Event Notification Report for May 12, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/11/2000 - 05/12/2000
** EVENT NUMBERS **
36989 36990 36991 36992
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|Power Reactor |Event Number: 36989 |
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| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/11/2000|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 09:29[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/11/2000|
+------------------------------------------------+EVENT TIME: 01:00[EDT]|
| NRC NOTIFIED BY: G. FIEDLER |LAST UPDATE DATE: 05/11/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN 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 |
| | |
| | |
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EVENT TEXT
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| AN APPARENT LIGHTNING STRIKE CAUSED THE LOSS OF ALL EMERGENCY SIRENS. |
| |
| An apparent lightning strike caused the loss of all Emergency Sirens. |
| Emergency Sirens were discovered inoperable at 0815 ET. Both repeaters for |
| the Emergency Sirens were found inoperable. Emergency Sirens were returned |
| to service at 0840 ET when one of the repeaters was restored to service. |
| The licensee will inform state and local officials of the loss of their |
| Emergency Sirens. |
| |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 36990 |
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/11/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 12:27[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/11/2000|
+------------------------------------------------+EVENT TIME: 08:18[CDT]|
| NRC NOTIFIED BY: TURNER |LAST UPDATE DATE: 05/11/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| THE PLANT HAD A REACTOR WATER CLEANUP ( RWCU) ISOLATION WHILE THEY WERE |
| PLACING A DEMINERALIZER FILTER IN SERVICE. |
| |
| "While placing Reactor Water Cleanup Demin "B" in service following a |
| precoat, received Division 2 isolation on sustained High Differential flow |
| of 55 gpm for 45 seconds. The following valves received closed signals |
| G33-F001, RWCU PUMPS INBD SUCTION VALVE, G33-F040, RWCU RETURN INBOARD ISOL. |
| VALVE, G33-F053, RWCU PUMPS INBD DISCH VALVE, G33-F02, RWCU INBD DRAIN VAL. |
| The Systems responded as designed with all valves closed and the Reactor |
| Water Cleanup Pumps tripped. Note: G33-F028 RWCU INBD DRAIN VAL was already |
| closed. |
| |
| "The isolation appears to be valid. The cause of the isolation appears to be |
| that valves used to flush a strainer were not full closed, causing flow to |
| the Backwash Receiving Tank where it was fully contained. The valves were |
| locally visibly verified closed, but the valves were actually 1/2 open. |
| Local position indications for both valves appeared to be defective. The |
| plant is stable and plans for restoration of the RWCU system are in |
| progress." |
| |
| The NRC Resident Inspector was notified. |
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|General Information or Other |Event Number: 36991 |
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| REP ORG: WAYNE CTY ENG TESTING OFFICE |NOTIFICATION DATE: 05/11/2000|
|LICENSEE: WAYNE CTY ENG TESTING OFFICE |NOTIFICATION TIME: 15:00[EDT]|
| CITY: DETROIT REGION: 3 |EVENT DATE: 05/11/2000|
| COUNTY: STATE: MI |EVENT TIME: 14:00[EDT]|
|LICENSE#: 21-13687-01 AGREEMENT: N |LAST UPDATE DATE: 05/11/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MELVYN LEACH R3 |
| |DON COOL NMSS |
+------------------------------------------------+BRENT CLAYTON R3 |
| NRC NOTIFIED BY: FAKHOURY | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NDAM DAMAGED GAUGE/DEVICE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| WAYNE COUNTY ENGINEERING REPORTED DAMAGE TO CPN DENSITY GAUGE. |
| |
| THE GAUGE WAS BEING USED IN DETROIT, MI. AT A ROAD MAINTENANCE SITE WHEN IT |
| WAS RUN OVER BY A CAR. THERE WAS NO MAJOR DAMAGE OR CRACKS TO THE |
| DEVICE(CPN MODEL MC3-82 PORTABLE) WHICH CONTAINED 10 MILLICURIE OF CS-137 |
| AND 50 MILLICURIE OF AMERICIUM-241/BERYLLIUM. NO LEAKAGE WAS DETECTED WHEN |
| THEY MADE A SURVEY. THE DEVICE, WHICH HAD A SLIGHT DENT AND BENT ROD WAS |
| PLACED BACK INTO ITS BOX AND WILL BE TAKEN TO THEIR FACILITY FOR STORAGE. |
| THE MANUFACTURER WILL BE CONTACTED TOMORROW. WAYNE COUNTY ENGINEERING |
| CONTACTED NRC REGION 3 (SIMMONS). |
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|Power Reactor |Event Number: 36992 |
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| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 05/11/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 16:41[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 05/11/2000|
+------------------------------------------------+EVENT TIME: 16:40[EDT]|
| NRC NOTIFIED BY: DEMONCH |LAST UPDATE DATE: 05/11/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE 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
+------------------------------------------------------------------------------+
| THE LICENSEE IDENTIFIED A DEGRADED FIRE BARRIER BETWEEN THE 4160 C AND D |
| VAULTS. |
| |
| The licensee identified the wall protecting the C & D 4160 vaults/rooms from |
| each other as a 3 hour rated fire barrier. It has been determined that the |
| wall as is does not meet the requirement for a 3 hour rating. Structural |
| steel for the wall does not have the required thickness of "Pyrocrete 102" |
| to provide a 3 hour rating. The wall is considered functional given the low |
| fire loading in each room and the presence of automatic fire detection and |
| manual suppression. They have commenced an hourly watch for the effected |
| area. |
| |
| The NRC Resident Inspector will be notified. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021