Event Notification Report for June 29, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/28/1999 - 06/29/1999 ** EVENT NUMBERS ** 35873 35874 35875 35876 35877 35878 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35873 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 06/27/1999| | UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 18:21[EDT]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/27/1999| +------------------------------------------------+EVENT TIME: 16:55[CDT]| | NRC NOTIFIED BY: VAUDY HOLLEY |LAST UPDATE DATE: 06/28/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |AL BELISLE R2 | |10 CFR SECTION: | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF OFFSITE COMMUNICATION SYSTEM - TONE ALERT RADIO | | | | After thunderstorms moved through the area of the plant, the licensee | | discovered that communications with the meteorological tower had been lost | | and the tone alert radio system was unavailable for greater than 15 minutes, | | part of the public communication (warning) system. | | | | Workers have been called in to investigate and repair the systems that have | | been lost. | | | | The licensee intends to notify the NRC Resident Inspector. | | | | * * * RETRACTION 1759 6/28/1999 FROM HAWKINS TAKEN BY STRANSKY * * * | | | | The licensee has determined that, although the primary power supply was | | lost, the backup power supply remained available; therefore, the tone alert | | radio system remained operable. The NRC resident inspector has been informed | | of this retraction by the licensee. Notified R2DO (Belisle). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35874 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/28/1999| | UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 03:55[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/28/1999| +------------------------------------------------+EVENT TIME: 03:00[EDT]| | NRC NOTIFIED BY: FRANK GORLEY |LAST UPDATE DATE: 06/28/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |AL BELISLE R2 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 100 Power Operation |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL | | | | The reactor automatically scrammed on low reactor vessel water level because | | of maintenance activities on the 'B' level keep fill system. Operators | | venting the keep fill system unintentionally vented the 'B' reference leg | | because the isolation valve between the two systems is apparently leaking. | | This venting caused level instruments using the 'B' reference leg to | | indicate high. The mismatch on level indicators caused the feed system to | | switch to the 'B' leg (which happened to be the failed system). This | | resulted in a decrease in feed flow and an actual decrease in reactor vessel | | water level. | | | | The decrease in reactor water level caused a reactor scram and High Pressure | | Coolant Injection (HPCI) initiation. Reactor Core Isolation Cooling (RCIC) | | did not initiate because it uses the 'B' reference leg as an input. | | All control rods fully inserted. The plant is stable in mode 3. Water | | level has been restored to the normal band and is being maintained by the | | feed system. The recirculating pumps are operating and no safety relief | | valves lifted. The lowest indicated level was -45". | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 35875 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/28/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:52[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/28/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:05[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/28/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN R3 | | DOCKET: 0707002 |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JEFF CASTLE | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 24 HOUR REPORT - CRANE STOPPED WHILE MOVING UF6 CYLINDER | | | | "On June 28, 1999 at approximately 0105, the X-343 south crane movement | | stopped completely and would not operate in any direction. The crane failed | | while a full liquid UF6 cylinder was being removed from autoclave #6. The | | crane brakes functioned as designed to prevent further movement of the UF6 | | cylinder. Following failure of the crane, the UF6 cylinder was suspended | | approximately two feet above the autoclave rollers. The exact cause of the | | crane movement failure is currently under investigation. The actuation of | | the crane brake is believed to have been necessary as a result of the | | opening of the thermal overloads. Pending further investigation of the cause | | for the brake actuation, the brake actuation is being considered a valid | | safety system actuation, and reportable in accordance with SAR Table 6.9, | | Criterion J2. As a precautionary measure, all liquid UF6 handling cranes | | have been tagged out of service pending the noted investigation. Support | | cradles have been positioned to support the suspended liquid UF6 cylinder." | | | | The NRC resident inspector has been informed of this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35876 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: WEST VIRGINIA UNIVERSITY |NOTIFICATION DATE: 06/28/1999| |LICENSEE: WEST VIRGINIA UNIVERSITY |NOTIFICATION TIME: 16:07[EDT]| | CITY: MORGANTOWN REGION: 2 |EVENT DATE: 06/25/1999| | COUNTY: STATE: WV |EVENT TIME: [EDT]| |LICENSE#: 47-23035-01 AGREEMENT: N |LAST UPDATE DATE: 06/28/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |AL BELISLE R2 | | |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEN DOUGLAS | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISSING SHIPMENT OF SULFUR-35 | | | | The licensee reported that 7 millicuries (mCi) of S-35 was missing from a | | shipment that arrived from ICN radiochemicals of California on the morning | | of 6/25/1999. Upon receipt, an individual inspected the package and reported | | that the shipment was present; however, during the investigation, he | | admitted that he may not have properly checked it. The loss was discovered | | when the package was opened in the laboratory, and the researcher discovered | | that the package contained only dry ice. | | | | The licensee has contacted the vendor, who indicated that the package went | | through a quality assurance inspection before shipment. The licensee's | | investigation is continuing. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35877 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 06/28/1999| | UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 19:29[EDT]| | RXTYPE: [2] GE-5 |EVENT DATE: 06/28/1999| +------------------------------------------------+EVENT TIME: 12:44[PDT]| | NRC NOTIFIED BY: BRIAN GARDES |LAST UPDATE DATE: 06/28/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LINDA SMITH R4 | |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N N 0 Cold Shutdown |0 Cold Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC CLOSURE OF MSIVs | | | | The licensee reported that the main steam isolation valves (MSIVs) | | automatically closed due to unknown reasons.; however, surveillance | | procedure ESP-RPS-X301 (Turbine Throttle Valves Channel Check) was being | | performed at the time. The unit is currently in Cold Shutdown for a fuel | | savings dispatch. | | | | The NRC resident inspector has been informed of this notification by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35878 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/28/1999| | UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 21:43[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/28/1999| +------------------------------------------------+EVENT TIME: 18:42[EDT]| | NRC NOTIFIED BY: DAVE JESTER |LAST UPDATE DATE: 06/28/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+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 | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 70 Power Operation |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR SCRAM DUE TO LOSS OF CONDENSER VACUUM | | | | At 1842 EDT, an automatic turbine trip/reactor scram occurred due to low | | condenser vacuum after all four circulating water pumps tripped. All control | | rods inserted following the scram, and the main steam isolation valves | | (MSIVs) remained open. No safety/relief valves lifted during the event. All | | systems functioned as expected with primary containment isolation system | | (PCIS) Group 2 (drywell floor and equipment drains), Group 6 (containment | | atmosphere cooling) and Group 8 (RHR shutdown cooling) isolations occurring | | due to low reactor vessel water level following the scram. The scram signal | | was reset at 1850 EDT. | | | | The unit is currently stable in Hot Shutdown. Reactor vessel pressure is | | being controlled using the main turbine bypass valves. The licensee has | | restored circulating water system flow to the main condenser. | | | | The licensee reported that the circulating water pumps tripped as a result | | of excessive differential pressure across the intake screens caused by a | | fish run in the intake canal. Operators had manually reduced power from | | 100% prior to the event in an attempt to stabilize condenser vacuum. Unit 1 | | experienced similar increased differential pressure in the circulating water | | system, but were able to stabilize condenser vacuum after reducing power to | | 70%. The fish run has subsided, and the licensee is currently returning Unit | | 1 to 100% or rated power. | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021