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 |
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*** NOT FOR PUBLIC DISTRIBUTION ***
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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
+------------------------------------------------------------------------------+
| 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 |
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*** NOT FOR PUBLIC DISTRIBUTION ***
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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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38602 |
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*** NOT FOR PUBLIC DISTRIBUTION ***
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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
+------------------------------------------------------------------------------+
| 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 |
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*** NOT FOR PUBLIC DISTRIBUTION ***
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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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*** NOT FOR PUBLIC DISTRIBUTION ***
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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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021