ML092810089

SG Tube ISI Conference Call for Fall 2009 RFO

ML092810089
Person / Time
Site:	Sequoyah
Issue date:	10/08/2009
From:	Siva Lingam Division of Operating Reactor Licensing
To:	Casey K Tennessee Valley Authority
Lingam, S NRR/DORL 415-1564
References
TAC ME2354
Download: ML092810089 (4)

Text

From: Lingam, Siva Sent: Thursday, October 08, 2009 9:37 AM To: 'kecasey@tva.gov' Cc: Boyce, Tom (NRR); Gavrilas, Mirela; Karwoski, Kenneth; Johnson, Andrew; Franke, Mark; 'fcmashburn@tva.gov'

Subject:

Sequoyah 2 - SG Tube ISI for Fall 2009 Outage (TAC No. ME2354)

Per our telephone conversation this morning, you agreed to participate in the conference call with NRC staff to discuss Steam Generator (SG) Tube in-service inspection (ISI) activities during the upcoming outage for Sequoyah Nuclear Plant, Unit 2. ISIs of SG tubes play a vital role in assuring SG tube integrity. A telephone conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Sequoyah Nuclear Plant, Unit 2 refueling outage. This call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. Following is a list of discussion points to facilitate this call. Please note that these discussion points have been updated since the last outage call was held with the plant.

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.

STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS The following discussion points have been prepared to facilitate the conference call that will be arranged with the licensee to discuss the results of the steam generator tube inspections to be conducted during the upcoming fall 2009, Unit 2 refueling outage for Sequoyah Nuclear Plant.

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.

The NRC staff plans to document a summary of the conference call as well as any material that is provided in support of the call.

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, U-bends 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, dent/dings, 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:

$ what inspections are performed to detect loose parts

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

$ if the loose parts were removed from the SG

$ 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.

If you have any questions, please contact me.

Siva P. Lingam U.S. Nuclear Regulatory Commission Project Manager (NRR/DORL/LPL2-2)

Sequoyah Nuclear Plant Location: O8-D5; Mail Stop: O8-G9a Telephone: 301-415-1564; Fax: 301-415-1222 E-mail address: siva.lingam@nrc.gov E-mail Properties Mail Envelope Properties ()

Subject:

Sequoyah 2 - SG Tube ISI for Fall 2009 Outage (TAC No. ME2354)

Sent Date: 10/8/2009 9:13:46 AM Received Date: 10/8/2009 9:37:00 AM From: Lingam, Siva Created By: Siva.Lingam@nrc.gov Recipients:

kecasey@tva.gov ('kecasey@tva.gov')

Tracking Status: None Tom.Boyce@nrc.gov (Boyce, Tom (NRR))

Tracking Status: None Mirela.Gavrilas@nrc.gov (Gavrilas, Mirela)

Tracking Status: None Kenneth.Karwoski@nrc.gov (Karwoski, Kenneth)

Tracking Status: None Andrew.Johnson@nrc.gov (Johnson, Andrew)

Tracking Status: None Mark.Franke@nrc.gov (Franke, Mark)

Tracking Status: None fcmashburn@tva.gov ('fcmashburn@tva.gov')

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 28126 10/8/2009 Options Expiration Date:

Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: