05000298/FIN-2015003-02: Difference between revisions
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| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71124.05 | | Inspection procedure = IP 71124.05 | ||
| Inspector = C Henderson, D Reinert, G Warnick, J Braisted, J Nance, J O, | | Inspector = C Henderson, D Reinert, G Warnick, J Braisted, J Nance, J O'Donnell, L Carson, M Hayes, M Phalen, P Elkmann, P Hernandez | ||
| CCA = P.1 | | CCA = P.1 | ||
| INPO aspect = PI.1 | | INPO aspect = PI.1 | ||
| description = The inspectors identified a non-cited violation of 10 CFR 20.1501(c) for the failure to ensure measurement conditions were consistent with instrument calibration parameters for the elevated release point monitor, compromising the ability to accurately determine the concentration of radioactive effluents released. Specifically, water intrusion/condensation in the elevated release point Kaman normal range effluent monitor noble gas sample chamber introduced discrepancies relative to the calibration geometry and water in the particulate filter and iodine cartridge adversely affected the sample media collection efficiencies. Immediate corrective actions included the licensee performing a functionality assessment of the monitor. The licensee entered this deficiency into the corrective action program as Condition Reports CR-CNS-2015-05051 and CR-CNS-2015-05067. The failure to ensure measurement conditions were consistent with instrument calibration parameters for the elevated release point monitor was a performance deficiency. The performance deficiency was more than minor, and therefore a finding, because it was associated with the Public Radiation Safety Cornerstone attribute of plant equipment/process radiation monitoring and adversely affected the cornerstone objective of ensuring adequate protection of public health and safety from exposure to radioactive materials released into the public domain as a result of routine civilian nuclear reactor operation. The inspectors used IMC 0609, Significance Determination Process, Attachment D, Public Radiation Safety Significance Determination Process, February 12, 2008, and determined the finding to be of very low safety significance (Green) because it was associated with the effluent program; however, it was not a substantial failure to implement the effluents program and it did not result in a public dose greater than an Appendix I criterion or 10 CFR 20.1301(e). The finding has a cross-cutting aspect in the area of problem identification and resolution associated with identification, because the organization failed to implement the corrective action program with a low threshold for identifying issues. Specifically, plant personnel failed to initiate condition reports, as required by procedure, on 89 occasions since the discovery on March 24, 2015 [P.1]. | | description = The inspectors identified a non-cited violation of 10 CFR 20.1501(c) for the failure to ensure measurement conditions were consistent with instrument calibration parameters for the elevated release point monitor, compromising the ability to accurately determine the concentration of radioactive effluents released. Specifically, water intrusion/condensation in the elevated release point Kaman normal range effluent monitor noble gas sample chamber introduced discrepancies relative to the calibration geometry and water in the particulate filter and iodine cartridge adversely affected the sample media collection efficiencies. Immediate corrective actions included the licensee performing a functionality assessment of the monitor. The licensee entered this deficiency into the corrective action program as Condition Reports CR-CNS-2015-05051 and CR-CNS-2015-05067. The failure to ensure measurement conditions were consistent with instrument calibration parameters for the elevated release point monitor was a performance deficiency. The performance deficiency was more than minor, and therefore a finding, because it was associated with the Public Radiation Safety Cornerstone attribute of plant equipment/process radiation monitoring and adversely affected the cornerstone objective of ensuring adequate protection of public health and safety from exposure to radioactive materials released into the public domain as a result of routine civilian nuclear reactor operation. The inspectors used IMC 0609, Significance Determination Process, Attachment D, Public Radiation Safety Significance Determination Process, February 12, 2008, and determined the finding to be of very low safety significance (Green) because it was associated with the effluent program; however, it was not a substantial failure to implement the effluents program and it did not result in a public dose greater than an Appendix I criterion or 10 CFR 20.1301(e). The finding has a cross-cutting aspect in the area of problem identification and resolution associated with identification, because the organization failed to implement the corrective action program with a low threshold for identifying issues. Specifically, plant personnel failed to initiate condition reports, as required by procedure, on 89 occasions since the discovery on March 24, 2015 [P.1]. | ||
}} | }} | ||
Latest revision as of 00:22, 22 February 2018
| Site: | Cooper  |
|---|---|
| Report | IR 05000298/2015003 Section 2RS5 |
| Date counted | Sep 30, 2015 (2015Q3) |
| Type: | NCV: Green |
| cornerstone | Pr Safety |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71124.05 |
| Inspectors (proximate) | C Henderson D Reinert G Warnick J Braisted J Nance J O'Donnell L Carson M Hayes M Phalen P Elkmann P Hernandez |
| Violation of: | 10 CFR 20.1301, Radiation Dose Limits for Individual Members of the Public 10 CFR 20.1501, Surveys and Monitoring |
| CCA | P.1, Identification |
| INPO aspect | PI.1 |
| ' | |