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On February 06, 2012, at 1524 PST, enginee … On February 06, 2012, at 1524 PST, engineers reviewing dose analyses for non-LOCA, non-fuel handling accident analyses identified deficiencies in the analyses. The analyses of concern include a locked reactor coolant pump rotor, a control rod ejection accident, main steam line break, and steam generator tube rupture. These deficiencies brought into question whether the 30 day control room operator dose received following one of these accidents would meet the station licensing basis limits of up to 5 rem whole body or its equivalent. </br>In response to this concern, plant operators placed the control room ventilation system in its safeguards alignment, thereby ensuring the events would continue to be bounded by the analysis of the large break loss of coolant accident. </br>The NRC Resident Inspector has been notified.</br>* * * RETRACTION FROM DAVID BAHNER TO CHARLES TEAL ON 02/28/13 AT 1815 EST * * *</br>Pacific Gas and Electric Company (PG&E) is correcting the event date in the above Description to February 06, 2013, and is retracting EN 48726 based on the results from reanalysis of each affected non-loss-of-coolant accident (LOCA) event (i.e., steam generator tube rupture, main steam line break, control rod ejection, and reactor coolant pump locked rotor) for potential impact on control room operator dose. The new dose assessment determined that control room dose consequences from a large-break LOCA bound the non-LOCA events as assumed in the original analyses. Accordingly, PG&E concludes the Diablo Canyon Power Plant control room ventilation system remains capable of maintaining control room dose limits within General Design Criteria-19.</br>Plant personnel notified the NRC resident inspector.</br>Notified R4DO (Allen).the NRC resident inspector.
Notified R4DO (Allen). +
23:24:00, 6 February 2013 +
48,726 +
21:23:00, 6 February 2013 +
23:24:00, 6 February 2013 +
On February 06, 2012, at 1524 PST, enginee … On February 06, 2012, at 1524 PST, engineers reviewing dose analyses for non-LOCA, non-fuel handling accident analyses identified deficiencies in the analyses. The analyses of concern include a locked reactor coolant pump rotor, a control rod ejection accident, main steam line break, and steam generator tube rupture. These deficiencies brought into question whether the 30 day control room operator dose received following one of these accidents would meet the station licensing basis limits of up to 5 rem whole body or its equivalent. </br>In response to this concern, plant operators placed the control room ventilation system in its safeguards alignment, thereby ensuring the events would continue to be bounded by the analysis of the large break loss of coolant accident. </br>The NRC Resident Inspector has been notified.</br>* * * RETRACTION FROM DAVID BAHNER TO CHARLES TEAL ON 02/28/13 AT 1815 EST * * *</br>Pacific Gas and Electric Company (PG&E) is correcting the event date in the above Description to February 06, 2013, and is retracting EN 48726 based on the results from reanalysis of each affected non-loss-of-coolant accident (LOCA) event (i.e., steam generator tube rupture, main steam line break, control rod ejection, and reactor coolant pump locked rotor) for potential impact on control room operator dose. The new dose assessment determined that control room dose consequences from a large-break LOCA bound the non-LOCA events as assumed in the original analyses. Accordingly, PG&E concludes the Diablo Canyon Power Plant control room ventilation system remains capable of maintaining control room dose limits within General Design Criteria-19.</br>Plant personnel notified the NRC resident inspector.</br>Notified R4DO (Allen).the NRC resident inspector.
Notified R4DO (Allen). +
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