The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38518       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                               |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38585       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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).                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38602       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38698       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
                         *** NOT FOR PUBLIC DISTRIBUTION ***
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                   |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Wednesday, March 24, 2021