05000395/FIN-2012005-03: Difference between revisions
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{{finding | {{finding | ||
| title = Reactor Vessel Supports Not Included | | title = Reactor Vessel Supports Not Included in the Licensee\\\'S ASME Section Xi ISI Program | ||
| docket = 05000395 | | docket = 05000395 | ||
| inspection report = IR 05000395/2012005 | | inspection report = IR 05000395/2012005 | ||
| Line 12: | Line 12: | ||
| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71111.08 | | Inspection procedure = IP 71111.08 | ||
| Inspector = E Coffman, E Lea, G Mccoy, J Laughlin, J Reece, M Coursey, R Hamilton, R Williamsj, | | Inspector = E Coffman, E Lea, G Mccoy, J Laughlin, J Reece, M Coursey, R Hamilton, R Williamsj, Reeceg Mccoy, M Coursey, C Fletcher, E Coffman, R Williams | ||
| CCA = N/A for ROP | | CCA = N/A for ROP | ||
| INPO aspect = | | INPO aspect = | ||
| description = The inspectors indentified an URI concerning the reactor vessel supports not being included in the licensees ASME Section XI ISI Program. Description: The inspectors identified that the scope of the V. C. Summer Unit 1 ISI program may not meet the requirements of 10 CFR 50.55a which requires that in-service inspections be conducted in accordance with the requirements of ASME Code, Section XI, Rules for In-service Inspection of Nuclear Power Plant Components. The V. C. Summer plant is currently in the third inspection interval and is required to meet the requirements of the 1998 Edition of the ASME Section XI Code, with addenda through 2000, as modified by 10 CFR 50.55a. The inspectors identified that the nuclear Class 1 reactor pressure vessel supports were not included in the scope of the V. C. Summer Unit 1 ISI Program for the third inspection interval. In accordance with the requirements of Section XI, Subsection IWB, the attachment weld associated with the RPV supports is required to be subjected to a surface examination, and in accordance with Subsection IWF, the RPV supports are required to be VT-3 visually examined. The V. C. Summer RPV is supported, in part, by six supports that are made up of a buildup of welded metal attached to the pressure boundary. The function of the reactor support assembly is to provide support to the reactor vessel and attached piping and to allow for thermal movement of the piping during normal and accident conditions, thereby ensuring the reactor pressure boundary and reactor coolant system boundary can perform their intended safety function of providing the second barrier to fission product release. The ISI program required by 10 CFR 50.55a, and the periodic examinations required by Section XI identified above, provides reasonable assurance that these supports can continue to perform their portion of the intended safety function. This issue remains unresolved as the licensee asserts that the integrally welded attachment of the nozzle that rests upon the support is excluded from examination per ASME Section XI, Table IWB-2500-1, Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps, and Valves, Note 1. Additionally, the licensee asserts that the reactor vessel supports are exempt from examination in accordance with ASME Section XI Subsection IWF-1230 due to inaccessibility. The inspectors have requested the following in order to evaluate this condition more fully in order to close this URI: Calculation of the loading on the welded attachment or support to ensure the welded attachment meets the exclusion of Note 1 for Table IWB-2500-1, Exam Category B-K. A construction drawing or QA records of the configuration of the weld buildup for the integral attachments. This information will be used to determine if the welded attachment does not meet the exclusion requirements of ASME Section XI, Table IWB-2500-1, Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps, and Valves, Note 1. The licensees written technical justification for calling the Reactor Vessel supports inaccessible IAW Section XI IWF-1230. This information is expected to be received and evaluated beyond the required time period of this report. This issue is identified as URI 05000395/2012005-03, Reactor Vessel Supports Not Included in the Licensees ASME Section XI ISI Program | | description = The inspectors indentified an URI concerning the reactor vessel supports not being included in the licensees ASME Section XI ISI Program. Description: The inspectors identified that the scope of the V. C. Summer Unit 1 ISI program may not meet the requirements of 10 CFR 50.55a which requires that in-service inspections be conducted in accordance with the requirements of ASME Code, Section XI, Rules for In-service Inspection of Nuclear Power Plant Components. The V. C. Summer plant is currently in the third inspection interval and is required to meet the requirements of the 1998 Edition of the ASME Section XI Code, with addenda through 2000, as modified by 10 CFR 50.55a. The inspectors identified that the nuclear Class 1 reactor pressure vessel supports were not included in the scope of the V. C. Summer Unit 1 ISI Program for the third inspection interval. In accordance with the requirements of Section XI, Subsection IWB, the attachment weld associated with the RPV supports is required to be subjected to a surface examination, and in accordance with Subsection IWF, the RPV supports are required to be VT-3 visually examined. The V. C. Summer RPV is supported, in part, by six supports that are made up of a buildup of welded metal attached to the pressure boundary. The function of the reactor support assembly is to provide support to the reactor vessel and attached piping and to allow for thermal movement of the piping during normal and accident conditions, thereby ensuring the reactor pressure boundary and reactor coolant system boundary can perform their intended safety function of providing the second barrier to fission product release. The ISI program required by 10 CFR 50.55a, and the periodic examinations required by Section XI identified above, provides reasonable assurance that these supports can continue to perform their portion of the intended safety function. This issue remains unresolved as the licensee asserts that the integrally welded attachment of the nozzle that rests upon the support is excluded from examination per ASME Section XI, Table IWB-2500-1, Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps, and Valves, Note 1. Additionally, the licensee asserts that the reactor vessel supports are exempt from examination in accordance with ASME Section XI Subsection IWF-1230 due to inaccessibility. The inspectors have requested the following in order to evaluate this condition more fully in order to close this URI: Calculation of the loading on the welded attachment or support to ensure the welded attachment meets the exclusion of Note 1 for Table IWB-2500-1, Exam Category B-K. A construction drawing or QA records of the configuration of the weld buildup for the integral attachments. This information will be used to determine if the welded attachment does not meet the exclusion requirements of ASME Section XI, Table IWB-2500-1, Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps, and Valves, Note 1. The licensees written technical justification for calling the Reactor Vessel supports inaccessible IAW Section XI IWF-1230. This information is expected to be received and evaluated beyond the required time period of this report. This issue is identified as URI 05000395/2012005-03, Reactor Vessel Supports Not Included in the Licensees ASME Section XI ISI Program | ||
}} | }} | ||
Latest revision as of 19:46, 20 February 2018
| Site: | Summer  |
|---|---|
| Report | IR 05000395/2012005 Section 1R08 |
| Date counted | Dec 31, 2012 (2012Q4) |
| Type: | URI: |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.08 |
| Inspectors (proximate) | E Coffman E Lea G Mccoy J Laughlin J Reece M Coursey R Hamilton R Williamsj Reeceg Mccoy M Coursey C Fletcher E Coffman R Williams |
| INPO aspect | |
| ' | |