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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  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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