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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35851 |
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| 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
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| 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. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35896 |
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| 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
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| 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. |
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|Power Reactor |Event Number: 35899 |
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+------------------------------------------------------------------------------+
| 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. |
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|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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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 |
+------------------------------------------------------------------------------+
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|Other Nuclear Material |Event Number: 35901 |
+------------------------------------------------------------------------------+
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| 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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021