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Event Notification Report for November 14, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/13/2002 - 11/14/2002

                              ** EVENT NUMBERS **

39300  39352  39356  39367  39368  39369  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39300       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 10/17/2002|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 18:55[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/17/2002|
+------------------------------------------------+EVENT TIME:        14:30[CDT]|
| NRC NOTIFIED BY:  BRIAN HUPKE                  |LAST UPDATE DATE:  11/13/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       94       Power Operation  |94       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI INOPERABLE DUE TO LOW INTERNAL BATTERY RESISTANCE                       |
|                                                                              |
| The licensee reported that during a 250 Vdc battery surveillance the         |
| internal resistance of cell #18 was greater than the technical specification |
| (TS) limit.  As a result, the licensee declared battery bank 1D4 inoperable  |
| which also rendered inoperable the HPCI system and any containment isolation |
| valves powered from the battery bank.  This included 5 total CIVs            |
| [Containment isolation valves] from the following systems: HPCI, RWCU and    |
| MSL drain and Torus drain valves.  Corrective maintenance was performed on   |
| the battery cell and the internal resistance passed the TS limit.  HPCI and  |
| CIVs were returned to an operable status approximately 3 hours after being   |
| declared inoperable.  At the time of this event, the RCIC system was         |
| inoperable for planned maintenance so the LCO entered for HPCI was more      |
| restrictive allowing 12 hours rather than the normal 14 day LCO for HPCI.    |
|                                                                              |
| *** THIS EVENT WAS RETRACTED AT 1357 ON 11/13/2002 BY CLARE BLEAU TO ERIC    |
| THOMAS ***                                                                   |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "On 10/17/02 Event Notification #39300 was completed pursuant to 10 CFR      |
| 50.72 (b)(3)(v)(D) due to the 250 Volt Station Battery 1D4 being declared    |
| inoperable which caused the High Pressure Coolant Injection (HPCI) system to |
| also be inoperable. At the time that this occurred, the Reactor Core         |
| Isolation Cooling (RCIC) system was also inoperable due to preplanned        |
| maintenance. This required that a 12 hour to hot shutdown and 36 hour to     |
| cold shutdown LCO be entered per Technical Specification 3.5.1.J.            |
| Maintenance was performed on battery 1D4 and it was returned to operability. |
| The other related LCOs were also exited prior to plant shutdown.             |
|                                                                              |
| "An operability evaluation was subsequently completed which determined that  |
| 1D4 could have performed its design function with the data taken from STP    |
| 3.8.4-05. C&D Technologies has confirmed this. Only one of the two           |
| connections needs to be below 50 micro ohms to meet TS 3.8.4.5.              |
|                                                                              |
| "If all of the discharge current were to pass through the 129 micro ohm      |
| connection, the voltage drop would be 0.06 volts. This has no bearing on the |
| design function of the 250 VDC system. 1D4 currently has a design margin of  |
| 1.65 (65% excess battery capacity). Therefore, battery 1D4 actually was      |
| operable and capable of performing its required safety function. The PCIV    |
| [Primary Containment Isolation Valve] LCO 3.6.1.3 was also entered for       |
| 250VDC MOVs that are PCIVs. This included the HPCI outboard steam supply     |
| valve MO-2239 and the HPCI feedwater injection isolation valve MO-2312.      |
| Review of the shift logs and discussion with the shift manager confirmed     |
| that these valves were not closed so that HPCI remained available during     |
| this event. No LER is required under 10 CFR 50.73 (a)(2)(v)(D) and the       |
| 8-hour Non-emergency notification under 10 CFR 50.72 (b)(3)(v)(D) (EN#39300) |
| can be retracted."                                                           |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
|                                                                              |
| Notified Bruce Burgess, R3DO.                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39352       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 11/07/2002|
|LICENSEE:  HARRINGTON GEOTECHNICAL ENGINEERING  |NOTIFICATION TIME: 12:50[EST]|
|    CITY:  ORANGE                   REGION:  4  |EVENT DATE:        10/06/2002|
|  COUNTY:  ORANGE                    STATE:  CA |EVENT TIME:        04:30[PST]|
|LICENSE#:  CA 5657               AGREEMENT:  Y  |LAST UPDATE DATE:  11/13/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT GREGER                |                             |
|  HQ OPS OFFICER:  MIKE RIPLEY                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING STOLEN MOISTURE DENSITY GAUGE               |
|                                                                              |
| The licensee reported at 1115 PST on 7/6/02 that a CPN Model MC3 moisture    |
| density gauge was stolen from the back of the licensee's pickup truck on     |
| 7/06/02 sometime between 0430 and 0530 PST in the city of Orange, CA .  The  |
| gauge serial number is not currently available.  Gauge contains nominally 10 |
| millicuries Cs-137 and 30 millicuries Am-241/Be.  The gauge was chained and  |
| locked in the back of the pickup and the chain was found cut.  Local law     |
| enforcement responded.  The licensee plans on issuing a press release and a  |
| reward for the return of the gauge.                                          |
|                                                                              |
| ****UPDATE ON 11/13/02 AT 14:100 FROM LAURA****                              |
|                                                                              |
| The above text listed the incorrect date for the event.  The event occurred  |
| on 11/6/02 and NOT 7/6/02.                                                   |
|                                                                              |
| Notified DIRO (McGinty) and R4DO (Cain).                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39356       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLORIDA BUREAU OF RADIATION CONTROL  |NOTIFICATION DATE: 11/08/2002|
|LICENSEE:  LITTON SYSTEMS, INC.                 |NOTIFICATION TIME: 09:41[EST]|
|    CITY:  Apopka                   REGION:  2  |EVENT DATE:        11/07/2002|
|  COUNTY:                            STATE:  FL |EVENT TIME:             [EST]|
|LICENSE#:  2159-1                AGREEMENT:  Y  |LAST UPDATE DATE:  11/08/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES R. OGLE      R2      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JERRY EAKINS                 |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - LOST OR STOLEN AM-241 SOURCE                        |
|                                                                              |
| "Licensee reported at 1530 [EST] that source could not be found during       |
| current inventory. Last inventory was performed on 14 February. Licensee is  |
| conducting an investigation."                                                |
|                                                                              |
| The lost or stolen material is a sealed 4 microcurie Am - 241 source used    |
| for military sighting application.                                           |
|                                                                              |
| The State of Florida Bureau of Radiation Control radiological incident       |
| number is FL02-172.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39367       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 11/13/2002|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 04:53[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/13/2002|
+------------------------------------------------+EVENT TIME:        04:07[EST]|
| NRC NOTIFIED BY:  J.C. WILLIAMS                |LAST UPDATE DATE:  11/13/2002|
|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LEONARD WERT         R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       21       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP FROM 21% POWER                                           |
|                                                                              |
| "Unit Two Reactor was at 21% power and Main Turbine roll up was in progress  |
| to synch to [the] grid after 2R9 refueling outage.  Main feedwater was in    |
| service to all 4 steam generators.  Steam generator #3 water level increased |
| to the Hi-Hi P-14 setpoint which tripped the main turbine and main           |
| feedwater.  AFW [auxiliary feedwater] actuated as required.  The reactor was |
| manually tripped.  All rods fully inserted.  The cause of the transient is   |
| being evaluated at this time.  The reactor is stable in Mode 3 [Hot          |
| Standby]."                                                                   |
|                                                                              |
| Highest steam generator level attained was 88%.                              |
|                                                                              |
| Licensee notified the NRC Resident Inspector.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39368       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 11/13/2002|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 10:13[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        11/13/2002|
+------------------------------------------------+EVENT TIME:        04:58[CST]|
| NRC NOTIFIED BY:  D. CLARK                     |LAST UPDATE DATE:  11/13/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 EMERGENCY DIESEL GENERATOR AUTOSTARTED AND LOADED TO DIVISION 2 BUS.  |
|                                                                              |
| "At 0458 CST on 11/13/02, an undervoltage was detected on  4 KV ESS Div 2    |
| Bus 14-1.  The normal  feed breaker to the bus auto tripped, the U-1         |
| Emergency Diesel Generator auto started, and loaded to the bus.  The         |
| preliminary investigation determined that work was being performed in a      |
| breaker cubicle adjacent to the bus auxiliary cubicle.  Vibration from the   |
| work may have caused the bus potential fuse drawer to fall open, actuating   |
| the bus undervoltage relay.  Normal power to the bus was restored at 0538    |
| hours.  A prompt investigation is in progress."                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39369       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 11/14/2002|
|    UNIT:  [] [] [3]                 STATE:  SC |NOTIFICATION TIME: 05:24[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        11/14/2002|
+------------------------------------------------+EVENT TIME:        04:19[EST]|
| NRC NOTIFIED BY:  NEIL CONSTANCE               |LAST UPDATE DATE:  11/14/2002|
|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LEONARD WERT         R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     A/R        Y       100      Power Operation  |0        Hot Standby      |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP                                   |
|                                                                              |
| "The Moisture Separator drain tanks each provide a trip signal to the main   |
| turbine on a high level on 2 [of] 3 level switches.  At 0419 [EST], 2 [of] 3 |
| level switches indicated a high level in the 3A Moisture Separator Drain     |
| Tank Level, resulting in a MT [Main Turbine] trip and anticipatory RPS trip. |
| Post-trip response was normal."                                              |
|                                                                              |
| All rods inserted into the core.  No PORV's lifted. No ECCS actuation. The   |
| cause of the heater drain system upset is under investigation.               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+