Indian Point Reactor Emergency Declared

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This is a bit too technical for me but maybe someone on this forum can interpret this (and whether it might relate to Y2K) for us? It's from Garden State Environews. Thanks... - Judy

INDIAN POINT: EMERGENCY DECLARED

Date: 990901 From: http://www.nrc.gov/NRR/DAILY/der.htm

Daily Events Report U.S. Nuclear Regulatory Commission Operations Center

---------------------------------------------------------------------- Power Reactor Event Number: 36104 ---------------------------------------------------------------------- ---------------------------------------------------------------------- FACILITY: INDIAN POINT REGION: 1 NOTIFICATION DATE: 08/31/1999 UNIT: [2] [] [] STATE: NY NOTIFICATION TIME: 16:01[EDT] RXTYPE: [2] W-4-LP,[3] W-4-LP EVENT DATE: 08/31/1999 -----------------------------------------EVENT TIME: 14:30[EDT] NRC NOTIFIED BY: DENNIS CORNAX LAST UPDATE DATE: 08/31/1999 HQ OPS OFFICER: BOB STRANSKY ----------------------------- ------------------------------------------PERSON ORGANIZATION EMERGENCY CLASS: N/A JOHN ROGGE R1 10 CFR SECTION: ED GOODWIN NRR ARPS 50.72(b)(2)(ii) RPS ACTUATION FRANK CONGEL IRO AESF 50.72(b)(2)(ii) ESF ACTUATION ---------------------------------------------------------------------- UNIT SCRAM CODERX CRITINIT PWR INIT RX MODE CURR PWR CURR RX MODE ---------------------------------------------------------------------- 2 A/R Y 100 Power Operation 0 Hot Standby ---------------------------------------------------------------------- EVENT TEXT ---------------------------------------------------------------------- AUTOMATIC REACTOR TRIP WITH COMPLICATIONS

An automatic reactor trip/turbine trip occurred due to an overtemperature differential temperature (OTdT) trip signal. The licensee was replacing Channel 3 pressurizer low pressure trip bistables when a spurious OTdT trip signal occurred on Channel 4, completing the 2/4 logic. Following the trip, control rod K-2 of Control Bank D had an indicated position of 14.4 steps out from fully inserted. All other control rods are fully inserted.

Following the trip, 480 VAC bus 6A received an undervoltage trip signal, causing buses 2A, 3A, 5A, and 6A to transfer to their associated emergency diesel generators (EDGs) (22, 21, and 23, respectively). Buses 2A, 3A, and 5A are currently being supplied by the EDGs; however, the output breaker for EDG 23 tripped upon loading to bus 6A, which remains deenergized. Operators manually started the turbine driven auxiliary feedwater pump due to the loss of control power to one of the motor driven AFW pumps caused by the loss of bus 6A.

The unit is currently stable in hot standby. The licensee is currently troubleshooting bus 6A in anticipation of restoring power. The NRC resident inspector has been informed of this event by the licensee.

HOO Note: See Event #36107.

* * *

---------------------------------------------------------------------- Power Reactor Event Number: 36107 ---------------------------------------------------------------------- ---------------------------------------------------------------------- FACILITY: INDIAN POINT EGION: 1 NOTIFICATION DATE: 08/31/1999 UNIT: [2] [] [] TATE: NY NOTIFICATION TIME: 22:39[EDT] RXTYPE: [2] W-4-LP,[3] W-4-LP EVENT DATE: 08/31/1999 -----------------------------------------EVENT TIME: 21:55[EDT] NRC NOTIFIED BY: MARK STUBBLE LAST UPDATE DATE: 09/01/1999 HQ OPS OFFICER: BOB STRANSKY ----------------------------- ------------------------------------------PERSON ORGANIZATION EMERGENCY CLASS: UNU JOHN WHITE R1 10 CFR SECTION: DAVID MATTHEWS NRR AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED CHARLES MILLER IRO JOHN ROGGE R1 GENE CANUPP FEMA

---------------------------------------------------------------------- UNIT SCRAM CODERX CRITINIT PWR INIT RX MODE CURR PWR CURR RX MODE ---------------------------------------------------------------------- 2 N N 0 Hot Standby 0 Hot Standby ---------------------------------------------------------------------- EVENT TEXT ---------------------------------------------------------------------- UNUSUAL EVENT DUE TO LOSS OF MOST CONTROL ROOM ANNUNCIATORS

An Unusual Event was declared at 2155 EDT due to an unplanned loss of greater than 75% of the control room safety system annunciators for longer than 15 minutes. The licensee reported that the annunciators are currently inoperable, and that additional panel walkdowns are being performed. The unit is currently stable in Hot Standby following a reactor trip earlier today (see EN 36104). The NRC resident inspector has been informed, and is in the control room.

* * UPDATE AT 0157 EDT ON 9/1/99 BY MARK STUBBLE TO FANGIE JONES * *

The plant conditions are improving and the plant is stable in Hot Shutdown. The annunciators have been restored. The previous problem with 480 VAC busses on Event #36104 has been found to be related to the loss of the annunciators. Further evaluation is ongoing and the licensee expects to exit the Unusual Event soon.

The licensee notified the NRC Resident Inspector. The HOO notified the R1DO (John White), NRR EO (David Matthews), and IRO Manager (Charles Miller).

* * UPDATE AT 0343 EDT ON 9/1/99 BY MARK STUBBLE TO FANGIE JONES * *

The plant has exited the Unusual Event, the plant is in normal Hot Shutdown. The licensee has notified the NRC Resident. The HOO notified the R1DO (John White), NRR EO (David Matthews), IRO Manager (Charles Miller), and FEMA (Gene Canupp)

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-- Anonymous, September 02, 1999


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