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05000397/FIN-2018401-0131 March 2018 23:59:59ColumbiaNRC identifiedSecurity
05000397/FIN-2018401-0231 March 2018 23:59:59ColumbiaNRC identifiedSecurity
05000397/FIN-2017003-0230 September 2017 23:59:59ColumbiaNRC identifiedFailure to Report Unplanned Valid Reactor Protection System ActuationThe inspectors identified a Severity Level IV, non- cited violation of 10 CFR 50.72(b)(3)(iv)(A) for the licensees failure to submit an event notification to the NRC 3 within 8 hours of occurrence of an unplanned valid reactor protection system actuation of the reactor protection system. Specifically, the licensee did not report are actor protection system Level 3 scram actuation when reactor vessel level dropped below +13 inches until prompted by the inspectors. The licensee subsequently restored compliance and reported the event in accordance with 10 CFR 50.72(b)(3)(iv)(A) on August 24, 2017, as an update to Emergency Notification System Report 52918 and entered the issue into their corrective action program as Action Request 370529 . The licensees failure to submit the event notification was a violation that impacted the regulator y process and warrants treatment using traditional enforcement . In accordance with Section 2.2.4 and the example in Section 6.9.d.9 of the NRC Enforcement Policy, dated November 1, 2016, the violation was determined to be a Severity Level IV violation. Traditional enforcement violations are not assessed for cross- cutting aspects.
05000397/FIN-2016009-0631 March 2017 23:59:59ColumbiaNRC identifiedFailure to Update the Final Safety Analysis Report with Changes to Radioactive Waste ProcessingSLIV. The team identified a Severity Level IV non-cited violation of 10 CFR 50.71(e) for the failure of the licensee to periodically pr ovide the NRC a Final Safety Analysis Report (FSAR) update with all changes made to the facility or procedures. Specifically, the licensee changed its radwaste management strategy for the spent fuel pool cooling and cleanup system and material being stored in the spent fuel pool. However, the licensee had not changed its process control program or updated the FSAR to reflect the impact on waste streams from processing items stored in the spent fuel pool including activated metals, Tri-Nuke filters, filter socks, and dem ineralizer filter resins. This issue was entered into the corrective action program as Action Requests 359293 and 359296. The failure to update the final safety analysis report to reflect changes in solid radwaste management and the process control program was a performance deficiency. The Reactor Oversight Programs SDP does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to address this violation which involves the ability of the NRC to perform its regulatory oversight function using traditional enforcement to adequa tely deter non-compliance. Referring to Section 6.1.d. of the Enforcement Policy, the finding is being characterized as a Severity Level IV violation. Traditional enforcement violations are not assessed for cross-cutting aspects.
05000397/FIN-2015002-0430 June 2015 23:59:59ColumbiaNRC identifiedFailure to Report a Major Loss of Emergency Assessment CapabilityThe inspectors identified a Severity Level IV non-cited violation of 10 CFR 50.72(b)(3)(xiii) for the licensees failure to make a required event notification within eight hours for a major loss of assessment capability. Specifically, the licensee failed to make a report for an unplanned loss of rod position indication on April 29, 2015 that resulted in the inability to evaluate the position of all control rods for emergency action levels involving failures of the reactor protection system and anticipated transient without scram scenarios. As corrective actions to address a late 8-hour report, the licensee submitted Event Notification EN 51027 on April 30, 2015 and initiated Action Request AR 326719. The inspectors determined that the failure to make a required event notification within the time limits specified in regulations was a violation 10 CFR 50.72. The violation was evaluated using Section 2.2.4 of the NRC Enforcement Policy, because the failure to submit a required licensee event report may impact the ability of the NRC to perform its regulatory oversight function. As a result, this violation was evaluated using traditional enforcement. In accordance with Section 6.9 of the NRC Enforcement Policy, this violation was determined to be a Severity Level IV, non-cited violation. The inspectors determined that a cross-cutting aspect was not applicable because the issue involving untimely reports to the NRC was strictly associated with a traditional enforcement violation.
05000397/FIN-2014003-0730 June 2014 23:59:59ColumbiaNRC identifiedFailure to Report an Unanalyzed Condition within Required Time LimitsSeverity Level IV. The inspectors identified a non-cited violation involving 10 CFR 50.73 Licensee event report system. Specifically, the inspectors identified that the licensee failed to submit a required licensee event report, within specified time limits, for an unanalyzed condition involving unfused DC ammeters. The licensee entered this issue into their corrective action program as AR 309600. The inspectors determined that the failure to make a required licensee event report within the time limits specified in regulations was a violation of 10 CFR 50.73. The violation was evaluated using Section 2.2.4 of the NRC Enforcement Policy, because the failure to submit a required licensee event report may impact the ability of the NRC to perform its regulatory oversight function. As a result, this violation was evaluated using traditional enforcement. I accordance with Section 6.9 of the NRC Enforcement Policy, this violation was determined to be a Severity Level IV, non-cited violation. The team determined that a cross-cutting aspect was not applicable because the issue involving untimely reports to the NRC was strictly associated with a traditional enforcement violation.
05000397/FIN-2013007-0430 September 2013 23:59:59ColumbiaNRC identifiedFailure to Update the FSAR for the Cleaning and Inspection Frequency of the Diesel Fuel Oil Storage TanksThe team identified a Severity Level IV non-cited violation of 10 CFR 50.71(e), which states, in part, that each person licensed to operate a nuclear power reactor shall update, periodically, the final safety analysis report originally submitted as part of the application for the license, to assure that the information included in the report contains the latest information. Specifically, from May 2009 to August 22, 2013, the team identified that the diesel engine fuel oil storage tanks cleaning and inspection frequency was not updated in the final safety analysis report to include the latest information developed. This violation was entered into the licensees corrective action program as Action Request 292360. The violation did not represent an immediate safety concern. The licensees failure to update the final safety analysis report to reflect the cleaning and inspection frequency of the diesel engine fuel oil storage tanks in Section 9.5.4.4 Testing and Inspection Requirements was a violation of the NRC requirements. The inspectors determined that this violation was also a performance deficiency. However, the inspectors determined that the performance deficiency was minor. The inspectors considered this issue to be within the traditional enforcement process because it had the potential to impact the NRC\\\'s ability to perform its regulatory oversight function. The inspectors used the NRC Enforcement Policy to evaluate the significance of this violation. The inspectors determined that the violation was a Severity Level IV because it was similar to an example provided in Section 6.1 of the NRC Enforcement Policy. The inspectors did not assign a cross-cutting aspect to this non-cited violation because there was no finding associated with this traditional enforcement violation.
05000397/FIN-2013003-0130 June 2013 23:59:59ColumbiaNRC identifiedFailure to Obtain NRC Approval for Changes to Reactor Water Cleanup System PipingThe inspectors identified a Severity Level IV non-cited violation of 10 CFR 50.59, Changes, Tests, and Experiments, because the licensee failed to obtain a license amendment, pursuant to 10 CFR 50.90, prior to implementing a change to piping classification of the reactor water cleanup system. Specifically, through a 1995 revision to the Final Safety Analysis Report, the licensee changed the classification of reactor water cleanup system piping from ASME Section III, Class 3, to ANSI B31.1 without first obtaining NRC approval. The licensee initiated Action Request AR 282022 to address the incorrect downgrading of piping in the reactor water cleanup system. The violation was evaluated using Section 2.2.4 of the NRC Enforcement Policy because the violation could impact the ability of the NRC to perform its regulatory oversight functions. Using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, the inspectors determined the finding was of very low safety significance because the finding did not result in exceeding the reactor coolant system leak rate for a small break loss of coolant accident and because the finding did not affect other systems used to mitigate a loss of coolant accident resulting in a total loss of function. Therefore, in accordance with Section 6.1.d of the NRC Enforcement Policy, the significance was determined to be Severity Level IV. This issue was entered into the licensees corrective action program as Action Request AR 282022. This violation did not have a cross-cutting aspect because it was strictly associated with a traditional enforcement violation.
05000397/FIN-2013002-0431 March 2013 23:59:59ColumbiaNRC identifiedFailure to Obtain NRC Approval for Changes to Control Room HVAC RequirementsThe inspectors identified a non-cited violation of 10 CFR 50.59, Changes, Tests, and Experiments, because the licensee failed to obtain a license amendment, pursuant to 10 CFR 50.90, prior to implementing a change to the control room heating, ventilation and air conditioning system (HVAC). Specifically, through the course of several Final Safety Analysis Report amendments, the licensee changed the control room habitability requirements from 75 degrees Fahrenheit (F) 3 degrees F to 85 degrees F effective temperature without obtaining a license amendment. The violation was evaluated using Section 2.2.4 of the NRC Enforcement Policy, because the violation may impact the ability for the NRC to perform its regulatory oversight function. In accordance with the NRC Enforcement Policy, the significance determination process was used to inform the significance of the failure to obtain a license amendment prior to implementing a proposed change to the main control room design requirements. Using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, the inspectors determined the finding was of very low safety significance because the finding does not represent a degradation of the radiological barrier function provided for the control room and does not represent a degradation of the barrier function of the control room against smoke or a toxic atmosphere. Therefore, in accordance with Section 6.1.d of the NRC Enforcement Policy, the significance was determined to be at Severity Level IV, since the impact of the incorrect changes was evaluated as having very low safety significance by the significance determination process. This issue was entered into the licensee\'s corrective action program as AR 280119, and therefore, this violation is treated as SL-IV NCV consistent with Section 2.3.2 of the NRC Enforcement Policy. This violation did not have a cross-cutting aspect because it was strictly associated with a traditional enforcement violation
05000397/FIN-2011002-0231 March 2011 23:59:59ColumbiaNRC identifiedFailure to Make Required Event NotificationThe inspectors identified a Severity Level IV violation of 10 CFR 50.72(b)(3)(v)(D) for the failure of the licensee to make a non-emergency event notification to the NRC. Specifically, on December 20, 2010, the licensee failed to report the low pressure core spray minimum flow valve failing to open on pump start, rendering the low pressure core spray system incapable of performing its specified safety function during testing. The licensee made Event Notification 46604 on February 8, 2011, to report the identified condition. As a corrective action the licensee has informed all current shift managers, and plans to train future senior reactor operators, of the expectation to evaluate low pressure core spray system failures as a failure of a single train system to complete a safety function. This violation has been placed in the licensees corrective action program as Action Request/Condition Report 236879. The performance deficiency was more than minor because the NRC relies on licensees to identify and report conditions or events meeting the criteria specified in the regulations in order to perform its regulatory function. The inspectors determined that this finding was not appropriate to evaluate using the Significance Determination Process due to the finding only affecting the NRCs ability to perform its regulatory oversight function. As a result, this finding was evaluated for traditional enforcement in accordance with the NRC Enforcement Policy. This finding was determined to be a Severity Level IV violation in accordance with Section 6.9.d.9 of the NRC Enforcement Policy, dated September 30, 2010. The inspectors determined that assigning a cross-cutting aspect was not applicable to this finding due to the finding being screened exclusively using the traditional enforcement process
05000397/FIN-2008008-0130 June 2008 23:59:59ColumbiaNRC identifiedProject Manager Instructed Plant Workers to Reach Across a Contamination Boundary Without Radiation Protection ApprovalDuring an NRC investigation and subsequent in-office inspection completed on May 13, 2008, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below: Technical Specification 5.4.1.a states, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Regulatory Guide 1.33, Appendix A, Section 7.e (1), specifies procedures for Access Control to Radiation Areas Including a Radiation Work Permit System. Columbia Generating Station Procedure GEN-RPP-04, Entry into, Conduct in, and Exit from Radiologically Controlled Areas, Revision 14, states, in part, Do not reach over, or cross contaminated area boundaries without RP approval. Contrary to the above, during repair of the HPCS-P-1 flange on June 16, 2007, a project manager instructed plant workers to reach across a contamination boundary without radiation protection approval. This is a Severity Level IV violation. (Supplement IV
05000397/FIN-2007005-0731 December 2007 23:59:59ColumbiaSelf-revealingWillful Failure to Complete Fire Watch Rounds and Falsification of LogsDuring a routine audit, the licensee identified that a fire watchstander failed to enter some plant areas required to complete portions of 2 hourly fire watch rounds on both April 30 and May 7, 2007. An NRC Office of Investigation Report 4-2007-038 concluded that the individual willfully failed to complete portions of the required compensatory fire tours and inaccurately indicated on the fire tour log, an NRC-required record that the fire watches had been conducted. This was a violation of 10 CFR 50.9 and Columbia Generating Station License Condition 2.C(14), Fire Protection Program, (EA-07-282). Failure to complete compensatory fire watches required by the fire protection program and falsifying fire watch records was a performance deficiency. This finding was of more than minor significance because it had the potential to impact the NRCs ability to perform its regulatory function, since required records were falsified. The finding is associated with the Mitigating Systems Cornerstone attribute of protection against external events. This finding had very low safety significance since proper tours were completed within 2 hours. Willful violations are a particular concern to the Commission because its regulatory program is based on licensees and their employees acting with integrity. However, in an effort to encourage licensees to act responsibly in the identification and correction of such violations, the NRC may choose to disposition certain violations by issuing an noncited violation if the licensee identified and corrected the violation. Therefore, in accordance with the NRC Enforcement Policy, this violation is being dispositioned as a Severity Level IV noncited violation because the licensee promptly identified and reported this violation and took appropriate corrective action. This issue was entered into the corrective action program under Condition Report 2-07-05033
05000397/FIN-2005009-0131 December 2005 23:59:59ColumbiaNRC identifiedFailure to Conduct an Evaluation and Obtain a LicenseThe team identified a finding of very low safety significance involving a noncited violation of 10 CFR 50.59, Changes, Tests, and Experiments, for the failure to obtain a license amendment pursuant to 10 CFR 50.90 for changes to the Updated Final Safety Analysis Report. In addition, licensee personnel did not create a written evaluation providing the bases for the determination that the change would not require a license amendment pursuant to paragraph (c)(2) of 10 CFR 50.59. In 2001, licensee personnel changed the Updated Final Safety Analysis Report by replacing allowable emergency diesel generator bus voltage minimums of 85, 81.9, and 80 percent with allowable minimum bus voltages of 75 percent These changes to the Updated Final Safety Analysis Report result in more than a minimal increase in the likelihood of occurrence of a malfunction of a structure, system, or component important to safety previously evaluated in the Updated Final Safety Analysis Report. By being a failure to adhere to a standard (10 CFR 50.59) that was reasonably within the licensee personnels ability to foresee and correct, this issue qualifies as a performance deficiency and a finding. Since the issue has the potential to impact the NRCs ability to perform its regulatory function, this finding must be evaluated under traditional enforcement utilizing the Enforcement Manual with further NRC management review This violation is more than minor because the change would have required NRC approval in accordance 10 CFR 50.59, as discussed previously. Since no changes were implemented in the plant, all systems designed to prevent or mitigate serious safety events were able to perform their intended safety functions. Therefore, since there was no actual loss of safety function, the finding screens as Green in Phase 1 of Manual Chapter 0609, Appendix A. Because this violation is of very low safety significance and has been entered into the licensee's corrective action program as Condition Report 2-05-08086, this violation is being treated as a Severity Level IV noncited violation consistent with Section VI.A of the NRC Enforcement Policy: NCV 05000397/2005009-001, Failure to Conduct an Evaluation and Obtain a License Amendment for FSAR Changes.
05000397/FIN-2005009-0231 December 2005 23:59:59ColumbiaNRC identifiedFailure to Obtain Prior Approval Prior to Implementing a New MethodologyThe team identified a finding of very low safety significance involving a noncited violation of 10 CFR 50.59 for the failure to obtain a license amendment prior to implementing a new methodology for determining spent fuel pool heat loading This finding is a performance deficiency because the licensee failed to meet requirements of 10 CFR 50.59. Specifically, licensee personnel failed to gain prior approval for a departure from an approved method to calculate spent fuel pool heat loading. Because violations of 10 CFR 50.59 are considered violations that impact the regulatory process, they are dispositioned using the traditional enforcement process. As stated in the NRC Enforcement Policy, the finding is more than minor because the departure from the method would require Commission review and approval prior to implementation. Because this violation is of very low safety significance and was entered into the licensees corrective action program as Condition Report 2-05-08137, this violation is being treated as a Severity Level IV noncited violation consistent with Section VI.A of the NRC Enforcement Policy: NCV 05000397/2005009-002, Failure to Obtain Prior Approval Prior to Implementing a New Methodology.