Event Notification Report for April 3, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/31/2000 - 04/03/2000
** EVENT NUMBERS **
36737 36825 36849 36850 36851 36852 36853 36854 36855 36856
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36737 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/28/2000|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 23:29[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/28/2000|
+------------------------------------------------+EVENT TIME: 23:09[EST]|
| NRC NOTIFIED BY: STEVEN BAKER |LAST UPDATE DATE: 03/31/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP 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 |97 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN - BACKLEAKAGE FROM THE S/G TO THE AUXILIARY |
| FEEDWATER SYSTEM. |
| |
| Check valve leakage from the # 1 Steam Generator caused a rise in |
| temperature in the discharge piping of the "A" auxiliary feedwater pump. |
| The maximum allowed temperature is 190 degrees F. The maximum temperature |
| reached was 300 degrees F. The licensee entered Tech Spec 3.0.3 at 1209 and |
| started slowly lowering power. Injection with the "A" AFW pump reduced |
| the temperature in the line below the limit. The licensee is waiting to |
| determine if the check valve has reseated. |
| |
| The licensee notified the NRC resident inspector, the town of Waterford and |
| the state of Connecticut. |
| |
| * * * UPDATE 0026 2/29/2000 FROM JOHN CLAIR TAKEN BY BOB STRANSKY * * * |
| |
| TS 3.0.3 was exited at 2338 2/28/2000. The unit is returning to rated power. |
| The NRC resident inspector will be informed of this update by the licensee. |
| Notified R1DO (Trapp). |
| |
| * * * RETRACTION 0833 3/31/2000 FROM KENNETH TRUSDALE TAKEN BY STRANSKY * * |
| * |
| |
| "This call is to retract a call made on 2/28/2000 under 10 CFR 50.72 |
| regarding entry into Tech Spec Action Statement 3.0.3, as the plant was in a |
| condition prohibited by the Tech Specs. The original notification was made |
| because the Shift Manager had indication that the auxiliary feedwater piping |
| temperature was above normal, and he did not have enough information or |
| guidance at that time to determine that the auxiliary feedwater system was |
| operable. As operability was indeterminate, the Shift Manager conservatively |
| assumed the auxiliary feedwater system was inoperable, which is a condition |
| prohibited by the plant Technical Specifications. Subsequent research and |
| investigation determined that the auxiliary feedwater system was operable |
| throughout the event and the plant was not in a condition prohibited by the |
| Technical Specifications. |
| |
| "As the plant was not in a condition prohibited by the Technical |
| Specifications, there was no requirement to enter Action Statement 3.0.3. |
| The notification made on 2/28/2000 is withdrawn." |
| |
| The NRC resident inspector has been informed of this retraction by the |
| licensee. Notified R1DO (Evans). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36825 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/23/2000|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 13:11[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/23/2000|
+------------------------------------------------+EVENT TIME: 12:00[EST]|
| NRC NOTIFIED BY: DENNIS CORNAX |LAST UPDATE DATE: 03/31/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LOUIS MANNING R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| C-3 DEFECTS DETECTED DURING EDDY CURRENT INSPECTION OF STEAM GENERATORS |
| |
| Indian Point 2 is conducting eddy current testing of 100% of the steam |
| generator (SG) tubes. With about 90% of the inspection complete, SG-21 and |
| SG-24 tubes have defects in greater than 1% of the tubes inspected. SG-22 |
| and SG-23 have defects in much less than 1% of the tubes inspected. The |
| majority of the defects are at the support plate intersections and in row 2 |
| U-bends. There are 41 indications in SG-21, 40 at the support plate and 1 |
| in the U-bend. There are 39 indications in SG-24, 36 at the support plate |
| and 3 in the U-bend. In accordance with Technical Specification 4.13, these |
| defects result in a C-3 classification. The testing will continue until |
| 100% of the tubes are inspected. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| |
| UPDATE ON 3/31/2000 BY LAMB, RECEIVED BY WEAVER * * * |
| |
| This report is being made as a follow up to previously reported event number |
| 36825. At approximately 1500 today, the tube at Row 2 Column 69 in steam |
| generator 24 failed the three delta pressure requirement during in-situ |
| pressure testing being performed in accordance with NEI 97-06 guidelines to |
| meet Technical Specification requirements. The three delta pressure value |
| was calculated to be 5118 psi, and with uncertainties applied, the test |
| pressure was specified at 5173 psi. Shortly after achieving 5173 psi for |
| the required two seconds specified in the test, pressure was noted to |
| rapidly drop indicating leakage. No leakage was observed at a steam line |
| test pressure of 2841 psi. Therefore, that performance criterion was met. |
| |
| The licensee notified the NRC resident inspector. The operations center |
| notified the R1DO (Evans). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36849 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 03/31/2000|
|LICENSEE: J. B. COXWELL CONTRACTING, INC. |NOTIFICATION TIME: 07:31[EST]|
| CITY: JACKSONVILLE REGION: 2 |EVENT DATE: 03/31/2000|
| COUNTY: STATE: FL |EVENT TIME: [EST]|
|LICENSE#: FL 2904-1 AGREEMENT: Y |LAST UPDATE DATE: 03/31/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CAUDLE JULIAN R2 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JERRY EAKINS | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN MOISTURE/DENSITY GAUGE |
| |
| The Florida Bureau of Radiation Control reported the theft of a Troxler |
| Model 3430 moisture/density gauge (Serial Number 2904-1) from a state |
| licensee. The theft occurred sometime between 0000 and 0600 on 3/31/2000 |
| from the parking lot of a motel in Jacksonville, FL. The gauge was stored in |
| its case, which was chained to the bed of a pickup truck. The chain was cut, |
| and both the gauge and case were taken. The theft has been reported to the |
| Jacksonville Police Department. The state has requested that the licensee |
| post a reward for the return of the gauge, and is helping the licensee to |
| prepare a press release regarding this incident. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36850 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/31/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:10[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/31/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: [CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/31/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |RONALD GARDNER R3 |
| DOCKET: 0707001 |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC WALKER | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM FAILURE DURING A TEST |
| |
| At 1845 on 03-30-2000, during functional testing of C-746Q Criticality |
| Accident Alarm System (CAAS), it was discovered that temperature control |
| system on cluster "AD" was unable to perform the ability to maintain the |
| system above the manufacturer's fourteen degree Fahrenheit recommendation |
| due to failure of a temperature switch. The system was last tested on |
| 12-30-99 and was determined to be functional at that time. In January of |
| this year there were several days were outside ambient temperature dropped |
| below fourteen degrees Fahrenheit and operability of system at those times |
| cannot be reasonably determined. Even though the failure was discovered |
| during testing, it is possible that the system would not have performed its |
| intended safety function if it had been required to since the last |
| surveillance on 12-30-99. |
| |
| This event is reportable under 10 CFR 76.120(c)(2) as an event in which |
| equipment required by the TSR is disabled or fails to function as designed. |
| |
| The NRC Senior Resident Inspector has been notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36851 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 03/31/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 15:40[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 03/31/2000|
+------------------------------------------------+EVENT TIME: 14:48[EST]|
| NRC NOTIFIED BY: MAURICE GRIFFIN |LAST UPDATE DATE: 03/31/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|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 Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A CONTRACT EMPLOYEE WAS INAPPROPRIATELY GRANTED UNESCORTED ACCESS. ACCESS |
| HAS BEEN SUSPENDED PENDING FURTHER INVESTIGATION. THE LICENSEE WILL NOTIFY |
| THE NRC RESIDENT INSPECTOR. ADDITIONAL DETAILS ARE AVAILABLE FROM THE NRC |
| OPERATIONS CENTER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36852 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/01/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 11:02[EST]|
| RXTYPE: [1] CE |EVENT DATE: 04/01/2000|
+------------------------------------------------+EVENT TIME: 09:20[CST]|
| NRC NOTIFIED BY: LARRY LEES |LAST UPDATE DATE: 04/01/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KRISS KENNEDY R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Standby |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN DUE TO EMERGENCY FEEDWATER STORAGE TANK LEVEL |
| DECREASING BELOW TECH SPEC LIMIT |
| |
| THE PLANT ENTERED ABNORMAL OPERATING PROCEDURE (AOP) 30, "EMERGENCY FILL OF |
| EMERGENCY FEEDWATER STORAGE TANK," AS A RESULT OF THE EMERGENCY FEEDWATER |
| STORAGE TANK LEVEL FALLING BELOW TECH SPEC LOW LIMIT OF 91%. THIS RESULTED |
| IN ENTRY INTO TECH SPEC 2.0.1 WHICH DIRECTS PLACING THE PLANT IN HOT |
| SHUTDOWN WITHIN 6 HOURS, LESS THAN 300 DEGREES F IN ANOTHER 6 HOURS AND IN |
| COLD SHUTDOWN IN 30 HOURS. AT THE TIME OF ENTRY INTO THIS TECH SPEC THE |
| PLANT WAS ALREADY IN HOT SHUTDOWN. ACTIONS TO REFILL THE EMERGENCY |
| FEEDWATER STORAGE TANK WERE TAKEN BY OPENING THE CONDENSATE FILL LINE AND |
| EMERGENCY FILLING. FILLING WAS IN PROGRESS BEFORE GOING BELOW 91%, HOWEVER, |
| SYSTEM DEMAND WAS GREATER THAN THE MAKEUP ABILITY OF THE DEMINERALIZED WATER |
| SOURCE (STEAM GENERATOR WATER SUPPLY SWAPOVER). LEVEL WAS ABOVE 91% AT |
| 0944CST AT WHICH TIME AOP 30 AND TECH SPEC 2.0.1 WERE EXITED. |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36853 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 04/01/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 21:04[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 04/01/2000|
+------------------------------------------------+EVENT TIME: 17:38[EST]|
| NRC NOTIFIED BY: TOM PLUMPTON |LAST UPDATE DATE: 04/01/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHELE EVANS R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 26 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM |
| |
| During a planned power reduction, the recombiner was removed from service. |
| The recombiner bypass valve shut, reason unknown, isolating all off gas |
| flow. Vacuum decayed as a result. The main turbine was manually tripped, |
| followed by an automatic reactor scram. |
| |
| Three rods did not indicate fully inserted immediately after the trip, but |
| were later verified to be full in. The recirculating pumps are running and |
| steam is being dumped to the main condenser (vacuum was restored) to remove |
| decay heat. |
| |
| The licensee informed the NRC resident inspector and will make a press |
| release. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36854 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/01/2000|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 22:28[EST]|
| RXTYPE: [2] GE-4 |EVENT DATE: 04/01/2000|
+------------------------------------------------+EVENT TIME: 19:15[EST]|
| NRC NOTIFIED BY: KEVIN DAHM |LAST UPDATE DATE: 04/01/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER R3 |
|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 M/R Y 23 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM |
| |
| On Saturday 4/1/2000, at 1200 hours, control room operators commenced a |
| planned unit shutdown in preparation for refueling outage number 7. At |
| 1815 hours, the 'A' Reactor Recirculation Pump exhibited speed fluctuations |
| and was tripped. The crew conducted an evaluation to determine existing |
| procedure guidance for operation at low power and low flow in a single loop |
| configuration, and conservatively decided to shut down the reactor. At 1915 |
| hours, the Reactor Operator placed the Reactor Mode Switch in Shutdown |
| inserting a manual scram from 23% reactor power. All control rods fully |
| inserted. All systems operated as expected, no safety/relief valves opened |
| and no ECCS systems initiated/actuated. |
| |
| The lowest reactor water level observed was 163 inches, normal operating |
| band is 196 inches, all level three isolations (173 inches) came in as |
| expected. At present, reactor water level is operating in normal operating |
| band and is being maintained on the startup level control valve. No steam |
| leaks noted. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36855 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/02/2000|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 07:25[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/02/2000|
+------------------------------------------------+EVENT TIME: 05:05[CDT]|
| NRC NOTIFIED BY: BILL ARENS |LAST UPDATE DATE: 04/02/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|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 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 1 HOUR SECURITY REPORT |
| |
| UNESCORTED PROTECTED AREA ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE |
| COMPENSATORY MEASURES TAKEN. THE LICENSEE WILL INFORM THE NRC RESIDENT |
| INSPECTOR. |
| |
| CONTACT THE HEADQUARTERS OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
| |
| * * * UPDATE 0955EDT ON 4/2/00 FROM VINCE MURPHY TO S.SANDIN * * * |
| |
| THE LICENSEE PROVIDED ADDITIONAL SPECIFIC INFORMATION. A REVIEW WILL BE |
| PERFORMED ON MONDAY 4/3 TO DETERMINE REPORTABILITY. NOTIFIED R2DO (JULIAN). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36856 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 04/02/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 09:38[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 04/02/2000|
+------------------------------------------------+EVENT TIME: 09:17[EDT]|
| NRC NOTIFIED BY: STAN LOWE |LAST UPDATE DATE: 04/02/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |CAUDLE JULIAN R2 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |CHARLES MILLER IRO |
| |CEGIELSKI FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO LOSS OF THE EMERGENCY RESPONSE FACILITY |
| INFORMATION SYSTEM (ERFIS) FOR GREATER THAN 4 HOURS |
| |
| AT 0917EDT THE LICENSEE DECLARED AN UNUSUAL EVENT BASED ON EMERGENCY ACTION |
| LEVEL (EAL) 6-2-1, "INABILITY OF ERFIS TO PERFORM ITS INTENDED FUNCTION FOR |
| A CONTINUOUS PERIOD OF 4 HOURS." BOTH THE "A" AND "B" PLANT PROCESS |
| COMPUTERS WHICH SUPPLY INPUT DATA TO ERFIS WOULD NOT REBOOT FOR REASONS |
| UNKNOWN. ADDITIONAL INFORMATION TECHNOLOGY (IT) STAFF HAS BEEN BROUGHT IN |
| TO RESOLVE THE FAILURE. THE LICENSEE HAS IMPLEMENTED MONITORING ON |
| REDUNDANT EQUIPMENT IN ACCORANCE WITH TECH SPEC REQUIREMENTS. THE UNIT IS |
| CURRENTLY STABLE AT 100% POWER. |
| |
| THE LICENSEE INFORMED STATE AND COUNTY AGENCIES AND WILL INFORM THE NRC |
| RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 1644 ON 4/2/00, BY LOWE RECEIVED BY WEAVER * * * |
| |
| The licensee terminated the Unusual Event at 1630 after having repaired and |
| tested the ERFIS system. The licensee informed the NRC resident inspector |
| as well as state and county agencies. The Operations Center notified the |
| RDO (Julian), EO (Zwolinski) and FEMA (Cegielski). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021