ML20134A369

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Forwards Com Ed Braidwood Nuclear Station Unit 2 Fifth Refuel Outage (Apr 1996) SG ISI Results
ML20134A369
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 01/15/1997
From: Tulon T
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134A372 List:
References
RTR-NUREG-1276 GL-95-03, GL-95-3, NUDOCS 9701280276
Download: ML20134A369 (1)


Text

Communucalth Edi,on Ormpany tiraidwood Generating $tation House al,llox H1 liraces ille,11. GHO73 Kit 9 Tel H15-453 2H01 January 15,1997 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Comed Braidwood Station Unit 2 Fifth Refuel Outage Steam Generator Inservice Inspection Report Docket No. STN 50-457

References:

(1) NUREG 1276, Technical Specifications, Braidwood Station, Unit Nos. I and 2 Specification 4.4.5.5.b of reference (1) requires that within 12 months following the complet.on of each insenice inspection of steam generator tubes, the complete results of the inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2. This report shall include the number and extent of tubes inspected, location and percentage of wall-thickness penetration for cach indication of an imperfection, and identification of tubes plugged or repaired.

The Braidwood Unit 2 steam generator eddy current inspection was completed on April 12,1996.

During this inspection,100% of the tubing received a full length bobbin coil cddy current inspection.

Also, the inspection included a Rotating Pancake Coil (RPC) inspection of 28% of the hot-leg top-of-tubesheet roll transition regions,100% of the Row I and Row 2 U-Bend regions,20% of the tubes expanded at Preheater Bames 'B"and 'D"in the 2 A Steam Generator, and 64% of the dents greater than 5 volts at the hot-leg tube suppon plates. All c.::uninations exceeded the minimum requirements .

of the Technical Specifications and commitments made in the response to Generic Letter 95-3, Circumferential Cracking of Steam Generator Tubes.

Enclosed is a sununary of the inspection results. Included are a guide to the abbr; utions used in the indication list, indication lists and maps, and the qualification requirements of th sertified personnel performing the eddy current examinations.

Please direct any questions regarding this submittal to Doug Huston, Braidwood Licensing Supervisor, (815) 458-2801, extension 2511.

Very truly yours.

. Tulon f Station Manager Braidwood Nuclear Station (( /

TTr/Rv9?NRC007 h Enclosure E'80103 cc: R. R. Assa, Braidwood Project Manager - NRR A. B. Beach. Regional Administrator - Rlli F. Niziolck IDNS C. J. Phillips Senior Resident inspector - Braidwood 9701280276 970115 PDR ADOCK 05000457 G PDR A linicom Q>mpan)

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