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On October 27, 2006, plant personnel deter … On October 27, 2006, plant personnel determined that Technical SpecifiCation (TS) Surveillance Requirement (SR) 3.4.1.1, which verifies that the recirculation pump speeds are within 20% of each other when operating at less than 75% of rated core flow or within 10% of each other when operating at greater than or equal to 75% of rated core flow, does not provide adequate assurance that the recirculation loops are operating within the initial conditions of the existing design bases loss of coolant accident (LOCA) analysis. SR 3.4.1.1 was a new surveillance, added during Brunswick Steam Electric Plants (BSEP) conversion to the Improved Technical Specifications in 1998. SR 3.4.1.1 required the recirculation loops to be operated with matched pump speeds, instead of matched pump flows, due to availability of control room indication.</br></br>This event is being reported in accordance with 10 CFR 50.73(a)(2)(ii)(B), as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degraded plant safety.</br></br>The root cause of this event was determined to be ineffective implementation of the SR due to not fully understanding the relationship between recirculation pump speed mismatch and core flow mismatch.</br></br>Corrective actions included issuing a new surveillance procedure to ensure plant operation within the design basis limits, and revising the Limited Condition of Operation (LCO) requirements of TS 3.4.1 and SR 3.4.1.1.) requirements of TS 3.4.1 and SR 3.4.1.1. +
October 27, 2006 +
On October 27, 2006, plant personnel deter … On October 27, 2006, plant personnel determined that Technical SpecifiCation (TS) Surveillance Requirement (SR) 3.4.1.1, which verifies that the recirculation pump speeds are within 20% of each other when operating at less than 75% of rated core flow or within 10% of each other when operating at greater than or equal to 75% of rated core flow, does not provide adequate assurance that the recirculation loops are operating within the initial conditions of the existing design bases loss of coolant accident (LOCA) analysis. SR 3.4.1.1 was a new surveillance, added during Brunswick Steam Electric Plants (BSEP) conversion to the Improved Technical Specifications in 1998. SR 3.4.1.1 required the recirculation loops to be operated with matched pump speeds, instead of matched pump flows, due to availability of control room indication.</br></br>This event is being reported in accordance with 10 CFR 50.73(a)(2)(ii)(B), as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degraded plant safety.</br></br>The root cause of this event was determined to be ineffective implementation of the SR due to not fully understanding the relationship between recirculation pump speed mismatch and core flow mismatch.</br></br>Corrective actions included issuing a new surveillance procedure to ensure plant operation within the design basis limits, and revising the Limited Condition of Operation (LCO) requirements of TS 3.4.1 and SR 3.4.1.1.) requirements of TS 3.4.1 and SR 3.4.1.1. +
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05:20:33, 1 December 2017 +
December 22, 2006 +
October 27, 2006 +
Technical Specifications for Reactor Recirculation Pump Speed Match Criteria is Non-Conservative. +
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