Event Notification Report for November 1, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/31/2001 - 11/01/2001 ** EVENT NUMBERS ** 38385 38441 38447 38448 38450 38451 38452 . !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38385 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 10/14/2001| | UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 12:14[EDT]| | RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 10/14/2001| +------------------------------------------------+EVENT TIME: 01:59[PDT]| | NRC NOTIFIED BY: KUNDSON |LAST UPDATE DATE: 10/31/2001| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL R4 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N N 0 Hot Standby |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE REACTOR COOLANT SYSTEM LEAKAGE | | | | During an inspection, while the plant was in shutdown mode 3, a dry white | | residue was discovered on a loop 2 hot leg spare thermowell plug. Being | | conservative they looked at this condition as a possible RCS pressure | | boundary leakage while in an operating mode. However, there was no active | | leak from the spare thermowell plug. The plant has 36 hours to be in mode | | 5. They will determine the type of repair work necessary to remedy the | | problem. | | | | The NRC Resident Inspector was notified. | | | | * * * RETRACTION 1623 10/31/2001 FROM RODRIGUEZ TAKEN BY STRANSKY * * * | | | | "On October 14, 2001, at 0914 PDT, Southern California Edison (SCE) made a | | 4-hour telephone notification in accordance with 10CFR50.72(b)(2)(i) for the | | initiation of a nuclear plant shutdown required by Technical Specification | | (TS). The purpose of this call is to retract that notification. | | | | "On October 14 2001, Unit 2 was being shutdown to Mode 5 to begin secondary | | plant equipment repairs. While in Mode 3, plant personnel discovered a white | | powdery substance on an RCS thermowell and considered that this could be | | dried boric acid and evidence of an RCS boundary leak. SCE logged entry into | | TS 3.4.13, action 'B' to be in Mode 3 within 6 hours and Mode 5 within 36 | | hours after discovery of RCS pressure boundary leakage. Even though the | | plant was shutdown and on its way to mode 5, because TS 3.4.13, action 'B' | | also required a reduction in plant mode, SCE conservatively considered this | | to be a 'shutdown required by the TS and made the phone report to the NRC in | | accordance with 10CFR50.72(b)(2)(I) | | | | "To investigate this finding, SCE: | | 1. Removed the thermowell threaded plug and the threads were found clean and | | dry with no evidence of an RCS pressure boundary leak. | | 2. Inspected the thermowell with a fiber-optic scope and found it clean and | | dry with no evidence of an RCS pressure boundary leak, | | 3. Inspected the thermowell-to-nozlle weld and found no indications (i.e., | | weld cracks or defects) present. | | 4. Analyzed the white powder and concluded it was not boric acid crystals. | | | | "Based on this evidence, SCE concluded that an RCS pressure boundary leak | | did not exist. Therefore, entry into TS 3.4.13, action 'B' was not required | | and a phone-report to the NRC for 'initiation of a plant shutdown required | | by the TS' was not required and is now being retracted. | | | | "At the time of the initial report Unit 2 was shutdown in mode 3, and Unit 3 | | was operating at about 100 percent power. The NRC Resident Inspectors will | | be notified of this occurrence and will be provided with a copy of this | | report." | | | | HOO Notified R4DO (Spitzberg). | +------------------------------------------------------------------------------+ . !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38441 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 10/30/2001| | UNIT: [1] [2] [] STATE: TN |NOTIFICATION TIME: 09:30[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/30/2001| +------------------------------------------------+EVENT TIME: 08:50[EST]| | NRC NOTIFIED BY: ALLEY/HARRIS |LAST UPDATE DATE: 10/31/2001| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNUSUAL EVENT |R2 IRC TEAM MANAGER R2 | |10 CFR SECTION: |JOHN TAPPERT NRR | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |RENE ZAPATA FEMA | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling Shutdow|0 Refueling Shutdow| |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO AN UNPLANNED RADIOLOGICAL RELEASE, EMERGENCY | | ACTION LEVEL 7.2 (LIQUID EFFLUENT). | | | | "At 0850 on 10/30/2001 a Notification of Unusual Event (NOUE) was declared | | and terminated at 0910 on 10/30/2001 at Sequoyah Nuclear Plant due to an | | unplanned radiological release. At 0640 on 10/30/2001 count rate on | | 0-RM-90-212, the Station Discharge Rad Monitor, reached the alarm setpoint | | of 600 CPM. An initial Chem Lab sample taken at 0720 indicated no abnormal | | activity. A followup sample completed at 0802 confirmed activity in the | | Turbine Building Sump. The Chem Lab samples confirmed the validity of this | | alarm and the REP declaration requirements were met. At 0810 the release | | was terminated by isolating the station sump and realigning to the Low | | Volume Waste Treatment Pond. Readings on 0-RM-90-212 are slowly trending up | | at present 39000 CPM. Investigation is in progress to determine and correct | | the source. Detailed sample analysis are also in progress to identify the | | magnitude and nuclides involved in this release. Followup information will | | be provided when available." State and Local officials were notified of | | this event by the licensee. | | | | The NRC Resident Inspector was notified of this event by the licensee. | | | | * * * UPDATE 1627EST ON 10/31/01 FROM CALVIN FIELDS TO S. SANDIN * * * | | | | The licensee is retracting this report based on the following: | | | | "This is an update to the October 30, 2001, notification. Subsequent | | analysis show that the total activity in the TB Sump was less than 35% of | | the ODCM limit. No release limits were exceeded and, therefore, the NOUE | | criteria of 2 times the ODCM limits did not exist. In accordance with | | NUREG-1022, Rev. 2, Section 2.8, TVA is retracting the previous notification | | via this follow-up telephone call." | | | | The licensee informed the NRC Resident Inspector and will inform both state | | and local agencies. Notified R2IRC. | +------------------------------------------------------------------------------+ . +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38447 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/31/2001| | UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 14:55[EST]| | RXTYPE: [2] GE-4 |EVENT DATE: 10/30/2001| +------------------------------------------------+EVENT TIME: 19:00[EST]| | NRC NOTIFIED BY: D. COSEO |LAST UPDATE DATE: 10/31/2001| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT DUE TO VIOLATION OF LICENSE CONDITION | | | | "On 10/30/2001 at 1900 hours, during a walkdown of approximately 600 fire | | barrier penetrations which had been mistakenly excluded from the Fermi 2 | | fire barrier penetration seal inspection program, 11 penetrations were found | | to have no seal material installed. To date, over 350 of the approximately | | 600 fire barrier penetrations not included in the program have been | | inspected. The lack of seal material in these penetrations constitutes an | | inoperable 10 CFR 50, Appendix R fire rated barrier and is reportable under | | License Condition 2.F as a violation of License Condition 2.C (9), | | 'Modifications for Fire Protection.' The plant is currently shut down for | | refueling. Hourly fire watches have been established in the affected areas | | as required by the Technical Requirements Manual. Detroit Edison will report | | any further missing seals that are identified as part of this inspection." | | | | The NRC resident inspector has been informed of this report by the licensee. | +------------------------------------------------------------------------------+ . +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38448 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 10/31/2001| | UNIT: [] [2] [] STATE: MN |NOTIFICATION TIME: 16:59[EST]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/31/2001| +------------------------------------------------+EVENT TIME: 14:09[CST]| | NRC NOTIFIED BY: BODIN |LAST UPDATE DATE: 10/31/2001| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 M/R Y 100 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL TURBINE/REACTOR TRIP | | | | "Unit 2 Turbine Condenser Air Ejector was isolated for a potential steam | | leak. After the condenser air ejector was isolated, the A/B condenser | | differential reached 2.5" Hg vacuum. This is a procedural requirement to | | trip the turbine. Operators initiated a manual reactor/turbine trip at 1409. | | The main steam isolation valves were manually closed to ensure air ejector | | isolation. Steam generator (S/G) power operated relief valves (PORVs) are | | controlling RCS temperature at 547 degrees F. | | | | "Both auxiliary feedwater pumps auto started on low S/G levels. N35 NIS | | intermediate range detector failed to reach the source range setpoint. | | Source range detectors were manually reenergized." | | | | The NRC resident inspector has been informed of this event by the licensee. | | The licensee plans to issue a press release regarding this event. | +------------------------------------------------------------------------------+ . +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 38450 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: GEO ENGINEERING |NOTIFICATION DATE: 10/31/2001| |LICENSEE: GEO ENGINEERING |NOTIFICATION TIME: 18:06[EST]| | CITY: CAROLINA REGION: 2 |EVENT DATE: 10/31/2001| | COUNTY: STATE: PR |EVENT TIME: [EST]| |LICENSE#: 52-25266-01 AGREEMENT: N |LAST UPDATE DATE: 10/31/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |R2 IRC TEAM MANAGER R2 | | | | +------------------------------------------------+ | | NRC NOTIFIED BY: HEMANES | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED MOISTURE/DENSITY GAUGE | | | | A CPN model MC-1 moisture/density gauge (S/N M15076270) was damaged when it | | was run over. The source rod was not exposed at the time of the event. The | | Puerto Rico Health Department responded to the scene and surveyed the gauge, | | but found no evidence of contamination. The gauge has been secured pending | | further action by the licensee. | | | | The licensee has contacted an NRC inspector in Puerto Rico, who is going to | | respond to the scene tomorrow. | +------------------------------------------------------------------------------+ . +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38451 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/31/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:33[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/31/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:20[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/31/2001| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY R3 | | DOCKET: 0707002 | | +------------------------------------------------+ | | NRC NOTIFIED BY: RICK LARSON | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |OCBA 76.120(c)(2) SAFETY EQUIPMENT FAILUR| | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE WATER SYSTEM ISOLATION VALVE FOUND CLOSED | | | | "DURING PERFORMANCE OF PROCEDURE XP4-CU-UG6206 'HIGH PRESSURE FIRE WATER | | SYSTEM (HPFW) UNDERGROUND DISTRIBUTION LOOP TESTING,' UTILITY OPERATIONS AND | | FIRE FIGHTING PERSONAL DISCOVERED A SECTIONAL ISOLATION VALVE, THAT WAS | | EXPECTED TO BE OPEN, WAS RESTRICTING FLOW TO THE PORTION OF THE LOOP BEING | | TESTED. THIS RESTRICTION IN THE LOOP CAUSED A PORTION OF THE HPFW SPRINKLER | | SYSTEM FOR THE X-326 BUILDING TO FAIL TO PERFORM ITS INTENDED SAFETY | | FUNCTION (FIRE SUPPRESSION). UPON IDENTIFYING THE PROBLEM THE FIRE | | DEPARTMENT NOTIFIED THE PLANT SHIFT SUPERINTENDENT (PSS) WHO IMMEDIATELY | | DECLARED THE HPFW SPRINKLERS SYSTEMS IN THE X-326 BUILDING INOPERABLE, AND | | DIRECTED THE REQUIRED TSR ACTIONS TO BE PERFORMED. UTILITY OPERATIONS | | PERSONNEL SECURED THE TEST AND REOPENED ALL SECTIONAL ISOLATION VALVES THAT | | WERE SHUT FOR THE TEST. AT 1345 HOURS HPFW WAS RESTORED TO THE ISOLATED | | PORTION OF THE LOOP. | | | | "ENTIRE EVOLUTION IS UNDER INVESTIGATION AT THIS TIME." | | | | The NRC resident inspector has been informed of this notification. | +------------------------------------------------------------------------------+ . +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38452 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 10/31/2001| | UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 18:44[EST]| | RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 10/31/2001| +------------------------------------------------+EVENT TIME: 14:23[CST]| | NRC NOTIFIED BY: KEITH TABER |LAST UPDATE DATE: 10/31/2001| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY 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 HYDRAULIC OIL SPILL | | | | "At 1423 hours CST Wednesday October 31, 2001 LaSalle control room received | | notification of an oil sheen at the Illinois River intake structure for | | LaSalle County Nuclear Stations Unit 1 and 2. Station procedures and the | | Spill Prevention Control and Counter Measures Plan was entered and the | | station Environmental Specialist and HAZMAT qualified personnel were | | dispatched to the scene. | | | | The Environmental Specialist notified the Main Control room that hydraulic | | fluid from the River intake structure equipment had leaked into the | | screenhouse inlet and due to a gap between in the floating boom and the | | concrete structure some hydraulic fluid had been released to the Illinois | | River. Current estimate is that approximately 5 gals of hydraulic fluid | | entered the inlet and approximately 100 milliliters was released into the | | Illinois River. Per the Exelon Reportability Manual ENV 3.19, and 40 CFR | | 110.10 Discharge of Oil into or upon Navigable Waters or Adjoining | | Shorelines the release of oil into the Illinois River is reportable to the | | National Response Center and Illinois Emergency Management Agency (IEMA) | | with in 1 hour. The National Response Center was notified at 1448 CST and | | the Illinois Emergency Management Agency was notified at 1505 CST. Pursuant | | to Exelon Reportability Manual SAP 1.9, and 10 CFR 50.72(b)(2)(xi) | | notification to the NRC is required to be notified within 4 hours, this | | notification is being made to address this requirement. | | | | "Currently, the HAZMAT team is at the scene and the oil release to the river | | has been stopped. Cleanup efforts are underway using oil booms and oil soak | | rags." | | | | The NRC resident inspector has been notified of this event. | +------------------------------------------------------------------------------+ .
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Page Last Reviewed/Updated Thursday, March 25, 2021