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| Quarter | Site | Title | Description | |
|---|---|---|---|---|
| 05000373/FIN-2005010-01 | 2005Q2 | LaSalle | Modifications Made to the Emergency Diesel Generator Output Circuit That Were Not Subject to Design Control Measures Commensurate with Those Applied to the Original Design | An apparent violation having a preliminary low to moderate safety significance was identified during the licensees review of a similar issue identified at Crystal River Nuclear Plant Unit 3 on January 27, 2005. A design deficiency in a metering circuit for the sites normal 4160 volts-alternating current (Vac) offsite power supply induced a vulnerability whereby a single fault in the metering circuitry, for a given unit, could have resulted in the loss of all Division 1 and Division 2 safety-related 4160 Vac power on a given unit. The finding was determined to be greater than minor because it impacted both the Initiating Events and Mitigating Systems Cornerstones. The finding was preliminarily determined to be of low to moderate safety significance following the performance of a case-specific Phase 3 SDP. Corrective actions taken by the licensee included installing temporary modifications on each unit to remove the metering circuitry in question. |
| 05000263/FIN-2005003-05 | 2005Q2 | Monticello | Failure to Report Inadvertent Engineered Safety System Actuations During Testing | The inspectors identified a Severity Level IV violation when the licensee failed to make a notification, within 8 hours, to the NRC Operations Center, in accordance with 10 CFR 50.72(b)(3)(iv)(A), for an event involving loss of bus 16 and actuation of engineered safety features on April 2, 2005. The licensee did not restore compliance or take any corrective actions. Because this issue affected the NRCs ability to perform its regulatory function, it was evaluated using the traditional enforcement process. The violation of 10 CFR 50.72 is categorized in accordance with the NRC Enforcement Policy at Severity Level IV. Since the licensee failed to place the violation into a corrective action program to address recurrence, the violation was cited. |
| 05000373/FIN-2004002-06 | 2004Q1 | LaSalle | Unauthorized Entry Into Unit 1 694' Reactor Building Raceway HRA by Contract Personnel | On January 25, 2004, a contract foreman and three contract workers were assigned to conduct outage work associated with a valve located in the reactor building. In preparation for the work, the foreman signed in on a radiation work permit (RWP) associated with entry into HRAs located in the turbine and auxiliary buildings but not for entry into the Unit 1 reactor building raceway described below. The three contract workers signed in on a pre-outage RWP associated with minor maintenance activities which did not permit entry into HRAs. During a walk down of the work, the contract workers could not locate the valve, and the foreman took the contract workers into a posted HRA in the Unit 1 reactor building raceway to locate the valve. Prior to entering the HRA, at least one of the contract workers told the foreman that the contract workers were not signed in on an RWP that permitted entry into HRAs. Before entering the HRA, two of the contract workers were aware that they had not received a briefing by radiation protection personnel for the HRA, a prerequisite for entry into HRAs. Therefore, the actions of the foreman and two contractor workers are considered a willful violation, representing careless disregard of requirements, and the violation has been categorized in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600 at Severity Level III. |