Event Notification Report for July 3, 2000
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/30/2000 - 07/03/2000 ** EVENT NUMBERS ** 37137 37138 37139 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37137 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/30/2000| | UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 00:28[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/29/2000| +------------------------------------------------+EVENT TIME: 21:12[EDT]| | NRC NOTIFIED BY: REINSBURROW |LAST UPDATE DATE: 06/30/2000| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 92 Power Operation |92 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - FAILURE OF A WARNING SIREN | | | | During normal plant operations, a spurious and sustained actuation of siren | | #7 of the Off Site Emergency Warning System occurred. The actuation was not | | as a result of personnel actions. Local government agencies were notified. | | The affected siren actuated at 2112 and was deactivated at 2201. The area | | covered by the siren has been placed on backup route alerting. | | | | The licensee will inform the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37138 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/30/2000| | UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 15:43[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 06/13/2000| +------------------------------------------------+EVENT TIME: 14:00[EDT]| | NRC NOTIFIED BY: MARK MAGNUSON |LAST UPDATE DATE: 06/30/2000| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |SCOTT MORRIS R1 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT OUTSIDE OF DESIGN BASIS | | | | "On 6/13/00, Vermont Yankee (VY) discovered that a turbine building to | | radwaste hallway door had been breached open for maintenance activities | | without proper engineering review. The condition has been corrected. | | | | "The door serves as a high energy line break (HELB) barrier such that a HELB | | in the turbine building would not propagate into the radwaste hallway and | | cause subsequent failure of masonry block wall between the hallway and the | | main plant switchgear rooms. Redundant equipment in the switchgear rooms is | | not qualified for operation in the environment postulated by the TB HELB. | | | | "VY review has determined that a compensatory measure to close the door in | | the event of a HELB that had been established at the time of the maintenance | | activities would not have provided adequate protection against the | | postulated HELB. | | | | "Based on the above, this condition is reportable in accordance with 10 CFR | | 50.72(b)(1)(ii)(B) as a condition found during operation that results in a | | condition that is outside the design basis of the plant." | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37139 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 07/01/2000| | UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 02:01[EDT]| | RXTYPE: [1] GE-6 |EVENT DATE: 07/01/2000| +------------------------------------------------+EVENT TIME: 00:50[CDT]| | NRC NOTIFIED BY: RICH CHEAR |LAST UPDATE DATE: 07/02/2000| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MELVYN LEACH R3 | |10 CFR SECTION: | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPDS OUT-OF-SERVICE FOR GREATER THAN 8 HOURS | | | | "Clinton Power Station's Safety Parameter Display System (SPDS) was | | inoperable at 1650 on 06/30/00 due to the plant process computer system | | supporting SPDS was removed from service for maintenance, At 0050 on 7/1/00 | | the SPDS function is still not restored to operable due to the plant process | | computer system outage is still in progress. Thus, based on the | | unavailability of the SPDS function for greater than an 8 hour period, this | | condition is being reported pursuant to 10CFR50.72(b)(1)(v). The control | | room operators are monitoring other information sources for the information | | unavailable on SPDS." | | | | The licensee intends to notify the NRC Resident Inspector. | | | | * * * UPDATE ON 7/2/00 AT 0530 EDT BY RICH CHEAR TO FANGIE JONES * * * | | | | The SPDS was returned to service at 2250 CDT on 7/1/00. The SPDS is now | | available and operational. | | | | The licensee intends to notify the NRC Resident Inspector. The operations | | officer notified the R3DO (Melvyn Leach) | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021