ML073310576: Difference between revisions
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{{#Wiki_filter:From: | {{#Wiki_filter:From: Mahesh Chawla To: bdotson@entergy.com; llahti@entergy.com Date: 09/24/2007 10:52:58 AM | ||
==Subject:== | ==Subject:== | ||
2006 SG Tube Inspections By letters dated April 26, 2006 (ML061160510), April 11, 2007 (ML071090247), | 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) | 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). | |||
submitted information pertaining to their 2006 steam generator (SG) tube | : 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. | |||
inspections at the Palisades Nuclear Plant. The U.S. Nuclear Regulatory | : 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: | |||
Commission (NRC) staff summarized three conference calls held with the | : 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., | |||
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). | factor of 1.2 on combined primary loads). | ||
: c. Please confirm that you satisfied the accident-induced leakage | : 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. | |||
performance criterion and please provide the leak rate you calculated during | : 6. Clarify the number of axial ODSCC indications in the freespan and | ||
this assessment, making sure to include leakage from all sources (e.g., | |||
plugs). | |||
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 | |||
in the freespan (R133C90 and R80C131). | 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 Mail Envelope Properties (46F7CF4A.823 : 2 : 35476) | |||
CC: Allen Hiser; | |||
Mail Envelope Properties (46F7CF4A.823 : 2 : 35476) | |||
==Subject:== | ==Subject:== | ||
2006 SG Tube Inspections Creation Date 09/24/2007 10:52:58 AM From: | 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 Files Size Date & Time MESSAGE 4023 09/24/2007 10:52:58 AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None | ||
Concealed | |||
==Subject:== | ==Subject:== | ||
No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened}} | |||
No | |||
Standard | |||
Latest revision as of 00:20, 23 November 2019
| ML073310576 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/24/2007 |
| From: | Mahesh Chawla NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Dotson B 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 Mail Envelope Properties (46F7CF4A.823 : 2 : 35476)
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 Files Size Date & Time MESSAGE 4023 09/24/2007 10:52:58 AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None
Concealed
Subject:
No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened