Event Notification Report for January 22, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/21/1999 - 01/22/1999 ** EVENT NUMBERS ** 35261 35275 35286 35288 35289 35290 35291 35292 35293 35294 35295 35296 35297 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35261 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 01/14/1999| | UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:06[EST]| | RXTYPE: [1] W-3-LP |EVENT DATE: 01/14/1999| +------------------------------------------------+EVENT TIME: 09:18[EST]| | NRC NOTIFIED BY: MARK PALMER |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |AL BELISLE R2 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 ON TRIP OF TWO OF THREE REACTOR COOLANT PUMPS AND | | LOSS OF TWO 6.9-kV BUSES | | | | During relay calibration on the 'A' 6.9-kV non-safety bus, the bus was | | unexpectedly deenergized. The 'C' 6.9-kV bus is a swing bus and was tied to | | the 'A' 6.9-kV bus, which caused it to be deenergized also. This caused the | | loss of two of three reactor coolant pumps, and in turn, caused an automatic | | reactor trip from 100% power. All systems functioned as expected, all rods | | fully inserted, and auxiliary feedwater started on low steam generator level | | as expected. All safety systems are operable except the 'A' containment | | hydrogen analyzer which is out of service for planned maintenance. | | | | The exact cause of the loss of the 6.9-kV buses is currently under | | investigation. | | | | The licensee notified the NRC Resident Inspector, the State of North | | Carolina, and the local county. | | | | ***Update on 01/21/99 at 1710 ET by Mark Ellington taken by MacKinnon*** | | | | The licensee stated that they had not made an official notification to the | | state of North Carolina or the local counties but instead they had made | | courtesy calls to the state of North Carolina and the applicable counties | | notifying them of the reactor trip. | | | | The licensee also stated that 'A-SA" Containment Hydrogen Recombiner was | | out of service instead of the "A" containment hydrogen analyzer. R2DO | | (Chris Christensen) notified. | | | | The NRC resident inspector was notified of this update by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 35275 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/15/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:08[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/15/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:10[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/21/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JIM GAVULA R3 | | DOCKET: 0707002 |JOHN SURMEIER NMSS | +------------------------------------------------+FRANK CONGEL IRO | | NRC NOTIFIED BY: RICHARD LARSON | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4-HOUR NRC 91-01 BULLETIN NOTIFICATION INVOLVING ABANDONED EQUIPMENT IN THE | | X-326 PROCESS BUILDING | | | | ON JANUARY 15, 1999, AT 1410 EST IT WAS DISCOVERED THAT THE X-326 PROCESS | | BUILDING NUCLEAR CRITICALITY APPROVALS (NCSAs) DO NOT DESCRIBE THE | | OPERATION/CONTROLS FOR THE FOLLOWING ABANDONED IN PLACE EQUIPMENT: PRODUCT | | PURIFICATION DISTILLATION TOWER, OLD EVACUATION JETS, OLD SO2 REACTOR, OLD | | PW BOOSTER CONNECTED TO CELL 25-7-15, AND [AN] OLD FREON DEGRADER. | | | | "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDONED | | EQUIPMENT. | | | | "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." | | | | A PRIOR NRC NOTIFICATION (EVENT #33627) WAS MADE WHICH IDENTIFIED LEGACY | | EQUIPMENT IN THE X-326 PROCESS BUILDING, HOWEVER, THE ABOVE EQUIPMENT WAS | | INADVERTENTLY OMITTED. THE EQUIPMENT IS IN GEOMETRICALLY FAVORABLE | | CONDITIONS AND CONTAINS URANIUM BELOW THE SAFE MASS LIMIT. THIS CONDITION | | WAS DISCOVERED IN A REVIEW OF COMPLETED NCSAs. | | | | THE LICENSEE WILL INFORM THE DOE SITE REPRESENTATIVE AND HAS INFORMED THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1955 ON 1/18/99, BY LARSON, TAKEN BY WEAVER * * * | | | | "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDONED | | EQUIPMENT. | | | | UPDATE: DUE TO THE PROBLEMS CONCERNING ABANDONED EQUIPMENT IN THE X-326 | | BUILDING NOT COVERED BY NUCLEAR CRITICALITY SAFETY APPROVALS (NCSAs), A | | SEARCH PERFORMED IN THE X-705 & X-700 REVEALED ABANDONED EQUIPMENT THAT MAY | | NEED NCSAs. THE PLANT IS FOLLOWING IT'S PROCEDURE FOR ANOMALOUS NCSA | | CONDITIONS AND FURTHER EVALUATIONS ARE IN PROGRESS TO DETERMINE IF THIS | | ABANDONED EQUIPMENT MEETS THE FISSILE MATERIAL LIMITS. THE FISSILE MATERIAL | | LIMIT OF 15 GRAMS U235 BY PLANT PROCEDURES REQUIRES NCSAs." | | | | THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | | | | The licensee informed the NRC resident inspector. The Operations Officer | | notified the RDO (Gavula); EO (Surmeier); IRO (Congel). | | | | * * * UPDATE AT 1643 ON 1/20/99, BY HALCOMB, TAKEN BY WEAVER * * * | | | | DUE TO PROBLEMS CONCERNING ABANDONED EQUIPMENT IDENTIFIED IN THE X-326 | | BUILDING NOT COVERED BY AN NCSA, A PLANT WIDE SEARCH WAS INITIATED TO | | IDENTIFY ALL EQUIPMENT WHICH MAY MEET THE FISSILE MATERIAL LIMITS AND WOULD | | REQUIRE AN ACTIVE NCSA. THIS SEARCH HAS IDENTIFIED THAT THE X-344, X-333, | | AND THE X-330 BUILDINGS CONTAIN ABANDONED EQUIPMENT THAT WILL REQUIRE AN | | NCSA. ALL IDENTIFIED EQUIPMENT HAS BEEN BOUNDARIED OFF AND AN ANOMALOUS NCS | | CONDITION REPORT COMPLETED. | | | | THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | | | | The licensee informed the NRC resident inspector. The Operations Officer | | notified the RDO (Lanksbury); EO (BELL); IRO (Congel). | | | | ***Update on 01/21/99 at 1847 ET by Sissler taken by MacKinnon*** | | | | During ongoing plant search for abandoned equipment, additional equipment | | was discovered in the X-326 building which may meet the fissile material | | limits and would require an active NCSA. The identified equipment has been | | boundaried off and an anomalous NCS condition report completed. | | | | The NRC resident inspector was notified of this event by the certificate | | holder. The Operations Officer notified R3DO (Lanksbury) and EO (Bell) . | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35286 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 01/20/1999| | UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 13:00[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/20/1999| +------------------------------------------------+EVENT TIME: 11:22[CST]| | NRC NOTIFIED BY: BOB NORK |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNU |ROGER LANKSBURY R3 | |10 CFR SECTION: |ED GOODWIN NRR | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROSEMARY HOGAN IRO | | |CANUPP FEMA | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT - LOSS OF APPROXIMATELY 50% OF CONTROL ROOM ANNUNCIATORS | | | | "Loss of redundant ANNUNCIATOR Power Supplies has rendered a substantial | | number of safety related annunciators inoperable. This required a GSEP | | notification - Unusual Event, (MU-6 - Loss of Annunciators for >= 15 | | minutes). Backup indications are available and increased main control board | | monitoring has been implemented." | | | | The licensee has notified the NRC resident inspector. | | | | Event #35280 involved the same equipment. | | | | ***UPDATE on 01/21/99 at 1450 ET by Dave Kruck taken by MacKinnon**** | | | | Unusual Event terminated at 1311 CT. The annunciator system is functional. | | The root cause for the failure had not been completed at the time of this | | event update notification. Troubleshooting and repairs of the annunciator | | system are continuing. R3DO (Lanksbury), NRR EO (Dennig), & FEMA (Canupp) | | notified. | | | | The NRC resident inspector was been notified of this event update by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35288 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 01/21/1999| | UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 09:00[EST]| | RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 05:02[EST]| | NRC NOTIFIED BY: TODD STRAYER |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 | |10 CFR SECTION: | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY GAS TREATMENT SYSTEM MAY NOT HAVE PERFORMED INTENDED FUNCTION DUE TO | | DAMPER PROBLEM | | | | While preparing to replace the solenoid valve for Standby Gas Treatment | | (SBGT) System damper PO-20466 (reactor building supply to SBGT), the damper | | did not open when the control room hand switch was placed in the "open" | | position. However, the damper did open when the pneumatic supply to the | | solenoid valve was isolated. This damper opens automatically upon a SBGT | | system initiation to provide a flow path from the Unit 2 reactor building. | | The SBGT system would still have had a flow path from the Unit 2 refuel | | floor and equipment cell exhaust areas upon an initiation. In addition, the | | Unit 2 refuel floor currently has direct communication with the Unit 2 | | reactor building because the refuel floor equipment hatch is removed. | | | | The licensee reported this event because the failure of the damper to open | | could have prevented the SBGT system from performing its intended function. | | The licensee is performing calculations to determine whether the failure | | would have prevented the fulfillment of the safety function. The damper is | | currently open, and the pneumatic supply to the solenoid valve has been | | isolated. The licensee plans to continue activities to replace the solenoid | | valve. | | | | The NRC resident inspector has been informed of this notification by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35289 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/21/1999| | UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 09:50[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 06:07[CST]| | NRC NOTIFIED BY: TIM FRAWLEY |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DALE POWERS R4 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 100 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE/REACTOR TRIP DURING TROUBLESHOOTING | | | | "During troubleshooting activities to isolate the source of a ground on a | | 480VAC load center, the power source to the main turbine trip interlocks was | | inadvertently deenergized. As a result, the main turbine tripped, resulting | | in an automatic reactor trip - reactor power was above P9 (50% power). All | | equipment performed as expected; all control rods fully inserted, and the | | auxiliary feedwater system actuated automatically on low steam generator | | levels (expected to occur upon a reactor trip from high power levels)." | | | | The licensee also reported that several steam generator PORVs lifted | | following the trip; this is expected following a trip from this power level. | | The NRC resident inspector has been informed of this event by the licensee. | | | | ***Update on 01/21/99 at 1700 ET by Frawley taken by MacKinnon*** | | | | On investigation it was determined that no steam generator PORVs lifted | | following the reactor trip. | | R4DO (Dale Powers) notified. | | | | The NRC resident inspector will be notified of this update by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35290 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 01/21/1999| | UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 13:59[EST]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 12:30[CST]| | NRC NOTIFIED BY: DOUG SMITH |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 | |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 | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DETERMINED THAT CERTAIN AUXILIARY BUILDING DOORS WOULD NOT RELIEVE | | PRESSURE AS DESIGNED FOLLOWING A HIGH ENERGY LINE BREAK (HELB). | | | | "The Prairie Island HELB analysis assumes that certain doors open to | | mitigate the pressure and temperature response. A calculation to | | reconstitute blow out pressure of the doors in the vent path was unable to | | verify doors would perform their HELB assumed function of opening to | | mitigate auxiliary building pressures. Latch pins on the stationary side of | | the doors do not allow the doors to swing open when required by the HELB | | event. Preliminary results from the calculation indicate damage would occur | | to other safety related structures. The doors will be unlatched to allow | | this pressure release to occur bringing the plant within the analysis. | | Category 1 doors 134, 184, 133, and 182 were declared inoperable per TS | | 3.6.E.1." | | | | Both units will remain in the 24-hour TS LCO until the latch pins are | | removed. Hourly fire watches are assigned while the doors are unlatched. | | The licensee has long-term corrective actions under review. This condition | | was discovered during an on-going design review. | | | | The licensee informed the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35291 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 01/21/1999| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 14:00[EST]| | RXTYPE: [1] CE |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 10:10[CST]| | NRC NOTIFIED BY: DAVE BANNISTER |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: |DALE POWERS R4 | |10 CFR SECTION: |BOB DENNIG, NRR EO | |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 +------------------------------------------------------------------------------+ | 161kV incoming line declared inoperable. | | | | Report required by Technical Specification 2.7(2) c. as a result of | | declaring 161kV incoming line inoperable. Declaring 161kV inoperable | | renders both house service transformers T1A3 and T1A4 inoperable (feed vital | | onsite buses). 161kV is energized, and breakers 110 and 111 did not open, | | but cannot be brought back-in-house until lockout 86X/FT/161, which tripped, | | is reset. | | | | A contractor performing modification work in the Fort Calhoun Station | | switchyard was trenching, and the trencher caught a cable buried | | approximately 4 inches underground. This cable supplies 161kV fast transfer | | secondary potential transformer alarm circuit. | | | | All 4160 v buses successfully fast transferred to the onsite 22kV power | | source, and Abnormal Operating Procedure AOP-31, "All 4160V Buses fed From | | 22kV," was entered. | | | | A new cable is being run, and should be completely installed and tested by | | mid-afternoon, allowing transfer back to 161kV. A relay exists that might | | be able to be bypassed, which would allow 161kV to be brought back into the | | plant. | | | | All Emergency Diesel Generators are fully operable if needed and the non-Q | | Auxiliary Feedwater Pump is also fully operable. | | | | The NRC resident inspector has been notified of this event by the licensee. | | | | | | ****Update on 01/21/99 at 1602 ET by Bannister taken by MacKinnon**** | | | | | | The cable damaged in the Fort Calhoun switchyard has been replaced; the | | lockout relay, 86X/FT/161, has been reset; and the plant is now back in its | | normal electrical lineup with 161kV supplying both house service | | transformers T1A3 and T1A4 at 1440 CT. Technical Specification 2.7.(2) c. | | and Abnormal Operating Procedure APO-31 were exited. R4DO (D. Powers) & NRR | | EO (Dennig) notified. | | | | The NRC resident inspector was notified of this event update by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35292 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: COMMONWEALTH OF MASS |NOTIFICATION DATE: 01/21/1999| |LICENSEE: AMERSHAM |NOTIFICATION TIME: 14:06[EST]| | CITY: Burlington REGION: 1 |EVENT DATE: 01/21/1999| | COUNTY: STATE: MA |EVENT TIME: 11:00[EST]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 01/21/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |JOHN KINNEMAN R1 | | |FRED COMBS, NMSS EO | +------------------------------------------------+EASTON, NMSS | | NRC NOTIFIED BY: R. FAIRFULL | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | The following facsimile was received from Massachusetts: | | | | "The Radiation Control Program was notified at approximately 11:00 a.m. | | today that a package exceeding transportation limits had been received by | | AEA Technology (formerly Amersham Corp.) this morning. | | | | "The following facts were reported: | | | | 1. package was from their parent company in England | | 2. max reading was 820 mr/hour; Transportation Index of 18 | | 3. package consisted of outer packaging, with styrofoam intermediate insert, | | containing a lead pot | | 4. lead pot contained three cesium sealed sources - total of 9 curies | | 5. sources were not braced within the pot | | 6. readings varied with package orientation range of 540-820 mr/hr | | | | "The Radiation Control Program dispatched an inspector to the AEA Technology | | facility in Burlington Massachusetts this afternoon to investigate." | | | | See HOO log book for phone number. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35293 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/21/1999| | UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 16:51[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 15:45[EST]| | NRC NOTIFIED BY: UMPHREY |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: |JOHN KINNEMAN R1 | |10 CFR SECTION: | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PENETRATION ROOM VENTILATION SYSTEM MAY NOT PROVIDE ADEQUATE ACCIDENT | | MITIGATION WHILE MAINTENANCE IS PERFORMED ON SYSTEM. | | | | Penetration room ventilation system does not provide adequate protection to | | control the release of radioactive material and mitigate the consequences of | | an accident during the maintenance activities on the system due to system | | design. At the present time the licensee is investigating corrective | | actions to be taken to corrective this problem. | | | | The NRC resident inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35294 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: U.S. ARMY |NOTIFICATION DATE: 01/21/1999| |LICENSEE: U. S. ARMY |NOTIFICATION TIME: 16:57[EST]| | CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 01/21/1999| | COUNTY: STATE: IL |EVENT TIME: 14:00[CST]| |LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 01/21/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ROGER LANKSBURY R3 | | |MIKE BELL, NMSS EO | +------------------------------------------------+ | | NRC NOTIFIED BY: TIM MOHS | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: | | |10 CFR SECTION: | | |IBAD 30.50(b)(1)(ii) MATL >5X LOWEST LIMIT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | U S ARMY M137 telescope found to have tritium contamination. | | | | An M137 telescope was received at Fort Campbell, KY on 12/21/98. The | | telescope outer cover was removed on 01/13/99 at which time it was found | | that at least one tritium vial inside the telescope was broken. Wipes taken | | of the telescope and the surrounding area were sent to Rock Island Arsenal, | | IL to be counted for tritium activity. Today, (01/21/99), the results of | | the highest reading wipe was determined to be 6E06 DPM. Nobody at this time | | is known to have been contaminated, but bioassays of personnel who have come | | into contact with the telescope are being or will be taken. The telescope | | was shipped out of Galesburg, IL to Macomb, IL, then from Macomb, IL to | | Springfield, IL. The telescope then passed through Ft. Drum, NY, and on to | | Fort Campbell, KY. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35295 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/21/1999| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 16:59[EST]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 15:00[CST]| | NRC NOTIFIED BY: RICK ROBBINS |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 | |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 +------------------------------------------------------------------------------+ | Material for deionized water supply valve changed | | | | During storeroom valve stock review, the licensee discovered that valve | | materials for a deionized water supply line containment isolation valve had | | changed. Specifically, the diaphragm material had changed. The design | | value for the original material was 200� F at 200 psi. The new valve was | | rated at 150� F at 300 psi. This valve inside containment and another | | valve outside containment are normally closed during operation. Further | | evaluations are underway. | | | | Containment integrity has been verified by ensuring the valve outside | | containment is locked shut. | | | | The NRC resident inspector will be notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35296 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/21/1999| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 18:17[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 14:00[EST]| | NRC NOTIFIED BY: ED HYNE |LAST UPDATE DATE: 01/21/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 | |10 CFR SECTION: | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Emergency diesel generators, while running unloaded, may have failed to | | energize emergency buses in the event of a unit trip with the 115 kV supply | | out of service. | | | | A fire in the plant's hydrogen storage facility (event # 35275 on 01/14/99) | | resulted in a decision to remove the 115 kV reserve power supply from | | service to safely suppress the fire. The Emergency diesel generators were | | started per plant surveillance procedure ST-9D to demonstrate operability as | | required by Technical Specifications. A decision was made to allow the | | emergency diesel generators to run unloaded for a period of time with the | | 115 kV reserve power out of service but available. A later review of the | | emergency diesel generator protective scheme indicates the possibility that | | one or more of the emergency diesel generators may have failed to energize | | the emergency buses in the event of a unit trip with the 115 kV supply out | | of service. Further evaluation of this scenario is continuing to determine | | any necessary procedural changes. | | | | The NRC resident inspector has been notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35297 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/22/1999| | UNIT: [1] [2] [] STATE: CA |NOTIFICATION TIME: 00:59[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/21/1999| +------------------------------------------------+EVENT TIME: 18:25[PST]| | NRC NOTIFIED BY: JOSEPHINE BROWN |LAST UPDATE DATE: 01/22/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DALE POWERS R4 | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | Courtesy call regarding safeguards system degradation related to computer. | | Compensatory measures were taken immediately upon discovery. Refer to the | | HOO Log for additional details. The NRC resident inspector will be informed | | of this notification by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021