ML050870457
| ML050870457 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 03/23/2005 |
| From: | Pace P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML050870457 (3) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City. Tennessee 37381-2000 March 23, 2005 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C.
20555 Gentlemen:
In the Matter of
)
Docket No.50-390 Tennessee Valley Authority
)
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 -
CYCLE 6 REFUELING OUTAGE STEAM GENERATOR TUBE INSPECTION ALTERNATE REPAIR CRITERIA F-STAR (F*) REPORT In accordance with WBN Technical Specification 5.9.9, SG Tube Inspection Report, this report provides the results of Unit 1 steam generator tube inspections for tubes having indications which may remain in service using the F* alternate repair criteria.
The Enclosure provides the required data which includes identification of these tubes, the uppermost elevation of the degradation, the location of the bottom of the roll transition, and the extent of the degradation.
There are no regulatory commitments associated with this submittal.
If you have any questions about this report, please contact me at (423) 365-1824.
Sincerely, P. L. Pace Manager, Site Licensing and Industry Affairs Enclosure cc:
See Page 2
a.
U.S. Nuclear Regulatory Commission Page 2 MAR 2 3 2005 Enclosure Cc:
(Enclosure)
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. D. V. Pickett, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
f -;
ENCLOSURE WATTS BAR NUCLEAR PLANT UNIT 1 ALTERNATE REPAIR CRITERIA F-STAR (F*)
CYCLE 6 REFUELING OUTAGE REPORT UPPER MOST ELEVATION OF THE BRT FLAW EXTENT FLAW SG ROW COL FLAW LOCATION (inches)
CHARACTERIZATION 2
5 67 HTS-3.09 HTS-0.14 0.33 PWSCC HTS AXIAL 3
19 75 HTS-4.32 HTS+0.0 0.12 PWSCC HTS AXIAL 3
19 75 HTS-4.28 HTS+0.0 0.22 PWSCC HTS AXIAL 3
19 75 HTS-4.29 HTS+0.0 0.19 PWSCC HTS AXIAL 3
19 75 HTS-4.27 HTS+0.0 0.19 PWSCC HTS AXIAL 3
19 75 HTS-4.31 HTS+0.0 0.22 PWSCC HTS AXIAL 3
22 84 HTS-2.29 HTS-0.16 0.12 PWSCC HTS AXIAL 3
35 58 HTS-2.45 HTS-0.16 0.34 VOLUMETRIC 3
38 18 HTS-2.10 HTS-0.13 0.29 VOLUMETRIC 4
35 14 HTS-4.77 HTS-0.19 0.45 PWSCC HTS AXIAL 4
35 14 HTS-4.68 HTS-0.19 0.8 PWSCC HTS AXIAL 4
39 19 HTS-4.73 HTS+0.0 0.22 PWSCC HTS AXIAL Steam Generator 4 Row 35 Column 58 is a small outer diameter indication in the tubesheet which has not changed from the last inspection.
The data from this location from Cycle 1 has been reviewed, and the indication has not changed from that data.
This is not service-induced degradation.
Steam Generator 4 Row 38 Column 18 is also a small outer diameter indication in the tubesheet with has not changed.
There is past data on this indication as far back as Cycle 2.
This is not service-induced degradation.
ACRONYMS:
BRT HTS PWSCC Bottom Roll Transition Hot Leg Top of Tube Sheet Primary Water Stress Corrosion Cracking