ML19290C138
| ML19290C138 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/16/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8001100120 | |
| Download: ML19290C138 (1) | |
Text
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Novenber 16, 1979 Docket Nos.
50-313 50-368 Arkansas Power.and Light Conpany ATTN:
Mr. William Cavanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 Gentle =en:
The enclosed IE Information Notice No. 79-28 provides information on the overloading of' structural elements due to pipe support loads.
Sincerely, c
SL-Karl V.
frit Director
Enclosures:
1.
IE Information Notice No. 79-28 2.
Listing of Recently Issued IE Information Notices James P. O'Hanlon, Plant Manager cc:
Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 1727 006 8001100 \\ 1 0
SSINS No.:
6870 Accession No.: 7910250476--
Y UNITED STATES 9
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NUCLEAR REGULATORY COMMISSION
^E OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 16, 1979 IE Information Notice No. 79-28 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 adequote 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 a 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 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.
1727 007
IE Information Notice No. 79-28 November 16, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Date Issued To Notice No.
Issued 79-20 NRC Enforcement Policy 8/14/79 All Holders of Reactor NRC Licensed Individuals Operating Licenses (OLs) and Construction Permits (cps), Research Reactors, Test Reactors Licensees with Licensed Operators 79-21 Transportation and 9/7/79 All power and research Commerical Burial reactors with Operating of Radioactive Material License (OL) 79-22 Qualification of Control 9/14/79 All power reactor Systems facilities with an Operating Licenses (OL) and Construction Permits (CP) 79-23 Emergency Diesel Generator 9/26/79 All power reactor Lube Oil Coolers facilities with an Operating License (OL) or Construction Permit (CP) 79-24 Overpressurization of 9/28/79 All power reactor Containment of a PWR Plant facilities with a After a Main Stream Line Construction Permit (CP)
Break 79-25 Reactor Trips at Turkey 10/1/79 All power reactor Point Unit 3 and 4 facilities with an Operating License (OL) or a Construction Permit (CP) 79-26 Breach of Containment 11/5/79 All power reactor Integrity holding Operating License (OL) and Construction Permits
~
(CFs)79-12A Attempted Damage to New 11/19/79 All Fuel Facilities, Fuel Assemblies research reactors, and power reactors with an Operating License (OL) or Construction Permit (CP)
Enclosure f