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Event Notification Report for March 16, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/15/2000 - 03/16/2000

                              ** EVENT NUMBERS **

36768  36796  36797  36798  36799  36800  36801  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36768       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/08/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 07:27[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/08/2000|
+------------------------------------------------+EVENT TIME:        03:30[EST]|
| NRC NOTIFIED BY:  PAUL UNDERWOOD               |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |EDWARD MCALPINE      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                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION - CONTROL ROOM VENTILATION SYSTEM                              |
|                                                                              |
| Moving the Unit 2 dryer during refueling operations set off an area          |
| radiation alarm.  The alarm caused the control room ventilation system to    |
| shift into pressurization mode.   The radiation alarm cleared as the dryer   |
| was placed in its storage location.  The trip has been reset and the control |
| room ventilation has been returned to its normal lineup.                     |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
|                                                                              |
| * * *  UPDATE ON 3/15/00 @ 1625 BY URQUHART TO GOULD * * *   RETRACTION      |
|                                                                              |
| Upon further investigation the licensee has determined that the control room |
| ventilation shifted to the pressurization mode as a result of an invalid     |
| signal.  Since the originating signal is not identified as an ESF, no        |
| notification is required, therefore the licensee is retracting this event.   |
|                                                                              |
| The NRC Resident Inspector will be notified. Reg 2 RDO (Belisle) was         |
| notified.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36796       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/15/2000|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 00:58[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/14/2000|
+------------------------------------------------+EVENT TIME:        22:45[EST]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - ESF ACTUATIONS DURING A RELAY REPLACEMENT CAUSED BY AN ELECTRICAL SHORT  - |
|                                                                              |
|                                                                              |
| While replacing the relay for TIP withdrawal & RHR valve #2A71B-K5C in       |
| Reactor Protection System relay panel #2H11-P609, an electrician caused an   |
| electrical short which resulted in the following:                            |
|                                                                              |
| - Units 1 & 2 Standby Gas Treatment System actuation (1A, 1B, 2A and 2B      |
| trains/fans started)                                                         |
| - Units 1 & 2 Outboard [B] Reactor Building Ventilation System isolation     |
| - Units 1 & 2 Outboard [B] Refueling Floor Ventilation System isolation      |
| - Discovered Group 2 Outboard Post Accident Sampling Isolation Valve         |
| #2E41-F121 closed                                                            |
| - Discovered Group 2 Outboard Fission Product Monitor Valve #2D11-F072       |
| closed                                                                       |
|                                                                              |
| The licensee is investigating the cause of this event.                       |
|                                                                              |
| The licensee plans to return the above systems and components to normal      |
| status as soon as possible.                                                  |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| Refer to related event #36795.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36797       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 03/15/2000|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 14:15[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        03/15/2000|
+------------------------------------------------+EVENT TIME:        10:36[EST]|
| NRC NOTIFIED BY:  GILES                        |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT ENTERED A 72 HOUR LCO ACTION STATEMENT DUE TO AN INOPERABLE HIGH   |
| PRESSURE COOLANT INJECTION SYSTEM.                                           |
|                                                                              |
| On 3/15/2000 at 1036 hours, the High Pressure Coolant Injection System       |
| (HPCI) Reactor Vessel Water Level 8 turbine trip was inadvertently received  |
| while performing surveillance 44.030.254, ECCS - Reactor Vessel Water Level  |
| (Levels 1, 2, and 8) Division 2 Channel D Functional Test.  The ability for  |
| HPCI to add water to the reactor vessel at Level 2 may have been inhibited   |
| with the Level 8 HPCI turbine trip initiated.  This may have made the HPCI   |
| system inoperable. The cause of the problem is currently under               |
| investigation.                                                               |
|                                                                              |
| The Level 8 HPCI turbine trip was reset at 1112 hours. Technical             |
| Specifications 3.5.1.E, emergency core cooling systems, and 3.3.5.1.C,       |
| emergency core cooling system instrumentation, were entered.                 |
|                                                                              |
| The plant has 72 hours to return HPCI to operable condition or be in hot     |
| shutdown within the following 12 hrs.                                        |
|                                                                              |
| This report is being made in accordance with 10 CFR 50.72 (b)(2)( iii)( D),  |
| any event or condition that alone could have prevented the fulfillment of    |
| the safety function of structures or systems necessary to mitigate the       |
| consequences of an accident.                                                 |
|                                                                              |
| The NRC Resident Inspector will be informed.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36798       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 03/15/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 15:55[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/27/1999|
+------------------------------------------------+EVENT TIME:        19:52[CST]|
| NRC NOTIFIED BY:  WILLIAMSON                   |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID GRAVES         R4      |
|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 ACTUATION OF THEIR STANDBY GAS TREATMENT AND ANNULUS MIXING        |
| SYSTEMS                                                                      |
|                                                                              |
| On December 27, 1999, at 1925 (CST), an unplanned automatic actuation of the |
| standby gas treatment and annulus mixing systems occurred.  The initiating   |
| signal originated in radiation monitor 11B, which monitors the reactor       |
| building annulus for gaseous activity.  Grab samples of the annulus          |
| atmosphere were taken, and were found to be normal. The 11A radiation        |
| monitor in the same process stream likewise indicated no presence of         |
| radioactivity.  The filter cartridge in the 11B radiation monitor was        |
| changed, and its indication returned to normal. The standby gas treatment    |
| and annulus mixing systems were returned to their normal lineup.             |
|                                                                              |
| This event is being reported in accordance with 10CFR50.72(b)(2)(ii) as an   |
| event that resulted in the automatic actuation of an engineered safety       |
| feature.                                                                     |
|                                                                              |
| An investigation of the event found that the filter cartridge in the 11B     |
| radiation monitor was incorrectly installed, such that particulate matter    |
| could reach the sample chamber.  The monitor is designed to detect gaseous   |
| radioactivity, and the purpose of the filter assembly is to keep particulate |
| matter out of the sample chamber. There is a charcoal cartridge in the       |
| upstream of the filter to remove iodine. The detector in the sample chamber  |
| was determined to be responding correctly, and it is postulated that a       |
| transient particle from the charcoal cartridge bypassed the filter element,  |
| and was detected in the sample chamber.                                      |
|                                                                              |
| The event was not reported within the timeframe required by 10CFR50.72,      |
| because there was no corroborating evidence that radioactivity sufficient to |
| actuate the ventilation process monitors was present in the annulus.         |
| Subsequent discussion with the NRC has determined that this event was        |
| reportable on 3/15/00 @ 1450 CST.                                            |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36799       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 03/15/2000|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 16:58[EST]|
|   RXTYPE: [3] CE                               |EVENT DATE:        03/15/2000|
+------------------------------------------------+EVENT TIME:        15:11[CST]|
| NRC NOTIFIED BY:  MCKINNEY                     |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID GRAVES         R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFEGUARD SYSTEM VULNERABILITY DUE INABILITY TO RESPOND TO PERIMETER ALARMS  |
| AROUND THE PROTECTED AREA BECAUSE OF ADVERSE WEATHER CONDITIONS.             |
|                                                                              |
| IMMEDIATE COMPENSATORY MEASURES NOT TAKEN UPON DISCOVERY; HOWEVER, THEY ARE  |
| NOW FULLY IMPLEMENTED.                                                       |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED.                                 |
|                                                                              |
| CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36800       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 03/15/2000|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 17:03[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        03/15/2000|
+------------------------------------------------+EVENT TIME:        15:32[EST]|
| NRC NOTIFIED BY:  CRAINE                       |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO THE MICHIGAN DEPARTMENT OF ENVIRONMENTAL        |
| QUALITY(MDEQ)                                                                |
|                                                                              |
| Cooling tower water was identified to be leaking from the south cooling      |
| tower to the ground.  The water accumulated and ran over land to the         |
| overflow canal which lead to the Swan Creek.  Samples were obtained to       |
| determine if chlorine could be detected in the water flowing to the overflow |
| canal.  Communication was made with Corporate Environmental and it was       |
| determined that this event is reportable to the State of Michigan.  The      |
| spill reaching the surface water was discovered at 1150 on 03/15/00.         |
| Temporary earthen dikes have been installed to stop flow to the overflow     |
| canal.  Initial studies indicated that no detectable chlorine reached the    |
| surface water.                                                               |
|                                                                              |
| Follow-up samples will be obtained from the overflow canal and near the      |
| point where the overflow canal meet Swan Creek.  A temporary deflector is    |
| being installed to route the water back into the tower instead of allowing   |
| it to flow to the ground.  A permanent fix will be installed in April 2000   |
| during the refueling outage.                                                 |
|                                                                              |
| The State MDEQ was contacted at 1532.                                        |
|                                                                              |
| The NRC Resident Inspector was informed.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36801       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 03/15/2000|
|    UNIT:  [1] [] []                 STATE:  AL |NOTIFICATION TIME: 22:38[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/15/2000|
+------------------------------------------------+EVENT TIME:        21:15[CST]|
| NRC NOTIFIED BY:  MURPHY                       |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT HAD ESF ACTUATION DUE TO A HIGH RADIATION ALARM                        |
|                                                                              |
| While performing fuel sipping in the unit 1 spent fuel pool, rad monitors    |
| R25A and R25B upscaled with R25B going into high alarm.  The alarm activated |
| both trains of the penetration room filtration system and secured the  spent |
| fuel pool ventilation system.  The alarm was valid due to a leaking fuel     |
| assembly that was discovered during the fuel sipping activity.  There was no |
| indication of any radiation release, fuel sipping operations were suspended  |
| and evacuation of the spent fuel pool was initiated.  They have not yet      |
| secured all of the actuations.                                               |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+