Event Notification Report for January 2, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/31/2001 - 01/02/2002
** EVENT NUMBERS **
38599 38600 38601 38602 38603 38604
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|Power Reactor |Event Number: 38599 |
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+------------------------------------------------------------------------------+
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| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/31/2001|
| UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 02:00[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/31/2001|
+------------------------------------------------+EVENT TIME: 00:10[EST]|
| NRC NOTIFIED BY: S. SAUER |LAST UPDATE DATE: 12/31/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHELE EVANS R1 |
|10 CFR SECTION: | |
|ACCS 50.72(b)(2)(iv)(A) ECCS INJECTION | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| REACTOR TRIP AND SAFETY INJECTION DUE TO SPRAY VALVE FAILING OPEN |
| |
| The unit experienced a reactor trip and safety injection as a result of a |
| pressurizer spray valve (2PS3) failing open. This caused a reactor trip on |
| Overtemperature DeltaT and a safety injection on low reactor coolant system |
| pressure. All emergency equipment responded properly, all safety injection |
| pumps started and all control rods fully inserted. The emergency diesels |
| started, but were not required to load. The auxiliary feedwater pumps |
| started on low steam generator level. The pressurizer spray valve closed |
| when the valve's operating air was isolated. |
| |
| The unit is stable in Mode 3 (Hot Standby) at normal temperature and |
| pressure. Auxiliary feedwater and steam dumps are in use to maintain steam |
| generator level and remove excess heat. An investigation of the failure is |
| underway. |
| |
| The licensee intends to notify the NRC Resident Inspector and the local |
| Township. |
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|Power Reactor |Event Number: 38600 |
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| FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 01/01/2002|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 03:19[EST]|
| RXTYPE: [1] B&W-R-LP |EVENT DATE: 12/31/2001|
+------------------------------------------------+EVENT TIME: 19:22[EST]|
| NRC NOTIFIED BY: RICHARD WALLEMAN |LAST UPDATE DATE: 01/01/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GARY SHEAR R3 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE |
| |
| The licensee reported that the SPDS display screens were locked up and thus |
| unavailable for use in case of an incident. Several procedures including |
| the Emergency Operating Procedures refer to the displays for information. |
| With the system unavailable for greater than 8 hours a report under loss of |
| assessment capabilities was made. The SPDS is being worked on at this time |
| and is expected back in service in a short period of time. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * UPDATE 1622EST ON 1/1/02 FROM TOM COBBLEDICK TO S. SANDIN * * * |
| |
| The SPDS was restored to service as of 1615EST. The licensee will inform |
| the NRC Resident Inspector. Notified R3DO(Shear). |
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|Power Reactor |Event Number: 38601 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/01/2002|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 09:41[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/01/2002|
+------------------------------------------------+EVENT TIME: 00:42[CST]|
| NRC NOTIFIED BY: STEVE WHEELER |LAST UPDATE DATE: 01/01/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 10 Power Operation |10 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) TURBINE DETERMINED TO BE
INOPERABLE |
| |
| The licensee determined during surveillance testing that the HPCI turbine |
| was inoperable due to the minimum flow valve cycling open and closed due to |
| problem with the associated flow switch. The problem is being worked on. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38602 |
+------------------------------------------------------------------------------+
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| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 01/01/2002|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 10:08[EST]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 01/01/2002|
+------------------------------------------------+EVENT TIME: 09:19[EST]|
| NRC NOTIFIED BY: BILL BANDHAUER |LAST UPDATE DATE: 01/01/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE BOLAND R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE RESCUED SEA TURTLE |
| |
| EN #37902 started the biennial report period. |
| |
| On January 1, 2002 at 0919, a rescued sea turtle was identified as a green |
| sea turtle. This is the 62nd rescue of a live sea turtle at Crystal River |
| Unit 3 (CR-3) in this biennial period. Notification to the National Marine |
| Fisheries Service and the Florida Fish and Wildlife Conservation Commission. |
| |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 38603 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE:
01/01/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/01/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 21:32[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/01/2002|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR R3 |
| DOCKET: 0707002 |THOMAS ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM McCLEERY | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 4-HOUR REPORT DUE TO EPA NOTIFICATION REGARDING AN OPACITY VIOLATION
|
| |
| The M4 electrical feeder was lost causing instrumentation associated with |
| Boiler #3 control to deenergize. This resulted in pollutant discharge |
| exceeding the 60% opacity limit specified by EPA to occur between 1620 and |
| 1720EST. Operations notified the Ohio Environmental Protection Agency |
| (OEPA) of the violation. |
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|Power Reactor |Event Number: 38604 |
+------------------------------------------------------------------------------+
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| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 01/02/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 04:56[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 01/02/2002|
+------------------------------------------------+EVENT TIME: 03:05[EST]|
| NRC NOTIFIED BY: SCOTT SAUNDERS |LAST UPDATE DATE: 01/02/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE BOLAND R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 7 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO DECREASING STEAM GENERATOR WATER LEVEL.
|
| |
| During a plant start-up at 7% reactor power, feedwater oscillations occurred |
| on all three steam generators. At 0215 on 01/02/02 the main feedwater |
| regulator bypass valves were placed in manual control to stabilize level. |
| The bypass valves were then returned to automatic control at 0245 on |
| 01/02/02, and the oscillations continued within the normal operating band of |
| 52-62%. At 0300 0n 01/02/02. The Control Operator noted lowering level on |
| the "C" steam generator at approximately 55% with indication that the "C" |
| main feedwater regulator bypass valve was shut. The operator placed the "C" |
| bypass valve in manual control and attempted to open the valve with no |
| response noted in valve position indication. At 30% indicated level in the |
| "C" steam generator and a lowering trend, the Unit Shift Control Operator |
| ordered a manual reactor trip prior to receipt of a steam generator low |
| water level trip signal at 25%. All safety systems functioned as expected. |
| Both Motor Driven Auxiliary Feedwater Pumps automatically actuated on the |
| subsequent 'C" steam generator low water level signal. All rods fully |
| inserted into the core and the electrical grid is stable. An investigation |
| into what caused this event is in progress. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
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