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Event Notification Report for June 17, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/14/2002 - 06/17/2002

                              ** EVENT NUMBERS **

38979  38985  38991  38992  38993  38995  

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|General Information or Other                     |Event Number:   38979       |
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| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE:
06/11/2002|
|LICENSEE:  THE BOEING COMPANY                   |NOTIFICATION TIME: 19:50[EDT]|
|    CITY:  ANAHEIM                  REGION:  4  |EVENT DATE:        06/11/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:  0065-30               AGREEMENT:  Y  |LAST UPDATE DATE:  06/11/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTHONY GODY         R4      |
|                                                |THOMAS ESSIG         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT GREGER                |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT FROM CA REGARDING POTENTIAL PERSONNEL
OVEREXPOSURE    |
|                                                                              |
| The California state radiation safety officer called in a potential 20.2202  |
| personnel overexposure incident that occurred at The Boeing Company in       |
| Anaheim, California.  The licensee utilizes irradiator facilities large      |
| enough for an individual to enter. The individual's dosimeter was read by    |
| the personnel monitoring vendor (i.e.,  Landauer) as 94 Rem DDE, 94 Rem LDE  |
| and 112 Rem SDE.  The dosimetry was worn during the period of April 1 to     |
| April 30, 2002.  The licensee commenced an investigation to determine the    |
| validity of the high and unexpected reading.  The licensee will conduct an   |
| interview with the individual and also the State indicated a blood test will |
| most likely be performed. The State indicated the badge received a "static"  |
| exposure, and it will probably turn out to be a dosimeter-only exposure.     |
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|General Information or Other                     |Event Number:   38985       |
+------------------------------------------------------------------------------+
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 06/12/2002|
|LICENSEE:  FURGO SOUTH INC.                     |NOTIFICATION TIME: 17:30[EDT]|
|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        06/12/2002|
|  COUNTY:  HARRIS                    STATE:  TX |EVENT TIME:        12:00[CDT]|
|LICENSE#:  L00058                AGREEMENT:  Y  |LAST UPDATE DATE:  06/12/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTHONY GODY         R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS (via fax)      |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE                      |
|                                                                              |
| "A technician was transporting a gauge that was chained, locked, and secured |
| on the back of a pickup truck. He stopped at a restaurant for a take out     |
| lunch. Upon returning to the truck, he noticed the gauge was missing. The    |
| chain was cut.                                                               |
| Some other items, including test equipment and a sand cone, were taken.      |
| Gauge: Troxler Model 3430, ser#26992 Sources: 8 mCi Cs-137 ser#750-171 [and] |
| 40 mCi Am-241 ser#47-23560."                                                 |
|                                                                              |
| The local police, Troxler Electronics and the TXDOT were informed.  Texas    |
| Incident No.:  I-7907                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38991       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 06/14/2002|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 07:14[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/14/2002|
+------------------------------------------------+EVENT TIME:        04:35[CDT]|
| NRC NOTIFIED BY:  KLAY KLIMPLE                 |LAST UPDATE DATE:  06/14/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY GODY         R4      |
|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 REACTOR TRIP FOLLOWING CLOSURE OF A FEEDWATER ISOLATION VALVE
DURING  |
| SURVEILLANCE TESTING                                                         |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 04:35 [CDT] on 06/14/2002, operators manually tripped the reactor        |
| following closure of feedwater isolation valve 2C during surveillance        |
| testing.  The cause of the feedwater isolation valve failure is unknown at   |
| this time.  Also, both source range nuclear instruments failed to energize   |
| following the reactor trip, but both extended range nuclear instruments are  |
| available.  The auxiliary feedwater system actuated as expected on steam     |
| generator low-low level."                                                    |
|                                                                              |
| "Did the rods fully insert?  yes                                             |
| Did steam bypass to the condenser or to atmosphere?  condenser               |
| Did any primary/secondary relief valves lift?  no                            |
| Any electrical bus transfer problems?  no                                    |
| State normal operating temperature and pressure (NOT/NOP)[:]  590 degrees    |
| 2235 psig                                                                    |
| Any significant TS LCOs entered?  no"                                        |
|                                                                              |
| The licensee stated that there was nothing unusual or misunderstood with the |
| exception of the cause of the feedwater isolation valve failure and the      |
| cause of the failure of both source range nuclear instruments to energize    |
| following the reactor trip.  All systems functioned as required with the     |
| same exceptions.                                                             |
|                                                                              |
| The licensee also stated that the unit is currently stable in Mode 3 (Hot    |
| Standby).  Normal charging and letdown, pressurizer heaters and sprays, and  |
| the reactor coolant pumps are currently being utilized for primary system    |
| level, pressure, and transport control.  Secondary steam is being dumped to  |
| the condenser, and auxiliary feedwater is supplying water to the steam       |
| generators.  Operators are in the process of transferring from auxiliary     |
| feedwater to main feedwater.  All engineered safety feature equipment and    |
| emergency core cooling systems are operable and available if needed.         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE ON 6/14/02 @ 2243 BY REDDIX TO GOULD * * *                      |
|                                                                              |
| Licensee reported that after further investigation it was determined that    |
| both source range instruments did energize as expected, however, after       |
| indicating some counts erratically, they decayed away to zero.  Both source  |
| range detectors are inoperable at this time.                                 |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Notified Reg 4 RDO(Gody)                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38992       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 06/14/2002|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 11:24[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        06/13/2002|
+------------------------------------------------+EVENT TIME:        11:30[EDT]|
| NRC NOTIFIED BY:  DOUG RICHARDSON              |LAST UPDATE DATE:  06/14/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |JOHN DAVIDSON        IAT     |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR REPORT ON LICENSE CONDITION 2F                                       |
|                                                                              |
| " At 1130 hours on 6/13/02 it was discovered that the Safety Relief Valve    |
| (SRV) Position Indication Channel for one of the SRVs controlled from the    |
| Remote Shutdown Panel was inoperable. The inoperability was due to both      |
| alarm card inhibit switches for associated acoustic monitoring channel being |
| found to be in the inhibit  position. These switches are normally in the     |
| "alarm"  position. With the switches in the "inhibit" position the SRV       |
| position indication from a high vibration condition would not provide an     |
| open position indication for the SRV in the Control Room or at the Remote    |
| Shutdown Panel. Immediate Action was to return the switches to the  alarm    |
| position and all other SRV acoustic monitoring switches were verified to be  |
| in the correct "alarm" position.                                             |
|                                                                              |
| "Technical Specification LCO 3.3.3.2 requires that the Remote Shutdown       |
| System Functions shall be OPERABLE. With this channel inoperable, Required   |
| Actions require restoration to OPERABLE status within 30 days OR placing the |
| Unit in Mode 3 within the following 12 hours. Since the potential exists     |
| that this condition has existed in excess of the 30-day requirement this     |
| event may be considered a Condition Prohibited by Technical Specifications.  |
|                                                                              |
| "This report is being made in accordance with Section 2F of Operating        |
| License NPF-69 for Nine-Mile Point Unit 2. Section 2F requires that the      |
| initial notification of a violation of any requirement contained in Section  |
| 2C to the Operating License (License Conditions) be reported to the NRC      |
| Operations Center via the Emergency Notification System within 24 hours with |
| written follow-up with 30 days. License Condition 2C requires that Nine Mile |
| Point Nuclear Station, LLC shall operate the facility in accordance with the |
| Technical Specifications."                                                   |
|                                                                              |
| The NRC Resident Inspector has been notified.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38993       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 06/14/2002|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 17:14[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/14/2002|
+------------------------------------------------+EVENT TIME:        14:43[EDT]|
| NRC NOTIFIED BY:  MAY                          |LAST UPDATE DATE:  06/14/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       88       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR MANUALLY TRIPPED FROM 88% POWER DUE TO LOSS OF THE EAST MAIN
FEED    |
| PUMP ON LOW CONDENSER VACUUM                                                 |
|                                                                              |
| At 1443 the unit one reactor was manually tripped from 88% reactor power due |
| to the loss of the East Main Feedwater pump on low condenser vacuum.  Loss   |
| of East Main Feedwater Pump Condenser Vacuum occurred during the start of    |
| #13 Main Circulating Water Pump.  It is believed that this was caused by     |
| high differential pressure across the feed pump condenser and it appeared    |
| that the circulating water pump transferred some debris from the forebay     |
| into the condenser resulting in the loss of condenser vacuum, but this       |
| incident is still under investigation.                                       |
|                                                                              |
| All rods fully inserted, no ECCS injection and no safety relief valves       |
| lifted.                                                                      |
|                                                                              |
| Plant is currently stable in Mode 3. All plant equipment functioned as       |
| designed. Event Investigation is currently in progress.                      |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38995       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 06/15/2002|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 14:54[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/15/2002|
+------------------------------------------------+EVENT TIME:        08:30[EDT]|
| NRC NOTIFIED BY:  WATTS                        |LAST UPDATE DATE:  06/15/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KERRY LANDIS         R2      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY QUESTIONED DUE TO FAILURE OF ALCOHOL TEST                   |
|                                                                              |
| COMPENSATORY MEASURES TAKEN                                                  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED                                          |
|                                                                              |
| Refer to HOO for additional details                                          |
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