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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  

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|Power Reactor                                    |Event Number:   37137       |
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| 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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| 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.                         |
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|Power Reactor                                    |Event Number:   37138       |
+------------------------------------------------------------------------------+
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| 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.  |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37139       |
+------------------------------------------------------------------------------+
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| 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)                                     |
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