Event Notification Report for April 29, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/28/1999 - 04/29/1999
** EVENT NUMBERS **
35645 35646 35647 35648 35649
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|Power Reactor |Event Number: 35645 |
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| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/28/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 11:21[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 04/28/1999|
+------------------------------------------------+EVENT TIME: 07:30[EDT]|
| NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 04/28/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLIFFORD ANDERSON R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| HPCI SYSTEM INOPERABLE |
| |
| During an I&C surveillance test of pressure switches associated with the |
| High Pressure Coolant Injection (HPCI) steam line, one of four low steam |
| line pressure switches failed its test. The licensee closed both HPCI steam |
| isolation valves rendering HPCI inoperable. The licensee has verified the |
| operability of the Automatic Depressurization System (ADS) as required by |
| plant Technical Specifications. |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
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|Fuel Cycle Facility |Event Number: 35646 |
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| FACILITY: ALLIED-SIGNAL INC. |NOTIFICATION DATE: 04/28/1999|
| RXTYPE: URANIUM HEXAFLUORIDE PRODUCTION |NOTIFICATION TIME: 12:20[EDT]|
| COMMENTS: UF6 CONVERSION (DRY PROCESS) |EVENT DATE: 04/28/1999|
| |EVENT TIME: 10:30[CDT]|
| |LAST UPDATE DATE: 04/28/1999|
| CITY: METROPOLIS REGION: 3 +-----------------------------+
| COUNTY: MASSAC STATE: IL |PERSON ORGANIZATION |
|LICENSE#: SUB-526 AGREEMENT: Y |JOHN MADERA R3 |
| DOCKET: 04003392 |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HUGH ROBERTS | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| FAILURE OF AN EMERGENCY SYSTEM WITH NO REDUNDANT EQUIPMENT AVAILABLE FOR |
| BACKUP - 24-HOUR REPORT IN ACCORDANCE WITH 10CFR40.60(b) |
| |
| The failure involves a health physics vacuum pump and a communication device |
| (the red lights for notification of respiratory conditions). Power is not |
| available to these devices. The licensee cannot switch to standby power due |
| to a common bus outage. The licensee was in the process of putting another |
| scrubber onto this system as part of an annual shutdown. The power feed |
| coming in from the local company (CIPS) went down, and the standby system |
| was not available due to ongoing work. The power outage occurred at 1003 |
| CDT, and it lasted for 2 minutes and 10 seconds. The licensee determined |
| that the health physic pump and red lights were inoperable at 1030 CDT. |
| |
| Prior to this event, the fluorination and distillation portions of this UF6 |
| conversion facility were down, and the licensee was operating the uranium |
| tetra-fluoride (UF4) portion of the facility. The licensee shut this |
| portion of the facility down a few minutes ago because there was no standby |
| power to the area due to a common bus outage. |
| |
| The licensee plans to inform the NRC Region 3 office and three NRC |
| inspectors that are currently located on site. (Call the NRC operations |
| officer for a licensee contact telephone number.) |
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|Power Reactor |Event Number: 35647 |
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/28/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 15:57[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/28/1999|
+------------------------------------------------+EVENT TIME: 15:00[EDT]|
| NRC NOTIFIED BY: BRIAN MUTZ |LAST UPDATE DATE: 04/28/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| DISCOVERY OF A SAFEGUARDS SYSTEM DEGRADATION RELATED TO THE PROTECTED AREA |
| (1-HOUR REPORT) |
| |
| Security personnel discovered a safeguard system degradation related to the |
| protected area. Immediate compensatory actions were taken upon discovery. |
| (Contact the NRC operations officer for additional details.) |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 35648 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/29/1999|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 00:45[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/28/1999|
+------------------------------------------------+EVENT TIME: 18:00[EDT]|
| NRC NOTIFIED BY: BRUCE BUTLER |LAST UPDATE DATE: 04/29/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|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 Y 16 Power Operation |16 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| - HPCI SYSTEM INOPERABLE DUE TO TRIPPED BAROMETRIC CONDENSER VACUUM PUMP |
| BREAKER - |
| |
| AT 1800 ON 04/28/99, WITH UNIT 1 AT 16% POWER, THE HIGH PRESSURE COOLANT |
| INJECTION (HPCI) SYSTEM BAROMETRIC CONDENSER VACUUM PUMP TRIPPED DURING A |
| TECH SPEC SURVEILLANCE TEST. PLANT OPERATORS WERE UNABLE TO RESET THE |
| VACUUM PUMP CIRCUIT BREAKER AND SHUT THE HPCI SYSTEM DOWN AND DECLARED THE |
| IT INOPERABLE. MAINTENANCE ELECTRICIANS RESET THE VACUUM PUMP CIRCUIT |
| BREAKER THERMAL OVERLOADS RESTORING POWER TO THE VACUUM PUMP. MAINTENANCE |
| ELECTRICIANS REPLACED THE HPCI SYSTEM VACUUM PUMP CONTROL SWITCH BECAUSE THE |
| SWITCH HAS RECENTLY EXPERIENCED PROBLEMS NOT RETURNING TO ITS MID POSITION, |
| AS DESIGNED. THE LICENSEE IS CONTINUING TO INVESTIGATE THE CAUSE OF THE |
| VACUUM PUMP TRIP. |
| |
| TECH SPEC LCO ACTION STATEMENT 3.5.1 REQUIRES THE LICENSEE TO VERIFY THE |
| OPERABILITY OF THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM AND RESTORE |
| THE HPCI SYSTEM TO OPERABLE STATUS WITHIN 14 DAYS OR SHUT UNIT 1 DOWN. AT |
| 1925, THE LICENSEE VERIFIED THE OPERABILITY OF THE RCIC SYSTEM. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
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|Power Reactor |Event Number: 35649 |
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+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/29/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 02:06[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/28/1999|
+------------------------------------------------+EVENT TIME: 21:51[CDT]|
| NRC NOTIFIED BY: RUSS GODWIN |LAST UPDATE DATE: 04/29/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| - Fuel Building inoperable due to loss of vacuum in Fuel Building due to an |
| open Fuel Building/Annulus door - |
| |
| At 2151 CDT on 04/28/99, with the plant in Operational Condition 5 in a |
| refueling outage, the Fuel Building was determined to be inoperable. At the |
| time, fuel inspection activities were in progress in the Fuel Building. |
| |
| The Fuel Building was rendered inoperable when a Fuel Building/Annulus door |
| was opened. The door was opened to allow entry of personnel for completion |
| of required testing of lighting circuits. The control room staff was alerted |
| to this condition when the "Fuel Building Pressure High" alarm was received. |
| Upon receipt of the alarm, the Control Room Supervisor directed that fuel |
| handling activities be suspended. Fuel handling activities were immediately |
| suspended and not resumed until the door was closed to reestablish Fuel |
| Building integrity. |
| |
| The fuel inspection activities in progress consisted of removing single fuel |
| pins from an irradiated bundle. The irradiated bundle was located in the |
| fuel preparation machine. |
| |
| The Fuel Building/Annulus door was required to be closed to maintain the |
| leak tightness of the Fuel Building. Plant staff personnel are continuing to |
| evaluate this event. However, as a result of the open door, the Fuel |
| Building may not have been able to perform its design function. |
| |
| The licensee informed the NRC Resident Inspector. |
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