Event Notification Report for May 20, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/17/2002 - 05/20/2002
** EVENT NUMBERS **
38602 38819 38908 38909 38925 38927 38928 38929 38930
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38602 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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: 05/19/2002|
| 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. |
| |
| * * * UPDATE ON 03/01/02 AT 1122 EST BY RICKY RAWLS TO GERRY WAIG * * * |
| |
| "On March 1, 2002 at 0952, a healthy rescued sea turtle was identified as a |
| Green Sea Turtle. This is the 66th 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 was notified. R2DO (Julian) was notified. |
| |
| * * * UPDATE ON 03/07/02 AT 1114 EST BY CHUCK MORRIS TO MIKE NORRIS * * * |
| |
| "On March 7, 2002 at 0835, two healthy sea turtles rescued at CR#3 were |
| identified as Green Sea Turtles. These are the 67th and 68th live sea turtle |
| rescues at the Crystal River Energy Complex 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 was notified. R2DO (Henson) was notified. |
| |
| * * * UPDATE ON 04/02/02 at 0408 EST BY RICKY RAWLS TO FANGIE JONES * * * |
| |
| "On April 2, 2002 at 0236, two sea turtles previously rescued at CR#3 intake |
| area were identified by FPC Mariculture staff as Kemp Ridley Sea Turtles. |
| One of the turtles appears to be in distress and may require transportation |
| to Clearwater Marine Science Center of Florida Fish and Wildlife |
| Conservation Refuge. These are the 69th and 70th live sea turtle rescues at |
| the Crystal River Energy Complex 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. The R2DO (Carolyn Evans) was |
| notified. |
| |
| ***** UPDATE AT 1023 EDT ON 05/19/02 FROM PELLERIN TO LEIGH TROCINE ***** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On May 19, 2002, at 0916, a sea turtle previously rescued at CR#3 intake |
| area was identified by FPC Mariculture staff as Green Sea Turtle. This is |
| the 71st live sea turtle rescue at the Crystal River Energy Complex 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 licensee plans to notify the National Marine Fisheries Service and |
| Florida Fish and Wildlife Conservation Commission and the NRC resident |
| inspector. The NRC operations officer notified the R2DO (Paul Fredrickson). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38819 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/01/2002|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 13:05[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/01/2002|
+------------------------------------------------+EVENT TIME: 09:17[CST]|
| NRC NOTIFIED BY: THOMAS JESSESSKY |LAST UPDATE DATE: 05/17/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NITROGEN BACKUP SYSTEM FOR CHARGING PUMP SPEED CONTROL FOUND NOT TO
SATISFY |
| APPENDIX R FIRE ASSUMPTION. |
| |
| At 0917 CT on 04/01/02, it was determined that a condition identified on |
| 03/28/02 potentially represents a significant degradation of plant safety |
| during response to an Appendix R event. The Appendix R credited nitrogen |
| backup system for charging pump speed control is unable to satisfy its |
| design function of controlling Charging System flow to the Reactor Coolant |
| System (RCS) for the time required to place the plant in Mode 5 (Cold |
| Shutdown). During an Appendix R fire it is assumed that the normal motive |
| force (instrument air) for charging control is unavailable and an installed |
| backup is credited. This installed nitrogen system allows inventory control |
| while in Mode 3 (Hot Standby) and is used to control RCS inventory and |
| pressure while the RCS is cooled down and depressurized from Mode 3 (Hot |
| Standby) to Mode 5 (Cold Shutdown). A nitrogen bottle 12-pack is calculated |
| to last for approximately 8 hours. PBNP has 1 spare approved nitrogen pack |
| on site - - it has been calculated that up to 15 spares would be required |
| for 72 hours of charging pump operation. Mode 5 (Cold Shutdown) is expected |
| to be reached in 30 hours but may be as long as 72 hours. |
| |
| This issue places the plant in an unanalyzed condition that has the |
| potential to significantly degrade plant safety (RCS Inventory Control) and |
| thus is reportable. |
| |
| The associated charging pumps have been declared out of service for Appendix |
| R use and compensatory actions undertaken that establish appropriate fire |
| rounds. Fire rounds will be continued until the condition is corrected or a |
| suitable evaluation is completed. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| ****RETRACTION ON 5/17/02 AT 13:10 FROM R. Robbins to R. Laura**** |
| |
| "ENS Event Notification #38819 was reported at 1205 CST on April 1, 2002. |
| This event was reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) for |
| identification of an unanalyzed condition that had the potential to |
| significantly degrade plant safety. The condition involved postulated |
| Appendix R fire scenarios for which the safe shutdown analyses assumes that |
| the normal motive force for charging pump control (instrument air) is |
| unavailable due to fire-induced damage. Certain Appendix R fire scenarios |
| require the availability of a single charging pump, operable at greater than |
| minimum pump capacity, in order to meet the Appendix R performance goal of |
| maintaining adequate RCS inventory control without loss of pressurizer |
| level. An installed back-up nitrogen supply is credited with maintaining the |
| ability to control charging pump flow for the duration of the 72 hour |
| Appendix R coping period. The unanalyzed condition identified in this |
| notification was that the installed back-up nitrogen supply, based on a |
| conservative calculation, would have adequate capacity to provide the motive |
| force for the Single Charging pump control function for only 8 hours. After |
| that time, the variable speed charging pump would run back to minimum speed, |
| which equates to a pumping capacity of approximately 18 gpm. |
| |
| "We have subsequently completed an engineering evaluation to estimate the |
| transient behavior of the RCS in the event of these Appendix R fire |
| scenarios assuming only 8 hours of Charging pump speed control is available. |
| This evaluation was based on conservative assumptions regarding reactor |
| coolant pump seal leakage and unavailability of normal cooling and safety |
| systems. This evaluation provided estimates of key RCS transient parameters |
| based on engineering analysis and predicts that upon reducing the available |
| charging pump flow to the pump minimum, pressurizer pressure and level will |
| no longer be maintained. Although RCS sub-cooling is lost and some voiding |
| in the RCS occurs, the core remains covered during the entire 72 hour |
| Appendix R coping period and core cooling is maintained throughout the |
| transient. |
| |
| "We have therefore concluded that this previously unanalyzed Appendix R |
| scenario would not have resulted in a condition that would have |
| significantly degraded plant safety. Therefore, this condition is not |
| reportable under 10 CFR 50.72 and we are hereby retracting this event |
| notification. |
| |
| "Until corrective actions are completed to ensure that the Appendix R safe |
| shutdown performance goal to maintain reactor coolant inventory control |
| within the level indication in the pressurizer can be satisfied, appropriate |
| fire rounds will continue." |
| |
| The NRC Resident Inspector was notified. |
| |
| Notified R3DO (R. Gardner) |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Hospital |Event Number: 38908 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: GEORGE WASHINGTON UNIV. HOSPITAL |NOTIFICATION DATE:
05/09/2002|
|LICENSEE: G.W. UNIV. HOSPITAL |NOTIFICATION TIME: 16:25[EDT]|
| CITY: WASHINGTON DC REGION: 1 |EVENT DATE: 05/09/2002|
| COUNTY: STATE: DC |EVENT TIME: 10:30[EDT]|
|LICENSE#: 08-30607-01 AGREEMENT: N |LAST UPDATE DATE: 05/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHELE EVANS R1 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+JOE HOLONICH IRO |
| NRC NOTIFIED BY: ANIS CHOWDHURG | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAE1 20.2202(b)(1) PERS OVEREXPOSURE/TEDE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PRELIMINARY ESTIMATED EXPOSURE OF 63 ROENTGEN TO THE HANDS OF A
MEDICAL |
| PHYSICIST |
| |
| |
| While using a Cordis delivery system to insert a ribbon containing Ir-192 |
| seeds into a patient, the ribbon came out into the hands of the Medical |
| Physicist. The screw and cap of the Cordis delivery system had been loosened |
| and the ribbon containing the Ir-192 seeds was supposed to be pushed into |
| patient via a catheter but somehow the ribbon containing the Ir-192 seeds |
| ended up in the hand of the Medical Physicist. George Washington Hospital |
| Radiation Safety Officer preliminarily estimated the minimum exposure to the |
| Medical Physicist hand was 63 roentgens. The Medical Physicist walked 5 or |
| 6 feet into another room where the Radiation Oncologist was located and |
| dropped the ribbon to the floor. The Radiation Oncologist, wearing gloves, |
| picked the ribbon up and placed it in a safe location. The Radiation Safety |
| Officer for George Washington Hospital said that the Radiation Oncologist |
| received a dose to his hand while carrying the ribbon. An estimated dose |
| calculation to Radiation Oncologist hands, etc., had not been made at the |
| time of the notification. |
| |
| ****UPDATE ON 5/17/02 at 11:15 FROM A. CHOWDHURY TO R. LAURA**** |
| |
| Further licensee investigation revealed that an actual overexposure did not |
| occur. The initial calculations of this event were too conservative. NRC |
| Region 1 inspectors made a site visit to review this event. |
| |
| Notified R1DO (D. Holody) and NMSS (D. Cool). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38909 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ROCKWELL AUTOMATION |NOTIFICATION DATE: 05/09/2002|
|LICENSEE: ROCKWELL AUTOMATION |NOTIFICATION TIME: 16:30[EDT]|
| CITY: FLOWERY BRANCH REGION: 2 |EVENT DATE: 05/09/2002|
| COUNTY: STATE: GA |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 05/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |VERN HODGE NRR |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JAMES THIGPEN | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PART 21 ISSUE ON ELECTRIC MOTORS |
| |
| Rockwell Automations report a potential defect involving insufficient slot |
| fill in electric motor windings used to drive fan assemblies. They have |
| contacted Hayden Company located in New Philadelphia, Ohio who was supplied |
| with these motors. The motors may be in use at commercial nuclear power |
| plants. |
| |
| ***UPDATE Curt Pratt to Mike Norris 5/16/02 13:59 EDT*** |
| |
| This update listed the Licensees that have these motors: Davis Besse, |
| Oconee and Braidwood. |
| Notified NRR (Hodges) , Reg 2 RDO(Fredrickson) and Reg 3 RDO(Gardner). |
| |
| ****UPDATE J. Thigpen to R. Laura on 5/17/02 at 13:19 by fax***** |
| |
| The licensee identified 1 additional motor and the customer was the same as |
| the others. |
| |
| Notified NRR (Hodges) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38925 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/17/2002|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 14:55[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/17/2002|
+------------------------------------------------+EVENT TIME: 11:30[CDT]|
| NRC NOTIFIED BY: GERALD HILDEBRANDT |LAST UPDATE DATE: 05/17/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |GREG PICK R4 |
|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
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EP SIREN INADVERTENTLY ACTUATED FOR ONE MINUTE PROMPTING AN OFFSITE
|
| NOTIFICATION |
| |
| "A South Texas Project Offsite Emergency Notification siren was |
| inadvertently going off. The Matagorda County Sheriffs office notified the |
| station a siren had activated for approximately 1 minute. This happened at |
| the same time a thunderstorm was moving through the area. Onsite personnel |
| have verified the sirens are operational and in a standby condition. The |
| Matagorda County Sheriffs office was the only offsite agency that was |
| contacted during this event." |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38927 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 05/19/2002|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 03:33[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/19/2002|
+------------------------------------------------+EVENT TIME: 00:54[EDT]|
| NRC NOTIFIED BY: PETE GARDNER |LAST UPDATE DATE: 05/19/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DANIEL HOLODY R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 94 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO A TURBINE TRIP FOR UNKNOWN REASONS
|
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[A] Unit-1 reactor scram occurred at 0054 hours on May 19, 2002. The |
| reactor scram occurred as a result of a main turbine trip. The cause of the |
| turbine trip is under investigation. All systems actuated as designed. The |
| unit is being maintained in Hot Shutdown at normal [reactor pressure vessel] |
| level. This report is being made pursuant to [10 CFR] 50.72(b)(2)(iv)(B) |
| due to actuation of the reactor protection system (RPS). No [safety relief |
| valves] lifted, and currently [one] reactor recirculation pump has been |
| restarted[. The] scram has been reset." |
| |
| The licensee stated that reactor vessel level control is currently being |
| maintained via normal condensate and feedwater. The main steam isolation |
| valves are open, the condenser is available as a heat sink, and reactor |
| vessel pressure control is being maintained via normal electrohydraulic |
| control pressure control. Containment parameters are normal. The licensee |
| also stated that the all control rods fully inserted, that there were no |
| engineered safety feature actuations or emergency core cooling system |
| injections, and that none were required. There was nothing unusual or not |
| understood with the exception of the cause of the turbine trip. |
| |
| Prior to this event, the unit had been operating at reduced power to |
| facilitate the performance of turbine stop valve testing. The licensee |
| stated that a combined intermediate valve (CIV) was being stroked at the |
| time of the turbine trip/reactor scram but that stroking of the CIV is |
| currently believed to be unrelated to the turbine trip. At this time, the |
| licensee believes that the cause of the turbine trip may have been related |
| to the thrust bearing wear detector. However, the final root cause of the |
| turbine trip remains under investigation. |
| |
| The licensee notified the NRC resident inspector, applicable State and local |
| agencies (including Montgomery, Chester, and Berks Counties), and the |
| Pennsylvania Emergency Management Agency. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38928 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 05/19/2002|
| UNIT: [] [2] [] STATE: TN |NOTIFICATION TIME: 06:03[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/19/2002|
+------------------------------------------------+EVENT TIME: 04:47[EDT]|
| NRC NOTIFIED BY: MICHAEL HOWARD |LAST UPDATE DATE: 05/19/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 0 Startup |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO A CONTROL ROD SYSTEM URGENT FAILURE ALARM
DURING |
| LOW POWER PHYSICS TESTING |
| |
| While in Mode 2 (Startup) with reactor power at 10E-6 in the intermediate |
| range as part of a refueling outage, Unit 2 was manually tripped at 0447 EDT |
| on 05/19/02. During the performance of low power physics testing, the unit |
| experienced a control rod system urgent failure alarm. Operators were |
| inserting Shutdown Bank 'B,' and the Shutdown Bank 'B' Group 2 step counter |
| failed to step. Rod movement was stopped. After performance of an |
| evaluation, operators noticed that reactivity was increasing slightly. |
| Operators then attempted to insert Control Bank 'D,' and the Control Bank |
| 'D' Group 2 step counter also failed to step. After evaluating rod control |
| problems, the reactor was manually tripped. |
| |
| All control rods fully inserted as a result of the manual reactor trip, and |
| all systems functioned as required. There were no engineered safety feature |
| actuations or emergency core cooling system injections, and none were |
| required. The licensee currently suspects that there may be a blown fuse in |
| the rod control cabinet. The investigation is currently underway. |
| |
| The unit is currently stable in Mode 3 (Hot Standby). Normal charging and |
| makeup, pressurizer heaters and sprays, and the reactor coolant pumps are |
| being utilized for primary system inventory, pressure, and transport |
| control. Main feedwater is supplying water to the steam generators, and |
| secondary steam is being dumped to the condenser. Containment parameters |
| are also normal. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38929 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 05/19/2002|
| UNIT: [1] [] [] STATE: CA |NOTIFICATION TIME: 20:59[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/19/2002|
+------------------------------------------------+EVENT TIME: 16:00[PDT]|
| NRC NOTIFIED BY: STEVE DAVID |LAST UPDATE DATE: 05/19/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GREG PICK R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GREATER THAN 1% OF STEAM GENERATOR 1-2 TUBES ARE DEFECTIVE |
| |
| On May 19, 2002, during the Unit 1 eleventh refueling outage, analysis of |
| eddy current data on steam generator (SG) 1-2 indicated that greater than |
| one percent of the total tubes inspected on SG 1-2 were defective. |
| Thirty-six (36) defective tubes in SG 1-2 were detected and are being |
| plugged. Most of the pluggable indications are due to outside diameter |
| stress corrosion cracking at the tube support plate intersections. Review |
| of the eddy current inspections are complete. Results of the SG tube |
| inspection fall into Category C-3, which requires a 4-hour non-emergency |
| report in accordance with Technical Specification Table 5.5.9-2 and 10 CFR |
| 50.72(b)(3)(ii) an 8-hour requirement. |
| |
| The other three SGs' tubes have been checked. |
| |
| An NRC teleconference in accordance with Technical Specification 5.6.10.d to |
| report the results of the voltage-based repair criteria implemented for the |
| tube support plate intersections is currently scheduled for Monday May 20, |
| 2002, at 1230 hours EDT. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38930 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 05/20/2002|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 05:43[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 05/20/2002|
+------------------------------------------------+EVENT TIME: 05:00[CDT]|
| NRC NOTIFIED BY: GARY OLMSTEAD |LAST UPDATE DATE: 05/20/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GREG PICK R4 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANNED MAINTENANCE RESULTING IN THE LOSS OF AN EMERGENCY RESPONSE
FACILITY |
| FOR THE DURATION OF THE EVOLUTION |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During performance of planned maintenance, the Emergency Operation Facility |
| (EOF) will be de-energized. These maintenance activities, including |
| electrical isolation and restoration, are expected to last approximately 16 |
| hours. Contingency plans for emergency situations have been established." |
| |
| "This event is reportable per 10CFR50.72(b)(3)(xiii) since this constitutes |
| a loss of an emergency response facility for the duration of the |
| evolution." |
| |
| "The NRC Resident was previously notified that this activity was scheduled |
| to occur and will be informed of this ENS notification." |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021