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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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37531       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37532       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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).              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37533       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37534       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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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