ML112220608
| ML112220608 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 04/29/2002 |
| From: | NRC/RGN-III/DRMA |
| To: | |
| References | |
| EA-03-057 IR-01-017 | |
| Download: ML112220608 (11) | |
Text
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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
Agenda Regulatory Conference
- Opening Remarks
.. J. Grobe, Director, DRS
- Description of Issues
.. R. Langstaff, Inspector, DRS
- Licensee Presentation
- Closing Remarks
.. J. Dyer, Regional Administrator
Potential Common Mode Failure Auxiliary Feedwater Pumps
- Operator actions to control AFW flow (in conjunction with recirculation valves failed shut) could result in low/no flow conditions for AFW pumps
- Pump damage would result within a short period of time due to low/no flow conditions
Operator Actions EOP Guidance
... Res Overcooling
... SG Overfill
- flow (i.e., throttling/closing valves versus securing pumps)
- Operators would typically throttle/close valves versus secure pumps
Operator Actions Overcooling of Res
- At the time operators control flow, recirculation valves may still be open due to remaining IA header pressure
Operator Actions Overfilling SG's
- Operator actions to control AFW flow to mitigate SG overfill typically required> 1 0 minutes into transient
- Recirculation valves expected to already have failed shut due to loss of IA
- Operators may fail to recognize recirculation valves had failed shut and associated consequences
Inadequate Procedure Guidance Regulatory Issue
- EOPs for Reactor Trip Response were not appropriate for the circumstances
- Procedures did not provide adequate guidance to operators regarding the potential to damage AFW pumps while controlling AFW flow upon low IA header pressure
- Apparent Violation of 1 0 CFR 50, Appendix B, Criterion V
Inadequate Corrective Action Regulatory Issue
- Licensee had seven prior opportunities to focus on the impact of recirculation valve closure
- Apparent Violation of 1 0 CFR 50, Appendix B, Criterion XVI
Risk Significance Preliminary Red (High Safety Significance)
- Relatively high frequency of applicable initiating events involving loss of IA
~ Loss of IA
~ Loss of Off-Site Power
~ Loss of Service Water
~ Seismic Event
- Substantially reduced mitigation capability
~ Main Feedwater Reliance on IA
~ Pressurizer PORV Reliance on IA
Abbreviations
.. 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
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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 Room 03B4 - Video Conference Location at One White Flint North Organization Deirdre Spaulding NRC/NRRlDLPM/PDIII Tim Frye NRC/NRR Mindy Landau NRC/EDO Daniel Horner McGraw - Hill Michelle Johnson ABS Consulting for NRC/RES Eliezer B. Goldfeiz NRC/RES Peter Wilson NRC/NRRlDSSA S. Sing Bajwa NRC/NRRIDLPM/PDIII Dave Nelson NRC/OE