ML19323G754
| ML19323G754 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/08/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8006060599 | |
| Download: ML19323G754 (1) | |
Text
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CENTRAL FILES UNITED STATES POR:HQ
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NUCLEAR REGULATORY COMMISSION LPOR
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y REGION IV MC 3
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611 RYAN PLAZA oRIVE,SulTE 1000 NS{g "o.,,
Sj ARUNGTON, TEXAS 78012
%,'V# o May 8, 1980
- --STATE - -
Docket Nos.
50-313 50-368 Arkansas Power and Light Company ATTN:
Mr. William Cavanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
Enclosed is IE. Bulletin No. 80-11 which requires action.by you.
A written response is required.
Should you.have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, pM-I Karl V. Seyfri Director
Enclosures:
1.
List of Recently Issued IE Bulletins cc:
James P. O'Hanlon, Plant Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 8006060 %
SSINS No.:
6820 Accession No.:
UNITED STATES 7912190695 NUCLEAR REGULATORY COMMISSION c
0FFICE OF INSPECTION AND ENFORCEMENT i
l WASHINGTON, D.C.
20555 g,)
IE Bulletin No. 80-11 Date: May 8, 1980 Page 1 of 4 i
MASONRY WALL DESIGN Description of Circumstances:
In the course of conducting inspections pursuant to IE Bulletin Nos. 79-02 and 1
79-14 at the Trojan Nuclear Plant, Portland General Electric Co. (PGE) identi-fied 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 Nuclear 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 operating facilities, we have concerns with regard to the adequacy of design criteria used for the design of masonry walls and an apparentlackofdesigncoordinationyyg'~@f,57 gid@MMM M'
design groups.
IE Bulletin 79-02, Revision 2 issued DUPLICATE DOCUMENT pipe supports attached to masonry wal pipe supports in this category, the e Entire document previously bolting through the wall or the suppe entered into systern under:
Supports that are bolted through maso
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review for this Bulletin.
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No. of pages:
Ade I
1
I l
i SSINS No.:
6870 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION 7910250475 0FFICE OF INSPECTION AND ENFORCEMENT c
WASHINGTON, D.C.
20555 g y-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 requested in response to this Information Notice.
If NRC evaluations se 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.
i i
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, - - ~ ~ ~.
IE Bulletin No. 80-11 May 8, 1980 l
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 Operating License Stainless Steel Pipe (OL) or Construction Permit (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 Velds Construction Permit and/or Operating License (0L) 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits (cps) 30-10 Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Potential for Operating License (0L)
Unmonitored, Uncontrolled or Construction Permit Release to Environment (CP)
Enclosure i