ML17053B251
| ML17053B251 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/16/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Rhode G NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 7912100133 | |
| Download: ML17053B251 (6) | |
Text
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Docket No. 50-410 NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406 Mw7K~
Niagara Mohawk Power Corporation ATTN:
Mr.
G.
K.
Rhode Vice President System Project Management 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, Boyce H. Grier Director
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:
Eugene B. Thomas, Jr.,
Esquire
ENCLOSURE 1
SSINS No.:
6870 Access1on 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 ear ly 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.
ENCLOSURE 2 IE Information Notice No. 79-28 Date:
November 16, 1979 Page l. of 1 RECENTLY ISSUED IE INFORMATION NOTICES Informati on Notice No.
79-19 79-20 Subject Pipe Cracks in Stagnant Borated Water Systems at PWR Plants NRC Enforcement Policy-NRC Licensed Individuals Date Issued 7/17/79 8/14/79 Issued to All power reactor facilities with an OL or CP All Holders of Reactor OLs and CPs and Production Licensees with Licensed Operators 79-20 (Revision No. 1) 79-21 79-22 79-23 79-24 79-25 79-26 79-12A 79-27 Same Title as 79-20 Transport'ation and Com-mercial Burial of Radio-active Material qualification of Control Systems Emergency Diesel Generator Lube Oil Coolers Overpressurization of Con-tainment of a PWR 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 9/7/79 Same as 79-20 9/7/79 All power and research reactors with OLs 9/14/79 All power reactor faci-lities with an OL or CP 9/26/79 All power reactor faci-lities with an OL or CP 10/1/79 All power reactor faci-lities with an OL or CP 10/1/79 All Power Reactor Faci-lities with an OL or CP 11/5/79 All Power Reactor Facilities with an OL or CP ll/9/79 All Fuel Facilities, Research Reactors and Power Reactors with an OL or CP ll/16/79 All Power Reactor Facilities with an OL or CP
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