Event Notification Report for April 7, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/04/2003 - 04/07/2003
** EVENT NUMBERS **
39583 39704 39717 39726 39727 39728 39729 39730 39731 39732 39733 39734
39735 39736 39737 39738
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39583 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 02/12/2003|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 21:21[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 02/12/2003|
+------------------------------------------------+EVENT TIME: 17:04[CST]|
| NRC NOTIFIED BY: LAUDENBACH |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |SONIA BURGESS R3 |
|10 CFR SECTION: | |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE DURING TESTING |
| |
| During a test of HPCI, the flow controller failed as the controller was |
| being transferred from manual to balance. The system was manually tripped |
| and remains inoperable. The system impacted is the High Pressure Coolant |
| Injection and the cause is being investigated. The plant is also in a LCO |
| action statement. Corrective action is being implemented to correct this |
| single train system failure. |
| |
| The NRC Resident Inspector was notified. State and local agencies will be |
| notified. |
| |
| *** EVENT RETRACTION BY TIM WITSCHEN TO ERIC THOMAS AT 1600 EST ON 4/4/03 |
| *** |
| |
| "Event report 39583 was determined not to be reportable. The HPCI system |
| would have been able to perform its safety function of automatically |
| delivering 2700 gpm to the reactor within 45 seconds of initiation signal in |
| the event of a loss of coolant accident, and to mitigate the consequences of |
| a high energy line break. [Therefore], this event is being retracted." |
| |
| The licensee will notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39704 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 03/26/2003|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 11:16[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/26/2003|
+------------------------------------------------+EVENT TIME: 10:12[EST]|
| NRC NOTIFIED BY: MICHAEL HOWARD |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RUDOLPH BERNHARD R2 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling Shutdow|0 Refueling Shutdow|
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR VESSEL HEAD DEGRADED CONDITION |
| |
| "During the unit 1 cycle 12 refueling and steam generator replacement |
| outage, an inspection was performed of the vessel head in accordance with |
| NRC Order EA-03-009. This bare metal inspection identified a potential leak |
| indication at the head to penetration interface for CRDM (Control Rod Drive |
| Mechanism) penetration #3. On March 26, 2003, at approximately 1012 hours |
| EST, it was decided that the chemical samples have confirmed that the |
| residue found at this interface contains boron, iron, and zinc, indicating |
| that this was an RCS leak. This leak is most likely from a through wall |
| crack in the RCS pressure boundary at the CRDM interface. Volumetric exams |
| are planned to confirm the crack and to determine the scope of any repairs. |
| In accordance with the Order, a 100% volumetric inspection is being prepared |
| for this outage. Prior to this identification, this unit was rated as a |
| 'low susceptibility category.' There had been no indication of RCS leakage |
| during the previous cycle's operation. This notification is being made in |
| accordance with 10 CFR 50.72(b)(3)(ii)(A)." |
| |
| The licensee has notified the NRC Resident Inspector. |
| |
| *****UPDATE ON 4/4/03 AT 1355 FROM LEAHY TO LAURA***** |
| |
| "The purpose of this notification is to update event #39704 concerning a |
| potential pressure boundary leak at CRDM #3. TVA has completed both UT and |
| PT examinations of CRDM #3. The results of these exams do not provide any |
| indication of a crack in the RCS pressure boundary. Investigations are |
| continuing as to the source of the residue found at the penetration. Based |
| on the results of the vessel head examination, this investigation is |
| focusing on determining whether the residue was a result of a prior leak |
| from a non-RCS pressure boundary location." |
| |
| Notified R2DO (A. Boland) |
| |
| *****RETRACTED ON 4/4/03 AT 1702 EST FROM LEAHY TO LAURA***** |
| |
| "The purpose of this notification is to retract the original 10 CFR 50.72 |
| notification described in event notification #39704. |
| TVA's previous update to this notification stated that we had no indication |
| of a pressure boundary crack and that we were continuing to investigate the |
| source of the residue found near CRDM penetration #3. Isotopic analysis |
| (Cesium isotopes) of the boron residue from the head now confirmed that the |
| residue was over 10 years old and likely the result of a conoseal leak that |
| occurred in that period. As such, TVA is retracting the original |
| notification." |
| |
| Notified R2DO (A. Boland) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39717 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 04/01/2003|
|LICENSEE: CTL/THOMPSON TEXAS, LLC |NOTIFICATION TIME: 12:49[EST]|
| CITY: Dallas REGION: 4 |EVENT DATE: 03/31/2003|
| COUNTY: STATE: TX |EVENT TIME: 20:00[CST]|
|LICENSE#: L04900-001 AGREEMENT: Y |LAST UPDATE DATE: 04/01/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANTHONY GODY R4 |
| |SUSAN FRANT NMSS |
+------------------------------------------------+JOHN DAVIDSON IAT |
| NRC NOTIFIED BY: JIM OGDEN | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE |
| |
| The following information was received from the Texas Department of Health, |
| Bureau of Radiation Control via facsimile: |
| |
| "The gauge operator was working a night assignment. After completion he |
| took his company vehicle to the company office to complete paperwork at |
| approximately 11:20 p.m. After completion of the paperwork he returned to |
| his vehicle at approximately 11:40 p.m. and discovered that his assigned CPN |
| nuclear density gauge (Model MC1-DR, Serial No. MD0129983) with two sealed |
| radiation sources: a 10 millicurie Amersham, Model CPN 131, cesium-137 |
| capsule, Serial No. 2870, that is engraved on the source rod as "CS9983" |
| (source type plus the last four digits of the gauge Serial No.); and a 50 |
| millicurie Amersham, Model CPN131, americium-241/beryllium, Serial No. 0992, |
| that is engraved on the gauge's internal source pedestal as "AM9983" (source |
| type plus the last four digits of the gauge Serial No.), was missing from |
| the truck. The Licensee's security chain had been cut and was left in the |
| vehicle. The 'red' transport case had been locked but the Licensee reports |
| finding a piece of it's lock, also cut, in the bed of the truck. However, |
| the transport case was also missing. In addition, the gauge's rod handle was |
| also locked within the case before the gauge was stolen. The Licensee also |
| reported that nothing except the gauge and it's case were removed from the |
| truck. This Agency has searched Agency Open Records requests back through |
| January 2002, with no suspicious request noted." |
| |
| There is no media attention at this time. The Licensee is considering |
| whether or not to post a reward for return of the gauge. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39726 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/03/2003|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 18:05[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/03/2003|
+------------------------------------------------+EVENT TIME: 14:56[CST]|
| NRC NOTIFIED BY: RYAN RODE |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|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 97 Power Operation |97 Power Operation |
|2 N Y 97 Power Operation |97 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PARTIAL LOSS OF COMMUNICATIONS |
| |
| "On 4/3/03 at 1456, due to adverse weather conditions, power was lost to the |
| Site Boundary Control Center. This resulted in a loss of ENS FTS 2000 |
| Communication System in the TSC and Control Room. This event is reportable |
| per Duty and Call Superintendent Handbook DOS 2.1.1 Section 4.7, |
| Clarification of NUREG-1022 Section 3.2.13, Loss of EP Capabilities. |
| Commercial phone lines are fully functional." |
| |
| The licensee informed the NRC Resident Inspector, as well as state and local |
| authorities. |
| |
| |
| * * * UPDATE ON 4/4/03 @ 0145 BY RAASCH TO GOULD * * * |
| |
| At 2309 on 4/3/03, the EP Manager reported from the EOF that all phones are |
| lost in the EOF. This event is reportable per Duty and Call Superintendent |
| Handbook DCS 2.1.1 section 4.7, clarification of NUREG - 1022, section |
| 3.2.13 loss of EP capabilities. |
| |
| At 2315 on 4/3/03, power was restored to the EOF. Communication |
| capabilities from the EOF, TSC and Control Room ENS phones are restored. |
| |
| The Resident Inspector will be notified. Region 3 RDO(Clayton) was |
| notified. |
| |
| * * * UPDATE FROM RYAN RODE TO ERIC THOMAS AT 1930 ON 4/4/03 * * * |
| |
| "Upon review of event notification 39726 at 1805 EST on 4/3/03, and the |
| update to that notification at 0148 EST on 4/4/03, two corrections should be |
| noted: |
| |
| 1) The original notification states that commercial phone lines were fully |
| functional. This was correct for the control room and TSC. The commercial |
| phones were not functional in the EOF located in the Site Boundary Control |
| Center (SBCC), |
| |
| 2) The update at 0148 EST, which reported that all phones were lost in the |
| EOF, occurred when the power was lost to the SBCC, which occurred at about |
| 1456 CST on 3 April 2003." |
| |
| The NRC Resident Inspector was notified. R3DO (B. Clayton) was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39727 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/03/2003|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 18:16[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 04/03/2003|
+------------------------------------------------+EVENT TIME: 16:05[CST]|
| NRC NOTIFIED BY: ETHAN TREPTOW |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
|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 85 Power Operation |85 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNPLANNED SIREN OUTAGE DUE TO ADVERSE WEATHER AND OFFSITE NOTIFICATION AT |
| KEWAUNEE |
| |
| "At 1605 on April 3, 2003 it was reported to the Control Room that greater |
| than 50% siren population coverage was lost. The percent siren coverage |
| population lost is 50.03%. The lost siren coverage is due to weather related |
| power outages. Crews have been dispatched and are working to restore power |
| to the affected sirens. |
| |
| "Additionally, substation Line Y-51 is out-of-service due to the weather |
| conditions. Three of the four off-site power lines remain available. |
| |
| "The plant is currently in the process of reducing power for a refueling |
| outage. |
| |
| "This is being reported under 10 CFR 50.72(b)(3)(xiii) as any event that |
| results in a major loss of emergency assessment capability, offsite response |
| capability, or offsite communications capability (loss of greater than 50% |
| of emergency sirens). It is also being reported under 10 CFR 50.72(b)(2)(xi) |
| as any event or situation, related to the health and safety of the public or |
| onsite personnel, or protection of the environment, for which a news release |
| is planned or notification to other government agencies has been or will be |
| made." |
| |
| The NRC Inspector was notified. |
| |
| *** UPDATE FROM JAMES BAPTIST TO ERIC THOMAS AT 1701 EST ON 4/4/03 *** |
| |
| Power has been reduced to 42 percent due to coastdown to refueling outage. |
| |
| Substation line Y-51 is back in service, rendering four or four off-site |
| power lines available. |
| |
| There are now 9 sirens out of service, which equals 61.97% of all available |
| sirens. |
| |
| The licensee has notified the NRC Resident Inspector, along with the local |
| sheriff's department and state officials. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39728 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 00:18[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/03/2003|
+------------------------------------------------+EVENT TIME: 22:05[CST]|
| NRC NOTIFIED BY: SAND |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|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
+------------------------------------------------------------------------------+
| FALSE ACTIVATION OF PUBLIC ALERT SYSTEM |
| |
| The plant had a false activation of the Public Alert Notification System |
| (PANS) by the Sherbune County Sheriff's Department. Sherbune County |
| personnel stated that they had accidentally triggered the system that |
| resulted in the sirens in both Sherbune and Wright counties to sound. Both |
| counties performed a signal cancellation and the sirens were silenced within |
| 5 - 10 minutes. |
| |
| The NRC Resident Inspector was notified along with the state and local |
| agencies. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39729 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 09:43[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 04/04/2003|
+------------------------------------------------+EVENT TIME: 07:16[EST]|
| NRC NOTIFIED BY: MCLAUGHLIN |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 |
|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
+------------------------------------------------------------------------------+
| LOSS OF MORE THAN 50% OF THE EMERGENCY SIRENS |
| |
| The plant has 59 of the 96 offsite notification system sirens out of service |
| due to loss of power caused by ice storms damage to the electrical power |
| supplies. They do not know how soon the sirens will be returned to |
| service. |
| |
| The NRC Resident Inspector and local government were notified and the state |
| will be informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39730 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 11:17[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 04/04/2003|
+------------------------------------------------+EVENT TIME: 09:17[EST]|
| NRC NOTIFIED BY: ALLEN |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 |
|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
+------------------------------------------------------------------------------+
| PLANT HAS MORE THAN 50% OF THEIR EMERGENCY SIRENS OUT OF SERVICE DUE TO ICE |
| STORMS |
| |
| The licensee received a call from the Oswego county EOC that 25 out of a |
| total of 37 emergency sirens are out of service due to ice storms. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39731 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 11:18[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/04/2003|
+------------------------------------------------+EVENT TIME: 09:13[EST]|
| NRC NOTIFIED BY: KEVIN BELDEN |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF 27 OUT OF A TOTAL OF 37 EMERGENCY NOTIFICATION SIRENS DUE TO ICE |
| STORM |
| |
| "This notification is being made per 10CFR50.72.(b)3 (xiii): Eight hour |
| reports - Any event that results in a major loss of emergency assessment |
| capability, offsite response capability or offsite communications |
| capability. |
| |
| "The following sequence of events have occurred: |
| - On 4/3/03, a severe Winter ice storm. Affecting Oswego County, NY began. |
| - On 4/4/03, Time: 0603, a report from the Oswego Warning Point informed |
| NMP1 Control Room that 14 Emergency Notification Sirens were inoperable. |
| - On 4/4/03, Time: 0913, a report from the Oswego County Emergency |
| Operations Center informed NMP 1 Control Room that 27 Emergency Notification |
| Sirens were inoperable." |
| |
| The NRC Resident Inspector and State and local government agencies have been |
| notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39732 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 12:58[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/04/2003|
+------------------------------------------------+EVENT TIME: 10:30[CST]|
| NRC NOTIFIED BY: Charles Stalzer |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF GREATER THAN 50% OF EMERGENCY SIRENS |
| |
| "At 1030 on April 4, 2003 it was reported to the Control Room that greater |
| than 50% siren population coverage was lost. The percent siren coverage |
| population lost is 55.06%. The lost siren coverage is due to weather related |
| power outages. Crews have been dispatched and are working to restore power |
| to the affected sirens. |
| |
| "This is being reported under 10 CFR 50.72(b)(3)(xiii) as any event that |
| results in a major loss of emergency assessment capability, offsite response |
| capability, or offsite communications capability (loss of greater than 50% |
| of emergency sirens). It is also being reported under 10 CFR 50.72(b)(2)(xi) |
| as any event or situation, related to the health and safety of the public or |
| onsite personnel, or protection of the environment, for which a news release |
| is planned or notification to other government agencies has been or will be |
| made. |
| |
| The NRC Resident Inspector was notified." |
| |
| *** UPDATE FROM RYAN RODE TO ERIC THOMAS AT 1930 EST ON 4/4/03 *** |
| |
| "At 1432 on 4/4/03, EP Manager informed control room staff that Two Rivers |
| Utilities completed repairs to various sirens. Total loss of coverage has |
| been reduced to 20.23%. NRC Resident, state and local agencies have been |
| notified." |
| |
| R3DO (B. Clayton) was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39733 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 16:35[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/04/2003|
+------------------------------------------------+EVENT TIME: 13:54[EST]|
| NRC NOTIFIED BY: CHARLES CASHWELL |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE BOLAND R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 22 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM AT BRUNSWICK DURING START-UP FROM REFUELING OUTAGE |
| |
| "On April 4, 2003, during a Unit 2 reactor start up, primary containment |
| group 1 isolation was received which resulted in a reactor scram. Following |
| the scram, reactor water level lowered to approximately 150 inches. This is |
| below the Reactor Water Low Level One set point of 166 inches. As a result |
| of the low water level, primary containment group 2, 6, & 8 isolation |
| signals were received. All required isolations occurred as a result of the |
| Reactor Water Low Level One isolation signal. All control rods fully |
| inserted on the scram. Reactor Core Isolation Cooling was manually started |
| and Reactor water level was restored to the normal band. Reactor Core |
| Isolation Cooling was shutdown after Reactor water level was restored. |
| |
| "It is believed that the cause of the group 1 isolation signal (Main Steam |
| Isolation Valve closure Scram signal) was an Electro-hydraulic Control (EHC) |
| malfunction that caused the Main Turbine Bypass valves to open. This |
| resulted in the Main Steam Line pressure dropping below the group 1 set |
| point of 850 psig. Investigation is ongoing to determine the exact cause of |
| the EHC malfunction." |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39734 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 18:26[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/04/2003|
+------------------------------------------------+EVENT TIME: 15:26[EST]|
| NRC NOTIFIED BY: CHARLES CASHWELL |LAST UPDATE DATE: 04/04/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION OF POTENTIAL FUEL OIL SPILL |
| |
| "Operations was notified by site chemistry management that a report of a |
| potential fuel oil spill was being made to the North Carolina Department of |
| Environmental Health and Natural Resources, Regional Division of Water |
| Quality. Diesel fuel oil has been identified seeping onto the floor of the |
| Augmented Off-Gas (AOG) building. A diesel fuel oil transfer line from the |
| off-load station to a fuel oil storage tank runs underground in the vicinity |
| of the AOG building and is suspected as the source of the leak. The quantity |
| of the leakage is not known at this time. A follow-up discussion with the |
| Division of Water Quality personnel is scheduled for Monday, April 7, 2003, |
| when more information will be available. |
| |
| "Initial safety significance of this event is zero because this does not |
| affect operation of the Units." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39735 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/04/2003|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 23:41[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/04/2003|
+------------------------------------------------+EVENT TIME: 18:24[PST]|
| NRC NOTIFIED BY: STEVE HACKLEMAN |LAST UPDATE DATE: 04/05/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANTHONY GODY R4 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 54 Power Operation |20 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| "On April 4, 2003, at 1824 PST, with Unit 2 at approximately 54 percent |
| power, operators commenced a shutdown to mode 5 in accordance with technical |
| specification 3.7.5 C. 1, 'Auxiliary Feedwater (AFW) System,' due to two AFW |
| trains determined to be inoperable. |
| |
| "While trouble-shooting leaking AFW check valves, AFW discharge check valve |
| (FW-2-377) to steam generator (SG) 2-1 was determined to be inoperable due |
| to incorrect installation. Based on radiography, the check valve appears to |
| be installed incorrectly such that it may not allow sufficient AFW flow to |
| SG 2-1. This condition renders two trains of AFW inoperable. |
| |
| "The two motor-driven and one turbine-driven AFW pumps and their flow paths |
| to the other three SGs remain operable. The system is designed such that |
| design basis decay heat can be removed by a single AFW pump delivering flow |
| to at least two SGs. |
| |
| "Unit 2 had ended the recent refueling outage on March 25 and had yet to |
| reach full power when this problem was discovered. Check Valve FW-2-377 had |
| been disassembled during this refueling outage." |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39736 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/05/2003|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:58[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/05/2003|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 02:07[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/05/2003|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRENT CLAYTON R3 |
| DOCKET: 0707002 |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: MIKE RIPLEY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NOTIFICATIONS MADE TO OTHER GOVERNMENT AGENCIES |
| |
| "On 4/4/03 at 2113 hrs the Plant Shift Superintendent's office was notified |
| that approximately 25,000 gallons of trichloroethene (TCE) contaminated |
| ground water was discharged onto the ground. During a routine shift |
| turnover an operator observed that the check valve on well B-10 stuck open |
| allowing water to backflow into the well casing and over flow onto the |
| ground. This requires a verbal notification to the Ohio Environmental |
| Protection Agency (OEPA) and to the National Response Center. |
| |
| "At 0207 hours, the Plant Shift Superintendent completed notifications to |
| the Ohio Environmental Protection Agency (OEPA) and to the National Response |
| Center. UE2-RA-RE1030 App. D, section P requires a 4 hour NRC event when |
| other government agencies are notified." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39737 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/05/2003|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 09:45[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/05/2003|
+------------------------------------------------+EVENT TIME: 07:45[EST]|
| NRC NOTIFIED BY: ROY MATTESON |LAST UPDATE DATE: 04/05/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF METEOROLOGICAL INSTRUMENTATION DUE TO ADVERSE WEATHER |
| |
| "This notification is being made per 10CFR50.72.(b)3(xiii): Eight hour |
| Reports - Any event that results in a major loss of emergency assessment |
| capability, offsite response or offsite communications capability. |
| |
| "The following events have occurred: |
| Due to freezing rain and icing conditions a Loss of on-site (Main Tower and |
| JAF Tower) meteorological instrumentation for wind speed, wind direction and |
| delta T or sigma theta has occurred. This is considered to be a major loss |
| of emergency assessment capability and is reportable under 10CFR50.72. |
| |
| "Back up Meteorological information remains available." |
| |
| The licensee has notified the NRC Resident Inspector and county agencies and |
| will be notifying State agencies. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39738 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/06/2003|
| UNIT: [] [2] [] STATE: WI |NOTIFICATION TIME: 09:42[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/06/2003|
+------------------------------------------------+EVENT TIME: 05:30[CDT]|
| NRC NOTIFIED BY: MIKE MILLEN |LAST UPDATE DATE: 04/06/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRENT CLAYTON R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 55 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| "At 2050 4/05/03 it was identified that the requirements of LCO 3.1.6 |
| Control Bank Insertion Limits was not met for Unit 2. Control rod bank |
| overlap between control bank C and control bank D was at 126 steps instead |
| of the required 125 steps. Entered TSAC 3.1.6.B.1.1 to verify SDM to be |
| within the limits provided in the COLR within 1 hour and entered TSAC |
| 3.1.6.B.2 to restore control bank sequence and overlap to within limits |
| within 2 hours. |
| |
| "TSAC 3.1.6.B.1.1 was met at 2124 when SDM was verified to be within the |
| limits provided in the COLR. |
| |
| "At 2250 TSAC 3.1.6.B.2 required action was declared not met. Entered TSAC |
| 3.1.6.C.1 to be in MODE 2 with Keff < 1.0 within 6 hours. |
| |
| "Unit 2 entered MODE 3 at 0530 4/06/03 in accordance with TSAC 3.1.6.C.1." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 2222 EDT ON 4/6/03 FROM F. FLENTJE TO E. THOMAS * * * |
| |
| "A news release on the Unit 2 shutdown was issued by Nuclear Management |
| Company, LLC (NMC) at 1845 hours CDT on April 6, 2003. The NRC Resident |
| Inspector was notified at 2041 hours CDT on April 6, 2003, that the news |
| release had been issued. Event investigation and equipment repairs |
| continue. Current estimated restart date is April 8, 2003." |
| |
| Notified B. Clayton (R3DO) |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021