Event Notification Report for August 6, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/05/1999 - 08/06/1999
** EVENT NUMBERS **
35925 35992 35993 35994 35995
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|General Information or Other |Event Number: 35925 |
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| REP ORG: TVA FOSSIL POWER GROUP |NOTIFICATION DATE: 07/16/1999|
|LICENSEE: TVA FOSSIL POWER GROUP |NOTIFICATION TIME: 15:41[EDT]|
| CITY: CHATTANOOGA REGION: 2 |EVENT DATE: 07/11/1999|
| COUNTY: HAMILTON STATE: TN |EVENT TIME: 18:00[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 08/05/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANN BOLAND R2 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MARCIA COOPER | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| TENNESSEE VALLEY AUTHORITY (TVA) TESTING AND MAINTENANCE DIVISION LOCATED IN |
| CHATTANOOGA, TN, REPORTED THAT A HAND-HELD X-MET ANALYZER CONTAINING 40 |
| MILLICURIES OF IRON-55 AND 10 MILLICURIES OF CADMIUM-109 WAS INADVERTENTLY |
| LEFT UNATTENDED ON A LOADING DOCK BETWEEN APPROXIMATELY 1000-1100 EDT ON |
| 07/10/99 THROUGH 1800-2000 EDT ON 07/11/99. THERE WAS NO INDICATION OF |
| TAMPERING, CONTAMINATION, OR PERSONNEL OVEREXPOSURE INVOLVED. THIS DEVICE |
| IS USED FOR METAL IDENTIFICATION AND FALLS UNDER A GENERAL LICENSE. THIS |
| REPORT WAS CONSERVATIVELY MADE UNDER 10 CFR 20.2201(a). |
| |
| ******************** UPDATE AT 1627 ON 08/05/99 FROM MARCIA COOPER TO |
| TROCINE ******************** |
| |
| TVA Fossil Power Group is retracting this event notification based upon |
| telephone conversations between the General Manager of the Maintenance and |
| Testing Services Group (Marcia Cooper) and an NRC Region 2 representative |
| (Mark Lesser). The interpretation of the regulation was intended to require |
| reporting of missing licensed material. Although there was a temporary loss |
| of control of generally licensed material, the material had already been |
| recovered and was in the licensee's possession when the initial report was |
| made. |
| |
| The NRC operations officer notified the R2DO (Fredrickson) and NMSS EO |
| (Shankman). |
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|Power Reactor |Event Number: 35992 |
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| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 08/05/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 12:45[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 08/05/1999|
+------------------------------------------------+EVENT TIME: 09:47[EDT]|
| NRC NOTIFIED BY: JOHN HOUSE |LAST UPDATE DATE: 08/05/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY 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 Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM DUE TO A MAIN TURBINE TRIP ON MOISTURE SEPARATOR |
| HIGH LEVEL DUE TO A CONTROLLER MALFUNCTION |
| |
| At 0947, the unit automatically scrammed from 100% power due to a main |
| turbine trip. All control rods fully inserted. The main turbine trip |
| resulted from moisture separator high level due to a controller malfunction. |
| Following the reactor scram, reactor pressure vessel level decreased to less |
| than 12", and preliminary investigations have shown that all required |
| engineered safety feature (ESF) actuations functioned as expected. The ESF |
| actuations included a full reactor scram, the scram function of the |
| hydraulic control units, a reactor building isolation, a standby gas |
| treatment system initiation, a Group II (miscellaneous containment) |
| isolation, and a Group VI (reactor water cleanup) isolation. The licensee |
| is still investigating this event, but stated that there may have been a |
| momentary safety relief valve actuation on the main turbine trip. The |
| safety relief valve is closed at this time. |
| |
| The only problem following the scram was that the 'C' source range monitor |
| would not drive into the core. This was the result of a blown fuse, and it |
| has been rectified. |
| |
| The unit is currently stable in Hot Shutdown. Steam is being dumped to the |
| main condenser, and normal feedwater is supplying water to the reactor |
| vessel. The recirculation pumps are operating. There were no unusual |
| radiological releases during or after this event, and there were no safety |
| injections or emergency core cooling system actuations. There was no loss |
| of offsite power, and there were no emergency diesel generator actuations. |
| |
| The licensee notified the NRC resident inspector and plans to notify the |
| state tomorrow. |
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|Power Reactor |Event Number: 35993 |
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| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/05/1999|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 14:54[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/05/1999|
+------------------------------------------------+EVENT TIME: 12:50[CDT]|
| NRC NOTIFIED BY: BRAD ELLISON |LAST UPDATE DATE: 08/05/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK RING R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| INOPERABILITY OF BOTH CONTROL ROOM SPECIAL VENTILATION SYSTEM TRAINS DUE TO |
| A BROKEN DOOR LATCH MECHANISM |
| |
| At 1250 CDT, door 158 (the entry door to the 122 control room/chiller room) |
| was identified as having a broken latch mechanism, and the broken latch |
| resulted in a breech of the control room special ventilation system such |
| that both trains were considered to be inoperable. Door 158 was returned |
| to an operable status at 1335 CDT (45 minutes after discovery of the |
| problem) following maintenance repairs on the latch mechanism. Therefore, |
| the 1-hour limiting condition for operation action statement for Technical |
| Specification 3.13.a.1 was met. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 35994 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 08/05/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 15:32[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 08/05/1999|
+------------------------------------------------+EVENT TIME: 12:58[CDT]|
| NRC NOTIFIED BY: SHANE FERGUSON |LAST UPDATE DATE: 08/05/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM STETKA 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP DUE TO CLOSURE OF THE 'D' STEAM GENERATOR FEEDWATER |
| REGULATION VALVE |
| |
| At 1258 CDT, an automatic reactor trip occurred due to the failure of the |
| 'D' steam generator feedwater regulation valve. The valve failed closed, |
| and steam generator level decreased to the reactor trip setpoint of 23%. |
| The minimum steam generator level was approximately 20%. The unit also |
| received a feedwater isolation and auxiliary feedwater actuation (both |
| motor-driven and turbine-driven) due to the low-low steam generator levels. |
| The licensee stated that these were expected for this event. All control |
| rods fully inserted, and all safety equipment performed as designed. One |
| cooldown steam dump valve failed to fully close, and it was isolated to |
| allow automatic control of reactor coolant system (RCS) temperature using |
| the remaining cooldown valves. The licensee stated that there was not an |
| excessive cooldown and that RCS temperature decreased to 553 �F. None of |
| the primary safety relief valves lifted. Secondary (atmospheric) relief |
| valves lifted and reseated, and there has been no history of steam generator |
| tube leakage. There were no radiological releases. |
| |
| The licensee's investigation is currently in progress, and it is currently |
| believed that the valve failure may have been the result of an electronic |
| problem. The controller for this valve had a 0% output while the others had |
| 100% output. There were no maintenance or surveillance activities |
| associated with the 'D' steam generator feedwater regulation valve ongoing |
| at the time of the event. The licensee stated that there was nothing that |
| was unusual or not understood. |
| |
| The unit is currently stable in Hot Standby with the RCS at approximately |
| 559 �F and 2,235 psi, steam generator levels at approximately 40%, and |
| pressurizer level at 28%. Normal charging and letdown, pressurizer heaters |
| and sprays, and the reactor coolant pumps are being utilized for primary |
| system level, pressure, and transport control. Secondary steam is being |
| dumped to the main condenser, and auxiliary feedwater is supplying water to |
| the steam generators. Grid stability is good, and all normal power feeds |
| are available. |
| |
| The licensee notified the NRC resident inspector and the applicable state |
| and county agencies. |
| |
| ***************** UPDATE AT 1749 EDT ON 08/05/99 FROM SHANE FERGUSON TO |
| TROCINE ***************** |
| |
| The licensee plans to issue a media/press release. The cause of the problem |
| was identified to be a failed valve controller circuitry card. The unit may |
| be restarted as early as tonight between 2100 CDT and 2200 CDT. |
| |
| The licensee plans to notify the NRC resident inspector. The NRC operations |
| officer notified the R4DOs (Stetka and Pellet). |
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|Fuel Cycle Facility |Event Number: 35995 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/05/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:22[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/05/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:38[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/05/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MARK RING R3 |
| DOCKET: 0707002 |SUSAN SHANKMAN NMSS |
+------------------------------------------------+CHARLES MILLER IRO |
| NRC NOTIFIED BY: RON CRABTREE | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NOTIFICATION TO ANOTHER GOVERNMENT AGENCY (4-HOUR REPORT) |
| |
| The following text is a portion of a facsimile received from Portsmouth: |
| |
| "At 1738 hours on 08/05/99, it was determined that a Nuclear Criticality |
| Safety Approval (NCSA) requirement was violated in the X-705 West Annex |
| which is a Department of Energy (DOE) regulated area of the PORTS site. |
| This event was reportable to DOE as a loss of one (1) NCSA control. This |
| notification to another government agency is reportable to the NRC as a |
| 4-hour notification report." |
| |
| Portsmouth personnel notified the NRC resident inspector and the DOE site |
| representative. |
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