ENS 41118
ENS Event | |
|---|---|
19:41 Oct 13, 2004 | |
| Title | Reactor Coolant Leakage Outside Containment Exceeding Final Safety Analysis Limits |
| Event Description | This is all 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. The event is being reported under paragraph (b)(3)(v) of 10 CFR 50.72.
On 10/13/04 at 1541, the control room was notified that tight system isolation boundaries could not be achieved on the 23 Charging pump [positive displacement pump]. The pump was tagged to support maintenance. Although the leak rate has not been quantified, it is suspected that it was greater than the UFSAR limit for ECCS leakage outside containment. With leakage greater than the UFSAR allowed limits (greater than 3840 cc/hr), GDC-19 limits for control room habitability cannot be assured. Actions have been completed to restore system integrity. The affected positive displacement charging pump is not a safety related pump and is not required for accident mitigation; however it is exposed to the ECCS recirculation flow path during the cold leg injection phase of the accident mitigation. The licensee has notified the NRC Resident Inspector of this event. The local township will also be notified. The licensee stated that the leakage has been isolated; there was no indication of an increase in radiation levels during the leakage; and that the duration of the leakage was approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+-0.45 h-0.0188 days <br />-0.00268 weeks <br />-6.1641e-4 months <br />) | |
| Opened: | Rick Desanctis 19:14 Oct 13, 2004 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Oct 13, 2004 |
| 41118 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |