ML021970080

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NRC Regulatory Conference Slides, Potential Common Mode Failure of Auxiliary Feedwater
ML021970080
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 04/29/2002
From:
NRC/RGN-III
To:
References
IR-01-017
Download: ML021970080 (10)


Text

Point Beach Potential Common Mode Failure of Auxiliary Feedwater Regulatory Conference April 29, 2002 NRC Inspection Report 50-266/01-17; 50-301/01-17

POpening Remarks

 J. Grobe, Director, DRS PDescription of Issues

 R. Langstaff, Inspector, DRS PLicensee Presentation PClosing Remarks

 J. Dyer, Regional Administrator Agenda Regulatory Conference

PAFW recirculation valves require IA to open PLoss of IA causes AFW recirculation valves to fail shut by design POperator actions to control AFW flow (in conjunction with recirculation valves failed shut) could result in low/no flow conditions for AFW pumps PPump damage would result within a short period of time due to low/no flow conditions Potential Common Mode Failure Auxiliary Feedwater Pumps

PEOPs directed operators to control AFW flow in response to

 RCS Overcooling

 SG Overfill PEOPs did not specify method to control AFW flow (i.e., throttling/closing valves versus securing pumps)

POperators would typically throttle/close valves versus secure pumps Operator Actions EOP Guidance

POperator actions to control AFW flow may be required within a few minutes of the transient PAt the time operators control flow, recirculation valves may still be open due to remaining IA header pressure PRecirculation valves may subsequently shut due to decreasing IA header pressure Operator Actions Overcooling of RCS

POperator actions to control AFW flow to mitigate SG overfill typically required > 10 minutes into transient PRecirculation valves expected to already have failed shut due to loss of IA POperators may fail to recognize recirculation valves had failed shut and associated consequences Operator Actions Overfilling SGs

PEOPs for Reactor Trip Response were not appropriate for the circumstances PProcedures did not provide adequate guidance to operators regarding the potential to damage AFW pumps while controlling AFW flow upon low IA header pressure PApparent Violation of 10 CFR 50, Appendix B, Criterion V Inadequate Procedure Guidance Regulatory Issue

PLicensee had seven prior opportunities to focus on the impact of recirculation valve closure PApparent Violation of 10 CFR 50, Appendix B, Criterion XVI Inadequate Corrective Action Regulatory Issue

PRelatively high frequency of applicable initiating events involving loss of IA

 Loss of IA

 Loss of Off-Site Power

 Loss of Service Water

 Seismic Event PSubstantially reduced mitigation capability

 Main Feedwater Reliance on IA

 Pressurizer PORV Reliance on IA Risk Significance Preliminary Red (High Safety Significance)

 AFW - Auxiliary Feedwater

 CFR - Code of Federal Regulations

 EOP - Emergency Operating Procedure

 GL - Generic Letter

 IA - Instrument Air

 PORV - Power Operated Relief Valve

 RCS - Reactor Coolant System

 SG - Steam Generator Abbreviations