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