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05000413/FIN-2015301-0130 June 2015 23:59:59CatawbaLicensee-identifiedLicensee-Identified ViolationThe following Severity Level IV violation was identified by the licensee and is a violation of NRC requirements which meets the criteria of the NRC Enforcement Policy, for being dispositioned as a Non-Cited Violation. Following the facilitys administration of the initial written examination on May 28, 2015, the licensee identified that an earlier version of the examination was inadvertently provided to the RO applicants. The licensee immediately informed the NRC. The earlier version of the examination did not include the changes that were made to resolve NRC comments provided during the preexamination review of the written examination. This earlier version of the examination had not been approved by the NRC for administration to the license applicants. 10 CRF 55.49, Integrity of examinations and tests states, in part, that facility licensees shall not engage in any activity that compromises the integrity of any test or examination required by this part. The integrity of a test or examination is considered compromised if any activity, regardless of intent, affected, or, but for detection, would have affected the equitable and consistent administration of the test or examination. Contrary to the above, on May 28, 2015, the licensee administered an unapproved RO written examination, an activity that compromised the integrity of the written examination. The RO applicants did not get the benefit of the question enhancements that occurred during the examination review. The SRO applicants experienced a higher quality exam than that of the RO applicants. This is neither equitable nor consistent. The unapproved version of the exam was subsequently reviewed by the NRC and was determined to be valid. See enclosure 3 to this report to review the analysis of the administered written exam for validity of the exam. A violation of 10 CFR 55.49 is a violation that potentially impacts the regulatory process, because the examination results are used by the NRC to make licensing decisions. An improperly administered examination has the potential to provide inaccurate information to the NRC regarding the competence of the applicants. There were no actual or potential safety consequences. This violation is being treated as a Severity Level IV non-cited violation consistent with Section 2.3.2.a. of the NRC Enforcement Policy. The violation was entered into the licensees corrective action program as Nuclear Condition report 01931989.
05000413/FIN-2010005-0131 December 2010 23:59:59CatawbaNRC identifiedFailure to Notify the Commission of a Change in Medical StatusAn NRC-identified NCV of 10 CFR 55.25 was identified when the licensee failed to notify the NRC of a permanent change in the medical status of a licensed operator within 30 days of learning of the change. The failure to meet the requirements of 10 CFR 55.25 was a performance deficiency (PD). The inspectors determined that the violation should be dispositioned using the Traditional Enforcement process because the PD impacted the regulatory process. The inspectors assessed the PD using the NRCs Enforcement Policy, Section 6.4, Licensed Reactor Operators, and determined the violation should be dispositioned as a SL-IV violation. Cross-cutting aspects are not assigned to PDs dispostioned using Traditional Enforcement.
05000413/FIN-2009007-0230 September 2009 23:59:59CatawbaNRC identifiedInaccurate Fire Watch RecordsThe NRC identified a violation of 10 CFR 50.9(a) requirements when it was determined that multiple contract fire watch employees deliberately pre-signed fire watch ICM forms resulting in inaccurate fire watch records. Specifically, on seven occasions fire watch employees deliberately pre-signed the fire watch ICM forms and then another qualified employee performed the fire watch but failed to correct the inaccurate ICM form. The licensee entered the deficiency into the corrective action program for resolution. This issue was dispositioned using traditional enforcement due to the willful aspects of the performance deficiency. Furthermore, the failure to provide complete and accurate information has the potential to impact the NRCs ability to perform its regulatory function. Although the investigation revealed that no fire watch surveillances were actually missed, this issue is considered more than minor due to the willful aspects of the performance deficiency. In accordance with the guidance in Supplement VII of the Enforcement Policy, 3 Enclosure 2 this issue is considered a Severity Level IV violation because it involved information that the NRC required be kept by a licensee that was incomplete or inaccurate and of more than minor safety significance. No cross-cutting aspect was identified because this performance deficiency was dispositioned using traditional enforcement
05000413/FIN-2007011-0130 September 2007 23:59:59CatawbaNRC identifiedFailure to Perform Indoctrination and Training of Personnel Performing 10 CFR 72.48 ReviewsBased on the results of this inspection, the NRC has determined that a violation of NRC requirements has occurred. The violation involved failure to perform indoctrination and training of personnel performing 10 CFR 72.48 review activities was not implemented during the pre-operational inspcetion as required by 10 CFR 72.144(d) and a Non-Cited Violation (NCV) has been issued (Attachment 2, 10 CFR 72.48 Training, Pages 46-48).
05000413/FIN-2005002-0231 March 2005 23:59:59CatawbaNRC identifiedInadequate 10 CFR 50.59 DocumentationThe inspectors identified a non-cited violation for making a change to the facility (implemented as a change to the UFSAR in 1995) that involved an Unreviewed Safety Question (USQ), for which no written evaluation provided an adequate bases for the determination that the change did not require a license amendment pursuant to 10 CFR 50.90. Specifically, the UFSAR change reflected an increased length of time for incore instrumentation room sump instrumentation, as well as gaseous and particulate radiation monitors, to detect a 1 gpm leak. This increased the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety evaluation report for the reactor coolant system loss of coolant accident (LOCA) leak rate predictions, because the ability to detect a 1 gpm leak within one hour was relied on and credited in the leak-before-break design analysis. The significance of the violation was evaluated under the 10 CFR 50.59 Rule that was in effect at the time of the change, as well as the current 10 CFR 50.59 Rule. The current 10 CFR50.59 Rule requires, in part that "records must include a written evaluation which provides the bases for the determination that the change does not require a license amendment". This information (i.e., the ability to detect a 1gpm leak within one hour) was relied on in part, by NRC for approval of the leak-before-break analysis. Since, the NRC Enforcement Manual states that violations which existed under the old and new rule should be categorized using the current enforcement guidance, this finding was assessed as a SL IV violation. The significance of this violation was not formally evaluated under the Reactor Oversight Process per the Enforcement Policy, because the Agency views 10 CFR 50.59 issues as potentially impeding the regulatory process (i.e., it precluded NRC review of a change to the facility). The finding was not suitable for evaluation using the SDP. Given that the change to the incore instrumentation room sump instrumentation sensitivity capabilities and the gaseous and particulate radiation monitor sensitivities increased the length of time to detect a 1 gpm leak, and the fact that a diverse means of detecting a 1 gpm leak within one hour existed in accordance with Technical Specification (TS) requirements, the delta core damage frequency for the applicable core damage accident sequences stemming from LOCA initiating events were determined to be of very low safety significance.