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Event Notification Report for May 19, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/18/1999 - 05/19/1999

                              ** EVENT NUMBERS **

35604  35729  35730  35731  35732  35734  35735  35736  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35604       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 04/19/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 15:07[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        04/19/1999|
+------------------------------------------------+EVENT TIME:        11:15[EDT]|
| NRC NOTIFIED BY:  RICK LANGE                   |LAST UPDATE DATE:  05/18/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION NOTIFIED OF 11 GALLON    |
| OIL SPILL -                                                                  |
|                                                                              |
| AT 1115 ON 04/19/99, THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF  |
| ENVIRONMENTAL CONSERVATION THAT APPROXIMATELY 11 GALLONS OF HYDRAULIC OIL    |
| HAD SPILLED ON PAVED AND UNPAVED AREAS FROM A RUPTURED FORKLIFT HYDRAULIC    |
| LINE.  THE LICENSEE CLEANED UP THE OIL AND REMOVED THE AFFECTED SOIL.        |
|                                                                              |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR.                     |
|                                                                              |
| * * * UPDATE 1431EDT ON 5/18/99 FROM BRIAN WEAVER TO S.SANDIN * * *          |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "At 1507 on 4/19/99, a 4-hr non-emergency phone notification was made to the |
| NRC by this facility regarding an 11 gallon hydraulic oil spill on paved and |
| unpaved areas from a rupture on a forklift hydraulic line under the category |
| of 10CFR 50.72(b)(2)(vi),  Any event or situation, related to the health and |
| safety of the public or onsite personnel, or protection of the environment,  |
| for which a news release is planned or notification to other government      |
| agencies has been or will be made.                                           |
|                                                                              |
| "Subsequent review of the site reportability procedure and 10CFR             |
| 50.72(b)(2)(vi) has determined that this event is not reportable under that  |
| statute, specifically that the oil spill was not environmentally significant |
| in that the volume was actually only 2.5 gallons and that the spill was      |
| immediately contained and cleaned up such that no oil reached ground or      |
| surface water. No news release was made for the incident.                    |
|                                                                              |
| "On this basis, this notification is being retracted."                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  Notified R1DO(Trapp).     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35729       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 05/18/1999|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 02:07[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        05/18/1999|
+------------------------------------------------+EVENT TIME:        00:41[EDT]|
| NRC NOTIFIED BY:  MIKE ECKHART                 |LAST UPDATE DATE:  05/18/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RUDOLPH BERNHARD     R2      |
|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     M/R        Y       83       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP FROM 73% POWER DUE TO UNEXPECTED HIGH  MAIN TURBINE      |
| VIBRATION                                                                    |
|                                                                              |
| While the licensee was in the process of increasing load after exiting a     |
| refueling outage, vibrations on the #1 and #2 bearings for the main turbine  |
| were noted to be increasing unexpectedly.  As a result, operators began to   |
| decrease load at 0036 on 05/18/99 with the unit at approximately 83% reactor |
| power.  Operators manually tripped the reactor from 73% power at 0041.  At   |
| that time of the manual reactor trip, vibrations on the #1 and #2 bearings   |
| were at a level of about 10 mills and 12 mils, respectively.  The limits on |
| vibration are either 10 mils for 15 minutes or when a vibration of 12 mils   |
| is reached.                                                                  |
|                                                                              |
| All control rods fully inserted as a result of the manual reactor trip, and  |
| all systems functioned as required.  There were no engineered safety feature |
| actuations or emergency core cooling system injections, and none were        |
| required.                                                                    |
|                                                                              |
| The unit is currently stable in Mode 3 (Hot Standby).  The reactor coolant   |
| pumps, normal charging and letdown, and pressurizer heaters and sprays are   |
| being utilized for primary system transport, level, and pressure control.    |
| All containment parameters are normal.  Emergency feedwater was manually     |
| initiated and is currently supplying water to the steam generators.          |
| Secondary steam is being dumped to the condenser.  Offsite power is          |
| available, and the emergency diesel generators and emergency core cooling    |
| systems are operable and available if needed.                                |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35730       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 05/18/1999|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 12:24[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/18/1999|
+------------------------------------------------+EVENT TIME:        09:07[EDT]|
| NRC NOTIFIED BY:  ART BREADY                   |LAST UPDATE DATE:  05/18/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |JIM TRAPP            R1      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Primary Containment Isolation Signal (PCIS) unexpectedly generated during    |
| planned maintenance on the "B" channel Radiation Monitoring System.          |
|                                                                              |
| "While de-energizing the 'B' channel Radiation Monitoring System (RMS) to    |
| replace a power supply, an unexpected 'B' channel actuation of the Primary   |
| Containment Isolation System (PCIS, an ESF system)                           |
| occurred. The single channel actuation resulted in isolation of three        |
| Containment Isolation Valves, electrical load shedding of two non-1E         |
| ventilation fans, and automatic starts of the 'B' channel Filtration         |
| Recirculation and Ventilation (FRVS) fans and Safety Auxiliaries Cooling     |
| Pump (SACS).  All isolations and actuations occurred as designed.  The power |
| supply was re-energized and plant systems and components restored.  The      |
| impact on plant operation from this single channel PCIS actuation was        |
| minimal.  All plant safety systems remained capable of performing their      |
| required functions, except for the 'B' Switchgear Room Cooler which had been |
| removed from service for scheduled maintenance.  As a result of the change   |
| in Reactor Building pressure, the Reactor Building to Turbine Building steam |
| tunnel blowout panel briefly indicated open, and is currently closed.  A     |
| visual inspection of the blowout panel is in progress.                       |
|                                                                              |
| "The initial investigation has determined that de-energizing the 'B' channel |
| RMS power supply simulated high Reactor Building exhaust and Refueling Floor |
| exhaust radiation signals from the three RMS channels which input into the   |
| 'B' PCIS channel.  Investigation into the root cause of the single channel   |
| actuation is in progress."                                                   |
|                                                                              |
| The licensee informed the NRC Resident Inspector and will inform local       |
| authorities (LAC Township).                                                  |
|                                                                              |
| * * * UPDATE 1453 EDT ON 5/18/99 FROM BREADY TO S. SANDIN * * *              |
|                                                                              |
| The licensee has completed the visual inspection of the blowout panel with   |
| no abnormalities noted.  The licensee will inform the NRC Resident           |
| Inspector.  Notified R1DO(Eselgroth).                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35731       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 05/18/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 12:47[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        05/18/1999|
+------------------------------------------------+EVENT TIME:             [EDT]|
| NRC NOTIFIED BY:  JOSEPH A. WIDAY (FAX)        |LAST UPDATE DATE:  05/18/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIM TRAPP            R1      |
|10 CFR SECTION:                                 |VERN HODGE           NRR     |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DEFICIENT CONTROL RELAYS IDENTIFIED DURING PRE-INSTALLATION TESTING.         |
|                                                                              |
| ON 4/2/99, THE LICENSEE IDENTIFIED THAT CONTROL RELAYS (NBFD65NR)            |
| MANUFACTURED BY EATON CORPORATION CONTAINED A MANUFACTURING DEFICIENCY,      |
| I.E., "THE RELAY COIL HAD BEEN INCORRECTLY WIRED SUCH THAT THE INTERNAL      |
| RELAY DESIGN, WHICH INCLUDES A PICK UP AND A HOLD COIL, WOULD OPPOSE EACH    |
| OTHER AT LOWER VOLTAGES AND PROHIBIT HOLDING COIL ACTUATION WHICH RESULTED   |
| IN EXCESSIVE RELAY CHATTER."  THIS DEFECT WAS IDENTIFIED DURING              |
| PRE-INSTALLATION TESTING PRIOR TO USE IN THE REACTOR TRIP LOGIC.  NO         |
| DEFICIENT RELAYS ARE INSTALLED.                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35732       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 05/18/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:06[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/17/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        15:40[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/18/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRENT CLAYTON        R3      |
|  DOCKET:  0707002                              |SCOTT MOORE          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT DUE TO A "Q" SAFETY SYSTEM ACTUATION.                         |
|                                                                              |
| "ON 5/17/99 AT 1540 HOURS THE #2 AUTOCLAVE EXPERIENCED A STEAM SHUT DOWN.    |
| THE AUTOCLAVE WAS IN MODE II(HEATING) APPROXIMATELY TEN MINUTES WHEN THE     |
| AUTOCLAVE EXPERIENCED A STEAM SHUTDOWN.  OPERATIONS PERSONNEL ATTEMPTING TO  |
| DETERMINE THE CAUSE RE-OPENED THE STEAM VALVE AND THEN RECEIVED A HIGH       |
| CONDENSATE LEVEL SHUTDOWN ALARM. THE AUTOCLAVE WAS DECLARED INOPERABLE AT    |
| 1710 HOURS AND INVESTIGATIONS ARE ON GOING.                                  |
|                                                                              |
| "THIS WAS AN AUTOMATIC ACTUATION OF A 'Q' SAFETY SYSTEM AND IS REPORTABLE TO |
| THE NRC BY USEC WITHIN 24 HOURS.  THE SENIOR NRC RESIDENT HAS BEEN           |
| NOTIFIED.                                                                    |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35734       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 05/18/1999|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 15:52[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        05/18/1999|
+------------------------------------------------+EVENT TIME:        15:00[EDT]|
| NRC NOTIFIED BY:  RON STRICKLAND               |LAST UPDATE DATE:  05/18/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETER ESELGROTH      R1      |
|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       85       Power Operation  |85       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 1-HOUR SECURITY REPORT                                                       |
|                                                                              |
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO DETECTION/MONITORING/ALARM OF VITAL |
| AREA ACCESS DOORS.  IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY.     |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.  CONTACT THE            |
| HEADQUARTERS OPERATIONS CENTER FOR ADDITIONAL DETAILS.                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35735       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 05/18/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 17:58[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        05/18/1999|
+------------------------------------------------+EVENT TIME:        17:08[EDT]|
| NRC NOTIFIED BY:  MICHAEL CLOUTIER             |LAST UPDATE DATE:  05/18/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|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     M/R        Y       97       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 MANUALLY SCRAMMED FOLLOWING TRIP OF THE "A" RECIRC PUMP.              |
|                                                                              |
| Unit 2 was manually scrammed following the unexpected trip of the "A" recirc |
| pump.  At the time, electrical maintenance was in progress on the respective |
| motor-generator set.  Following the recirc pump trip, operators initiated a  |
| manual scram per procedure based on power-to-flow criteria.  There was no    |
| power peaking observed.  All control rods fully inserted.  Unit 2 is         |
| currently in hot shutdown with steam bleed to the main condenser for decay   |
| heat removal.  All systems functioned as required.  Both the traverse incore |
| probes and the recirc sump isolated during the transient as expected.        |
| Offsite power is available and the emergency diesel generators are in        |
| standby.  The licensee informed the NRC Resident Inspector.                  |
|                                                                              |
| * * * UPDATE 2108EDT ON 5/18/99 FROM JEFF GROFF TO S.SANDIN * * *            |
|                                                                              |
| The following information was provided as an update:                         |
|                                                                              |
| "On 5/18/99 at 17:08, operators inserted a manual reactor scram due to       |
| operation in the 'Scram Region' of the Power to Flow Map.  All control rods  |
| fully inserted into the core.  Reactor water level is being maintained in    |
| the normal operating band using the condensate system.                       |
|                                                                              |
| "Preliminary investigation determined that while performing routine field    |
| brush maintenance, a ground occurred tripping the 'A' Recirculation Pump.    |
| The subsequent reactor power and flow decrease placed the reactor in the     |
| 'Scram Region.'                                                              |
|                                                                              |
| "Following the scram, water level dropped to approximately 130 inches, the   |
| following 'Level 3' isolations occurred as expected:                         |
|                                                                              |
| Group 4 - RHR Shutdown Cooling and Head Spray                                |
| Group 13 - Drywell Sumps                                                     |
| Group 15 - Traversing Incore Probe System                                    |
|                                                                              |
| "All valves in Group 4 and 15 were closed prior to the event, Group 13       |
| valves closed as designed.  No ECCS systems initiated and no SRVs lifted.    |
| All Emergency Diesel Generators are available."                              |
|                                                                              |
| The licensee informed the NRC Resident Inspector of this update.  Notified   |
| R3DO(Clayton).                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35736       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 05/18/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 19:13[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/18/1999|
+------------------------------------------------+EVENT TIME:        18:52[EDT]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  05/18/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |PETER ESELGROTH      R1      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |CHARLES MILLER       IRO     |
|                                                |SAM COLLINS          NRR     |
|                                                |JOHN ZWOLINSKI       NRR     |
|                                                |VICTOR DRICKS        OPA     |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO REQUEST FOR OFFSITE FIRE FIGHTING ASSISTANCE   |
| TO EXTINGUISH MAIN TRANSFORMER FIRE.                                         |
|                                                                              |
| THE UNIT IS CURRENTLY IN A REFUELING OUTAGE WITH FUEL IN THE VESSEL WITH NO  |
| FUEL MOVEMENTS IN PROGRESS.  DURING HI-POT TESTING OF THE MAIN TRANSFORMER   |
| WHICH HAD BEEN DISCONNECTED FROM THE ELECTRICAL DISTRIBUTION SYSTEM, SMOKE   |
| ERUPTED AT 1832EDT.  THE FIRE BRIGADE RESPONDED AND A REQUEST FOR ASSISTANCE |
| TO THE PLYMOUTH FIRE DEPARTMENT WAS MADE.  AT 1852EDT THE LICENSEE DECLARED  |
| AN UNUSUAL EVENT BASED ON "ANY FIRE ONSITE FOR WHICH FIRE FIGHTING           |
| ASSISTANCE IS REQUESTED."  THERE WERE NO INJURIES OR UNACCOUNTED FOR         |
| PERSONNEL.  PLANT OPERATIONS IS NOT IMPACTED.  THE FIRE BRIGADE IS ON SCENE  |
| USING CARBON DIOXIDE FOR FIRE SUPPRESSION.  LAYDOWN HOSES ARE POSITIONED     |
| SHOULD THEY BECOME NECESSARY.  THE LICENSEE DESCRIBED THE FIRE AS SMOLDERING |
| WITH NO VISIBLE FLAMES AND WAS NOT ABLE TO PROVIDE A DAMAGE ASSESSMENT AT    |
| THIS TIME.                                                                   |
|                                                                              |
| THE LICENSEE CONTACTED STATE/LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR.  |
|                                                                              |
| * * * UPDATE 2143EDT ON 5/18/99 FROM MIKE ENGLAND TO S.SANDIN * * *          |
|                                                                              |
| THE UNUSUAL EVENT WAS TERMINATED AT 2125EDT AFTER VERIFYING THAT THE FIRE    |
| WAS EXTINGUISHED.  THE FIRE DEPARTMENT IS EXITING THE SITE.  THE LICENSEE IS |
| PERFORMING A DAMAGE ASSESSMENT AT THIS TIME AND HAS INFORMED STATE/LOCAL     |
| AGENCIES AND THE NRC RESIDENT INSPECTOR.  NOTIFIED R1(ESELGROTH, ANDERSON),  |
| NRR(RICHARDS) AND IRO(MILLER) AND FEMA (DEPUY).                              |
+------------------------------------------------------------------------------+