ML20210L707

Interim Deficiency Rept SCR Bln 4949 Re Use of Long Slotted Holes W/O Plate Washers.Initially Reported on 860822. Investigation of Reactor Bldgs & Pipe Support Connections Required to Determine If Corrective Action Needed

ML20210L707
Person / Time
Site:	Bellefonte
Issue date:	09/22/1986
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
SCR-BLN-4949, NUDOCS 8610020178
Download: ML20210L707 (2)

Text

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 5 15 1,L poutPlace A

BB SEP 2 BLRD-50-438/86-10 'iP 2 BB6 BLRD-50-439/86-08 U.S. Nuclear Regulatory Commission Region II Attention: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

Dear Dr. Grace:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - USE OF LONG SLOTTED HOLES WITHOUT PLATE WASHERS - BLRD-50-438/86-10 AND BLRD-50-439/86 INTERIM REPORT The subject deficiency was initially reported to NRC-OIE Inspector Art Johnson on August 22, 1986 in accordance with 10 CFR 50.55(e) as SCR BLN 4949. Enclosed is our interim report. We expect to submit our final report on or about one year before fuel load of unit 1.

If there are any questions, please get in touch with D. L. Terrill at FTS 858-7558.

Very truly yours, TENNESSEE V LEY AUTHORITY b-R. L. Gridley Director I

Nuclear Safet and Licensing Enclosure cc (Enclosure):

Mr. James Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8610020178 860922 PDR ADOCK 05000438 S PDR I \

An Equal Opportunity Employer

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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 USE OF LONG SLOTTED HOLES WITHOUT PLATE WASHERS i BLRD-50-438/86-10 AND BLRD-50-439/86-08 SCR BLN 4949 10 CFR 50.55(e)

FIRST INTERIM REPORT DESCRIPTION OF DEFICIENCY Structural connections utilizing A325 and A490 bolts with long slotted holes in the outer ply were identified as not being installed with bars or plate washers to completely cover the slots as required by American Institute of Steel Construction (AISC).

This condition was initially identified as occurring on the blowout roof framing for the Main Steam Valve Rooms As (drawing 4AWO804-X2) and a significant condition report (SCR BLN 4949) was issued. Subsequent investigation ~ identified a similar violation in the Control Building and determined that violations may occur in the Reactor Buildings. In addition, two AISC designed pipe supports in the Main Steam Valve Room Bs had long slotted holes that do not specify plate washers.

TVA is continuing investigation of the apparent cause and generic implications ' ' '

of these deficiencies.

SAFETY IMPLICATIONS This condition could result in the slippage of the affected connections, thereby reducing their load carrying capability. Under extreme loadings, failure of a connection could occur, thereby resulting in a condition that could adversely affect the safe operation of the plant.

INTERIM PROGRESS Through use of test results (referenced by AISC) for oversized and slotted holes, investigation of the conditions in the Main Steam Valve Room As and the Control Building indicate the as-constructed condition is structurally acceptable. Further investigation of the Reactor Buildlings and pipe support connections is required to determine if corrective action is required.

A final report will be provided one year before fuel load of unit 1.

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