ML20112C587
| ML20112C587 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 02/22/1985 |
| From: | Hufham J TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-85, REF-PT21-85-131-000 PT21-85-131, PT21-85-131-000, NUDOCS 8503220023 | |
| Download: ML20112C587 (2) | |
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=o TENNESSEE VALLEY AUTHORITY 3
CHATTANOOGA. TENNESSEE 374of 400 Chestnut Street Tower II 85 MAR 6 "Ab '! VD,1985 f
BLRD-50-43 8/84-20 BLRD-50-439/84-19 U.S. Nuclear Regulatory Commission Region II Attn:
Dr. J. Nelsen Grace, Regional Administrator i
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Dear Dr. Grace:
BELLEFONTE NUCLEAR PLANI UNITS 1 AND 2 - ITT GRINNELL PIPE SUPPORTS DESICNED WITH SWAY STRUIS INSTEAD OF REQUIRED GAPS - BLRD-50-438/84-20 AND i
BLRD-50-439/84 SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector P. E. Fredrickson an February 16, 1984 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8404.
Our first interim report was submitted March 13, 1984.
Enclosed is our second interim report. We expect to submit our next report on x about December 4,1985. We consider 10 CFR Part 21 applicable to this deficiency.,
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY
. W. Hufham, Manager Licensing and Regulations Enclosure oc:
Mr. James Taylor, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Catter (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 FED 8503220023 850222
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Brnan con PDR ADOCK 0500043G 8 l 8
PDR An Equal Opportunity Employer
y-ENQ 0SURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 ITT GRINNELL PIPE SUPPORTS DESIGIED WITH SWAY STRUTS INSTEAD OF REQUIRED GAPS BLRD-50-43 8/84-20 AND BLRD-50-439/84-19 10 TR 50.55(e)
NCR BLN BLP 8404 SECOND INTERIM REPORT Description of Deficiency Seismic pipe supports designed by ITT Grinnell, Providence, Rhode Island, which are used on safety-related systems have sway struts specified where the piping analysis load tables generated by TVA require gaps ranging from 1/16 to 1/8 inches in the restrained dimetion. The sway struts (ITT Grinnell Figure 211) do not specify any allowable movements in the restrained direction in the load capacity data sheets. The deficient supports which
~ have been identified are as follows:
1 RT-MPHG-A052 Sh3 1RT-MPHG-A052 Sh4 1RT-MPHG-B052 Sh3 1RT-MPHG-B052 Sh4 ORF-MPHG-0300 Sh1
-eThe cited supports were designed for use on the standby diesel generator and controls (RT) system and the high-pressure fim protection (RF) system.
Interim Progress As indicated in TVA's first repert on this deficiency, a design myiew was conducted -by TVA to determine which support designs specified a gap in a restrained direction. The affected designs were reviewed as follows.
Support designs for which a 1/16-inch gap in the restrained direction was specified in the load tables were acceptable without the gap due to the inherent flexibility of supports and pipe valls and the plastic deformation of pipe which occurs during the first few cycles of operation.
Support designs for which a 1/8-inch gap in the restrained dimetion was specified in the load tables were rot uniformly accepted. The designs were reviewed on the basis of the following guidelines which have been incorporated into the Bellefonte Nuclear Plant Rigorous Analysis Handbook.
1.
On reanalysis, first investigate the possibility of eliminating the support. If the support cannot be eliminated, investigste the possibility of accepting the gap tolerance in General Construction Specification G-43 and standard snubber fme travel and spring rates should be accepted as adequate (i.e., the free travel plus deformation under load of, a snubber based on engineering judgnent should be specified without regard for the 1/8-inch gap considered in the analysis).
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