05000266/FIN-2012004-09
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Finding | |
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| Title | FAILURE TO PERFORM ADEQUATE EVALUATIONS TO ENSURE COMPLIANCE WITH 10 CFR 72.212(b)(6) AND 10 CFR 72.122(b)(2)(i) |
| Description | The inspectors identified a Severity Level lV non-cited violation of 10 CFR 72.146, Design Control, for the licensees failure to perform adequate evaluations to ensure compliance with 10 CFR 72.122(b)(2)(i) and 10 CFR 72.212(b)(6). Specifically, the inspectors identified that the licensee failed to evaluate that the reactor site parameters, including analyses of earthquakes, were enveloped by the transfer cask design basis. The issue was entered into the licensees corrective action program for resolution as action request AR01780357, for evaluation and development of corrective actions. The violation was determined to be more than minor in accordance with IMC 0612, Power Reactor Inspection Reports, Appendix B, Issue Screening, and Appendix E, Example of Minor Issues, dated August 11, 2009, and found that it was similar to Example 3i. Specifically, the licensees lack of evaluation did not assure cask integrity during a design basis earthquake and an additional calculation was required to evaluate the effects of the design basis earthquake during dry shielded canister processing operations in the primary auxiliary building on the cask decontamination stand in accordance with the Independent Spent Fuel Storage Installation (ISFSI) licensing/design basis analysis requirements. Consistent with the guidance in the NRC Enforcement Manual, Section 2.6.D, if a violation does not fit an example in the enforcement policy violation examples, it should be assigned a severity level: (1) commensurate with its safety significance; and, (2) informed by similar violations addressed in the Violation Examples. Therefore, the inspectors determined violation screened as having very low safety significance (Severity Level IV). Specifically, following the inspection inquiry the licensee revised their calculations and determined that overturning and sliding of the transfer cask in the primary auxiliary building on the cask decontamination stand and in the spent fuel pool would not occur during the design basis earthquake. In accordance with Section 2.2 of the NRC Enforcement Policy, ISFSIs are not subject to the Significance Determination Process (SDP) and, thus, traditional enforcement will be used for these facilities and thus a cross-cutting aspect is not assigned to this violation. In accordance with Section 2.2 of the NRC Enforcement Policy, ISFSIs are not subject to the SDP and, thus, traditional enforcement will be used for these facilities and thus a cross-cutting aspect is not assigned to this violation. |
| Site: | Point Beach  |
|---|---|
| Report | IR 05000266/2012004 Section 4OA5 |
| Date counted | Sep 30, 2012 (2012Q3) |
| Type: | TEV: Severity level IV |
| cornerstone | Other |
| Identified by: | NRC identified |
| Inspection Procedure: | |
| Inspectors (proximate) | C Zoia J Jandovitz M Kunowski S Burton R Krsek V Meghani M Learn M Thorpe-Kavanaugh P Cardona-Morales K Carrington |
| INPO aspect | |
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Finding - Point Beach - IR 05000266/2012004 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Point Beach) @ 2012Q3
Self-Identified List (Point Beach)
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