ML20207Q660

Final Part 21 & Deficiency Rept Re Misinterpretation of Pipe Movement Data for Itt Grinnell Designed Pipe Supports. Initially Reported on 840208.Pipe Support Detail Sheet Reviewed & Incorrect Drawings Revised

ML20207Q660
Person / Time
Site:	Bellefonte
Issue date:	01/21/1987
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	Grace J NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
REF-PT21-87, REF-PT21-87-024-000 PT21-87-024-000, PT21-87-24, NUDOCS 8701280471
Download: ML20207Q660 (3)

Text

e TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place OnN21's BLRD-50-438/84-17 BLRD-50-439/84-16 U.S. Nuclear Regulatory Conunission Attn: Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C. 20555 Attention: Dr. J. Nelson Grace BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - MISINTERPRETATION OF PIPE MOVENENT DATA FOR ITT GRINNELL DESIGNED PIPE SUPPORTS - BLRD-438/84-17 BLRD-439/84 FINAL REPORT The subject deficiency was initially reported to NRC-OIE Inspector Ross Butcher on February 8, 1984 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8403.

This was followed by our interim reports dated March 6,1984 and August 28, 1985. Inclosed is our final report. We consider 10 CFR Part 21 applicable to this deficiency.

If you have any quostions concerning this matter, please set in touch with D. L. Terrill at (205) 574-8820.

Very truly yours, TENNESSEE VALLEY AUTHORITY h

.4 6 dt. L. Cridley, Director Nuclear Safety and Licensing Enclosure cc: See paEe 2 8701280471 870121 PDR ADOCK C5000438 8 PDR An Equal Opportunity Employer

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U.S. Nuclear Regulatory Comission cc (Enclosure):

Mr. G. G. Zech, Director TVA Projects U.S. Nuclear Regulatory Comission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Bellefonte Resident Inspector Bellefonte Nuclear Plant P.O. Box 2000 Hollywood, Alabama 35152 Records Center Institute of Nuclear Power Operations t 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 j

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r 0 ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 MISINTERPRETATION OF PIPE MOVEMENT DATA FOR ITT GRINNELL DESIGNED PIPE SUPPORTS BLRD-50-438/84-17, 50-439/84-16 NCR BLN BLP 8403 10CFR50.55(e) FINAL REPORT Description of Deficiency ITT Grinnell (ITTG) Pipe Hanger Division (Providence, Rhode Island) designed pipe supports ORF-NPNG-0309 R3, IVE-NPHC-2392 Sheet 1 R2, and IVE-NPNG-2392 Sheet 2 RO Which are located on alternately analyzed safety-related plant systems have incorrect pipe movement data shown on the ITT Grinnell detail sheets. Some of the incorrect data was supplied by ITTC and some of it entered by ITTC at the direction of TVA designers due to confusion in terminology used with respect to pipe movements. This could result in a support design where friction loads were not properly evaluated or swing angles were not properly checked contributing possibly to unconservative pipe support designs.

The incorrect movement data shown on the pipe support detail sheets resulted from the misinterpretation of non numeric data in the pipe movement chart on the table of support loads for alternately analyzed systems (specifically where the movement charts had blanks or NAs).

The problem identified by this NCR is unique to Bellefonte alternately analyzed piping and does not apply to other TVA plants; thus no generic condition exists.

Safety Implications Failure to properly consider friction loads or check swing angles when designing supports could lead to unconservative support designs for some design conditions. This could lead to a support failure or, at a minimum, I reduce the margin of safety intended for support designs. Such unconservatively designed supports could be adverse to the safety of operations of the plant.

Corrective Action The ITT Grinnell pipe support detail sheets were reviewed against the revised alternate analysis table of support loads to identify where incorrect movement data was used. Pipe support drawings identified as possessing incorrect movements will be revised in accordance with the current plant schedule. This work and any necessary corrections to installed pipe supports will be completed at least six months before fuel loading of the applicable unit.

The action required to prevent recurrence hno been completod: that is, the pipe movement columns on the alternately analyzed table of support loads were revised to show numeric entries and a section polley issued to indicate that numeric entries must be used for pipe movements on alternately analyzed piping in the future.