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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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