ENS 44252
ENS Event | |
|---|---|
16:48 Jun 1, 2008 | |
| Title | Lube Oil Moisture Content Greater than Acceptable Limit |
| Event Description | A sample was taken of the lubrication/control oil from the Unit 1 High Pressure Coolant Injection (HPCI) System for moisture content analysis. The results of this analysis concluded that the moisture content in the oil exceeded acceptable levels. As a result of this condition the Browns Ferry Nuclear Unit 1 HPCI system was declared inoperable at 11:48 on 6/1/08.
This event is reportable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in accordance with 10 CFR 50.72 (b)(3)(v) as event or condition that at the time of discovery could have prevented the fulfillment of a safety function. It also requires a 60 day written report in accordance with 10 CFR 50.73 (a)(2)(vii). Unit 1 remains at 100% power. Unit 1 has entered Technical Specification LCO 3.5.1 and is performing the required actions. Troubleshooting of the moisture intrusion condition is in progress, and a corrective action plan is being developed. The NRC Resident inspector has been notified.
ENS Event Number 44252, made on June 1, 2008, is being retracted. NRC Notification 44252 was conservatively made to ensure that the Eight-Hour Non-Emergency reporting requirements of 10 CFR 50.72 were met when an oil sample indicated the Unit 1 High Pressure Coolant Injection (HPCI) System turbine oil system contained excessive amounts of water. An evaluation performed in response to this report concluded that the Unit 1 HPCI System was capable of performing its intended safety function with the turbine oil system containing more water than recommended in the TVA Lubrication Oil Analysis and Monitoring Program. TVA found through an engineering evaluation that the amount of water contained in the turbine oil system would not impact the HPCI operation during its mission time for the Design Basis Loss-of-Coolant Accident. As such, the circumstances discussed in the report did not result in any condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat, or mitigate the consequences of an accident. Thus, there was no impact on nuclear safety. Therefore, this event is not reportable under 10 CFR 50.72(b)(3)(v)(B) or 10 CFR 50.72(b)(3)(v)(D). TVA's evaluation of this issue is documented in the corrective action program (PER 145517). The licensee has notified the NRC Resident Inspector. R2DO (Haag) notified. |
| Where | |
|---|---|
Browns Ferry  Alabama (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+0.75 h0.0313 days <br />0.00446 weeks <br />0.00103 months <br />) | |
| Opened: | Joe Bennett 17:33 Jun 1, 2008 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Jul 17, 2008 |
| 44252 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |