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Event Notification Report for October 7, 2002



                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/04/2002 - 10/07/2002

                              ** EVENT NUMBERS **

39237  39246  39247  39248  39249  39250  39251  

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|General Information or Other                     |Event Number:   39237       |
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| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 10/02/2002|
|LICENSEE:  CONSTRUCTION TESTING & ENG., INC.    |NOTIFICATION TIME: 10:19[EDT]|
|    CITY:  ESCONDIDO                REGION:  4  |EVENT DATE:        09/24/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:        06:00[PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/02/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KRISS KENNEDY        R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PEGGY L. MCKARNAN            |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| STOLEN AND RECOVERED CPN MOISTURE DENSITY GAUGE                              |
|                                                                              |
| "The user stated, he picked up gauge from the temporary storage location at  |
| approximately 4:30am.  He blocked, braced and locked the case to the bed of  |
| his truck and drove back to his residence to make some phone calls.  When he |
| came out to the truck between 7:30 and 8am the chain had been cut and the    |
| gauge was gone.  He contacted the police and the ARSO and also talked to     |
| neighbors to see if anyone had seen anything suspicious.  The ARSO contacted |
| the RHB at approximately 10:15am to report the theft.  At 11 am the ARSO     |
| contacted us to let us know that the gauge had been recovered.  The gauge    |
| was found in a park approximately 2 blocks from where the gauge was stolen.  |
| The gauge was still in the case and the gauge handle was still locked.  The  |
| gauge was returned to the office where a leak test was performed."           |
|                                                                              |
| Gauge stolen and recovered was a CPN Model # 501 gauge which contains 10     |
| millicuries of Cesium-137 and 50 millicuries of AM241:Be.  Leak test result  |
| (in microcuries) was less than 0.005.                                        |
|                                                                              |
| State of California incident number for this event is XCA 251.               |
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|Power Reactor                                    |Event Number:   39246       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 10/04/2002|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 12:26[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        10/04/2002|
+------------------------------------------------+EVENT TIME:        10:45[CDT]|
| NRC NOTIFIED BY:  DAVE DEES                    |LAST UPDATE DATE:  10/04/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |KRISS KENNEDY        R4      |
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO SMALL FIRE IN TURBINE BUILDING                   |
|                                                                              |
| "Press release issued to local media at 0145 CDT 10/4/2002.  Press release   |
| described response to an electrical component fire that occurred at 0650 CDT |
| 10/4/2002.  The fire occurred in a cathodic protection transformer located   |
| in the turbine building.  The plant fire brigade responded to the scene.     |
| Power to the component was secured which extinguished the fire.  Plant       |
| operation was not affected.  The fire was declared out at 0700 CDT           |
| 10/4/2002."                                                                  |
|                                                                              |
| The press release was issued to the local paper -  Coffey County Republican  |
| and local radio KSNP.  The New Strawn Fire Department was called, however,   |
| the fire was extinguished before they arrived.  The licensee informed        |
| state/local agencies and the NRC resident inspector.                         |
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+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39247       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  GENERAL ELECTRIC COMPANY             |NOTIFICATION DATE: 10/04/2002|
|LICENSEE:  GENERAL ELECTRIC COMPANY             |NOTIFICATION TIME: 12:35[EDT]|
|    CITY:  SAN JOSE                 REGION:  4  |EVENT DATE:        10/04/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/04/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KRISS KENNEDY        R4      |
|                                                |SONIA BURGESS        R3      |
+------------------------------------------------+VERN HODGE (via fax) NRR     |
| NRC NOTIFIED BY:  JASON S. POST (via fax)      |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FUEL SUPPORT SIDE ENTRY ORIFICE LOSS COEFFICIENT IN CORE MONITORING SYSTEM   |
| DATABANK                                                                     |
|                                                                              |
| "This letter provides notification of a Reportable Condition under 10CFR     |
| 21.21(d) for Clinton and Perry 1. The basis for this conclusion is the data  |
| used for the fuel support side entry orifice (SEO) loss coefficient in the   |
| core monitoring system supplied by GE Nuclear Energy (GE)/Global Nuclear     |
| Fuel (GNF). Other plants that have a similar geometry, but for which GE/GNF  |
| did not provide the core monitoring system (Grand Gulf and River Bend) have  |
| also been informed of this issue.                                            |
|                                                                              |
| "The core support structure in a BWR/6 affects the fuel support casting SEO  |
| loss coefficient. Bundles may be adjacent to zero, one, or two core support  |
| beams depending upon their location as illustrated in Figure 1. The SEO loss |
| coefficient depends upon the number of adjacent core support beams.          |
|                                                                              |
| "The core monitoring system in the affected plants uses an average SEO loss  |
| coefficient for all of the central bundles, and a separate average value for |
| all of the peripheral bundles. This was previously evaluated for GE/GNF 8x8  |
| fuel designs and found to be acceptable. Recent calculations have shown that |
| the Critical Power Ratio (CPR) response for newer GE/GNF fuel designs are    |
| more sensitive to the reduced flow in bundles that are adjacent to two core  |
| support beams (which have the highest loss coefficient). Thus, the core      |
| monitoring system over predicts CPR for these bundles, and thereby, may      |
| under predict the margin to the Operating Limit Minimum CPR (OLMCPR). The    |
| CPR over prediction is approximately 0.01 in CPR, which reaches the          |
| threshold for a reportable condition on a Technical Specification Safety     |
| Limit. In actual practice, plants maintain significantly more than 0.01 CPR  |
| margin to the OLMCPR, so MCPR Safety Limit protection is not threatened."    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39248       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 10/05/2002|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 00:30[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        10/04/2002|
+------------------------------------------------+EVENT TIME:        22:14[CDT]|
| NRC NOTIFIED BY:  WAYNE AHO                    |LAST UPDATE DATE:  10/05/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JONES        R4      |
|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     A/R        Y       42       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TURBINE TRIP CAUSED REACTOR TRIP DURING SHUTDOWN IN PREPARATION FOR          |
| REFUELING OUTAGE                                                             |
|                                                                              |
| "A power reduction was in progress for entry into refueling outage 1R17. A   |
| main turbine overspeed trip test was being conducted which resulted in a     |
| turbine trip which then caused a reactor trip on RPS".                       |
|                                                                              |
| All rods were automatically inserted into the core with no problems. The     |
| trip occurred from 42% reactor power. No safety systems were actuated and    |
| all plant systems functioned as designed.                                    |
|                                                                              |
| The Resident Inspector was notified.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39249       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 10/05/2002|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 14:16[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/05/2002|
+------------------------------------------------+EVENT TIME:        11:25[EDT]|
| NRC NOTIFIED BY:  BRAD BROWN                   |LAST UPDATE DATE:  10/05/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAY HENSON           R2      |
|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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO A FREON RELEASE IN THE TURBINE BUILDING          |
|                                                                              |
| "At 0210 today, 10/5/02, we had a failure of a seal on our mechanical        |
| refrigeration unit.  This resulted in 5,250 lbs of freon, R-12, being        |
| released to the environment.  This required reporting to Federal, State and  |
| Local agencies that a release of greater than 5,000 lbs had occurred in less |
| than 24 hours.  The release ended at 0454 today due to the contents had      |
| completely blown down.                                                       |
|                                                                              |
| -  The National Response Center was notified at 1125 today                   |
| -  The Virginia Emergency Services Operations Center was notified at 1130    |
| today                                                                        |
| -  The Virginia State Dept. of Environmental Quality and the Local Emergency |
| Planning Coordinator will be notified by the Virginia Emergency Services     |
| Operations Center.                                                           |
|                                                                              |
| "Due to these offsite notifications we are making this 4 hour report."       |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39250       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 10/06/2002|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 18:00[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/06/2002|
+------------------------------------------------+EVENT TIME:        11:30[EDT]|
| NRC NOTIFIED BY:  MITCH McCLUSKIE              |LAST UPDATE DATE:  10/06/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RCIC SYSTEM DECLARED INOPERABLE                                              |
|                                                                              |
| Following reactor core isolation cooling system injection check valve        |
| surveillance, the check valve apparently did not fully close.  This resulted |
| in high pump suction pressure trip which would have prevented further system |
| operation.  The licensee conservatively declared the RCIC system inoperable  |
| and entered Tech Spec LCO 3.5.G.2, a 14 day action statement.  Shortly       |
| afterwards the plant pressure was dropped to less than 150 psig as part of   |
| normal plant shutdown to refueling, this takes the plant out of the Tech     |
| Spec action statement as it no longer applies.  The licensee is conducting   |
| an investigation of the problem with RCIC injection check valve.  Repairs    |
| will be completed prior to plant restart.                                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector and the State of Vermont.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39251       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 10/06/2002|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 18:45[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/06/2002|
+------------------------------------------------+EVENT TIME:        16:50[CDT]|
| NRC NOTIFIED BY:  MARK VERBECK                 |LAST UPDATE DATE:  10/06/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JONES        R4      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 4-HOUR REPORT PURSUANT TO 10 CFR 50.72(b)(2) PER LICENSEE ADMINISTRATIVE     |
| REQUIREMENTS                                                                 |
|                                                                              |
| "Results of the steam generator eddy current testing of the hot leg top of   |
| the tube sheet rotating plus point coil program indicated that greater than  |
| 1% of the tubes are defective in Steam Generator #2.                         |
|                                                                              |
| "Technical Specification category C-3. 5.6.10."                              |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE 2326EDT ON 10/6/02 FROM DENNIS REDINGER TO S.SANDIN * * *       |
|                                                                              |
| The licensee is updating this report to include the following additional SG  |
| inspection findings for Steam Generators #3 and #4:                          |
|                                                                              |
| "Results of the steam generator eddy current testing of the hot leg top of   |
| the tube sheet rotating pancake plus point coil indicates that greater than  |
| 1% of the tubes are defective in CPSES Unit 1 Steam Generators # 3 and Steam |
| Generators # 4.                                                              |
|                                                                              |
| "CPSES Technical Specification states that, '[R]esults of steam generator    |
| tube inspections which fall into Category C-3 shall be reported to the       |
| Commission pursuant to 10 CFR 50.72(b)(2) within four hours of initial       |
| discovery, and in a report within 30 days and prior to resumption of plant   |
| operation.'                                                                  |
|                                                                              |
| "Note:                                                                       |
|                                                                              |
| "We understand that CPSES Technical Specification is conservative with       |
| respect to timing of reporting this condition; and that the current 10 CFR   |
| 50.72 requirements are eight hour notification. However, until the license   |
| amendment (which is in process) is issued, CPSES will continue to report     |
| this condition within four hours."                                           |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R4DO(Jones).     |
+------------------------------------------------------------------------------+