United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 1999

Event Notification Report for June 2, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/28/1999 - 06/02/1999

                              ** EVENT NUMBERS **

35666  35772  35774  35775  35776  35777  35778  35779  35780  35781  35782  35783 
35784  35785  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35666       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 05/03/1999|
|    UNIT:  [] [2] []                 STATE:  NJ |NOTIFICATION TIME: 13:12[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/03/1999|
+------------------------------------------------+EVENT TIME:        10:00[EDT]|
| NRC NOTIFIED BY:  JOSEPH SULLIVAN              |LAST UPDATE DATE:  06/01/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ONE HIGH HEAD SAFETY INJECTION LINE DETERMINED NOT TO HAVE FLOW DURING       |
| TESTING                                                                      |
|                                                                              |
| "During performance of the 18 month high head charging valve throttle test,  |
| it was discovered that the #21 high head cold leg injection line did not     |
| pass flow until the other three lines for high head cold leg injection were  |
| closed.  At that point, an audible indication was heard and flow was         |
| observed through the #21 cold leg.  All cold leg injection flows were        |
| subsequently balanced.  The cause of this is under investigation and will be |
| resolved prior to Mode 4."                                                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector and will be notifying the   |
| local government agencies.                                                   |
|                                                                              |
| * * * UPDATE AT 1212 ON 6/1/99 BY SIMPSON TAKEN BY WEAVER * * *              |
|                                                                              |
| On 5/3/99,  Salem Unit 2 reported an event concerning a safety injection     |
| system cold leg injection line which appeared to not pass flow during the    |
| performance in an 18 month surveillance test for flow balancing.   The       |
| discrepancy appeared to be due to a stuck check valve.   At the time of the  |
| event it was not known how long the condition had existed thus a 50.72 call  |
| was made.  The valve in question (21SJ17) was subsequently physically        |
| removed from the system and inspected.  No failure mode was determined.  No  |
| evidence was found that the valve had been inoperable for any length of      |
| time.  These valves do not have a history of negative performance in this    |
| application.  A review of' industry data did not identify any similar        |
| sticking problems, generally the failure reported concerned leakage.         |
| Therefore, the guidance of NUREG 1022 applies.  This guidance states that    |
| the out of service time is calculated using the  time of discovery unless    |
| there is firm evidence based on a review of relevant information (e.g. the   |
| equipment history and cause of failure) to believe the discrepancy existed   |
| previously.  Based on the time of discovery being the event date,  this      |
| event is not reportable because the requirements of the Technical            |
| Specifications were being met for the current mode of operations and the     |
| event is bounded by current design.  Further review of the design bases is   |
| underway to confirm assumptions.                                             |
|                                                                              |
| The licensee informed the NRC resident inspector.  The Operations Center     |
| informed R1DO (Conte).                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35772       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WILLIAM BEAUMONT HOSPITAL            |NOTIFICATION DATE: 05/27/1999|
|LICENSEE:  WILLIAM BEAUMONT HOSPITAL            |NOTIFICATION TIME: 13:41[EDT]|
|    CITY:  ROYAL OAK                REGION:  3  |EVENT DATE:        05/26/1999|
|  COUNTY:                            STATE:  MI |EVENT TIME:        14:30[EDT]|
|LICENSE#:  21-01333-01           AGREEMENT:  N  |LAST UPDATE DATE:  05/28/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROGER LANKSBURY      R3      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHERYL SCHULTZ, RSO          |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - HOSPITAL DOSIMETER MEASURED A DOSE READING OF GREATER THAN 1000 RADS -     |
|                                                                              |
| AT 1430 ON 05/26/99, LYNN [LAST NAME UNKNOWN] EMPLOYED BY LANDAUER RADIATION |
| BADGE DOSIMETRY COMPANY, GLENWOOD, IL, REPORTED TO CHERYL SCHULTZ, RADIATION |
| SAFETY OFFICER (RSO), WILLIAM BEAUMONT HOSPITAL, ROYAL OAK, MI, THAT ONE OF  |
| BEAUMONT HOSPITAL'S RADIATION DOSIMETERS MEASURED A DOSE READING OF GREATER  |
| THAN 1000 RADS.  THE RADIATION DOSIMETER IS A LUXEL ALUMINUM OXIDE FILMLESS  |
| RADIATION DOSIMETER THAT HAS BEEN USED IN THE INDUSTRY SINCE THE FALL OF     |
| 1998.  THIS TYPE OF DOSIMETER HAS BEEN USED AT BEAUMONT HOSPITAL SINCE       |
| JANUARY 1999.  THE HOSPITAL MEDICAL TECHNOLOGIST WHO USED THIS DOSIMETER     |
| WORKS IN A BLOOD BANK AND LAST USED A BLOOD IRRADIATOR IN APRIL 1999.  THE   |
| IRRADIATOR CONTAINS A SELF CONTAINED SEALED 10,000 CURIE CESIUM-137          |
| RADIATION SOURCE.                                                            |
|                                                                              |
| THE HOSPITAL RSO STATED THAT THE IRRADIATOR IS FUNCTIONING PROPERLY AND THAT |
| THE TECHNOLOGIST DID NOT RECEIVE THIS HIGH DOSE.  THE RSO FURTHER STATED     |
| THAT HOSPITAL PERSONNEL HAVE NEVER RECEIVED GREATER THAN 0.06 MR/HR MAXIMUM  |
| DOSE RATE WITH THE IRRADIATOR SOURCE EXPOSED.  THE RSO BELIEVES THAT THE     |
| DOSE READING IS INCORRECT OR THAT THE DOSIMETER SOMEHOW BECAME IRRADIATED.   |
| THE DOSIMETRY COMPANY REPRESENTATIVE STATED THAT THE DOSIMETER READINGS WERE |
| OBTAINED TWICE AND THE DOSIMETER IS NOT DAMAGED.                             |
|                                                                              |
| THE HOSPITAL RSO PLANS TO OBTAIN A BLOOD SAMPLE FROM THE TECHNOLOGIST AND    |
| HAVE IT ANALYZED ON 05/27/99.                                                |
|                                                                              |
| * * * UPDATE 5/28/99 FROM BRIAN SMITH (NMSS) TAKEN BY STRANSKY  * * *        |
|                                                                              |
| The blood irradiator is a CIS-US Model IBL-473C with a source strength of    |
| approximately 2,000 Ci, contrary to the information provided in the initial  |
| report.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35774       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  GEORGIA DEPT. OF NATURAL RESOURCES   |NOTIFICATION DATE: 05/28/1999|
|LICENSEE:  THERAGENICS, INC.                    |NOTIFICATION TIME: 10:05[EDT]|
|    CITY:  BUFORD                   REGION:  2  |EVENT DATE:        05/26/1999|
|  COUNTY:                            STATE:  GA |EVENT TIME:        08:00[EDT]|
|LICENSE#:  GA 881-2MD            AGREEMENT:  Y  |LAST UPDATE DATE:  05/28/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |THOMAS DECKER        R2      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOM HILL                     |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:                                |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INFORMATION REPORT RECEIVED FROM AN AGREEMENT STATE INVOLVING AN UNPLANNED   |
| CONTAMINATION EVENT                                                          |
|                                                                              |
| "Description of Event : In accordance with Rule .03(14)(b)2. of the Rules    |
| and Regulations for Radioactive Material, Joseph Rodgers, Deputy RSO, ((770) |
| 271-0233) notified the Department of an unplanned contamination event.       |
| While transporting a shielded 100 milliliter volumetric flask containing 24  |
| Curies of purified liquid Pd 103 (cyclotron produced) the transport cart     |
| struck an object in the lab and the flask toppled out of the shield onto the |
| floor. The Chemist immediately exited the area and notified health physics.  |
| Steps were immediately implemented to: minimize any exposure; prevent the    |
| spread of contamination; and initiate timely gross decontamination.  Access  |
| to the room remains restricted and monitoring will continue with             |
| decontamination planned for the end of next week after the radiation levels  |
| are reduced by decay of the Palladium.  Emergency processing of the film     |
| badges for the three involved employees was initiated with the following     |
| range of exposures reported for whole body:  DDE 55 mrem to 277 mrem; LDE 61 |
| mrem to 326 mrem; SDE 65 mrem to 355 mrem; and for extremities: SDE 170 mrem |
| to 4040 mrem. Nasal swabs of the affected employees were negative.  Results  |
| from a fixed air sampler, whose intake is directly above the area of the     |
| spill, indicated the 10 CFR Part 20 Appendix B values for inhalation were    |
| not exceeded.  No radioactive materials were released outside the restricted |
| area.  Representatives of the Radiation Control Program visited the site on  |
| 5/27/99. The Licensee will submit a written report within 30 days, implement |
| short term corrective actions and resume operation in this facility in early |
| June, 1999."                                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35775       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 05/29/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 01:45[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/28/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        09:45[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/29/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |TONY VEGEL           R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING LOSS OF CRITICALITY CONTROL      |
|                                                                              |
| "On 5/28/99 at 0945 hrs operations personnel discovered a 5" polybottle      |
| containing uranium bearing material leaking solution from around the top of  |
| the container. The lid was found to be loose on the polybottle.  An onsight  |
| NCS Engineer responded to the scene and assessed the condition to be a loss  |
| of control such that only one double contingency control remained in place.  |
| NCSA-PLANT006 requirement #2 and requirement #12 state in part: lids provide |
| a barrier against spilling the material and the container is not moved while |
| the lid is loose.                                                            |
|                                                                              |
| "THERE WAS NO RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF |
| THIS EVENT.                                                                  |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
|                                                                              |
| "Safety Significance is low due to the small amount of material that leaked  |
| (10-20 ml) and the fact that the container was upright and spaced.           |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| "Sufficient leakage could have accumulated in an unfavorable geometry, i.e., |
| a building drain. With a high enrichment to create a criticality.            |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
|                                                                              |
| "Geometry and spacing are the controlled parameters.                         |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| "Amount of material is 10-20 ml of UF4 contaminated oil at 10.77%            |
| enrichment.                                                                  |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| "The geometry of the container was deficient when the lid was left loose     |
| enough to allow material to slosh inside and seep through the threads.       |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| "The material was cleaned up and some material decanted into another         |
| polybottle at approx. 1230 hrs.  Remaining storage areas were policed for    |
| polybottles with loose lids, none were found."                               |
|                                                                              |
| Operations informed the DOE Site Representative and the NRC Resident         |
| Inspector.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35776       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 05/29/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 01:45[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/28/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        08:10[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/29/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |TONY VEGEL           R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:                                |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING LOSS OF CRITICALITY CONTROL      |
|                                                                              |
| "On Friday, May 28, 1999 at 0810 hours, Operating personnel discovered that  |
| a Nuclear Criticality Safety Approval (NCSA) Requirement was not being       |
| maintained in the X-705 Decontamination Facility.  NCSA-PLANT 053.A01 titled |
| 'Uranium Analysis and Sampling' requirement #8 states in part, Samples may   |
| be grouped together but groups shall be spaced a minimum of two feet edge-to |
| edge. Six 250 ml sample bottles containing uranium bearing material were     |
| found within 16 inches of a polybottle.                                      |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
|                                                                              |
| "The Safety Significance is low since all the material is less than 10%      |
| enrichment, the sample batch is less than 2 liters, and some spacing was     |
| provided.                                                                    |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| "Numerous spacing violations of highly concentrated uranium solutions can    |
| lead to a criticality in the absence of volume and/or geometry controls.     |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
|                                                                              |
| "Volume arid Interactions were the controlled parameters.  Interactions was  |
| lost.                                                                        |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| "Six 250 ml sample bottles were involved containing various uranium bearing  |
| solutions of uranyl nitrate and/or uranyl fluoride. Enrichment is not        |
| expected to be greater than 10%.                                             |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| "The applicable controls are volume and spacing. Spacing between the samples |
| and the polybottle was lost.                                                 |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| "The spacing controls were corrected at 0900 hrs."                           |
|                                                                              |
| Operations informed the DOE Site Representative and the NRC Resident         |
| Inspector.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35777       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 05/29/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 07:45[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/28/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:14[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/29/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |TONY VEGEL           R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEITH VANDERPOOL             |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NON-CFR REPORT INVOLVING ACTUATION OF A SAFETY SYSTEM                        |
|                                                                              |
| "ON MAY 28, 1999, AT APPROXIMATELY 1714 HOURS THE HOIST BRAKES ON THE SOUTH  |
| TAILS WITHDRAWAL CRANE ACTUATED. THE ACTUATION OCCURRED WHILE A FULL 14-TON  |
| LIQUID UF6 CYLINDER WAS BEING PLACED ON A RAIL CAR TO BEGIN THE REQUIRED     |
| 5-DAY COOL DOWN PERIOD. THE CRANE BRAKES FUNCTIONED AS DESIGNED TO PREVENT   |
| FURTHER MOVEMENT OF THE LIQUID UF6 CYLINDER. FOLLOWING THE ACTUATION. THE    |
| CYLINDER WAS SUSPENDED APPROXIMATELY TWELVE (12") INCHES ABOVE THE RAIL CAR  |
| CRADLE. THE EXACT CAUSE FOR THE ACTUATION IS CURRENTLY UNDER INVESTIGATION.  |
| HOWEVER, THE ACTUATION IS BELIEVED TO HAVE BEEN CAUSED BY A MALFUNCTION OF   |
| THE MECHANISM THAT KEEPS THE BRAKES IN AN OPEN POSITION WHEN LOADS ARE BEING |
| RAISED AND LOWERED.  PENDING FURTHER INVESTIGATION INTO THE CAUSE FOR THE    |
| BRAKE ACTUATION, THE BRAKE ACTUATION IS BEING CONSIDERED A VALID SAFETY      |
| SYSTEM ACTUATION AND REPORTABLE IN ACCORDANCE WITH THE SAR,TABLE 6.9,        |
| CRITERIA J2.                                                                 |
|                                                                              |
| "AS A PRECAUTIONARY MEASURE THE PLANT SHIFT SUPERINTENDENT DIRECTED THAT ALL |
| LIQUID UF6 HANDLING CRANES BE TAGGED OUT-OF-SERVICE PENDING THE NOTED        |
| INVESTIGATION. NOTE AS A PRECAUTIONARY MEASURE SUPPORT CRADLES HAVE BEEN     |
| POSITIONED TO SUPPORT THE SUSPENDED LIQUID UF6 CYLINDER. CURRENT PLANS ARE   |
| TO LET THE CYLINDER COMPLETE THE REQUIRED 5-DAY COOL DOWN PERIOD PRIOR TO    |
| INITIATING FURTHER ACTIONS TO LOWER THE CYLINDER ONTO THE RAIL CAR.          |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."  |
|                                                                              |
| OPERATIONS INFORMED THE DOE SITE REPRESENTATIVE AND THE NRC RESIDENT         |
| INSPECTOR.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35778       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 05/29/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 18:37[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        05/29/1999|
+------------------------------------------------+EVENT TIME:        17:24[EDT]|
| NRC NOTIFIED BY:  DAVID WALSH                  |LAST UPDATE DATE:  05/29/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       18       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COURTESY CALL DUE TO UNIT SHUTDOWN                                           |
|                                                                              |
| "Susquehanna Unit 1 was manually shutdown on 5/29/99 to repair Fast Acting   |
| Solenoid Valves on the EHC System. At 1055 on 5/29/99, a controlled shutdown |
| was commenced by reducing recirc flow and then inserting control rods. At    |
| 1704 on 5/29/99, the Main Turbine was manually tripped with power at 18%. At |
| 1724, the reactor mode switch was taken to shutdown placing the unit in      |
| condition 3. Rx Water level dropped to approximately -0.5 inches as recorded |
| on wide range instrumentation and was restored using Feedwater. There were   |
| no ECCS initiations or Diesel Generator starts. There were no challenges to  |
| containment as a result of the shutdown. -                                   |
|                                                                              |
| "This event does not represent a shutdown required by Technical              |
| Specifications. The ESF actuation of the Reactor Protection System and the   |
| resulting level 3 isolations are not reportable since it is procedurally     |
| recognized as preplanned.                                                    |
|                                                                              |
| "The unit will be taken to cold shutdown to repair Fast Acting Solenoid      |
| Valves on the EHC System. Unit 2 was not affected by this event and is       |
| currently in Condition 1 at 100% power."                                     |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35779       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 05/30/1999|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 08:00[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        05/30/1999|
+------------------------------------------------+EVENT TIME:        05:22[CDT]|
| NRC NOTIFIED BY:  JOE BENNETT                  |LAST UPDATE DATE:  05/30/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNIT 2 EXPERIENCED VARIOUS ESF ACTUATIONS IN RESPONSE TO THE UNEXPECTED TRIP |
| OF THE "2B" RPS MOTOR GENERATOR SET.                                         |
|                                                                              |
| "AT 0522CDT ON 5/30/99, THE '2B' REACTOR PROTECTION SYSTEM (RPS) MOTOR       |
| GENERATOR (MG) SET TRIPPED.  THE CAUSE OF THE RPS MG SET TRIP HAS NOT BEEN   |
| DETERMINED.  THE LOSS OF POWER RESULTED IN AN ISOLATION OF PRIMARY           |
| CONTAINMENT ISOLATION SYSTEM (PCIS) GROUPS 6 (VENTILATION) AND 8 (TIPS), AND |
| PARTIAL ISOLATIONS OF GROUPS 3 (RWCU) AND 2 (DRYWELL SUMP ISOLATION VALVES). |
| ADDITIONALLY, THE STANDBY GAS TREATMENT AND CREV SYSTEMS AUTOMATICALLY       |
| INITIATED.  AT 0538CDT, ALTERNATE POWER WAS RESTORED AND THE SYSTEMS WERE    |
| RETURNED TO NORMAL.                                                          |
|                                                                              |
| "THIS [EVENT] ALSO REQUIRES A 30 DAY WRITTEN REPORT PER 10 CFR               |
| 50.73(a)(2)(iv)."                                                            |
|                                                                              |
| THERE WAS NO ONGOING ELECTRICAL MAINTENANCE AT THE TIME.  THE LICENSEE       |
| INFORMED THE NRC RESIDENT INSPECTOR.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35780       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 05/30/1999|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 17:04[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/30/1999|
+------------------------------------------------+EVENT TIME:        12:10[PDT]|
| NRC NOTIFIED BY:  DAVID PIERCE                 |LAST UPDATE DATE:  05/30/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     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 OF THE CAPTURE AND SUBSEQUENT RELEASE OF A GREEN SEA    |
| TURTLE                                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 05/30/99 at approximately 1210 PDT, a male green sea turtle was removed  |
| from the Diablo Canyon Power Plant intake structure.  The sea turtle had     |
| entered the intake structure by swimming under the apron wall and surfacing  |
| outside of the bar racks.  The sea turtle was transported by boat to a       |
| release point approximately 0.5 miles due west of the intake structure.  It  |
| was observed to swim strongly away from the release point.  The turtle's     |
| shell length was measured at 69 cm, and its weight was estimated to be 50-75 |
| lbs.  The turtle appeared to be in good health with no visible injuries with |
| the exception of some scrapes on the rear of its shell."                     |
|                                                                              |
| "The Diablo Canyon Power Plant Environmental Services Department has         |
| notified the National Marine Fisheries Service and the California Department |
| of Fish and Game of the capture and subsequent release of the sea turtle,    |
| which is protected under the Endangered Species Act."                        |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35781       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 06/01/1999|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 07:57[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/01/1999|
+------------------------------------------------+EVENT TIME:        06:08[CDT]|
| NRC NOTIFIED BY:  JANAK                        |LAST UPDATE DATE:  06/01/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST/STOLEN/UNACCOUNTED/FALSIFIED KEY CARDS/I.D. CARDS/KEYS/OTHER ACCESS     |
| DEVICE.                                                                      |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY.                        |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35782       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NUCLEAR LOGISTICS INC                |NOTIFICATION DATE: 06/01/1999|
|LICENSEE:  NUCLEAR LOGISTICS INC                |NOTIFICATION TIME: 11:07[EDT]|
|    CITY:  FORT WORTH               REGION:  4  |EVENT DATE:        04/19/1999|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  06/01/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |VERN HODGE(FAX)      NRR     |
|                                                |RICHARD CONTE        R1      |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SEIKEN (FAX)                 |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 REPORT -  DEVIATION IN A NUCLEAR LOGISTICS INC (NLI) DC POWER        |
| SUPPLY.                                                                      |
|                                                                              |
| A DEVIATION HAS BEEN IDENTIFIED IN A NLI DC POWER SUPPLY, P/N                |
| NLI-LGS-G-24-OV-R-8018 WHICH HAVE BEEN SUPPLIED AS A CLASS 1E COMPONENT,     |
| THAT ALLOWS A PREMATURE OVER VOLTAGE PROTECTION ACTUATION TO OCCUR IN A      |
| CIRCUIT SPECIFIC APPLICATION.  THIS CONDITION OCCURRED DURING DIESEL         |
| GENERATOR STARTUP, SPECIFICALLY DURING DIESEL GENERATOR LOADING.  THIS ISSUE |
| WAS DETERMINED TO BE A DEVIATION ON 4/19/99, HOWEVER, TO DATE NLI HAS NOT    |
| BEEN ABLE TO DUPLICATE THIS CONDITION DURING LABORATORY TESTING.  DATA       |
| COLLECTION AND ADDITIONAL TESTING IS BEING PERFORMED TO RESOLVE THE          |
| DEVIATION.  IT THE PREMATURE OVER VOLTAGE PROTECTION ACTUATION IS DETERMINED |
| TO BE THE RESULT OF THE POWER SUPPLY DESIGN, OTHER NLI-L SERIES POWER        |
| SUPPLIES WILL BE TESTED TO DETERMINE THEIR SUSCEPTIBILITY TO SIMILAR         |
| CONDITIONS.  TESTING AND EVALUATION ACTIVITIES WILL BE COMPLETED ON 7/16/99. |
| THESE COMPONENTS HAVE BEEN SUPPLIED AS SAFETY-RELATED COMPONENTS TO PUBLIC   |
| SERVICE ELECTRIC AND GAS COMPANY.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35783       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MID MICHIGAN MEDICAL CENTER          |NOTIFICATION DATE: 06/01/1999|
|LICENSEE:  MID MICHIGAN MEDICAL CENTER          |NOTIFICATION TIME: 11:23[EDT]|
|    CITY:  MIDLAND                  REGION:  3  |EVENT DATE:        05/24/1999|
|  COUNTY:                            STATE:  MI |EVENT TIME:             [EDT]|
|LICENSE#:  21-01549-02           AGREEMENT:  N  |LAST UPDATE DATE:  06/01/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID HILLS          R3      |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LANGRILL                     |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION OCCURRED AT THE MID MICHIGAN MEDICAL CENTER DURING |
| ADMINISTRATION OF A THERAPY DOSE OF I-131.                                   |
|                                                                              |
| A PATIENT WAS TO RECEIVE 150 MILLICURIES OF I-131 FOR A PRESCRIBED THERAPY   |
| DOSE, BUT ACTUALLY RECEIVED 100 MILLICURIES OF I-131.  THE PRESCRIBING       |
| PHYSICIAN WAS NOTIFIED BUT IT IS NOT KNOWN WHETHER THE PATIENT HAS NOTIFIED. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35784       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  POWER RESOURCES                      |NOTIFICATION DATE: 06/01/1999|
|LICENSEE:  POWER RESOURCES                      |NOTIFICATION TIME: 14:39[EDT]|
|    CITY:  GLENROCK                 REGION:  4  |EVENT DATE:        06/01/1999|
|  COUNTY:  CONVERSE                  STATE:  WY |EVENT TIME:        09:30[MDT]|
|LICENSE#:  SUA1511               AGREEMENT:  N  |LAST UPDATE DATE:  06/01/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA HOWELL         R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WILLIAM KEARNEY              |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BYPRODUCT MATERIAL SPILLED IN A RESTRICTED AREA                              |
|                                                                              |
| A backhoe accidentally broke a pipeline from the central plant to the waste  |
| disposal well causing a spill of about 4000 gallons of fluid.  The fluid     |
| contained approximately 15-20 ppm U3O8.  The pipeline was not in use at the  |
| time of the break so only the fluid in the pipe drained into the ditch that  |
| the backhoe was digging.  The fluid has been pumped back into the process    |
| facility and any residual solids have been cleaned up.    The accident       |
| occurred within the confines of the site.                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35785       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 06/02/1999|
|    UNIT:  [] [2] []                 STATE:  FL |NOTIFICATION TIME: 01:09[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        06/01/1999|
+------------------------------------------------+EVENT TIME:        20:55[EDT]|
| NRC NOTIFIED BY:  JACK BREEN                   |LAST UPDATE DATE:  06/02/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH BARR         R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |50       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - TS REQUIRED PLANT SHUTDOWN DUE TO DROPPED CONTROL ROD FOR UNKNOWN REASONS  |
| -                                                                            |
|                                                                              |
| AT 2055 ON 06/01/99, WITH UNIT 2 AT 100% POWER, CONTROL ELEMENT ASSEMBLY     |
| (CONTROL ROD) #40 OF SHUTDOWN GROUP 'B' DROPPED INTO THE REACTOR CORE FOR    |
| UNKNOWN REASONS.  NO MAINTENANCE OR TESTING ACTIVITIES WERE BEING CONDUCTED  |
| AT THE TIME.                                                                 |
|                                                                              |
| THE LICENSEE DECLARED THE CONTROL ROD INOPERABLE AND REDUCED POWER TO        |
| INVESTIGATE THE CAUSE OF THE DROPPED CONTROL ROD.  TECH SPEC 3.1.3.1         |
| REQUIRES THE LICENSEE TO  RESTORE THE CONTROL ROD TO OPERABLE STATUS WITHIN  |
| 6 HOURS OR PLACE UNIT 2 IN HOT SHUTDOWN MODE.                                |
|                                                                              |
| THIS EVENT HAS NO EFFECT ON UNIT 1 WHICH IS AT 100% POWER.                   |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| * * * UPDATE AT 0210 ON 06/02/99 BY JOE MARTIN TO JOLLIFFE * * *             |
|                                                                              |
| AT 0210 ON 06/02/99, I & C TECHNICIANS REPLACED A FAILED HALL EFFECT         |
| TRANSDUCER (CURRENT SENSOR) WHICH CAUSED CONTROL ELEMENT ASSEMBLY #40 TO     |
| TRIP OPEN AND DROP INTO THE REACTOR CORE.  PLANT OPERATORS WITHDREW THE      |
| CONTROL ROD, DECLARED IT OPERABLE, AND EXITED TECH SPEC 3.1.3.1.             |
|                                                                              |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR.                     |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO KEN BARR.                       |
+------------------------------------------------------------------------------+