2017 Reactor Actions
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Exelon Generation Company (Clinton Power Station) EA-17-098
On November 27, 2017, the NRC issued a Notice of Violation to Exelon Generation Company (Exelon) for a violation of Title 10 of the Code of Federal Regulations Part 50, Appendix B, Criterion III at Clinton Power Station, associated with a White Significance Determination Process finding. Contrary to the requirements, Exelon failed to review for suitability of application replacement relays essential to the safety-related functions of the Division 1 Emergency Diesel Generator (EDG) Room Ventilation Fan. Specifically, Exelon failed to evaluate the change in the actual drop out voltages for replacement relays associated with the Division 1 EDG Room Ventilation Fan resulting in the safety-related fan becoming inoperable during undervoltage conditions. Additionally, there is an associated violation of Technical Specification 3.8.1, "AC Sources-Operating," for one Standby Diesel Generator being inoperable for greater than the allowed outage time of 14 days.
Dominion Nuclear Connecticut, Inc. (Millstone Power Station) EA-17-077
On November 21, 2017, the NRC issued a Confirmatory Order (CO) to Dominion Nuclear Connecticut, Inc. (Dominion), to formalize commitments made as a result of an alternative dispute resolution (ADR) mediation session held on September 20, 2017. The commitments were made as part of a settlement agreement between Dominion and the NRC based on evidence gathered during an investigation in which the NRC had identified multiple examples of two apparent violations. The violations involved a, now-former, contract security officer who was employed by G4S Secure Solutions, USA, Inc. as an Armorer at Millstone who deliberately failed to: (1) perform required maintenance of site weapons; and (2) properly conduct monthly inventories of out of service weapons. The NRC also determined that the contract security officer deliberately falsified records related to both of these issues. Because licensees are responsible for the actions of their employees and contractors, the NRC concluded that the contract security officer's actions placed Millstone in violation of NRC requirements and the NRC-approved Millstone Security Plan. In response to the incident, Dominion agreed to complete additional corrective actions and enhancements, as fully discussed in the CO. In consideration of the corrective actions and commitments outlined in the CO, the NRC agreed not to pursue any further enforcement action (including issuance of a civil penalty) relating to the notice of apparent violations (Case no. EA-17-077, Inspection Report Nos. 05000336/2017405 & 05000423/2017405, Office of Investigations Report No. 1-2016-019), dated July 20, 2017.
Duke Energy Corporation (Catawba Nuclear Station, Unit 2) EA-17-122
On October, 16, 2017, the NRC issued a Notice of Violation to Duke Energy Corporation, for a violation of Technical Specification, 5.4.1.a, "Procedures," and Title 10 of the Code of Federal Regulations, Part 50, Appendix B, that were associated with a White Significance Determination Process finding at Catawba Nuclear Station, Unit 2. Specifically, the licensee failed to develop adequate preventive maintenance strategies for the emergency diesel generator (EDG) excitation system. As a result, a condition adverse to quality associated with elevated diode temperatures was uncorrected. This caused the 2A EDG output breaker to trip open during monthly surveillance testing.
FirstEnergy Nuclear Operating Company (Perry Nuclear Power Plant) EA-17-043
On August 24, 2017, the NRC issued a Notice of Violation to FirstEnergy Nuclear Operating Company (FirstEnergy) for a violation of Title 10 of the Code of Federal Regulations Part 50, Appendix B at Perry Nuclear Power Plant, associated with a White Significance Determination Process finding. Contrary to the requirements, FirstEnergy failed to conduct adequate design control of a modification to the electrical circuitry for emergency start of the site Standby Diesel Generators. Specifically, FirstEnergy failed to evaluate the effect of a shorted diode on the emergency start circuitry. Additionally, there is an associated violation of Technical Specification 3.8.1, "AC Sources Operating," for one Standby Diesel Generator being inoperable for greater than the allowed outage time of 14 days.
STP Nuclear Operating Company (South Texas Project Electric Generating Station) EA-16-216
On August 18, 2017, the NRC issued a Severity Level Ill Notice of Violation to STP Nuclear Operating Company for violations of 10 CFR 50.9, "Completeness and accuracy of information" and 10 CFR 50.48, "Fire protection". Specifically, the Notice of Violation involved two examples of failing to implement fire protection program written procedures for fire watches; and three examples of failing to ensure that fire protection documents were complete and accurate in all material respects.
Tennessee Valley Authority (Watts Bar Nuclear Plant) EA 17-022
On July 27, 2017, the NRC issued a Confirmatory Order (CO) to Tennessee Valley Authority (TVA) for a violation identified during the staff’s performance of a Problem Identification and Resolution (PI&R) inspection at Watts Bar Nuclear Plant (WBN) (ML17069A133). The CO is the result of a violation for failure to implement a 2009 Adverse Employee Action (AEA) Process Confirmatory Order (ML093510993). The PI&R inspection was conducted as follow-up for a chilled work environment letter (ML16083A479) that had been issued to WBN.
The new Order requires TVA to confirm proper implementation of all past orders, implement independent oversight for the AEA process, and take additional actions to understand and improve safety culture.
Energy Northwest (Columbia Generating Station) EA-17-028
On July 6, 2017, the NRC issued a Notice of Violation to Energy Northwest, for a violation associated with a White Significance Determination Process finding identified during an inspection at Columbia Generating Station. The White finding, an issue of low to moderate safety significance, involved Energy Northwest's failure to ship Type B quantity of radioactive material in a container that was approved or tested for that purpose. The significance of this event was based on the increased risk to the public and accident hazard posed when a Type B quantity of radioactive material was shipped in a container that was not approved or tested for that purpose. The violation involves the failure to transport low specific activity material in accordance with the condition that the external dose rate may not exceed an external radiation level of 10 mSv/hour (1 rem/hour) at 3 meters (10 feet) from the unshielded material. Specifically, the licensee transported a package as low specific activity material with an external radiation level of 2.1 rem/hour at a distance of 3 meters from the unshielded material.
DTE Energy Company (Fermi Power Plant, Unit 2) EA 17-012
On May 11, 2017, the NRC issued a Notice of Violation to DTE Energy Company (DTE Energy) for a violation of Title 10 of the Code of Federal Regulations 50.54(q)(2) at Fermi Power Plant, Unit 2, associated with a White Significance Determination Process finding. Contrary to the requirements, DTE Energy failed to maintain the effectiveness of its emergency plan and to use adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency. Specifically, the licensee failed to maintain the ability to accurately declare an Emergency Action Level Classification RG-1.1, and to develop and issue accurate protective action recommendations during the implementation of the site’s Emergency Plan in response to a rapidly progressing accident.
PSEG Nuclear, LLC (Hope Creek Generating Station) EA-16-251
On May 3, 2017, the NRC issued a Notice of Violation to PSEG Nuclear, LLC Hope Creek Generating Station (Hope Creek) for a Severity Level III violation associated with the failure to follow site procedures, resulting in a reactor scram. An investigation conducted by the NRC Office of Investigations determined that the technician deliberately failed to implement a procedure for a surveillance activity of safety-related equipment when the technician made an error while performing a surveillance test and deliberately attempted to correct the error rather than comply with the procedural guidance to stop and inform management. Specifically, the technician, who was performing a surveillance test on the Redundant Reactivity Control System (RRCS), inadvertently selected the wrong RRCS channel to test. Rather than immediately stopping and informing the job supervisor, as required by the procedure, the technician deliberately attempted to correct the error by selecting the proper channel.
Southern Nuclear Operating Co., Inc., (Vogtle Electric Generating Plant, Units 1 and 2) EA 17-014
On April 25, 2017, the NRC issued a Notice of Violation to Southern Nuclear Operating Co., Inc., for its failure to maintain the effectiveness of an emergency plan and have a standardized emergency action level scheme in use based on facility system and effluent parameters at Vogtle Electric Generating Plant, Units 1 and 2. This is a violation of 10 CFR 50.47(b)(4) and Appendix E to Part 50 and is associated with a White Significance Determination Process finding. Specifically, the emergency classifications for a General Emergency and Site Area Emergency contained effluent radiation monitor threshold values that were forty-two times different than the correct values. These radiation monitors were being relied upon to determine the magnitude of, and for continuously assessing the impact of the release of radioactive materials, as well as providing criteria for determining the need for notification and participation of local and State agencies.
Exelon Nuclear (Oyster Creek Nuclear Generating Station) EA-16-241
On April 13, 2017, the NRC issued a Notice of Violation to Exelon Nuclear (Exelon) for a violation of Technical Specification 6.8.1, “Procedures and Programs,” at Oyster Creek associated with a White Significance Determination Process finding. Specifically, Exelon failed to properly implement a procedure for rebuilding and reassembly of an electromagnetic relief valve. The maintenance instruction directed reinstallation of a lever plate with previously removed lock washers. By failing to reinstall the lock washers, the licensee caused excessive friction between the solenoid frame and the cut-out switch lever plate, causing the cut-out switch lever to become bound in the energized position and rendering the valve unable to perform its safety-related function. Additionally, this incorrect reassembly resulted in the relief valve being inoperable for greater than the Technical Specification allowed outage time for the Automatic Depressurization System.
Entergy Operations, Inc (Arkansas Nuclear One) EA-16-247
On February 27, 2017, the NRC issued a Notice of Violation to Entergy Operations, Inc., for a violation of Technical Specification 6.4.1.a, associated with a White Significance Determination Process finding at Arkansas Nuclear One, Unit 2. Technical Specification 6.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, "Quality Assurance Program Requirements," Revision 2, Appendix A, February 1978. Specifically, Entergy failed to properly pre-plan and perform maintenance on a diesel generator inboard bearing because of inadequate work instructions.
Exelon Generation Company, LLC (Dresden Nuclear Power) EA-16-236
On February 27, 2017, the NRC issued a Notice of Violation to Exelon Generation Company, LLC, for a violation of 10 CFR Part 50, Appendix B, Criterion III, "Design Control," associated with a White Significance Determination Process finding at Dresden Nuclear Power Station, Unit 3. Criterion III requires, in part, that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program. Specifically, from June of 2002 until July of 2016, Exelon failed to verify the adequacy of the design of a high pressure coolant injection auxiliary oil pump required for the successful operation of the high pressure injection system and subject to the requirements of Appendix B to 10 CFR Part 50.
PSEG Nuclear, LLC (Hope Creek Generating Station) EA-16-184
On February 6, 2017, the NRC issued a Notice of Violation to PSEG Nuclear, LLC, for a violation of 10 CFR, Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," associated with a White Significance Determination Process finding. Criterion V requires, in part, that activities affecting quality shall be prescribed by documented instructions and procedures and shall be accomplished in accordance with these instructions and procedures. During the spring of 2016, PSEG specifically failed to follow a procedure in place to detect and act upon water intrusion into the lubricating oil reservoir for the high pressure core injection system. Subsequently, high pressure core injection, a safety-related system, became inoperable for an extended period of time because of undetected water in the oil. Additionally, the extended period of inoperability exceeded the high pressure core injection system technical specification (TS 3.5.1.c) allowed outage time of 14 days. Both violations were documented in this Notice of Violation.
Page Last Reviewed/Updated Friday, March 20, 2020