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Des accidents nucléaires partout

Etats-Unis : Indian Point : Safety injection actuation during testing




27 mars 2013


Enclenchement intempestif de l’injection de liquide de refroidissement de sécurité durant l’exécution d’un test.

1 ère divergence : avril 1976 – Type PWR – P : 1040 Mwe

Available in english only.


Facility : INDIAN POINT - State : NY - Unit : [3] - RX Type : [3] W-4-LP

Event Date : 03/27/2013 - Event Time : 06:01

Emergency Class : NON EMERGENCY 10 CFR Section : 50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION

Initial PWR : 0 %

Current PWR : 0 %

Event Text

SAFETY INJECTION ACTUATION DURING TESTING

"On March 27, 2013 at 0601 EDT, the Safety Injection System automatically actuated while in Mode 3 during performance of I&C [Instrument and Control] testing due to faulty test equipment. All plant equipment responded normally to the safety injection. This is reportable under 10 CFR 50.72(b)(2)(iv)(A). The plant is stable in Mode 3 at this time.

"The Auxiliary Feedwater System actuated following the safety injection signal as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at 1140 psig and 395 degrees F with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the atmospheric steam dumps. There was no radiation released.

"Indian Point Unit Two was not affected by this event and remains at 100% power.

"Notified NRC Resident Inspector. Notified NRC Emergency Operations Center Duty Officer."

The Safety Injection was reset and all plant equipment was restored to normal alignment. Pressurizer level remained in the indication range during the Safety Injection. The cause of the Safety Injection is still under investigation, but appears to be related to a faulty jumper necessary for the test.

* * * UPDATE FROM MICHAEL McCARTHY TO DONALD NORWOOD AT 1335 EDT ON 3/27/2013 * * *

"The event reported above resulted in additional reportable actuations under 10 CFR 50.72(b)(3)(iv)(A). These were : 1) RPS actuation, 2) Phase A containment isolation, 3) Containment fan cooler unit actuation, and 4) Emergency Diesel Generator actuation (start but did not load).

"The licensee notified the NRC Resident Inspector of the 1335 EDT update."

Notified R1DO (Krohn).

https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2013/20130328en.html


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