ENS 41132
ENS Event | |
|---|---|
08:50 Aug 22, 2004 | |
| Title | 60 Day Report - Invalid Actuation of Specified System |
| Event Description | This 60-day optional report as allowed by 10 CFR 50.73(a)(1), is being made under the reporting requirement in 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid actuation of a specified system, specifically the Nuclear Service Water System (NSWS).
During TSM 158 work associated with W/O 98686671 a SPOC Relief Supervisor inadvertently caused a ground when disconnecting test meter leads from an energized circuit. This ground resulted in an unplanned RN [Nuclear Service Water] swap to the SNSWP [Standby Nuclear Service Water System]. At 0450 on 8/22/04, a lo-lo level signal was received for B Train RN Pit and this initiated a swap to the SNSWP for both A and B trains. Prior to this event, both trains of RN had been aligned to the SNSWP on 8/16/04 for maintenance, and remained on the SNSWP due to 1RN-4B degraded condition (PIP C-04-3937) The lo-lo level signal did initiate a start of all four RN Pumps (1B and 2B started; 1A and 2A were already operating). RN crossover valves 1RN-53B and 1RN 54A closed as expected, separating RN trains A and B. Flow was manually initiated through all four NS Heat Exchangers to attempt to meet RN pump minimum flow demands. This was a complete actuation for Train B and the system performed as designed for existing plant conditions. This event was entered into the site corrective action program for resolution (PIP C04-04056). At 1629 on 8/22/04, a lo-lo level signal was received for B Train RN Pit and this initiated a swap to the SNSWP for both A and B trains. Prior to this event, both trains of RN had been aligned to the SNSWP on 8/16/04 for maintenance, and remained on the SNSWP due to 1RN-4B degraded condition (PIP C-04-3937). RN system response was as expected. The lo-lo level signal did initiate a start of all four RN Pumps (1B and 2A started; 1A and 2B were already operating). RN crossover valves 1RN-47A and 2RN-47A closed as expected, and return header isolation valves 1RN-53B and 1RN-54A closed as expected, separating RN trains A and B. Flow was manually initiated through all four NS heat exchangers to attempt to meet RN pump minimum flow demands. The reasons for the inadvertent actuation was a blown fuse. Performed Troubleshooting Plan to I/R Cause of Fuse HA-1 in 1EATC6 blowing under W/O #98686856-01 and 03. No cause for the fuse blowing on 2004-08-22 could be found. All data obtained under the plan were well within normal values. Thermography data indicate the fuse temperature was about 3 Deg F above ambient. The current through the fuse is 1.3 Amps. (Fuse HA-1 is a FLQ-3) Current alarm HF in 1EATC6 was calibrated, and was found in tolerance. No change in current through the fuse was noted during the calibration of the current alarm. The current alarm was cycled 5 times. This was a complete actuation for Train B and the system performed as designed for the existing plant conditions. This event has been entered into the site specific corrective action program for resolution. (C04-4060). The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| Time - Person (Reporting Time:+1392 h58 days <br />8.286 weeks <br />1.907 months <br />) | |
| Opened: | Wallace Judd 08:50 Oct 19, 2004 |
| NRC Officer: | Bill Gott |
| Last Updated: | Oct 19, 2004 |
| 41132 - 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 491952013-05-28T17:39:00028 May 2013 17:39:00
[Table view]10 CFR 50.73(a)(1), Submit an LER 60 Day Report - Invalid Actuation of Specified System ENS 487062012-12-22T06:42:00022 December 2012 06:42:00 10 CFR 50.73(a)(1), Submit an LER 60 Day Report - Invalid Actuation of the Afw System ENS 443522008-06-09T20:31:0009 June 2008 20:31:00 10 CFR 50.73(a)(1), Submit an LER 60 Day Report - Invalid Actuation of Main Steam Isolation System ENS 440512008-01-24T07:35:00024 January 2008 07:35:00 10 CFR 50.73(a)(1), Submit an LER 60 Day Report - Invalid Actuation of the Nuclear Service Water System ENS 428732006-08-08T20:17:0008 August 2006 20:17:00 10 CFR 50.73(a)(1), Submit an LER 60 Day Report - Invalid Actuation of Auxiliary Feed Pump 2B ENS 411322004-08-22T08:50:00022 August 2004 08:50:00 10 CFR 50.73(a)(1), Submit an LER 60 Day Report - Invalid Actuation of Specified System 2013-05-28T17:39:00 | |