ENS 52655
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ENS Event | |
|---|---|
15:55 Mar 31, 2017 | |
| Title | Pressure Suppression Pool Declared Inoperable Due to Torus High Water Level |
| Event Description | On March 31, 2017 at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> [EDT], with the reactor at 97% core thermal power and steady state conditions, operators inadvertently caused water level to rise in the Pressure Suppression Pool (TORUS). Pilgrim Nuclear Power Station (PNPS) was restoring normal system valve line-ups after performing flushing of the suction piping of the Core Spray system in accordance with station procedures. During the process of restoring the appropriate valve line-ups, water was inadvertently transferred to the TORUS from the Condensate Storage Tank. The cause of the event is understood.
The Technical Specification (TS) Limiting Condition for Operation (LCO) Action Statement (AS) 3.7.A.5 was entered. The LCO AS was exited at 1540 when TORUS water level was restored to the limits specified in LCO's 3.7.A.1.b and 3.7.A.1.m. Because the TORUS was declared inoperable, PNPS is providing an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(v)(D), an event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. This was a case of the water level in the TORUS being above the TS limit. The TORUS was potentially available to provide cooling to the reactor if required. The NRC Resident Inspector has been notified. The licensee notified the Commonwealth of Massachusetts and Plymouth County. |
| Where | |
|---|---|
| Pilgrim Massachusetts (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:+3.32 h0.138 days <br />0.0198 weeks <br />0.00455 months <br />) | |
| Opened: | Kenneth Gracia 19:14 Mar 31, 2017 |
| NRC Officer: | Vince Klco |
| Last Updated: | Mar 31, 2017 |
| 52655 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (97 %) |
| After | Power Operation (97 %) |
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