ML19241A817
| ML19241A817 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/08/1979 |
| From: | Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JAFP-79-291, NUDOCS 7907090421 | |
| Download: ML19241A817 (2) | |
Text
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FtTzPATRICK NUCLEAR power PLANT h W JOHN O. LEONAnD, JR.
P.O. BOX 41 Resident Manager Lycoming, New York 13053 June 8, 1979 JAFP-79-291 315-342a84c Mr. Boyce H. Grier, Di rector United States Nuclear Regulatory Commission Region i 631 Park Avenue King of Prussia, Pennsylvania 19406
SUBJECT:
NRC I & E BULLETIN 79 INTERIM REE;AT
Dear Mr. Grier:
Pursuant to a telephone conversation between Mr. Stetka of your s taff and mysel f, I am forwarding an Interim Report on the status of our action regarding ISE Bulletin 79-02 entitled " Pipe S mport Base Plate Designs Using Concrete Expansion Anchor Bolts."
The bu letin was received at the James A. FitzPatrick Nuclear l
Power Plant in mid-March and reviewed by the staff at the plant.
It was determined by the plant staff that this bulletin significantly impacted the piping stress analysis being conducted on the FitzPatrick Plant due to the Show Cause Order issued by the Regulatory Commission on March 13, 1979 and therefore it was requested that our headquarters office take this bulletin for action and include it as part of the over-all piping engineering survey and analysis.
The justification for this action was af firmed when, on April 2, 1979, Mr. Victor Stello, Director, Division of Operating Reactor Office of Nuclear Reactor Regulations, issued a letter to the Authori ty which stated that the schedule for compliance with this bulletin would be an element cor.sidered in the Regulatory Commission review of the piping stress analysis program for the Fi tzPa trick Plant.
Since that time, an extensive amount cf work has been conducted at the plant in the verification of the adequr,y of hangers and in the physical inspection of the anchor bolts.
This inspection has formed the basis for the program for physically correcting any discrepancies noted at the plant.
The initial program for correcting anchrr bolt discrepancies if found, was to assure correct installation in accordance with the manufacturer's instructions and take credi t for the guaranteed anchor strength of the support.
Corcrete expansion anchors were then to be torqued to the proper value to insure prelcad in accordance with the bulletin.
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Boyce H. Grier, Director June 8, 1979 United States Nuclear Regulatory Commission JAFP 291
SUBJECT:
NRC I & E BULLETIN 79-02 Page We are expanding this program to include a pull test on the anchor itself for those anchors which are not fully embedded or have other discrepancies determined by %spection.
The procedure for this test is expected to be completed in the immediate future.
Experimental results on non-safety related system enchor bolts indicate that these anchors may hold a considersble load in excess of the manuf acturer's guaranteed holding strength and that in spite of installation deficiencies such as non perpendicularity, reduced length embedment, and partially set plugs in " redheads," the anchor is more than capable of performing its intended function.
Based on conversation with Mr. 0;rr of your staff, we will attempt to inspect and repair any noted deficiencies in as many as possible of the anchors in locations inaccessible durino power operation.
Should the Show Cause Order be lif ted and plant startup be permitted, we will continue the program in accessible areas on safety related systems until completion.
The results of this program will insure that anchors and base plates will perform their intended function.
In addition, the headquarters office of the Authori ty is proceeding, through a consu! tant, with an engineering program to determine the effect of flexibili y on presently installed t
base plates.
The headquarters staf f has also ccamitted to the Office of Nuclear Reactor Regulation that any re-design or piping supports which might occur due to the piping stress ana?y:Is which is presently being carried out for the plant, will be recdet igceti using the criteria of Bulletin 79-02.
Very trul-y-yours,
L,...
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- r /.wwf'8' A A V4 JDL:brp JOHttD. LEONARD, JR.
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Attachment RESIDENT MANAGER
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CC:
G. T. Berry, PASNY, N'O N.
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G. A. Wilverding, PASNY, NY0 P. W.
Lyon, PASNY, NY0 M. C. Cosgrove, JAF R. J. Pasternak, JAF Document Control Center 310 197