ML20134J424

Forwards Braidwood Station Unit 1 Fifth Refuel Outage Steam Generator Inservice Insp Rept

ML20134J424
Person / Time
Site:	Braidwood
Issue date:	11/06/1996
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134J426	List: ML20134J424 ML20134J450
References
NUDOCS 9611150205
Download: ML20134J424 (2)

Text

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Commonwealth IMison Company l Ilraidwood Genenwing $tation Route 01, Ibx M4 Ilracesille, n.NH07M19 i Tel H15-45&2801 I November 6,1996 1

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555

Subject:

Comed Braidwood Station Unit 1 Finh Refuel Outage i Steam Generator Inservice Inspection Report  !

Docket No. STN 50-456

References:

(1) NUREG-1276, Technical Specifications, Braidwood Station, Unit Nos. I and 2 1 1

(2) Comed Letter b J/95-0109 to U.S. Nuclear Regulatory  !

Commission from T. J. Tulon, Comed Braidwood Station Unit  !

I Fifth Refuel Outage Steam Generator Inservice Inspection l Report, Docket No. STN 50-456, dated November 13,1995 Specification 4.4.5.5.b of reference (1) requires that within 12 months following the completion of each inservice inspection of steam generator tubes, the complete results of the inspection shall be submitted to the Commission in a Special Report pursuant to i Specification 6.9.2. This report shall include the number and extent of tubes 1 inspected, location and percentage of wall-thickness penetration for each indication of an imperfection, and identification of tubes plugged or repaired. The Braidwood Unit I steam generator eddy current inspection was completed November 13,1995.

During this inspection,100% of the tubing received a full length bobbin coil eddy current inspection. Due to the number of tubes being defective and, therefore, requiring to be repaired / plugged, a three volt interim plugging criteria (IPC) was approved by the NRC. Also, the inspection included a Rotating Pancake Coil (RPC) inspection of 100% of the hotAg top-of-tubesheet roll transition regions, RPC of a i minimum of 20% of the Row I und Row 2 U-Bend regions, RPC of a minimum of 20% of the tubes expanded at Preheater Baflies 'B" and 'D" in the IC Steam Generator, RPC inspection of all hot-leg distorted support indications (DSI) greater .

than 3.0 volts, RPC inspection of all cold-leg DSI's greater than 1.0 volt, RPC l inspection of a minimum of 20% of the hot-leg DSI's between 1.0 volt and 3.0 volts, $' l and RPC inspections to meet the requirements of Generic Letter 95-05. l 9611150205 961106 PDR ADOCK 05000456 G PDR A Unicom Compan)

Enclosed is a summary of the inspection results. Included are a guide to abbreviations used in the indication list, indication lists and maps, and the qualification requirements

of the certified personnel performing the eddy current examinations.

i Please direct any questions regarding this submittal to Doug Huston, Braidwood ,

Licensing Supervisor, (815) 458-2801, extension 2511.

T Very truly yours, 1 T* hy J. n ation Manager Braidwood Nuclear Station TJT/fb Enclosure I

cc: A. B. Beach, NRC Regional Administrator, Region III .

R. R. Assa, Project Manager, NRR I C. J. Phillips, Senior Resident Inspector l Office ofNuclear Safety -IDNE t

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