United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2002

Event Notification Report for October 18, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/17/2002 - 10/18/2002

                              ** EVENT NUMBERS **

39276  39284  39285  39289  39290  39295  39296  39297  39298  39299  39300  39301  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39276       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 10/12/2002|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 08:02[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/12/2002|
+------------------------------------------------+EVENT TIME:        01:30[PDT]|
| NRC NOTIFIED BY:  J. BROWN                     |LAST UPDATE DATE:  10/17/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KRISS KENNEDY        R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71(b)(1)         SAFEGUARDS REPORTS     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       54       Power Operation  |54       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ALLEGED FITNESS-FOR-DUTY QUESTIONED DUE TO SLEEPING ON WATCH.                |
|                                                                              |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY.                        |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR .                           |
|                                                                              |
| ***** RETRACTED ON 10/17/02 AT 22:10 FROM J. BROWN TO A. COSTA *****         |
|                                                                              |
| The licensee is retracting this event since proper security was maintained   |
| in the Owner Controlled Area as required by the Order.                       |
|                                                                              |
| Notified R4DO (Pick) via email.                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39284       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  LOUISIANA RADIATION PROTECTION DIV   |NOTIFICATION DATE: 10/14/2002|
|LICENSEE:  SCHLUMBERGER TECHNOLOGY CORP         |NOTIFICATION TIME: 16:27[EDT]|
|    CITY:  CAMERON                  REGION:  4  |EVENT DATE:        10/12/2002|
|  COUNTY:                            STATE:  LA |EVENT TIME:             [CDT]|
|LICENSE#:  LA-2783-L01           AGREEMENT:  Y  |LAST UPDATE DATE:  10/14/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KRISS KENNEDY        R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SCOTT BLACKWELL (email)      |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE - IRRETRIEVABLE WELL LOGGING SOURCE                          |
|                                                                              |
| "Agreement State Agency: Louisiana Department of Environmental Quality       |
|                                                                              |
| "Event Report ID No.: LA020013                                               |
|                                                                              |
| "License No.: LA-2783-L01                                                    |
|                                                                              |
| "Licensee: Schlumberger Technology Corp                                      |
|                                                                              |
| "Event date and Time: October 12, 2002                                       |
|                                                                              |
| "Event Location: Miami Corp #1S in Cameron, LA                               |
|                                                                              |
| "Event type: Irretrievable Well Logging Source                               |
|                                                                              |
| "Notifications: Schlumberger notified the Louisiana Department of Natural    |
| Resources and the Louisiana Department of Environmental Quality.             |
|                                                                              |
| "Event description:                                                          |
|                                                                              |
| On October 9, 2002, a well logging tool was stuck down hole. The tool        |
| contained a 1.7 Ci source of Cs-137 model number GSRZ with s/n 2009 and a 16 |
| Ci source of Am241Be model number NSR-L with s/n 3068. There were repeated   |
| attempts to retrieve the tool. On October 12, 2002, it was decided to        |
| abandon the tool. Approval was given from the state of Louisiana on October  |
| 12, 2002, to abandon the tool. The approximate depth of the tool is 10,822   |
| feet.  A cement plug was going to be placed above the tool, cement is going  |
| to be added around the tool, and an upside down drill bit is to be used as a |
| deflection device."                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39285       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 10/15/2002|
|LICENSEE:  BAYLOR ALL SAINTS MED CENTER, MEDI-PH|NOTIFICATION TIME: 11:35[EDT]|
|    CITY:  FORT WORTH, DALLAS       REGION:  4  |EVENT DATE:        09/25/2002|
|  COUNTY:                            STATE:  TX |EVENT TIME:        11:30[CDT]|
|LICENSE#:  L2212, L05529         AGREEMENT:  Y  |LAST UPDATE DATE:  10/15/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GREG PICK            R4      |
|                                                |WAYNE HODGES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS                |                             |
|  HQ OPS OFFICER:  MIKE RIPLEY                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PERSONNEL CONTAMINATION AND EXCESSIVE PACKAGE LEVELS AT NUCLEAR MEDICINE     |
| FACILITIES                                                                   |
|                                                                              |
| "A 300 millicurie multidose glass vial of technetium-99m was dropped on the  |
| floor at about 11:30 am [September 25, 2002] in a hot lab area at Baylor by  |
| a nuclear medicine technologist. About 40% of the vial contents spilled on   |
| the tech's pants, legs, and shoes. The initial radiation reading on the      |
| tech's clothing was 35.2 [millirem]/hr. An initial wipe test of the floor    |
| gave a reading of 81,012 dpm. The floor was decontaminated using radiowash   |
| until radiation wipe levels were at 366 dpm and the survey meter detected    |
| 1.8 [millirem]/hr. The tech's clothing were placed in storage for decay.     |
|                                                                              |
| "An outgoing nuclear medicine ammo box was about three feet from the spill.  |
| The box was labeled and had been surveyed and was ready for pickup by the    |
| nuclear pharmacy, Medi-Physics. The technologist did not believe the spill   |
| had contaminated the ammo box and did not perform an additional survey of    |
| it. The ammo box was picked up by a courier for the nuclear pharmacy. The    |
| courier picked up the ammo box by using the keypad lock to access the        |
| unoccupied hot lab as was his normal routine.                                |
|                                                                              |
| "At around 1:00pm, as the courier was leaving the Medi-Physics facility, he  |
| surveyed his hands and noticed radiation readings. Both palms were           |
| contaminated and so was his shirt and pants. The hands gave readings of 8340 |
| cpm's. The courier was decontaminated to approximate background levels. The  |
| only package picked up and transported by the courier was the ammo box from  |
| Baylor. The nuclear pharmacy contacted Baylor and notified the State.        |
|                                                                              |
| "The ammo box radiation readings were 2,664,800 cpm's and the main area of   |
| contamination read 150 [millirem]/hr. The courier vehicle showed             |
| contamination on the door handle, radio knob, steering wheel, and gear       |
| shift.  Radiation readings were in the range of 81,649 cpm's. The ammo box   |
| was placed in storage for decay. The vehicle was quarantined, decontaminated |
| to background revels, and returned to service the following day.             |
|                                                                              |
| "Additional information will be provided to the Agency in the Licensee's     |
| written report. An onsite investigation by the Texas Department of Health    |
| Bureau of Radiation Control identified items of noncompliance with Agency    |
| regulations."                                                                |
|                                                                              |
| Texas Incident No.  I-7938                                                   |
|                                                                              |
| Medi-Physics, Inc  (doing business as Amersham Health of Dallas) Dallas, TX  |
| - License No. L05529                                                         |
| BaylorAll Saints Med Center, Ft. Worth, TX  - License No. L02212             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39289       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ARIZONA RADIATION REGULATORY AGENCY  |NOTIFICATION DATE: 10/15/2002|
|LICENSEE:  CONSTRUCTION INSPECTION AND TESTING  |NOTIFICATION TIME: 19:18[EDT]|
|    CITY:  TEMPE                    REGION:  4  |EVENT DATE:        10/15/2002|
|  COUNTY:                            STATE:  AZ |EVENT TIME:        15:25[MST]|
|LICENSE#:  7-98                  AGREEMENT:  Y  |LAST UPDATE DATE:  10/15/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GREG PICK            R4      |
|                                                |M. WAYNE HODGES      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  AZ RAD REGULATORY AGENCY     |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE - LOST OR STOLEN TROXLER MOISTURE DENSITY GAUGE              |
|                                                                              |
| "Date: 15 October 2002                                                       |
|                                                                              |
| "Time: 3:25 p.m. MST                                                         |
|                                                                              |
| "First Notice No.: 02-15                                                     |
|                                                                              |
| "Arizona Licensee: Construction Inspection and Testing                       |
| 2137 West 7th St.                                                            |
| Tempe, AZ 85281                                                              |
|                                                                              |
| "RSO: John Ritter                                                            |
|                                                                              |
| "License No.: 7-98                                                           |
|                                                                              |
| "Description of event: The licensee reported the loss of a Troxler           |
| moisture/density gauge sometime between 1030 and 1115 on 15 October after    |
| the technician left a job site in the vicinity of Cactus and 151st  Ave. The |
| gauge had been in the back of a pickup with the tailgate down. The gauge did |
| not have a handle lock. A search of his route for several hours failed to    |
| turn up the gauge. The gauge is a Troxler Model 3400 series, serial number   |
| 29519. It contains approximately 10 millicuries of cesium 137 and            |
| approximately 50 millicuries of americium-beryllium. The company is offering |
| a $250 reward for information leading to the return of the gauge and truck.  |
|                                                                              |
| "The U.S. NRC, FBI, Mexico, and the states of Colorado, Nevada, Utah, New    |
| Mexico and California are being informed of this incident."                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39290       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COLORADO DEPT OF HEALTH              |NOTIFICATION DATE: 10/15/2002|
|LICENSEE:  MIDWEST INSPECTION SERVICES          |NOTIFICATION TIME: 19:15[EDT]|
|    CITY:  DENVER                   REGION:  4  |EVENT DATE:        10/14/2002|
|  COUNTY:                            STATE:  CO |EVENT TIME:             [MDT]|
|LICENSE#:  CO 902-01             AGREEMENT:  Y  |LAST UPDATE DATE:  10/15/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GREG PICK            R4      |
|                                                |M. WAYNE HODGES      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TIM BONZER (VIA FAX)         |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING INDUSTRIAL RADIOGRAPHY INCIDENT             |
|                                                                              |
| The following information was documented as a telecon "to file" received by  |
| State of Colorado staff:                                                     |
|                                                                              |
| "Received phone notification today from Jeff Conners at Midwest Inspection   |
| Services concerning a source disconnect incident that happened yesterday,    |
| 10/14/02. Mr. Conners reported a radiography crew, working at a field site   |
| north of Denver, was unable to retract an Iridium-192 radiography source     |
| back into the camera. The radiographers called Mr. Conners, who is the       |
| assistant Radiation Safety Officer, for help.  Mr. Conners reported that he  |
| responded to the scene and was successful in connecting the source assembly  |
| to the drive cable and retracting it back into the radiography camera. He    |
| also responded that there were no overexposures to the radiography crew or   |
| members of the public.  Mr. Conners estimated his exposure for the recovery  |
| operation to be about 500 millirem, based on his pocket dosimeter readings.  |
| He stated that he would send a detailed written report to the Department     |
| within 30 days. The corporate RSO, David Ezell, was also notified of the     |
| incident."                                                                   |
|                                                                              |
| Contact the Headquarters Operations Officer for additional information.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39295       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 10/17/2002|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 10:27[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/17/2002|
+------------------------------------------------+EVENT TIME:        09:21[EDT]|
| NRC NOTIFIED BY:  WHEELER                      |LAST UPDATE DATE:  10/17/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KEN BARR             R2      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) IS OUT OF SERVICE DUE TO PLANNED      |
| MAINTENANCE                                                                  |
|                                                                              |
|                                                                              |
| At 0921 hours on 10/I7/02, the Safety Parameter Display System (SPDS) was    |
| removed from service as part of preplanned work to facilitate future         |
| replacement of the Emergency Response Facility Computer System (FRFCS).      |
| Electrical service was also interrupted to the Technical Support Center      |
| rendering that emergency response facility (ERF) unavailable for use.  Work  |
| should be complete by mid afternoon.                                         |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39296       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 10/17/2002|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 11:24[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        10/17/2002|
+------------------------------------------------+EVENT TIME:        05:15[CDT]|
| NRC NOTIFIED BY:  PHIL WARDLOW                 |LAST UPDATE DATE:  10/17/2002|
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONDITION WHICH COULD HAVE PREVENTED FULFILLMENT OF A SAFETY FUNCTION        |
|                                                                              |
| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or      |
| Condition that could have prevented fulfillment of a Safety Function needed  |
| to Mitigate the Consequences of an Accident. During a post maintenance test  |
| run of the 2B Diesel Generator following a planned maintenance window, the   |
| Diesel Generator reactive load (VARs) was identified to be erratic, as the   |
| Diesel Generator was loaded. At 05:15 CDST on 10/17, it was discovered that  |
| a potentiometer in the voltage regulating circuit had erratic output. This   |
| potentiometer was not worked on during the planned maintenance window.       |
| Because this component failure could have prevented the Diesel Generator     |
| from performing its design function, and because the 2B Diesel Generator is  |
| the emergency power supply for the High Pressure Core Spray System (HPCS),   |
| which is a single train safety system, it has been determined that this      |
| failure could potentially effect the Safety Function of this system, and is  |
| reportable as an 8 hour ENS notification."                                   |
|                                                                              |
| "Add info on current results/status below.                                   |
| The required actions of Technical Specification 3.5.1 were entered when the  |
| system was made inoperable for the maintenance window on 10/13 at 1900, and  |
| are continuing to be followed for the Inoperable High pressure Core Spray    |
| System (HPCS), until the Diesel Generator is restored to Operable Status."   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39297       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 10/17/2002|
|    UNIT:  [1] [2] [3]               STATE:  SC |NOTIFICATION TIME: 13:03[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        10/17/2002|
+------------------------------------------------+EVENT TIME:        11:21[EDT]|
| NRC NOTIFIED BY:  RANDY BRAMLETT               |LAST UPDATE DATE:  10/17/2002|
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KEN BARR             R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71(b)(1)         SAFEGUARDS REPORTS     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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          N       0        Refueling        |0        Refueling        |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COMPROMISE OF SAFEGUARDS INFORMATION                                         |
|                                                                              |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY.                        |
|                                                                              |
| CONTACT HOO FOR ADDITIONAL DETAILS.                                          |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39298       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CREST FOAM INDUSTRIES                |NOTIFICATION DATE: 10/17/2002|
|LICENSEE:  CREST FOAM INDUSTRIES                |NOTIFICATION TIME: 14:37[EDT]|
|    CITY:  MOONACHIE                REGION:  1  |EVENT DATE:        10/17/2002|
|  COUNTY:                            STATE:  NJ |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  10/17/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KENNETH JENISON      R1      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LARRY LAVELLE                |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING NUCLEAR DENSITY METER                                                |
|                                                                              |
| The licensee reported a missing Texas Nuclear Density Meter, Model 5201,     |
| serial number B764 and source number GV1731. The meter source contains 100   |
| millicuries of  Cs-137.  The licensee had already contacted the local police |
| department to report the missing meter. The exact date of loss is not known  |
| but the last physical audit performed by the licensee was in January 2002.   |
| The meter is used to measure the thickness of the foam density.              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39299       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 10/17/2002|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 15:50[EDT]|
|   RXTYPE: [3] CE                               |EVENT DATE:        10/14/2000|
+------------------------------------------------+EVENT TIME:        23:00[CDT]|
| NRC NOTIFIED BY:  GREGORY SCOTT                |LAST UPDATE DATE:  10/17/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GREG PICK            R4      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT EFW ACTUATION ON 10/14/2000                                      |
|                                                                              |
| "Per 10CFR50.73(a), Entergy is providing a verbal notification of an         |
| inadvertent actuation of the emergency feedwater (EFW) system at Waterford   |
| 3, which occurred on October 14, 2000. This event was initially determined   |
| to be not reportable, based on the reasoning that the actuation of the       |
| emergency feedwater components were initiated from the Diverse Emergency     |
| Feedwater System (DEFAS), and not from an Emergency Feedwater Actuation      |
| System (ESFAS) actuation. However, during a technical specification audit in |
| August of 2002, questions were raised regarding the validity of this         |
| reportability determination and a condition report was initiated. A          |
| subsequent review by licensing completed on August 21, 2002 determined that  |
| the event should have been reported per the then existing 10CFR50.72         |
| (b)(3)(iv) requirement as a 4-hour notification and reported as a follow-up  |
| LER notification per 10CFR50.73(a). The current applicable reporting         |
| criteria do not require immediate notification, however an LER or verbal     |
| notification is required per 10CFR50.73(a). Accordingly, this report is      |
| provided as a verbal notification per 10CFR50.73(a), Reportable events,      |
| which states, in part, in the case of an invalid actuation reported under    |
| 50.73(a)(2)(iv), the licensee may, at its option, provide a telephone        |
| notification to the NRC Operation Center within 60 days after the discovery  |
| of the event instead of submitting a written LER. This actuation was         |
| invalid, as described further below.                                         |
|                                                                              |
| "On October 14, 2000, the plant was in mode 3 in preparation for refueling   |
| outage 10, when an inadvertent actuation of emergency feedwater components   |
| occurred. This event occurred during the performance of procedure            |
| OP-904-017, Anticipated Transient System Check. While performing section     |
| 7.2, Testing of Diverse Emergency Feedwater System (DEFAS), step 7.2.12 (to  |
| replace the Diverse Emergency Feedwater Actuation System selector switch to  |
| disable) was inadvertently missed. This caused the emergency feedwater       |
| components to move to their safety positions when the DEFAS test switch was  |
| restored to its normal position. The two motor driven emergency feedwater    |
| pumps and the steam driven emergency feedwater pump started. The emergency   |
| feedwater isolation valves opened, but the emergency feedwater control       |
| valves did not open, as per design, due to adequate steam generator water    |
| levels. Accordingly, this event did not result in emergency feedwater flow   |
| or emergency feedwater injection into the steam generators. The operator     |
| immediately secured the EFW pumps and closed the EFW isolation valves.       |
|                                                                              |
| "NUREG 1022, revision 2, Event Reporting Guidelines 10CFR50.72 and 50.73     |
| provides guidance for determining if an actuation is invalid. The NUREG      |
| states, in part, that invalid actuations include actuations that are not the |
| result of valid signals and are not intentional manual actuations. Valid     |
| signals are those signals that are initiated in response to actual plant     |
| conditions or parameters satisfying the requirements for initiation of the   |
| safety function of the system. This report documents an actuation that was   |
| not the result of a valid signal and was not an intentional manual           |
| actuation, For these reasons, this event constitutes an invalid actuation."  |
|                                                                              |
| The NRC resident inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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:  10/17/2002|
|  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 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.                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39301       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 10/17/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 23:30[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/17/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:40[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/17/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |THOMAS KOZAK         R3      |
|  DOCKET:  0707001                              |M. WAYNE HODGES      NMSS    |
+------------------------------------------------+NADER MAMISH         IRO     |
| NRC NOTIFIED BY:  K. A. BEASLEY                |                             |
|  HQ OPS OFFICER:  ARLON COSTA                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR 91-01 BULLETIN RESPONSE NOTIFICATION                                 |
|                                                                              |
| At 1708 on 10-17-02, the Plant Shift Superintendent (PSS) was notified that  |
| potentially fissile (PF) waste had been discovered improperly stored at the  |
| Wet Air Pump station in the C-333 building. A pile of used absorbent pads    |
| was found in the floor at the West Air station. The absorbent pads are used  |
| to soak up oil that has leaked from the pumps. These pads should have been   |
| placed in an AQ-NCS approved 5.5 gallon drum and controlled as PF waste as   |
| they were picked up. This is a violation of the requirements of NCSA         |
| GEN-15.                                                                      |
|                                                                              |
| The NRC Resident inspector has been notified of this event.                  |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS: The used absorbent pads were accumulated      |
| incorrectly; however the uranium concentration for heterogeneous waste is    |
| low and a large quantity of heterogeneous fissile material would be required |
| for a criticality to occur.                                                  |
|                                                                              |
| PATHWAYS INVOLVED:  In order for a criticality to be possible, the           |
| interaction process condition would also have to be violated. However, the   |
| interaction control was maintained and therefore a criticality was not       |
| possible.                                                                    |
|                                                                              |
| CONTROLLED PARAMETERS: The two process conditions relied upon for double     |
| contingency for this scenario are interaction and geometry.                  |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEMS(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES: The first leg of double contingency is      |
| based on a minimum 2 ft. edge-to-edge spacing requirement to ensure double   |
| contingency for spacing violations involving waste drums end other items     |
| containing fissile/potentially fissile material. This control was not        |
| violated.                                                                    |
|                                                                              |
| The second leg of double contingency is based on geometry controls of the    |
| waste when it is placed into an AQ-NCS approved waste drum and the secondary |
| containment pans used to store the drums. Since the waste was accumulated on |
| the floor and not into the NCS-approved container, this control was          |
| violated. The process condition was not maintained and double contingency    |
| was not maintained                                                           |
|                                                                              |
| Since the used absorbent pads were not generated into an AQ-NCS approved     |
| waste container, the process condition for waste accumulation was not        |
| maintained. Therefore, double contingency was not maintained.                |
|                                                                              |
| CORRECTIVE ACTIONS: A buffer area has been established to control movement   |
| of fissile material within the area. A remediation guide will be prepared by |
| NCS prior to removal of the used absorbent pads.                             |
+------------------------------------------------------------------------------+