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| Quarter | Site | Title | Description | |
|---|---|---|---|---|
| 05000410/FIN-2018003-01 | 2018Q3 | Nine Mile Point | Failure to Ensure that Thermal Power is Less Than or Equal to the Licensed Power Limit | The inspectors identified a Green finding and associated non-cited violation (NCV) of the NMPNS Unit 2 Operating License (NPF-69), Condition 2.C(1), Maximum Power Level, when Exelon did not ensure that thermal power was less than or equal to the licensed power limit of 3988 megawatts-thermal (MWth). Specifically, on multiple occurrences between May 22, 2018 and October 19, 2018, licensed operators in the main control room did not appropriately monitor and control 2-hour average thermal power at or below the licensed power limit. The inspectors determined the 2-hour average thermal power exceeded the licensed power limit outside of normal steady-state fluctuations, and did not take timely, effective corrective action to reduce thermal power below the licensed power limit when the 2-hour average was found to exceed the licensed power limit |
| 05000293/FIN-2018003-01 | 2018Q3 | Pilgrim | Failure to Identify an Adverse Condition Associated with Elevated Standby Gas Treatment System Accumulator Leakage | The inspectors identified a Green non-cited violation (NCV) of Technical Specifications 3.7.B.1.c because Entergy exceeded the TS allowed outage time for the standby gas treatment system (SBGT) when the station did not identify an adverse condition associated with elevated air accumulator leakage in the system. |
| 05000410/FIN-2018003-02 | 2018Q3 | Nine Mile Point | Minor Violation | During the review of Licensee Event Report (LER) 05000220/2017-002-01, Manual Reactor Scram Due to Presesure Oscillations, the inspectors identified a minor violation of 10 CFR 50.9, Completeness and accuracy of information. The LER was found to be inaccurate. Specifically, the LER timeline contained inaccurancies regarding the time operators entered a special operating procedure and did not include an actuation of high-pressure coolant injection (HPCI). The timeline stated at 2:10 AM operators entered the special operating procedure for Pressure Regulator Malfunction, due to reactor pressure oscillations of 2-3 psig. At 2:27 AM operators inserted a manual scram of the reactor due to pressure oscillations exceeding procedural limits. This information was confirmed by a review of the operational logs for March 20, 2017. During OI Investigation 1-2018-002, it was determined that this entry was not accurate and although an exact time could not be established is was estimated to have been at 2:20 AM vice 2:10 AM. Additionally the timeline did not include a mention that at 2:16 AM unexpected turbine trip signal was received and HPCI was initiated due to a tagging error. Operators reset HPCI at 2:18 AM and restored main feedwater flow to restore Reactor Vessel water level. A sixty day telephone notification instead of a written licensee event report was conducted for this invalid initiation of HPCI was completed on May, 11, 2017, as EN 52747 as allowed by 10 CFR 50.73(a)(2)(iv). Screening: Violations involving the submittal of inaccrurate or incomplete information are evaluated under Traditional Enforecement because they impact the NRCs regulatory process. Accordingly, the inspectors evlauted this issue against the example violations in Section 6.9 of the NRC Enforcement Policy. Inspectors concluded that the violation is of minor safety significance because the inaccurate information did not change the NRCs review of the licensee event report. Enforcement: 10 CFR 50.9 requires that information provided to the Commission by a licensee shall be complete and accurate in all material respects. Contrary to the above, on June 22, 2015, Entergy provided information to the Commission that was not complete and accurate in all material respects. In the licensee event report, Exelon documented incorrect information that resulted in the NRC launching a substation further inquiry (OI investigation), but did not substantiate that licensed operators deliberately failed to follow a Technical Specifications required procedure. Exelon identified the inaccuracy and entered the issue into the corrective action program (IR 04091110) on January 7, 2018, and submitted LER 05000220/2017-002-01 on August 18, 2018, revising the timeline to show operators entering N1-SOP-31.2 at 2:20 AM vice 2:10 AM. The disposition of this violation closed Licensee Event Report 05000220/2017-002-01 |
| 05000410/FIN-2018002-01 | 2018Q2 | Nine Mile Point | Failure to Ensure Proper Control of the Standby Gas Treatment System Damper Valve, 2GTS*V2000B, Within Procedures, Materials, and Design Control Measures | The inspectors identified a Green finding and associated NCVof 10 CFRPart 50, Appendix B, Criterion III, Design Control, when Exelon failed to ensure proper control of the SGTS damper valve 2GTS*V2000B within procedures, materials, and design control measures. Specifically, on April 15, 2018 operators attempted to run B SGTS for containment purge; however, no flow was observed and the system was secured. Operators discovered the 2GTS*V2000B closed due to the failure of the operating mechanism to maintain control of the valve position. |
| 05000220/FIN-2018002-02 | 2018Q2 | Nine Mile Point | Inadequate Procedure Causes Water Hammer Condition Resulting in Isolation and Inoperability of the 12 Train of the Emergency Condenser System | The inspectors identified a Green finding and associated NCVof 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures and Drawings, when Exelon did not provide appropriate quantitative or qualitative criteria and guidance to operators in procedure N1- OP- 13 Emergency Cooling System to return an emergency condenser loop to service without inducing a water hammer condition which caused operators to re-isolate the emergency condenser loop and declare it inoperable |
| 05000259/FIN-2017003-01 | 2017Q3 | Browns Ferry | Degraded EDG Flood Door Seals | An NRC- identified non- cited violation (NCV of 10 CFR Part 50, Appendix B, Criterion V was identified for the licensee's failure to use appropriate procedural surveillance criteria to ensure the diesel generator buildings were protected against flood- water up to the design basis flood elevation. The annual door inspection procedure did not contain instructions with appropriate acceptance criteria to determine whether the diesel generator building doors would create a watertight seal when closed. The performance deficiency is more -than -minor because it was associated with the protection against external factors attribute of the mitigating systems cornerstone and adversely affected the cornerstone objective. A detailed risk evaluation by a regional Senior Risk Analyst ( SRA ) determined the finding was of very low safety significance (Green) . The licensee entered the violation into the corrective action program (CAP) as CR 1306268. The inspectors determined that the finding had a cross -cutting aspect in the Self -Assessment area of the Problem Identification and Resolution aspect (P.6), because recent self - assessments had not been self -critical of the external flood protection program and practices. |
| 05000259/FIN-2017003-02 | 2017Q3 | Browns Ferry | Failure to Maintain Intake Building Flood Barrier | An NRC- identified NCV of Technical Specification (TS) 5.4.1, Procedures, was identified for the failure to follow procedure MCI -0-023- PMP003, Emergency Equipment Cooling Water (EECW) and Residual Heat Removal Service Water Pump (RHRSW) Removal and Reinstallation, Revision 22. The performance deficiency is more than minor because it affected the Mitigating Systems cornerstone attribute of Equipment Performance and adversely affected the cornerstone objective. A detailed risk evaluation by a regional SRA determined the finding was Green . The licensee entered the violation into the CAP as CR 1338684. The finding had a cross cutting aspect in the Avoid Complacency component of the Human Performance area because the maintenance staff chose to not refer to a previously related condition report (CR) (PER 599190) or the maintenance procedure that were corrective actions for a previous NRC finding. (H.12). |
| 05000259/FIN-2017002-02 | 2017Q2 | Browns Ferry | Non -conservative Assumptions in Emergency Drain Capacity Design Review | Green . An NRC- identifi ed non- cited violation of 10 CFR 50, Appendix B, Criterion III was identified for the licensee's failure to verify the adequacy of the U nit 1 and 2 diesel building emergency drain pipe to mitigate a postulated internal flood. Specifically, the licensees design review contained non- conservative assumptions. As an immediate corrective action, the licensee reevaluated the potential water accumulation and concluded the diesel generators were still protected. The violation was entered into the licensee's corrective action program as CR 1303737. The performance deficiency was more -than- minor because it was associated with the design control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the capability of systems that respond to initiating events to prevent undesirable consequenc es. Specifically, non- conservative assumptions in calculation MDQ00004020110008 resulted in inaccurate conclusions about the capacity of the drain and the resulting water accumulation in the building. The finding was determined to be Green because it represented a deficiency affecting the design of the drain piping, but it maintained its functionality. Functionality was preserved because additional evaluation showed that the resulting water accumulation would not affect any safety related equipment . No cross -cutting aspect was assigned because it was not considered to be reflective of current licensee performance because the performance deficiency occurred more than three years ago . |
| 05000259/FIN-2017002-01 | 2017Q2 | Browns Ferry | Inadequate Fire Risk Evaluation for Postulated Fires Affecting EECW Strainers | Green . An NRC- identified non- cited violation of 10 CFR 50.48(c) and NFPA 805, Section 2.4.2.4 was identified for the licensee's failure to perform an adequate engineering analysis to determine the effects of fire on the ability to achieve the nuclear safety performance criteria . Specifically, the licensees fire risk evaluation (FRE) of the effects of fire on the Emerge ncy Equipment Cooling Water (EECW ) strainers did not have an adequate basis . As an immediate corrective action, the licensee performed plant -specific analyses to determine the effects of fire on the functionality of EECW strainers and EECW system . The violation was entered into the licensee's corrective action program as CR 1263434. The performance deficiency was determined to be more -than- minor because it wa s associated with the protection against external factors attribute of t he Mitigating Systems cornerstone and adversely impacted the cornerstone objective in that failure to adequately 3 analyze the effects of fire damaged cables for the EECW strainers and backwash valves impacted the objective of ensuring the reliability of the E ECW system during a fire. This finding was determined to be Green because the finding did not affect the ability to reach and maintain a stable plant condition within the first 24 hours of a fire event. The inspectors determined that the finding had a cross -cutting aspect of Avoid Complacency (H.12) within the cross- cutting area of Human Performance because the licensee did not recognize that historical assumptions about long -term strainer functionality could contain mistakes and latent issues during development of the nuclear safety capability analysis. |
| 05000259/FIN-2017002-03 | 2017Q2 | Browns Ferry | Failure to Assure EECW Design Basis Capability | Green . An NRC- identified non- cited violation of 10 CFR Part 50, Appendix B, Criterion III was identified for the licensee's failure to correctly translate the design basis of the EECW system into technical instruction 0 -TI-579(EECW). The effects of instrument uncertainty and diesel frequency variations were not considered when establishing the minimum allowed inservice test low alert pump flow limits . As an immediate corrective action, the licensee evaluated the operability of the EECW pump and initiated corrective action to make changes to the test criteria and/or the system design analysis . The violation was entered into the licensee's corrective action program as CR 1288208. The performance deficiency was more- than- minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective in that there was a reasonable doubt on the operability of the B3 EECW pump since portions of the adjusted pump curve would be below the minimum pump curve established in the design basis calcul ation. Additionally, there was a significant reduction in available margin for the pump under design basis conditions. The finding was determined to be Green because the finding was a deficiency affecting the design of a mitigating system, but the pump maintained its operability. The inspectors determined that the finding had a cross -cutting aspect of Human Performance (H.6 ) within the cross -cutting area of De sign Margins because engineers did not demonstrate the characteristic of ensuring that design margins were guarded and changed only through a systematic and rigorous process . |
| 05000259/FIN-2017002-05 | 2017Q2 | Browns Ferry | Licensee-Identified Violation | 10 CFR 50 Appendix B, Criterion V, Instructions, Procedures, and Drawings, required, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. Contrary to the above, between October 5, 2016 , and December 22, 2016, the 4kV shutdown board C degraded voltage relay timer was not installed in accordance with MAI -3.8, Installation of Electrical Components. The failure to install mounting screws of an appropriate length with suitable thread engagement for the seismic restraining strap resulted in the relay being inoperable for longer than the Technical Specification allowed outage time. The licensee entered the violation into the corrective action program as CR 1244680 and replaced t he damaged mounting screw and installed the seismic restraining strap. Using an exposure time of 78 days, the change in core damage frequency was conservatively estimated to be less than 4E -8 per year. The most dominant core damage s equences were those involving the loss of the high pressure injection systems. The significance of the finding was limited because it did not affect the 22 ability of the diesel generator to automatically start under loss of of fsite power conditions and it did not affect the ability of operators to manually start the diesel generator in response to degraded voltage conditions. The inspectors determined the finding was Green . |
| 05000260/FIN-2017002-04 | 2017Q2 | Browns Ferry | Failure to Implement Corrective Actions to Prevent the Recurrence of a Reactor Scram Due to IRM spiking | Green . A self -revealing non- cited violation (NCV) of 10 CFR Part 50, Appendix B, Criterion XVI , Corrective Action, was reviewed for the licensees failure to establish measures to assure that corrective action was taken to preclude repetition of a significant condition adverse to quality (SCAQ) . The licensee failed to correct electronic noise problems with the scram reset switch which led to a March 29, 2017, reactor scram. As an immediate corrective action, the licensee initiated more rigorous test s to identify noise vulnerabilities on Intermediate Range and Source Range Monitors . The licens ee entered this issue into their corrective action program as Condition Report (CR) 1278595. This performance deficiency wa s more -than- minor because it is associated with the equipment performance attribute of the Initiating Events Cornerstone and adversely affected the cornerstone objective in that the licensee failed to implement corrective actions to address I ntermediate Range Monitor (IRM) spiking following the May 24, 2012, reactor scram . T he finding was determined to be Green because it did not involve the loss of mitigation equipment . The inspectors determined that the finding had a cross -cutting aspect of Challenge the Unknown (H.11) with in the cross -cutting area of Human Performance because the licensee failed to res olve the unknown noise paths to ensure that scram vulnerabilities were corrected. |