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. |
+------------------------------------------------------------------------------+
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