05000275/FIN-2012004-01: Difference between revisions
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{{finding | {{finding | ||
| title = Inadequate Corrective Actions | | title = Inadequate Corrective Actions to Update the Final Safety Analysis Report Update with Required Information | ||
| docket = 05000275, 05000323 | | docket = 05000275, 05000323 | ||
| inspection report = IR 05000275/2012004 | | inspection report = IR 05000275/2012004 | ||
| Line 12: | Line 12: | ||
| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71111.18 | | Inspection procedure = IP 71111.18 | ||
| Inspector = D Overland, G Kuzo, J Laughlin, J O,' | | Inspector = D Overland, G Kuzo, J Laughlin, J O, 'Donnelll Carlson, L Micewski, L Ricketson, M Brooks, M Peck, N O, 'Keef | ||
| CCA = H.14 | | CCA = H.14 | ||
| INPO aspect = DM.2 | | INPO aspect = DM.2 | ||
| description = The inspectors identified a cited violation of 10 CFR Part 50.71(e), Maintenance of Records, Making of Reports, for failing to update the Final Safety Analysis Report. Specifically, the licensee failed to update the Final Safety Analysis Report to include the information describing the extent to which plant structures, systems, and components met 10 CFR 50, Appendix A, or describing and justifying exceptions to those General Design Criteria. This failure to update the Final Safety Analysis Report was previously identified as a non-cited violation in NRCs Diablo Canyon Power Plant Integrated Inspection Report 05000275/2009003 and 05000323/2009003. The licensee entered the condition into the corrective action program as Notification 50513243. The failure to correct missing information that was required to be in the Final Safety Analysis Report Update was a performance deficiency. The inspectors concluded that the finding is more than minor because, if left uncorrected, this could lead to a more significant safety concern because future changes to the facility, procedures, and programs would not be able to consider the licensing basis information that was removed or never inserted. The finding was screened using Manual Chapter 0609, Significance Determination Process. The inspectors concluded that the finding was of very low safety significance (Green) because while the finding was a deficiency affecting design or qualification of a mitigating system, it did not result in the loss of operability or functionality of a system. The finding also affected the NRCs ability to perform its regulatory function and was evaluated using the traditional enforcement process. The finding was determined to be Severity Level IV because the required information was not used to make an unacceptable change to the facility or procedures, which was consistent with the determination that the issue had very low safety significance. The inspectors concluded that this finding had a crosscutting aspect in the area of human performance associated with the decision making component because the licensee did not use conservative assumptions in decision making and did not adopt a requirement to demonstrate that the proposed action is safe in order to proceed | | description = The inspectors identified a cited violation of 10 CFR Part 50.71(e), Maintenance of Records, Making of Reports, for failing to update the Final Safety Analysis Report. Specifically, the licensee failed to update the Final Safety Analysis Report to include the information describing the extent to which plant structures, systems, and components met 10 CFR 50, Appendix A, or describing and justifying exceptions to those General Design Criteria. This failure to update the Final Safety Analysis Report was previously identified as a non-cited violation in NRCs Diablo Canyon Power Plant Integrated Inspection Report 05000275/2009003 and 05000323/2009003. The licensee entered the condition into the corrective action program as Notification 50513243. The failure to correct missing information that was required to be in the Final Safety Analysis Report Update was a performance deficiency. The inspectors concluded that the finding is more than minor because, if left uncorrected, this could lead to a more significant safety concern because future changes to the facility, procedures, and programs would not be able to consider the licensing basis information that was removed or never inserted. The finding was screened using Manual Chapter 0609, Significance Determination Process. The inspectors concluded that the finding was of very low safety significance (Green) because while the finding was a deficiency affecting design or qualification of a mitigating system, it did not result in the loss of operability or functionality of a system. The finding also affected the NRCs ability to perform its regulatory function and was evaluated using the traditional enforcement process. The finding was determined to be Severity Level IV because the required information was not used to make an unacceptable change to the facility or procedures, which was consistent with the determination that the issue had very low safety significance. The inspectors concluded that this finding had a crosscutting aspect in the area of human performance associated with the decision making component because the licensee did not use conservative assumptions in decision making and did not adopt a requirement to demonstrate that the proposed action is safe in order to proceed | ||
}} | }} | ||
Revision as of 19:46, 20 February 2018
| Site: | Diablo Canyon  |
|---|---|
| Report | IR 05000275/2012004 Section 1R18 |
| Date counted | Sep 30, 2012 (2012Q3) |
| Type: | Violation: Green |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.18 |
| Inspectors (proximate) | D Overland G Kuzo J Laughlin J O 'Donnelll Carlson L Micewski L Ricketson M Brooks M Peck N O 'Keef |
| CCA | H.14, Conservative Bias |
| INPO aspect | DM.2 |
| ' | |