
6820 Accession No.:
UNITED STATES 7912190695 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555
_ IE Bulletin No. 80-11 Date:
May 8, 1980 Page 1 of 4 MASONRY WALL DESIGN Description of Circumstances:
In the course of conducting inspections pursuant to IE Bulletin Nos. 79-02 and 79-14 at the Trojan Nuclear Plant, Portland General Electric Co. (PGE) identi-fled a problem with the structural integrity of concrete masonry walls with Seismic Category I piping attached to them.
This problem was briefly addressed in IE Information Notice No. 79-28, which was sent to all Construction Permit and Operating License holders on November 16, 1979 (Attachment 1).
The problem was that some walls were found which did not have adequate structural strength to sustain the required piping system support reactions.
These structural deficiencies were at that time reported to be attributable to two deficiencies:
1)
Apparent lack of a final check of certain pipe support locations and reactions to ensure that the supporting elements possessed adequate structural integrity to sustain the required loads.
2)
Non-conservative design criteria for the reactions from supports anchored into the face of concrete masonry walls; e.g., relying on the combined strength of double block walls without substantial positive connection between the two walls by means other than the bond provided by a layer of mortar, grout or concrete between them.
Continued investigations into the deficiencies identified at the Trojan Naclear Plant, engineered by Bechtel, confirmed the deficiencies to be attributable to error in engineering judgment, lack of procedures and procedural detail, and inadequate design criteria (details are in Trojan Nuclear Plant's LER No.
79-15, and supplements).
Because of this and the generic implications of similar deficiencies with other cperating facilities, we have concerns with regard to the adequacy of design criteria used for the design of masonry walls and an apparent lack of design coordination between the structural and piping /
equipment design groups.
IE Bulletin 79-02, Revision 2 issu pipe supports attached to masonry DUPLICATE DOCUMENT most pipe supports in this catego by bolting through the wall or the Entire document previously Supports that are bolted through a entered.into systen under:
the review for this Bulletin.
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No. of pages:
[
n SSINS No.:
6870 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION 7910250475 0FFICE OF INSPECTION AND ENFORCEMENT 4
WASHINGTON, D.C.
20555 IE Information Notice No. 79-28 Date:
November 16, 1979 Page 1 of 1 OVERLOADING OF STRUCTURAL ELEMENTS DUE TO PIPE SUPPORT LOADS Description of Circumstances:
Recently, the NRC was informed that, in the course of the inspections pursuant to IE Bulletin No. 79-02 and 79-14 by the Portland General Electric Co.
(PGE) at the Trojan Nuclear Plant, some walls were found which did not have adequate structural strength to sustain the required support reactions.
Bechtel Corporation was the Architect Engineer for the plant.
These structural inadequacies were reported to be attributable to two deficiencies:
1)
Apparent lack of a final check of certain pipe support locations and reactions to ensure that the supporting structural elements possessed adequate structural integrity to sustain the required loads.
2)
Inadequate design criteria for the reactions from supports anchored into the face of concrete block walls; e.g., relying on the combined strength of double concrete block walls without positive connection between the two walls by means other than the bond provided by layer of grout between them.
The NRC is currently pursuing these issues in detail for the Trojan Nuclear Plant to determine the extent of these deficiencies and the generic implications for other Bechtel facilities.
This Information Notice is provided as an early notification of a possible signif-icant matter.
It is expected that recipients will review the information for possible applicability to their facilities and the actions being performed under IE Bulletin No. 79-02.
Specific action is being requested relating to the adequacy of attachments to concrete block walls under IE Bulletin No. 79-02, Revision 2, item 5.c.
No specific actions are Tequested in response to this Information Notice.
If NRC evaluations so indicate, further licensee actions may be requested or required.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
No written response to this IE Information Notice is required.
IE Bulletin No. 80-11 May 8, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-06 Engineered Safety Feature 3/13/80 All power reactor facilities (ESF) Reset Controls with an Operating License (OL)79-03A Longitudinal Weld Defects 4/4/80 All power reactor facilities In ASME SA-312 Type 304 with an Opersting License Stainless Steel Pipe (OL) or Construction Permit 1
(CP) 80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and BWR-4 Failure facilities with an Operating License (OL) 80-08 Examination of Containment 4/7/80 All power reactors with a Liner Penetration Welds Construction Permit and/or Operating License (OL) 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits (cps) so-10 Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Potential for Operating License (OL)
Unmonitored, Uncontrolled or Construction Permit Release to Environment (CP)
Enclosure