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Event Notification Report for February 3, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/02/2000 - 02/03/2000

                              ** EVENT NUMBERS **

36586  36638  36643  36653  36654  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36586       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [1] [2] []                STATE:  SC |NOTIFICATION TIME: 04:21[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/13/2000|
+------------------------------------------------+EVENT TIME:        03:26[EST]|
| NRC NOTIFIED BY:  JIM BURGESS                  |LAST UPDATE DATE:  02/02/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR 17 MINUTES DUE TO LOW DIFFERENTIAL |
| PRESSURE BETWEEN THE CONTROL ROOM AND THE AUXILIARY BUILDING.                |
|                                                                              |
| A LOW CONTROL ROOM VENTILATION SYSTEM DIFFERENTIAL PRESSURE WAS DISCOVERED   |
| WHILE A CONTROL ROOM VENTILATION SYSTEM AND AUXILIARY BUILDING VENTILATION   |
| SYSTEM COMPENSATORY ACTION WAS IN EFFECT DUE TO AUXILIARY BUILDING           |
| VENTILATION SYSTEM WORK.  THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 |
| AT 0326 ET.  AT 0333 ET, THE LICENSEE SECURED THE '2A' AUXILIARY BUILDING    |
| VENTILATION FILTER EXHAUST FAN.  TECHNICAL SPECIFICATION 3.0.3 WAS EXITED AT |
| 0343 ET AFTER CONTROL ROOM DIFFERENTIAL PRESSURE WAS VERIFIED ABOVE THE      |
| MINIMUM LIMIT.                                                               |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.   |
|                                                                              |
| * * *  UPDATE ON 02/02/00 AT 1644 BY TRUESDALE TO GOULD  * * *  RETRACTION   |
|                                                                              |
| The determination to declare both trains of the control room area            |
| ventilation system (CRAVS) inoperable on 01/13/00 was based on the data from |
| only one of the two CRAVS intakes.  At the time this decision was made,  the |
| 'A' train of the CRAVS was in operation.  When the control room pressure was |
| checked, the only intake alignment that was tested was the Unit 2 intake     |
| alignment.  No test was performed using the Unit 1 intake for CRAVS.  This   |
| was done because of how the procedure was written for the control pressure   |
| check.                                                                       |
|                                                                              |
| A licensee engineering evaluation was performed to review CRAVS test data    |
| and alignment before, during and after the event.  This evaluation           |
| determined that the inability to pressurize the control room to technical    |
| specification (TS) surveillance requirement required value of 0.125 inches   |
| water gage using the Unit 2 intake caused one CRAVS train (but not both) to  |
| be inoperable.  The cause of the event was a failed auxiliary building       |
| ventilation system supply damper.  This supply damper prevented the          |
| auxiliary building system from supplying adequate air into the auxiliary     |
| building to compensate for the amount of air being exhausted by the          |
| auxiliary building system unfiltered and filtered exhaust fans.  TS 3.7.10,  |
| Action A (restore CRAVS train to OPERABLE status within 7 days), not action  |
| E (enter TS 3.0.3 for two CRAVS trains inoperable), should have been         |
| followed.  The inoperable train was restored to operable status by           |
| realigning auxiliary building exhaust and supply fans which restored         |
| auxiliary building pressure to normal.  Thus, since only one train of CRAVS  |
| was inoperable, neither unit was ever in TS LCO 3.0.3 for this event.        |
| Therefore, this event is not reportable per 10CFR50.72(b)(l)(ii)(B) and the  |
| previous notification is being retracted.  In addition, as a result of this  |
| event notification retraction, licensee event reporting regarding this issue |
| is not required nor is planned.                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R2DO (Kerry Landis).                                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36638       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 01/28/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 05:14[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        01/28/2000|
+------------------------------------------------+EVENT TIME:        02:40[CST]|
| NRC NOTIFIED BY:  DARYL CLARK                  |LAST UPDATE DATE:  02/02/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MONTE PHILLIPS       R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS INOPERABLE DURING CORE ALTERATIONS.         |
|                                                                              |
| "On 1/28/00 at 0005 hrs, the U-2 Emergency Diesel Generator was found to be  |
| inoperable due to the diesel generator room vent fan selector switch being   |
| selected to the alternate feed.  The 1/2 Emergency Diesel Generator was      |
| inoperable due to Division I electrical system refuel outage work. Core      |
| alterations were in progress.                                                |
|                                                                              |
| "Per Tech Spec 3.9.B, one diesel generator must be operable in Mode 5 and    |
| when handling irradiated fuel in the secondary containment.                  |
|                                                                              |
| "The switch was aligned to the normal position, and vent fan operation was   |
| verified within approximately 15 minutes to restore the U-2 diesel generator |
| to an operable status.  An internal investigation is commencing. Although    |
| both the 1/2 and U-2 EDGs were inoperable, both diesels remained available   |
| for operation.                                                               |
|                                                                              |
| "This event is being reported as required by 10CFR50.72(b)(2)(iii)(D), an    |
| event which alone could have prevented the fulfillment of a safety function  |
| needed to mitigate the consequences of an accident."                         |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| * * *  UPDATE ON 02/02/00 AT 1841 FROM HILL TO GOULD  * * *  RETRACTION      |
|                                                                              |
| The licensee has completed its evaluation and determined that the Unit 2     |
| Emergency Diesel Generator was able to meet its intended safety function     |
| considering reasonable operator actions.  Therefore, this event is not       |
| reportable with respect to 10CFR 50.72(b)(2)(iii)(D) and is hereby           |
| retracted.                                                                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified R3DO (Tony Vegel).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36643       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  DEPARTMENT OF THE NAVY               |NOTIFICATION DATE: 01/31/2000|
|LICENSEE:  DEPARTMENT OF THE NAVY               |NOTIFICATION TIME: 12:34[EST]|
|    CITY:  CHERRY POINT             REGION:  2  |EVENT DATE:        01/20/2000|
|  COUNTY:                            STATE:  NC |EVENT TIME:             [EST]|
|LICENSE#:  45TAC23645TAC         AGREEMENT:  Y  |LAST UPDATE DATE:  02/02/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CAUDLE JULIAN        R2      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  HIGGINS                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| U.S. NAVY REPORTED MISSING DROGUE LIGHTS AT THE MARINE CORP AIR STATION IN   |
| CHERRY POINT, N.C.                                                           |
|                                                                              |
| A DROGUE LIGHT (USED DURING NIGHT AIRCRAFT REFUELING) IS A BASKET ASSEMBLY   |
| CONTAINING 6 ISOLITES WHICH CONTAIN 1 CURIE OF TRITIUM EACH FOR A TOTAL OF 6 |
| CURIES.  THERE WAS A SECOND BASKET ASSEMBLY CONTAINING 5 ISOLITES WHICH ALSO |
| CONTAINED 1 CURIE EACH OF TRITIUM AND A 6th ISOLITE WHICH CONTAINED 25       |
| MILLICURIES OF KRYPTON-85.  THEREFORE, THERE IS A TOTAL ACTIVITY OF 11       |
| CURIES OF TRITIUM AND 25 MILLICURIES OF KRYPTON-85 MISSING.  THEY HAVE BEEN  |
| SEARCHING FOR THESE SOURCES SINCE 01/20/00 WITH NO SUCCESS.  ON 01/28/00, IT |
| WAS DETERMINED THAT THIS WAS A REPORTABLE EVENT.  THEY BELIEVE, HOWEVER,     |
| THAT THESE SOURCES WERE NOT STOLEN OR LOST BUT WERE RETURNED TO THE NAVY     |
| SUPPLY SYSTEM AFTER THEY HAD BEEN REMOVED ON 12/14/99. THEY ARE HAVING A     |
| NAVY JAG INVESTIGATION ON THIS INCIDENT.                                     |
|                                                                              |
| CALL THE NRC OPERATIONS OFFICER FOR A LICENSEE CONTACT TELEPHONE NUMBER.     |
|                                                                              |
| *  *  * UPDATE AT 1033 ON 02/02/00 FROM HIGGINS TAKEN BY STRANSKY  *  *  *   |
|                                                                              |
| The licensee has recovered the sources. The lights had been mistaken for     |
| surplus material, and had been installed on another aircraft.                |
|                                                                              |
| The licensee has already contacted NRC Region 2 regarding this update.  The  |
| NRC Operations Officer notified the R2DO (Kerry Landis).                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36653       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 02/02/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 14:51[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        02/02/2000|
+------------------------------------------------+EVENT TIME:        11:34[PST]|
| NRC NOTIFIED BY:  HEDGES                       |LAST UPDATE DATE:  02/02/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLAUDE JOHNSON       R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE DISCOVERED A CONDITION THAT IS OUTSIDE THE PLANT DESIGN BASIS       |
|                                                                              |
| At 1134 PST on 02/02/00, after discussions with General Electric Company     |
| representatives, the licensee determined that the condition described below  |
| was not known to be previously analyzed and was outside the design basis of  |
| the plant and was reportable to the NRC..  The plant remains in Condition 1  |
| at 100% power with the condition yielding primary containment and reactor    |
| coolant pressure boundary OPERABLE but nonconforming in accordance with NRC  |
| Generic Letter 91-18, Revision 1.                                            |
|                                                                              |
| The WNP-2 UFSAR Section 7.4.1.1.2 and TMI response ll.K.1.22 state that the  |
| Reactor Core Isolation Cooling (RCIC) System is designed to automatically    |
| start if reactor water level decreases to the low level signal setpoint      |
| (level 2), automatically stop at the high water level signal setpoint (level |
| 8), and restart if water level decreases again to low level signal setpoint  |
| (level 2).  The RCIC System is equipped with a "Keep-Fill" pump designed to  |
| maintain the RCIC System full.  However, the RCIC Keep-Fill pump is not      |
| single failure proof.  Therefore, during accident or transient scenarios     |
| which include a sufficient decrease in reactor vessel water level, restart   |
| of the RCIC System in conjunction with a failure of the Keep-Fill pump,      |
| could create a water hammer in the RCIC System piping and potentially        |
| jeopardize the integrity of the reactor coolant pressure boundary (RCPB) or  |
| primary containment (PC) isolation barriers associated with the RCIC         |
| System.                                                                      |
|                                                                              |
| An operability assessment has determined that the RCPB and PC are OPERABLE   |
| but nonconforming to single failure criteria, crediting existing             |
| proceduralized operator actions.  The RCIC System is equipped with low       |
| pressure alarm annunciation in the main control room.  To prevent water      |
| hammer, plant procedures require operator action to inhibit RCIC pump starts |
| (except as directed by emergency operating procedures) upon receipt of this  |
| low pressure alarm.                                                          |
|                                                                              |
| WNP-2 is continuing to evaluate the significance of this postulated scenario |
| through engineering analysis.                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36654       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 02/02/2000|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 23:50[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/02/2000|
+------------------------------------------------+EVENT TIME:        23:00[EST]|
| NRC NOTIFIED BY:  MARK SCHWIKER                |LAST UPDATE DATE:  02/02/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TONY DIMITRIADIS     R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - LONG TERM ADS BACKUP NITROGEN SUPPLY HEADER MANUAL BLOCK VALVES FOUND      |
| CLOSED -                                                                     |
|                                                                              |
| At 2105 on 02/02/00, a plant  operator found one manual block valve to each  |
| Long Term Automatic Depressurization System (ADS) backup nitrogen supply     |
| header isolated.  This would have prevented Unit 2's ability to establish    |
| long term alternate decay heat removal capability in accordance with the     |
| plant design basis.  Tech Spec 3.5.1.d requires Unit 2 to be placed in hot   |
| shutdown condition within 12 hours with these valves closed.                 |
|                                                                              |
| At 2125 on 02/02/00, plant operators opened both ADS manual block valves     |
| reestablishing long term backup nitrogen supply to the ADS valves and exited |
| Tech Spec 3.5.1.d.                                                           |
|                                                                              |
| Normal ADS nitrogen supply header pressure was present with these valves in  |
| the closed position.                                                         |
|                                                                              |
| The licensee is investigating the cause of these valves being in the closed  |
| position.                                                                    |
|                                                                              |
| At 2300 on 02/02/00, the licensee determined that this event was reportable  |
| to the NRC.                                                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+