ENS 41354
ENS Event | |
|---|---|
21:10 Jan 24, 2005 | |
| Title | Unusual Event Due to Unidentified Leakage Greater than 10 Gpm |
| Event Description | The licensee reported that it had indications of unidentified reactor coolant leakage greater than 10 gpm which placed the licensee into an unusual event emergency action level (EAL). Indication of drywell sump level increase and pump out rate gave an approximate leak rate of 30 gpm. The licensee also indicated that drywell pressure was above the normal range. The unusual event declaration was made at 1610 EST.
At 1619 EST, the licensee manually scrammed the reactor. The scram was uncomplicated with all rods fully inserting and all systems functioning as required. Decay heat is being rejected to the main condenser. There has been no ECCS injection actuation and reactor water level is being maintained by feed pumps. The licensee has no significant safety related equipment out of service. The licensee stated that there is no indication of further degradation of the leak rate and the source of the leak is still under investigation The licensee has notified the NRC Resident Inspector along with State, Local, and other government agencies.
At 1640 EST, the licensee upgraded to an ALERT following additional leak rate calculations that indicated the leak rate was approximately 75 - 80 gpm based on drywell sump pump out rate. The licensee's EAL for an alert is RCS leakage greater than 50 gpm. The NRC entered the monitoring mode at 1653 EST. The licensee stated that there has been no increase in drywell radiation levels and that sump water chemistry analysis is in progress. In addition to the normal government agencies notified, the NRC also notified the Canadian Nuclear Safety Commission Duty Officer (R. Chamberlaine).
The licensee has indications that the leakage may not be reactor coolant leakage. Chemistry results show that the sump water radiation levels are at a level less than would be expected for RCS leakage. In addition, a secondary cooling system was found in a lineup configuration that could have masked leakage from the system. The licensee is waiting to get additional chemistry results on the presence of corrosion inhibitors in the sump water to provide additional confirmation that the leakage is not from the RCS.
The licensee confirmed the presence of corrosion inhibitors in the drywell sump. In addition, based on manipulations of the Reactor Building Closed Cooling Water system and the Emergency Equipment Cooling Water system the licensee believes that the leakage is from the Reactor Building Closed Cooling Water system and not RCS leakage. The plant is stable and the licensee is continuing to cool down with pressure now at 180 psi and decreasing.
The licensee terminated its Alert and Unusual Event at 22:28 EST based on sump water chemistry, activity, and Reactor Building Closed Cooling Water System manipulations that indicate the leakage is secondary cooling water and not from the RCS. The NRC secured from the monitoring mode at 22:36 EST. Notified DHS (Belt), FEMA (Caldwell), DOE (Dasilva), EPA (Baumgartner) USDA (Sykes), and HHS( Pyles). The Canadian Nuclear Safety Commission Duty Officer (R. Chamberlaine) was also notified. |
| Where | |
|---|---|
Fermi  Michigan (NRC Region 3) | |
| Reporting | |
| Emergency class: | Alert |
| 10 CFR 50.72(a) (1) (i), Emergency Class Declaration 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000341/LER-2005-001 |
| Time - Person (Reporting Time:+-4.7 h-0.196 days <br />-0.028 weeks <br />-0.00644 months <br />) | |
| Opened: | Phil Skorbek 16:28 Jan 24, 2005 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Jan 24, 2005 |
| 41354 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
Fermi with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration | |
WEEKMONTHYEARENS 570462024-03-23T04:04:00023 March 2024 04:04:00
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