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Event Notification Report for December 11, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/08/2000 - 12/11/2000

                              ** EVENT NUMBERS **

37579  37580  37581  37582  37583  37584  37585  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37579       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 12/08/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 08:05[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/08/2000|
+------------------------------------------------+EVENT TIME:        06:30[EST]|
| NRC NOTIFIED BY:  STEVE SAUER                  |LAST UPDATE DATE:  12/08/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 EXPERIENCED A REACTOR TRIP/TURBINE TRIP DUE TO LOW-LOW STEAM          |
| GENERATOR WATER LEVEL                                                        |
|                                                                              |
| "Unit 1 reactor and turbine trip, first out annunciator was '13' steam       |
| generator low-low level.  Preliminary indications are that a feedwater       |
| isolation signal was generated, although actual conditions were not present. |
| This resulted in the feed reg and its bypass valves closing, resulting in    |
| the low-low level.  All aux feedwater pumps started on the level signal and  |
| maintained steam generator water inventory.  The plant is currently in mode  |
| 3 (hot standby) at normal operating temperature and pressure."               |
|                                                                              |
| All control rods fully inserted. The main condenser is in service removing   |
| decay heat via the bypass valves.  There were no maintenance activities      |
| ongoing which could have resulted in the trip.  All systems functioned as    |
| required.  The licensee will inform local agencies and has informed the NRC  |
| resident inspector.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37580       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 12/08/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 12:07[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/08/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:15[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  12/08/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MICHAEL PARKER       R3      |
|  DOCKET:  0707002                              |PAUL FREDRICKSON     R2      |
+------------------------------------------------+BRIAN SMITH          NMSS    |
| NRC NOTIFIED BY:  DALE NOEL                    |CHARLES MILLER       IRO     |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF SURFACE RADIATION READINGS IN EXCESS OF TRANSPORTATION LIMITS   |
| ON 3 OF 30 CYLINDERS SHIPPED FROM WESTINGHOUSE ELECTRIC COMPANY IN COLUMBIA, |
| SOUTH CAROLINA                                                               |
|                                                                              |
| At 1115 hours on 12/08/00, USEC Portsmouth health physics personnel          |
| determined that an inbound shipment of empty, 2.5-ton, healed cylinders had  |
| external radiation levels in excess of the limits in 10CFR71.47.  The        |
| shipment involved 30, empty, 2.5-ton, healed cylinders from Westinghouse     |
| Electric Company in Columbia, South Carolina; and surveys showed that three  |
| rear cylinders had radiation readings of 225 to 250 millirem per hour on     |
| contact.  This exceeds the 10CFR71.47 limit of 200 millirem per hour and     |
| meets the 1-hour reporting criteria of 10CFR20.1906(d)(1).                   |
|                                                                              |
| The truck will be properly dispositioned on the plant site.  Portsmouth      |
| personnel are in the process of making notifications to Westinghouse         |
| Electric Company (the shipper) and Hitman Transport Company (the carrier).   |
| There was nothing unusual or misunderstood, and all systems functioned as    |
| required.                                                                    |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector and plan to notify  |
| the Department of Energy.                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37581       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TRU-TEC SERVICES, INC.               |NOTIFICATION DATE: 12/08/2000|
|LICENSEE:  TRU-TEC SERVICES, INC.               |NOTIFICATION TIME: 18:47[EST]|
|    CITY:  LA PORTE                 REGION:  4  |EVENT DATE:        12/08/2000|
|  COUNTY:  HARRIS                    STATE:  TX |EVENT TIME:        03:30[CST]|
|LICENSE#:  07-28386-01           AGREEMENT:  Y  |LAST UPDATE DATE:  12/08/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BLAIR SPITZBERG      R4      |
|                                                |PAUL FREDRICKSON     R2      |
+------------------------------------------------+THOMAS ESSIG         NMSS    |
| NRC NOTIFIED BY:  NORMAN LANIER                |CHARLES MILLER       IRO     |
|  HQ OPS OFFICER:  LEIGH TROCINE                |JOHN ROGGE           R1      |
+------------------------------------------------+STAMBAUGH            DOE     |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|NTRA                     TRANSPORTATION EVENT   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RECEIPT OF A TRU-TEC SERVICES, INC., CONTAINER OF BROMINE-82 THAT APPEARED   |
| TO HAVE BEEN OPENED AND RE-PACKAGED INCORRECTLY DURING TRANSPORT BETWEEN     |
| TEXAS A&M AND ST. CROIX IN THE VIRGIN ISLANDS                                |
|                                                                              |
| On 12/04/00, Tru-Tec Services, Inc., shipped an empty container from their   |
| facility in La Porte, Texas, to Texas A&M via Acme Trucking.  The container  |
| was similar in shape to a propane tank (but taller).  It was lead filled and |
| weighed between 700 and 750 pounds.  It also had a 3-inch by 3-inch cavity   |
| inside and a lid with a T-bar to hold the lid in place.  Texas A&M loaded    |
| the empty container with bromine-82, and the activity of the bromine-82 at   |
| noon on 12/04/00 was 900 millicuries.  The bromine-82 was double             |
| encapsulated (inside three glass ampoules which were also inside a metal     |
| swagelock container with a screw on cap).  After Texas A&M loaded the        |
| container, Acme Trucking transported the container to Federal Express at     |
| Intercontinental Airport in Houston, Texas, on 12/04/00.  Apparently, the    |
| container arrived at a Federal Express hub in Memphis, Tennessee, on         |
| 12/05/00, and it remained there until 12/07/00.  On 12/07/00, the shipment   |
| left Memphis, Tennessee, via Federal Express and arrived in Puerto Rico on   |
| the morning of 12/08/00.  It was then transported by 4 Star Air Cargo to St. |
| Croix in the Virgin Islands.  Tru-Tec Services, Inc., received the container |
| between approximately 1600 and 1630 EST on 12/08/00.                         |
|                                                                              |
| Upon arrival in St. Croix, Tru-Tec personnel discovered a problem with the   |
| container.  It appeared that the container had been opened and put back      |
| together incorrectly.  The container's T-bar was missing, and the lid was    |
| upside-down with the bromine-82 on the outside of the container rather than  |
| shielded on the inside of the container.  The bromine-82 appeared to be      |
| intact.  Smear tests were performed using a GM detector, and there was no    |
| evidence of contamination or of a breech in the double encapsulated          |
| material.  Survey readings with the bromine-82 unshielded on the outside of  |
| the package resulted a dose rate of 6 millirem per hour at a distance of 6   |
| feet.  The bromine-82 is currently under control and in the possession of    |
| the Tru-Tec Services, Inc.                                                   |
|                                                                              |
| The bromine-82 was intended for use in tracer studies at chemical plants,    |
| and it was manufactured at Texas A&M.  It was reported that the half life of |
| bromine-82 is 35 hours, and the estimated activity of the material at noon   |
| on 12/08/00 would have been 140 millicuries.  bromine-82 is a strong gamma   |
| emitter.  The Tru-Tec Services, Inc. main office is located in Delaware.     |
|                                                                              |
| The licensee plans to contact the carriers and plans to attempt to trace its |
| path and discover who came into contact with the container.                  |
|                                                                              |
| (Call the NRC operations officer for licensee contact information.)          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37582       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 12/08/2000|
|LICENSEE:  ASSOCIATED SOILS ENGINEERING, INC.   |NOTIFICATION TIME: 20:06[EST]|
|    CITY:  ORANGE                   REGION:  4  |EVENT DATE:        12/04/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:        05:30[PST]|
|LICENSE#:  2446-19               AGREEMENT:  Y  |LAST UPDATE DATE:  12/08/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BLAIR SPITZBERG      R4      |
|                                                |THOMAS ESSIG         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PAUL BALDENWEG               |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN ASSOCIATED SOILS ENGINEERING, INC, MOISTURE DENSITY GAUGE             |
|                                                                              |
| The following text is a portion of a facsimile received from the State of    |
| California, Department of Health Services, Radiologic Health Branch:         |
|                                                                              |
| "A CPN Moisture/Density gauge, model MC1 DR, S/N MD 01005909, was picked up  |
| from the office [in Long Beach, CA] on 12/03/00.  It was locked down in the  |
| back of the truck of the gauge user [...].  The gauge was stolen between     |
| 2100 [PST] on 12/03/00 and 0530 [PST] on 12/04/00 from [the user's] trailer  |
| [park located in ...] Orange, CA [...]."                                     |
|                                                                              |
| It was reported that the licensee notified the local Police Department and   |
| that the gauge contained an unknown quantity of americium-241/beryllium.     |
|                                                                              |
| (Call the NRC operations officer for contact information.)                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37583       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 12/09/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 12:40[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/09/2000|
+------------------------------------------------+EVENT TIME:        10:15[EST]|
| NRC NOTIFIED BY:  CECIL H. WILLIAMS, JR.       |LAST UPDATE DATE:  12/09/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DURING PERFORMANCE OF A REVISED PROCEDURE FOR A SOLID |
| STATE PROTECTION SYSTEM (SSPS) AND REACTOR TRIP BREAKER OPERABILITY TEST     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "While performing a new revision to [procedure] 14421-1, 'SOLID STATE        |
| PROTECTION SYSTEM AND REACTOR TRIP BREAKER TRAIN B OPERABILITY TEST,' a      |
| reactor trip occurred from Intermediate Range High Flux while performing     |
| section 5.3, SAFETY INJECTION RESET TIMING CIRCUIT TEST.  Both trains of     |
| [the] reactor protection system functioned as expected.  A feedwater         |
| isolation was received as expected from P4-Low Tavg, but only from SSPS      |
| Train A due to SSPS Train B being in 'TEST' for the surveillance in          |
| progress.  Also, an [auxiliary feedwater] actuation signal (AFWAS) was       |
| received from Steam Generator Lo-Lo level in all four steam generators, but  |
| only the [turbine-driven auxiliary feedwater pump] pump and [motor-driven    |
| auxiliary feedwater pump] pump A started, again due to SSPS Train B being in |
| 'TEST.'  The steam generator blowdown system also isolated properly on the   |
| AFWAS signal.  The plant is currently stable in Mode 3, and an Event Review  |
| Team is currently being formed.  At 1207, Train B SSPS was restored to [its] |
| normal configuration.  No estimated restart date is currently available."    |
|                                                                              |
| The licensee stated that all control rods fully inserted as a result of the  |
| trip.  It was also reported that all systems functioned as required based on |
| the configuration of the plant at the time of the event (SSPS Train B in     |
| test) and that there was nothing unusual or misunderstood.  The root cause   |
| of the reactor trip is currently under investigation.                        |
|                                                                              |
| The unit is currently stable in Mode 3 (Hot Standby).  Normal charging and   |
| letdown, pressurizer heaters and sprays, and the reactor coolant pumps are   |
| being utilized for primary system inventory, pressure, and transport         |
| control.  Secondary steam is being dumped to the condenser, and auxiliary    |
| feedwater is being supplied to the steam generators.  All containment        |
| parameters are normal, and offsite power is available.                       |
|                                                                              |
| The NRC resident inspector was in the control room watching performance of   |
| the surveillance procedure at the time of the event.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37584       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 12/09/2000|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 13:23[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/09/2000|
+------------------------------------------------+EVENT TIME:        11:55[CST]|
| NRC NOTIFIED BY:  FRANK WEAVER                 |LAST UPDATE DATE:  12/09/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BLAIR SPITZBERG      R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A DEFICIENCY THAT COULD POTENTIALLY COMPROMISE THE ABILITY OF A |
| FIRE BARRIER TO PROVIDE ADEQUATE PROTECTION IN THE EVENT OF A FIRE           |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During destructive examination of the Kaowool fire barrier system used to   |
| protect Appendix R raceways, a deficiency was identified that could          |
| potentially compromise the ability of the fire barrier to provide adequate   |
| protection for at least one train of redundant safe shutdown capability in   |
| the event of a fire.  The affected plant area is the Division 2 [engineered  |
| safety feature] switchgear room, where redundant functions of both the       |
| Division 1 and 2 Standby Service Water systems could be affected.  Fire      |
| protection program compensatory actions, i.e., [an] hourly firewatch has     |
| been in place since the deficiencies as identified in SECY 99-204 were       |
| documented at Grand Gulf.  The area has detection and automatic fire         |
| suppression [systems] that are OPERABLE.  Additionally, because of the       |
| outcome of the above mentioned examination, a continuous firewatch has been  |
| established as an additional compensatory measure."                          |
|                                                                              |
| The licensee stated that the hourly fire watch has been in place since       |
| 09/01/99.  The hourly fire watch is required be technical specifications;    |
| however, the continuous fire watch has been established as an additional     |
| conservative measure.                                                        |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37585       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 12/11/2000|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 04:42[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        12/11/2000|
+------------------------------------------------+EVENT TIME:        04:05[EST]|
| NRC NOTIFIED BY:  THOMAS                       |LAST UPDATE DATE:  12/11/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |50       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED TECHNICAL SPECIFICATION REQUIRED SHUTDOWN PRIMARY LEAK         |
| EXCEEDING ALLOWABLE VALUES.                                                  |
|                                                                              |
| At 0320 Unit 2 received indications of a primary leak in containment that    |
| exceeded allowable values in Tech Spec 3.4.6.2. These indications included   |
| containment gas activity alert alarm, Pressurizer level reduction,           |
| Pressurizer spray valve closure and an increase in charging flow. Indicated  |
| charging/letdown mismatch is 7 gpm.  Calculated primary leak rate estimate   |
| based on VCT and Pressurizer level changes was 9.5 gpm at 0400. At 0412 Unit |
| 2 began a plant shutdown at 2% per minute.  This constitutes the initiation  |
| of a plant shutdown required by Tech Specs.  A containment entry is planned  |
| to identify the source of the leak. The entry will be made after the reactor |
| is subcritical.                                                              |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
|                                                                              |
| * * *  UPDATE ON 12/20/00 @ 0603 BY THOMAS TO GOULD  * * *                   |
|                                                                              |
| Update at 0543: Estimated RCS leak rate based on charging/letdown mismatch   |
| exceeds 10 gpm. An Unusual Event was declared at 0536 due to Unidentified    |
| Leakage exceeding 10 gpm. Current leak rate estimate is between 12 and 20    |
| gpm.  Plant is currently at 22% power.                                       |
|                                                                              |
| The NRC Resident Inspector was notified.   FEMA(Bagwell), RDO(Rogge),        |
| EO(Zwolinski), and IRO(Miller)                                               |
+------------------------------------------------------------------------------+