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
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|General Information or Other |Event Number: 37866 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37867 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37868 |
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| 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 | |
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| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| 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." |
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|Power Reactor |Event Number: 37869 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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