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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+
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