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| Start date | Site | Identified by | Title | Description | |
|---|---|---|---|---|---|
| 05000390/FIN-2018003-06 | 30 September 2018 23:59:59 | Watts Bar | Licensee-identified | Licensee-Identified Violation | This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy. Violation: Watts Bar Unit 1 TS 3.8.1, AC Sources - Operating, Condition A, requires, in part, that an inoperable required offsite circuit be restored to operable status within 72 hours. Contrary to the requirements of Technical Specification 3.8.1, a required offsite circuit was determined to be inoperable from May 27, 2017, to June 2, 2017. |
| 05000390/FIN-2018002-02 | 30 June 2018 23:59:59 | Watts Bar | Licensee-identified | Licensee-Identified Violation | LER: 05000390, 391/2017-013-00, Incorrectly Adjusted Auxiliary Building Gas Treatment System Damper Leads to a Condition Prohibited by Technical Specifications, November 6, 2017. Violation: Watts Bar Unit 1 TS 3.7.12, Auxiliary Building Gas Treatment System (ABGTS), Condition A, requires that an inoperable ABGTS train to be restored to operable status within 7 days. Condition B of TS 3.7.12 requires the plant to be in Mode 3 within 6 hours and Mode 5 within 36 hours if one train of ABGTS is inoperable longer than 7 days. Contrary to the requirements of TS 3.7.12, ABGTS, train A was determined to be inoperable from July 7, 2017, at 2030 Eastern Daylight Time (EDT) to September 5, 2017, at 1645 EDT while the plant remained in Mode 1. Significance/Severity Level: This violation was characterized using traditional enforcement because the NRC determined that this violation was not reasonably foreseeable and preventable by the licensee and, therefore, is not a performance deficiency. The violation was assessed using Sections 2.2.4 and 6.1.d.1 of the NRCs Enforcement Policy and determined to be a SL IV violation. Corrective Action Reference(s): Condition Report (CR) 1335791 |
| 05000390/FIN-2017002-06 | 30 June 2017 23:59:59 | Watts Bar | Licensee-identified | Licensee-Identified Violation | Title 10 CFR 50.72(b)(3)(v)(C) requires, in part, that the licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of any event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function of structures or systems or components that are needed to control the release of radioactive material. Contrary to the above, on March 9, 2017, the licensee failed to notify the NRC that reactor containment was inoperable, resulting in a condition that could have prevented fulfillment of a safety function. Specifically, an inner containment door equalizing valve was not fully shut when the outer containment door was open for entry into upper containment, thereby resulting in a direct path from containment to the auxiliary building. This failure to report was assessed using Section 2.2.4 of the NRCs Enforcement Policy using the example listed in Section 6.9.d.9, A licensee fails to make a report required by 10 CFR 50.72 or 50.73, and the issue was determined to be a SL IV violation. The licensee entered this issue into their corrective action program as CR 1273873. |
| 05000390/FIN-2017002-04 | 30 June 2017 23:59:59 | Watts Bar | NRC identified | Failure to Report Multiple Examples of a Loss of Safety Function in accordance with 10 CFR 50.72 and 50.73 | Severity Level IV. The inspectors identified a Severity Level IV non-cited violation of 10 Code of Federal Regulations (CFR) 50.72 and 50.73, with multiple examples due to the licensees failure to make the required eight-hour non-emergency notification and submit a Licensee Event Report (LER) to the NRC within 60 days for conditions that, at the time of discovery, could have prevented fulfillment of a safety function. These issues have been entered into the licensees corrective action program as condition report (CR) 1310096. The inspectors determined that the licensees failure to comply with 10 CFR 50.72(b)(3)(v) and 50.72(a)(2)(v) was a performance deficiency. This performance deficiency was dispositioned under traditional enforcement because the failure to make a non-emergency notification and submit an LER within the time requirements may impact the ability of the NRC to perform its regulatory oversight function. The violation was assessed using Sections 2.2.4 and 6.9.d.9 of the NRCs Enforcement Policy and determined to be a SL IV violation. Traditional enforcement violations are not assessed for cross-cutting aspects. |
| 05000390/FIN-2016013-02 | 31 December 2016 23:59:59 | Watts Bar | NRC identified | Failure to Provide Accurate Information | SL-IV. The NRC identified a Non-cited Violation (NCV) of 10 CFR 50.9, Completeness and Accuracy of Information for the licensees failure to provide accurate information in all material respects to the Commission. The team determined on April 22, 2016, the licensee provided inaccurate information in a letter to the NRC titled, RESPONSE TO NRC LETTER CONCERNING A CHILLED WORK ENVIRONMENT FOR RAISING AND ADDRESSING SAFETY CONCERNS AT THE WATTS BAR NUCLEAR PLANT (ML16113A228). This information was material because the NRC relied on this information to conclude that TVA was in compliance with CO-EA-09-009/203 requirements. The licensee placed this issue into their corrective action program. The NRC determined this violation constituted a more than minor traditional enforcement violation associated with failure to provide accurate information. The ROPs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to address violations which impede the NRCs ability to regulate using traditional enforcement. The inspector determined that the licensees failure to provide accurate information was a violation of 10CFR50.9 which had the potential to impede or impact the regulatory process, and therefore subject to traditional enforcement as described in the NRC Enforcement Policy, dated November 1, 2016. This violation is characterized as a Severity Level IV violation because it was similar to Example Section 6.9.d.1 of the NRC Enforcement Policy. |
| 05000391/FIN-2016011-04 | 30 September 2016 23:59:59 | Watts Bar | NRC identified | Failure To Adequately Evaluate Available Net Positive Suction Head To The Unit 2 AFW Pumps | The NRC identified a SL IV NCV of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for the licensees failure to properly evaluate the available net positive suction head to the Unit 2 auxiliary feedwater pumps. These issues were entered into the licensees corrective action program as condition report 1196925. The licensee confirmed current operability and had determined that likely corrective actions will include revisions to the net positive suction head calculation. The performance deficiency was determined to be more than minor because it represented an inadequate quality oversight function that, if left uncorrected, could adversely affect the quality of the analysis of a safety related SSC. Specifically, the licensees inadequate evaluation of the available NPSH for the AFW pumps resulted in a significant margin reduction of approximately 57%. The team determined this finding to be of very low safety significance, SL IV, because it represented a failure to meet a regulatory requirement, including one or more Quality Assurance criteria that had more than minor safety significance. The team determined the finding was indicative of current licensee performance and assigned a cross-cutting aspect of Design Margin in the area of Human Performance. |
| 05000391/FIN-2016011-03 | 30 September 2016 23:59:59 | Watts Bar | NRC identified | Failure To Ensure Adequate Unit 2 Emergency Diesel Generator Surveillance Instructions | The NRC identified a SL IV NCV of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures and Drawings, for the licensees failure to have adequate instructions and acceptance criteria in the emergency diesel generators surveillance procedures to ensure that the largest load rejection test bounded the power demand of the largest load. These issues were entered into the licensees corrective action program as condition reports 1201749 and 1199001. The licensee confirmed current operability and determined that likely corrective actions will include revisions to the surveillance instructions. The performance deficiency was determined to be more than minor because it represented an inadequate procedure that, if left uncorrected, could adversely affect the quality of the testing of a safety-related SSC. Specifically, the licensees procedures to implement TS SR 3.8.1.9 failed to ensure that the tested kW level of the rejected load bounded the largest predicted post-accident load. The team determined this finding to be of very low safety significance, SL IV, because it represented a failure to meet a regulatory requirement, including one or more Quality Assurance criteria that had more than minor safety significance. The team determined the finding was indicative of current licensee performance and assigned a cross-cutting aspect of Documentation in the area of Human Performance. |
| 05000390/FIN-2016003-01 | 30 September 2016 23:59:59 | Watts Bar | NRC identified | Falsified Fire Watch Records | Severity Level IV. The NRC identified a Severity Level IV violation of 10 CFR 50.9 Completeness and Accuracy of Information, for the failure to maintain continuous compensatory fire watch information that was complete and accurate in all material respects. The licensees actions of creating falsified fire watch completion records for the 713 elevation of the Auxiliary Building was a performance deficiency. The licensee entered this issue into the corrective action program as CR 1019953 and took remedial action against the involved individuals commensurate with the circumstances. The NRC evaluated this issue under the traditional enforcement process because it involved willfulness. In consideration of the fact that the individuals were contract fire watch personnel with minimal supervisory responsibilities, and that the underlying safety significance of the missed fire watch was low, the NRC concluded that this violation should be characterized at Severity Level IV in accordance with Section 2.2.1.d of the Enforcement Policy. Furthermore, because this violation involved willfulness and lack of supervisory oversight, the non-cited violation criteria of paragraph 2.3.2.a.4.(c) was not satisfied, such that this violation will be cited. This violation was evaluated under the traditional enforcement process and thus does not have a cross cutting aspect. |
| 05000390/FIN-2016002-09 | 30 June 2016 23:59:59 | Watts Bar | NRC identified | Untimely 10 CFR 50.73 Notification of Failure to Meet Technical Specification Surveillance Requirement 3.5.2.3 for the Emergency Core Cooling System | The NRC identified a SL IV NCV of 10 CFR 50.73(a)(2)(i)(B) for the licensee's failure to report, within 60 days of discovery, a condition which was prohibited by the plants TS associated with recent performances of TS surveillance requirement (SR) 3.5.2.3 for verification that emergency core cooling system (ECCS) piping is full of water. Subsequently, the licensee submitted LER 2016-003-00 for this issue on May 10, 2016. This violation was placed in the licensees corrective action program as CR 1166564. Since the failure to submit an event report within the time requirements may impact the ability of the NRC to perform its regulatory oversight function, this performance deficiency was dispositioned under traditional enforcement and the violation was assessed using Section 2.2.4 of the NRCs Enforcement Policy. Using the example listed in Section 6.9.d.9, A licensee fails to make report required by 10 CFR 50.73, the issue was determined to be a SL IV violation. In accordance with IMC 0612, Power Reactor Inspection Reports, dated May 6, 2016, traditional enforcement violations are not assessed for cross-cutting aspects. |
| 05000390/FIN-2016002-10 | 30 June 2016 23:59:59 | Watts Bar | NRC identified | Untimely 10 CFR 50.73 Notification of an Inoperable Rod Position Indication | The NRC identified a SL IV NCV of 10 CFR 50.73(a)(2)(i)(B) for the licensee's failure notify the NRC that the TS LCO 3.1.8 required action and completion time were not met when the analog rod position indication (ARPI) and the demand position indication system were not operable. Subsequently, the licensee submitted LER 2016-007-00 for this issue on June 20, 2016. This violation was placed in the licensees corrective action program as CR 1163150. Since the failure to submit an event report within the time requirements may impact the ability of the NRC to perform its regulatory oversight function, this performance deficiency was dispositioned under traditional enforcement and the violation was assessed using Section 2.2.4 of the NRCs Enforcement Policy. Using the example listed in Section 6.9.d.9, A licensee fails to make report required by 10 CFR 50.73, the issue was determined to be a SL IV violation. In accordance with IMC 0612, Power Reactor Inspection Reports, dated May 6, 2016, traditional enforcement violations are not assessed for cross-cutting aspects. |
| 05000391/FIN-2016002-08 | 30 June 2016 23:59:59 | Watts Bar | Self-revealing | Failure to Follow Maintenance Procedure Results in overspeed trip of the 2C-S Turbine Driven Auxiliary Feedwater Pump | A self-revealed Severity Level (SL) IV non-cited violation (NCV) of 10 Code of Federal Regulations (CFR) 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified at Watts Bar Unit 2 for the licensees failure to follow procedure 0-MI-1.003, Disassembly, Inspection, and Reassembly of Auxiliary Feedwater Pump Turbine. Specifically, the valve stem spring coil gap was not set in accordance with procedure, causing the turbine-driven auxiliary feedwater (TDAFW) pump to trip on electrical overspeed when the level control valves (LCVs) were closed. This issue was corrected on May 30, 2016, when the proper spring coil gap was set and verified and the post maintenance test was performed satisfactorily. The issue was entered into the licensees corrective action program as CR 1175968. The performance deficiency was more than minor because it represented an improper or uncontrolled work practice that could impact quality or safety involving safety-related structures, systems, and components (SSCs). The finding was a SL IV violation because it represented a failure to meet a regulatory requirement, specifically a quality assurance (QA) criteria to follow quality-related procedures, which had more than minor safety significance. The finding was assigned a crosscutting aspect of resources in the Human Performance area because the licensee failed to ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety. Specifically, the procedure that set the coil spring gap lacked sufficient detail and rigor to ensure that the coil gap would be set appropriately by the technicians. |
| 05000390/FIN-2016002-07 | 30 June 2016 23:59:59 | Watts Bar | NRC identified | Untimely 10 CFR 50.73 Notification of Inoperable Containment Penetrations | The NRC identified a SL IV NCV of 10 CFR 50.73(a)(2)(i)(B) for the licensee's failure notify the NRC that the TS LCO 3.6.3 required action and completion time were not met for an inoperable emergency raw cooling water (ERCW) containment isolation valve. Subsequently, the licensee submitted LER 2016-009-00 for this issue on July 15, 2016. This issue was placed in the licensees corrective action program as CR 1174000. Since the failure to submit an event report within the time requirements may impact the ability of the NRC to perform its regulatory oversight function, this performance deficiency was dispositioned under traditional enforcement and the violation was assessed using Section 2.2.4 of the NRCs Enforcement Policy. Using the example listed in Section 6.9.d.9, A licensee fails to make report required by 10 CFR 50.73, the issue was determined to be a SL IV violation. In accordance with IMC 0612, Power Reactor Inspection Reports, dated May 6, 2016, traditional enforcement violations are not assessed for cross-cutting aspects. |
| 05000391/FIN-2016002-05 | 30 June 2016 23:59:59 | Watts Bar | NRC identified | Failure to Perform A TDAFW Surveillance In Accordance With Procedures | The NRC identified a SL IV NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, at Watts Bar Unit 2 for the licensees failure to follow the surveillance test program procedure by making adjustments to the turbine-driven auxiliary feedwater (TDAFW) pump control system during the performance of a surveillance instruction. The licensee reperformed the surveillance instruction with satisfactory results. The issue was entered into the licensees corrective action program as CR 1167102. The performance deficiency was more than minor because making adjustments to the TDAFW pump control system during the performance of a surveillance instruction could invalidate the test and result in the TDAFW pump being inappropriately declared operable. As described in IMC 2517, the significance of this issue was determined using traditional enforcement, because the cornerstone associated with this finding was not being assessed by the reactor oversight process (ROP). The inspectors determined this finding to be of very low safety significance, SL IV, because it represented a failure to meet a regulatory requirement, specifically a QA criteria to follow quality-related procedures, which had more than minor safety significance. The finding was assigned a cross-cutting aspect of Conservative Bias in the Human Performance area because numerous individuals were aware the speed adjustment had been made while completing the surveillance instruction but did not question the appropriateness of that adjustment until prompted by NRC inspectors. |
| 05000391/FIN-2016002-04 | 30 June 2016 23:59:59 | Watts Bar | NRC identified | Failure to Follow Operability Procedure Results in Potential Inoperability of the 2A-A Auxiliary Feedwater Pump | The NRC identified a SL IV NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, at Watts Bar Unit 2 for the licensees failure to follow procedure OPDP-8, Operability Determination Process and Limiting Condition for Operation Tracking, Revision 22. Specifically, the 2A-A motor-driven auxiliary feedwater pump (MDAFW) was potentially inoperable in mode 3 due to inadequate compensatory measures that were being controlled outside of the operability process. The issue was corrected and the pump returned to operable status on April 19, 2016. The issue was entered into the licensees corrective action program as CR 1163431. The performance deficiency was more than minor because it represented an improper or uncontrolled work practice that could impact quality or safety, involving safety-related SSCs. Specifically, failure to appropriately use the operability process when measures must be established to compensate for degraded or nonconforming conditions can lead to SSC inoperability. As described in IMC 2517, the significance of this issue was determined using traditional enforcement, because the cornerstone associated with this finding was not being assessed by the reactor oversight process (ROP). The inspectors determined this finding to be of very low safety significance, SL IV because it represented a failure to meet a regulatory requirement, specifically a quality assurance (QA) criteria to follow quality-related procedures, which had more than minor safety significance. The finding was assigned a cross-cutting aspect of Work Management in the Human Performance area because the minor maintenance work order created to compensate for the oil loss from the 2A-A MDAFW pump was never reviewed by operations, which could have identified the out of process error. (H.5). |
| 05000390/FIN-2016002-03 | 30 June 2016 23:59:59 | Watts Bar | NRC identified | Untimely 10 CFR 50.73 Notification of an Inoperable Charging Pump | The NRC identified a Severity Level (SL) IV non-cited violation (NCV) of 10 Code of Federal Regulations (CFR) 50.73(a)(2)(i)(B) for the licensee's failure to notify the NRC that the technical specification (TS) limiting condition for operation (LCO) 3.5.2 required action and completion time were not met when the 1B-B centrifugal charging pump (CCP) was inoperable due to an inoperable room cooler. Subsequently, the licensee submitted LER 2016-006-00 for this event on June 30, 2016. This issue was placed in the licensees corrective action program (CAP) as CR 1165380. Since the failure to submit an event report within the time requirements may impact the ability of the NRC to perform its regulatory oversight function, this performance deficiency was dispositioned under traditional enforcement and the violation was assessed using Section 2.2.4 of the NRCs Enforcement Policy. Using the example listed in Section 6.9.d.9, A licensee fails to make report required by 10 CFR 50.73, the issue was determined to be a SL IV violation. In accordance with IMC 0612, Power Reactor Inspection Reports, dated May 6, 2016, traditional enforcement violations are not assessed for cross-cutting aspects. |
| 05000391/FIN-2016008-03 | 31 March 2016 23:59:59 | Watts Bar | NRC identified | Failure to Perform 50.59 Screenings For Procedures For Unit 2 | The NRC identified a SL IV non-cited violation of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, at Watts Bar Unit 2 for the licensees failure to perform 10 CFR 50.59 screening reviews for new technical procedures and changes to technical procedures, as directed by procedure NPG-SPP- 01.2.1, Interim Administration of Site Technical Programs and Procedures for Watts Bar 1 and 2, Rev. 2. The licensee entered this issue into their corrective action program as condition report 1145320 and performed the procedurally directed screening reviews which determined that no 50.59 Evaluations were required. The licensees failure to perform 10 CFR 50.59 screening reviews for new technical procedures and changes to technical procedures as directed by procedure NPG-SPP- 01.2.1 was determined to be a performance deficiency. The performance deficiency was more than minor because it represented an improper or uncontrolled work practice that could impact quality or safety, involving safety-related SSCs. The inspectors determined this finding to be of very low safety significance (SL IV) in accordance with Section 6.5 of the Enforcement Policy. The finding has a cross-cutting aspect of Change Management in the Human Performance area because the licensee failed to use a systematic process for evaluating and implementing change so that nuclear safety remained the overriding priority (H.3). |
| 05000391/FIN-2016008-04 | 31 March 2016 23:59:59 | Watts Bar | NRC identified | Failure to Perform Verification and Validation For Abnormal Operating Instructions For Unit 2 | The NRC identified a SL IV non-cited violation of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, at Watts Bar Unit 2 for the licensees failure to perform verification and validation for abnormal operating instructions as directed by technical instruction 0-TI-12.11, Emergency Operating Instruction (EOI). The licensee entered this issue into their corrective action program as condition reports 1151954 and 1153507, and performed the procedurally directed verification and validations which determined that all of the abnormal operating instructions in question were adequate. The licensees failure to perform verification and validation for abnormal operating instructions as directed by technical instruction 0-TI-12.11 was determined to be a performance deficiency. The performance deficiency was more than minor because it represented an improper or uncontrolled work practice that could impact quality or safety, involving safety-related SSCs. The inspectors determined this finding to be of very low safety significance (SL IV) in accordance with Section 6.5 of the Enforcement Policy. The finding was assigned a cross-cutting aspect of Change Management in the Human Performance area because the licensee failed to use a systematic process for evaluating and implementing change so that nuclear safety remained the overriding priority (H.3). |
| 05000390/FIN-2016001-07 | 31 March 2016 23:59:59 | Watts Bar | NRC identified | Failure to Maintain Operating Logs | The NRC identified a NCV of 10 CFR 50, Appendix B, Criterion XVII, Quality Assurance Records, for the licensees failure to maintain sufficient records to furnish evidence of activities affecting quality. The licensee entered this issue into their corrective action program as CR 1127691. The inspectors determined that the licensees failure to document plant operations in the operating logs in accordance with OPDP-1 was a violation of 10 CFR 50, Appendix B, Criterion XVII, Quality Assurance Records. This violation constitutes a traditional enforcement violation because it impacts the NRC's ability to carry out its regulatory function. The failure to maintain accurate logs was more than minor because it would have likely caused the NRC to undertake further inquiry and was consistent with Enforcement Policy section 6.9.d.1 for a SL-IV violation. Crosscutting aspects are not assigned to traditional enforcement violations. |
| 05000390/FIN-2015404-01 | 30 June 2015 23:59:59 | Watts Bar | NRC identified | Security | |
| 05000390/FIN-2010002-03 | 31 March 2010 23:59:59 | Watts Bar | NRC identified | Failure to Submit Complete and Accurate Information for a Requested License Amendment | The inspectors identified an NCV of 10 CFR 50.9(a), Completeness and Accuracy of Information, when the licensee failed to submit complete and accurate information for License Amendment 77 (LA 77) related to the permeation of the Tritium Producing Burnable Absorber Rods (TPBARS) when pertinent information became available to the licensee prior to the issuance of LA 77. The licensee has entered this item into its corrective action program as PER 210845This finding was considered as traditional enforcement because the failure to provide complete and accurate information impacted the regulatory process. This finding was determined to be minor because the licensee configured the core TPBAR loading in a conservative manner. However, due to a lack of completeness of information provided by the licensee to the NRC, the NRC approved LA 77 which gave the licensee allowance to change the configuration of core TPBAR loading which the NRC may not have otherwise allowed. The lack of completeness impeded the NRC regulatory process. Consistent with the guidance in Section IV.A.3 and Supplement VII, Paragraph D.1 of the NRC Enforcement Policy, this finding was determined to be a Severity Level IV non-cited violation. |
| 05000390/FIN-2009005-02 | 31 December 2009 23:59:59 | Watts Bar | NRC identified | Failure to Adequately Update the UFSAR for the Removal of the Additional Diesel Generator Unit. | The inspectors identified an NCV of 10 CFR 50.71(e) for failure to adequately update the Updated Final Safety Analysis Report (UFSAR) to reflect that the additional diesel generator unit (ADGU) was never completed and made available for use as described in the UFSAR. The licensee entered these issues into the CAP as PER 175830. This finding was considered as traditional enforcement because it had the potential for impacting the NRCs ability to perform its regulatory function. The inspectors used the NRC Enforcement Policy, Supplement I, to determine that the issue was more than minor because including references of incomplete equipment in the UFSAR would have a material impact on licensed activities associated with the onsite emergency AC power distribution system. This issue was considered a SL-IV violation because the inaccurate information was not used to make any change to the facility. No cross-cutting aspect was identified |
| 05000391/FIN-2009602-01 | 31 March 2009 23:59:59 | Watts Bar | NRC identified | Failure to follow procedure for scaffold inspections | A SL IV NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified by the inspectors for failure to accomplish activities affecting quality in accordance with instructions and procedures. The inspectors identified three examples associated with scaffolding deficiencies where procedural requirements were not implemented in accordance with applicant procedure MMTP-102, Erection of Scaffold/Temporary Work Platforms and Ladders. TVA entered the issue into the corrective action program and, as part of the corrective actions, immediately corrected the scaffolding to comply with procedural requirements, conducted an apparent cause evaluation and completed appropriate engineering evaluations. The inspectors determined that this finding was more than minor because the finding represented an improper/uncontrolled work practice and represented a deviation that, if left uncorrected, could potentially adversely affect the seismic qualification of a system structure or component (SSC). The cause of this finding was directly related to the work practices component of the Human Performance cross-cutting area because TVA and Bechtel did not define and effectively communicate expectations regarding procedural compliance and as a result personnel failed to follow procedures (H.4.b). (Section E.1.1 |
| 05000390/FIN-2003002-02 | 30 June 2003 23:59:59 | Watts Bar | NRC identified | Noncompliance of the Unit 2 Layup Process to10 CFR 50, Appendix B | The inspectors identified that the applicant had initiated an unapproved reduction in equipment preservation to the Unit 2 lay-up process. The applicant had elected to cease performing preventive maintenance on many components An inspector-identified, non-cited violation of 10 CFR 50, Appendix B, Criteria XIII, Identification and Control of Materials, Parts, and Components, was identified. This finding satisfied a traditional enforcement criterion of failure to receive NRC approval for a change in licensee activity In accordance with the NRC Enforcement Policy, the finding was characterized as a Severity Level IV NCV involving a failure to receive prior NRC approval for a change in licensee activity (Section 4OA5). |
| 05000390/FIN-2002006-02 | 31 March 2002 23:59:59 | Watts Bar | NRC identified | Exposure of a minor in third quarter of 1981 in excess of the requirements of 10 CFR 20.104 | 10 CFR 20.401 and subsequently 10 CFR 20.2106 requires that the licensee maintain records of doses received by all individuals for whom monitoring was required. 10 CFR 50.9 requires, in part, that information required by the Commissions regulations to be maintained shall be complete and accurate in all material respects. Contrary to these requirements, the licensee failed to maintain accurate records of personnel exposures during the period 1970 to 1999. This violation was not assessed in accordance with the significance determination process because it was identified and corrected prior to implementation of the Reactor Oversight Process and involved a violation of 10 CFR 50.9. Therefore, in accordance with Section VI of the Enforcement Policy, this licensee identified and corrected Severity IV violation is being characterized as a non-cited violation (NCV) and is identified as NCV 50-259/01-08-02, 50-260/01-08-02, 50-296/01-08-02, 50-327/02- 06-02, 50-328/02-06-02, 50-390/02-05-02 and 50-391/02-05-02) 1, Failure to maintain complete and accurate personnel dose records as required by 10 CFR 20.401, 10 CFR 20.2106, and 10 CFR 50.9 . This issue is in the licensees corrective action program as Problem Evaluation Report (PER) CHSCA940002 Personnel Exposure Records-Reconciliation Project. |