ENS 49201
ENS Event | |
|---|---|
14:54 Jul 17, 2013 | |
| Title | Salt Service Water System Declared Inoperable |
| Event Description | On Wednesday, July 17, 2013 at 1054 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.01047e-4 months <br /> EDT, with the reactor at 100% core thermal power (CTP) the Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation (LCO) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO was subsequently exited at 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> when the temperature of SSW trended to below the TS limit.
Under certain accident conditions the SSW system is required to provide cooling water to the Reactor Building Closed Cooling Water (RBCCW) system heat exchanger. When the inlet temperature to this supplied load exceeds the 75 [degrees] F limit established in the TS, the SSW system is declared inoperable until the temperature trends below this value. This condition existed for approximately 5-1/2 hours and the SSW system was declared operable and the LCO exited. A maximum temperature of 75.5 [degrees] F was recorded during this period. At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> a power reduction was conducted to improve secondary plant parameters and Rx power is currently 85%. 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." The licensee will notify the Commonwealth of Massachusetts. |
| 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:+2.8 h0.117 days <br />0.0167 weeks <br />0.00384 months <br />) | |
| Opened: | Mike Hettwer 17:42 Jul 17, 2013 |
| NRC Officer: | Dong Park |
| Last Updated: | Jul 17, 2013 |
| 49201 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (85 %) |