ENS 49460
ENS Event | |
|---|---|
14:54 Aug 23, 2013 | |
| Title | 60-Day Optional Telephonic Notification for an Invalid Primary Containment Isolation Valve Actuation |
| Event Description | At 0754 on 8/23/13, a loss of power to the Reactor Protection System (RPS) 'B' occurred due to the unexpected opening of the circuit breaker (RPS-CB-MG2) for the RPS 'B' motor generator due to a failure of the voltage regulator circuit card. The loss of RPS 'B' resulted in a half scram signal, closure of Primary Containment Isolation Valves (PCIVs) from multiple systems and loss of power to main steam line radiation monitors (MS-RIS-610B & MS-RIS-610D). No plant parameters or maintenance activities existed which would cause the opening of RPS-CB-MG2 or actuation of the primary containment isolation; therefore, this is considered to be an invalid actuation of a system listed in 10CFR50.73(a)(2)(iv).
The half scram signal, closure of Primary Containment Isolation Valves (PCIVs) from multiple systems, and loss of power to main steam line radiation monitors were an expected response to the loss of RPS 'B'. RPS 'B' was repowered from an alternate power supply. The half scram signal was reset, the containment isolation valves were opened and the affected systems were returned to normal operation. The voltage regulator circuit card was replaced and RPS 'B' was returned to its normal power supply. As indicated in 10CFR50.73(a)(1), in the case of an invalid actuation reported under 10CFR50.73(a)(2)(iv)(A), the licensee may, at its option, provide a telephonic notification to the NRC Operations Center within 60 days of discovery of the event instead of submitting a written LER. This 60-day telephone notification is being made to meet the reporting requirements instead of submitting an LER since the actuation was invalid. The following additional information is provided as specified in NUREG-1022: The specific train(s) and system(s) that were actuated: PCIVs in multiple systems EDR-V-19 Drywell Equipment Drain Inboard Isolation Valve EDR-V-20 Drywell Equipment Drain Outboard Isolation Valve FDR-V-3 Drywell Floor Drain Inboard Isolation Valve FDR-V-4 Drywell Floor Drain Outboard Isolation Valve RWCU-V-1 Reactor Water Cleanup Suction Inboard Isolation Valve RWCU-V-4 Reactor Water Cleanup Suction Outboard Isolation Valve RRC-V-19 Reactor Water Sample Inboard Isolation Valve RRC-V-20 Reactor Water Sample Outboard Isolation Valve TIP-V-15 Traversing In-Core Probe Purge Isolation Valve CRD-V-11 Control Rod Drive Scram Discharge Volume Drain Valve Whether each train actuation was complete or partial: All PCIVs actuations for a loss of RPS 'B' were complete. The reactor half scram for a loss of RPS 'B' was a partial activation. Whether or not the system started and functioned successfully: All PCIVs functioned successfully. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Columbia Generating Station  Washington (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| Time - Person (Reporting Time:+1437.82 h59.909 days <br />8.558 weeks <br />1.97 months <br />) | |
| Opened: | Mot Hedges 12:43 Oct 22, 2013 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Oct 22, 2013 |
| 49460 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 566252023-05-17T10:39:00017 May 2023 10:39:00
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