ML073310576

E-mail from Mahesh Chawla to Bdotson@Entergy.Com 2006 SG Tube Inspections

ML073310576
Person / Time
Site:	Palisades
Issue date:	09/24/2007
From:	Chawla M L NRC/NRR/ADRO/DORL/LPLIII-1
To:	Dotson B E Entergy Nuclear Operations
Chawla, ML, NRR/DLPM/LPD III-2, 415-8371
References
Download: ML073310576 (3)

Text

From: Mahesh Chawla To: bdotson@entergy.com; llahti@entergy.com Date: 09/24/2007 10:52:58 AM

Subject:

2006 SG Tube Inspections By letters dated April 26, 2006 (ML061160510), April 11, 2007 (ML071090247),

and June 19, 2007 (ML071780216), Entergy Nuclear Operations, Inc. (the licensee)

submitted information pertaining to their 2006 steam generator (SG) tube

inspections at the Palisades Nuclear Plant. The U.S. Nuclear Regulatory

Commission (NRC) staff summarized three conference calls held with the

licensee, concerning the 2006 SG tube inspections, in a letter dated September

22, 2006 (ML062560069). In order to complete its review of the documents

listed above, the staff needs the following additional information:

1. You indicated that the location, orientation, and measured sizes of

service-induced indications were included in Tables 4A, 4B, and 4C. These

tables do not appear to contain all service-induced indications, since none of

the wear indications listed in Table 6 are included in these tables. Please

clarify. Please provide the sizes for the wear indications in Tables 4B and

4C (since presumably they were sized and are less than 40% throughwall).

2. In Table 3, you highlighted various degradation mechanisms for which you

inspected. Please clarify this table. In particular, discuss whether you

consider dents and dings greater than five volts susceptible to axial and

circumferential primary water stress corrosion cracking and outside diameter

stress corrosion cracking (ODSCC).

3. Please provide the scope and results of any secondary side inspections

(including foreign object search and retrieval) performed during

the 2006 outage.

4. Please clarify Table 6 and the discussion on in-situ pressure testing.

Table 6 does not appear to address the results of condition monitoring, but

the discussion on in-situ pressure testing does appear to address some of the

results of the condition monitoring assessment. With respect to condition

monitoring, please address the following:

a. Please discuss whether a bladder was used at the location of the flaw

during the in-situ pressure testing.

b. Please confirm that none of the structural integrity performance

criteria contained within the Technical Specifications were exceeded (e.g.,

factor of 1.2 on combined primary loads).

c. Please confirm that you satisfied the accident-induced leakage

performance criterion and please provide the leak rate you calculated during

this assessment, making sure to include leakage from all sources (e.g.,

plugs).

5. Clarify the entries in Table 4A since several of the freespan

indications seem to be below the top of the tubesheet and some of the eggcrate

indications appear to be in the freespan.

6. Clarify the number of axial ODSCC indications in the freespan and eggcrate locations. Table 5 indicates two indications are at eggcrates and one indication is in the freespan; however, Table 6

only lists one indication at an eggcrate (R71C84) and two indications

in the freespan (R133C90 and R80C131).

CC: Allen Hiser; Andrew Johnson; Kenneth Karwoski

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Subject:

2006 SG Tube Inspections Creation Date 09/24/2007 10:52:58 AM From: Mahesh Chawla Created By: MLC@nrc.gov Recipients Action Date & Time entergy.com Transferred 09/24/2007 10:53:14 AM bdotson (bdotson@entergy.com) llahti (llahti@entergy.com)

nrc.gov OWGWPO04.HQGWDO01 Delivered 09/24/2007 10:53:06

AM ABJ1 CC (Andrew Johnson) Opened 09/24/2007 11:11:50

AM ALH1 CC (Allen Hiser) Opened 09/24/2007 11:09:53

AM KJK1 CC (Kenneth Karwoski) Opened 09/24/2007 11:16:31

AM Post Office Delivered Route entergy.com OWGWPO04.HQGWDO01 09/24/2007 10:53:06 AM nrc.gov

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