Event Notification Report for May 12, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/09/2003 - 05/12/2003
** EVENT NUMBERS **
39835 39836 39837 39838
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|Power Reactor |Event Number: 39835 |
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/10/2003|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 13:37[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/10/2003|
+------------------------------------------------+EVENT TIME: 10:28[CDT]|
| NRC NOTIFIED BY: RICKY MAYEUX |LAST UPDATE DATE: 05/10/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA SMITH R4 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 98 Power Operation |98 Power Operation |
| | |
| | |
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EVENT TEXT
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| PLANT MAY HAVE EXCEEDED RATED THERMAL POWER DURING PREVIOUS OPERATING CYCLE |
| |
| The following information was obtained from the licensee via facsimile: |
| |
| "On May 10, 2003, plant personnel determined that River Bend Station [RBS] |
| may have operated above the licensed thermal power limit of 3039 MWt |
| [megawatts thermal] during the last operating cycle due to a |
| non-conservative error in feedwater flow measurement. RBS installed a new |
| feedwater ultrasonic flow meter during the last refueling outage. Data |
| analyzed following initial testing of the new flow meter resulted in the |
| identification of discrepancies between feedwater flow measurements from the |
| new ultrasonic flow meter, the previously installed external ultrasonic flow |
| meter and the venturi nozzle flow meter. Feedwater flow measurement |
| directly impacts the calculation of thermal power during plant operation. |
| The plant normally operates at 100% thermal power. Thus, any non |
| conservative error in feedwater measurement results in thermal power greater |
| than 100%. |
| |
| "Initial review of feedwater flow data indicates that the licensed thermal |
| power limit may have been exceeded. Further analysis is ongoing to |
| determine the magnitude of the condition. This condition was primarily |
| caused by error in the flow measurement using the previously installed |
| external ultrasonic flow meter. As this device is no longer installed in |
| the plant, the reported condition has no impact on current plant operation. |
| This report is being made as required by RBS Operating License [OL] |
| Condition 2.E as a violation of OL Condition 2.C(1)." |
| |
| The licensee has notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39836 |
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| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 05/10/2003|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 17:25[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 05/10/2003|
+------------------------------------------------+EVENT TIME: 15:06[CDT]|
| NRC NOTIFIED BY: JAMES BAPTIST |LAST UPDATE DATE: 05/10/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| OFFSITE NOTIFICATION TO STATE OF WISCONSIN |
| |
| The following information was obtained from the licensee via facsimile: |
| |
| "On 5/10/03, while performing a reactor plant startup, the 'B' AFW |
| [Auxiliary Feed Water] pump Safeguards Alley trench overflowed. Recent |
| procedural changes have been made to N-FW-05B which do[es] not allow |
| throttling of the lube oil coolers discharge valves to prevent flooding. To |
| address the condition, a sump pump was used to pump water from the trench |
| directly to the turbine building standpipe because the normal flowpath ( |
| Turbine Building Sump ) capacity had been exceeded. This water is believed |
| to be free from radiological, chemical, or petroleum products as it is |
| processed as pure DI [de-ionized] water. This has effectively created a |
| previously unrecognized and consequently unauthorized discharge flowpath. |
| This notification is being made due to the expected report to the Wisconsin |
| DNR [Department of Natural Resources] on the same incident." |
| |
| To mitigate this condition, the licensee has temporarily changed the revised |
| procedure to allow throttling of lube oil coolers discharge valves (original |
| procedural guidance) until the revised procedure can be re-evaluated. The |
| discharge did not exceed any reportable quantities. |
| |
| The licensee has notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39837 |
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/10/2003|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 20:54[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/10/2003|
+------------------------------------------------+EVENT TIME: 15:09[EDT]|
| NRC NOTIFIED BY: ALAN RABENOLD |LAST UPDATE DATE: 05/10/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| MANUAL RPS ACTUATION DUE TO FAILED OVERRIDE FEATURE |
| |
| "At 1509 [CDT], during the performance of the Division One (1) LOOP / LOCA |
| Test, the instrument air to Control Rods was lost due to a failure of the |
| supply isolation valve to re-open during the test. It was planned that the |
| Scram Air Header isolation valve would close during the test but the LOCA |
| Override feature failed to work and prevented the valve from being |
| re-opened. A manual Rx Scram was inserted before Scram Air Header pressure |
| dropped to the point that it would have caused a Rx Scram. |
| |
| "The Control Rods were already inserted into the Core and no Rod motion |
| occurred. The valve was manually re-opened and air was restored to the Scram |
| Air Header. The Scram was reset at 1546 [hrs.]. The Plant is currently in a |
| Refueling Outage. Troubleshooting will be occurring to determine the failure |
| of the override feature to function:" |
| |
| Normal Scram Air Header pressure is 120 psig. At a pressure of 38 psig, the |
| Scram Air Header valves will start to fail close due to low air pressure and |
| result in a Scram. The licensee initiated the manual Rx Scram when pressure |
| reached 60 psig decreasing. The air header depressurized completely until |
| the air supply valve was manually re-opened after operators were unable to |
| open the valve from the control room. During this outage, there was some |
| work performed on the Scram Air Supply Isolation valve but none that would |
| have affected the LOCA Override feature. The Isolation valve override will |
| be repaired during this refueling outage. |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39838 |
+------------------------------------------------------------------------------+
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| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 05/12/2003|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 03:28[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 05/12/2003|
+------------------------------------------------+EVENT TIME: 01:02[EDT]|
| NRC NOTIFIED BY: EDDIE BYARS |LAST UPDATE DATE: 05/12/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO MAIN GENERATOR OUTPUT BREAKER |
| OPENING |
| |
| Main Generator output breaker opened after receiving Main Generator voltage |
| regulator # 1 (core 1) & # 2 (core 2) alarms causing an automatic turbine |
| trip followed by an automatic reactor trip (first out annunciator was over |
| temperature differential temperature). All rods fully inserted into the |
| core. Both motor driven auxiliary feedwater pumps were manually started to |
| maintain reactor coolant temperature and proper steam generator water |
| levels. Steam is being dumped to the main condenser. Emergency Operating |
| procedure 1.0 entered and then Emergency Operating procedure 1.1, Reactor |
| Recovery Procedure was entered. All emergency core cooling systems and the |
| emergency diesel generators are fully operable if needed. The licensee |
| believes that the main generator exciter breaker opened before the main |
| generator output breaker opened. No work was going on in the area of the |
| main generator when the output breaker opened. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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