ML13330A585
| ML13330A585 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/19/2013 |
| From: | John Hughey Plant Licensing Branch 1 |
| To: | Duke P Plant Licensing Branch 1 |
| Hughey J | |
| References | |
| Download: ML13330A585 (1) | |
Text
From:
Hughey, John To:
"Duke, Paul R."
Subject:
RAIs Associated With Review of Salem Unit 2, 2R19 Steam Generator Tube Inspections Date:
Tuesday, November 19, 2013 3:33:00 PM
- Paul, By letter dated May 9, 2013 (Agencywide Documents Access System (ADAMS) Accession No. ML13133A083), PSEG Nuclear, submitted information summarizing the results of the 2012 steam generator (SG) tube inspections performed at Salem Nuclear Generating Station, Unit 2 during the nineteenth refueling outage.
The NRC staff has reviewed the information provided and determined that additional information is needed in order to complete our review.
- 1. In the Steam Generator Tube Plugging table of Attachment 1, it shows that 72 tubes were plugged in the 2012 outage. However, in the table in Attachment 4, it shows that 74 tubes were plugged in all SGs. Please clarify the number of tubes plugged during the 2012 outage.
- 2. Please discuss the scope and results of any secondary side inspections.
Please discuss whether the nuts that were previously found loose on various hatches or camera ports remained tightened and whether previously inaccessible locations were accessed to tighten the nuts using a higher torque.
- 3. Please provide the cumulative effective full power year for each inspection outage since SG replacement.
- 4. During inspection of the channel heads, various marks were found on the cladding in all four SGs. Please discuss the results of the eddy current exams and enhanced video inspection of these marks. Please discuss the cause and the disposition of these marks.
- 5. Please discuss whether the number of new anti-vibration bar wear indications has decreased from inspection to inspection and whether the growth rate has been decreasing with time. Please discuss any trends in this data. Please discuss whether the results of the inspection were bounded by your previous operational assessment.
- 6. In 3 of the 4 SGs, there is wear at a tube support plate (TSP) in the tube located in row 1, column 63. Since wear at the TSPs is normally random, please discuss any insights on why this location appears to be particularly susceptible to wear at the TSPs.
The NRC staff requests a response to the above questions by December 20, 2013. Please advise if PSEG would like to have a teleconference with NRC staff to clarify any of the questions above.
Thank you, John
John Hughey Salem / Hope Creek / TMI Project Manager NRR - Division of Operating Reactor Licensing Phone: 301-415-3204 e-mail: John.Hughey@nrc.gov