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Event Notification Report for October 25, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/24/2001 - 10/25/2001

                              ** EVENT NUMBERS **

38414  38416  38421  38422  38423  38424  38425  
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|General Information or Other                     |Event Number:   38414       |
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 10/22/2001|
|LICENSEE:  QTE GROUP, INC.                      |NOTIFICATION TIME: 12:00[EDT]|
|    CITY:  GARLAND                  REGION:  4  |EVENT DATE:        09/29/2001|
|  COUNTY:                            STATE:  TX |EVENT TIME:        08:30[CDT]|
|LICENSE#:  L05222                AGREEMENT:  Y  |LAST UPDATE DATE:  10/22/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JOHNSON      R4      |
|                                                |SUSAN FRANT          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS (via fax)      |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE                      |
|                                                                              |
| The following is a portion of a fax received from the Texas Department of    |
| Health:                                                                      |
|                                                                              |
| "On the morning of September 29, 2001, [a] QTE technician picked up Troxler  |
| Gauge [Model 3440] SN:30229 from office to perform test on a project in      |
| Garland at 8:30 a.m. On his way to project he realized that he forgot his    |
| wallet and returned home to pick it up.  After returning to his pickup (1998 |
| Chevy S-10 -  Silver), he noticed that the lock was cut and the gauge had    |
| been stolen (approximately 8:00 a.m.).  Source numbers are (CS-137:          |
| 750-4377) and (AM-241: 47-27208)."                                           |
|                                                                              |
| The licensee notified the City of Garland Police Department (Report Number   |
| R028859) and the Texas Department of Health (Texas Incident Number I-7816).  |
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|Power Reactor                                    |Event Number:   38416       |
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| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 10/22/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 18:48[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        10/22/2001|
+------------------------------------------------+EVENT TIME:        13:57[EDT]|
| NRC NOTIFIED BY:  MILLER                       |LAST UPDATE DATE:  10/24/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |WILLIAM BECKNER      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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A THROUGH-WALL LEAK AROUND 3 (THREE) CONTROL ROD DRIVE       
  |
| MECHANISM NOZZLES (REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK)     
      |
|                                                                              |
| On October 11 and 12, 2001, following shutdown for a scheduled refueling     |
| outage, Three Mile Island Unit 1 (TMI-1) performed a visual inspection of    |
| the Reactor Vessel (RV) Control Rod Drive Mechanism (CRDM) nozzles per NRC   |
| Bulletin 2001-01. The inspection revealed evidence of boric acid buildup     |
| around 12 CRDM nozzles.  No other CRDM nozzles showed similar boron buildup. |
| After the RV head was removed and placed on the storage stand, additional    |
| inspections were performed.  At approximately 1357 on October 22, 2001,      |
| Engineering evaluation of the visual inspection, Liquid Penetrant Test (PT)  |
| data and Ultrasonic Test (UT) data identified through-wall indications on    |
| three CRDM nozzles. This engineering evaluation concluded that the visual    |
| indications around CRDMs 44, 35, and 37 indicate a Reactor Coolant System    |
| (RCS) pressure boundary leak.  The inspection is not yet completed, thus     |
| additional CRDM through-wall indications may be identified. This condition   |
| is consistent with industry experience with Primary Water Stress Corrosion   |
| Cracking (PWSCC) in similar components that have been evaluated as part of   |
| the NRC Generic Letter 97-01 and NRC Bulletin 2001-01.  Additional nozzles   |
| may be examined by UT in accordance with TMl-1's response to NRC Bulletin    |
| 2001-01.  This condition did not pose a significant safety risk during plant |
| operation.  TMl-1 plans to perform CRDM nozzle repairs during the current    |
| refueling outage.  Since the condition resulted in leakage through the RCS   |
| pressure boundary, it is being reported as a non-emergency [8-hour] report   |
| in accordance with 10 CFR 50.72(b)(3) (ii)(A) and 50.73(a)(2)(ii) (A).       |
|                                                                              |
| The NRC resident inspector has been notified.                                |
|                                                                              |
| * * * UPDATED AT 1015 EDT ON 10/24/01 BY ADAM MILLER TO FANGIE JONES * * *   |
|                                                                              |
| Two additional CRDMs (29 and 64) indicate a RCS pressure boundary leak.      |
| This brings the total to 5 CRDM nozzles showing through-wall leaks.  The     |
| licensee notified the NRC Resident Inspector.                                |
|                                                                              |
| The R1DO (John Kinneman) and the NRR EO (William Beckner) have been          |
| informed.                                                                    |
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|General Information or Other                     |Event Number:   38421       |
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| REP ORG:  DRESSER-RAND                         |NOTIFICATION DATE: 10/24/2001|
|LICENSEE:  GIMPEL                               |NOTIFICATION TIME: 05:05[EDT]|
|    CITY:  WELLSVILLE               REGION:  1  |EVENT DATE:        10/22/2001|
|  COUNTY:                            STATE:  NY |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/24/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAWRENCE DOERFLEIN   R1      |
|                                                |EDWARD MCALPINE      R2      |
+------------------------------------------------+BRENT CLAYTON        R3      |
| NRC NOTIFIED BY:  GEORGE HERMANN               |WILLIAM JOHNSON      R4      |
|  HQ OPS OFFICER:  FANGIE JONES                 |VERN HODGE (FAX)     NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 10 CFR PART 21 REPORT CONCERNING TERRY TURBINE TRIP & THROTTLE VALVE
SCREW   |
| SPINDLE                                                                      |
|                                                                              |
| The following is from a facsimile report:                                    |
|                                                                              |
| DESCRIPTION OF DEFECT:                                                       |
|                                                                              |
| Material substitution of grade 1212 Steel in place of grade 1018 carbon      |
| steel specified by design.                                                   |
|                                                                              |
| ENGINEERING EVALUATION & RECOMMENDATIONS:                                    |
|                                                                              |
| Following the failure of an installed Trip/Throttle valve screw spindle on   |
| the Catawba unit #2 AFW Pump Turbine (Terry Turbine S/N 40096A or B) on May  |
| 25, 2000, the material of the failed screw was analyzed and found to be      |
| Grade 1212 steel. Gimpel gave verbal confirmation that the screw material    |
| was incorrect (Grade 1213 and 1215 steel) at the Terry Turbine Users Group   |
| meeting on July 18, 2001 Gimpel has traced the supplied material to a single |
| lot of approximately 50 original screw spindles manufactured in 1974, and    |
| has identified the originally affected Trip & Throttle valve serial numbers  |
| as 74-12201-01 to 74-12244-02, 78-13136-01, 78-13215-01, and 78-13091-01.    |
| Written confirmation of this defect and a listing of affected valves was     |
| received by Dresser-Rand 10/11/01.                                           |
|                                                                              |
| Following this incident, additional information was received indicating that |
| a screw spindle installed in Palo Verde Unit 1 was found cracked In 1992,    |
| and was determined to be grade 1213 steel.                                   |
|                                                                              |
| Dresser-Rand tested the material of a functional screw spindle removed from  |
| an in-house test valve (Gimpel serial number 74-12243) and determined the    |
| material was grade 1212.                                                     |
|                                                                              |
| It is unknown whether the material substitution was a contributing factor in |
| the failures of the screw spindles at these sites. The trip valves in        |
| question have been in operation for many years, and although the material    |
| used is less desirable in this application than the design specified         |
| material, the limited number of failures indicates that the immediate risk   |
| of continued operation is minimal. It is acknowledged however, that a        |
| substantial safety hazard may exist due to this defect in that failure of    |
| this component can result in steam isolation preventing the emergency        |
| feedwater turbine from performing its safety-related function.               |
|                                                                              |
| Recommendations:                                                             |
| 1) Units using Gimpel T&T valves in the serial number series listed above    |
| which may have the original Screw spindle installed should replace their     |
| screw spindles at the next maintenance opportunity. The original spindles    |
| should be destroyed.                                                         |
| 2) It is additionally recommended that any Gimpel screw spindles in-stock or |
| in-service which may have been manufactured in the 1974-75 timeframe be      |
| treated as suspect and be tested to confirm that the material is correct     |
| (Grade 1018 carbon steel).                                                   |
|                                                                              |
| A written Final Report will be submitted no later than 11/21/01.             |
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|Power Reactor                                    |Event Number:   38422       |
+------------------------------------------------------------------------------+
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| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 10/24/2001|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 13:41[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        10/24/2001|
+------------------------------------------------+EVENT TIME:        10:00[EDT]|
| NRC NOTIFIED BY:  RAWLS                        |LAST UPDATE DATE:  10/24/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R2 IRC TEAM MANAGER  R2      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ACTUATION OF THE EMERGENCY FEEDWATER SYSTEM                                  |
|                                                                              |
| At 1000 on October 24, 2001, Crystal River Unit 3 (CR-3) was in MODE 3       |
| withdrawing Safety Rod Group 2 in preparation for Reactor Startup following  |
| a refueling outage.  In-plant Auxiliary Steam loads were being supplied from |
| Crystal River Unit 1 (CR-1).  Auxiliary Steam (AS) loads are normally        |
| supplied from CR-1 or Crystal River Unit 2 (CR-2) (sister fossil units) when |
| Unit 3 is not operating at high power.  CR-2 was off-line at the time and    |
| CR-1 tripped, resulting in a complete loss of Auxiliary Steam (AS) to Unit   |
| 3.  Motive steam was lost for the running Main Feed Pump and Main Condenser  |
| vacuum lowered.  Both Once Thru Steam Generator (OTSG) levels lowered        |
| resulting in an Emergency Feedwater System (EFW) actuation on low OTSG       |
| level.  The OTSG levels were restored to normal by EFW.  OTSG levels         |
| remained on scale throughout the transient.  Safety Rod Group 2 was fully    |
| inserted and Reactor Startup preparations were suspended.  The AS header was |
| repressurized from the Main Steam System and Main Condenser vacuum was       |
| restored.  Reactor Coolant System (RCS) temperature and pressure are stable  |
| at normal hot standby values and plant startup will continue once AS is      |
| restored from CR-1.  This event was an event or condition that resulted in a |
| valid actuation of the Emergency Feedwater System and is thus reportable as  |
| an eight hour report.                                                        |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38423       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 10/24/2001|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 18:41[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/24/2001|
+------------------------------------------------+EVENT TIME:        17:40[CDT]|
| NRC NOTIFIED BY:  MATHEWS                      |LAST UPDATE DATE:  10/24/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| GREATER THAN 25% OF THE OFFSITE EMERGENCY SIRENS WERE OUT OF SERVICE    
    |
|                                                                              |
| At 1523 on 10/24/01 16 of 44 emergency sirens were determined to be          |
| inoperable for greater than one hour due to a storm causing power outages.   |
| At 1620 six of the original non-functioning sirens were returned to service, |
| leaving a total of ten sirens out of service which is less than 25% being    |
| out of service  The remaining out of service sirens are expected to be       |
| returned to service on 10/25/01 as power is restored to these areas.         |
|                                                                              |
| The NRC Resident Inspector and local agencies were notified.                 |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38424       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 10/24/2001|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 19:09[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/24/2001|
+------------------------------------------------+EVENT TIME:        16:25[CDT]|
| NRC NOTIFIED BY:  RODE                         |LAST UPDATE DATE:  10/24/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       63       Power Operation  |63       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PROCEDURE USED FOR INSTALLATION OF TEMPORARY FIRE SEALS WAS NOT IN         
 |
| COMPLIANCE WITH THE CALCULATION QUALIFYING THE TEMPORARY FIRE SEALS       
  |
|                                                                              |
| During an internal review of the fire protection program at Point Beach      |
| Nuclear Power Plant, it was determined that the procedure used for the       |
| installation of temporary fire seals was not in compliance with the          |
| calculation qualifying the temporary fire seals. The procedure called for 4  |
| inches of Kaowool while the calculation demonstrated the 5 inches would      |
| ensure adequate fire protection.                                             |
|                                                                              |
| Out of the 9 barriers that were identified, 4 of them are required to        |
| provide train separation for safe shut down equipment. Due to the identified |
| condition, these penetrations may not have adequately provided such          |
| separation as required by our safe shutdown analysis.                        |
|                                                                              |
| Immediate actions taken included:  1) Affected penetrations were identified  |
| and declared out of service. 2) Appropriate fire rounds were commenced. 3)   |
| Installed the required 5 inches of Kaowool in the identified barriers and    |
| returned the barriers back to service.                                       |
|                                                                              |
| Pending corrective actions:  Although the calculation determined 5 inches of |
| Kaowool provides an adequate fire barrier, engineering will perform an       |
| additional evaluation to determine if 4 inches of Kaowool would suffice.     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38425       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 10/25/2001|
|    UNIT:  [1] [] []                 STATE:  AL |NOTIFICATION TIME: 02:07[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/25/2001|
+------------------------------------------------+EVENT TIME:        00:25[CDT]|
| NRC NOTIFIED BY:  FUCICH                       |LAST UPDATE DATE:  10/25/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN MONNINGER       R2      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(3)(xii)    OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| WORKER OVERCOME BY HEAT TAKEN TO LOCAL MEDICAL FACILITY                      |
|                                                                              |
| The licensee evacuated a worker who was working in containment and was       |
| overcome by the heat.  The worker was transported using the utility's        |
| emergency vehicle.  There was a small area of contamination on the worker's  |
| neck which was decontaminated during the trip to the hospital.  The worker   |
| was not contaminated when admitted to the hospital.                          |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+
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