ML19260B408
| ML19260B408 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/16/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 7912100136 | |
| Download: ML19260B408 (1) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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KINc OF PRUSSIA, PENNSYLVANIA 19406 0D Docket No. 50-333 Power Authority of the State of New York James A. FitzPatrick Nuclear Power Plant ATTN:
Mr. J. D. Leonard Resident Manager P. O. Box 41 Lycoming, New York 13093 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, L277)L $/
b' v
'N 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:
George T. Berry, Executive Director P. W. Lyon, Manager - Nuclear Operations A. Klausmann, Director, Quality Assurance M. C. Cosgrove, Quality Assurance Supervisor J. F. Davis, Chairman, Safety Review Committee V. J. Cassan, Assistant General Counsel G. M. Wilverding, Licensing Supervisor 1517 315
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ENCLOSURE 1 SSINS No.:
6870 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 t, 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 tbc Architect End neer for the plant.
These structural inadequacies were reparted to be attributable to two deficiencies:
1)
Apparent lack of a final check of certain pipe support locations and reactions to ens Te that the supporting structural elements possessed adequate structural integrity to sustain the required loads.
2)
Inad(quate design criteria for the reactions from supports anchored into the f' ace 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 curren':ly 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 ycu have any questions regarding this matter, plaase contact the Director of the appropriate NRC Regional Office.
1517 316 No written response tt
'4 IE Information Notice is required.
ENCLOSURE 2 IE Informatisn Notice No. 79-28 Date:
November 16, 1979 Page 1 of 1 RECENTLY ISSUE 0 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 Ali 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 auptures at Two PWR with an OL or CP Facilities 1517 317