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The following information was provided by … The following information was provided by the licensee via phone and email:</br>On March 4, 2023, it was determined that the main steam line (MSL) local leak rate test results for MSL 'B' were in exceedance of technical specification (TS) surveillance requirement (SR) 3.6.1.3.10 limits. Additionally, the leakage at the outboard main steam isolation valve (MSIV) 'B', was indeterminate due to a gross packing gland leak. An engineering calculation dated April 6, 2023, showed that this leakage, in conjunction with a design basis loss of coolant accident, would result in the radiological dose exceeding Updated Safety Analysis Report limits to the exclusion area boundary, the low population zone, and the control room. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B) as a condition that results in the power plant being in an unanalyzed condition that degrades plant safety.</br>Both inboard and outboard 'B' MSIVs have been reworked and are within the TS SR limits. </br>There was no impact on the health and safety of the public or plant personnel. </br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified. +
20:46:00, 6 April 2023 +
16:46:00, 6 April 2023 +
20:46:00, 6 April 2023 +
The following information was provided by … The following information was provided by the licensee via phone and email:</br>On March 4, 2023, it was determined that the main steam line (MSL) local leak rate test results for MSL 'B' were in exceedance of technical specification (TS) surveillance requirement (SR) 3.6.1.3.10 limits. Additionally, the leakage at the outboard main steam isolation valve (MSIV) 'B', was indeterminate due to a gross packing gland leak. An engineering calculation dated April 6, 2023, showed that this leakage, in conjunction with a design basis loss of coolant accident, would result in the radiological dose exceeding Updated Safety Analysis Report limits to the exclusion area boundary, the low population zone, and the control room. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B) as a condition that results in the power plant being in an unanalyzed condition that degrades plant safety.</br>Both inboard and outboard 'B' MSIVs have been reworked and are within the TS SR limits. </br>There was no impact on the health and safety of the public or plant personnel. </br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified. +
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