Event Notification Report for May 28, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/27/1999 - 05/28/1999 ** EVENT NUMBERS ** 35680 35771 35772 35773 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35680 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 05/05/1999| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 19:17[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 05/05/1999| +------------------------------------------------+EVENT TIME: 15:33[EDT]| | NRC NOTIFIED BY: DOUG GOMEZ |LAST UPDATE DATE: 05/27/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JAMES LINVILLE R1 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 97 Power Operation |94 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE POWER RUNBACK SIGNAL FROM REACTOR PROTECTION SYSTEM | | | | The unit received a runback signal from Overpower Delta T channels 3 and 4 | | for 1.2 sec, during which time turbine reference power decreased from 90.7% | | to 90.3%. Actual turbine load was manually reduced to lower reactor power | | to 94% for increased margin to the runback. I&C personnel are investigating | | why the signal actuated as there is no readily apparent reason. | | | | This report is required per the unit's procedures. | | | | The licensee plans to notify the NRC Resident Inspector and the Public | | Service Commission for the State of New York. | | | | * * * UPDATE 1049EDT ON 5/27/99 FROM KEVIN McLAUGHLIN TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS REPORT BASED ON THE FOLLOWING: | | | | "Rochester Gas and Electric (RG&E) is retracting this event notification. A | | turbine runback signal was listed in the unit's procedures as an RPS signal. | | Upon further review, a turbine runback is not an RPS signal, and was | | erroneously listed as such in the unit's procedures. The procedure has been | | revised to delete a turbine runback as an RPS signal. Therefore, the | | licensee has concluded that the event is not reportable. The NRC Resident | | Inspector has been notified of this retraction by the licensee." | | | | NOTIFIED R1DO(CONTE). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35771 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 05/27/1999| | UNIT: [1] [] [] STATE: AL |NOTIFICATION TIME: 11:06[EDT]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/27/1999| +------------------------------------------------+EVENT TIME: 08:56[CDT]| | NRC NOTIFIED BY: VAUDY HOLLEY |LAST UPDATE DATE: 05/27/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: |THOMAS DECKER R2 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(ii) RPS 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 ON 2 OUT OF 3 OVERTEMPERATURE DELTA-TEMPERATURE | | (OTdT). ALL RODS FULLY INSERTED INTO THE CORE. | | | | At 0854 CDT while swapping Main Feedwater Pump "1A" Main Feedwater Pump lube | | oil coolers "1A" Main Feedwater Pump (MFW P "1A")tripped on low lube oil | | pressure. Operators manually ramped back the Main Turbine to reduce reactor | | power due to the loss of MFW P "1A". The Manual Main Turbine runback caused | | both Pressurizer PORVs valves to open/close (open a few seconds) when | | reactor coolant pressure increased to 2310 psig. The reactor tripped on a 2 | | out of 3 Overtemperature Delta-Temperature trip signal at 0856 CDT (Manual | | Main Turbine reduction in power was faster than the control rods reduction | | in reactor power). All rods fully inserted into the core. Both Motor Driven | | Auxiliary Feedwater Pumps started due to low Steam Generator Water Levels | | (caused by the Main Turbine runback and the automatic reactor trip). | | Currently Steam Generator Water Levels are being maintained by the operating | | Motor Driven Auxiliary Feedwater pumps. No Code Safety valves on the | | Primary or the Secondary side of the plant opened. No Steam Generator | | Atmospheric Valves opened. Reactor Power level was between 77% to 82% | | (Main Generator Power was at approximately 500 Mwe ) when the automatic | | reactor trip occurred. The licensee initially entered EEP-0 (Safety | | Injection/Reactor Trip procedure) performed the first 4 steps then entered | | ESP-0.1 (Reactor Trip Response procedure) and after completing ESP-0.1 they | | entered Unit Operating Procedure. | | All Emergency Core Cooling Systems, Emergency Diesel Generators are | | available, if needed. Offsite electrical power is stable. | | | | The licensee is investigating why Main Feedwater Pump "1A" tripped on low | | lube oil pressure. | | | | The NRC Resident Inspector was notified of this event by the licensee. | | | | ***Update on 5/27/99 at 1352 EDT by Vaudy Holley taken by MacKinnon**** | | | | When the Pressurizer PORVs were opened it caused a reduction in the reactor | | pressure to drop low enough for the Overtemperature Delta-Temperature | | setpoints to be reached. This caused a reactor trip/turbine trip. | | R2DO (Tom Decker) notified. The NRC Resident Inspector was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Hospital |Event Number: 35772 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: WILLIAM BEAUMONT HOSPITAL |NOTIFICATION DATE: 05/27/1999| |LICENSEE: WILLIAM BEAUMONT HOSPITAL |NOTIFICATION TIME: 13:41[EDT]| | CITY: ROYAL OAK REGION: 3 |EVENT DATE: 05/26/1999| | COUNTY: STATE: MI |EVENT TIME: 14:30[EDT]| |LICENSE#: 21-01333-01 AGREEMENT: N |LAST UPDATE DATE: 05/27/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ROGER LANKSBURY R3 | | |FRED COMBS NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: CHERYL SCHULTZ, RSO | | | HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HOSPITAL DOSIMETER MEASURED A DOSE READING OF GREATER THAN 1000 RADS - | | | | AT 1430 ON 05/26/99, LYNN [LAST NAME UNKNOWN] EMPLOYED BY LANDAUER RADIATION | | BADGE DOSIMETRY COMPANY, GLENWOOD, IL, REPORTED TO CHERYL SCHULTZ, RADIATION | | SAFETY OFFICER (RSO), WILLIAM BEAUMONT HOSPITAL, ROYAL OAK, MI, THAT ONE OF | | BEAUMONT HOSPITAL'S RADIATION DOSIMETERS MEASURED A DOSE READING OF GREATER | | THAN 1000 RADS. THE RADIATION DOSIMETER IS A LUXEL ALUMINUM OXIDE FILMLESS | | RADIATION DOSIMETER THAT HAS BEEN USED IN THE INDUSTRY SINCE THE FALL OF | | 1998. THIS TYPE OF DOSIMETER HAS BEEN USED AT BEAUMONT HOSPITAL SINCE | | JANUARY 1999. THE HOSPITAL MEDICAL TECHNOLOGIST WHO USED THIS DOSIMETER | | WORKS IN A BLOOD BANK AND LAST USED A BLOOD IRRADIATOR IN APRIL 1999. THE | | IRRADIATOR CONTAINS A SELF CONTAINED SEALED 10,000 CURIE CESIUM-137 | | RADIATION SOURCE. | | | | THE HOSPITAL RSO STATED THAT THE IRRADIATOR IS FUNCTIONING PROPERLY AND THAT | | THE TECHNOLOGIST DID NOT RECEIVE THIS HIGH DOSE. THE RSO FURTHER STATED | | THAT HOSPITAL PERSONNEL HAVE NEVER RECEIVED GREATER THAN 0.06 MR/HR MAXIMUM | | DOSE RATE WITH THE IRRADIATOR SOURCE EXPOSED. THE RSO BELIEVES THAT THE | | DOSE READING IS INCORRECT OR THAT THE DOSIMETER SOMEHOW BECAME IRRADIATED. | | THE DOSIMETRY COMPANY REPRESENTATIVE STATED THAT THE DOSIMETER READINGS WERE | | OBTAINED TWICE AND THE DOSIMETER IS NOT DAMAGED. | | | | THE HOSPITAL RSO PLANS TO OBTAIN A BLOOD SAMPLE FROM THE TECHNOLOGIST AND | | HAVE IT ANALYZED ON 05/27/99. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35773 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/27/1999| | UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 15:33[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/27/1999| +------------------------------------------------+EVENT TIME: 13:45[CDT]| | NRC NOTIFIED BY: MIKE SCHAEFER |LAST UPDATE DATE: 05/27/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |THOMAS ANDREWS R4 | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - PHYSICAL SECURITY REPORT - | | | | DISCOVERY OF CRIMINAL INFORMATION INVOLVING A CONTRACTOR WHO WAS GRANTED | | UNESCORTED ACCESS TO THE PLANT. COMPENSATORY MEASURES WERE IMMEDIATELY | | TAKEN UPON DISCOVERY. THE LICENSEE PLANS TO INFORM THE NRC RESIDENT | | INSPECTOR. REFER TO THE NRC OPERATIONS OFFICER LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+
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