United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2000

Event Notification Report for September 26, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/25/2000 - 09/26/2000

                              ** EVENT NUMBERS **

37374  37375  37376  37377  37378  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37374       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 09/25/2000|
|LICENSEE:  ARIAF & KEZAR INC                    |NOTIFICATION TIME: 09:14[EDT]|
|    CITY:  SAN ANTONIO              REGION:  4  |EVENT DATE:        09/25/2000|
|  COUNTY:                            STATE:  TX |EVENT TIME:        07:30[CDT]|
|LICENSE#:  L04964-001            AGREEMENT:  Y  |LAST UPDATE DATE:  09/25/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  OGDEN (FAX)                  |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TEXAS DEPARTMENT OF HEALTH WAS NOTIFIED BY ONE OF THEIR LICENSEES OF A       |
| STOLEN TROXLER GAUGE IN BROWNSVILLE, TEXAS                                   |
|                                                                              |
| A Troxler Model 3430, Serial No. 31532, sources: 8 millicurie Cs-137, Serial |
| No. 750-6340; and 40 millicurie Am-241 /Be, Serial No. 47-28154 was          |
| apparently stolen from the back of a company truck at an overnight lodging   |
| in Brownsville Texas. The operator/driver discovered the theft between 7:30  |
| a.m. and 8:00 a.m. this morning. The security chains in the bed of the truck |
| had been cut.  The gauge and the operators tool box were stolen.  A police   |
| report has been filed with the Brownsville Police Department. The gauge was  |
| to be used at a temporary jobsite today.  The owner of the stolen gauge is a |
| Texas Licensee, L04964-001.  The licensee is considering offering a reward   |
| for return of the gauge.                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37375       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 09/25/2000|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 11:18[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/25/2000|
+------------------------------------------------+EVENT TIME:        10:33[EDT]|
| NRC NOTIFIED BY:  HOWARD                       |LAST UPDATE DATE:  09/25/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       78       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP FROM 78% POWER DUE TO A LOW STEAM GENERATOR LEVEL               |
|                                                                              |
| The event was initiated at 1030 EDT when the "1A" main feedwater pump        |
| tripped.  An automatic runback [from 100%] to 75% turbine power occurred,    |
| however, the "1B" main feedwater pump did not automatically speedup to full  |
| load as designed.  An attempt to manually load the "1B" main feedwater pump  |
| was ineffective and a trip occurred as a result of a low steam generator     |
| level.  All rods fully inserted, no ECCS initiated and no safety valves      |
| lifted.  They are investigating the cause of this event.                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37376       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 09/25/2000|
|    UNIT:  [1] [2] []                STATE:  MD |NOTIFICATION TIME: 12:47[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        09/25/2000|
+------------------------------------------------+EVENT TIME:        08:15[EDT]|
| NRC NOTIFIED BY:  O'MEARA                      |LAST UPDATE DATE:  09/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE TECHNICAL REQUIREMENT 24 HOUR REPORT                                |
|                                                                              |
| The licensee, in accordance with their Technical Review (Requirement) Manual |
| 15.7.5.c, reported that one of their diesel fire pumps and one pretreatment  |
| water storage tank (# 12) was removed from service for planned maintenance.  |
| The diesel fire pump was taken out of service to install a flange to isolate |
| the pretreatment water storage tank for maintenance. The pump being          |
| out-of-service and having one of two sources of water out-of-service         |
| prompted the 24 hour report.                                                 |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| See similar Event # 37367 reported on 09/22/00.                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37377       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 09/25/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 14:30[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/25/2000|
+------------------------------------------------+EVENT TIME:        14:00[EDT]|
| NRC NOTIFIED BY:  UNDERWOOD                    |LAST UPDATE DATE:  09/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Unescorted access granted inappropriately. Immediate compensatory measures   |
| taken upon discovery.                                                        |
|                                                                              |
| Refer to the HOO Log for additional details.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37378       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 09/26/2000|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 01:23[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/26/2000|
+------------------------------------------------+EVENT TIME:        00:43[EDT]|
| NRC NOTIFIED BY:  THOMAS MARSHALL              |LAST UPDATE DATE:  09/26/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |BILL BATEMAN         NRR     |
|AAEC                                            |JOSEPH GIITTER       IRO     |
|                                                |CANUPP               FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 MET THE CONDITIONS FOR AN UNUSUAL EVENT BASED ON RCS LEAKAGE > 25 GPM |
| WHILE IN MODE 4.                                                             |
|                                                                              |
| "While placing the '1A'  RHR Pump in service for shutdown cooling, the Unit  |
| experienced an RCS leak of approximately 45 gpm.  It is believed that the    |
| cause of the leak is a relief valve that lifted and failed to reseat.  The   |
| leak was isolated from the RCS when the RHR suction valves from the RCS      |
| (1-FCV-74-1 and 1-FCV-74-2) were closed.  The leak lasted approximately 10   |
| minutes.                                                                     |
|                                                                              |
| "According to the Plant's Radiological Emergency Plan, the conditions for a  |
| Notification of Unusual Event (NOUE) were met, but before it could be        |
| declared the leak was isolated, so an NOUE was not declared but will be      |
| reported."                                                                   |
|                                                                              |
| The RCS which leak occurred at 0002EDT was terminated at 0012EDT (10         |
| minutes).  Operators estimated the leakage at 45 gpm based on the change in  |
| PRT (pressurizer relief tank) level.  The two relief valves involved are     |
| 1-VLV-63-626 and 1-VLV-63-627 with setpoints of approximately 600 psig.  RCS |
| pressure was 345 psig when the RHR suction valves were opened.  The RHR      |
| pumps develop approximately 180 psig which combined with the 345 psig RCS    |
| pressure (inlet) indicated about 525 psig RHR discharge pressure in the      |
| control room.  Both trains of RHR have been declared inoperable pending      |
| identification and correction of the problem.  Decay heat is current being   |
| removed by the main condenser through the steam dumps using both             |
| motor-driven auxiliary feedwater pumps.  The licensee has no plans for a     |
| press release at this time and did inform the NRC resident inspector.        |
+------------------------------------------------------------------------------+