ENS 41546
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ENS Event | |
|---|---|
16:57 Mar 29, 2005 | |
| Title | Actuation of the Reactor Protection System and Auxiliary Feedwater System While Establishing Initial Conditions for Leak Test in Mode 3. |
| Event Description | The licensee faxed the following information:
On 3/29/05, with the Callaway plant at 0 % power in Mode 3, Steam Generator (S/G) levels were being maintained using 'B' Condensate Pump. Reactor Coolant System (RCS) temperature was being controlled using Condenser Steam Dumps. Preparation was in progress for performance of a leak test on Main Feedwater Isolation Valve AEFV0041. As part of the leak test, condensate flow was temporarily isolated to 'C' S/G and the Auxiliary Feedwater System was aligned to provide water to the 'C' S/G. When low was initiated to 'C' S/G using auxiliary Feedwater, level initially increased due to the injection of a small volume of warm water contained within the Feedwater piping at the S/G, then proceeded to rapidly decrease due to S/G shrink caused by the injection of Auxiliary Feedwater with a temperature of approximately 70 degree F. Level in 'C' S/G decreased until S/G Lo Lo Level reactor trip and Auxiliary Feedwater Actuation signals were generated. Performance of the leak test was terminated and RCS temperature and S/G levels were stabilized at normal parameters for Mode 3. The licensee informed the NRC Resident Inspector. |
| Where | |
|---|---|
Callaway  Missouri (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+2.17 h0.0904 days <br />0.0129 weeks <br />0.00297 months <br />) | |
| Opened: | J. Milligan 19:07 Mar 29, 2005 |
| NRC Officer: | John Knoke |
| Last Updated: | Mar 29, 2005 |
| 41546 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 570432024-03-22T01:56:00022 March 2024 01:56:00
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