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
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|Power Reactor |Event Number: 39191 |
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+------------------------------------------------------------------------------+
| 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
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| 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. |
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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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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. |
+------------------------------------------------------------------------------+
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|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
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| 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. |
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|General Information or Other |Event Number: 39252 |
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| 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. |
+------------------------------------------------------------------------------+
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|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. |
+------------------------------------------------------------------------------+
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