ENS 43421
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ENS Event | |
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13:10 Jun 14, 2007 | |
Title | Unable to Perform Safe Shutdown as a Result of Appendix R Fire Affecting Hpci |
Event Description | During verification of plant procedures associated with achieving safe shutdown during and after an Appendix R fire, it was determined that there was no readily available success path to secure HPCI when required. The scenario in question involves a fire-induced spurious HPCI initiation that must be terminated within 10 minutes to prevent flooding main steam lines and disabling both available methods of hot shutdown. For this event, RCIC is one defined method of temperature and pressure control to achieve hot shutdown. The other defined method requires ADS valves to lower pressure to allow CS to provide makeup water. As written, the procedure steps provided to Operations personnel would not have been sufficient to isolate steam to the HPCI turbine. All other methods to secure HPCI that would have been reasonably available required operation of components that could have been affected by the same fire that caused the spurious initiation of HPCI.
The procedures have been changed to provide Operations personnel adequate and effective instructions to isolate HPCI when required after a spurious initiation during an Appendix R fire. This is being reported under 10 CFR 50.72(b)(3)(v)(A) as a condition that could have prevented the plant from achieving safe shutdown. The Senior Resident Inspector has been notified. |
Where | |
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Cooper ![]() Nebraska (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | |
Time - Person (Reporting Time:+1.17 h0.0488 days <br />0.00696 weeks <br />0.0016 months <br />) | |
Opened: | Roy Giles 14:20 Jun 14, 2007 |
NRC Officer: | Joe O'Hara |
Last Updated: | Jun 14, 2007 |
43421 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 434212007-06-14T13:10:00014 June 2007 13:10:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Unable to Perform Safe Shutdown as a Result of Appendix R Fire Affecting Hpci 2007-06-14T13:10:00 | |
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