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Event Notification Report for July 8, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/07/1999 - 07/08/1999

                              ** EVENT NUMBERS **

35851  35896  35899  35900  35901  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35851       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 06/22/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 18:23[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        06/22/1999|
+------------------------------------------------+EVENT TIME:        16:48[CDT]|
| NRC NOTIFIED BY:  FERGUSON                     |LAST UPDATE DATE:  07/07/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOSEPH TAPIA         R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SEPARATION CRITERIA FOR REACTOR TRIP SWITCHGEAR NOT MET.                     |
|                                                                              |
| IT WAS DISCOVERED THAT BOTH TRAINS OF THE REACTOR TRIP SWITCHGEAR WERE 12"   |
| APART WHILE THE REQUIRED SEPARATION IS 20 FEET.  THIS CONDITION PUTS THE     |
| PLANT OUTSIDE ITS DESIGN BASIS AS PER 10CFR50 APPENDIX R, SEC. III.G.2.      |
| THEY HAVE STATIONED A CONTINUOUS FIRE WATCH IN THE AREA.  PLANT OPERATION    |
| WILL CONTINUE.  AS A CORRECTIVE MEASURE VARIOUS OPTIONS ARE BEING            |
| CONSIDERED, WITH ONE REQUIRING A PLANT SHUTDOWN.  THEY HAVE NOT YET          |
| DETERMINED WHICH CORRECTIVE OPTION THEY WILL IMPLEMENT.  INSTRUCTIONS HAVE   |
| BEEN GIVEN TO TRIP THE REACTOR UPON A REPORT FROM THE CONTINUOUS FIRE WATCH  |
| OF AN ACTIVE FIRE IN THE AREA THAT IS BEING MONITORED.                       |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| ***RETRACTION ON 07/07/99 AT 1721 ET BY D. DEES TAKEN BY MACKINNON***        |
|                                                                              |
| BASED ON ENGINEERING EVALUATION THE PLANT WAS NOT OUTSIDE ITS DESIGN BASIS   |
| WITH RESPECT TO APPENDIX "R" TO 10CFR50.  THE APPROVED FIRE PROTECTION       |
| PROGRAM ALLOWS A DIVERSE MEANS TO ACHIEVE SAFE SHUTDOWN, AS IDENTIFIED IN    |
| WCGS RESPONSE TO APPENDIX "R" SECTION III.G.  IN THIS CASE, THE DIVERSE      |
| MEANS TO ACHIEVE AND MAINTAIN SAFE SHUTDOWN USING EQUIPMENT FREE OF FIRE     |
| DAMAGE IS ACCOMPLISHED THROUGH MANUAL ROD INSERTION AS SPECIFIED IN EMG      |
| FR-S1, RESPONSE TO NUCLEAR POWER GENERATION/ATWT.  THEREFORE, THIS EVENT IS  |
| BEING RETRACTED.  R4DO (CHARLES MARSCHALL) NOTIFIED.                         |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS RETRACTION BY THE        |
| LICENSEE.                                                                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35896       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 07/05/1999|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 15:40[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        07/05/1999|
+------------------------------------------------+EVENT TIME:        14:53[EDT]|
| NRC NOTIFIED BY:  ERIC deMONCH                 |LAST UPDATE DATE:  07/07/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |LEDYARD (TAD) MARSH  NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |JOSEPH GIITTER       IRO     |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN DUE TO LOSS OF POWER TO STARTUP TRANSFORMERS FOR |
| APPROXIMATELY 8 MINUTES                                                      |
|                                                                              |
| The units main generator output supplies power to two (2) 230KV "A" & "B"    |
| buses.  The 230KV "A" & "B" buses, in addition to supplying power to the     |
| grid, each have a 230KV/34.5KV step-down transformer energizing the 34.5KV   |
| "A" & "B" buses, respectively.  These 34.5KV buses feed Bank 5 and 6 Startup |
| Transformers using offsite  power when the main generator is offline.  Both  |
| the "A" & "B" 34.5KV  buses deenergized for approximately 8 minutes,         |
| possibly due to a thermal overload trip condition caused by high ambient     |
| temperatures >100 degrees F (the specific location of the 34.5KV loss is     |
| under investigation).  This placed the  unit in Tech Spec 3.7.A.(3) which    |
| states "that one 230KV line must be fully operational and switchgear for     |
| both Startup Transformers to the station are energized to carry power . . .  |
| ." or the unit must be shutdown.  The unit exited the Technical              |
| Specification required Shutdown after approximately 8 minutes when both      |
| 34.5KV buses were reenergized.  The associated 4.16KV safeguard buses        |
| remained energized throughout the transient since they normally receive      |
| power from the Auxiliary Transformer during power operations. Both emergency |
| diesel generators are available, if needed.                                  |
|                                                                              |
| At the present time the licensee said that they are carrying a large amount  |
| of VARS.                                                                     |
|                                                                              |
| The NRC Resident Inspector will be informed of this event notification by    |
| the licensee.                                                                |
|                                                                              |
| **** RETRACTION ON 07/07/99 AT 1502 ET BY J.  FREEMAN TAKEN BY               |
| MACKINNON****                                                                |
|                                                                              |
| After further review the licensee determined that this notification was made |
| prematurely. The licensee determined that they had not begun a Technical     |
| Specification required shutdown under section 3.7.A.3, therefore, this event |
| is not reportable. Based on this information the licensee is retracting the  |
| above notification.                                                          |
| R1DO (J Trapp) notified.                                                     |
|                                                                              |
| The NRC Resident Inspector will be notified of this retraction.              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35899       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 07/07/1999|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 02:41[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        07/07/1999|
+------------------------------------------------+EVENT TIME:        01:10[EDT]|
| NRC NOTIFIED BY:  MICHAEL DUNTON               |LAST UPDATE DATE:  07/07/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       15       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP DUE TO LOSS OF MAIN FEEDWATER                                   |
|                                                                              |
| The unit automatically tripped due to the loss of all main feedwater flow    |
| after the main feedwater pump tripped on low suction pressure. All control   |
| rods inserted following the trip.  Emergency feedwater actuated as           |
| expected.                                                                    |
|                                                                              |
| The licensee reported that two main steam relief valves remained open        |
| following the trip, but reclosed after steam generator pressure was reduced  |
| to 920 psig. The unit is currently stable in Hot Standby, with steam         |
| generator levels being maintained by the motor driven emergency feedwater    |
| pumps, and decay heat being relieved to the main condenser via the turbine   |
| bypass valves.                                                               |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35900       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WAUKESHA MEMORIAL HOSPITAL           |NOTIFICATION DATE: 07/07/1999|
|LICENSEE:  WAUKESHA MEMORIAL HOSPITAL           |NOTIFICATION TIME: 16:37[EDT]|
|    CITY:  WAUKESHA                 REGION:  3  |EVENT DATE:        06/29/1999|
|  COUNTY:  WAUKESHA                  STATE:  WI |EVENT TIME:        12:00[CDT]|
|LICENSE#:  48-06239-01           AGREEMENT:  N  |LAST UPDATE DATE:  07/07/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |TONY VEGEL           R3      |
|                                                |JOHN SURMEIER        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MARY WETZGER                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POST IMPLANT SURVEY OF A LOADING CART STERILE DRAPE DETECTED A RADIOACTIVE   |
| LEVEL OF 20MREM/HR..                                                         |
|                                                                              |
| Post implant survey in the operating room found radiation reading levels on  |
| the sterile drape of a cart used to hold Iodine-125 seeds which were         |
| implanted into a patients thyroid . A small piece of metal (less than 1      |
| millimeter in length)  on the carts sterile drape was found to have a        |
| radioactive level of  20mrem/hr at 3 centimeters.  The small piece of metal  |
| was placed in a lead pig and is now stored in the Hospital isotope room.     |
| All the Iodine-125 seeds that were not used for implantation in the patient  |
| were accounted for and placed in lead containers.  A bioassay will be        |
| performed on the patient within in the next few days to make sure the        |
| patient does not have any leaking iodine-125 seeds in their thyroid.         |
|                                                                              |
| This event was discovered to be reportable yesterday evening ,7/6/99, after  |
| the Radiation Safety Officer discovered that leaking seeds is considered a   |
| Medical Misadministration                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35901       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NATIONAL RESPONSE CENTER             |NOTIFICATION DATE: 07/07/1999|
|LICENSEE:  POWER RESOURCES, INC.                |NOTIFICATION TIME: 18:34[EDT]|
|    CITY:  CARBON                   REGION:  4  |EVENT DATE:        07/07/1999|
|  COUNTY:                            STATE:  WY |EVENT TIME:        13:00[MDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  07/07/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |JOHN SURMEIER        NMSS    |
+------------------------------------------------+DANIAL GILLEN        NMSS    |
| NRC NOTIFIED BY:  GAUTHIER                     |FEMA, DOE, HHS,      FAX     |
|  HQ OPS OFFICER:  JOHN MacKINNON               |EPA, DOT (NRC), USDA FAX     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SPILLAGE AND CLEANUP OF 3-5 GALLONS OF WATER CONTAINING LSA OF URANIUM       |
| BYPRODUCT MATERIAL.                                                          |
|                                                                              |
| FOLLOWING INFORMATION WAS RECEIVED FROM THE NATIONAL RESPONSE CENTER.        |
|                                                                              |
| A dumpster transporting LSA byproduct material to a disposal site developed  |
| a minor leak. The dumpster leaked  3 to 5 gallons of water containing LSA of |
| uranium byproduct material on the ground next to a roadway (highway 487      |
| about 50 miles Southwest of Carbon, Wyoming).  The area affected by the leak |
| was less than 20 square feet and cleanup of the contaminated soil is in      |
| progress.                                                                    |
|                                                                              |
| This event was reported to the National Response Center by William Kearney,  |
| Power Resources, Inc., located in Douglas, Wyoming.                          |
+------------------------------------------------------------------------------+


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