Event Notification Report for July 23, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/20/2001 - 07/23/2001 ** EVENT NUMBERS ** 38037 38156 38157 38158 38159 38160 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38037 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/30/2001| | UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 17:20[EDT]| | RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/30/2001| +------------------------------------------------+EVENT TIME: 13:08[EDT]| | NRC NOTIFIED BY: PETRELLI |LAST UPDATE DATE: 07/20/2001| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ERIC REBER R1 | |10 CFR SECTION: | | |AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM WAS DECLARED INOPERABLE. | | | | The RCIC system was inoperable and available for planned maintenance and | | surveillance testing. During the planned surveillance testing, the | | mechanical overspeed mechanism for the RCIC turbine was discovered to be | | tripped with no overspeed trip testing having been performed. The | | overspeed trip mechanism may be degraded thereby constituting a condition | | that could have prevented the system from performing its function. RCIC is | | currently in standby and inoperable but available. Troubleshooting is in | | progress to determine the cause of the trip. This report may be retracted | | if the cause of the trip is determined to not affect the operability of the | | system. | | | | The NRC resident inspector was notified. | | | | ***** RETRACTION FROM THOMAS SCWALECK TO LEIGH TROCINE AT 1537 ON 07/20/01 | | ***** | | | | The following text is a portion of a facsimile received from the licensee: | | | | "On 5/30/01, during Reactor Core Isolation Cooling (RCIC) surveillance | | testing, the overspeed trip mechanism was discovered tripped with no | | overspeed testing having been performed. The overspeed trip mechanism was | | discovered tripped after a section of the surveillance testing that closed | | the trip/throttle valve and then cycled the trip solenoid several times. | | Nine Mile Point determined that, because of degraded engagement between the | | trip tappet nut and the head lever, the overspeed mechanism was susceptible | | to tripping during the cycling of the trip solenoid with the throttle valve | | tripped. Additionally, Nine Mile Point concluded that with the throttle | | valve latched open and RCIC aligned for operation, the overspeed trip | | mechanism would not have been susceptible to tripping. Therefore, the | | conditions that resulted in the tripping of the RCIC overspeed trip | | mechanism during the surveillance would not have prevented RCIC from | | performing its function. Based on the above, we are retracting the | | 50.72(b)(3)(v)(D) notification made on 5/30/01." | | | | The licensee notified the NRC resident inspector. The NRC operations | | officer notified the R1DO (Cook). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38156 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 07/20/2001| | UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 17:06[EDT]| | RXTYPE: [1] W-3-LP |EVENT DATE: 07/20/2001| +------------------------------------------------+EVENT TIME: 16:15[EDT]| | NRC NOTIFIED BY: CHARLES McKINNEY |LAST UPDATE DATE: 07/20/2001| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JAY HENSON R2 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING A SODIUM NITRITE CHEMICAL RELEASE | | | | The following text is a portion of a facsimile received from the licensee: | | | | "Notification is being made for exceeding the reportable quantity for | | release of sodium nitrite from a closed cycle cooling system to the outfalls | | discharging effluents from the V.C. Summer Nuclear Station to the | | environment (Lake Monticello). A drain valve was left open during | | maintenance on an instrument air compressor at approximately 1600 hours on | | 7/19/01. The drain line discharged effluent from a closed cycle coolant | | system containing sodium nitrite to the plant sumps for approximately 16.5 | | hours. Following isolation of the line, a review of flow rates and | | discharge paths found (completed at 1615 hours on 7/20/01) that | | approximately 16,000 gallons of effluent had been discharged from the plant | | to the environment." | | | | "It has been determined that approximately 135 pounds of sodium nitrite was | | discharged from the plant during this period. The reportable quantity for | | release is 100 pounds in a 24-hour period." | | | | "The hazard from sodium nitrite is from the pH level of 10.5. A daily check | | of pH at the plant outfall that received this discharge found the pH to be | | 9.0; therefore, there is no hazard to the environment from this release | | since this is the normal pH at this sample point. Plant personnel will | | continue to check the pH level of this discharge point each day." | | | | The licensee reported that they have not observed any environmental impacts | | and that there was no release of radioactive materials. | | | | The licensee notified the Environmental Protection Agency via the National | | Response Center at 1650 hours, and the National Response Center is | | documenting this event under report #573719. Because the site is located in | | an Agreement State, the licensee also notified the South Carolina Department | | of Health and Environmental Control at 1700 hours. In addition, the | | licensee notified the Local Planning Committee and the NRC resident | | inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38157 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 07/20/2001| | UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 21:57[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/20/2001| +------------------------------------------------+EVENT TIME: 14:50[EDT]| | NRC NOTIFIED BY: PETE ORPHANOS |LAST UPDATE DATE: 07/20/2001| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |WILLIAM COOK R1 | |10 CFR SECTION: | | |AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL FOR A LOSS OF REACTOR CORE ISOLATION COOLING | | (RCIC) REMOTE SHUTDOWN PANEL CAPABILITY DURING A POSTULATED MAIN CONTROL | | ROOM FIRE | | | | The following text is a portion of a facsimile received from the licensee: | | | | "A review of the Limerick fire safe shutdown analysis identified that during | | a fire in the control room, RCIC system operation from the remote shutdown | | panel (RSP) may not be available for safe shutdown of the unit. A | | postulated fire that results in a short of the Division 1 DC distribution | | system to ground causes a voltage control device to fail integral to [an | | RSP] instrument power supply inverter. This ground, potentially caused by a | | fire that affects Division 1 DC in the control room, results in failure of | | the fused instrument power supply to the RCIC RSP inverter." | | | | "The current fire safe shutdown analysis credits only one safe shutdown | | method as being analyzed as acceptable during a worst case main control room | | fire. This analysis requires RCIC to be operational from the RSP to support | | acceptability of the method. With this loss of RCIC RSP capability during a | | [main control room] fire, this event is reportable under | | 10CFR50.72(b)(3)(ii)." | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38158 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/21/2001| | UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 18:26[EDT]| | RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/21/2001| +------------------------------------------------+EVENT TIME: 15:28[CDT]| | NRC NOTIFIED BY: MARK OKOPNY |LAST UPDATE DATE: 07/21/2001| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |GARY SHEAR R3 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING A MINOR FISH KILL IN THE COOLING LAKE DUE TO | | INCREASING SUMMER TEMPERATURES | | | | The following text is a portion of a facsimile received from the licensee: | | | | "... this notification is being made pursuant to 10CFR50.72(b)(2)(xi) and | | Exelon Reportability Manual Section SAF 1.9. At 1528 CST on 07/21/01, it | | was discovered that a minor fish kill took place in LaSalle County Nuclear | | Station's cooling lake due to increased temperature. As summer air | | temperatures increase, the cooling lake temperature increased to 97�F, | | beyond the threshold at which point species susceptible to increased | | temperature begin to perish. It was communicated to the Illinois Department | | of Natural Resources that approximately 2,000 fish, mainly Gizzard Shad, had | | perished." | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38159 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 07/22/2001| | UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 15:15[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/22/2001| +------------------------------------------------+EVENT TIME: 13:30[CDT]| | NRC NOTIFIED BY: DAN COMISKY |LAST UPDATE DATE: 07/22/2001| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |GARY SHEAR R3 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING A MINOR FISH KILL | | | | This notification was being made pursuant to 10CFR50.72(b)(2)(xi), | | Braidwood Station Technical Specification Appendix B 4.1, and Exelon | | Reportability Manual Section SAF 1.9. At 1330 CDT on 07/22/01, it was | | communicated to the Illinois Department of Natural Resources that | | approximately 700 fish had perished in a minor fish kill in Braidwood | | Nuclear Station cooling lake due to increased temperature. As summer air | | temperature increased, the cooling lake temperature increased to above 97 | | degrees F, beyond the threshold at which point species susceptible increased | | temperature begin to perish. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38160 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 07/22/2001| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 19:08[EDT]| | RXTYPE: [1] GE-2 |EVENT DATE: 07/22/2001| +------------------------------------------------+EVENT TIME: 17:44[EDT]| | NRC NOTIFIED BY: MALCOLM BROWNE |LAST UPDATE DATE: 07/22/2001| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |WILLIAM COOK R1 | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CALLED IN AS A 24 HOUR NOTIFICATION | | | | A dead sea turtle, species unknown, was discovered in dilution intake | | structure bay # 5. The sea turtle has a gash in the back of the head which | | may have been caused by a boat propeller. National Marine Fisheries was | | notified. The licensee will notify the New Jersey Department of | | Environmental Protection. | | | | The licensee will contact the NRC resident inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021