ENS 41856
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ENS Event | |
|---|---|
09:51 Jul 20, 2005 | |
| Title | Minimum Recirculation Valves Will Not Automatically Open in Local Operating Mode |
| Event Description | While performing a test start of P-38A Motor Driven Auxiliary Feedwater Pump utilizing the local control station, it was discovered that AF-4007, the mini-recirculation valve for P-38A would not automatically open in the local mode of operation. The mini-recirculation valve provides a minimum flow path for pump operation to prevent pump damage. After this condition was discovered, a review of procedures associated with initiating safe shutdown via local operation disclosed that the procedure did not address manually opening the mini-recirculation valve prior to local pump start. As a result, pump damage could occur due to no flow though the pump prior to aligning a flow path into a steam generator. This condition is also applicable to AF-4014, the mini-recirculation valve for P-38B Motor Driven Auxiliary Feedwater Pump.
P-38A and P-38B Motor Driven Auxiliary Feedwater pumps would only be used in a safe shutdown local control condition if steam generator level could not be maintained using the normal means of 1P-29 and 2P-29 Turbine Driven Auxiliary Feedwater Pumps. The station has taken compensatory actions to brief the operators about the condition. Additionally, temporary procedure changes are in progress to direct the operator to manually open each Motor Driven Auxiliary Feedwater Pump's associated mini-recirculation valve prior to a local start of the P-38A or P-38B Motor Driven Auxiliary Feedwater Pump. The associated mini-recirculation valve will operate when P-38A or P-38B Motor Driven Auxiliary Feedwater Pump is started from the control room. Follow up testing has verified P-38A Auxiliary Feedwater Pump operability. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Point Beach  Wisconsin (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+2.93 h0.122 days <br />0.0174 weeks <br />0.00401 months <br />) | |
| Opened: | Charles Stalzer 12:47 Jul 20, 2005 |
| NRC Officer: | Mike Ripley |
| Last Updated: | Jul 20, 2005 |
| 41856 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 532392018-03-01T22:43:0001 March 2018 22:43:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Tornado Missile Vulnerabilities ENS 529762017-09-18T22:24:00018 September 2017 22:24:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Control Room Envelope Not Maintained ENS 507402015-01-15T23:04:00015 January 2015 23:04:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Inadequately Sealed Piping Penetrations and Postulated Flooding Event ENS 484022012-10-12T09:20:00012 October 2012 09:20:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Reactor Power Exceeded Fsar Analyzed Value ENS 443512008-07-16T20:16:00016 July 2008 20:16:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Fire Propagation Between Rooms Could Affect Appendix R Safe Shutdown ENS 434872007-07-12T15:15:00012 July 2007 15:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Inspection Analysis of Pressurizer Porvs and Block Valves ENS 433532007-05-09T21:23:0009 May 2007 21:23:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Identified Non Compliant Fire Protection Manual Operator Actions ENS 421292005-11-08T14:44:0008 November 2005 14:44:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Design Basis for Long Term Cooling Not Correctly Modeled ENS 421092005-11-02T05:00:0002 November 2005 05:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Degradation of Containment Coatings ENS 420202005-09-27T15:00:00027 September 2005 15:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Faults Have Electrical Current in Excess of the Maximum Listed Interrupting Ratings. ENS 418562005-07-20T09:51:00020 July 2005 09:51:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Minimum Recirculation Valves Will Not Automatically Open in Local Operating Mode ENS 417582005-06-08T22:24:0008 June 2005 22:24:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Fire Organizational Plan No Longer Aligned with Safe Shutdown Analysis ENS 417542005-06-07T23:00:0007 June 2005 23:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Appendix R Safe Shutdown Strategy Deficiency 2018-03-01T22:43:00 | |
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