ENS 41216
ENS Event | |
|---|---|
01:30 Nov 23, 2004 | |
| Title | Inadvertent Isolation of the Reactor Core Isolation Cooling System |
| Event Description | This ENS notification is made to report that on November 22, 2004 at 17:30 PST the Reactor Core Isolation Cooling (RCIC) system was rendered inoperable when its inboard steam supply containment isolation valve inadvertently closed during the performance of a routine surveillance procedure. The surveillance procedure was stopped and plant operators entered the appropriate Technical Specification Action Statements. The RCIC system was restored to its normal standby lineup and declared operable two hours and three minutes after the isolation.
NRC guidance in NUREG 1022 (Rev. 2), 'Event Reporting Guidelines,' and NRC Regulatory Issue Summary (RIS) 2001-14, 'Position on Reportability Requirements for Reactor Core Isolation Cooling System Failure,' indicates that RCIC failures are not reportable unless the RCIC system is specifically credited in the plant's Final Safety Analysis Report for mitigating the consequences of a Control Rod Drop Accident (CRDA). Columbia Generating Station has determined that the current licensing basis and docketed correspondence is not clear regarding RCIC credit for CRDA mitigation. Proposed FSAR changes were recently submitted by Energy Northwest to the NRC that would clarify that RCIC is not credited for CRDA mitigation. However, the NRC staff has not yet approved these proposed changes. Therefore, Columbia Generating Station has decided to conservatively report this event under 10 CFR 50.72(b)(3)(v)(D). A follow-up LER will be issued under 10 CFR 50.73(a)(2)(v)(D). The licensed has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Columbia Generating Station  Washington (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+1.52 h0.0633 days <br />0.00905 weeks <br />0.00208 months <br />) | |
| Opened: | Dan Jordheim 03:01 Nov 23, 2004 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Nov 23, 2004 |
| 41216 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |