ML102560350

Upcoming Steam Generator Inspection

ML102560350
Person / Time
Site:	Palisades
Issue date:	09/09/2010
From:	Mahesh Chawla Plant Licensing Branch III
To:	Dotson B Entergy Nuclear Operations
Chawla M, NRR/DORL, 415-8371
References
Download: ML102560350 (2)

Text

Zeleznock, Karen From: Chawla, Mahesh Sent: Thursday, September 09,20102:18 PM To: DOTSON, BARBARA E Cc: Karwoski, Kenneth; Johnson, Andrew; Ellegood, John; Taylor, Thomas; Orlikowski, Robert; Wengert, Thomas; KUEMIN, JAMES L: Anderson, Paula SUbject:

SUBJECT:

PALISADES PLANT - UPCOMING STEAM GENERATOR INSPECTION Barb:

In-service inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. Please arrange a telephone conference call with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Palisades Nuclear Plant refueling outage. This call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed.

Listed below are the discussion points to facilitate this call.

STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS This conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the unit completes the inspections and repairs.

1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.

2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.

3. Discuss any exceptions taken to the industry guidelines.

4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, Ubends with a rotating probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts),

and the expansion criteria.

5. For each area examined (e.g., tube supports, denUdings, sleeves, etc), provide a summary of the number of indications identified to-date for each degradation mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).

6. Describe repair/plugging plans.

7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).

8. Discuss the following regarding loose parts:

1. what inspections are performed to detect loose parts 1

2. a description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known)

3. if the loose parts were removed from the SG

4. indications of tube damage associated with the loose parts

9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessing deposit loading, etc).

10. Discuss any unexpected or unusual results.

11. Provide the schedule for steam generator-related activities during the remainder of the current outage.

The NRC staff will document a summary of the conference call, including any material that you provide to the NRC staff in support of the call.

Should you have any questions you can contact me at 301-415-8371.

Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 3-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 2