05000259/FIN-2006002-02: Difference between revisions
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| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71153 | | Inspection procedure = IP 71153 | ||
| Inspector = C Stancil, E Christnot, R Monk, T Ross, A Nielsen, E Michel, F Ehrhardt, J Griffis, J Rivera, | | Inspector = C Stancil, E Christnot, R Monk, T Ross, A Nielsen, E Michel, F Ehrhardt, J Griffis, J Rivera-Ortiz, K Harper, R Hamilton, R Rodriguez, R Taylor, W Lewis, W Loo | ||
| CCA = N/A for ROP | | CCA = N/A for ROP | ||
| INPO aspect = | | INPO aspect = | ||
| description = A Severity Level IV non-cited violation (NCV) of 10 CFR 50.73(a)(2)(v)(D) and (vii)(D) was identified by the inspectors for the licensees failure to submit a licensee event report for a safety system functional failure of the Unit 2 residual heat removal pressure suppression chamber containment isolation valves. This issue was documented in the licensees corrective action program as Problem Evaluation Report 99193. In Section IV of the NRC Enforcement Policy, the significance of violations involving the failure to make required reports is not dispositioned using the Reactor Oversight Programs Significance Determination Process. The licensees failure to provide a written event report does potentially impact the NRC\'s ability to carry out its regulatory function. However, because this failure to report per 10 CFR 50.73 did not actually impede or influence regulatory action, and the condition that required reporting under 10 CFR 50.73 was previously determined to be of very low safety significance in inspection report 05000260/2005003, the NRC has characterized the significance of this reporting violation as a Severity Level IV in accordance with Section IV.A.3 and Supplement I of the NRC Enforcement Policy. | | description = A Severity Level IV non-cited violation (NCV) of 10 CFR 50.73(a)(2)(v)(D) and (vii)(D) was identified by the inspectors for the licensees failure to submit a licensee event report for a safety system functional failure of the Unit 2 residual heat removal pressure suppression chamber containment isolation valves. This issue was documented in the licensees corrective action program as Problem Evaluation Report 99193. In Section IV of the NRC Enforcement Policy, the significance of violations involving the failure to make required reports is not dispositioned using the Reactor Oversight Programs Significance Determination Process. The licensees failure to provide a written event report does potentially impact the NRC\'s ability to carry out its regulatory function. However, because this failure to report per 10 CFR 50.73 did not actually impede or influence regulatory action, and the condition that required reporting under 10 CFR 50.73 was previously determined to be of very low safety significance in inspection report 05000260/2005003, the NRC has characterized the significance of this reporting violation as a Severity Level IV in accordance with Section IV.A.3 and Supplement I of the NRC Enforcement Policy. | ||
}} | }} | ||
Revision as of 19:34, 20 February 2018
| Site: | Browns Ferry  |
|---|---|
| Report | IR 05000259/2006002 Section 4OA3 |
| Date counted | Mar 31, 2006 (2006Q1) |
| Type: | TEV: Severity level IV |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71153 |
| Inspectors (proximate) | C Stancil E Christnot R Monk T Ross A Nielsen E Michel F Ehrhardt J Griffis J Rivera-Ortiz K Harper R Hamilton R Rodriguez R Taylor W Lewis W Loo |
| INPO aspect | |
| ' | |