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Event Notification Report for October 23, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/20/2000 - 10/23/2000

                              ** EVENT NUMBERS **

37443  37444  37445  37446  37447  37448  37449  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37443       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 10/20/2000|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 14:08[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        10/20/2000|
+------------------------------------------------+EVENT TIME:        13:43[EDT]|
| NRC NOTIFIED BY:  ALAN HALL                    |LAST UPDATE DATE:  10/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION                                                         |
|                                                                              |
| The licensee notified the Florida Fish and Wildlife Conservation Commission  |
| (FF&WCC) regarding the rescue of a live green sea turtle from the intake     |
| canal. The animal will be transferred to the FF&WCC for rehabilitation at    |
| the Sea Turtle Hospital in Marathon, Florida. The NRC resident inspector has |
| been informed of this notification.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37444       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 10/20/2000|
|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 22:50[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/20/2000|
+------------------------------------------------+EVENT TIME:        19:45[EDT]|
| NRC NOTIFIED BY:  STEVE SAUER                  |LAST UPDATE DATE:  10/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DESIGN ISSUE REGARDING MSIV CLOSURE ABILITY DURING MODE TRANSITION           |
|                                                                              |
| "The main steam isolation valves, which accomplish the steam line isolation  |
| function, require steam pressure assist to close (fast close). They can also |
| be closed hydraulically (slow close).                                        |
|                                                                              |
| "The main steam isolation valve function had been demonstrated to be         |
| acceptable in Mode 1, 2, and 3. However, the analyses performed for Mode 3   |
| do not explicitly address all steam pressures in region between the NOP/NOT  |
| area of Mode 3 and the entry condition to Mode 4. The potential could exist  |
| where the plant is in a Mode 3 condition in transition to a Mode 4           |
| condition. During this transition condition, if a steam line break were to   |
| occur, closure of the MSIVs would be required. If the steam pressure in this |
| transition condition were near the minimum pressure required to close the    |
| MSIVs at the initiation of the event, it is possible that the steam pressure |
| in the system could decay below the required pressure to close the MSIVs.    |
| This would mean that the fast close Main Steam Isolation Function could-be   |
| inoperable in Mode 3.                                                        |
|                                                                              |
| "This function is operable in Modes 1 and 2. Further analysis is required to |
| demonstrate operability in all conditions bounded by Mode 3."                |
|                                                                              |
| The NRC resident inspector will be informed of this notification by the      |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37445       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 10/21/2000|
|    UNIT:  [] [4] []                 STATE:  FL |NOTIFICATION TIME: 05:23[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        10/21/2000|
+------------------------------------------------+EVENT TIME:        04:25[EDT]|
| NRC NOTIFIED BY:  BOB STEWART                  |LAST UPDATE DATE:  10/21/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|AAEC                                            |FRANK CONGEL         IRO     |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |GENE CANUPP          FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|4     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER TO THE VITAL BUSSES      |
|                                                                              |
| An unusual event was declared at 0435 EDT on 10/21/00 due to the loss of     |
| offsite power to the 4 kv vital busses.  The startup transformer was tripped |
| due to a lockout for an unknown reason.  Both emergency diesel generators    |
| started and energized their respective busses.  The licensee is              |
| investigating the cause of the lockout.  The unusual event will be exited    |
| when offsite power is restored to the vital busses.                          |
|                                                                              |
| The licensee has notified the state and local authorities and intends to     |
| notify the NRC Resident Inspector.                                           |
|                                                                              |
| * * * UPDATE AT 0620 EDT ON 10/21/00 BY BOB STEWART TO FANGIE JONES * * *    |
|                                                                              |
| During attempts to restore offsite power a safety injection occurred at 0553 |
| EDT due to differential pressure on the steam lines.  The main steam         |
| isolation valves were closed with main steam line pressure indication nulled |
| at 585 psig and steam generator pressure dropped to 485 psig during the      |
| cooldown giving the 100 psid for the safety injection.  The licensee was     |
| slowed by natural circulation in the process of reducing reactor coolant     |
| system pressure to clear the override setpoint for the safety injection, but |
| didn't make it.  When the safety injection occurred all equipment operated   |
| as required.                                                                 |
|                                                                              |
| Offsite power was restored at 0616 EDT and the emergency diesel generators   |
| were being shutdown.  The licensee is waiting to ensure the startup          |
| transformer is stable prior to exiting the unusual event.                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.   The R2DO (Caudle         |
| Julian), NRR EO (Bruce Boger) and the IRO (Frank Congel) have been           |
| informed.                                                                    |
|                                                                              |
| * * * UPDATE AT 0701 EDT ON 10/21/00 BY BOB STEWART TO FANGIE JONES * * *    |
|                                                                              |
| The licensee exited the unusual event at 0645 EDT.  The safety injection has |
| been terminated and the plant is stable in mode 3 with one reactor coolant   |
| pump running.  The cause of the loss of the startup transformer was due to a |
| short in a backup relay for breaker protection.                              |
|                                                                              |
| The licensee has notified the NRC Resident Inspector and the state and local |
| authorities.  The R2DO (Caudle Julian), NRR EO (Bruce Boger) and the IRO     |
| (Frank Congel) have been informed.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37446       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 10/21/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 17:58[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        10/21/2000|
+------------------------------------------------+EVENT TIME:        14:18[EDT]|
| NRC NOTIFIED BY:  SCOTT REED                   |LAST UPDATE DATE:  10/21/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|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     N          Y       70       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO LOSS OF CIRCULATING WATER PUMP                    |
|                                                                              |
| Operators manually tripped the unit from 70% power, in accordance with plant |
| procedures, after the 'B' circulating water pump tripped. Following the      |
| trip, all systems functioned as expected, with the following exceptions: the |
| main feedwater pumps tripped due to seal differential pressure problems, and |
| intermediate range neutron monitoring channel N-36 failed downscale. The     |
| licensee is investigating these problems, as well as the cause of the        |
| circulating water pump trip.                                                 |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37447       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 10/22/2000|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 00:22[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/21/2000|
+------------------------------------------------+EVENT TIME:        18:00[PDT]|
| NRC NOTIFIED BY:  DAVID PIERCE                 |LAST UPDATE DATE:  10/22/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ESF LOAD SHED SIGNAL GENERATED WHILE RESTORING RELAYS                        |
|                                                                              |
| "While restoring vital 4160 Bus G Auto-Transfer Relays to service, a shed    |
| load signal was initiated to the Bus G components, apparently due to Bus G   |
| First Level Undervoltage Relays not resetting after they were energized.     |
| When the Feature Cutout Switch was subsequently cut-in to the Load Shed      |
| Relay (27XHGT) the load shed was then actuated. The only load available to   |
| be shed was Auxiliary Salt Water Pp 1-2 which shut down. Auxiliary Saltwater |
| was aligned from Unit 2 at 1805 (PDT) and remained in that configuration     |
| until 1940 (PDT), when Auxiliary Saltwater Pp 1-1 was placed in service.     |
| DCPP Unit One is currently in its 10th Refueling Outage, with the core       |
| off-loaded to the Spent Fuel Pool. The temperature of the Spent Fuel Pool    |
| did not change.  The cause of the event is under investigation."             |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37448       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 10/22/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 07:55[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        10/22/2000|
+------------------------------------------------+EVENT TIME:        01:50[EDT]|
| NRC NOTIFIED BY:  KEVIN DONALLY                |LAST UPDATE DATE:  10/22/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR REPORT - 10 CFR 50.72 AND APPENDIX R                                 |
|                                                                              |
| "A section of the high pressure fire header will be isolated and drained.    |
| The reason for the impairment is planned maintenance for the replacement of  |
| a section of 12" piping and various small bore valve replacements. This      |
| header section provides fire protection for the Units 1 and 2 Intake         |
| Structure, the Auxiliary Boiler Feed Pump Building, the Transformer Yard and |
| the Electrical Tunnel Deluge System.                                         |
|                                                                              |
| "Indian Point Station is in cold shutdown with the reactor defueIed and      |
| steam generator replacement in progress. Therefore, the Auxiliary Boiler     |
| Feed Pumps and the Main and Unit Auxiliary Transformers are out of service   |
| and do not require fire protection. The safety related equipment that is     |
| required to be protected under this plant condition are the Service Water    |
| Pumps and the 480 VAC Electrical Cables for the Spent Fuel Cooling Pumps and |
| Component Cooling Pumps which traverse the Electrical Tunnel. Compensatory   |
| hoses will be staged prior to applying the tagout. Fire tours will also be   |
| established to supplement the frequency with which these and the other       |
| impaired areas are surveilled.                                               |
|                                                                              |
| "The 24 Hour notification to the NRC for the Fire header impairment will     |
| made pursuant to 10CFR50.72 and App. R as well as the written report to      |
| follow within 14 days. The alternate fire protection system will not be      |
| established since the station is already in cold shutdown. A 30 day action   |
| statement will be entered for the inoperable hydrants protecting the Intake  |
| Structure and Service Water Pumps. A separate 14 day action statement will   |
| be entered for the inoperable Electrical Tunnel Deluge System. The duration  |
| of the impairment will be minimized and further compensatory measures may be |
| necessary should any of the time limits be approached due to unforeseen      |
| circumstances."                                                              |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37449       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 10/22/2000|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 18:41[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        10/22/2000|
+------------------------------------------------+EVENT TIME:        17:55[EDT]|
| NRC NOTIFIED BY:  WILLIAM CAMPBELL             |LAST UPDATE DATE:  10/22/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|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                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN                                    |
|                                                                              |
| The licensee reported that one of the suppression chamber to drywell vacuum  |
| breakers cannot be seated completely and the unit 2 primary containment has  |
| been declared inoperable. Technical Specification 3.6.1.1 Condition b        |
| requires that the unit be taken to a hot shutdown condition within 12 hours. |
| The licensee intends to reduce reactor power in order to make a drywell      |
| entry if possible to correct the problem. If the problem cannot be           |
| corrected, the licensee intends to take the unit to cold shutdown and        |
| deinert the containment.                                                     |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+