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Event Notification Report for March 10, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           03/07/2003 - 03/10/2003



                              ** EVENT NUMBERS **



39526  39575  39630  39643  39644  39645  39646  39647  39648  39649  39650  39651  



!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39526       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 01/20/2003|

|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 20:13[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/20/2003|

+------------------------------------------------+EVENT TIME:        14:30[EST]|

| NRC NOTIFIED BY:  JAMES WITTER                 |LAST UPDATE DATE:  03/07/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JOHN ROGGE           R1      |

|10 CFR SECTION:                                 |MOHAMED SHANBAKY     R1      |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| SERVICE WATER SYSTEM VALVE PIT PIPING PENETRATION SEAL                       |

|                                                                              |

| "On 1/20/2003 at 1430 hours, the Beaver Valley Power Station control room    |

| was notified by Engineering that a penetration seal previously installed in  |

| a wall which separates two service water system valve pits may have not been |

| adequate. A review of the supporting analysis shows that this penetration    |

| seal may not be qualified to withstand the hydraulic pressure which could    |

| result from a postulated internal flooding event occurring due to a service  |

| water system pipe failure filling the valve pit and its above compartment    |

| prior to operator intervention. A failure of this seal during a postulated   |

| internal flooding event may result in the loss of motor operated valve       |

| movement in both trains of the service water system that would be needed     |

| following a design basis accident (DBA).                                     |

|                                                                              |

| "This design basis calculation and the penetration seal capability are       |

| continuing to be evaluated. However, this seal could potentially have        |

| prevented the service water system from meeting single failure criterion     |

| during a postulated service water system pipe failure. Therefore, Technical  |

| Specification (TS) 3.7.4.1 was entered due to less than two trains of        |

| service water system being operable as a conservative decision based upon    |

| the limited information immediately available to show acceptable seal        |

| integrity at the postulated conditions. The TS Action requires restoration   |

| of two independent service water system trains within 72 hours. Actions are  |

| in progress to install a qualified seal which will prevent the unacceptable  |

| flooding conditions from being able to occur.                                |

|                                                                              |

| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an   |

| unanalyzed condition that significantly degraded plant safety since this     |

| seal has been installed for five months and may have invalidated the         |

| independence between the two service water system trains. The NRC resident   |

| has been notified of the degraded condition."                                |

|                                                                              |

| * * * RETRACTION RECEIVED AT 1002 EST ON 3/07/2003 BY WITTER TO CROUCH * * * |

|                                                                              |

|                                                                              |

| "Beaver Valley Power Station (BVPS) Unit No. 2 retracts the notification     |

| made on 01/20/2003 at 20:13 hrs [EST] regarding the event reported under 10  |

| CFR 50.72(b)(3)(ii)(B) [ENS #39526]. The previous notification identified a  |

| potential issue with a seal penetration which may have invalidated the       |

| independence between two Service Water System trains.                        |

|                                                                              |

| "Subsequent analysis of the event identified that the installed penetration  |

| seal between the two Service Water System valve pits would have been capable |

| of performing its intended safety function. Therefore, the separation and    |

| independence between the two Service Water System trains, as required by     |

| Technical Specification 3.7.4.1, would have been satisfied.                  |

|                                                                              |

| "Given that both trains of the Service Water System were able to perform     |

| their safety functions, this was not a condition that significantly degraded |

| plant safety."                                                               |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|General Information or Other                     |Event Number:   39575       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  MA RADIATION CONTROL PROGRAM         |NOTIFICATION DATE: 02/10/2003|

|LICENSEE:  PERKINELMER LIFE SCIENCES            |NOTIFICATION TIME: 14:29[EST]|

|    CITY:  BOSTON                   REGION:  1  |EVENT DATE:        07/18/2002|

|  COUNTY:                            STATE:  MA |EVENT TIME:             [EST]|

|LICENSE#:  00-3200               AGREEMENT:  Y  |LAST UPDATE DATE:  03/07/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |GLENN MEYER          R1      |

|                                                |DON COOL     EO      NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  CARPENITO                    |                             |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| POTENTIALLY MISSING  PHOSPHORUS-32 SHIPPING PACKAGES                         |

|                                                                              |

| Single packages containing P-32 (~14 day half-life) were destined for four   |

| different out-of-state locations (in CA, KS, NY and TX). Intended shipping   |

| dates were July 18, August 5 and August 6, 2002. Carrier reported packages   |

| potentially missing within 2-3 days after intended shipping dates. The       |

| per-package activities ranged from 250 microcuries to 1 millicurie. All      |

| subject radioactive material contents are presently well past ten            |

| half-lives. After several months of shipper-carrier joint investigation, the |

| cause(s) remain undetermined. Actions have been taken by shipper and carrier |

| to prevent recurrence.                                                       |

|                                                                              |

| * * * * UPDATE RECEIVED BY RIPLEY FROM CARPENITO 1448 EST ON 03/07/03 VIA    |

| FAX                                                                          |

|                                                                              |

| "Five additional single-package shipments (four P-32 and one I-125),         |

| destined for five different locations, shipped August 27, October 17,        |

| November 4 and 26, and December 13, 2002, were reported to MARCP as missing  |

| on 2/14/03.  The per-package activities ranged from 250 to 500 microcuries   |

| of P-32 and 50 microcuries I-125.  All subject packages were shipped before  |

| the shipper and carrier corrective actions had been implemented in late      |

| December 2002.  No packages shipped since the corrective actions have been   |

| implemented have been reported to MARCP as missing."                         |

|                                                                              |

| Notified NMSS EO (Reamer) and R1 DO (Shanbaky)                               |

+------------------------------------------------------------------------------+



!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39630       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 03/02/2003|

|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 10:43[EST]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        03/02/2003|

+------------------------------------------------+EVENT TIME:        03:35[CST]|

| NRC NOTIFIED BY:  LONG                         |LAST UPDATE DATE:  03/07/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID GRAVES         R4      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| PRIMARY CONTAINMENT MEASURED LEAKAGE EXCEEDS THE ALLOWED LEAKAGE.            |

|                                                                              |

| During routine scheduled LLRT (Local Leak Rate Testing) of Penetration       |

| X-214,  HPCI (High Pressure Coolant Injection) Exhaust Discharge to the      |

| Torus, leakage was unable to be quantified.   Additionally, of the two       |

| isolation check valves in the line, the licensee could not determine which   |

| one was leaking.   As such, Primary Containment Allowed Leakage (La) is      |

| unable to be verified to be less than allowed.                               |

|                                                                              |

| The plant was in Mode 4 (Cold S/D) for a scheduled refueling outage with     |

| temperature being maintained between 130 and 145 degrees Fahrenheit and      |

| Primary Containment not required at the time of discovery.  The plant will   |

| remain in cold shutdown until repairs are completed.                         |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

|                                                                              |

| * * * * RETRACTION RECEIVED AT 1326 EST ON 03/07/03 BY BLAIR TO RIPLEY * * * |

| *                                                                            |

|                                                                              |

| "On 3/2/03 at 0943 CST, Cooper Nuclear Station made an 8 hour 50.72          |

| non-emergency notification to the NRC.  This was done due to the failure of  |

| Local Leak Rate Testing (LLRT) involving the High Pressure Coolant Injection |

| (HPCI) exhaust discharge to the Suppression Chamber.  Leakage was unable to  |

| be quantified.  Additionally, of the two isolation check valves in the line, |

| testing was unable to determine which one was leaking.                       |

|                                                                              |

| "Based on indications of leakage during the LLRT, maintenance activities     |

| were started on one of the valves (HPCI-15CV).  Upon removal of the          |

| HPCI-15CV bonnet it was noticed that the valve was not properly seated.      |

| Engineering is continuing to evaluate this condition.  To facilitate         |

| continuing troubleshooting HPCI-15CV was manually closed by pushing the disk |

| into the valve seat.  The bonnet was re-installed and the LLRT was repeated. |

| The other check valve in this line (HPCI-44) was not touched or manipulated  |

| during the period of time between successive LLRT's.                         |

|                                                                              |

| "The results of the repeat LLRT were well within acceptance criteria limits  |

| demonstrating that HPCI-44 was properly performing its containment isolation |

| function.  Since HPCI-44 was working properly, the conditions that required  |

| an 8 hour 50.72 notification no longer apply. The penetration was always     |

| capable of performing the containment isolation function.                    |

|                                                                              |

| "The NRC Resident Inspector was notified."                                   |

|                                                                              |

| Notified R4 DO (D. Powers).                                                  |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39643       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 03/07/2003|

|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 19:17[EST]|

|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/07/2003|

+------------------------------------------------+EVENT TIME:        14:40[EST]|

| NRC NOTIFIED BY:  ROBERT KIDDER                |LAST UPDATE DATE:  03/07/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       R3      |

|10 CFR SECTION:                                 |JOHN DAVIDSON        IAT     |

|DDDD 73.71(b)(1)         SAFEGUARDS REPORTS     |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       83       Power Operation  |83       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| 1- HOUR SAFEGUARD REPORT                                                     |

|                                                                              |

| Discovery of criminal act involving individual granted access to the site.   |

| Immediate compensatory measures taken upon discovery.  Contact the           |

| Headquarters Operations Officer for details.                                 |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39644       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 03/07/2003|

|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 15:46[EST]|

|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        03/07/2003|

+------------------------------------------------+EVENT TIME:        14:39[EST]|

| NRC NOTIFIED BY:  JOHN CHUNIS                  |LAST UPDATE DATE:  03/07/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          UNUSUAL EVENT         |MOHAMED SHANBAKY     R1      |

|10 CFR SECTION:                                 |CHRISTOPHER GRIMES   NRR     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |JOSEPH HOLONICH      IRO     |

|                                                |MIKE EACHES          FEMA    |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     A/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| PLANT DECLARED UNUSUAL EVENT DUE TO REACTOR TRIP WITH LEAKAGE FROM CHARGING  |

| SYSTEM                                                                       |

|                                                                              |

| A reactor automatic trip was received at 1439 EST.  The cause of the trip is |

| unknown and investigation continues, although reactor protection system      |

| testing was in progress at the time of the trip.  All systems responded      |

| normally with the exception of the charging system.  The licensee declared   |

| an unusual event at 1516 EST due to charging pump discharge relief valves    |

| lifting thereby creating leakage into the auxiliary building.                |

| Preliminarily, the cause of the relief valve discharge was blockage in the   |

| normal charging line downstream.  Charging flow was reestablished via the    |

| alternate flowpath.  A minimal radioactive release from the auxiliary        |

| building ventilation resulted from the charging system leakage.              |

|                                                                              |

| The NRC Resident Inspector was notified.  State and local officials were     |

| notified and the licensee issued a press release.                            |

|                                                                              |

| * * * UPDATE 0420EST ON 3/8/03 FROM ROBERT MALONEY TO S.SANDIN * * *         |

| The licensee terminated the Unusual Event at 0146EST after Unit 2 entered    |

| mode 4.  The licensee informed state/local agencies and the NRC resident     |

| inspector.  Notified R1DO(Shanbaky), EO(Grimes) and FEMA(Stinedurf).         |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39645       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 03/07/2003|

|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 21:32[EST]|

|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        03/07/2003|

+------------------------------------------------+EVENT TIME:        20:49[EST]|

| NRC NOTIFIED BY:  ROBERT WHITE                 |LAST UPDATE DATE:  03/07/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          UNUSUAL EVENT         |MOHAMED SHANBAKY     R1      |

|10 CFR SECTION:                                 |JOSEPH HOLONICH      IRO     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |CHRISTOPHER GRIMES   NRR     |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |FEMA WATCH OFFICER   FEMA    |

|ADEV 50.72(b)(1)         DEVIATION FROM T SPEC  |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          N       0        Hot Standby      |0        Hot Standby      |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| UNUSUAL EVENT DECLARED DUE TO INABILITY TO REACH HOT SHUTDOWN WITHIN TECH    |

| SPEC ACTION STATEMENT TIME LIMIT                                             |

|                                                                              |

| The licensee declared an unusual event at 2049 EST due to the inability to   |

| reach Mode 4  within the Technical Specification action statement time limit |

| of 2049 EST for charging pumps inoperable.  The charging pumps were declared |

| inoperable as a result of system complications associated with the reactor   |

| trip and charging system leakage occurring at 1439 EST 3/7/03 (see Event #   |

| 39644).                                                                      |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

|                                                                              |

| * * * UPDATE 0420EST ON 3/8/03 FROM ROBERT MALONEY TO S.SANDIN * * *         |

| The licensee terminated the Unusual Event at 0146EST after Unit 2 entered    |

| mode 4.  The licensee informed state/local agencies and the NRC resident     |

| inspector.  Notified R1DO(Shanbaky), EO(Grimes) and FEMA(Stinedurf).         |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39646       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 03/07/2003|

|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 22:06[EST]|

|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/07/2003|

+------------------------------------------------+EVENT TIME:        13:31[CST]|

| NRC NOTIFIED BY:  BRYAN KELLEY                 |LAST UPDATE DATE:  03/07/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DALE POWERS          R4      |

|10 CFR SECTION:                                 |                             |

|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       88       Power Operation  |88       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| OPEN AUXILIARY BUILDING DOOR COULD HAVE CAUSED A LOSS OF SECONDARY           |

| CONTAINMENT FUNCTION                                                         |

|                                                                              |

| "At 1622 CST on 3/7/03, a Condition Report was written to identify that      |

| Auxiliary Building door PW-95-02 was open because a door assist device       |

| malfunction prevented closure of the door. This condition existed from 1331  |

| until 1449 on 3/7/03.                                                        |

|                                                                              |

| "This condition could have resulted in a loss of function of the Secondary   |

| Containment since Standby Gas Treatment system may not have been able to     |

| draw down pressure in the Auxiliary Building to the required vacuum."        |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39647       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 03/08/2003|

|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 01:58[EST]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/07/2003|

+------------------------------------------------+EVENT TIME:        23:55[EST]|

| NRC NOTIFIED BY:  DAVE JESTER                  |LAST UPDATE DATE:  03/08/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |CAROLYN EVANS        R2      |

|10 CFR SECTION:                                 |                             |

|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     N          Y       22       Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| AUTOMATIC DIESEL ACTUATION CAUSED BY LOSS OF GENERATION EXCITATION TRIP      |

|                                                                              |

| "During planned Unit Two manual scram in preparation for refueling outage,   |

| all four Emergency Diesel Generators received an auto start signal.  Auto    |

| start signal was generated from a Primary Generator Lockout caused by a Loss |

| of Generator ExcitatIon Trip.  A 1/2 Group 1 signal was also received during |

| the shutdown due to a steam flow trip unit failure, which has been repaired. |

| All other systems operated as designed, scram actions completed, plant       |

| stable.  The Loss of Excitation Trip should have been blocked by main        |

| generator PCB openings.  Investigation currently underway to determine cause |

| of Loss of Excitation Trip malfunction."                                     |

|                                                                              |

| There was no loss of power.  The busses were not loaded after all four       |

| diesels started. The diesels operated normally and have been returned to a   |

| standby lineup.  All other systems operated as required.                     |

|                                                                              |

| The Licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39648       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/09/2003|

|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 04:08[EST]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/09/2003|

+------------------------------------------------+EVENT TIME:        03:12[EST]|

| NRC NOTIFIED BY:  DON ROLAND                   |LAST UPDATE DATE:  03/09/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     R1      |

|10 CFR SECTION:                                 |                             |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       100      Power Operation  |100      Power Operation  |

|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| OFFSITE NOTIFICATION                                                         |

|                                                                              |

| "On 3/9/03 at 0140 the Main Control Room was notified that an ambulance was  |

| requested at the site.  A contract pipe fitter working in Primary            |

| Containment on unit 2 experienced heat stress.  Site EMT's stabilized the    |

| individual and he was transported to a local hospital for treatment.  The    |

| individual was not contaminated.  The ambulance left site at 0216, and the   |

| Pennsylvania Emergency Management Agency was notified at 0312.  Due to       |

| notification to another government agency, this event is reportable under    |

| 10CFR50.72(b)(2)(xi)."                                                       |

|                                                                              |

| The Licensee notified the State of Pennsylvania and will notify the NRC      |

| Resident Inspector.                                                          |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39649       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/09/2003|

|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 12:08[EST]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/08/2003|

+------------------------------------------------+EVENT TIME:        22:18[EST]|

| NRC NOTIFIED BY:  GRANT FERNSLER               |LAST UPDATE DATE:  03/09/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     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   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| LOSS OF EMERGENCY ASSESSMENT CAPABILITY FOR GREATER THAN 8 HOURS             |

|                                                                              |

| "On 3/9/03 the Main Control Room was notified that the Unit 2 SPDS [Safety   |

| Parameter Display System] computer was not updating properly.  A review into |

| the history identified that the SPDS computer had stopped updating at 22:18  |

| on 3/8/03.  The computer group attempted to reset the SPDS computer to       |

| correct the condition.  The reset was successful and all indication returned |

| to normal.                                                                   |

|                                                                              |

| "Since the Unit 2 SPDS computer system was unavailable for greater than 8    |

| hours, this is considered a Loss of Emergency Assessment Capability and      |

| therefore reportable under 10CFR50.72(b)(3)(xiii)."                          |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39650       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 03/10/2003|

|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 00:46[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/09/2003|

+------------------------------------------------+EVENT TIME:        20:47[CST]|

| NRC NOTIFIED BY:  JONATHAN PIERCE              |LAST UPDATE DATE:  03/10/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DALE POWERS          R4      |

|10 CFR SECTION:                                 |                             |

|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     N          N       0        Hot Standby      |0        Hot Standby      |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| SAFETY INJECTION SYSTEM  ACTUATION AND CAUSE UNDER INVESTIGATION             |

|                                                                              |

| "At 20:47 on 3/9/03, Unit 2 experienced a Safety Injection while the plant   |

| was stable at NOP(2235 psig)/NOT                                             |

| (567 degrees) in Mode 3.  All systems actuated as designed.  An operator was |

| operating the 'B'  S/G PORV shortly                                          |

| before the event occurred.  All MSIVs were closed for ongoing work on the    |

| main turbine. The Sequence of                                                |

| events report showed all 3 channels of steam pressure spiking low on the 'B' |

| Steam Generator as the cause of the event. Initial look at trends on the     |

| integrated computer system showed [that] steam pressure channels did not     |

| lower to a point to cause the safety injection.  An Event Review Team is     |

| being formed to investigate this event.                                      |

|                                                                              |

| "A Reactor Coolant System PORV opened due to high pressure when the Spray    |

| valves closed due to the Instrument Air isolation (due to phase 'A') with    |

| the Pressurizer Heaters in manual. The Pressurizer heaters were secured and  |

| Reactor coolant System pressure stabilized.  All ESF systems actuated as     |

| designed. The following systems actuated: Auxiliary Feedwater, Safety        |

| Injection, Phase 'A', Control Room Envelope and Fuel Handling Building HVAC  |

| systems, Essential Cooling Water, Component Cooling Water, Emergency Diesel  |

| Generators and ESF sequencers."                                              |

|                                                                              |

| There was no safety injection since pressure was maintained above 2199 psi   |

| during the transient (Hi Head is 1700 psi).  Heat removal is being performed |

| through S/G PORVs and Unit 2 is currently stable at Mode 3.                  |

|                                                                              |

| The Licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39651       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 03/10/2003|

|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 03:45[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/10/2003|

+------------------------------------------------+EVENT TIME:        00:12[EST]|

| NRC NOTIFIED BY:  JOHN RODEN                   |LAST UPDATE DATE:  03/10/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |STEPHEN CAHILL       R2      |

|10 CFR SECTION:                                 |CAROLYN EVANS        R2      |

|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   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP ON GENERATOR DIFFERENTIAL RELAY   |

| ACTUATION                                                                    |

|                                                                              |

| "At 0012 EST on March 10, 2003, with Watts Bar Unit 1 in Mode 1 at 100%      |

| power, the reactor tripped due to an automatic signal.  All plant safety     |

| systems were in service at the time to the trip, except  for the 2B-B diesel |

| generator which was out of service for scheduled maintenance, and all        |

| [safety systems] responded as designed.  All control rods inserted as        |

| required and the Auxiliary Feedwater System [AFW] initiated as expected.     |

|                                                                              |

| "The reactor trip resulted from a turbine trip signal that was generated as  |

| a result of a main generator/transformer differential electrical relay       |

| actuation.  The plant is currently stable in Mode 3 and will remain in this  |

| Mode until completion of the investigation."                                 |

|                                                                              |

| AFW was removed from operation and the main feed pumps have resumed normal   |

| feed to the Steam Generators.  The Licensee notified the NRC Resident        |

| Inspector.                                                                   |

+------------------------------------------------------------------------------+