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Event Notification Report for October 26, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/25/1999 - 10/26/1999

                              ** EVENT NUMBERS **

36215  36329  36341  36342  36343  36344  36345  36346  36347  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36215       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 09/23/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 03:13[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        09/22/1999|
+------------------------------------------------+EVENT TIME:        23:55[CDT]|
| NRC NOTIFIED BY:  McLAUGHLIN                   |LAST UPDATE DATE:  10/25/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       90       Power Operation  |90       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DIVISION 3 EMERGENCY DIESEL GENERATOR TRIPPED ON OVER SPEED DURING MONTHLY   |
| SURVEILLANCE TESTING.                                                        |
|                                                                              |
| While performing monthly surveillance start of the High Pressure Core Spray  |
| system Emergency Diesel Generator, the Diesel automatically tripped off on   |
| an overspeed signal.  The diesel does not appear to have been damaged but    |
| remains shutdown and unavailable for on-going investigation of the failure.  |
| The High Pressure Core Spray system is inoperable but available from normal  |
| power source only. The failure mechanism is being investigated and           |
| corrective actions will be performed.   The Reactor Core Isolation Cooling   |
| pump and all other Emergency Core Cooling Systems are also fully operable.   |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
|                                                                              |
| * * * RETRACTION AT 1756ET ON 10/25/99 BY R HASTY TAKEN BY MACKINNON* * *    |
|                                                                              |
| Preliminary troubleshooting on the 1B Emergency Diesel Generator determined  |
| that the cause of the overspeed trip was that the governor synchronizer      |
| speed setting was at its mechanical high-speed stop.  It was not known when  |
| the governor synchronizer speed setting had reached that position, so an ENS |
| call was made per 10 CFR 50.72.                                              |
|                                                                              |
| A through investigation has been performed.  The investigation has           |
| determined that the most probable cause of the event was a mechanical        |
| failure of the local governor control switch.  This switch is only in the    |
| governor control circuit when the governor control is in local manual, which |
| indicates that the failure occurred during the initial start sequence, after |
| the diesel generator was out of service for the surveillance test.  In       |
| addition, the local governor control switch is bypassed when in remote       |
| manual, switch is required for standby conditions and operability of the     |
| diesel generator.                                                            |
|                                                                              |
| Since the failure occurred after the diesel generator was out of service,    |
| and was identified and repaired in 31 hours, well within the 14 day          |
| Technical Specification allowed outage time, it has been determined that     |
| this event is not reportable to the NRC, and this event notification is      |
| being retracted. R3DO (Mike Jordan)  notified.                               |
|                                                                              |
| The NRC Resident was notified of this retraction by the licensee.            |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36329       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 10/22/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 06:24[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        10/22/1999|
+------------------------------------------------+EVENT TIME:        03:15[EDT]|
| NRC NOTIFIED BY:  JESTER                       |LAST UPDATE DATE:  10/25/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI IS INOPERABLE                                                           |
|                                                                              |
| WHILE PERFORMING HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM OPERABILITY   |
| TEST (OPT-09-2) FOR POST MAINTENANCE TESTING, THE TURBINE STEAM SUPPLY VALVE |
| #1-E41-F001 FAILED IN MID-POSITION.  THIS OCCURRED WHEN THE VALVE WAS BEING  |
| CLOSED TO PLACE THE SYSTEM IN ITS STANDBY LINEUP FOLLOWING COMPLETION OF THE |
| OPERABILITY TEST.  IN ADDITION, THE STEAM SUPPLY DRAIN POT INBOARD AND       |
| OUTBOARD DRAIN VALVES #1-E41-F028 AND #1-E41-F029 DID NOT OPERATE AS         |
| EXPECTED.  THESE VALVES OPEN AND CLOSE IN UNISON AUTOMATICALLY AS DETERMINED |
| BY THE POSITION OF THE TURBINE STEAM SUPPLY VALVE #1-E41-F001.  CURRENTLY,   |
| THE INBOARD DRAIN VALVE #1-E41-F028 IS CLOSED AND THE OUTBOARD DRAIN VALVE   |
| #1-E41-F029 IS OPEN.                                                         |
|                                                                              |
| THE AUTOMATIC DEPRESSURIZATION SYSTEM, LOW PRESSURE COOLANT INJECTION        |
| SYSTEM, CORE SPRAY SYSTEM AND REACTOR CORE ISOLATION COOLANT SYSTEM ARE      |
| OPERABLE.  THE LICENSEE IS INVESTIGATING THE CAUSE OF THE PROBLEM AND        |
| SUSPECTS IT MIGHT BE DUE TO A LOGIC/LIMIT SWITCH CIRCUITRY PROBLEM.          |
|                                                                              |
| THE SAFETY SIGNIFICANCE OF THIS EVENT IS MINIMAL.                            |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| * * * RETRACTION AT 1614ET ON 10/25/99 BY STEVE TABOR TAKEN BY MACKINNON * * |
| *                                                                            |
|                                                                              |
| BASED ON FURTHER EVALUATION, IT HAS BEEN DETERMINED THAT THE HPCI            |
| MALFUNCTION WAS CAUSED BY THE PLANNED MAINTENANCE ACTIVITIES AND WAS NOT A   |
| PRE-EXISTING CONDITION.  SPECIFICALLY, THE MALFUNCTION WAS DUE TO A          |
| CONDITION WHICH WAS INTRODUCED BY THE REPLACEMENT OF THE HPCI TURBINE TRIP   |
| SOLENOID VALVE, E41-C002-SV1 (ie,  DELAYED OPERATION OF THE E41-C003-SV1).   |
| THIS CONDITION WAS CORRECTED AND POST-MAINTENANCE TESTING COMPLETED          |
| SATISFACTORILY.  SINCE THIS CONDITION WAS INTRODUCED DURING THE MAINTENANCE  |
| ACTIVITIES WITH THE HPCI SYSTEM PROPERLY REMOVED FROM SERVICE AND IDENTIFIED |
| AS PART OF POST-MAINTENANCE TESTING ACTIVITIES, IT DOES NOT REPRESENT AN     |
| EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE    |
| SAFETY FUNCTION OF HPCI. AS SUCH, THIS EVENT IS REPORTABLE  IN ACCORDANCE    |
| WITH 10 CFR 50.72(b)(2)(iii)(D). R2DO (K.  LANDIS) NOTIFIED.                 |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36341       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 10/25/1999|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 09:39[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        10/23/1999|
+------------------------------------------------+EVENT TIME:        02:00[EDT]|
| NRC NOTIFIED BY:  MALCOLM BROWNE               |LAST UPDATE DATE:  10/25/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO THE NATIONAL MARINE FISHERIES SERVICE AND THE NEW    |
| JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION (NJ DEP).                      |
|                                                                              |
| AN IMMATURE GREEN SEA TURTLE WAS FOUND DEAD AT APPROXIMATELY 0200EDT ON      |
| 10/23/99 IN UNIT'S DILUTION WATER STRUCTURE.  THE LICENSEE WILL NOTIFY THE   |
| NJ DEP AND MARINE FISHERIES SERVICE AND WILL INFORM THE NRC RESIDENT         |
| INSPECTOR.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36342       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 10/25/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 11:17[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/24/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        22:50[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/25/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |ROGER LANKSBURY              |
|  DOCKET:  0707001                              |JOSIE PICCONE                |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  W. F. CAGE                   |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|OCBC 76.120(c)(2)(iii)   REDUNDANT EQUIP INOP   |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADEQUATE HIGH PRESSURE FIRE WATER SYSTEM INSTALLATION IN THE C-337         |
| BUILDING                                                                     |
|                                                                              |
| "On 10/24/99, at 2250 CDT, the Plant Shift Superintendent was notified that  |
| High Pressure Fire Water system D5 in the C-337 building,  does not meet     |
| NFPA Code 13.  During a walkdown of the system, two non-conformances were    |
| noted.  The spacing between two of the branch lines exceeds the NFPA 13      |
| maximum spacing criteria of 15 feet.  It was also noted that the spacing of  |
| the sprinkler heads on these two branch lines is between 5 to 6 feet. NFPA   |
| 13 requires the heads to be spaced a minimum of 6 feet apart unless baffles  |
| have been installed.  These heads do not have baffles installed on them.     |
| This system was inoperable at the time of discovery, and LCO required fire   |
| patrols were being performed.                                                |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed.                                                        |
|                                                                              |
| "The NRC Resident Inspector has been notified of this event."                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36343       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 10/25/1999|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 15:30[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/25/1999|
+------------------------------------------------+EVENT TIME:        14:15[CDT]|
| NRC NOTIFIED BY:  JOHN SELL                    |LAST UPDATE DATE:  10/25/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY              |
|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          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SEVERAL SAFE SHUTDOWN PANELS WERE FOUND THAT NEEDED ADDITIONAL LIGHTING      |
|                                                                              |
| During the Appendix R re-baselining project, several safe shutdown           |
| components were found that need additional emergency lighting on them and    |
| additional pathway lighting. This additional lighting is required by 10CFR   |
| 50 Appendix R, Section III. This condition is also applicable to Unit 1.     |
| Unit 1 is presently in a refueling outage.                                   |
|                                                                              |
| Extra Emergency lighting is needed in the following areas:  Auxiliary        |
| Feedwater Cubicles; D-16, 17, 18, & 19 Panels in Control Room,; Panels in    |
| the Computer Room; Non Vital 4.16kV buses 1A01, 1A02, 2A01, & 2A02; Vital AC |
| 120V Buses D107, D109, D302, & D303; 480V Non Vital  Buses 2B01, 2B02;  480V |
| Non Vital Buses 1B01, & 1B02; Unit 1 Sump Room West Entry, etc.              |
|                                                                              |
| The Licensee is not in any Tech Spec action statements as a result of the    |
| above information.                                                           |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36344       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STATE OF TENNESSEE                   |NOTIFICATION DATE: 10/25/1999|
|LICENSEE:  GTS DURATEK WEST                     |NOTIFICATION TIME: 14:30[EDT]|
|    CITY:  MEMPHIS                  REGION:  2  |EVENT DATE:        10/25/1999|
|  COUNTY:                            STATE:  TN |EVENT TIME:        12:00[EDT]|
|LICENSE#:  TN-99-145             AGREEMENT:  Y  |LAST UPDATE DATE:  10/25/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KERRY LANDIS         R2      |
|                                                |CHARLEY HAUGHNEY     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  EDDIE NANNY, FAXED           |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTTOM OF BOX RADIATION READINGS ARE 350mR/hr. SHIPPING PAPERS SHOW A        |
| MAXIMUM READING OF 105mR/hr.                                                 |
|                                                                              |
| A shipment from G.E. Laguna Verde power plant in Mexico was received at GTS  |
| Duratek West, (formerly Frank W. Hake) , Memphis, TN.  The receiving survey  |
| at GTS revealed a small hot spot on the bottom of an upper stacked box       |
| (between boxes ) of equipment being shipped from G.E. The elevated area was  |
| 10" across with a maximum measured level of 350 mR/hr.  The point of origin  |
| surveys showed a maximum of 105 mR/hr  on the bottom of the box.  GTS        |
| requested and was given permission to receive and offload shipment to        |
| minimize perimeter and allow evaluation of the cause of the elevated         |
| reading. Event number assigned to this event by the State of TN is           |
| TN-99-145. License number is R-79171.                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36345       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 10/25/1999|
|    UNIT:  [1] [2] [3]               STATE:  SC |NOTIFICATION TIME: 17:36[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        10/25/1999|
+------------------------------------------------+EVENT TIME:        16:50[EDT]|
| NRC NOTIFIED BY:  J. MCGUFFIN                  |LAST UPDATE DATE:  10/25/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       99       Power Operation  |99       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TEMPORARY ACCESS GRANTED INAPPROPRIATELY.  IMMEDIATE COMPENSATORY MEASURES   |
| TAKEN UPON DISCOVERY.  VENDOR EMPLOYEE WAS TERMINATED.  AN INVESTIGATION     |
| INTO THE INCIDENT IS CONTINUING.                                             |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.       |
|                                                                              |
| SEE HOO LOG BOOK FOR FURTHER DETAILS.                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36346       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  RAC SERVICES, INC.                   |NOTIFICATION DATE: 10/25/1999|
|LICENSEE:  RAC SERVICES, INC.                   |NOTIFICATION TIME: 18:27[EDT]|
|    CITY:  WASHINGTON               REGION:  4  |EVENT DATE:        10/22/1999|
|  COUNTY:                            STATE:  OK |EVENT TIME:        12:30[CDT]|
|LICENSE#:  UNK                   AGREEMENT:  N  |LAST UPDATE DATE:  10/25/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID LOVELESS       R4      |
|                                                |LINDA HOWELL         R4      |
+------------------------------------------------+CHARLEY HAUGHNEY     NMSS    |
| NRC NOTIFIED BY:  JUDY GAYANICH                |JOSEPH GIITTER       IRO     |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| IN-LINE DENSIOMETER CONTAINING 200mCi of CESIUM-137 STOLEN THE MORNING OF    |
| OCTOBER 22, 1999. POLICE AND SHERIFFS DEPARTMENTS NOTIFIED, REWARD POSTED BY |
| LICENSEE.                                                                    |
|                                                                              |
| The following event was reported by RAC Services, Inc., located in           |
| Washington, OK.  NRC Region 4 Linda Howell had the licensee call the event   |
| into the Operations Center and she remained on line during the event         |
| notification.                                                                |
|                                                                              |
| The In-Line Densiometer was last serviced by Texas Nuclear (TN) Technologies |
| on October 14, 1999 at its  office located in Round Rock, Tx (10-15 miles    |
| north of Austin).  The In-Line Densiometer is 3' in length, 2' wide and      |
| weighs about 80 pounds.  The In-Line Densiometer is gray in color and its    |
| model number is 5192 and its serial number is B6670, contains 200mCi of      |
| Cs-137.   It is licensed under a general license number (owners did not      |
| know/have  the license number for the In-Line Densiometer).  Rex, one of the |
| callers, said that this In-Line Densiometer did not have any radioactive     |
| placards or labels on it (may have been rubbed off). Rex said that he did    |
| not have to wear a Film Badge or TLD when carrying the In-Line Densiometer.  |
|                                                                              |
|                                                                              |
| In the early morning hours (0300 AM) of 10/21/99 the licensee was heading    |
| back on a county road (road runs between 2 county lines) about 8 miles North |
| of Calumet, OK when the trailer blew a tire. The trailer was full of scrap   |
| iron painted red and the In-Line Densiometer was chained to the trailer. The |
| In-Line Densiometer was not in its case at this time.  The licensee checked  |
| on the trailer twice during October 21, 1999 (Thursday) and the last time    |
| they saw the trailer was around 2030 hours on 10/21/99.    When the licensee |
| arrived around 1230 hours on 10/22/99 (Friday) to replace the flat tire they |
| discovered that the trailer was missing and presumed stolen.                 |
|                                                                              |
| The licensee notified police and one of the county Sheriffs Department  that |
| the trailer and In-Line Densiometer had been stolen Friday afternoon         |
| (10/22/99). On Monday, October 25, 1999, the licensee notified the other     |
| county Sheriffs Department that their In-Line Densiometer had been stolen    |
| along with the trailer.  The licensee has offered a $5,000 reward for the    |
| In-Line Densiometer. The In-Line Densiometer is shipped  in a Type "A        |
| "package.                                                                    |
|                                                                              |
| A telephone call was placed to Texas Nuclear Technologies and a message was  |
| left on their answering machine to either call the NRC Headquarters          |
| Operations  Officer or call NRC Region 4 Office.                             |
|                                                                              |
| Ask HOO for telephone numbers and address..                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36347       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 10/26/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 03:06[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        10/26/1999|
+------------------------------------------------+EVENT TIME:        01:32[CDT]|
| NRC NOTIFIED BY:  LARRY LEES                   |LAST UPDATE DATE:  10/26/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          ALE                   |DAVID LOVELESS       R4      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |JOSEPH GIITTER       IRO     |
|                                                |CANUPP               FEMA    |
|                                                |PERKINS              DOE     |
|                                                |TURMAN               EPA     |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 REPORTED ENTERING AND EXITING CONDITIONS REQUIRING AN ALERT           |
| DECLARATION                                                                  |
|                                                                              |
| "AT 0132CDT, WHEN ATTEMPTING TO TRANSFER STATION LIGHTING, VITAL BUSES 1A3   |
| AND 1A4 WERE DEENERGIZED.  [BOTH] DIESEL GENERATORS [DG-1 AND DG-2]  WERE IN |
| 'OFF-AUTO' FOR MODE 5 CONDITIONS.  WHEN THE DIESEL GENERATORS WERE TAKEN TO  |
| 'AUTO,' THE DIESEL  GENERATORS AUTOSTARTED AND ENERGIZED VITAL BUSES 1A3 AND |
| 1A4, AT 0134CDT.  SHUTDOWN COOLING WAS LOST FOR APPROXIMATELY [TWO] 2        |
| MINUTES AND RESTORED WHEN THE DIESEL GENERATORS WERE PLACED ON THE BUS.      |
| SHUTDOWN COOLING TEMPERATURE INDICATED [ZERO] 0 DEGREES FAHRENHEIT           |
| TEMPERATURE RISE IN THE [TWO] 2 MINUTES THAT SHUTDOWN COOLING WAS LOST.      |
| WHEN THE EMERGENCY PLAN WAS ENTERED, VITAL BUSES WERE ALREADY RE-ENERGIZED.  |
| AN ALERT WAS REPORTED UNDER EAL 4.3 BUT NOT DECLARED.  OFFSITE POWER WAS     |
| ALWAYS AVAILABLE, AND AS OF THIS TIME IS ON VITAL BUS 1A3."                  |
|                                                                              |
| OFFSITE POWER WAS RESTORED TO BUSES 1A3 AND 1A4 AT 0159CDT AND 0209CDT,      |
| RESPECTIVELY.  INITIAL RCS TEMPERATURE WAS 103 DEGREES FAHRENHEIT.  SHUTDOWN |
| COOLING TRAIN "A" WAS PLACED IN-SERVICE TO REPLACE THE OPERATING TRAIN "B"   |
| WHICH WAS DEENERGIZED.  THE    ELECTRICAL MAINTENANCE HAS LOOKED AT          |
| TRANSFORMERS INSIDE AND OUTSIDE THE PLANT AND FOUND NO APPARENT FAILURE.     |
|                                                                              |
| THE LICENSEE NOTIFIED BOTH STATE AND LOCAL AGENCIES AND WILL INFORM THE NRC  |
| RESIDENT INSPECTOR.                                                          |
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