ML20210T037

Second Revised Final Deficiency Rept Re Attachment of Pipe Supports to 6-inch Strip Plates Lacking Capacity to Withstand Seismic Pipe Support Loads.Initially Reported on 811231.All Affected Supports Identified & Procedure Revised

ML20210T037
Person / Time
Site:	Bellefonte
Issue date:	09/15/1986
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8610080289
Download: ML20210T037 (2)

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TENNESSEE VALLEY AUTH'ORITY CHATTANOOGA, TENNESSEE 37401 SN 157B Lookout Place BLRD-50-43$38N719 n 9 : 49 SEP 15 SN BLRD-50-439/82-07 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 - ATTACHMENT OF PIPE SUPPORTS TO 6-INCH STRIP PLATES - BLRD-50-438/82-07, BLRD-50-439/82 SECOND REVISED FINAL REPORT The subject deficiency was initially reported to NRC-OIE Inspector R. V. Crlenjak on December 31, 1981 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8133. TVA's previous reports on this deficiency indicated that one of the six unacceptable supports was modified and all required rework completed.

Further investigation has revealed that the support was redesigned but has not yet been modified. Consequently, TVA has included rework of the affected support in the scope of our corrective action tracking mechanisms and has revised our final report to reflect the correct status. All corrective actions will be complete by six months before fuel load. Enclosed is our second revised final report.

If you have any questions concerning this matter, please get in touch with 4 D. L. Terrill at (615) 751-7558.

Very truly yours, TENNESSEE VALLEY AUTHORITY R. L. Gridley, irector Nuclear Safety 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 8610080289 860915 PDR ADOCK 05000438 S PDR ,

1 l An Equal Opportunity Employer f 1d]

.** ENCLOSURE

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BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 l ATTACHMENT OF PIPE SUPPORTS TO 6-INCH STRIP PLATES NCR BLN BLP 8133 BLRD-50-438/82-07, BLRD-50-439/82-07 10 CFR 50.55(e)

SECOND REVISED FINAL REPORT Description of Condition i

Six-inch wide embedded strip plates with a single row of 3/4-inch diameter Nelson studs were provided in the Reactor Buildings for the attachment of instrumentation and conduit supports. However, 149 ITT Grinnell pipe supports and TVA typical seismic pipe supports have been i installed attached to the strip plates. The apparent cause of this deficiency was a lack of controls which would restrict the use of the strip plates or would assure review of field installed supports before installation.

Safety Implications With the six-inch wide embedded strip plates lacking sufficient capacity in some cases to withstand the applied seismic pipe support loads, the ,

supported pipe could fail or cease to serve its intended function. This could result in failure to a safety class piping system and adversely affect the safety of operation of the plant.

Corrective Action i

TVA field personnel identified all pipe supports attached to the 6-inch wide plates. A total of 149 TVA and Grinnell pipe supports were found installed in that manner and a total of five were identified in the

preinstallation stage. Of these supports, five Grinnell supports and one TVA support were found to be unacceptable. Engineering Change Notice

1572 was written to accomplish the required modification of the TVA

-support. Support modification requests (SMR) were written to accomplish the necessary revisions to the Grinnell supports and are listed as i follows:

2CA-MPHG-0205 SMR 12557 1ND-MPHG-0022 (Sheet 2) SMR 12558

2ND-MPHG-0015 SMR 12955 1WD-MPHG-0068 (Sheet 1) SMR 12559 IWD-MPHG-0108 (Sheet 2) SMR 12560 To prevent recurrence, TVA's Division of Nuclear Construction (DNC) j Quality Control Procedure 6.17 has been revised to establish prework hold

points to ensure that all future installations have been reviewed and

! approved by TVA's Division of Nuclear Engineering.

1 DNC will complete the mouifications on the TVA and Grinnell supports by l six months before fuel load.

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