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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021