ML20141H384
| ML20141H384 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/15/1997 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20141H388 | List: |
| References | |
| NUDOCS 9705230289 | |
| Download: ML20141H384 (2) | |
Text
l j
Commonwealth Liison G>mpany l
Braidwood Generating station j
Route ci, liox Hi j
15rgceville, II,60 6u7%I9 l
Tel HI 5-4542801 May 15,1997 l
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Comed Braidwood Station Unit I Cycle 6 Refuel Outage Steam Generator Inservice Inspection Report Docket No. STN 50-456
References:
(1) NUREG-1276, Technical Specifications, Braidwood Station, Unit Nos. I and 2 Technical Specification 4.4.5.5.c of reference (1) requires that the results of steam generator (SG) tube inspections which fall into Category C-3 shall be reported in a Special Repon to the Commission pursuant to Specification 6.9.2 within 30 days, and prior to resumption of plant operation.
Additionally, a License Event Report evaluating the condition is required pursuant to 10CFR5073(a)(2)(ii). This report provides a description of investigations conducted to determine the cause of tube degradation and corrective measures taken to prevent recurrence.
)/
An initial sample size of 100% of all available tubes was selected. The eddy current data was analyzed using the EddyNet 95 software. The initial sample inspection resulted in the following SGs being classified into Category C-3 based on the NN, following reasons:
lA On April 23,1997, at 07:30 hours, greater than 1% of the 3986 inservice tubes being defective.
IB On April 21,1997, at 07:15 hours, greater than 1% of the 4154 inservice tubes being defective.
IC On April 27,1997, at 22:30 hours, greater than 1% of the 3662 inservice tubes being defective.
ID On April 23,1997, at 21:00 hours, greater than 1% of the 4153 l
inservice tubes being defective.
Notification per Technical Specification 4.4.5.2 pursuant to 10 CFR 50.72(b)(2)(i) for steam generators being classified in Category C-3 was initiated within four hours of 9705230289 970515 lililllillituilllitillllil l!Il lllIU sl11 l
PDR ADOCK 05000456-lillllllllllHllillllllisll ulu ll S
- PDR, A 1inicom company
t Document Control Desk May 15.1997 Page 2 l
the affected SGs being evaluated as C-3. The enclosed License Event Report (456-180-97-002) summarizes the inspection results.
Please direct any questions regarding this submittal to Terrence Simpkin, Braidwood Regulatory Assurance Supervisor,(815) 458-2801, extension 2980.
Very truly yours, WJ othy J. Tulon tation Manager Braidwood Station l
TJT'Mhusol4 doc
Enclosure:
Steam Generator C-3 Report cc:
Senior Resident inspector - Braidwood
'Braidwood Project Manager, NRR Regional Administrator, Region ill I
1 i
i