ML20027B057

LER 82-007/01T-1:on 820825,updated Secondary Containment Vol Calculation Had Not Replaced Preliminary Analysis Utilized to Obtain Values in Fsar.Vol Based on Preliminary Calculation Which Did Not Account for Floors & Equipment

ML20027B057
Person / Time
Site:	Susquehanna
Issue date:	09/08/1982
From:	Mitchell D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20027B048	List: ML20027B046 ML20027B057
References
LER-82-007-01T, LER-82-7-1T, NUDOCS 8209160302
Download: ML20027B057 (2)

Text

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o l2 l l Prior to initial criticality. It was determined through n vn-ovninneinn nr ehn l l o 13 l l Reactor buildinn free air volumn rhnt rho n11munhin l on te v,epliarod in TnchnienLl lo I4 l l Specifications was incorrect. The flow rate from secondary containmont thrnughl l 0 l5 l l the Standby Gas Treatment System should therefore. be limited to lounr vnlnnn en I l o le j l prevent exceeding design basis LOCA doses and 10CFR limits. This event is l l o l 7 l l reportable per 6.9.1.8.h. Prior to initial criticality there is insufficient l limits at currently specified flow rates. l l o l 8 l l radioactive inventory to exceed dose

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l i l1 l lwhich did not account for floors, equipment, and filling the spent fuel pool. l l 1 l 2 l l All actions which require secondary containment integrity were halted. An evo- l l1l3! Ut19R WS_ pCrformad_which supported _9peration at_the values contained in Tech l l 1 l 4 l l Specifications , prior to initial criticality. [

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SSES ER 100450 File 841-23 Attachment to PLA- 1283 LICENSEE EVENT REPORT 82-007/0lT-1 The corporate engineering staff informed the plant that, while reviewing allowable leak rate calculations, it was determined that an updated secondary containment volume calculation had not replaced the preliminary analysis utilized to obtain the values presented in the FSAR. By using the more accurate volume, the new allowable leak rate decreased from 3050 cfm to 2885 cfm (2300 cfm to 2000 cfm with the interim barrier installed in Zone III).

This in leakage corresponds to the Standby Gas Treatment System flow rate as listed in the Technical Specifications 4.6.5.1. The allowable offsite doses could be exceeded during a LOCA with the flow rates listed in Technical Specifications, and is therefore reportable, per 6.9.1.8.h.

Upon receipt of this information, the plant staff ceased all operations which required secondary containment. An evaluation was performed which determined that the Standby Gas Treatment System operated at 2300 cfm will not impact safe operation, due to the lack of fission products in the core, prior to initial criticality.

A Technical Specification change was received from the NRC, revising the flow rates to 2885 cfm (2000 cfm with interim barrier installed), and the Standby Gas Treatment System was retested to verify this requirement.