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Event Notification Report for October 24, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/23/2001 - 10/24/2001

                              ** EVENT NUMBERS **

38414  38417  38418  38419  38420  38421  
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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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|General Information or Other                     |Event Number:   38417       |
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| REP ORG:  COLORADO DEPT OF HEALTH              |NOTIFICATION DATE: 10/23/2001|
|LICENSEE:  CITY OF COLORADO SPRINGS             |NOTIFICATION TIME: 12:59[EDT]|
|    CITY:  COLORADO SPRINGS         REGION:  4  |EVENT DATE:        10/23/2001|
|  COUNTY:                            STATE:  CO |EVENT TIME:             [MDT]|
|LICENSE#:  48-01                 AGREEMENT:  Y  |LAST UPDATE DATE:  10/23/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JOHNSON      R4      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JACOBI by FAX                |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| THE CITY OF COLORADO SPRINGS REPORTED A MISSING Ni-63 RADIATION SOURCE    
  |
|                                                                              |
| The wastewater treatment plant has gas chromatography equipment that uses    |
| electron capture detectors containing 8-15 mCi Ni-63.  For as long as anyone |
| now present can remember, the instruments in use there have been made by     |
| Hewlett Packard.  There have been 4 detectors made by Varian in a box in     |
| storage on a shelf in a cabinet in the lab.  Those detector cells did not    |
| fit on the HP GCs.  The lab manager discovered another laboratory that       |
| wanted the detectors that were in storage.  They solicited and received a    |
| copy of that laboratories license to possess radioactive material (as well   |
| as the license for CJ Bruyn, a detector maintenance facility). The 4         |
| detectors were sent to C.J. Bruyn of Bellingham Washington, who upon         |
| receiving the detectors and opening the cases for cleaning reported that one |
| of them did not contain the radioactive source.                              |
|                                                                              |
| An exhaustive search of the lab, concentrating on the cabinet area where the |
| sources were stored revealed no hint of the source.  The emissions or Ni-63  |
| are of such energy that external readings with a survey instrument would     |
| never indicate the presence of such a source.  Areas of the laboratory have  |
| been wipe tested for contamination from the time that sources have been in   |
| use there, and no lost source has been so revealed.                          |
|                                                                              |
| The source housings for the Varian sources have not been opened at the       |
| Laboratory, to the best of anyone's knowledge. In the past, the HP sources   |
| were opened for cleaning and maintenance, but never the Varian sources.  No  |
| one now at the lab can remember using Varian GCs and so cannot remember that |
| one of those detectors did not work (possibly indicating a missing source).  |
|                                                                              |
| The only scenarios that make any sense is that either                        |
| 1. The detector cell was received without the radioactive source from the    |
| original vendor or a facility that cleaned it.                               |
| 2. The source inadvertently fell out of the detector cell when it was opened |
| at CJ Bruyn and was not detected. The individual involved at CJ Bruyn denies |
| this possibility.                                                            |
|                                                                              |
| Ni-63 is a beta emitter with 67 keV electron energy and approximately 100y   |
| half-life.  The range of the emissions in air is ~10 inches, if the source   |
| was in contact with an individuals skin the electrons would penetrate        |
| ~0.35mm.  A significant radiological hazard is hard to imagine unless the    |
| source was ingested, inhaled, or held against the skin for a protracted      |
| period.   It has been discussed with the department that ingesting Ni-63 is  |
| not even a hazard of significance.  Nickel is not absorbed by the body and   |
| the beta particles are absorbed by the fecal matter.                         |
|                                                                              |
| Modifying the procedures to avoid a future occurrence of a similar instance  |
| is not indicated due to the extremely unlikely probability.  We no longer    |
| have EC detectors that are in long-term storage and use the ones that we     |
| have on a regular rotation, so we will know if the source is not present.    |
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|Power Reactor                                    |Event Number:   38418       |
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| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 10/23/2001|
|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 14:54[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/23/2001|
+------------------------------------------------+EVENT TIME:             [CDT]|
| NRC NOTIFIED BY:  HAWKINS                      |LAST UPDATE DATE:  10/23/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R2 IRC TEAM MANAGER  R2      |
|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          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| THE EMERGENCY NOTIFICATION NETWORK WAS INOPERABLE                            |
|                                                                              |
| The licensee reported that their Emergency Notification Network(ENN) was     |
| declared inoperable due to an on site switching problem.  Three channel      |
| banks went down and did not automatically transfer to backup source.  The    |
| problem has been identified and was restored(test satisfactory) at 1324 CDT. |
| The problem with the automatic transfer is still being investigated.  The    |
| licensee uses the Southern Line System as a backup for the ENN.              |
|                                                                              |
| The NRC Resident inspector was notified.                                     |
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|Power Reactor                                    |Event Number:   38419       |
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| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 10/23/2001|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 14:57[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        10/23/2001|
+------------------------------------------------+EVENT TIME:        11:02[EDT]|
| NRC NOTIFIED BY:  CAMPBELL                     |LAST UPDATE DATE:  10/23/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R1 IRC TEAM MANAGER  R1      |
|10 CFR SECTION:                                 |GENE IMBRO           NRR     |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|RICHARD WESSMAN      IRO     |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR  SCRAMMED FROM 100% POWER DUE TO TURBINE VALVE FAST CLOSURE
SIGNAL   |
|                                                                              |
| Unit 2 was operating at 100% power when a Main Generator Lockout resulted in |
| a Reactor SCRAM from a Turbine Control Valve Fast Closure Signal.  Reactor   |
| Pressure peaked at 1125 psig causing 5 Safety Relief Valves to open, and an  |
| automatic ARI (Alternate Rod Insertion) initiation on high reactor pressure. |
| The SCRAM transient also caused an expected reactor low level condition of   |
| minus seven inches (-7 inches) resulting in PCIS (Primary Containment        |
| Isolation System) Group II and III Isolations and SBGTS (Standby Gas         |
| Treatment System) initiation.  All plant systems operated as expected with   |
| all rods being fully inserted and all relief valves fully reseating.         |
|                                                                              |
| The Unit 2 Reactor is shutdown, and cause of the Generator Lockout is being  |
| investigated.  Reactor level is 23 inches, and a controlled reactor cool     |
| down is in progress.                                                         |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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|Power Reactor                                    |Event Number:   38420       |
+------------------------------------------------------------------------------+
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| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 10/23/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 19:40[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        10/23/2001|
+------------------------------------------------+EVENT TIME:        17:12[CDT]|
| NRC NOTIFIED BY:  STOCKHAM                     |LAST UPDATE DATE:  10/23/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       98       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT HAD A REACTOR SCRAM FROM 98% POWER DUE TO A GROUP 1
ISOLATION      |
|                                                                              |
| The group 1 MSIV isolation instrumentation was bumped in the plant causing   |
| an inadvertent group 1 isolation which resulted in a reactor scram.  Group 2 |
| and 3 isolations also occurred on low reactor level (+9") during the reactor |
| scram.  The low-low set controlled reactor pressure while the MSIV's were    |
| closed.  The "H" SRV cycled approximately 6 times and fully reseated.  All   |
| rods fully inserted and no ECCS actuation occurred.                          |
|                                                                              |
| The NRC Resident Inspector, the state, and local agencies were notified.     |
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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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