ML033180464
| ML033180464 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 11/03/2003 |
| From: | Peschel J Florida Power & Light Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033180464 (3) | |
Text
. -1 FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 Seabrook Station (603) 773-7000 NOV 3 2003 Docket No. 50-443 NYN-03089 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555 - 0001 Seabrook Station Steam Generator Tubes Plugged During Ninth Inservice Inspection FPL Energy Seabrook, LLC encloses pursuant to Seabrook Station Technical Specification Surveillance Requirement 4.4.5.5a, a tabulation of the number of tubes plugged in each steam generator ("A", "B", "C", and "D") inspected during the ninth inservice inspection. The ninth inservice inspection was completed on October 29, 2003.
The complete results of the ninth inservice inspection for steam generators will be submitted prior to October 29, 2004, pursuant to Technical Specification Surveillance Requirement 4.4.5.5b.
Should you have any questions regarding this information, please contact Mr. Michael D.
O'Keefe, Regulatory Compliance Supervisor at (603) 773-7745.
Very truly yours, FPL Energy Seabrook, LLC rap es-M. -Peschel Regulatory Programs Manager cc:
H. J. Miller, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G.T. Dentel, NRC Senior Resident Inspector A-q1 an FPL Group company
ENCLOSURE TO NYN-03089
I -
Seabrook Station Steam Generator Tubes Plugged During Eighth Inservice Inspection Technical Specification 4.4.5.5a requires that "within 15 days of completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.8.2."
Steam Generator Location Plugging reason S/G A Row 47 Column 96 AVB Wear 40%
S/G B Row 18 Column 64 AVB Wear 41%
S/G C Row 42 Column 72 AVB Wear 40%
S/G C Row 40 Column 39 AVB Wear 40%
S/G D Row 40 Column 80 AVB Wear 40%
S/G D Row 49 Column 69 AVB Wear 43%
SIG D Row 42 Column 49 AVB Wear 41%
S/G D Row 42 Column 52 AVB Wear 41%
S/G D Row 47 Column 44 AVB Wear 43%
S/G D Row 4 Column 64 ODSCC (Note 2)
S/G D Row 9 Column 25 ODSCC (Note 2)
S/G D Row 5 Column 87 ODSCC (Note 2)
S/G D Row 7 Column 91 Administrative (Note 2)
S/G D Row 9 Column 28 Administrative (Note 2)
S/G D Row 10 Column 22 Administrative (Note 2)
Note 1:
Plugging of AVB wear is required when wear is greater than or equal to 40%
through-wall.
Note 2:
There were six tubes identified in the Root Cause Report on Axial Cracking at Tube Support Plates that exhibited the eddy current absolute drift signal. All six are now plugged: three contained ODSCC and three had no degradation.