Event Notification Report for November 20, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/17/2000 - 11/20/2000
** EVENT NUMBERS **
37530 37531 37532 37533 37534
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|Power Reactor |Event Number: 37530 |
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| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 11/17/2000|
| UNIT: [] [2] [] STATE: TN |NOTIFICATION TIME: 10:41[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/17/2000|
+------------------------------------------------+EVENT TIME: 08:42[EST]|
| NRC NOTIFIED BY: HARRIS |LAST UPDATE DATE: 11/17/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE ERNSTES 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 53 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| PLANT HAD A REACTOR TRIP FROM 53% POWER DUE TO A TURBINE TRIP |
| |
| A "Turbine Trip/Reactor Trip" occurred at 53% reactor power due to a sudden |
| pressure relay actuation on C phase Main Bank transformer which sent signal |
| to the generator resulting in the turbine trip. Motor Driven Auxiliary |
| Feedwater pumps started as required when level decreased to less than 10% in |
| one Steam Generator and the Turbine Driven Auxiliary Feedwater pump started |
| as required on less than 10% in two steam generators. Preliminary walkdown |
| of the transformer showed no visible exterior damage or degradation. |
| Investigation is in progress to determine the cause of this event. The Unit |
| is stable and operating in accordance with Plant General Operating |
| procedures. All rods fully inserted, there were no ECCS actuations and no |
| safety relief valves lifted. |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 37531 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 11/17/2000|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 15:21[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 11/16/2000|
+------------------------------------------------+EVENT TIME: 15:54[EST]|
| NRC NOTIFIED BY: KEVIN DONNELLY |LAST UPDATE DATE: 11/17/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ERIC REBER R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SITE ACCESS INAPPROPRIATELY GRANTED TO UTILITY EMPLOYEE |
| |
| During a QA Audit it was determined that one (1) utility employee may have |
| been granted access inappropriately following offsite drug testing conducted |
| on 9/99. The employee was recalled to the site today for retesting. |
| |
| The licensee informed the NRC resident inspector. |
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|Power Reactor |Event Number: 37532 |
+------------------------------------------------------------------------------+
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 11/17/2000|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 20:41[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/17/2000|
+------------------------------------------------+EVENT TIME: 20:10[EST]|
| NRC NOTIFIED BY: SCOTT RICHARDSON |LAST UPDATE DATE: 11/18/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 ENTERED TS 3.0.3 AFTER DECLARING BOTH LOOPS ECCS INOPERABLE |
| |
| "Tech Spec 3.5.2 requires two independent Emergency Core Cooling System |
| (ECCS) loops, each capable of taking suction from the Refueling Water |
| Storage Tank (RWST) and being transferred to the containment recirculation |
| sump. This spec applies in modes 1 - 3. Following evaluation of recent |
| modifications to the containment recirc sump ECCS suction isolation valves, |
| it has been determined that neither of the two isolation valves (2-ICM-305 |
| and 2-ICM-306) could be relied upon to open when transfer of ECCS suction is |
| required. This is attributed to a lack of assurance that between seat |
| relief valves on 2-ICM-305 and 2-ICM-306 would lift and preclude thermal |
| hydraulic locking of the valves in the closed position. Since neither ECCS |
| loop recirc sump suction is operable, the action statement of TS 3.5.2 is |
| not valid. This led to the Shift Manager declaring entry into TS 3.0.3 with |
| a requirement to place the unit in a mode for which TS 3.5.2 does not apply. |
| A unit shutdown at 2% per hour has been initiated. Plans are to implement |
| compensatory actions or have the unit in hot standby within 6 hours." |
| |
| The licensee anticipates exiting TS 3.0.3 after bleeding the fluid trapped |
| between the double disk valves in approximately two hours. The licensee |
| informed the NRC resident inspector. |
| |
| * * * UPDATE 0310 11/18/2000 FROM RICHARDSON TAKEN BY STRANSKY * * * |
| |
| The united exited the shutdown LCO at 2315. Reactor power had been reduced |
| from 100% to 90%. The licensee removed approximately 4.5 gallons of water |
| from the body of each valve in order to prevent thermal locking. The NRC |
| resident inspector will be informed. Notified R3DO (Jorgensen). |
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|Power Reactor |Event Number: 37533 |
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| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 11/18/2000|
| UNIT: [] [2] [] STATE: AZ |NOTIFICATION TIME: 17:36[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 11/18/2000|
+------------------------------------------------+EVENT TIME: 11:47[MST]|
| NRC NOTIFIED BY: RUSSELL A. STROUD |LAST UPDATE DATE: 11/18/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM ANDREWS R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 45 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP FOLLOWING A REACTOR POWER |
| CUTBACK |
| |
| "On November 18, 2000, at approximately 1147 MST, Palo Verde Unit 2 |
| experienced an automatic reactor trip (RPS actuation) from approximately 45% |
| rated thermal power. Unit 2 is stable at normal operating temperature and |
| pressure in Mode 3. The event did not result in any challenges to the |
| fission product barrier. There were no adverse safety consequences or |
| implications as a result of this event. The event did not adversely affect |
| the safe operation of the plant or the health and safety of the public. |
| |
| "Prior to the reactor trip, at approximately 1008 MST, Unit 2 was at 100 |
| percent power and normal operating temperature and pressure, when testing |
| began to validate various parts of the electrical generator and exciter |
| model parameters. At approximately 1059 MST, Unit 2 experienced a |
| generator/turbine trip. Steam bypass control valves opened and a reactor |
| power cutback was initiated. |
| |
| "Operations personnel were in the process of plant stabilization after the |
| reactor power cutback, when at approximately 1147 MST, the reactor tripped. |
| All control element assemblies (CEAs) inserted as required and the trip was |
| classified as uncomplicated with respect to the emergency plan. The primary |
| plant is now stabilized in Mode 3 in forced circulation with both steam |
| generators being used for heat removal, |
| |
| "The cause of the reactor trip has not been determined and is under |
| investigation at this time. APS [Arizona Public Service] will supplement |
| this report if information is developed which significantly alters this |
| information." |
| |
| The licensee informed the NRC resident inspector. |
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|Power Reactor |Event Number: 37534 |
+------------------------------------------------------------------------------+
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 11/19/2000|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 13:15[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/19/2000|
+------------------------------------------------+EVENT TIME: 06:20[EST]|
| NRC NOTIFIED BY: VINCENT WOODS |LAST UPDATE DATE: 11/19/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LICENSED EMPLOYEE DETERMINED POSITIVE FOR FAILURE TO PROVIDE A FOR-CAUSE |
| TEST SAMPLE |
| |
| A licensed employee was determined to be under the influence of alcohol |
| after refusing to provide a sample during a for-cause test. The employee's |
| left the site and access to the plant has been terminated. The licensee |
| informed the NRC resident inspector. Contact the Headquarters Operations |
| Officer for additional details. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021