Event Notification Report for March 29, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/28/2001 - 03/29/2001 ** EVENT NUMBERS ** 37866 37867 37868 37869 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37866 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MISSISSIPPI DIV OF RAD HEALTH |NOTIFICATION DATE: 03/28/2001| |LICENSEE: BHATE ENGINEERING CORP. |NOTIFICATION TIME: 14:16[EST]| | CITY: SOUTH HAVEN REGION: 2 |EVENT DATE: 03/27/2001| | COUNTY: STATE: MS |EVENT TIME: 18:30[CST]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/28/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |EDWARD MCALPINE R2 | | |JOHN HICKEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: BOB GOFF | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING A RECOVERED TROXLER MOISTURE DENSITY GAUGE | | | | On 3/27/01 at 1830CST, the Mississippi Division of Rad Health was notified | | by Mississippi Emergency Management that the South Haven Fire Department had | | recovered a Troxler Moisture Density Gauge, Model 3411D, S/N 5155. The | | locks were still in place and the source was not exposed. The gauge is in | | custody awaiting notification of the licensee. | | | | HOO NOTE: The gauge was reported stolen from a construction site in | | Memphis, Tennessee, in 1994. See event #26822. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37867 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 03/28/2001| | UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 16:22[EST]| | RXTYPE: [1] GE-6 |EVENT DATE: 03/28/2001| +------------------------------------------------+EVENT TIME: 13:35[CST]| | NRC NOTIFIED BY: CHARLES BOTTEMILLER |LAST UPDATE DATE: 03/28/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DAVE LOVELESS R4 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FITNESS FOR DUTY REPORT INVOLVING A CONTRACT EMPLOYEE | | | | A contract employee was determined to be under the influence of an illegal | | drug during a random test. The employee's access to the plant has been | | terminated. | | | | The licensee informed the NRC resident inspector. Contact the Headquarters | | Operations Officer for additional details. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37868 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 03/28/2001| | UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 16:47[EST]| | RXTYPE: [1] W-3-LP |EVENT DATE: 03/28/2001| +------------------------------------------------+EVENT TIME: [EST]| | NRC NOTIFIED BY: R. J. FIELDS (via fax) |LAST UPDATE DATE: 03/28/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 | |10 CFR SECTION: |VERN HODGE NRR | |CCCC 21.21 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 +------------------------------------------------------------------------------+ | PART 21 REPORT INVOLVING REPLACEMENT SIEMENS ELECTRICAL BREAKER COMPONENTS | | NOT MEETING DESIGN SPECIFICATIONS | | | | "On March 26, 2001, Carolina Power & Light Company (CP&L) determined the | | following condition to be reportable in accordance with 10 CFR Part 21. | | | | "Description of Defect or Failure to Comply: | | | | "Siemens RLN/RLNF breaker cubicle Mechanism Operated Cells (MOC) were | | supplied to the Harris Nuclear Plant (HNP) as replacements which do not | | match design specifications. The parts procured were received with improper | | push bar length and configuration. The length and configuration are critical | | characteristics of this component. Improper length and configuration of the | | push bar on the MOC can result in the MOC not actuating upon breaker closure | | as per design. These parts were received commercial grade and dedicated | | onsite by CP&L for use in safety-related applications. CP&L's inspection of | | critical characteristics failed to identify that the component was not | | manufactured in accordance with the approved design specifications. | | Therefore, the defective MOCs were available in HNP stores for installation | | in safety-related applications. | | | | "HNP has identified a potential application where, had the subject MOC been | | installed, safety related functions designed to help mitigate the | | consequences of design basis events could have been lost. | | | | "A more detailed 30 day report will be submitted to the NRC in accordance | | with 10 CFR 21.21 by April 25, 2001." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37869 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/28/2001| | UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 20:50[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/28/2001| +------------------------------------------------+EVENT TIME: 18:53[EST]| | NRC NOTIFIED BY: ALAN WOLF |LAST UPDATE DATE: 03/28/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 | |10 CFR SECTION: | | |*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |*ESF 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A/R Y 100 Power Operation |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A GENERATOR TRIP FOR REASONS UNKNOWN | | | | At 1853EST on 3/28/01, Unit 1 experienced a main generator trip, turbine | | trip and reactor scram. The first out indication showed "power load | | unbalance." There were no maintenance or surveillance activities ongoing at | | the time. All control rods fully inserted. During the transient reactor | | vessel water level decreased to a minimum of -31 (Div I) and -37 (Div II) | | inches as shown on level recorders. Both HPCI and RCIC initiated but did | | not inject due to level increasing above the -35 inches setpoint required | | for the injection valves to open. The four low-low pressure setpoint (1120 | | psig) SRVs, i.e., "A", "C", "G" and "F", opened and reseated controlling | | reactor pressure. Subsequent to the investigation, it was determined that | | the "B" SRV also momentarily lifted based on a review of computer edits and | | an approximate 10 degree F increase on the temperature recorder. The | | highest recorded pressure was 1125 psig. Group II isolations occurred as | | expected including initiation of the Standby Gas Treatment System. All | | isolations have been reset and the affected equipment restored to standby | | status. | | | | Unit 1 is currently stable in hot shutdown with reactor pressure controlled | | using bypass valves to the main condenser. Condensate feed is in service | | supplying makeup with the reactor recirculation pumps at minimum speed. An | | event review team is responding to the site to determine the root cause. | | Three 230KV breakers, i.e., two generator output and one switchyard, opened | | during the transient. Unit 1 will remain shutdown pending the results of | | the investigation and completion of other scheduled maintenance. | | | | The licensee informed the NRC resident inspector and does not plan a press | | release at this time. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021