ML20135D403
| ML20135D403 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 08/28/1985 |
| From: | Hufham J TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-85, REF-PT21-85-407-000 PT21-85-407, PT21-85-407-000, NUDOCS 8509160044 | |
| Download: ML20135D403 (2) | |
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a TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ol 1630 Chestnut Street Tower II August 28, 1985 w
BLRD-50-438/84-17
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BLRD-50-439/84-16 co U.S. Nuclear Regulatory Commission g
Region II ro Attn:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900
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Atlanta, Georgia 30323
Dear Dr. Grace:
BELLEFONTE NUCLFAR PLANT UNITS 1 AND 2 - ITT GRINNELL PIPE SUPPORTS DESIGNED WITH SWAY STRUTS INSTEAD OF REQUIRED CAPS - BLRD-438/84-17, BLRD-439/84 SECOND INTERIM 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 first interim report dated March 6, 1984.
Enclosed is our second interim report. We expect to submit our next report on or about October 29, 1986. We consider 10 CFR Part 21 applicable to this deficiency.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY
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J. W. Hufham, Manager Licensing and Risk Protection Enclosure cc:
Mr. James Taylor, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8509160044 85 820430 PDR ADOCK PDR S
1 An Equal Opportunity Employer l
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I A 1 ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 ITT GRINNELL PIPE SUPPORTS DESIGNED WITH SWAY STEUTS INSTEAD OF REQUIRED GAPS BLRD-50-438/84-17, BLRD-50-439/84-16 NCR BLNBLP8403 10 CFR 50.55(e)
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4 SECOND INTERIM REPORT i
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Description of Deficiency J
ITT Grinnell-designed pipe supports ORF-MPHG-03-9, revision 3,1VE-MPHG-2392, i
1 sheet 1, revision 2, and 1VE-MPHG-2392, sheet 2, revision 0, which are located on alternately analyzed safety-related plant systems have incorrect l
This could i
pipe movement data shown on the ITT Grinnell detail sheets.
result in a support design where friction loads were not evaluated or swing i
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angles were not properly checked.
i Interim Progress l
TVA is approximately 90-percent complete with the revision of the support j
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designs identified as deficient. TVA will provide the report on this deficiency upon conclusion of our design revisions, which is expected to be on or about October 29, 1986.
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