05000454/FIN-2012005-03: Difference between revisions
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| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71151 | | Inspection procedure = IP 71151 | ||
| Inspector = A Shaikh, B Bartlett, C Moore, C Sanders, C St,. | | Inspector = A Shaikh, B Bartlett, C Moore, C Sanders, C St, . Petersc Thompson, E Sanchez, J Gilliam, J Laughlin, J Robbins, N Feliz Adorno, R Ng, R Walton, T Daun, T Go | ||
| CCA = N/A for ROP | | CCA = N/A for ROP | ||
| INPO aspect = | | INPO aspect = | ||
| description = The inspectors identified a Severity Level IV NCV of 10 CFR 50.73(a)(2)(v) when licensee personnel failed to report a condition that resulted in a loss of safety function when both containment area radiation monitors were declared inoperable. Specifically, on May 24, 2011, the licensee identified that when reducing reactor power with the isolation setpoints for containment area radiation monitors 1/2AR11J and 1/2AR12J constant and background radiation levels decreasing, the TS setpoint limit for containment area radiation monitors were exceeded and could have prevented the fulfillment of a safety function to automatically isolate containment. The inspectors determined that although this condition represented a loss of safety function in accordance with the 10 CFR 50.73 reporting requirements and NUREG-1022, Event Reporting Guidelines: 10 CFR 50.72 and 10 CFR 50.73, Revision 2, the condition was not reported as required. This issue was entered into the licensees CAP as IR 1463675. Corrective actions included an action to report this event in accordance with NRC requirements. The inspectors determined that the failure to submit a Licensee Event Report (LER) required by 10 CFR 50.73 for a loss of safety function after both containment area radiation monitors were declared inoperable was a performance deficiency. This violation had the potential to impact the regulatory process based, in part, on the generic communications that 10 CFR 50.72 and 10 CFR 50.73 reports serve, the required Reactor Oversight Process (ROP) inspection reviews that the NRC performs on all LERs, and the potential impact on licensee performance assessment. The inspectors determined that this issue was a Severity Level IV violation based on Example 9, The licensee fails to make a report required by 10 CFR 50.72 or 10 CFR 50.73, and Example 10, A failure to identify all applicable reporting codes on a Licensee Event Report that may impact the completeness or accuracy of other information (e.g., performance indicator data) submitted to the NRC, discussed in Section 6.9 of the NRC Enforcement Policy. Because cross-cutting aspects do not apply to traditional enforcement issues, no cross-cutting aspect was assigned to this Severity Level IV violation. | | description = The inspectors identified a Severity Level IV NCV of 10 CFR 50.73(a)(2)(v) when licensee personnel failed to report a condition that resulted in a loss of safety function when both containment area radiation monitors were declared inoperable. Specifically, on May 24, 2011, the licensee identified that when reducing reactor power with the isolation setpoints for containment area radiation monitors 1/2AR11J and 1/2AR12J constant and background radiation levels decreasing, the TS setpoint limit for containment area radiation monitors were exceeded and could have prevented the fulfillment of a safety function to automatically isolate containment. The inspectors determined that although this condition represented a loss of safety function in accordance with the 10 CFR 50.73 reporting requirements and NUREG-1022, Event Reporting Guidelines: 10 CFR 50.72 and 10 CFR 50.73, Revision 2, the condition was not reported as required. This issue was entered into the licensees CAP as IR 1463675. Corrective actions included an action to report this event in accordance with NRC requirements. The inspectors determined that the failure to submit a Licensee Event Report (LER) required by 10 CFR 50.73 for a loss of safety function after both containment area radiation monitors were declared inoperable was a performance deficiency. This violation had the potential to impact the regulatory process based, in part, on the generic communications that 10 CFR 50.72 and 10 CFR 50.73 reports serve, the required Reactor Oversight Process (ROP) inspection reviews that the NRC performs on all LERs, and the potential impact on licensee performance assessment. The inspectors determined that this issue was a Severity Level IV violation based on Example 9, The licensee fails to make a report required by 10 CFR 50.72 or 10 CFR 50.73, and Example 10, A failure to identify all applicable reporting codes on a Licensee Event Report that may impact the completeness or accuracy of other information (e.g., performance indicator data) submitted to the NRC, discussed in Section 6.9 of the NRC Enforcement Policy. Because cross-cutting aspects do not apply to traditional enforcement issues, no cross-cutting aspect was assigned to this Severity Level IV violation. | ||
}} | }} | ||
Latest revision as of 20:46, 20 February 2018
| Site: | Byron  |
|---|---|
| Report | IR 05000454/2012005 Section 4OA1 |
| Date counted | Dec 31, 2012 (2012Q4) |
| Type: | TEV: Severity level IV |
| cornerstone | Barrier Integrity |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71151 |
| Inspectors (proximate) | A Shaikh B Bartlett C Moore C Sanders C St . Petersc Thompson E Sanchez J Gilliam J Laughlin J Robbins N Feliz Adorno R Ng R Walton T Daun T Go |
| INPO aspect | |
| ' | |