05000424/FIN-2012005-02: Difference between revisions
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{{finding | {{finding | ||
| title = Unauthorized Entry Into | | title = Unauthorized Entry Into a High Radiation Area | ||
| docket = 05000424, 05000425 | | docket = 05000424, 05000425 | ||
| inspection report = IR 05000424/2012005 | | inspection report = IR 05000424/2012005 | ||
Line 12: | Line 12: | ||
| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71124.01 | | Inspection procedure = IP 71124.01 | ||
| Inspector = A Nielsen, F Ehrhardt, A Vargas | | Inspector = A Nielsen, F Ehrhardt, A Vargas-Mendez, J Laughlin, M Cain, B Caballero, T Chandler, R Williams, C Dykes, W Pursley | ||
| CCA = H.8 | | CCA = H.8 | ||
| INPO aspect = WP.4 | | INPO aspect = WP.4 | ||
| description = The inspectors identified a Green, self-revealing, Non-cited Violation of technical specification 5.7.1, High Radiation Area, for an unauthorized entry into a High Radiation Area (HRA). A maintenance worker entered a HRA in Unit 1 containment without being briefed on the radiological conditions. The licensee entered this issue into their corrective action program as CR 523976 and took immediate corrective actions including an outage work crew stand down. This finding was more than minor because it was associated with the occupational radiation safety cornerstone attribute of human performance and adversely affects the cornerstone objective of ensuring adequate protection of worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation. The finding was evaluated using the occupational radiation safety significance determination process. The finding was not related to As Low As Reasonably Achievable (ALARA) planning, nor did it involve an overexposure or substantial potential for overexposure, and the ability to assess dose was not compromised. Therefore, the finding was determined to be of very low safety significance (Green). This finding involved the cross-cutting aspect of human performance, work practices [H.4.b] because the HRA event was a direct result of poor communications during the pre-job briefing and a lack of procedure adherence on the part of the maintenance worker. The licensee entered this issue into the Corrective Action Program (CAP) as CR 523976. | | description = The inspectors identified a Green, self-revealing, Non-cited Violation of technical specification 5.7.1, High Radiation Area, for an unauthorized entry into a High Radiation Area (HRA). A maintenance worker entered a HRA in Unit 1 containment without being briefed on the radiological conditions. The licensee entered this issue into their corrective action program as CR 523976 and took immediate corrective actions including an outage work crew stand down. This finding was more than minor because it was associated with the occupational radiation safety cornerstone attribute of human performance and adversely affects the cornerstone objective of ensuring adequate protection of worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation. The finding was evaluated using the occupational radiation safety significance determination process. The finding was not related to As Low As Reasonably Achievable (ALARA) planning, nor did it involve an overexposure or substantial potential for overexposure, and the ability to assess dose was not compromised. Therefore, the finding was determined to be of very low safety significance (Green). This finding involved the cross-cutting aspect of human performance, work practices [H.4.b] because the HRA event was a direct result of poor communications during the pre-job briefing and a lack of procedure adherence on the part of the maintenance worker. The licensee entered this issue into the Corrective Action Program (CAP) as CR 523976. | ||
}} | }} |
Latest revision as of 19:46, 20 February 2018
Site: | Vogtle |
---|---|
Report | IR 05000424/2012005 Section 2RS1 |
Date counted | Dec 31, 2012 (2012Q4) |
Type: | NCV: Green |
cornerstone | Or Safety |
Identified by: | NRC identified |
Inspection Procedure: | IP 71124.01 |
Inspectors (proximate) | A Nielsen F Ehrhardt A Vargas-Mendez J Laughlin M Cain B Caballero T Chandler R Williams C Dykes W Pursley |
CCA | H.8, Procedure Adherence |
INPO aspect | WP.4 |
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