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
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|Power Reactor |Event Number: 37579 |
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+------------------------------------------------------------------------------+
| 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
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| 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. |
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|Fuel Cycle Facility |Event Number: 37580 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Other Nuclear Material |Event Number: 37581 |
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| 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
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| 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
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| 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
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| 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) |
+------------------------------------------------------------------------------+
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