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Event Notification Report for October 8, 2002



                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/07/2002 - 10/08/2002

                              ** EVENT NUMBERS **

39191  39237  39244  39246  39252  39253  39254  39255  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39191       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 09/14/2002|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 22:14[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        09/14/2002|
+------------------------------------------------+EVENT TIME:        20:12[EDT]|
| NRC NOTIFIED BY:  JOHNSTONE                    |LAST UPDATE DATE:  10/07/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MIKE ERNSTES         R2      |
|10 CFR SECTION:                                 |WILLIAM DEAN         NRR     |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BORIC ACID RESIDUE DISCOVERED DURING A BARE HEAD INSPECTION OF THE REACTOR   |
| VESSEL HEAD                                                                  |
|                                                                              |
| Two reactor vessel head penetrations on Unit 2 ( #21 and # 31) appear to     |
| have exhibited some amount of leakage during the past cycle of operation.    |
| This conclusion is based on the boric acid residue found at these locations  |
| during the bare head inspection.  This is a preliminary finding, further NDE |
| and Liquid Penetrant Inspections will be performed and a repair plan will be |
| developed during this outage.                                                |
|                                                                              |
| A inspection of the reactor vessel head was performed last year and no boric |
| acid residue was noted.                                                      |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
|                                                                              |
| * * * UPDATE ON 10/07/02 @ 1647 FROM JOHNSTONE TO GOULD * * *                |
|                                                                              |
| Preliminary results obtained during the fall refueling outage are as         |
| follows:                                                                     |
|                                                                              |
| A bare head visual inspection resulted in the identification of two          |
| penetrations that appeared to have exhibited some amount of leakage          |
| (penetrations 21 and 31 as previously reported), four additional             |
| penetrations are suspected of leaking, and several penetrations are masked   |
| with boric acid residue (due to a conoseal leak) that made their status      |
| indeterminate.  Inspection of 59 J-groove welds with eddy current (ET) was   |
| performed.  The ET inspections identified at least one indication of greater |
| than 6 mm in length in about 83% of the J-groove welds.  Additionally six    |
| J-groove welds, on thermocouple locations that could not be interrogated by  |
| ET, were examined by liquid penetrant test (PT) and found to have rejectable |
| (greater than 1/16'" linear) indications.  Three of the penetrations with    |
| indications discovered by PT had been previously repaired with an embedded   |
| flaw technique that now is believed to have been improperly executed.   All  |
| penetrations exhibiting leakage and suspected of leakage based on the bare   |
| head visual inspection had ET indications> 6 mm in length or rejectable PT   |
| indications.  One of the suspected leaking penetrations was one of three     |
| previously repaired.                                                         |
|                                                                              |
| Thirty five penetration inspections from the tube ID utilizing an open       |
| housing ET and ultrasonic inspection (UT) probe have been conducted.         |
| Numerous axial and circumferential ID and OD indications have been found.    |
| Most of the OD indications lie in the penetration tube between the toe and   |
| the root of the J-groove weld.   About 20% of the penetrations have tube OD  |
| circumferential "crack like" indications.  All are located between the root  |
| and the penetration side toe of the J-groove weld. Penetration (54) has two  |
| OD circumferential tube indications, the most limiting being about 80        |
| degrees and .226 inches deep (tube wall .62 inches). This penetration had no |
| leakage.   Penetration 54 is bounding for the inspections completed.         |
|                                                                              |
| A boat sample from one suspected leaking penetration was obtained and sent   |
| to a vendor lab for analysis.                                                |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39237       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39244       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 10/03/2002|
|LICENSEE:  JIM TAYLOR                           |NOTIFICATION TIME: 09:35[EDT]|
|    CITY:  STOCKTON                 REGION:  4  |EVENT DATE:        10/01/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:        09:30[PDT]|
|LICENSE#:  4900                  AGREEMENT:  Y  |LAST UPDATE DATE:  10/03/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KRISS KENNEDY        R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  R. GREGER                    |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING CPN GAUGE                                                            |
|                                                                              |
| The Licensee had a CPN moisture density gauge in a box of his ATV he uses    |
| for transport in the agriculture fields.  He stopped at a porta-potty on     |
| Duncan Road near Stockton, CA.  When he came out of the porta potty the      |
| gauge was missing.                                                           |
|                                                                              |
| The gauge is a CPN Hydroprobe model No. 503DR. Serial No: H36107151.  Gauge  |
| contains 10 millicuries of Cs-137 and 30 millicuries of Am-241.              |
|                                                                              |
| The Licensee will inform the local police of the missing gauge and he will   |
| run an offer of a reward in a local newspaper for the recovery of the gauge. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39246       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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:  10/07/2002|
|  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.                         |
|                                                                              |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 10/07/02 @ 1321 BY YUNK TO GOULD * * *                       |
|                                                                              |
| Correct time of press release to local media was 1045 CDT on 10/4/2002 not   |
| 0145 CDT.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39252       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ANVIL CORPORATION                    |NOTIFICATION DATE: 10/07/2002|
|LICENSEE:  ANVIL CORPORATION                    |NOTIFICATION TIME: 12:05[EDT]|
|    CITY:  BILLINGS                 REGION:  4  |EVENT DATE:        10/04/2002|
|  COUNTY:                            STATE:  MT |EVENT TIME:        10:30[MDT]|
|LICENSE#:  46-23236-03           AGREEMENT:  N  |LAST UPDATE DATE:  10/07/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JONES        R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TURNER                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INFORMATION REPORT INVOLVING A DAMAGED GUIDE TUBE INCIDENT                   |
|                                                                              |
| "[Radiographer #1 and Radiographer #2] received permission to perform x-ray  |
| on small branch connections in the tank dike of Tank 17 at the ExxonMobil    |
| refinery in Billings,  MT. They had an additional two-inch post stress       |
| x-ray. They x-rayed three small branch connections at seven minutes and one  |
| at three minutes. They then set up a two-inch spool by attaching it to a     |
| pipe support and made their first exposure.                                  |
|                                                                              |
| "The second exposure was set up on and made at 10:30am. When the exposure    |
| was complete [Radiographer #2] tried to crank the source into the shielded   |
| position. The crank would only turn three times before stopping.             |
| [Radiographer #1] explained later that the pipe support appeared to be set   |
| in the asphalt that it was sitting on. This turned [out] not to be the case. |
| The pipe support was only partly covered by asphalt and became dislodged     |
| during their second exposure.                                                |
|                                                                              |
| "[Radiographer #2] stated that the pipe stand fell approximately ten seconds |
| before the exposure was complete.                                            |
|                                                                              |
| "They then went into emergency procedures.                                   |
|                                                                              |
| "They increased their boundary sizes and contacted the RSO Kathy Turner.     |
|                                                                              |
| Amersham 660B                                                                |
| Camera No. B3125                                                             |
| Source No. 05416B                                                            |
| 51 Curies                                                                    |
|                                                                              |
| "[Radiographer #1] has been a radiographer for approximately four years.     |
| [Radiographer #2] has been a radiographer for three months."                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39253       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 10/07/2002|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 12:14[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/07/2002|
+------------------------------------------------+EVENT TIME:        09:35[CDT]|
| NRC NOTIFIED BY:  MIKE SMITH                   |LAST UPDATE DATE:  10/07/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JONES        R4      |
|10 CFR SECTION:                                 |                             |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOSTART OF EDG  FOLLOWING TRANSFER OF "1E" SWITCHGEAR TO ALTERNATE POWER   |
| SUPPLY                                                                       |
|                                                                              |
| "During Design Modification testing in the switchyard, an unplanned contact  |
| picked up which de-energized the train 'C' electrical switchgear and the     |
| '1E' switchgear to transfer to the Alternate Power (-2 bkr).  Core           |
| Alterations were in progress and were suspended."                            |
|                                                                              |
| Train "C" consists of four (4) electrical buses; 1A1, 1A2, 1A3 and 1A4.  The |
| -2 bkr transferred power from the 1EA1 to the 1EA2 bus which is energized    |
| from the XST1 transformer.  During the slow transfer, the operating Spent    |
| Fuel Pool (SFP) pump and RHR "B" train were de-energized.  There was no      |
| observed increase in SFP or appreciable increase in RCS temperatures.  RHR   |
| cooling was re-established in approximately eight (8) minutes.  Emergency    |
| Diesel Generator "1-02" autostarted on low voltage but did not supply power  |
| to the affected 1E buses.  The cause of the EDG autostart is under           |
| investigation.  Core Alterations are suspended pending completion of the     |
| investigation.                                                               |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39254       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 10/07/2002|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 12:38[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        10/07/2002|
+------------------------------------------------+EVENT TIME:        05:07[CDT]|
| NRC NOTIFIED BY:  HOGUE                        |LAST UPDATE DATE:  10/07/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JONES        R4      |
|10 CFR SECTION:                                 |CHRIS GRIMES         EO      |
|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        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BORIC ACID CRYSTALS DETECTED IN THE AREA OF THE CONTROL ROD DRIVE MECHANISM  |
| NOZZLE                                                                       |
|                                                                              |
| On October 7, 2002, following shutdown for a scheduled refueling outage,     |
| Arkansas Nuclear One (ANO) Unit 1 personnel performed a routine visual       |
| inspection of the Reactor Vessel (RV) head area per NRC Generic Letter       |
| 88-05.  This inspection revealed a small nodule of boric acid crystals in    |
| the area of Control Rod Drive Mechanism (CRDM) Nozzle #56.   The boric acid  |
| residue was detected on the down hill side of the nozzle (extending  180     |
| degrees In the nozzle annulus area), with a small nodule of boric acid at    |
| the most downhill point.  Prior to unit shutdown, on October 4. the total    |
| unidentified Reactor Coolant System (RCS) leak rate was determined to be     |
| significantly less than the 1 gpm allowed by Technical Specifications.  This |
| indication is consistent with industry experience associated with Primary    |
| Water Stress Corrosion Cracking (PWSCC) in similar components that has been  |
| evaluated as part of the NRC Generic Letter 97-01 response.  These cracks do |
| not pose a significant safety risk during plant operation, ANO plans to      |
| perform repairs during the current outage.  Since the visual inspection      |
| indicates leakage through the Reactor Coolant System pressure boundary, this |
| condition is being reported as a non-emergency eight-hour report in          |
| accordance with 10CFR50.72(b)(3)(II), degradation of a principal safety      |
| barrier.   Reactor vessel head inspection is continuing.   Any additional    |
| findings will be reported as an update to this notification.                 |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39255       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 10/07/2002|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 19:02[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/07/2002|
+------------------------------------------------+EVENT TIME:        17:15[EDT]|
| NRC NOTIFIED BY:  BROOKS                       |LAST UPDATE DATE:  10/07/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|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                                   
+------------------------------------------------------------------------------+
| PLANT FAILED THEIR INTEGRATED LEAKRATE TESTING                               |
|                                                                              |
| During the normal outage integrated leakrate testing, it was determined the  |
| total primary containment leakage rate is in excess of allowable leakage     |
| rate.  The calculated leakage rate is 216.55 scfh while the allowable        |
| leakage rate is 192.126 scfh.  Repair work on the valves has been            |
| initiated.                                                                   |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+