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Event Notification Report for April 1, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           03/31/2003 - 04/01/2003



                              ** EVENT NUMBERS **



39631  39645  39696  39706  39707  39708  39715  39716  



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

|Power Reactor                                    |Event Number:   39631       |

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

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

| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 03/02/2003|

|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 16:00[EST]|

|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        03/02/2003|

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

| NRC NOTIFIED BY:  CHARLES PIKE                 |LAST UPDATE DATE:  03/31/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       R2      |

|10 CFR SECTION:                                 |DAVID AYRES          R2      |

|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          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| OFFSITE NOTIFICATION TO STATE AGENCY OF EXPIRED GREEN SEA TURTLE FOUND AT    |

| BARRIER NET                                                                  |

|                                                                              |

| "NRC notification [is] being made due to state notification to [the] Florida |

| Wildlife Commission regarding a Green Sea Turtle found dead at barrier net   |

| pursuant to 10 CFR 50.72(b)(2)(xi)."                                         |

|                                                                              |

| The turtle was found on the surface at the barrier net with no injuries or   |

| abnormalities except for fresh cuts common for turtles coming through pipes. |

| The cause of death is unknown at this time. A necropsy is planned.           |

|                                                                              |

| The NRC Resident Inspector will be notified by the licensee.                 |

|                                                                              |

| * * * UPDATE ON 3/15/03 @ 1033 EST FROM TEREZAKIS TO CROUCH * * *            |

|                                                                              |

| "On 3-15-03, a green sea turtle was retrieved from the plant's intake canal. |

| The turtle was determined to be in need of rehabilitation.  The injuries to  |

| the turtle are not causal to plant operation. Per the plant's turtle permit, |

| the Florida Fish and Wildlife Conservation Commission (FWCC) was notified at |

| 0920 EST.  This non-emergency notification is being made pursuant to 10 CFR  |

| 50.72(b)(2)(xi) due to the notification of FWCC."                            |

|                                                                              |

| The NRC Resident Inspector will be notified by the licensee.                 |

|                                                                              |

| * * * UPDATE ON 3/19/03 AT 1222 EST FROM E. SUMNER TO RIPLEY  * * *          |

|                                                                              |

| "On 03/19/03 @ 1105 hrs., one loggerhead turtle was retrieved from the       |

| plant's intake canal.  The turtle was determined to be in need of            |

| rehabilitation.  The injury to the turtle is not causal to plant operation.  |

| Per the plant's turtle permit, the Florida Fish and Wildlife Conservation    |

| Commission (FWCC) was notified at 1115 EST."                                 |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

|                                                                              |

| * * * UPDATED ON 3/31/03 AT 1159 EST FROM W.L. PARK TO A. COSTA * * *        |

|                                                                              |

| "On 3-31-03 [1105 EST], a loggerhead sea turtle was retrieved from the       |

| plant's intake canal. The turtle was determined to be in need of             |

| rehabilitation. The injuries to the turtle are not causal to plant           |

| operation. Per the plant's turtle permit, the Florida Fish and Wildlife      |

| Conservation Commission (FWCC) was notified at 1105 EST. This non-emergency  |

| notification is being made pursuant to 10 CFR 50.72(b)(2)(xi) due to the     |

| notification of FWCC."                                                       |

|                                                                              |

| The NRC Resident Inspector will be notified.                                 |

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



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

|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:  03/31/2003|

|  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    |

|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   |

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

|                                                   |                          |

|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).         |

|                                                                              |

| * * * UPDATE 0944EST ON 3/31/03 FROM STEPHEN BAKER TO S. SANDIN * * *        |

|                                                                              |

| The following information was submitted as an update:                        |

|                                                                              |

| "On March 7, 2003, Millstone Unit No. 2 made a 1-hour report of an Unusual   |

| Event declared due to an inability to reach hot shutdown within Tech Spec    |

| action statement time limit (Event no. 39645). This notification was made    |

| because the required Mode was not reached within the required Tech Spec      |

| action time. Three charging pumps were declared inoperable resulting in an   |

| entry into TS 3.0.3. The appropriate Mode could not be reached within the    |

| time prescribed by the TS due to the inability of the charging system to     |

| supply adequate makeup to the RCS through the normal flow path. An alternate |

| alignment was established via HPSI, The limited rate of makeup via this      |

| alternate path prevented the plant from reaching Mode 4 within the allowed   |

| outage time.                                                                 |

|                                                                              |

| "The criteria for deviation from plant Tech Specs was inappropriately        |

| checked off as it was interpreted to mean a violation of plant Tech Specs.   |

| Criterion 10CFR50.72(b)(1) 'deviation from the plant's Tech Specs pursuant   |

| to  50.54(x)' did not apply.                                                |

|                                                                              |

| "Additionally, criterion 10CFR50.72(b)(3)(v)(A), loss of safety function,    |

| did apply and this event should have been reported under this criterion      |

| since three charging pumps were declared inoperable."                        |

|                                                                              |

| The licensee will inform the NRC resident inspector.  Notified R1DO          |

| (Bellamy).                                                                   |

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



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

|Fuel Cycle Facility                              |Event Number:   39696       |

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

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

| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 03/25/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 01:15[EST]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/24/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        00:30[CST]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/31/2003|

|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+

|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |

|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MICHAEL PARKER       R3      |

|  DOCKET:  0707001                              |LARRY CAMPER         NMSS    |

+------------------------------------------------+JOHN JOLICOEUR       IRO     |

| NRC NOTIFIED BY:  TOM WHITE                    |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NBNL                     RESPONSE-BULLETIN      |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| BULLETIN 91-01 24 HOUR REPORT FOR CRITICALITY CONTROL                        |

|                                                                              |

| At 0030 on 3-24-03, the Plant Shift Superintendent (PSS) was notified that   |

| nine (9) pallets of process equipment containing less than a safe uranium    |

| mass and spaced 2 feet edge to edge were discovered in C-335. NCSA GEN-010   |

| requires that the total uranium mass of an equipment group be independently  |

| verified and documented to be less than or equal to a safe mass based on the |

| highest assay according to CP2-PO-FO1031. No documentation exists to support |

| that the total uranium mass was verified or independently verified according |

| to CP2-PO-FO1031 in violation of NCSA GEN-010.                               |

|                                                                              |

| The NRC Senior Resident Inspector has been notified of this event.           |

|                                                                              |

| PGDP Assessment and Tracking Report No. ATR 03-0876; PGDP Event Report No.   |

| PAD-2003-006, NRC Event Worksheet [EN 39696].                                |

|                                                                              |

| Responsible Division: Operations                                             |

|                                                                              |

| SAFETY SIGNIFICANCE OF EVENTS:                                               |

|                                                                              |

| Although the total mass of the grouped items was not independently verified  |

| to be less than a safe mass, no single pallet contains greater than 35       |

| pounds of uranium. The highest enrichment of any item was 2.0 wt. % 235U.    |

| The safe mass for uranium at 2.0 wt. % 235U is approximately 250 pounds.     |

|                                                                              |

| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW            |

| CRITICALITY COULD OCCUR                                                      |

|                                                                              |

| In order for a criticality to be possible, greater than a safe mass of       |

| uranium must be accumulated and then become moderated.                       |

|                                                                              |

| CONTROLLED PARAMETERS MASS. MODERATION, GEOMETRY, CONCENTRATION, ETC         |

|                                                                              |

| Double contingency is maintained by implementation of two controls           |

| (verification and independent verification) of mass.                         |

|                                                                              |

| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |

| LIMIT AND % WORST CASE CRITICAL MASS);                                       |

|                                                                              |

| No single pallet has greater than 35 pounds of uranium and the highest assay |

| of any Item is 2.0 wt. % 235U. The safe mass for this assay is 250 pounds.   |

|                                                                              |

| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |

| OF THE FAILURES OR DEFICIENCIES                                              |

|                                                                              |

| The first leg of double contingency is based on mass. NCSA GEN-010 requires  |

| that the total uranium mass of grouped items be verified less than the UH    |

| [Uncomplicated Handling] mass limit and documented. No documentation exists  |

| that substantiates that this verification was performed; therefore, this     |

| control was violated. However, since none of the groups contain greater than |

| a safe mass this parameter was not exceeded.                                 |

|                                                                              |

| The second leg of double contingency is based on mass. NCSA GEN-010 requires |

| that the total uranium mass of grouped items be independently verified less  |

| than the UH mass limit and documented in accordance with CP2-PO-FO1031. No   |

| documentation exists that substantiates that this independent verification   |

| was performed; therefore, this control was violated.                         |

|                                                                              |

| Even though the mass parameter was maintained, double contingency is based   |

| on two controls on mass. Since neither control was maintained, double        |

| contingency was not maintained.                                              |

|                                                                              |

| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |

|                                                                              |

| 1. Properly group and document each pallet according to CP2-CO-CN2030.       |

| 2. Upon completion of corrective action 1 for each of the 9 pallets, the     |

| exclusion zone and postings may be removed.                                  |

|                                                                              |

| *** UPDATE ON 3/31/03 AT 2137 EST FROM T. WHITE TO A. COSTA ***              |

|                                                                              |

| "As a result of further investigation, four additional palettes of process   |

| equipment containing less than a safe mass were discovered in C-335 at Col   |

| W-26 to  W-27 (the original event was in C-335 Col D-2 to D-3). These        |

| additional pallets exist in the same state as the original nine.  No         |

| documentation exists to support that the total uranium mass was verified or  |

| independently verified according to CP2-PO-FO1031 in violation of NCSA       |

| GEN-010.                                                                     |

|                                                                              |

| "The NRC Resident Inspector has been notified of this update.                |

|                                                                              |

| "PGDP Assessment and Tracking Report No. ATR 03-0943."                       |

|                                                                              |

| Notified R3DO (Clayton), NMSS EO (Frant) and DIRO (Jolicoeur).               |

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



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

|General Information or Other                     |Event Number:   39706       |

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

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

| REP ORG:  ILLINOIS DEPT OF NUCLEAR SAFETY      |NOTIFICATION DATE: 03/27/2003|

|LICENSEE:  SOURCE TECH MEDICAL                  |NOTIFICATION TIME: 16:22[EST]|

|    CITY:  SCHAUMBERG               REGION:  3  |EVENT DATE:        03/26/2003|

|  COUNTY:                            STATE:  IL |EVENT TIME:        15:00[CST]|

|LICENSE#:  IL-02062-01           AGREEMENT:  Y  |LAST UPDATE DATE:  03/27/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |MICHAEL PARKER       R3      |

|                                                |RUDOLPH BERNHARD     R2      |

+------------------------------------------------+E. WILLIAM BRACH     NMSS    |

| NRC NOTIFIED BY:  JOE KLINGER (E-MAIL)         |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| AGREEMENT STATE REPORT - LOST OR STOLEN IODINE SOURCES                       |

|                                                                              |

| The following information was received via e-mail from the Illinois          |

| Department of Nuclear Safety:                                                |

|                                                                              |

| "[DELETED], RSO of SourceTech Medical [(DELETED)] in Carol Stream, IL called |

| at 1500 hours on March 26, 2003, to report that he had received a shipment   |

| of returned I-125 seeds.  The dose rate on the surface of the package was 9  |

| [millirem/hr] instead of the expected dose rate of less than 0.5             |

| [millirem/hr].   Upon opening the box, 2 loose sources were found on top of  |

| the packing material.  7 sources were noted in the shipping papers.   An     |

| additional source was found in a partially loaded Mick applicator but there  |

| were no sources in the second Mick applicator.  A total of only 3 sources    |

| were found after looking through the other two lead containers in the        |

| package.                                                                     |

|                                                                              |

| "Based on assay of the three seeds, the 4 missing seeds are 425 [microcurie] |

| I-125 each for a total of 1.7 [millicurie].  The contents of the package     |

| (Fed Ex tracking no., [DELETED]) were obviously not prepared in accordance   |

| with instructions provided by Source Tech in that the lids to the containers |

| were not secured nor were the vials used in the lead containers as the       |

| instructions call for.  The carrier, Federal Express had been contacted by   |

| [DELETED] and the delivery truck surveyed.  No sources were located during   |

| the survey.   According to tracking information, the package had gone from   |

| St. Augustine through Jacksonville FL, Atlanta GA, Memphis TN, Chicago, IL   |

| and the Schaumburg IL sorting facility prior to delivery in Carol Stream.    |

| An inspector was dispatched to the Schaumburg facility at 15:45 to attempt a |

| search of the Schaumburg facility.                                           |

|                                                                              |

| "The sources were shipped from Slagley Hospital (Florida [DELETED]) in St.   |

| Augustine Florida on Monday 3/24/2003. [DELETED] tried contacting the site   |

| RSO, [DELETED], this afternoon but was unsuccessful.  The department         |

| contacted Mr. [DELETED] of the Florida program in their Orlando office and   |

| relayed the information available at the time (see above).  He indicated     |

| that he would attempt a call as well but suspected the hospital staff would  |

| be gone given the time of day (16:30) in Fla.  On 3/27/03, [DELETED]         |

| notified the department that he contacted the Florida licensee and the St.   |

| Augustine hospital claimed that they counted twice the seven seeds not used  |

| in a patient, placed them in a 'screwed sealed cartridge' then put them in a |

| shipping box for FedEx.  The department also informed [DELETED], Ph.D.,      |

| health physics consultant for FedEx, that there are apparently 4 iodine-125  |

| seeds in FedEx facilities or vehicles somewhere as indicated by the routing  |

| in the message below.  Jim Lynch of the NRC was also advised  of the         |

| situation. On 03/26/03, a departmental inspector  arrived at the Federal     |

| Express Depot located at 1270 Wilkening Road in Schaumburg; [DELETED] and    |

| explained the purpose of the visit.  The inspector was provided access to    |

| the package/truck staging area.  Based on the FedEx tracking number, the     |

| author was told that the bay used by the vehicle was the same one used in a  |

| previous, recent incident involving I-125 seeds.  Surveys were performed by  |

| the inspector using an Eberline Model PRM-6 ratemeter, serial number 1470,   |

| last calibrated on May 16, 2002, with an Eberline Model LEG-1 probe.         |

| Background readings were [approximately] 250 - 350 CPM.  Areas surveyed      |

| included the conveyor belt system, particularly junctions between belts,     |

| walkways, and the concrete pad where vehicles park for loading/unloading.    |

| Particular attention was paid to the area where the truck was unloaded and   |

| the seeds had been found in the previous incident.  No seeds were located by |

| the inspector.   The department is reviewing the packaging used by           |

| SourceTech and the instructions to see if there they can be improved to      |

| prevent recurrences.  The event was reported to the NRC Operations Center at |

| 1622 hours EST on 3/27/03 and assigned Event No. 39706.  A copy of this      |

| report was electronically forwarded to the Ops Center as well as the states  |

| of FL, GA, TN and NRC   Region III."                                         |

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



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

|General Information or Other                     |Event Number:   39707       |

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

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

| REP ORG:  NEW YORK STATE DEPT. OF HEALTH       |NOTIFICATION DATE: 03/27/2003|

|LICENSEE:  NOT AVAILABLE                        |NOTIFICATION TIME: 17:40[EST]|

|    CITY:                           REGION:  1  |EVENT DATE:        03/27/2003|

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

|LICENSE#:  NOT AVAILABLE         AGREEMENT:  Y  |LAST UPDATE DATE:  03/27/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |PAMELA HENDERSON     R1      |

|                                                |E. WILLIAM BRACH     NMSS    |

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

| NRC NOTIFIED BY:  ROBERT DANSEREAU (FAX)       |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION                           |

|                                                                              |

| The following information was received from the New York State Department of |

| Health, Bureau of Environmental Radiation Protection:                        |

|                                                                              |

| "This notice is in regard to a medical misadministration involving a Novoste |

| Beta-Cath IVB 3.5F system, Model A1767 with AEAT Model SIC W.2 source train. |

| The event occurred on March 25, 2003.                                        |

|                                                                              |

| "Two attempts to advance the source train into the delivery catheter were    |

| unsuccessful. A third (and final) attempt resulted in the source train       |

| becoming stuck in the patient's femoral artery, somewhere in the lower groin |

| area. The sources could not be returned to the base unit. The treatment team |

| then removed the catheter, with the source extended, and placed these items  |

| into the emergency bailout box.                                              |

|                                                                              |

| "The licensee estimated that the patient received an exposure of 250 Rads to |

| an area of the femoral artery in the lower groin area. The oncologist and    |

| cardiologist decided not to proceed with IVB treatment of this patient.      |

| Hospital staff concluded that the misdirected radiation exposure would not   |

| have a significant health effect on the patient.                             |

|                                                                              |

| "This event meets the reporting requirements in 10 NYCRR 16. The facility    |

| will investigate the circumstances, procedures, training, history of use,    |

| etc., and will submit a written report within 7 days. The device, including  |

| catheter and hydraulic attachment (syringe) will be sent to the vendor for   |

| evaluation."                                                                 |

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



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

|General Information or Other                     |Event Number:   39708       |

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

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

| REP ORG:  ALABAMA RADIATION CONTROL            |NOTIFICATION DATE: 03/27/2003|

|LICENSEE:  THOMPSON ENGINEERING AND TESTING, INC|NOTIFICATION TIME: 15:18[EST]|

|    CITY:                           REGION:  2  |EVENT DATE:        03/27/2003|

|  COUNTY:                            STATE:  AL |EVENT TIME:             [CST]|

|LICENSE#:  694                   AGREEMENT:  Y  |LAST UPDATE DATE:  03/27/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |RUDOLPH BERNHARD     R2      |

|                                                |E. WILLIAM BRACH     NMSS    |

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

| NRC NOTIFIED BY:  DAVID WALTER (FAX)           |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| AGREEMENT STATE REPORT - LOST TROXLER MOISTURE/DENSITY GAUGE                 |

|                                                                              |

| The following information was received from Alabama Office of Radiation      |

| Control via facsimile:                                                       |

|                                                                              |

| "The Agency has been notified by Thompson Engineering and Testing, Inc. that |

| a Troxler Model 3440 Gauge (serial #32128) containing a maximum of 9         |

| millicuries of cesium 137 and 44 millicuries of americium 241/beryllium is   |

| missing. They have conducted a search of many of their Alabama offices, and  |

| have been unable to locate it.  Since their records do not show this device  |

| being used in some time, it had been in storage, and was not detected as     |

| lost until the six month leak test was due.  They are continuing to search   |

| for the gauge, and will notify this office of their findings."               |

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



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

|Power Reactor                                    |Event Number:   39715       |

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

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

| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 03/31/2003|

|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 15:40[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/31/2003|

+------------------------------------------------+EVENT TIME:        12:59[EST]|

| NRC NOTIFIED BY:  ROBERT RINK                  |LAST UPDATE DATE:  03/31/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |RUDOLPH BERNHARD     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       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| AUTOMATIC REACTOR TRIP DUE TO A MAIN FEEDWATER REGULATING VALVE FAILING      |

| CLOSED                                                                       |

|                                                                              |

| "While Unit 2 was operation at 100% power steady state, 'C' MFRV [Main       |

| Feedwater Regulating Valve] failed closed due to a failed driver card at     |

| 1259 [EST].  The reactor automatically tripped 13 [thirteen] seconds later   |

| due to steam flow greater than feed flow coincident with a low SG [Steam     |

| Generator] level in the 'C' SG as expected.  This is a 4 [four] hour         |

| notification.                                                                |

|                                                                              |

| "All 3 [three] AFW [Auxiliary Feedwater] pumps auto started due to a low-low |

| SG level in 'C' SG as expected.  This is an 8 [eight] hour notification.     |

|                                                                              |

| "The unit is stable in Mode 3.  Expect to re-start after repairs are made to |

| 'C' MFRV circuitry."                                                         |

|                                                                              |

| All rods inserted normally.  All safety and electrical systems operated as   |

| designed during and after the reactor trip.  There was nothing unusual or    |

| not understood.                                                              |

|                                                                              |

| The NRC Resident Inspector has been notified.                                |

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



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

|Power Reactor                                    |Event Number:   39716       |

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

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

| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 03/31/2003|

|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 18:03[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/31/2003|

+------------------------------------------------+EVENT TIME:        16:25[CST]|

| NRC NOTIFIED BY:  RICK LULLING                 |LAST UPDATE DATE:  03/31/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |RUDOLPH BERNHARD     R2      |

|10 CFR SECTION:                                 |CATHY HANEY          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          N       0        Cold Shutdown    |0        Cold Shutdown    |

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

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| LOST/MISSING SAFEGUARDS INFORMATION                                          |

|                                                                              |

| Compensatory measures not required at this time.                             |

|                                                                              |

| The licensee will be informing the NRC Resident Inspector.                   |

|                                                                              |

| Contact the Headquarters Operations Officer for additional details.          |

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