ENS 52181
ENS Event | |
|---|---|
19:52 Aug 15, 2016 | |
| Title | Salt Service Water System Declared Inoperable |
| Event Description | On Monday, August 15, 2016 at 1552 [EDT], with the reactor at [about] 70 percent core thermal power (CTP), Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation Action Statement (LCO-AS) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO-AS was subsequently exited at 1651 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.282055e-4 months <br /> when the temperature of SSW trended to below the TS limit.
Under certain design conditions, the SSW system is required to provide cooling water to various heat exchangers such as the Reactor Building Closed Cooling Water (RBCCW) and Turbine Building Closed Cooling Water (TBCCW) systems. When the inlet temperature to these supplied loads exceeds the 75 degrees F limit established in the TS, the SSW system is conservatively declared inoperable until the temperature trends below this value. This condition existed for approximately 60 minutes. The SSW temperature is being closely monitored and trended on a continuous basis. This event has no impact on the health and safety of the public. The licensee has notified the NRC Senior Resident Inspector. This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(B) and 10 CFR 50.72(b)(3)(v)(D) due to an event or condition that could have prevented fulfillment of a safety function. The licensee will be notifying the Commonwealth of Massachusetts Emergency Management Agency. |
| Where | |
|---|---|
| Pilgrim Massachusetts (NRC Region 1) | |
| 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:+-2.07 h-0.0863 days <br />-0.0123 weeks <br />-0.00284 months <br />) | |
| Opened: | Kenneth Goodall 17:48 Aug 15, 2016 |
| NRC Officer: | Vince Klco |
| Last Updated: | Aug 15, 2016 |
| 52181 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (70 %) |
| After | Power Operation (62 %) |