ML20113A262
| ML20113A262 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/18/1996 |
| From: | Kofron K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYRON-96-5100, NUDOCS 9606240194 | |
| Download: ML20113A262 (3) | |
Text
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BYRON-96-5100 FILE:
3.11.0530 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Document Control Desk
SUBJECT:
Byron Unit 1 Steam Generator F* Criteria implementation During the Cycle 7 Refueling inspection Byron Nuclear Power Station, Unit 1 Facility Operating License NPF-37 NRC Docket No. 50-45.4 This letter is to inform the Staff of steam generator tubes that were left inservice through application of the F* repair criteria during the Byron Unit 1 Cycle 7 refueling outage eddy current inspection. This information is being reported pursuant to Facility Operating License NPF-37, Appendix A, Technical Specification 3/4.4.5.5.e.
In accordance with Specification 3/4.4.5.5.e, the F* report shall include:
1)
Identification of F* Tubes, and 2)
Location and size of the degradation.
A total of four tubes were left inservice as a result of applying the F* repair criteria. identifies the F* tubes with the location and size of the degradation. Also included in the Attachment is the measured F* distance. The F* distance is the measured length from the last hardroll contact point or the secondary tubesheet face, whichever is further into the tubesheet, to the crack ip nearest the top of the tubesheet, in cases where an elevated sleeve is present, the F* distance is measured from the bottom of the sleeve to the nearest crack tip. The minimum F* length required by Technical Specification 4.4.5.4.a.12) is 1.7 inches of hard roll that is free from degradation.
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~X Should you have any questions regarding this matter, please contact Mr. J. R. Smith at (815) 234-5441, extension 2604, cM K. L. Kofron Q Station Manager Byron Nuclear Power Station DBW/cb cc:
H. J. Miller, NRC Regional Adrr,inistrator - Rlli G. F. Dick, Jr., Byron Project Manager - NRR H. Peterson, Senior Resident inspector - Byron i
Office of Nuclear Facility Safety - IDNS l
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ATTACHMENT 1 BYRON UNIT 1 CYCLE 7 F* TUBES SA Intte Location F* Lenath Siza Comment B
3-113 TSH-2.03" 1.83" 4.59 volts C
45-43 TEH + 2.67' 12.45" 1.15 volts Below Sleave C
40-46 TEH + 3.35" 11.33" 0.44 volts Below Sleeve D
29-91 TSH-2.89" 2.29" 4.17 volts DEFINITIONS iSH Top of the Tubesheet on the Hot Leg side (tubesheet secondary face)
TEH Tube End on the Hot Leg side (tubesheet primary face)
SIZE Eddy Current Voltage from the Plus-Point Probe operating at a frequency of 300 kHz.
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