ML20236N381

Responds to NRC Re Violations Noted in Insp Repts 50-259/87-20,50-260/87-20 & 50-296/87-20.Corrective Actions: Engineering Drawings Now Required to Specify Anchorage Requirement & Control Room Panel Seismic Analysis Scheduled

ML20236N381
Person / Time
Site:	Browns Ferry
Issue date:	08/06/1987
From:	Domer J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8708110480
Download: ML20236N381 (4)

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374o1 SN 157B Lookout Place AUG 061987 U.S. Nuclear Regulatory Commission

@ "i: bocument Control Desk Wewhington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260

) 50-296 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 - NRC OIE INSPECTION REPORT NOS. 50-259/87-20, 50-260/87-20, AND 50-296/87 RESPONSES TO DEVIATION Enclosed is TVA's response-to the letter from G. G. Zech to S. A. White dated July 8, 1987, which transmitted IE Inspection Report Nos. 50-259/87-20, 50-260/87-20, and 50-296/87-20 for TVA's Browns Ferry Nuclear Plant units 1, 2, and 3. This report cited TVA with one deviation. Enclosure 1 provides TVA's description of corrective actions and the completion date. A list of commitments is provided in enclosure 2.

If there are any questions, please telephone M. J. May at (205) 729-3566.

To the best of my knowledge, I declare the statements contained herein are complete and true.

Very truly yours.

TENNESSEE VALLEY AUTHORITY J. A. Domer, Assistant Director Nuclear Safety and Licensing Enclosures cc: See page 2 l

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l An Equal Opportunity Employer

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.cc (Enclosure): j Mr.'G. G.'Zech, Assistant Director-Regional. Inspections- '

office of Special Projects U.S. Nuclear ReSulatory Commission Region II 101 Marietta-St., NW, Suite 2900 Atlanta, Georgia 30323.

Browns Ferry Resident Inspector )

Browns Ferry Nuclear Plant P.O. Box 311 Athens,' Alabama- 35611 Mr. J. A. Zwolinski, Assistant Director for Projects -

Division of TVA Projects Office of Special. Projects U.S. Nuclear Regulatory Commission

.4350 East West Highway EWW 322 Bethesda, Maryland 20814-

I ENCLOSURE 1 i RESPONSE TO NRC INSPECTION REPORT NOS. 50-259/87-20, 50-260/87-20, AND 50-296/87-20 DATED JULY 8, 1987 ITEM Section 7.2.5.2 of the Browns Ferry Plant Final Safety Analysis Report (FSAR) l states that the seismic capability of certain safety systems, including l

control room panels, were demonstrated by vibration testing, of the representative assemblies. The FSAR further states that during testing the panels were mounted on the shaker table in a manner similar to the service mounting.

Contrary to the above, main control room vertical bench board type control panels and freestanding vertical control panels were found to be mounted in a manner not consistent with the seismic qualification with no similarity analysis to justify the differences. NEDO-10678, " Seismic Qualification of Class 1 Electric Equipment," documents that the panels were to be floor mounted using 5/8 inch bolts in all mounting holes. Mechanical layout drawing 47W605-3 shows the as-constructed mounting details of these panels to be " tack welded at intervals to fasten in place."

1. Corrective Steps Which Have Been Taken and Results Achieved The anchorage details for the control room panels specified on the mechanical layout drawing 47W605-3 issued on May 1, 1968, did not adequately specify the anchorage details to ensure installation similar to that required by the qualification test. TVA's engineering procedures now require engineering drawings to clearly specify the anchorage requirements which are documented by appropriate engineering evaluations. Also, TVA has since improved the quality inspection program to require a more rigid inspection of the anchorage installation and to provide the proper documentation certifying the proper installation.

2. Corrective Steps Which Will Be Taken to Avoid Further Deviation TVA will perform a seismic review of the main control room vertical bench board panels and freestanding control panels to determine the appropriate mounting arrangement. Following this analysis, the engineering drawings will be revised to reflect the correct anchorage requirements. After the design is complete, the subject panele will be modified to meet the design requirements. The design change, together with the modification, will bring the seismic qualification of the subject panels into compliance with FSAR Section 7.2.5.2.

3. Date of Full Compliance The main control room panels will be modified by February 27, 1988.

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ENCLOSURE 2 RESPONSE TO NRC INSPECTION REPORT Nos. 50-250/87-20, 50-260/87-20, AND 50-296/87-20 DATED JULY 8, 1987 List of commitments made in enclosure 1.

1. The engineering drawing will be revised to reflect the correct anchorage requirements.

2. The subject panels will be modified by February 27, 1988, i

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