05000335/FIN-2015010-01: Difference between revisions
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| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71003 | | Inspection procedure = IP 71003 | ||
| Inspector = A Butcavage, B Collins, J Rivera | | Inspector = A Butcavage, B Collins, J Rivera-Ortiz, P Cooper, R Carrion, S Walker | ||
| CCA = N/A for ROP | | CCA = N/A for ROP | ||
| INPO aspect = | | INPO aspect = | ||
| description = The inspectors identified a URI associated with the implementation status of various commitments and AMPs. Description: The inspectors identified that there were pending actions for various regulatory commitments/AMPs as a result of commitment changes implemented by the licensee after the renewed operating license was issued. The licensee informed the NRC of such changes, and submitted correspondence to the NRC for review and approval. At the time of this inspection, the NRC was still in the process of reviewing the licensees submittals. While the licensee met its commitment to submit the proposed changes to the NRC prior to the PEO, the inspectors were unable to determine whether the licensees implementation of the affected AMPs was consistent with the staffs final position, which will be provided through the issuance of SERs. The affected commitment items, and their respective pending actions, are summarized below. Commitment 1, Condensate Storage Tank Cross-Connect Buried Piping Inspection On May 12, 2015, the licensee informed the NRC of a commitment change based on the as-found configuration of the cross-tie line after excavation. On September 1, 2015, the NRC issued a Request for Additional information, for which the licensee provided responses in letter L2015-258, dated October 6, 2015. At the time of this inspection the NRC was reviewing the licensees response to the Request for Additional Information, and no SER had yet been issued. Commitments 4 and 5, Reactor Vessel Internals Inspection Program As described in the inspection scope section of this report, the licensee submitted several letters to the NRC after the renewed operating license was issued describing the proposed program to manage the aging effects of the reactor vessel internals. At the time of this inspection, the NRC was reviewing the licensees submittals and no final SER had yet been issued. Commitment 6, Small Bore Class 1 Piping Inspection Program On May 11, 2015, the licensee submitted a revision to the previously approved Small Bore Class 1 Piping Inspection Program for NRC review and approval. The revision was related to the use of destructive examinations in lieu of volumetric examinations. At the time of this inspection, the NRC was reviewing the licensees submittal and no final SER had yet been issued. Commitment 20, Environmentally-Assisted Fatigue of the Pressurizer Surge Line On October 29, 2015, the licensee submitted its proposed program for managing environmentally-assisted fatigue of the pressurizer surge line to the NRC. The inspectors noted that the proposal detailed the licensees intent to utilize the ASME BPVC, Section XI ISI Program (UFSAR Section 18.2.2) to manage the recurring inspections, and the associated evaluations for any flaws noted. At the time of this inspection, the NRC was reviewing the licensees submittal and no SER had yet been issued. In addition to the commitment changes under NRC review, the inspectors identified a followup item for Commitment 17, Reactor Vessel Integrity Program. The inspectors noted that the licensee credited fleet procedure ER-AA-110 to meet the regulatory commitment associated with the integration of all four reactor vessel integrity subprograms into a single program document. Fleet procedure ER-AA-110 requires a plant-specific procedure be developed for each site describing the important parameters needed to meet the regulatory requirements specific to that station. The inspectors noted that the plant-specific procedure for Unit 1, procedure ADM 17.38, was still under development with a target completion date of March 1, 2016. Therefore, the inspectors concluded that there still were pending actions associated with the development of the site-specific program, and additional inspection was required to verify that the Reactor Vessel Integrity Program was implemented as intended. The licensee initiated AR 02094578 to enter this item in the CAP. The inspectors determined that it was necessary to open a URI to further review the implementation of the commitments/AMPs, and verify that the commitments were met as approved by the NRC in the final SERs. This issue requires followup inspection, and will be tracked as URI 05000335/2015010-001, Implementation of Commitments and Aging Management Programs. | | description = The inspectors identified a URI associated with the implementation status of various commitments and AMPs. Description: The inspectors identified that there were pending actions for various regulatory commitments/AMPs as a result of commitment changes implemented by the licensee after the renewed operating license was issued. The licensee informed the NRC of such changes, and submitted correspondence to the NRC for review and approval. At the time of this inspection, the NRC was still in the process of reviewing the licensees submittals. While the licensee met its commitment to submit the proposed changes to the NRC prior to the PEO, the inspectors were unable to determine whether the licensees implementation of the affected AMPs was consistent with the staffs final position, which will be provided through the issuance of SERs. The affected commitment items, and their respective pending actions, are summarized below. Commitment 1, Condensate Storage Tank Cross-Connect Buried Piping Inspection On May 12, 2015, the licensee informed the NRC of a commitment change based on the as-found configuration of the cross-tie line after excavation. On September 1, 2015, the NRC issued a Request for Additional information, for which the licensee provided responses in letter L2015-258, dated October 6, 2015. At the time of this inspection the NRC was reviewing the licensees response to the Request for Additional Information, and no SER had yet been issued. Commitments 4 and 5, Reactor Vessel Internals Inspection Program As described in the inspection scope section of this report, the licensee submitted several letters to the NRC after the renewed operating license was issued describing the proposed program to manage the aging effects of the reactor vessel internals. At the time of this inspection, the NRC was reviewing the licensees submittals and no final SER had yet been issued. Commitment 6, Small Bore Class 1 Piping Inspection Program On May 11, 2015, the licensee submitted a revision to the previously approved Small Bore Class 1 Piping Inspection Program for NRC review and approval. The revision was related to the use of destructive examinations in lieu of volumetric examinations. At the time of this inspection, the NRC was reviewing the licensees submittal and no final SER had yet been issued. Commitment 20, Environmentally-Assisted Fatigue of the Pressurizer Surge Line On October 29, 2015, the licensee submitted its proposed program for managing environmentally-assisted fatigue of the pressurizer surge line to the NRC. The inspectors noted that the proposal detailed the licensees intent to utilize the ASME BPVC, Section XI ISI Program (UFSAR Section 18.2.2) to manage the recurring inspections, and the associated evaluations for any flaws noted. At the time of this inspection, the NRC was reviewing the licensees submittal and no SER had yet been issued. In addition to the commitment changes under NRC review, the inspectors identified a followup item for Commitment 17, Reactor Vessel Integrity Program. The inspectors noted that the licensee credited fleet procedure ER-AA-110 to meet the regulatory commitment associated with the integration of all four reactor vessel integrity subprograms into a single program document. Fleet procedure ER-AA-110 requires a plant-specific procedure be developed for each site describing the important parameters needed to meet the regulatory requirements specific to that station. The inspectors noted that the plant-specific procedure for Unit 1, procedure ADM 17.38, was still under development with a target completion date of March 1, 2016. Therefore, the inspectors concluded that there still were pending actions associated with the development of the site-specific program, and additional inspection was required to verify that the Reactor Vessel Integrity Program was implemented as intended. The licensee initiated AR 02094578 to enter this item in the CAP. The inspectors determined that it was necessary to open a URI to further review the implementation of the commitments/AMPs, and verify that the commitments were met as approved by the NRC in the final SERs. This issue requires followup inspection, and will be tracked as URI 05000335/2015010-001, Implementation of Commitments and Aging Management Programs. | ||
}} | }} | ||
Latest revision as of 20:54, 20 February 2018
| Site: | Saint Lucie  |
|---|---|
| Report | IR 05000335/2015010 Section 4OA5 |
| Date counted | Dec 31, 2015 (2015Q4) |
| Type: | URI: |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71003 |
| Inspectors (proximate) | A Butcavage B Collins J Rivera-Ortiz P Cooper R Carrion S Walker |
| INPO aspect | |
| ' | |