BW030110, Tenth Refuel Outage Steam Generator In-Service Inspection Report
| ML033360656 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/24/2003 |
| From: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW030110 | |
| Download: ML033360656 (2) | |
Text
ExeIenpM Exelon Generation Company, LLC www.exeloncorp.com Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 November 24,2003 BW0301 10 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Braidwood Station, Unit 2 Facility Operating License No. NPF 77 NRC Docket No. STN 50-457
Subject:
Tenth Refuel Outage Steam Generator In-Service Inspection Report In accordance with Technical Specification 5.6.9, "Steam Generator (SG) Tube Inspection Reports," Exelon Generation Company, LLC is reporting the number of tubes plugged or repaired during the SG in-service inspection activities conducted during the Braidwood Station Unit 2 tenth refueling outage (i.e., A2R10). Technical Specification 5.6.9.a requires that following each in-service inspection of the SG tubes, the number of tubes plugged or repaired in each Scshati be reported to the NRC within 15 days. Therefore, we are providing this report by November 27, 2003.
During A2R10 refueling outage, which began November 4, 2003, eddy current inspection of the SG tubes was conducted. The scope of the inspection included 100% full-length bobbin coil inspection of the 2A, 26, 2C and 2D SGs. Fifty percent "Plus Point" Inspection of the hot leg top of tubesheet region, Row 1 and 2 U-Bend region and hot leg dents / dings > 5.0 volts was also conducted in the 2A, 2B, 2C and 2D SGs. Plus Point inspection was conducted on any bobbin coil indications classified as requiring additional diagnostic testing.
The SG tube inspections were completed on November 12, 2003. No tube sleeving was performed this outage. The Braidwood Unit 2 Steam Generator Tube Plugging Summary provides the inspection results during A2R1 0 and number of tubes removed from service to date by tube plugging.
November 20, 2003 U.S. Nuclear Regulatory Commission Page 2 of 3 BRAIDWOOD UNIT 2 STEAM GENERATOR TUBE PLUGGING
SUMMARY
l SGA SG B SGC SG D Total ProusLy Rugged 45 9
44 24 122 Rugged Dudng A2RO 8
39 10 1
58 Total 53 48 l
54 l
25 l
180 l
Dct any questions regarding this submittal to Kelly Root, Braidwood Manager, (815) 417-2800.
Regulatory Michael J. PAcili-Site Vice President Braidwood Station MP/MS/vk
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cc:
-- fRegional Administrator-NRC RegionIll.-
NRC Senior Resident Inspection - Braidwood Station