ML19262A672
| ML19262A672 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 11/16/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7912100218 | |
| Download: ML19262A672 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION
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Docket No. 50-358 006 1'
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Cincinnati Gas and Electric Company ATTN:
Mr. Earl A. Borgmann Senior Vice President Engineering Services and Electric Productic n 139 East 4th Street Cincinnati, OH 45201 Gentlemen:
The enclosed IE Information Notice No. 79-28 provides information on the overloading of structural elemente due to pipe support loads.
Sincerely,
[0 4s
. James G. Keppler Director
Enclosure:
IE Information Notice No. 79-28 cc w/ encl:
Mr. J. R. Schott, Plant Superint udent Central Files Director, hRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission Citizens Against a Radioactive Environment Helen W. Evans, State of Ohio 1527 150 791c100 h[
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SSINS No.:
6870 E
Accession No.: 79102504I5 UNITED STATES NUCLEAR RFGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 16, 1979 IE Information Notice No. 79-28 OVERLOADING 0F 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 ar.d 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 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 beiag requested relating to the adequacy
,( 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 licenste 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.
Enclosure:
Receatly Issued IE Information Notices 1527 151
IE Information Notice No. 79-28 Enclosure Novezber 16, 1979 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 79-27 Steam Generator Tube 11/16/79 All power reactor facilities Ruptures At Two PWR holding OLs and cps Facilities79-12A Attempted Damage To New 11/9/79 All Fuel Facilities, Fuel Assemblies research reactors, and power reactors with an OL or CP 79-26 Breach of Containment 11/5/79 All power reactor facilities Integrity holding OLs and cps 79-25 Reactor Trips At Turkey 10/1/79 All power facilities with Point Units 3 And 4 an OL or a CP 79-24 Overpressurization Of 10/1/79 All power reactor facilities Containment Of A PWR Plant with a CP After A Main Steam Line Break 79-23 Emergency Diesel Generator 9/26/79 All power reactor Lube Oil Coolers facilities holding OLs and cps 79-22 Qualification of Control 9/14/79 All power reactor Systems facilities with operating licenses and construction permits.
79-21 Transportation and Commercial 9/7/79 All power and research Burial of Radioactive Material reactors with OL's 79-20 NRC Enforcement Policy 9/7/79 All Holders of Reactor (Rev. 1)
NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-20 NRC Enforcement Policy 8/14/79 All Holders of Reactor NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 1527 152