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
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|General Information or Other |Event Number: 37374 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37375 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37376 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37377 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| Unescorted access granted inappropriately. Immediate compensatory measures |
| taken upon discovery. |
| |
| Refer to the HOO Log for additional details. |
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|Power Reactor |Event Number: 37378 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021