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) |
+------------------------------------------------------------------------------+