ML17053B252
| ML17053B252 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/16/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider R NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 7912100134 | |
| Download: ML17053B252 (6) | |
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e UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406 Docket No. 50-220 BOY 16 typal Niagara Mohawk Power Corporation ATTN:
Mr.
R.
R. Schneider Vice President Electric Operations 300 Erie Boulevard West
- Syracuse, New York 13202 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,
~vv Boyce H. Grier Di-rector
/
Enclosures:
l.
IE Information Notice No. 79-28 2.
List of Recently Issued Information Notices CONTACT:
L.
E. Tripp (215"337"5282) cc w/encls:
T.
E.
- Lempges, General Superintendent, Nuclear Generation T. J
~ Perkins, Station Superintendent C.
L. Stuart, Operations Supervisor E.
B. Thomas, Jr.,
Esquire eel.2~00 ISS OP
ENCLOSURE 1
e SSINS No.:
6870 Accession No.: 79102504)5 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 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 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.
Information Notice No.
ENCLOSURE 2 IE Information Notice No. 79-28 Date:
November 16, 1979 Page 1 of 1 RECENTLY ISSUED IE INFORMATION NOTICES Subject Date Issued to Issued 79-19 79-20 79-20 (Revision No. 1) 79-21 79-22 79-23 79-24 79-25 79"26 79-12A 79-27 Pipe Cracks in Stagnant Borated Mater Systems at PWR Plants NRC Enforcement Policy-NRC Licensed Individuals Same Title as 79-20 Transportation and Com-mercial Burial of Radio-active Material qualification of Control Systems Emergency Diesel Generator Lube Oil Coolers Overpressurization of Con-tainment of a PMR Plant After a Main Steam Line Break Reactor Trips at Turkey Point Unit 3 and 4 Breach of Containment Integrity Attempted Damage to New Fuel Assemblies Steam Generator Tube Ruptures at Two PWR Facilities 7/17/79 8/14/79 9/7/79 9/7/79 9/14/79 9/26/79 10/1/79 10/1/79 ll/5/79 11/9/79 11/16/79 All power reactor facilities with an OL or CP All Holders of Reactor OLs and CPs and Production Licensees with Licensed Operators Same as 79-20 All power and research reactors with OLs All power reactor faci-lities with an OL or CP All power reactor faci-lities with an OL or CP All power reactor faci-lities with an OL or CP All Power Reactor Faci-lities with an OL or CP All Power Reactor Facilities with an OL or CP All Fuel Facilities, Research Reactors and Power Reactors with an OL or CP
.All Power Reactor Facilities with an OL or CP
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