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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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)                                                   |
+------------------------------------------------------------------------------+