ENS 46392
ENS Event | |
|---|---|
05:23 Nov 4, 2010 | |
| Title | Charging Pump '23' Declared Inoperable During Surveillance Testing |
| Event Description | On November 4, 2010 at 0123 [EDT], '23' Charging Pump was declared inoperable due to not meeting required test parameters during surveillance testing. '23' Charging Pump is required for remote shutdown per Technical Specification 3.3.4, Remote Shutdown, and is a single component system intended to perform the inventory control safety function. Since '23' Charging Pump has been declared inoperable, a loss of safely function has occurred and is reportable per 10CFR50.72 (b)(3)(v)(A).
The cause of the inoperability is under investigation. Per Technical Specification 3.3.4, Remote Shutdown, '23' Charging Pump must be restored to operable status within 30 days. The licensee will inform the NY State PSC (Public Service Commission) and the NRC Resident Inspector.
Indian Point Unit 2 is withdrawing the 8-hour non-emergency notification made on November 4, 2010, at 0305 EST. The notification on November 4, 2010, reported a safety system functional failure (SSFF) as a result of declaring the 23 Charging Pump (CP) inoperable. The 23 CP failed to meet test parameters during testing. Because the 23 CP is credited in Technical Specification (TS) 3.3.4 for Remote Shutdown, the inoperable condition was determined to be a loss of safety function. The TS 3.3.4 Allowed Outage Time (AOT) for inoperable conditions is 30 days. The remote shutdown function is not credited in the accident analysis. Subsequent investigations determined that during a two year comprehensive test (IST) the 23 CP failed the flow test due to low pump discharge flow (79.3 gpm) at the prescribed test speed (85% of rated speed). Troubleshooting determined that the 23 CP recirculation line valves 1279 and 4902 had leak-by of approximately 6.7 gpm. The leak-by results in a reduction of available discharge flow from the 23 CP to the Reactor Coolant System (RCS) due to a small amount of the pump discharge being diverted through the recirculation line. Engineering determined that the CP capacity for emergency boration with the recirculation line valves leak-by was within the capability of the 23 CP to maintain overall system function. The 23 CP is also credited for RCS inventory maintenance per TS 3.3.4 and Station Administrative Order (SAO) 703 for fire protection. Engineering concluded that with a normal CP output of approximately 87-90 gpm and a nominal rated capacity of 98 gpm, the reduction by approximately 6.7 gpm due to leak-by did not significantly impact normal operation of the CP. Therefore, the 23 CP continues to meet the established IST requirement when the 6.7 gpm recirculation line valve leak-by is accounted for. The degraded output is associated with the system rather than the 23 CP therefore the IST requirement for the 23 CP is satisfied. Additionally, the 23 CP test was performed at approximately 85% of rated speed in accordance with the IST requirements. At 100% rated speed, the remaining available capability to the RCS would be approximately 92 gpm. Engineering concludes that although degraded the 23 CP and system can perform their intended function and no SSFF occurred." The licensee will notify the NRC Resident Inspector. The R1DO (Perry) was notified. |
| Where | |
|---|---|
Indian Point  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | |
| Time - Person (Reporting Time:+-2.3 h-0.0958 days <br />-0.0137 weeks <br />-0.00315 months <br />) | |
| Opened: | Frank Kich 03:05 Nov 4, 2010 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Dec 20, 2010 |
| 46392 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 528012017-06-11T13:11:00011 June 2017 13:11:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Excessive Bonnet Leakage from Chemical Volume Control System Valve ENS 467822011-04-25T13:50:00025 April 2011 13:50:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Single Train Charging Pump Declared Inoperable ENS 463922010-11-04T05:23:0004 November 2010 05:23:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Charging Pump '23' Declared Inoperable During Surveillance Testing ENS 462222010-09-01T20:00:0001 September 2010 20:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Loss of Temperature Instrumentation ENS 454322009-10-14T19:00:00014 October 2009 19:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Safety System Functional Failure - Alternate Safe Shutdown Source Range Neutron Monitor Inoperable ENS 451522009-06-23T22:23:00023 June 2009 22:23:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Potentially Degraded Inventory Control During Shutdown ENS 442362008-05-23T07:30:00023 May 2008 07:30:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Charging Pump Declared Inoperable Due to Relief Valve Lifting Below Setpoint 2017-06-11T13:11:00 | |