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Event Notification Report for September 5, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/01/2000 - 09/05/2000

                              ** EVENT NUMBERS **

37281  37282  37283  37284  37285  37286  37287  37288  37289  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37281       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 08/31/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 21:32[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        08/31/2000|
+------------------------------------------------+EVENT TIME:        17:47[CDT]|
| NRC NOTIFIED BY:  TIEDEMANN                    |LAST UPDATE DATE:  09/01/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED 72 HOUR LCO ACTION STATEMENT WHEN DIVISION III DIESEL          |
| GENERATOR WAS DECLARED INOPERABLE                                            |
|                                                                              |
| During performance of Fire Protection Surveillance 9337.81 (performs a       |
| functional check of the Division III Diesel Generator (DG) Carbon Dioxide    |
| (CO2) system operation), the Division III DG ventilation system tripped      |
| during restoration.  Electrical Maintenance personnel were performing a      |
| functional check of the Division III DG room thermal detectors when the      |
| panel reset push button was depressed.  The anticipated resets did not occur |
| and the decision was made to restore the system to a safe condition.  During |
| restoration, a sticking relay prevented restoration of the Division III DG   |
| ventilation system.  The relay has been reset and the ventilation system     |
| restored.                                                                    |
|                                                                              |
| Division III DG was declared INOPERABLE at 1747 and the plant entered LCO    |
| 3.8.1.                                                                       |
| Action B.1- Perform 9082.01 within 1 hour and every 8 hours thereafter.      |
| Action B.2- Declare required features supported by Division Ill DG inop when |
| the redundant required features are inop, within 4 hours.                    |
| Action B.3.1- Determine Operable DG are not inop due to common cause failure |
| within 24 hours - This action -completed.                                    |
| Action B.4- Restore Div 3 DG to Operable within 72 hrs.                      |
| Division Ill DG was declared OPERABLE at 1813 and the LCO was exited.        |
|                                                                              |
| The NRC Resident Inspector was notified..                                    |
|                                                                              |
| * * * UPDATE ON 09/01/00 @ 1400 BY SHELTON TO GOULD * * *                    |
|                                                                              |
| The time the diesel became inoperable was 1420 but it was not declared       |
| inoperable until 1747.   This event is being reported pursuant to 10CFR50.72 |
| (b)(2)(iii)(D) as a condition that alone could have prevented the            |
| fulfillment of the High Pressure Core Spray (HPCS) system, a single-train    |
| safety system needed to mitigate the consequences of an accident, since the  |
| Div. 3 DG is an essential support system for the HPCS system needed to       |
| mitigate a small break LOCA concurrent with a loss of offsite power.         |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| The Reg 3 RDO (Leach) was notified.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37282       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ENGELHARDT & ASSOCIATES              |NOTIFICATION DATE: 09/01/2000|
|LICENSEE:  ENGELHARDT & ASSOCIATES              |NOTIFICATION TIME: 10:09[EDT]|
|    CITY:  MADISON                  REGION:  3  |EVENT DATE:        06/12/2000|
|  COUNTY:                            STATE:  WI |EVENT TIME:             [CDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  09/01/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MELVYN LEACH         R3      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SUSAN ENGELHARDT             |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AN EMPLOYEE OF A RADIATION CONSULTING FIRM MAY HAVE RECEIVED A PERSONNEL     |
| OVEREXPOSURE                                                                 |
|                                                                              |
| ENGELHARDT & ASSOCIATES, INC. WAS HIRED BY SOUTHEAST MISSOURI STATE          |
| UNIVERSITY LOCATED IN CAPE GIRARDEAU, MO. TO ASSESS AND UPGRADE THE          |
| UNIVERSITY'S RADIATION SAFETY PROGRAM.  SEVERAL YEARS BEFORE THE UNIVERSITY  |
| INFORMED THE NRC THAT A COUPLE OF AMERICIUM-241 SOURCES HAD BEEN REMOVED.    |
| DURING AN NRC RIII INSPECTION LATE LAST YEAR, THE SOURCES WERE FOUND ON      |
| CAMPUS.  DURING THE CONSULTANTS ASSESSMENT,  HE DISCOVERED THAT ONE OF THE   |
| SOURCES HAD BEEN SPILLED (LIQUID FORM) CAUSING A LARGER PROBLEM THAN         |
| INITIALLY BELIEVED.  THE EMPLOYEE'S UPTAKE WAS DETERMINED BY ARGONNE         |
| NATIONAL LAB TO BE ON THE ORDER OF 9 REM CUMULATIVE DOSE EQUIVALENT.  NRC    |
| REGION III (WRIGHT, JORGENSEN) WAS INFORMED BY ENGELHARDT.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37283       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 09/01/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 12:20[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/01/2000|
+------------------------------------------------+EVENT TIME:        11:30[EDT]|
| NRC NOTIFIED BY:  UNDERWOOD                    |LAST UPDATE DATE:  09/01/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT HAD CLOSURE OF THE POST ACCIDENT SAMPLING SYSTEM INBOARD PRIMARY       |
| CONTAINMENT ISOLATION VALVE                                                  |
|                                                                              |
| During performance of Reactor Building Isolation LSFT (34SV-SUV-027-1S),     |
| 1E41-F122, Post Accident Sampling System Inboard PCIV, failed closed between |
| approximately 1145 and 1230 on 08/31/00. 1E41-H22 was verified to be open at |
| approximately 1145 following completion of channel A performance test        |
| (section 7.2). After returning from lunch break, operators observed          |
| 1E41-F122 closed and could not be reopened with control switch.              |
|                                                                              |
| The isolation has not been reset and they have also isolated the outboard    |
| valve by TS requirement. Investigation into cause of closure is continuing.  |
|                                                                              |
| During discussions with Nuclear Safety and Compliance Department at 1130 on  |
| 09/01/00 it was determined that this PCIV failing closed was a reportable    |
| ESF actuation.                                                               |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37284       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 09/01/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 18:49[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        09/01/2000|
+------------------------------------------------+EVENT TIME:        14:19[CDT]|
| NRC NOTIFIED BY:  HOPMAN                       |LAST UPDATE DATE:  09/01/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING SYSTEM RECEIVED AN ISOLATION SIGNAL DURING    |
| MAINTENANCE.                                                                 |
|                                                                              |
| Unit 2 was operating at 100% power.  The Reactor Core Isolation Cooling      |
| System was removed from service for scheduled maintenance.  Following valve  |
| packing adjustment, the Reactor Core Isolation Cooling system steam supply   |
| outboard isolation valve was opened per approved procedure.  Approximately   |
| 10 seconds after the Reactor Core Isolation Cooling system steam inboard     |
| isolation bypass valve was throttled open for warming. "Division 2 Reactor   |
| Core isolation Cooling system steam line DP hi" and "Reactor Core Isolation  |
| Cooling system Steam Line/Turbine isolation" alarms were received.  The      |
| Reactor Core Isolation Cooling system steam inboard isolation bypass valve   |
| automatically closed due to an isolation signal.  The Reactor Core Isolation |
| Cooling system remains isolated by the inboard isolation valves.  The cause  |
| of the isolation signal is unknown at this time.  An investigation is in     |
| progress to determine the cause of the isolation and initiate actions to     |
| restore the Reactor Core Isolation Cooling system to an operable and         |
| available status and exit the LCO action statement.                          |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37285       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 09/01/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 21:08[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        09/01/2000|
+------------------------------------------------+EVENT TIME:        19:40[EDT]|
| NRC NOTIFIED BY:  MCDONNELL                    |LAST UPDATE DATE:  09/01/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE PLACING THE PLANT IN A   |
| 14 DAY LCO ACTION STATEMENT.                                                 |
|                                                                              |
| During the performance of 8.5.4.1 (HPCI operability test), HPCI failed to    |
| meet acceptance criteria.  The HPCI pump failed to meet the required flow,   |
| pressure and rpm requirements.  Troubleshooting of the problem is in         |
| progress to make HPCI operable within the 14 day LCO action statement        |
| requirement.                                                                 |
|                                                                              |
| The NRC Resident Inspector was informed.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37286       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 09/03/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 15:49[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        09/03/2000|
+------------------------------------------------+EVENT TIME:        15:10[EDT]|
| NRC NOTIFIED BY:  DAVE OWEN                    |LAST UPDATE DATE:  09/03/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|AAEC                                            |JOSEPH GIITTER       IRO     |
|                                                |CALDWELL             FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - FIRE IN CONTAINMENT                                          |
|                                                                              |
| The licensee declared an unusual event at 1510 because of a fire in          |
| containment that lasted more than 15 minutes.  A fire was reported at 1440   |
| in a tarp that was being used in containment.  The tarp is believed to have  |
| been ignited by some cutting or grinding going on in the vicinity.   The     |
| licensee called for assistance from the local fire department, but they      |
| extinguished the fire before the fire company could assist.  The fire was    |
| reported out at 1509.  The unusual event was terminated at 1615.             |
|                                                                              |
| The reactor is defueled with all fuel having been moved to the spent fuel    |
| pool.  No radioactivity was released.                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37287       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 09/04/2000|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 15:00[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        09/04/2000|
+------------------------------------------------+EVENT TIME:        11:32[CDT]|
| NRC NOTIFIED BY:  JIM GILMORE                  |LAST UPDATE DATE:  09/04/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVE LOVELESS        R4      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |VICTOR DRICKS        PAO     |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP DUE TO FIRE IN UNIT AUXILIARY TRANSFORMER                       |
|                                                                              |
| At about 1132 CDT a fire was reported in the unit auxiliary transformer,     |
| alarms were received in the control room with a unit trip, all rods fully    |
| inserted.  The on-site fire brigade and the off-site fire department were    |
| called to respond.  The fire was extinguished by installed fire suppression  |
| equipment and declared out at 1143 CDT.  The fire is being investigated by   |
| fire protection personnel.  The off-site fire department was released.       |
|                                                                              |
| The plant is stable in Hot Standby at normal temperature and pressure.  Heat |
| removal is via the main condensers with steam generator level being          |
| maintained by auxiliary feedwater.                                           |
|                                                                              |
| The auxiliary feedwater system, both turbine and motor driven, started       |
| automatically on low steam generator level as expected with this event.  All |
| safety equipment performed as designed.                                      |
|                                                                              |
| Concurrent with the reactor trip, the 'C' and 'D' reactor coolant pumps      |
| tripped along with other loads due to one (PA02) of the two non-vital busses |
| not automatically transferring as expected to off-site power.  The bus is    |
| presently energized by off-site power and the 'D' reactor coolant pump was   |
| restarted.  The actual cause of the problem is being investigating.          |
|                                                                              |
| One of the reactor coolant system power operated relief valve opened and     |
| closed one time due the transient of the 'D' reactor coolant pump trip and   |
| subsequent loss of pressurizer spray.                                        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37288       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 09/04/2000|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 15:30[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/04/2000|
+------------------------------------------------+EVENT TIME:        14:16[EDT]|
| NRC NOTIFIED BY:  ANDY DISMUKE                 |LAST UPDATE DATE:  09/04/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT DEENERGIZATION OF THE '2A' RPS MG SET CAUSED GROUP 2 AND 5       |
| ISOLATIONS                                                                   |
|                                                                              |
| Plant personnel inadvertently tripped breaker to the '2A' reactor protection |
| system motor generator (RPS MG) set resulting in de-energization of the '2A' |
| RPS bus.  This resulted in the closure of the inboard Group 2 containment    |
| isolation valves, the inboard Group 5 reactor water cleanup valve, inboard   |
| reactor water sample valve, the control room ventilation swapped to the      |
| pressurization mode of operation, and a half scram in the 'A' RPS channel.   |
| All actuations have been reset and the '2A' RPS bus is energized from the    |
| alternate supply while an investigation is being conducted.                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37289       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 09/05/2000|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 05:42[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/05/2000|
+------------------------------------------------+EVENT TIME:        02:00[EDT]|
| NRC NOTIFIED BY:  R.T.  ELLIOT                 |LAST UPDATE DATE:  09/05/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| "2B" AUXILIARY FEEDWATER PUMP RAN 2 HOURS AND 55 MINUTES BEFORE IT WAS       |
| DISCOVERED THAT IT WAS OPERATING. STEAM GENERATORS WERE ISOLATED FROM THE    |
| AFW SYSTEM.                                                                  |
|                                                                              |
| At 0200 ET the "B" Train of the Solid State Protection System (SSPS) was     |
| deenergized for part of their refueling outage maintenance.  When the SSPS   |
| was deenergized the blocks for the Main Feedwater Pump blocks clear which    |
| gave an automatic start signal to the "2B" AFW pump.   The on shift reactor  |
| operator did not notice that the "2B" AFW pump run light was on until 0455   |
| ET due to refueling outage maintenance activities in Control Room.  "2B" AFW |
| pump recirculated water to the Upper Surge Tank since the Steam Generators   |
| were isolated.  NO damage occurred to the AFW pump.  The licensee is         |
| investigating this event.                                                    |
|                                                                              |
| The NRC Resident Inspector will be notified  of this event.                  |
+------------------------------------------------------------------------------+