ML19260B396
| ML19260B396 | |
| Person / Time | |
|---|---|
| Site: | 05000363 |
| Issue date: | 11/16/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 7912100122 | |
| Download: ML19260B396 (1) | |
Text
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7A acc,,h es UNITED STATES g
y '; ) e c - (,g NUCLEAR REGULATORY COMMISSION REGION 1 O..., 4 './ j f 631 PARK AVENUE S *+ '
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Docket No. 50-363 M 16lm Jersey Central Power & Light Company ATTN:
Mr. I. R. Finfrock, Jr.
Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Gentlemen:
The enclosed IE Information Notice No. 79-28 provides information on the over-loading of structural elements due to pipe support loads.
If you have any questions regarding this matter, please contact this office.
Sincerely, 0
- t!) //i
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_ Bbyce H. Grier g, J rector i
Enclosures:
1.
IE Information Notice No. 79-28 2.
List of Recently Issued Information Notices CONTACT:
L. E. Tripp (215-337-5282) cc w/encls:
M. K. Pastor, Project Manager i
1517 288 79141100 )? 2.
~
ENCLOSURE 1 SSINS No.:
6870 I
Accession No.: 79102504I5 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-28 Date: November 16, 1979 Page 1 of 1 OVERLOADING 0F STRUCTURAL ELEMENTS DUE TO PIPE SUPPORT LOADS Description of Circumstances:
Recently, the NRC was irformed 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 strectural 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 io ds.
2)
Inadequate design criteria for the reactions from st.morts 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 significant 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.
1517 289
e ENCLOSURE 2 IE Information Notice No. 79-28 Date:
November 16, 1979 Page 1 of 1 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 79-19 Pipe Cracks in Stagnant 7/17/79 All power reactor Borated Water Systems at facilities with an PWR Plants OL or CP 79-20 NRC Enforcement Policy -
8/14/79 All Holders of Reactor NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-20 Same Title as 79-20 9/7/79 Same as 79-20 (Revision No. 1) 79-21 Transportation and Com-9/7/79 All power and research mercial Burial of Radio-reactors with OLs active Material 79-22 Qualification of Control 9/14/79 All power reactor faci-Systems lities with an OL or CP 79-23 Emergency Diesel Generator 9/26/79 All power reactor faci-Lube Oil Coolers lities with an OL or CP 79-24 Overpressurization of Con-10/1/79 All power reactor faci-tainment of a PWR Plant lities with an OL or CP After a Main Steam Line Break 79-25 Reactor Trips at Turkey 10/1/79 All Power Reactor Faci-Point Unit 3 and 4 lities with an OL or CP 79-26 Breach of Containment 11/5/79 All Power Reactor Facilities Integrity with an OL or CP 79-12A Attempted Damage to New 11/9/79 All Fuel Facilities, Research Fuel Assemblies Reactors and Power Reactors with an OL or CP 79-27 Steam Generator Tube 11/16/79 All Power Reactor Facilities Ruptures at Two PWR with an OL or CP Facilities
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