ML102910571
| ML102910571 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/09/2009 |
| From: | Herrin D Progress Energy Florida |
| To: | Masters A NRC/RGN-II/DCP/CPB1 |
| References | |
| FOIA/PA-2010-0116 | |
| Download: ML102910571 (11) | |
Text
Masters, Anthony From: Herrin, Dennis W. [Dennis.Herrin @pgnmail.com]
Sent: Monday, November 09, 2009 11:23 AM To: Masters, Anthony Cc: Portmann, Rick
Subject:
FW: NRC SIT Team Questions Attachments: !NRC Request,#44 Information.docx; !NRC Request #45 Information.docx; !NRC Request #
46 Information.docx; !NRC Request #47 Information.docx; !NRC Request #48 Information.docx; !NRC Request #51 Information.docx; !NRC Request #53 Information.docx;!
NRC Request #54 Information.docx; !NRC Request #56 Information.docx; !NRC Request #57 Information.docx Anthony - Input to questions from last week.
From: Portmann, Rick Sent: Monday, November 09, 2009 10:59 AM To: Herrin, Dennis W.
Cc: Dye, Linda F; Dyksterhouse, Don
Subject:
NRC SIT Team Questions Dennis - Attached you will find responses to for Request#'s 44-48, 51, 53-54, 56-57. I will update the NRC's folder with the attached. Thanks, Rick x-7846
Request #45, NRC SIT Question Information
- 45. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, indicates compliance with the 1992 addenda of the 1992 Edition of ASME Section Xl, Subsection IWL, while the document titled ASME Section XI/ASME OM Code Program, Interval 4: Containment Inspection Program (2 nd CISI) Revision 3 (Dated 5/6/09) indicates the 2001 Edition through the 2003 Addenda. Please clarity.
Response to the above question:
The last performance of the Tendon Surveillance under SP-182 was in 2007. The ASME Section Xl code of record during that time was the 1992 addenda of the 1992 Edition of ASME Section Xl, Subsection IWL. In accordance with 10CFR50.55a, licensees are required to update their ISI Programs to meet the requirements of ASME Section Xl once every 10 years or inspection interval. The 3rd inspection interval was completed on August 13, 2008 and the new interval ( 4 th) began on August 14, 2008. For the 4 th interval , the 2001 Edition through the 2003 Addenda is the code of record. The SP-182 will be revised to reflect the new code edition prior to its next required 5 year tendon surveillance.
Request #44, NRC SIT Question.Information
- 44. If Possible, I would like to speak with Mr. Bernard Komara and Mr. Marc LeBlanc as they were listed as the inspectors on two previous inspection reports that I have reviewed.
Response to the above question:
Mr. Marc LeBlanc (NIC Contractor Inspector) was here in refuel 15 (2007) and to my knowledge is not here for refuel 16. Mr. Bernard Komara (NIC Contractor Inspector)has returned to CR3 for refuel 16 and is working for the site QC Organization. The Supervisor for Mr. Komara is Jeff Bennett.. Please contact Jeff (x-3323) for Bernie's availability.
Request #46, NRC SIT Question Information
- 46. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, has some concrete inspection activities associated with it as part of the tendon surveillances. Are they documented and reported in separate documentation or are the VT-1C and VT-3C examinations credited for this (i.e. VT-07-111 and VT-07-289)? If not, I would like to review the additional documentation.
Response to the above question:
The visual examinations for the tendon surveillances are documented separately from the IWL concrete examinations. The last two tendon surveillances and the last two IWL examination reports have been supplied. See the Request #24, NRC SIT Question #18 folder for these examination reports.
Request #47, NRC SIT Question Information
- 47. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, Section 3.5.3.1 specifies requirements for calibration for all measuring devices. I would like to review a sample of those records also.
Response to the above question:
The tendon surveillance reports have the calibration records for the tendon testing equipment. The last two tendon surveillances reports have been supplied. See the Request #24, NRC SIT Question #18 folder for these examination reports.
Request #48, NRC SIT Question Information 48 SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, Section 3.6 specifies acceptance criteria. Section 3.6.2 states that "abnormal conditions determined as the result of a visual inspection of the exterior concrete surface of the containment shell be recorded and documented, and investigated by Engineering for possible degradation of the structure."
Also, "Cracks found in concrete adjacent to the tendons (within 2 feet of the bearing plate) having widths greater than 0.010 inch shall be recorded and reported to Engineering for evaluation and resolution. Any crack widths greater than 0.050 inch shall be cause for investigation by Engineering to determine the cause and if there ia any abnormal degradation of the structural integrity of the containment."
Photographs VT-07-289-8 and VT-07-289-11, which are associated with VT-1CReport VT 289, appear to show cracks within 2 feet of the bearing plate. Have these been documented and evaluated.
Response to the above question:
The SP-182 criteria specified applies to the anchorage and bearing plate inspections performed for the tendon surveillances. The reports discussed are from the ASME Section Xl IWL examinations performed.
The recording and acceptance criteria may differ as the performance requirements come from separate requirements. These particular indications described on R15 IWL Report VT-07-289 were included in NCR 256010 for evaluation.
Request #51, NRC SIT Question Information
- 51. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program. Enclosure 1 lists tendons in the 5 th and 7 th surveillance as 46H21, 46H28, etc...;
however, Enclosure 11 indicates that they are numbered as 64H21, 64H28, etc... I believe these are in fact the same tendons, but should the number not be consistent?
Response to the above question:
These are the same tendons. The first two digits of the horizontal tendon identification refer to the tendon series on the containment buttresses it spans (ie. Between buttresses 4 and 6 [46Hxx] is the same as between buttresses 6 and 4[64Hxx]). Over the years CR3 has not been consistent in the use of one versus the other. A spreadsheet has been provided showing the tendon identifications used over prior surveillances. [Note: the spreadsheet is not a controlled document, just an aid for review of previous surveillance documentation.]
Enclosed in the Request# 51 folder:
Spreadsheet: Tendon Identification History (#51).xls
Request #53, NRC SIT Question Information
- 53. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, Enclosure 11 lists original lift-off values. Are the values for the dome in this listing before or after the repair?
Response to the above question:
The values listed in SP-182, Enclosure 11 are following the 1976 delamination event repair of the Dome.
Request #48, NRC SIT Question Information 48 SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, Section 3.6 specifies acceptance criteria. Section 3.6.2 states that "abnormal conditions determined as the result of a visual inspection of the exterior concrete surface of the containment shell be recorded and documented, and investigated by Engineering for possible degradation of the structure."
Also, "Cracks found in concrete adjacent to the tendons (within 2 feet of the bearing plate) having widths greater than 0.010 inch shall be recorded and reported to Engineering for evaluation and resolution. Any crack widths greater than 0.050 inch shall be cause for investigation by Engineering to determine the cause and if there ia any abnormal degradation of the structural integrity of the containment."
Photographs VT-07-289-8 and VT-07-289-11, which are associated with VT-lCReport VT 289, appear to show cracks within 2 feet of the bearing plate. Have these been documented and evaluated.
Response to the above question:
The SP-182 criteria specified applies to the anchorage and bearing plate inspections performed for the tendon surveillances: The reports discussed are from the ASME Section XI IWL examinations performed.
The recording and acceptance criteria may differ as the performance requirements come from separate requirements. These particular indications described on R15 IWL Report VT-07-289 were included in NCR 256010 for evaluation.
Request #54, NRC SIT Question Information
- 54. I have reviewed some inspection reports for the IWL inspections for the shell, but would like to review some reports and evaluations for inspections on the dome.
Response to the above question:
The last two IWL examination reports for 2001 (R12 and 2007 (R15) have been supplied and include examination of the dome. See the Request #24, NRC SIT Question #18 folder for these examination reports.
Request #56, NRC SIT Question Information
- 56. VT-07-111 and 289, Item #11 indicate that spalls were due to some embedded cables near boxes (shown in photographs VT-07-289-6 and VT-07-289-15). What were these cables?
Response to the above question:
It is believed that these cables and boxes are abandoned remnants from the testing equipment utilized during the original Structural Integrity Test in 1976. (stress & strain gages etc.)