ML20108D233
| ML20108D233 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/23/1996 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ED-96-0352-BRW, ED-96-352-BRW, NUDOCS 9605070344 | |
| Download: ML20108D233 (3) | |
Text
Commonw caltli I:dnun Company tiraidw ood 0rnerating Station Route 81, llox HI s
If racculle. Il 6040' 9619 Tel H1445M 2M01 April 23,1996 ED-96-0352-BRW U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Subject:
Braidwood Station Unit 2 Fifth Refuel Outage Steam Generator Inservice Inspection Report NRC Docket No. STN 50-457
References:
(1) NUREG-1276, Technical Specifications, Braidwood Station, Unit Nos. I and 2 Specification 4.4.5.5.a of referenc.e (1) requires that within 15 days following the completion of each inservice inspection of steam generator (SG) tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2.
During the Braidwood Unit 2 Fifth Refuel Outage which began on March 16, 1996, an eddy current inspection of the steam generator tubing was conducted. The initial inspection scope was to inspect the 2A and 2D SGs only, but due to indications identified in the 2A and 2D SGs, the inspection scope was expanded to the 2B and 2C SGs. The following inspections were performed:
100% of the total inservice SG tubing was inspected full length using the bobbin coil probe 23% of the total SG tubing hot-leg roll transition regions was inspected using the Rotating Pancake Coil probe.
64% of the Dents greater than 5 volts at the hot-leg Tube Support Plates were inspected using the Rotating Pancake Coil probe.
100% of the inservice SG tubes in the Row I and Row 2 U-Bend region were e
inspected using the Rotating Pancake Coil probe.
20% of the SG tubing expanded at Preheater BafIles "B" and "D"in the 2A SG was inspected using the Rotating Pancake Coil probe.
All of the inspections met the minimum requirements of the NRC commitments. The inspection was completed on April 12,1996. Attachment A summarizes the results of this inspection, and Attachment B includes a tube plugging history for Braidwood Unit 2.
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U.S. Nuclear Regulatory Commission April 23,1996 2
Please direct any questions regarding this submittal to Doug Huston, Braidwood Licensing Supervisor, (815) 458-2801, extension 2511.
Very truly yours,
. J. Tulon Station Manager Braidwood Nuclear Station Attachments cc:
Senior Resident Inspector - Braidwood Braidwood Project Manager - NRR Regional Administrator-RIII l
6
Attachment A BraidWood Unit 2 Fifth Refuel Outage (A2R05) SG Tube Plugging Results 2A SG 28SG 2C SG 2DSG TOTALS Total Tubes 4570 4570 4570 4570 18280 Previously Plugged Tubes 11 2
23 4
40 Total Tubes inspected This Obtage 4559 4568 4547 4566 18240 Anti-Vibration Bar Wear Pluggable 16 2
4 7
29 Tubes Plugged With VOL Indication at 1H TSP 1
0 0
1 2
Tubes Plugged With indications in U-Bend 0
0 0
1 1
2 Loose Part*,
Tubes Plugged due to 1 VOL Administrative Reasons 0
0 0
Freespan 3
A2R05 Total Tubes Plugged 17 2
4 12 35 Restart Total Tubes Available 4542 4566 4543 4554 18205 Total Tubes Plugged 28 4
27 16 75 Percentage of Tubes Plugged 0.61 0.09 0.59 0.35 0.41 SG Tube Plugging Limits are a maximum of 30% in any one SG with a maximum of 24% total.
- Loose Part found in the 2D SG at the 8H TSP Row 43 Column 73 (62% throughwall). Unsuccessful attempt made to retrieve loose part. Safety Evaluation performed to allow loose part to be left inside SG.
Two tubes plugged per Safety Evaluation.
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