ML13058A183
| ML13058A183 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/26/2013 |
| From: | Wideman S Wolf Creek |
| To: | Lyon F Plant Licensing Branch IV |
| Lyon C | |
| Shared Package | |
| ML13058A178 | List: |
| References | |
| TAC MF0736 | |
| Download: ML13058A183 (2) | |
Text
From:
Wideman Steve G To:
Lyon, Fred Cc:
Muilenburg William T; Peabody, Charles; Kopriva, Ron; Wagner Pat G; Herrman Paul J; Broschak John P; Westman Mike J; Fredrickson Kenneth L
Subject:
RE: Steam Generator Inspections for Upcoming RFO Date:
Tuesday, February 26, 2013 9:32:21 AM Attachments:
SG A HL RUST 3.png Fred - in accordance with the below email of February 1, 2013, this email is to make you aware of two items identified during the current refueling outage Steam Generator (SG) Inspections. If it is determined that a conference call is needed, please let Bill Muilenburg and myself know.
Item 1 - During the primary bowl scan of SG 'A' Hot Leg as part of the Westinghouse Nuclear Safety Advisor Letter NSAL-12-1, "Steam Generator Channel Head Degradation," a rust color spot was identified approximately 6 inches down from the face of the tubesheet along the divider plate to bowl weld (see attached photo). Following identification of this area, UT was attempted of the area from outside the SG primary bowl. The first attempt was unsuccessful utilizing a straight beam UT probe due to interferences with the SG support beam. Subsequently, a 60-degree L Wave UT probe was utilized to characterize the area. This UT determined that the flaw was approximately 0.1 inches deep by approximately 1 inch long. No width could be obtained. This item is currently being evaluated by WCNOC and Westinghouse to determine what the future course of action will be necessary.
Item 2 - During the Top-of-Tubesheet eddy current inspection, a circumferential indication was confirmed in SG 'B' Hot Leg (17,89) ~TTS -6.46" which is located at a bulge indication.
Due to this indication, 100% of the tubes containing BLG and/or OXP will be inspected in SG 'B' within the inspection region. Also, 20% of the tubes containing BLG and/or OXP within the inspection region for SGs 'A', 'C', and 'D' will need to be inspected. It should be noted that as part of the original inspection program that greater than 20% of the BLG and/or OXP within the tubesheet in SG 'A', 'C', and 'D' are already being inspected.
Therefore, currently there is no additional testing required in SG 'A', 'C', and 'D'.
Steve Wideman WCNOC Licensing 620-364-4037
From: Lyon, Fred [1]
Sent: Friday, February 01, 2013 5:35 AM To: Wideman Steve G; Elwood, Thomas B Cc: Muilenburg William T; Maglio, Scott A; Hartman, Thomas; Peabody Charles A
Subject:
Steam Generator Inspections for Upcoming RFO
As you are may recall, the steam generator branch (ESGB) participates in conference calls with a handful of licensees performing steam generator inspections every outage season.
They have not selected Wolf Creek or Callaway for such a call during their upcoming
outages; however, please notify me if one (or more) of the following circumstances is identified during the outage:
- 1. If a degradation mechanism (other than wear from loose parts) is observed that has not been previously observed in these steam generators.
- 2. If degradation of steam generator secondary side internals is observed that has not been previously observed in these steam generators.
- 3. If a flaw is more severe than expected, or if the number of flaws identified are more than expected.
- 4. If an in-situ pressure test is performed.
If you experience one (or more) of the above, please let me know. The staff may request that you participate in a conference call to discuss your findings.
If you are not performing any steam generator tube inspections this upcoming outage, please let me know.
Thanks, Fred