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Event Notification Report for February 19, 2002

                         *** NOT FOR PUBLIC DISTRIBUTION ***
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/15/2002 - 02/19/2002

                              ** EVENT NUMBERS **

38518  38585  38602  38698  38699  38700  38701  38702  38703  38704  38705  38706 
38707  

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|Power Reactor                                    |Event Number:   38518       |
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| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/26/2001|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 13:37[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/26/2001|
+------------------------------------------------+EVENT TIME:        12:32[CST]|
| NRC NOTIFIED BY:  ROBERT ADAMS                 |LAST UPDATE DATE:  02/15/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
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| ERDS INOPERABLE DUE TO PLANNED OUTAGE OF THE PLANT PROCESS COMPUTER
SYSTEM   |
| (PPCS)                                                                       |
|                                                                              |
| AT 1232 CT, the Point Beach Nuclear Plant ERDS became inoperable as a result |
| of modifications to change out the plant process computer system (PPCS).     |
| This is a planned evolution.  ERDS will remain inoperable until              |
| approximately, December 18, 2001.                                            |
|                                                                              |
| This information was verbally provided to a representative of NRR during the |
| week of 10/15/2001.  The senior resident inspector has also been briefed on  |
| the modifications and schedule.  NMC to NRC letter (NRC 01-0080) dated       |
| 11/21/2001 stated we would be submitting this Non-Emergency report.          |
|                                                                              |
| ***** UPDATE FROM RICK ROBBINS TO LEIGH TROCINE AT 2006 EST ON 11/27/01      |
| *****                                                                        |
|                                                                              |
| The following additional information is a portion of a facsimile received    |
| from the licensee:                                                           |
|                                                                              |
| "As part of the PPCS modification, several inputs to the SPDS monitor were   |
| also made unavailable.  Any out-of-service indications on the SPDS can be    |
| obtained by control room control board indications."                         |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations center |
| notified the R3DO (Bruce Jorgensen).                                         |
|                                                                              |
| * * * UPDATE 1259EST ON 12/22/01 FROM RYAN RODE TO S. SANDIN * * *           |
|                                                                              |
| The licensee provided the following information as an update:                |
|                                                                              |
| "On 11/26/01 at 12:32, the PBNP ERDS and SPDS were declared out of service   |
| for the PPCS upgrade project.  EN #38518 indicated to the NRC that the       |
| systems would remain unavailable until approximately December 18, 2001.  Due |
| to reliability issues with the newly installed PPCS, that expected date has  |
| been delayed to approximately January 3, 2002."                              |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R3DO(Phillips).  |
|                                                                              |
| * * * UPDATE ON 01/03/02 @1430 BY MEYER TO GOULD * * *                       |
|                                                                              |
| During the installation of the new PPCS, issues were identified which need   |
| to be resolved to allow SPDS and ERDS to be placed back in service fully.    |
| Currently, the new PPCS is only partially operable.  Work is continuing on   |
| the new PPCS to allow full operability.  The current estimate for return to  |
| service of SPDS and ERDS is 01/19/02.  This date may need to be extended     |
| again due to parts availability.                                             |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Notified Reg 3 RDO(Shear)                                                    |
|                                                                              |
| * * * UPDATE ON 1/17/02 @ 1855 BY HARRSCH TO GOULD * * *                     |
|                                                                              |
| Update to 1/3/02 update (see below).  Work continues on the Plant Process    |
| Computer System (PPCS) to allow full operability. The Safety Parameter       |
| Display System (SPDS) is still out of service, however the Emergency         |
| Response Data System (ERDS) is now available. As mentioned in the 1/3/02     |
| update, parts availability has been a problem and the date for returning     |
| SPDS to service is now estimated to be 2/16/02.                              |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 3 RDO(Vegel) was informed                                                |
|                                                                              |
| ***UPDATE ON 2/15/02 @ 1323 EST BY ADAMS TO NORRIS                           |
|                                                                              |
| Update to 1/17/02 update.  Work continues on the Plant Process Computer      |
| System (PPCS) to allow full operability. The Safety Parameter Display System |
| (SPDS) is still out of service.  Due to parts availabilty, the date for      |
| returning SPDS to service is now estimated to be 3/09/02.                    |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 3 RDO(Vegel) was informed.                                               |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38585       |
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| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 12/19/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 19:12[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/19/2001|
+------------------------------------------------+EVENT TIME:        16:00[CST]|
| NRC NOTIFIED BY:  BRUCE SCHOENBACH             |LAST UPDATE DATE:  02/15/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GARY SANBORN         R4      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EVENT OR CONDITION THAT COULD HAVE PREVENTED FULFILLMENT OF A SAFETY    
    |
| FUNCTION                                                                     |
|                                                                              |
| "The Callaway Plant Final Safety Analysis-Site Addenda, Chapter 2.4          |
| specifies controls to ensure site drainage paths are maintained to prevent   |
| flooding of the safety related facilities during postulated design basis     |
| precipitation events. Controls are specifically established to ensure        |
| modifications to site grading and roadway elevations are evaluated to ensure |
| the Probable Maximum Precipitation (PMP) design basis is not adversely       |
| affected and the safety-related structures are protected from flooding.      |
|                                                                              |
| "During installation of highway barriers at the site perimeter on December   |
| 19, 2001, it was determined that the barrier installation had not been       |
| properly evaluated to ensure the PMP design basis was not adversely          |
| impacted.                                                                    |
|                                                                              |
| "It was concluded this event was reportable per 10 CFR 50.72(b)(3)(v)        |
| because the barrier configuration, in conjunction with PMP conditions could  |
| have prevented the fulfillment of the safety function of structures or       |
| systems due to flooding.                                                     |
|                                                                              |
| "Immediate actions have been initiated to remove the barriers, thus          |
| restoring site grading and road elevations. These actions are targeted for   |
| completion within the next twelve-hour shift. In addition, current weather   |
| conditions are clear, with no precipitation forecast for the next 24 hours.  |
|                                                                              |
| "The NRC Resident Inspector was notified of this event by the licensee."     |
|                                                                              |
| *** RETRACTION FROM PATRICK McKENNA TO LEIGH TROCINE RECEIVED AT 1650
EST ON |
| 02/15/02 ***                                                                 |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On December 19, 2001, Callaway Plant filed Event Notification 33585 to      |
| report that concrete security barriers had been installed along the Plant    |
| North perimeter and this installation had the potential to violate the       |
| Probable Maximum Precipitation (PMP) design basis analysis.  Calculations    |
| have since been performed to verify current drainage areas and slopes and    |
| the potential water surface elevations due to the concrete security          |
| barriers.  These calculations verify that the potential water surface        |
| elevations do not exceed the power block weir and, therefore, do not impact  |
| the Operability of the power block buildings."                               |
|                                                                              |
| "The Operability Determination is based on the FSAR-SA pg. 2.5-15, which     |
| states that the ponding elevation during the site PMP rainfall must be       |
| maintained less than elevation 840.5 MSL.  As shown in Calculation SPA-18,   |
| Addenda 4, the maximum water surface elevation is calculated at 839.4 MSL,   |
| an increase of 0.3 feet, and the plant was Operable with the security        |
| barriers installed.  Since these calculations prove that there was no        |
| Operability concern, Callaway Plant is retracting Event Notification         |
| 38585."                                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R4DO (Linda Smith).                                     |
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|Power Reactor                                    |Event Number:   38602       |
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| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 01/01/2002|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 10:08[EST]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        01/01/2002|
+------------------------------------------------+EVENT TIME:        09:19[EST]|
| NRC NOTIFIED BY:  BILL BANDHAUER               |LAST UPDATE DATE:  02/17/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANNE BOLAND          R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION DUE RESCUED SEA TURTLE                                  |
|                                                                              |
| EN #37902 started the biennial report period.                                |
|                                                                              |
| On January 1, 2002 at 0919, a rescued sea turtle was identified as a green   |
| sea turtle.  This is the 62nd rescue of a live sea turtle at Crystal River   |
| Unit 3 (CR-3) in this biennial period. Notification to the National Marine   |
| Fisheries Service and the Florida Fish and Wildlife Conservation Commission. |
|                                                                              |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| * * *  UPDATE ON 1/05/02 @ 1002 BY RAWLS TO GOULD  * * *                     |
|                                                                              |
| On January 5, 2002, at 0720, a rescued sea turtle was identified as a        |
| Loggerhead Sea Turtle. This is the 63rd rescue of a live sea turtle at       |
| Crystal River Unit 3 (CR3) in this biennial period.  This is reportable as a |
| 4-hour report under 10 CFR 50.72(b)(2)(xi) as this event is related to the   |
| protection of the environment for which a notification to other government   |
| agencies (National Marine Fisheries Service and Florida Fish and Wildlife    |
| Conservation Commission) has been or will be made.                           |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 2 RDO (Decker) was notified.                                             |
|                                                                              |
| * * * UPDATE ON 01/09/02 @ 1107 EST BY ANDY BARNES TAKEN BY MACKINNON * * *  |
|                                                                              |
| On January 9, 2002, at 0838, a rescued sea turtle was identified as a Kemp's |
| Ridley Sea Turtle. This is the 64th rescue of a live turtle at Crystal River |
| Unit 3 (CR-3) in this biennial period. This is reportable as a 4-hour 10 CFR |
| 50.72 (b)(2)(xi) as this event is related to the protection of the           |
| environment for which a notification to other government agencies (National  |
| Marine Fisheries Service and Florida Fish and Wildlife Conservation          |
| Commission) has been or will be made.                                        |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 2 (Brian Bonser) was notified.                                           |
|                                                                              |
| * * * UPDATE ON 02/17/02 at 0940 EST BY RICKY RAWLS TO FANGIE JONES * * *    |
|                                                                              |
| "On February 17, 2002 at 0820, a rescued injured sea turtle was identified   |
| as a Kemp's Ridley Sea Turtle. The injury will require transportation to     |
| Clearwater Marine Science Center or Florida Fish and Wildlife Conservation   |
| Refuge. The Injury appears to be from a boat propeller. This is the 65th     |
| rescue of a live sea turtle at Crystal River Unit 3 (CR-3) in this biennial  |
| period. This is Reportable as a 4-Hour Report under 10 CFR 50.72(b) (2) (xi) |
| as this event is related to the protection of the environment for which a    |
| notification to other government agencies (National Marine Fisheries Service |
| and Florida Fish and Wildlife Conservation Commission) has been or will be   |
| made. This Is an update to event 38602."                                     |
|                                                                              |
| The NRC Resident Inspector will be notified.  R2DO (Stephen Cahill) has been |
| notified.                                                                    |
+------------------------------------------------------------------------------+

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|Power Reactor                                    |Event Number:   38698       |
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| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 02/15/2002|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 05:36[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        02/15/2002|
+------------------------------------------------+EVENT TIME:        03:53[CST]|
| NRC NOTIFIED BY:  RANDY CADE                   |LAST UPDATE DATE:  02/15/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |JOSE CALVO           NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |STEINDURF            FEMA    |
|                                                |JOSEPH HOLONICH      IRO     |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCRETIONARY DECLARATION OF UNUSUAL EVENT DUE TO "INCREASED PLANT       
   |
| AWARENESS"                                                                   |
|                                                                              |
| During a dewatering evolution of the Spent Resin Storage Tank, some spent    |
| resin entered the tank vent header. This caused an elevated reading of 263   |
| mrem on a single area radiation monitor (RM-081). The licensee declared an   |
| Unusual Event in accordance with EAL 11.4, "Increased Plant Awareness."      |
| Additional personnel are being called in to the site to assist in devising a |
| plan to flush the resin from the affected piping. The licensee estimates     |
| that it will take two to three hours to complete this evolution. The NRC     |
| resident inspector and state and local government agencies have been         |
| informed of this event by the licensee.                                      |
|                                                                              |
| * * * UPDATE 1045 2/15/02 FROM LUIKENS TAKEN BY STRANSKY * * *               |
|                                                                              |
| The licensee has terminated the UE as of 0945 CST. The licensee has          |
| developed a plan to flush the resin from the inappropriate areas and will be |
| commencing the activity shortly. The affected areas have been properly       |
| surveyed and posted. The NRC resident inspector has been informed of this    |
| update. Notified R4DO (Smith), NRR (Koshy), FEMA (Zapata).                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38699       |
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                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
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| REP ORG:  ALABAMA RADIATION CONTROL            |NOTIFICATION DATE: 02/15/2002|
|LICENSEE:  McWane Cast Iron Pipe Company        |NOTIFICATION TIME: 13:53[EST]|
|    CITY:                           REGION:  2  |EVENT DATE:        02/14/2002|
|  COUNTY:                            STATE:  AL |EVENT TIME:        16:45[CST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  02/15/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |STEPHEN CAHILL       R2      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+JOHN HICKEY          NMSS    |
| NRC NOTIFIED BY:  DAVID TURBERVILLE            |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - DAMAGED FIXED GAUGE                                 |
|                                                                              |
| SUBJECT: Damage to Fixed Gauge Containing Radioactive Material.              |
|                                                                              |
| On February 14,2002 at 4:45 PM CDT, a representative of McWane Cast Iron     |
| Pipe Company notified the Agency that on February 13,2002, the burner on a   |
| cupola caused a partial melting of the shielding of a mounted Ohmart model   |
| A2104 gauge containing 4,500 millicuries of Cesium-137 to melt. McWane Cast  |
| Iron Pipe Company possesses and uses radioactive material under Alabama      |
| Specific License No. 507. A hole was burned in the side of the source holder |
| and approximately one quart of lead flowed to the floor. A consultant was    |
| hired and performed surveys and leak tests of the device. No excessive       |
| radiation levels were noted and the leak test results were within acceptable |
| limits. The gauge remains mounted and is isolated. The manufacturer's        |
| representative is scheduled to come to the facility on February 15, 2002 to  |
| replace the device. The incident did not cause any exposure of radiation     |
| above applicable limits.                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38700       |
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+------------------------------------------------------------------------------+
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 02/15/2002|
|LICENSEE:  APEX Geoscience, Inc                 |NOTIFICATION TIME: 14:25[EST]|
|    CITY:  Longview                 REGION:  4  |EVENT DATE:        02/14/2002|
|  COUNTY:                            STATE:  TX |EVENT TIME:        15:35[CST]|
|LICENSE#:  L04929-001            AGREEMENT:  Y  |LAST UPDATE DATE:  02/15/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+DON COOL             NMSS    |
| NRC NOTIFIED BY:  JAMES OGDEN                  |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - DAMAGED NUCLEAR DENSITY GAUGE                       |
|                                                                              |
| February 14, 2002 / 3:35 p.m.                                                |
|                                                                              |
| Hallsville, Texas (between Longview and Marshall, Texas along U.S. Highway   |
| 80, north of Interstate Highway 20) - Hallsville High School near small      |
| concession stand.                                                            |
|                                                                              |
| Damaged nuclear density gauge - Troxler Model 3430, Serial No 29993; Source  |
| Cs-137 Serial No. 7504631, activity 8 millicuries; Source Am-24 :Be Serial   |
| No. 47-26971, activity 20 millicuries. Last leak tested December 5, 2001.    |
|                                                                              |
| Texas Bureau of Radiation Control was notified of the incident at            |
| approximately 4 p.m. February 14, 2002. Troxler Electronic Labs has been     |
| contacted to leak test the damaged gauge and to arrange repair/disposal.     |
|                                                                              |
| Event description: The gauge operator was preparing to conduct density tests |
| when a dump truck passed. The operator prepared to drive the pin to provide  |
| a hole for the source rod. As he was performing this task he noticed that    |
| the truck was now backing toward him. He jumped  out of harms way  and       |
| immediately began banging on the side of the truck with his hammer near the  |
| tailgate to get the driver's attention. However, the driver was looking in   |
| his other mirror and talking on either a cell phone or radio.  The truck's   |
| rear dual wheels backed over the gauge. The driver then sensed he had hit    |
| something and immediately stopped the vehicle. The gauge's source rod was in |
| the up and locked position. After the impact the rod was bent but still      |
| intact. The gauge case was severely damage but the integral source retained  |
| it's structural integrity. The area was roped off. A radiation survey was    |
| performed, in place, on the damaged gauge.  A NDS Survey Meter Model ND      |
| 2000, Serial No 25207 obtained readings of 2.5 to 3.5 mRem/hour near at the  |
| surface of the damaged device.  After assessment, the gauge was removed from |
| the site and placed in its transport container in the company transport      |
| vehicle. The soil under the damaged gauge was removed to check for debris    |
| (none found) and surveyed with no measurable radiation detected. The gauge   |
| was transported to the Longview headquarters site and locked in a storage    |
| closet pending a leak test of the device by Troxler. Radiation levels at the |
| closet were consistent with those taken at the incident site. Arrangements   |
| for transportation and repair/disposal of the damaged gauge are pending with |
| the Troxler Office in Arlington, Texas.                                      |
|                                                                              |
|                                                                              |
| Transport vehicle description:   Not applicable. Gauge was in use. Gauge was |
| damaged by a loaded dump truck belonging to the  K.K. Mobbs Construction     |
| Company, Kilgore, Texas.  The vehicle was surveyed and released.             |
|                                                                              |
| Media attention: None known                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38701       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  LOUISIANA RADIATION PROTECTION DIV   |NOTIFICATION DATE:
02/15/2002|
|LICENSEE:  BACKER ATLAS                         |NOTIFICATION TIME: 15:10[EST]|
|    CITY:  HOUMA                    REGION:  4  |EVENT DATE:        02/14/2002|
|  COUNTY:                            STATE:  LA |EVENT TIME:             [CST]|
|LICENSE#:  LA-2187-L01           AGREEMENT:  Y  |LAST UPDATE DATE:  02/15/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SCOTT BLACKWELL              |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE NOTIFICATION OF LOST NEUTRON GENERATOR BETWEEN
HOUMA, LA AND |
| PEARLAND, TEXAS                                                              |
|                                                                              |
| The following is a portion of the facsimile received from the State of       |
| Louisiana:                                                                   |
|                                                                              |
| "Agreement State Agency:  Louisiana Department of Environmental Quality"     |
|                                                                              |
| "Event Report ID No:  LA020002"                                              |
|                                                                              |
| "License No.:   LA-2187-LO1"                                                 |
| "Licensee:   Baker Atlas"                                                    |
|                                                                              |
| "Event date and Time: January, 3-3 1, 2002"                                  |
|                                                                              |
| "Event Location:   Between Houma, LA and Pearland, TX"                       |
|                                                                              |
| "Event type:   Lost Neutron Generator"                                       |
|                                                                              |
| "Notifications:  Licensee notified State Police, Highway Maintenance, LA     |
| Department of Environmental Quality,                                         |
| and the State of Texas. Has not notified media yet."                         |
|                                                                              |
| "Event description:  Baker Atlas requested two Neutron Generator tools with  |
| 0.878 Ci of H-3 in sponge form in each tool from Pearland, TX. The tools are |
| shipped in four sections for each tool for a total of 8 sections. The night  |
| watchmen in Houma, LA recorded on January 3, 2002, that 8 sections were      |
| delivered and then placed in storage. On January 31, 2002, Pearland wanted   |
| the tools back. It was discovered that there were only 7 sections instead of |
| eight. The section that was missing contained the H-3. The RSO was notified  |
| of the lost source on February 14, 2002. The RSO notified the LA Department  |
| of Environmental Quality on February 14, 2002. The night watchmen was        |
| interviewed and said he thought there were 8 sections delivered."            |
|                                                                              |
| "Transport vehicle description:  Flatbed truck (Hot Shot Transport           |
| Company)"                                                                    |
|                                                                              |
| "Media attention:  Media not notified."                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38702       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 02/15/2002|
|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 20:15[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/15/2002|
+------------------------------------------------+EVENT TIME:        18:15[EST]|
| NRC NOTIFIED BY:  STEVE SAUER                  |LAST UPDATE DATE:  02/15/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES TRAPP          R1      |
|10 CFR SECTION:                                 |JOSE CALVO           NRR     |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       77       Power Operation  |77       Power Operation  |
|2     N          Y       78       Power Operation  |78       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A NON-CONSERVATIVE LO-LO LEVEL TRIP SETPOINT DUE TO A          
|
| DIFFERENTIAL PRESSURE PHENOMENA THAT CAUSES STEAM GENERATOR
NARROW RANGE     |
| LEVEL CHANNELS TO READ HIGHER THAN ACTUAL WATER LEVEL AT HIGH STEAM
FLOWS    |
|                                                                              |
| "Based on the review of [Operating Experience (OE)] 13294 from Diablo Canyon |
| regarding unexpected response of Steam Generator [(SG)] Narrow Range level   |
| trip not responding as expected, an assessment was performed of the narrow   |
| range (NR) Steam Generator level channels at Salem 1 and 2.  This assessment |
| determined that the current 9% lo-lo level trip setpoint did not account for |
| the uncertainties associated with the differential pressure (dP) created by  |
| the steam flow past the mid-deck plate in the moisture separator section of  |
| the steam generator.  This dP phenomena will cause the SG NR level channels  |
| to read higher than actual water level at high steam flows.  Thus the lo-lo  |
| level trip setpoint is non-conservative."                                    |
|                                                                              |
| "In the unlikely event of a Loss of Main Feedwater to the Station            |
| Auxiliaries, or a Main Feedwater Rupture, the potential exists that a        |
| required reactor trip on lo-lo steam generator level may be delayed or may   |
| not be received at all.  In this scenario, other trip functions such as      |
| overtemperature delta-T would be expected to actuate in response to the      |
| initiating event.  However, these would arrive in a different sequence, and  |
| the net effect on the UFSAR Chapter 15 accident analysis results is unknown. |
| Thus, a condition exists in that a safety function could have been           |
| prevented."                                                                  |
|                                                                              |
| The licensee stated that operators were in the process of decreasing power   |
| on Unit 1 to below 38% based on engineering information.  The licensee plans |
| to maintain Unit 2 operations at 78% power.                                  |
|                                                                              |
| The licensee plans to notify the NRC resident inspector and the Lower        |
| Alloways Creek Township.                                                     |
|                                                                              |
| (Refer to event #38697 for a similar issue reported by Diablo Canyon.)       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38703       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 02/15/2002|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 21:16[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        02/15/2002|
+------------------------------------------------+EVENT TIME:        20:30[EST]|
| NRC NOTIFIED BY:  JOHN FAVEAU                  |LAST UPDATE DATE:  02/15/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES TRAPP          R1      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       78       Power Operation  |60       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A SCHEDULED UNIT SHUTDOWN FOR A
PLANNED       |
| REFUELING OUTAGE                                                             |
|                                                                              |
| The licensee notified the State Department of Environmental Protection and   |
| local county that the unit is in the process of reducing power to enter a    |
| planned refueling outage.  The licensee also notified the NRC resident       |
| inspector.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38704       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE:
02/16/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 11:11[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/15/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        22:00[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/16/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |ANTON VEGEL          R3      |
|  DOCKET:  0707001                              |SUSAN FRANT          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEVIN BEASLEY                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)        SAFETY EQUIPMENT FAILUR|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILURE - PROCESS GAS LEAK DETECTION FAILURE                |
|                                                                              |
| "At 2200 CST, on 02-15-02 the Plant Shift Superintendent (PSS) was notified  |
| of a failure of the Process Gas Leak Detector (PGLD) system in the C-333     |
| building.  During above atmospheric operation a PGLD alarm was received in   |
| the Area Control Room on C-333 Unit 4 Cell 4.  An operator responded to the  |
| local cell panel to investigate according to the alarm response procedure.   |
| Upon arriving at the cell panel the operator discovered that the Ready light |
| was not Illuminated on the PGLD panel.  At this time the operator attempted  |
| to test fire the PGLD system, however the system would not respond. The      |
| Front Line Mgr. and the PSS were immediately notified of the system failure. |
| At this time, required TSR 2.4.4.1 LCO continuous smoke watches were put in  |
| place in the affected areas until repair of the system was completed.        |
| Following replacement of the power supply by Instrument Maintenance and      |
| testing by Operations, ten Unit 4 Cell 4 PGLD system was declared operable   |
| by the PSS at 2340 CST. At this time the TSR required smoke watches were     |
| discontinued                                                                 |
|                                                                              |
| "The PGLD system is designed to detect the leakage of process gas from the   |
| process system and is required to be operable while operating in Cascade     |
| Mode 2 (Above Atmospheric Pressure).  Due to the failure of this TSR         |
| required system; the PSS has determined that this is reportable as a 24 hour |
| Event Report.                                                                |
|                                                                              |
| "The NRC Resident inspector has been notified of this event."                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38705       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 02/18/2002|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 13:26[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        02/18/2002|
+------------------------------------------------+EVENT TIME:        11:13[EST]|
| NRC NOTIFIED BY:  MARK LEONE                   |LAST UPDATE DATE:  02/18/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES TRAPP          R1      |
|10 CFR SECTION:                                 |ROBERTA WARREN       IAT     |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO OTHER FEDERAL AGENCY                                 |
|                                                                              |
| A member of the licensee's staff received an e-mail from a former contractor |
| requesting a meeting with senior Energy representatives.. The licensee       |
| notified the local FBI office.  The licensee informed the NRC Resident       |
| Inspector.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38706       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 02/18/2002|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 22:42[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        02/18/2002|
+------------------------------------------------+EVENT TIME:        20:20[EST]|
| NRC NOTIFIED BY:  HITT CRIDER                  |LAST UPDATE DATE:  02/18/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |STEPHEN CAHILL       R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT COMMENCED TECH SPEC REQUIRED SHUTDOWN AFTER DECLARING TWO
MSIVs         |
| INOPERABLE                                                                   |
|                                                                              |
| "Plant entered Tech spec 3.0.3 at 2020 on 2/18/2002. Two Main Steam          |
| Isolation Valves (MSIVs) were determined to have operating air pressures     |
| outside the required 70 - 80 psig operating range, which rendered the valves |
| inoperable per Tech Spec 3.7.1.5, Main steam line isolation valves.  At 2055 |
| commenced power reduction per Tech Spec 3.0.3.  At 2102 one of the MSIV      |
| valve operating pressures was restored to operable. Terminated power         |
| reduction at 99.5% and exited Tech Spec 3.0.3. Tech Spec 3.7.1.5 was still   |
| applicable.  At 2129 the remaining MSIV operating pressure was restored to   |
| the normal tech spec required pressure, exited Tech Spec 3.7.1 .5.           |
|                                                                              |
| "(An operator making a plant tour found XVM02801C-MS at 82 psig and          |
| XVM02801A-MS at 95 psig.)"                                                   |
|                                                                              |
| Partial MSIV stroke time testing was performed earlier today with MSIV       |
| operating pressure verified in the 70-80 psig range.  The licensee informed  |
| the NRC Resident Inspector.                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38707       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/19/2002|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 01:27[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/18/2002|
+------------------------------------------------+EVENT TIME:        18:15[EST]|
| NRC NOTIFIED BY:  JAMES WITTER                 |LAST UPDATE DATE:  02/19/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES TRAPP          R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS INADVERTENTLY MADE INOPERABLE           
   |
|                                                                              |
| "On 02/18/02, at 1815 hours, the licensee discovered that the Beaver Valley  |
| Unit 2 #1 Emergency Diesel Generator had been rendered inoperable            |
| inadvertently, by the posting of a clearance at 1408 hours on 2/14/02. The   |
| #2 Emergency Diesel Generator had previously been removed from service for   |
| maintenance activities. Upon discovery that the #1 Emergency Diesel          |
| Generator was inoperable, action was immediately initiated to restore the #1 |
| Emergency Diesel Generator to Operable status. These actions were completed  |
| and the #1 Emergency Diesel Generator was restored to Operable status at     |
| 1830 hrs on 02/18/02.                                                        |
|                                                                              |
| "The #1 Diesel Generator was rendered inoperable at 1406 hrs on 02/14/02.    |
| During the period of inoperability, the licensee conducted core alterations  |
| including core reload during the ongoing ninth refueling outage. During the  |
| affected period, there were no challenges to the offsite power sources, and  |
| core cooling was maintained. Investigation into this event is ongoing.       |
|                                                                              |
| "This event is being reported under 10CFR50.72(v)(A) and 10CFR50.72(v)(B) as |
| a loss of Safe Shutdown Capability, and RHR Capability, respectively. There  |
| were no radiological releases associated with this event,"                   |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+