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At 0000 hours on Sunday, February 20, 2011 … At 0000 hours on Sunday, February 20, 2011, the Pilgrim Nuclear Power Station (PNPS) commenced a controlled shutdown of the reactor due to the 'B' train of Reactor Building Closed Cooling Water (RBCCW) being declared inoperable at 1250 hours on February 18, 2011 and expected to exceed its 72-hour Limiting Condition for Operability (LCO) as required by TS prior to return to operable status.</br>With the plant operating at 100% power, leakage of Salt Service Water (SSW) was detected in the RBCCW system due to high chloride levels and increased inventory in the system. An investigation into the event determined that the source of the SSW was isolated to the 'B' RBCCW heat exchanger which is designed to cool RBCCW under normal and post-accident conditions. The quantity of the leakage was determined to exceed the design limits established to ensure post-accident operation of the system and the 'B' train of RBCCW was subsequently declared inoperable.</br>The leak identification and repair activities are expected to exceed the TS LCO for the RBCCW system and therefore a controlled shutdown of the reactor was initiated.</br>This event had no impact on the health and/or safety of the public.</br>The licensee has notified the NRC Senior Resident Inspector.</br>This 4-hour notification is being made in accordance with 10 CFR 50.72 (b)(2)(i).in accordance with 10 CFR 50.72 (b)(2)(i). +
05:00:00, 20 February 2011 +
00:55:00, 20 February 2011 +
05:00:00, 20 February 2011 +
At 0000 hours on Sunday, February 20, 2011 … At 0000 hours on Sunday, February 20, 2011, the Pilgrim Nuclear Power Station (PNPS) commenced a controlled shutdown of the reactor due to the 'B' train of Reactor Building Closed Cooling Water (RBCCW) being declared inoperable at 1250 hours on February 18, 2011 and expected to exceed its 72-hour Limiting Condition for Operability (LCO) as required by TS prior to return to operable status.</br>With the plant operating at 100% power, leakage of Salt Service Water (SSW) was detected in the RBCCW system due to high chloride levels and increased inventory in the system. An investigation into the event determined that the source of the SSW was isolated to the 'B' RBCCW heat exchanger which is designed to cool RBCCW under normal and post-accident conditions. The quantity of the leakage was determined to exceed the design limits established to ensure post-accident operation of the system and the 'B' train of RBCCW was subsequently declared inoperable.</br>The leak identification and repair activities are expected to exceed the TS LCO for the RBCCW system and therefore a controlled shutdown of the reactor was initiated.</br>This event had no impact on the health and/or safety of the public.</br>The licensee has notified the NRC Senior Resident Inspector.</br>This 4-hour notification is being made in accordance with 10 CFR 50.72 (b)(2)(i).in accordance with 10 CFR 50.72 (b)(2)(i). +
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00:00:00, 20 February 2011 +
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22:28:34, 24 September 2017 +
00:55:00, 20 February 2011 +
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05:00:00, 20 February 2011 +
Technical Specification Required Shutdown-Reactor Building Closed Cooling Water Train Inoperable +
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