Daily Events Report U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/11/2000 - 02/14/2000 ** EVENT NUMBERS ** 36665 36667 36679 36680 36681 36682 36683 36684 36685 36686 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------------------------+ |Power Reactor |Event Number: 36665 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 02/06/2000| | UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 18:37[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/06/2000| +----------------------+EVENT TIME: 17:55[EST]| | NRC NOTIFIED BY: BRUCE BUTLER |LAST | UPDATE DATE: 02/11/2000| | HQ OPS OFFICER: JOHN MacKINNON +---------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |KERRY LANDIS R2 | |10 CFR SECTION: | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+------+-------+-------+-------+-------+-------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+------+-------+-------+-------+-------+-------+ |1 N Y 93 Power Operation |93 Power Operation | |2 N Y 98 Power Operation |98 Power Operation | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | PUBLIC PROMPT NOTIFICATION SYSTEM INOPERABLE FOR 2 | MINUTES | | | | Due to technical difficulties in Jacksonville, | Florida, the Public Prompt | | Notification System (NOAA weather radio) was lost at | 1755 ET and was | | restored to service at 1757 ET. Primary and backup | system were inoperable | | during this period of time. | | | | The NRC Resident will be notified of this event | notification by the | | licensee. | | | | * * * UPDATE AT 1420 ON 02/11/00 BY TIM BEINKE TO | JOLLIFFE * * * | | | | The licensee desires to retract this event in | accordance with the guidance | contained in NRC | NUREG-1022 since the Public Prompt Notification | System was | | inoperable for less than 15 minutes. | | | | The licensee plans to notify the NRC Resident | Inspector. | | | | The NRC Operations Officer notified the R2DO Mark | Lesser. | +----------------------------------------------------+  !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------------------------+ |Power Reactor |Event Number: 36667 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 02/07/2000| | UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 04:28[EST]| | RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/07/2000| +----------------------+EVENT TIME: 02:40[CST]| | NRC NOTIFIED BY: DAVE KLIMECK |LAST | UPDATE DATE: 02/11/2000| | HQ OPS OFFICER: DOUG WEAVER +-----------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |TONY VEGEL R3 | |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 | |2 N Y 100 Power Operation |100 Power Operation | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | Minimum security personnel staffing requirements not | met. Immediate | compensatory actions taken | upon discovery. The licensee will notify the NRC | | resident inspector. Additional details of this | event may be obtained by | | contacting the NRC operations officer. | | | | * * * UPDATE AT 2057 ON 02/11/00 BY CHRIS KENT TO | JOLLIFFE * * * | | | | The licensee desires to retract this event since the | commitments in the | | approved Plant Physical Security Plan had been | complied with during this | | event. The licensee plans to notify the NRC | Resident Inspector. The NRC | | Operations Officer notified the R3DO Mike Parker. | Additional details of | | this event retraction may be obtained by contacting | the NRC Operations | | Officer. | +----------------------------------------------------+  +----------------------------------------------------+ |Power Reactor |Event Number: 36679 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/11/2000| | UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 00:59[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/2000| +----------------------+EVENT TIME: 18:50[EST]| | NRC NOTIFIED BY: BROWN |LAST | UPDATE DATE: 02/11/2000| | HQ OPS OFFICER: CHAUNCEY GOULD +---------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MARK LESSER R2 | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | |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 | |2 N Y 100 Power Operation |100 Power Operation | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | THE LICENSEE SUBMITTED A 24 HOUR OPERATING LICENSE | DEVIATION REPORT. | | | | While performing the Penetration Seal Firestop | Configuration verification | | project, engineering determined that 37 firestop | penetrations are not | | configured in accordance with existing approved | details. Therefore, these | | 37 penetrations are not operable, putting the plant | in a LCO action | | statement. Remedial action has been taken per | Selected License Commitment | | 16.9-5 Fire Barrier Penetrations, this action | establishes hourly fire | | watches on each affected penetration. | | | | The NRC Resident Inspector was notified. | +----------------------------------------------------+  +----------------------------------------------------+ |Power Reactor |Event Number: 36680 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 02/11/2000| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 07:13[EST]| | RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 02/11/2000| +----------------------+EVENT TIME: 02:58[CST]| | NRC NOTIFIED BY: OSELAND |LAST | UPDATE DATE: 02/11/2000| | HQ OPS OFFICER: CHAUNCEY GOULD +---------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MICHAEL PARKER R3 | |10 CFR SECTION: | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+------+-------+-------+-------+-------+-------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+------+-------+-------+-------+-------+-------+ | | | |2 N Y 4 Startup |4 Startup | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | HPCI DECLARED INOPERABLE, PLACING THE PLANT IN A LCO | ACTION STATEMENT. | | | | On 2/11/2000 at 0258 hours, HPCI low pressure | operability testing was in | | progress following a scheduled refueling outage. At | that time, the HPCI | | turbine failed to roll when the motor speed changer | was taken to its high | | speed stop. There was no change in steam flow as | indicated by the main | turbine bypass valve | position. The operator in attendance visually | verified | HPCI was still on the turning gear. The | surveillance was terminated and the | | system restored to standby lineup. At 0341 hours, | reactor pressure was | | reduced below 150 psig to place the reactor in a | condition where HPCI was | | not required to be operable, and they exited the LCO | at that time. | | | | The cause of this failure is under investigation. | | | | The NRC Resident Inspector was notified. | +----------------------------------------------------+  +----------------------------------------------------+ |Hospital |Event Number: 36681 | +----------------------------------------------------+ +----------------------------------------------------+ | REP ORG: JASPER COUNTY HOSPITAL |NOTIFICATION DATE: 02/11/2000| |LICENSEE: JASPER COUNTY HOSPITAL |NOTIFICATION TIME: 10:45[EST]| | CITY: RENSSELAER REGION: 3 |EVENT DATE: 02/11/2000| | COUNTY: STATE: IN |EVENT TIME: 08:45[CST]| |LICENSE#: 13-26527-01 AGREEMENT: N |LAST |UPDATE DATE: 02/11/2000| | DOCKET: |+---------------------+ | |PERSON ORGANIZATION | | |JAMES CREED R3 | | |BRIAN SMITH NMSS | +-------------------------+ | | NRC NOTIFIED BY: ROTH | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +-------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |BAAA 20.1906(d) SURFACE CONT/ EXT RAD | | | | | | | | | | | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | JASPER COUNTY HOSPITAL RECEIVED A SURFACE | CONTAMINATED BOX WHICH CONTAINED | | NUCLEAR MEDICINE. | | | | A METAL AMMO BOX USED TO TRANSPORT NUCLEAR MEDICINE | CONTAINED IN INDIVIDUAL | PIGS WAS FOUND TO HAVE | SURFACE TECHNICIUM CONTAMINATION ON THE LOCKING | CLASP | | MEASURING 604 DPM/CM2 (LIMIT IS EQUAL TO OR LESS | THAN 220 DPM/CM2). THERE | WAS NO DAMAGE TO THE | PIG CONTAINERS INSIDE THE AMMO BOX AND NO | CONTAMINATION | | WAS MEASURED INSIDE THE BOX. THE SOURCE OF THE | CONTAMINATION IS UNKNOWN, | BUT IT COULD HAVE | OCCURRED AT THE PHARMACEUTICAL COMPANY, THE | TRANSPORTER OR | | IN THE HOSPITAL LABORATORY. HOSPITAL PERSONNEL HAVE | ISOLATED THE AMMO BOX | | AND WILL ALLOW THE TECHNICIUM CONTAMINATION TO DECAY | OFF. | | | | (CALL THE NRC OPERATIONS OFFICER FOR A LICENSEE | CONTACT TELEPHONE NUMBER.) | +----------------------------------------------------+  +----------------------------------------------------+ |Power Reactor |Event Number: 36682 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/11/2000| | UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 14:32[EST]| | RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/11/2000| +----------------------+EVENT TIME: 13:46[EST]| | NRC NOTIFIED BY: MIKE BAIN |LAST | UPDATE DATE: 02/11/2000| | HQ OPS OFFICER: DICK JOLLIFFE +----------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |HAROLD GRAY R1 | |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 | +-----+------+-------+-------+-------+-------+-------+ | | | |2 M/R Y 96 Power Operation |0 Hot Standby | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | - MANUAL REACTOR TRIP FROM 96% POWER AFTER 2 CONTROL | RODS DROPPED INTO THE | | CORE - | | | | During the performance of a tech spec surveillance | test of control rod | motion with Unit 2 at | 100% power, one control rod dropped into the core | for | unknown reasons. Control room operators | reduced power. With Unit 2 at 96% | | power, a second control rod dropped into the core | for unknown reasons. | Control room operators | manually tripped Unit 2 from 96% power. All control | | | rods inserted completely into the core. The | auxiliary feedwater system | | actuated, as expected. Control room operators | manually secured the | | auxiliary feedwater system. Steam generator water | levels are being | | maintained in their normal range by the main | feedwater system. Steam is | | being dumped to the main condenser. No safety or | relief valves lifted. | Unit 2 is stable in | Mode 3 (Hot Standby). The licensee is investigating | the | | cause of the control rods dropping into the core. | | | | The licensee notified state and local officials and | the NRC Resident | | Inspector and plans to issue a press release. | +----------------------------------------------------+  +----------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36683 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/11/2000| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:27[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/10/2000| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 23:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST | UPDATE DATE: 02/11/2000| | CITY: PIKETON REGION: 3 +-----------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED R3 | | DOCKET: 0707002 |JOSEPHINE PICCONE NMSS | +-------------------------+ | | NRC NOTIFIED BY: RICK LARSON | | | HQ OPS OFFICER: DICK JOLLIFFE | | +-------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | NRC Bulletin 91-01, 24 Hour Report - Loss of 1 of 2 | Controlled Parameters | | (Geometry) - | | | | At 2330 on 02/10/00, the Plant Shift Superintendent | (PSS) was notified that | | a Nuclear Criticality Safety Approval (NCSA) | requirement was not being | | maintained in the X-705 decontamination facility. | While performing an NCS | Self Assessment, | facility personnel noticed an operation where | requirements | | for the control of "Inadvertent Containers" was not | being met. The | | Inadvertent container was a rectangular support | structure for a ventilator | | that was approximately 5.5 inches deep and did not | have any holes or slots | | to provide drainage. The critical height dimension | is 1.5 inches from the | | bottom of the container. | | | | Requirement #5 of NCSA-0705-076.A00 states, in part | that modifications to | | inadvertent containers, where practical, shall be | accomplished by drilling | holes or making slots | in the container to provide drainage. This | structure, | not having drainage holes, was a loss | of one control (geometry). The other | | control (concentration) was maintained. | | | | At the direction of the PSS, the requirements for an | NCS anomalous condition | | were established per plant procedures. At | approximately 0130 on 02/11/00, | | double contingency controls were reestablished. | | | | SAFETY SIGNIFICANCE OF THE EVENT: | | | | The safety significance of this event is low. The | inadvertent container is | an iron support | structure for a ventilator that is approximately 5.5 | inches | | deep by 24 inches wide and just over 60 inches long. | This structure is in | | the high bay of the X-705 building bolted to the | floor under the overhead | | storage system. However, there were no indications | that any solution had | | collected in the container or that any leakage had | occurred from the | overhead storage in this | area. Also, data on the concentration of uranium | | in the overhead storage indicates that it is | currently less than 500 ppm. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED [BRIEF | SCENARIO(S) OF HOW | | CRITICALITY COULD OCCUR]: | | | | The potential pathway for a criticality is a failure | of the overhead storage | | system. This would allow uranium bearing solution | to collect in the | container. Since the | container has a depth greater than the safe slab | depth | | of 1.5 inches for 100% enriched material, a | criticality could occur if the | collected | solution's depth exceeds 1.5 inches and the uranium | concentration | | of the solution exceeds 11,600 ppm. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY. | CONCENTRATION, ETC.): | | | | The parameters being controlled are geometry | (container geometry and | | overhead storage piping) and concentration of | solution in the overhead | | storage. | | | | ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED | MATERIAL (INCLUDE PROCESS | | LIMIT AND PER CENT WORST CASE OF CRITICAL MASS): | | | | There was no uranium material involved with this | event. If the overhead | | storage were to leak, the enrichment is considered | to be 100% and the form | | would be U02F2 solution (worst case). | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL | SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: | | | | The geometry control of container was lost. The | NCSA requires that holes or | | slots be added to the container to limit the height | of the solution that | | could collect to less than 1.5 inches. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN | EACH WAS IMPLEMENTED: | | | | Compliance was regained at 0130 on 02/11/00 when | plastic has placed over the | | container to prevent the introduction of solution. | | | | | There was no loss of hazardous or radioactive | material nor radioactive or | | radiological contamination exposure as a result of | this event. | | | | Portsmouth personnel notified the NRC Resident | Inspector and the Site DOE | | Representative. | | | | PTS-2000-009 PR-PTS-00-00829 | +----------------------------------------------------+  +----------------------------------------------------+ |Power Reactor |Event Number: 36684 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 02/11/2000| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 20:13[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 02/11/2000| +----------------------+EVENT TIME: 17:07[CST]| | NRC NOTIFIED BY: STEVE WHEELER |LAST | UPDATE DATE: 02/11/2000| | HQ OPS OFFICER: DICK JOLLIFFE +----------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LINDA HOWELL 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 | | | | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | - Nebraska Game and Parks Department notified of a | dead American Bald Eagle | | found onsite - | | | | At 1707 CST on 02/11/00, a licensee employee found | an American Bald Eagle | | under a 345 kV line on licensee property. The | licensee notified the | Nebraska Game and | Parks Department. A Nebraska Game Warden reported | to the | site and took possession of the eagle. The | warden stated that the eagle had | | been dead for some time. The warden plans to notify | the Fish and Wildlife | | Service of this incident and to send the bird to | them. | | | | The licensee notified the NRC Resident Inspector. | +----------------------------------------------------+  +----------------------------------------------------+ |Power Reactor |Event Number: 36685 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 02/13/2000| | UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 11:11[EST]| | RXTYPE: [1] W-4-LP |EVENT DATE: 02/13/2000| +----------------------+EVENT TIME: 07:34[CST]| | NRC NOTIFIED BY: ROBERT BARTON |LAST | UPDATE DATE: 02/13/2000| | HQ OPS OFFICER: STEVE SANDIN +----------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LINDA HOWELL R4 | |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 100 Power Operation |0 Hot Standby | | | | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | AUTOMATIC REACTOR TRIP ON LOSS OF REACTOR COOLANT | SYSTEM (RCS) FLOW | | | | THE UNIT EXPERIENCED AN AUTOMATIC REACTOR | TRIP-TURBINE TRIP FROM 100% POWER | DUE TO THE LOSS | OF RCS FLOW CAUSED BY THE TRIP OF THE REACTOR | COOLANT PUMPS | | (INITIALLY "B" RCP FOLLOWED BY THE "A", "C" AND | "D"). FLUCTUATING GRID | | VOLTAGE DUE TO AN ELECTRICAL PROBLEM IN SOUTHEAST | MISSOURI CAUSED THE LOSS | | OF THE RCPs AND THE OPERATING CIRCULATING WATER (CW) | PUMPS. DURING THE | | PERIOD TIME BEFORE THE RCPs WERE RESTARTED, RCS | PRESSURE INCREASED CAUSING | | ONE (1) PRESSURIZER PORV TO LIFT AND RESEAT | (SETPOINT 2335 PSIG - PRIMARY | SAFETY SETPOINT | IS 2485 PSIG). A SLIGHT INCREASE IN THE PRESSURIZER | RELIEF | TANK PRESSURE WAS OBSERVED. A FEEDWATER | ISOLATION SIGNAL OCCURRED WITH ALL | | SYSTEMS FUNCTIONING AS EXPECTED INCLUDING AUTOSTART | OF ALL AUXILIARY | FEEDWATER PUMPS (BOTH | MOTOR-DRIVEN AND THE TURBINE-DRIVEN PUMPS). | CONDENSER | VACUUM WAS LOST AS A RESULT OF THE CW | PUMP TRIPS. HOWEVER, TWO (2) CW PUMPS | | WERE RESTARTED AND THE MAIN CONDENSER PLACED BACK IN | SERVICE AS THE HEAT | | SINK. THE LICENSEE ESTIMATES THAT THE STEAM | GENERATOR ATMOSPHERIC DUMPS | | WERE USED FOR NO MORE THAN 20 MINUTES DURING THE | PERIOD OF TIME WHEN THE | | MAIN CONDENSER WAS NOT AVAILABLE. THERE IS NO | INDICATION OF ANY | PRIMARY-SECONDARY | LEAKAGE PRIOR TO THIS EVENT. THE PLANT IS CURRENTLY | STABLE | | WITH OPERATORS RESTORING MAIN FEEDWATER. BOTH | EMERGENCY DIESELS ARE IN | | STANDBY AND AVAILABLE, IF NEEDED. THE UNIT WILL | REMAIN IN MODE 3 PENDING | | THE OUTCOME OF THE INVESTIGATION INTO THE GRID | ELECTRICAL TRANSIENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +----------------------------------------------------+  +----------------------------------------------------+ |Power Reactor |Event Number: 36686 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/13/2000| | UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 19:56[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/13/2000| +----------------------+EVENT TIME: 18:32[EST]| | NRC NOTIFIED BY: J. K. McCONNELL |LAST | UPDATE DATE: 02/13/2000| | HQ OPS OFFICER: LEIGH TROCINE +----------+ +----------------------+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 100 Power Operation |0 Hot Standby | | | | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | AUTOMATIC REACTOR TRIP DUE TO A TURBINE TRIP FOR | UNKNOWN REASONS | | | | The following text is a portion of a facsimile | received from the licensee: | | | | "Unit 1 reactor trip occurred at 1832 hours on | 02/13/2000. Control room | annunciators | indicate that the cause of the reactor trip was a | turbine trip. | | At this time, the cause of the turbine trip is | unknown. All systems and | | plant responses to the reactor trip were normal." | | | | The licensee stated that all control rods fully | inserted and that all | | support systems functioned correctly. None of the | primary or secondary | | system safety relief valves lifted. There were no | emergency core cooling | | system actuations, and none were required. The | following three engineered | | safety feature actuations occurred: turbine trip | (for unknown reasons), | | feedwater isolation, and auxiliary feedwater | automatic start. Feedwater | | isolated and auxiliary feedwater automatically | started as designed. | | | | The cause of the turbine trip is unknown but is | currently believed to be | | electrical in nature. There were no related | maintenance or surveillance | | activities ongoing at the time of the event. | | | | The unit is currently stable in Mode 3 (Hot | Standby). Normal charging and | | letdown, pressurizer heaters and sprays, and the | reactor coolant pumps are | | being utilized at this time for primary system | level, pressure, and | | transport control. Auxiliary feedwater is supplying | water to the steam | | generators, and secondary steam is being dumped to | the condenser. The | | electrical grid is stable. | | | | The licensee notified the NRC resident inspector. | +----------------------------------------------------+ 

-- Trish (adler2@webtv.net), February 14, 2000

Answers

Would someone make an attempt to clean up this post? I think that there is some important info here, but I'm not sure.

-- (kb8um8@yahoo.com), February 14, 2000.

LINK? LINK? LINK? HOAX? HOAX? HOAX? - PARTIAL CLEAN UP -------------------------------------------------------------- Daily Events Report U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/11/2000 - 02/14/2000 ** EVENT NUMBERS ** 36665 36667 36679 36680 36681 36682 36683 36684 36685 36686

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!

EVENT TEXT PUBLIC PROMPT NOTIFICATION SYSTEM INOPERABLE FOR 2 MINUTES

Due to technical difficulties in Jacksonville, Florida, the Public Prompt Notification System (NOAA weather radio) was lost at 1755 ET and was restored to service at 1757 ET. Primary and backup system were inoperable| during this period of time.

The NRC Resident will be notified of this event notification by the licensee.

* * * UPDATE AT 1420 ON 02/11/00 BY TIM BEINKE TO | JOLLIFFE * * *

The licensee desires to retract this event in accordance with the guidance contained in NRC NUREG-1022 since the Public Prompt Notification System was inoperable for less than 15 minutes.

The licensee plans to notify the NRC Resident Inspector. The NRC Operations Officer notified the R2DO Mark | Lesser. THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!

----------------------------+ EVENT TEXT +---------------------------- ------------------------+ | Minimum security personnel staffing requirements not met. Immediate compensatory actions taken upon discovery. The licensee will notify the NRC resident inspector. Additional details of this event may be obtained by contacting the NRC operations officer.

* * * UPDATE AT 2057 ON 02/11/00 BY CHRIS KENT TO | JOLLIFFE * * *

The licensee desires to retract this event since the commitments in the approved Plant Physical Security Plan had been complied with during this event. The licensee plans to notify the NRC Resident Inspector. The NRC Operations Officer notified the R3DO Mike Parker. Additional details of this event retraction may be obtained by contacting the NRC Operations Officer.

FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/11/2000| | UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 00:59[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/2000 EVENT TIME: 18:50[EST]| | NRC NOTIFIED BY: BROWN |LAST | UPDATE DATE: 02/11/2000| |

------------------------------------------------+ EVENT TEXT +-------- -----------------------------------| THE LICENSEE SUBMITTED A 24 HOUR OPERATING LICENSE | DEVIATION REPORT.

While performing the Penetration Seal Firestop Configuration verification project, engineering determined that 37 firestop penetrations are not configured in accordance with existing approved details. Therefore, these 37 penetrations are not operable, putting the plant in a LCO action statement. Remedial action has been taken per Selected License Commitment 16.9-5 Fire Barrier Penetrations, this action establishes hourly fire watches on each affected penetration. The NRC Resident Inspector was notified. |

CLASS: N/A | | |10 CFR SECTION: | | |BAAA 20.1906(d) SURFACE CONT/ EXT RAD | | | | | | | | | | | | | | +--------------------------------- -------------------+ EVENT TEXT +------------------------------------- ---------------+ |

JASPER COUNTY HOSPITAL RECEIVED A SURFACE | CONTAMINATED BOX WHICH CONTAINED NUCLEAR MEDICINE.

A METAL AMMO BOX USED TO TRANSPORT NUCLEAR MEDICINE | CONTAINED IN INDIVIDUAL PIGS WAS FOUND TO HAVE SURFACE TECHNICIUM CONTAMINATION ON THE LOCKING CLASP MEASURING 604 DPM/CM2 (LIMIT IS EQUAL TO OR LESS THAN 220 DPM/CM2). THERE WAS NO DAMAGE TO THE PIG CONTAINERS INSIDE THE AMMO BOX AND NO CONTAMINATION | | WAS MEASURED INSIDE THE BOX. THE SOURCE OF THE | CONTAMINATION IS UNKNOWN,

BUT IT COULD HAVE | OCCURRED AT THE PHARMACEUTICAL COMPANY, THE TRANSPORTER OR | | IN THE HOSPITAL LABORATORY. HOSPITAL PERSONNEL HAVE | ISOLATED THE AMMO BOX | | AND WILL ALLOW THE TECHNICIUM CONTAMINATION TO DECAY | OFF. | | | | (CALL THE NRC OPERATIONS OFFICER FOR A LICENSEE | CONTACT TELEPHONE NUMBER.) Operation |0 Hot Standby | | | | +----

------------------------------------------------+ EVENT TEXT +-------- -----------------------------------

-- (harri5@aol.com), February 14, 2000.

Could you please post a link for this site? Is it accessible without a password? Thanks!

-- Margo (margos@bigisland.com), February 14, 2000.

Sorry, I didn't cut and paste the NRC link, was running late for work. This forum is so addictive, can't tell how many times I've been late.

I don't have a link, but if you search US NRC, then hit on Nuclear Reactors, then Daily Events Report, you'll get the present day update.

-- Trish (adler2@webtv.net), February 14, 2000.

Thank you for the post Trish.

-- Dee (T1Colt556@aol.com), February 14, 2000.