Event Notification Report for January 6, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/05/2000 - 01/06/2000
** EVENT NUMBERS **
36503 36562 36563 36564 36565
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36503 |
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| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 12/13/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 11:57[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 12/13/1999|
+------------------------------------------------+EVENT TIME: 11:09[EST]|
| NRC NOTIFIED BY: KEVIN ABELL |LAST UPDATE DATE: 01/05/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| FIRE WRAP DISCOVERED IMPROPERLY INSTALLED AT INTERFACE WITH FIRE SEAL |
| |
| "On December 13, 1999 while operating at 100% power, Harris Nuclear Plant |
| (HNP) discovered fire wrap improperly installed on an individual electrical |
| conduit at the interface between the fire wrap and fire seal. This condition |
| was identified as part of field walkdowns of cable fire wrap installations |
| associated with a recent NRC Fire Protection inspection. Initial |
| investigation has determined that in the event of a fire under certain |
| circumstances HNP could not achieve and maintain a safe shutdown due to a |
| loss of instrumentation used to verify natural circulation. HNP has |
| established a 1 hour roving fire watch in the area as a compensatory measure |
| until this issue is resolved since fire detection and suppression are |
| available in the area. This condition is being reported as a condition |
| outside of the design bases (10CFR50.72.(b)(I)(ii)(B))." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| *** UPDATE ON 1/5/00 @ 1353 BY GILLIAN TO GOULD *** RETRACTION |
| |
| Subsequent investigation has determined that adequate instrumentation would |
| be available to verify natural circulation, assuming a loss of some |
| instrumentation due to the improperly installed fire wrap. Therefore, the |
| plant remained within its design basis and the licensee is retracting this |
| event. Corrective actions for the improperly installed fire wrap is ongoing |
| and the licensee is maintaining the one hour roving fire watch. |
| |
| The NRC Resident was informed. Reg 2 RDO (Decker) was notified. |
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|Power Reactor |Event Number: 36562 |
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| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/05/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 12:34[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/05/2000|
+------------------------------------------------+EVENT TIME: 11:30[CST]|
| NRC NOTIFIED BY: M KIER |LAST UPDATE DATE: 01/05/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE (NOT Y2K RELATED) |
| |
| Clinton Power Station's SPDS was determined to be inoperable at 0400 CST on |
| 01/05/00 due to the loss of computer points utilized in the SPDS for |
| determining Emergency Operating Procedure entry conditions. |
| |
| At 1130 CST on 01/05/00, the licensee determined that the extent of repairs |
| to restore the SPDS function would take longer than 8 hours. Thus, based on |
| the potential unavailability of the SPDS function for longer than 8 hours, |
| this condition is being reported pursuant to 10CFR50.72(b)(1)(v). |
| |
| This problem has no apparent link to transition to Y2K issues. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE AT 1743 ON 01/05/00 FROM HALVERSON TAKEN BY MACKINNON * * * |
| |
| SPDS returned to service at 1605 CST on 01/05/00. R3DO (Madera) notified. |
| |
| The NRC Resident Inspector was notified of this update by the licensee. |
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|Other Nuclear Material |Event Number: 36563 |
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| REP ORG: ADVANCED INPUT DEVICES |NOTIFICATION DATE: 01/05/2000|
|LICENSEE: ADVANCED INPUT DEVICES |NOTIFICATION TIME: 13:47[EST]|
| CITY: COEUR d' ALENE REGION: 4 |EVENT DATE: 01/05/2000|
| COUNTY: STATE: ID |EVENT TIME: 00:00[MST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/05/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES CAIN R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JODY PLUMMER | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| MISSING 10 MILLICURIE POLONIUM-210 STATIC IONIZER ELIMINATOR CARTRIDGE |
| |
| On 03/14/99, Advanced Input Devices Company moved to a new location. A box |
| containing one polonium-210 static ionizer eliminator cartridge was shipped |
| to the new office and the box apparently got lost during the move. The |
| caller discovered that the ionizer eliminator was missing since last week |
| and that the box ended up in a land fill. The model P-2021 series static |
| ionizer eliminator cartridge, made by NDR, Grand Island, NY, contained 10 |
| millicuries of polonium-210. The static ionizer eliminator is used to |
| remove static from the air at their printing company. The caller has |
| already relayed the above information to NRC Region 4 Jeffrey Cruz. |
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|Power Reactor |Event Number: 36564 |
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| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 01/05/2000|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 13:48[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 01/05/2000|
+------------------------------------------------+EVENT TIME: 11:50[CST]|
| NRC NOTIFIED BY: HARRINGTON |LAST UPDATE DATE: 01/05/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |JOHN MADERA R3 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| EMERGENCY SIRENS INOPERABLE. |
| |
| DURING THE MONTHLY TEST OF THE EMERGENCY SIREN NOTIFICATION SYSTEM, THE |
| LICENSEE EXPERIENCED A 59% LOSS OF CAPACITY. THE PROBLEM APPEARS TO BE |
| ASSOCIATED WITH THE INITIATION EQUIPMENT NOT THE REMOTE RECEIVER OR |
| EQUIPMENT. A CALL FOR EQUIPMENT REPAIR HAS BEEN PLACED AND REPAIRS SHOULD |
| BE COMPLETED BY THE END OF THE WORKDAY. A FULL FUNCTION TEST OF A SECONDARY |
| REMOTE LOCATION WAS SATISFACTORY. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED. |
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|Power Reactor |Event Number: 36565 |
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| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 01/05/2000|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 15:30[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/05/2000|
+------------------------------------------------+EVENT TIME: 12:09[CST]|
| NRC NOTIFIED BY: M HAUNER |LAST UPDATE DATE: 01/05/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL DURING RESTORATION OF |
| REACTOR VESSEL WIDE RANGE LEVEL INSTRUMENTATION |
| |
| "During the performance of Surveillance Test Procedure 3.3.3.2-01, Remote |
| Shutdown System Instrument Calibration, an instrument technician was |
| restoring the wide range (flood-up) reactor vessel level instrument which |
| resulted in a level transient for the 'A' and 'B' reactor vessel narrow |
| range level instruments which share a common reference leg. The level |
| transient resulted in a Reactor SCRAM on reactor vessel low level and a |
| Turbine trip on reactor vessel high level. All rods fully inserted into |
| the core. Upon receipt of the low level (170 inches), Group 2 (RHR sump & |
| Drywell drains, etc.), Group 3 (Reactor Building Isolation), and Group 4 |
| (Primary Containment Isolation Signal for Shutdown Cooling) isolations were |
| completed. However, a Reactor Water Cleanup partial isolation was initiated |
| as well. The Reactor Operator as directed by the Shift Supervisor took the |
| isolation to completion. The cause of this partial isolation is still under |
| investigation at this time." |
| |
| "Subsequent to the reactor SCRAM, a Reactor Feed Pump and High Pressure |
| Coolant Injection (HPCI) turbine high level trip occurred (HPCI was not |
| running at this time) and the "A" Reactor Recirculation Pump failed to run |
| back to minimum speed. It was further recognized that a Fuel Pool Cooling |
| pump had tripped but the cause of that trip is still under investigation. |
| Reactor Vessel Level as indicated on the GEMAC Level Indicators was |
| downscale. The plant is at a normal level band with pressure and |
| temperature stable." |
| |
| The high level turbine trip was caused by the Reactor Feed Regulating Valve |
| not going fully closed. |
| |
| No Safety Relief Valves opened and the offsite electrical grid is stable. |
| |
| All Emergency Core Cooling Systems and the Emergency Diesel Generators are |
| fully operable if needed. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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