U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/17/1998 - 12/18/1998 ** EVENT NUMBERS ** 35159 35160 35161 35162 35163 35164 35165 35166 35167 35168 35169 +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35159 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: BLUE RIDGE NUCLEAR PHARMACY |NOTIFICATION DATE: 12/17/1998| |LICENSEE: BLUE RIDGE NUCLEAR PHARMACY |NOTIFICATION TIME: 11:48[EST]| | CITY: ROANOAK REGION: 2 |EVENT DATE: 12/17/1998| | COUNTY: STATE: VA |EVENT TIME: 02:30[EST]| |LICENSE#: 452533901MD AGREEMENT: N |LAST UPDATE DATE: 12/17/1998| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PAUL FREDRICKSON R2 | | |WILLIAM KANE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: BOB BEIGHTOL, RSO | | | HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAMINATED RADIOPHARMACEUTICAL METAL DELIVERY CONTAINERS SENT TO 4 | | HOSPITALS - | | | | WHILE HEATING THREE 6-ml VIALS OF LIQUID Tc-99m CARDIOLITE IN A LEAD HEATING | | BLOCK AT 100þC FOR 10 MINUTES AT THE BLUE RIDGE COMMERCIAL NUCLEAR PHARMACY, | | ROANOKE, VA, ONE OF THE VIALS EXPLODED FOR UNKNOWN REASONS CONTAMINATING THE | | ENTIRE LABORATORY. THE TOP PORTION OF THE VIAL EMBEDDED ITSELF INTO THE | | CEILING ACOUSTIC TILE AND THE INSULATION ABOVE THE TILE APPROXIMATELY 10 | | FEET ABOVE THE BLOCK. THE LONE PHARMACIST PRESENT IN THE LABORATORY WAS NOT | | INJURED. HE CLEANED UP AND DECONTAMINATED THE LABORATORY, ITS CONTENTS, AND | | THE RADIOPHARMACEUTICAL METAL DELIVERY CONTAINERS PRESENT IN THE | | LABORATORY. | | | | LATER IN THE DAY, FOUR HOSPITALS NOTIFIED BLUE RIDGE THAT | | RADIOPHARMACEUTICAL METAL DELIVERY CONTAINERS RECEIVED FROM BLUE RIDGE IN | | THE MORNING HAD REMOVABLE CONTAMINATION IN EXCESS OF 10CFR20 ACCEPTABLE | | LIMITS (>6600 DPM). (THESE HOSPITALS ARE: CARILION ROANOKE MEMORIAL, | | CARILION COMMUNITY, RADFORD, AND ALLEGANY REGIONAL HOSPITALS). BLUE RIDGE | | DRIVERS PLAN TO RETRIEVE THE CONTAINERS AND BLUE RIDGE PHARMACISTS PLAN TO | | FURTHER DECONTAMINATE THE CONTAINERS. | | | | MR BEIGHTOL PLANS TO THOROUGHLY REVIEW THIS INCIDENT AND DETERMINE | | CORRECTIVE ACTIONS. | | | | MR BEIGHTOL IS REPORTING THIS INCIDENT TO THE NRC OPERATIONS CENTER IN | | ACCORDANCE WITH 10CFR20.1906. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Hospital |Event Number: 35160 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: SAINT FRANCIS HOSPITAL |NOTIFICATION DATE: 12/17/1998| |LICENSEE: SAINT FRANCIS HOSPITAL |NOTIFICATION TIME: 11:36[EST]| | CITY: HARTFORD REGION: 1 |EVENT DATE: 12/16/1998| | COUNTY: STATE: CT |EVENT TIME: 18:00[EST]| |LICENSE#: 06-00854-03 AGREEMENT: N |LAST UPDATE DATE: 12/17/1998| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |HAROLD GRAY R1 | | |WILLIAM KANE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: RICE | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAINT FRANCIS HOSPITAL IN HARTFORD, CONNECTICUT, REPORTED THAT ON 12/15/98 | | AT 1533, A PATIENT BEGAN TREATMENT WITH A "NUCLETRON" SELECTRON LDR REMOTE | | AFTER-LOADER. THE PATIENT WAS TO RECEIVE 2,348 CENTIGRAYS USING Cs-137 BUT | | ONLY RECEIVED 90 CENTIGRAYS USING Cs-137 DUE TO THE FAILURE OF THE EQUIPMENT | | AFTER ONLY 1.6 HOURS OF TREATMENT (TREATMENT SHOULD HAVE LASTED A TOTAL OF | | 42 HOURS). THE PATIENT WILL RETURN TO THE HOSPITAL FOR THE COMPLETION OF | | THE TREATMENT AT A LATER DATE. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35161 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 12/17/1998| | UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 12:10[EST]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/17/1998| +------------------------------------------------+EVENT TIME: 11:07[CST]| | NRC NOTIFIED BY: WES CUMBY |LAST UPDATE DATE: 12/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPDS OUT OF SERVICE FOR MAINTENANCE | | | | At 1007, the licensee removed the Safety Parameter Display System (SPDS) | | from service for scheduled maintenance. At 1107, the licensee determined | | that the SPDS outage exceeded the definition of a "short outage" as | | described in NUREG-1022. The NRC resident inspector has been informed of | | this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35162 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/17/1998| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 13:38[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 12/17/1998| +------------------------------------------------+EVENT TIME: 10:42[CST]| | NRC NOTIFIED BY: JOHN OSWALD |LAST UPDATE DATE: 12/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |IAN BARNES R4 | |10 CFR SECTION: | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 1 Startup |1 Startup | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC SYSTEM DECLARED INOPERABLE | | | | While performing Reactor Core Isolation Cooling (RCIC) System surveillance | | procedure #6.RCIC.309, "RCIC (150 psig) Beginning of Cycle Test," the RCIC | | turbine unexpectedly tripped 27 seconds after the RCIC start signal. The | | cause of the turbine trip has not been determined, but the licensee reported | | that the overspeed trip mechanism was found tripped. Reactor pressure was | | approximately 163 psig at the time of the test. An investigation of this | | event is ongoing. | | | | The NRC Resident Inspector has been informed by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35163 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: ECS, LTD |NOTIFICATION DATE: 12/17/1998| |LICENSEE: ECS, LTD |NOTIFICATION TIME: 13:58[EST]| | CITY: CHARLOTTE REGION: 2 |EVENT DATE: 12/17/1998| | COUNTY: STATE: NC |EVENT TIME: 09:00[EST]| |LICENSE#: 060-0253-03 AGREEMENT: Y |LAST UPDATE DATE: 12/17/1998| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PAUL FREDRICKSON R2 | | |WILLIAM KANE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: GRANT MILLS, NC | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NORTH CAROLINA DEPARTMENT OF ENVIRONMENT AND NATURAL RESOURCES DIVISION | | OF RADIATION PROTECTION NOTIFIED THE NUCLEAR REGULATORY COMMISSION OF A | | DAMAGED MOISTURE DENSITY GAUGE AT A NC JOBSITE. | | | | ON 12/17/98, NORTH CAROLINA LICENSEE ECS, LTD, NOTIFIED NC THAT A MOISTURE | | DENSITY GAUGE CONTAINING 10mCi OF Cs-137 AND 50mCi OF Am-241(Be) WAS DAMAGED | | BY HEAVY PAVING EQUIPMENT AT A JOBSITE. THE ACCIDENT TOOK PLACE ON 12/09/98 | | RESULTING IN DAMAGE TO THE GAUGE MAKING RETRACTION OF THE SOURCE ROD | | IMPOSSIBLE (THE ROD WAS IN THE MEASUREMENT POSITION AT THE TIME OF THE | | RETRACTION). THE GAUGE OPERATOR RETURNED THE GAUGE TO ITS TRANSPORT CASE | | AND PLACED IT IN STORAGE AT THE LICENSEE'S HOME OFFICE. THE LICENSEE HAS | | MADE ARRANGEMENTS WITH THE GAUGE MANUFACTURER FOR INSPECTION, EVALUATION AND | | RECOMMENDATIONS BY A MANUFACTURER REPRESENTATIVE WHO IS TRAVELING TO THE | | LICENSEE'S HOME OFFICE. THE LICENSEE HAS COMMITTED TO PROVIDE NC WITH A | | FULL REPORT AFTER THE EVALUATION. IT IS ANTICIPATED THAT THE MANUFACTURER'S | | REPRESENTATIVE WILL ARRANGE FOR THE SHIPMENT OF THE GAUGE TO THE | | MANUFACTURER'S FACILITY. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35164 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: PROFESSIONAL SERVICE INDUSTRIES INC |NOTIFICATION DATE: 12/17/1998| |LICENSEE: PROFESSIONAL SERVICE INDUSTRIES INC |NOTIFICATION TIME: 14:52[EST]| | CITY: SEATTLE REGION: 4 |EVENT DATE: 12/16/1998| | COUNTY: STATE: WA |EVENT TIME: [PST]| |LICENSE#: WN-IR021-1 AGREEMENT: Y |LAST UPDATE DATE: 12/17/1998| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |IAN BARNES R4 | | |WILLIAM KANE NMSS | +------------------------------------------------+ROSEMARY HOGAN IRD | | NRC NOTIFIED BY: TERRY FRAZEE, WA | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT - OVEREXPOSURE OF INDIVIDUAL | | | | The following information was received via Email in the NRC Operations | | Center: | | Licensee: Professional Service Industries, Inc. | | City and state: Seattle, WA | | License number: WN-IR021-1 | | Type of license: Radiography | | Date of Event: December 16, 1998 | | Location of Event: Seattle, WA | | | | ABSTRACT: The licensee had set up for a series of 2 minute ceiling shots in | | the parking garage of an office building in Seattle. One radiographer | | monitored the floor above the parking garage while the shot took place. | | It is not clear at this time why or how, but two contractor employees were | | inside the parking garage with the second radiographer during the shots. | | During one shot the radiographer was talking with the contractor employees. | | Apparently, one of the contractor employees walked away and, for reasons not | | known at this time, approached the source collimator. The contractor | | employee's actions caused the collimator to become | | dislodged from the source guide tube. The contractor employee reassembled | | the source and guide tube at the same time that the radiographer became | | aware of the situation. The radiographer immediately shouted a warning and | | ran to crank in the source. The licensee RSO was notified and radiography | | operations were suspended. The licensee began an immediate investigation, | | including a re-enactment, and notified the state radiation control program. | | Preliminary dose estimates for the extremities range from 600 to 1700 REM. | | The whole body exposure is estimated to be approximately 50 REM. The | | overexposed individual's physician has already contacted REAC/TS. An | | investigation team from the state radiation control program is on site. | | | | Activity and Isotope(s) involved: 60 Curies of Iridium-192. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35165 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 12/17/1998| | UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 15:38[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/16/1998| +------------------------------------------------+EVENT TIME: 03:37[EST]| | NRC NOTIFIED BY: DAVE JESTER |LAST UPDATE DATE: 12/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 | |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 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE | | | | "On 12/16/98, at approximately 0337 hours, the Unit 2 High Pressure Coolant | | Injection (HPCI) turbine exhaust line vacuum breaker isolation valve, | | 2E41-F079, was closed and placed under clearance. This action was taken to | | support a maintenance activity on the valve power supply auto bus transfer | | device. Prior to closing the valve, Technical Specifications and associated | | bases were reviewed to determine what LCOs were required, and if HPCI should | | be declared inoperable. The results of that review determined that since | | the breaker for the valve would be placed in the OFF position, a PCIV LCO | | was required. During the planning of this activity it was not identified | | that closing the vacuum breaker isolation valve would render HPCI | | inoperable. | | | | "Following review of the condition by Engineering personnel, it was revealed | | that HPCI was in fact inoperable with the turbine exhaust line vacuum | | breaker line isolated. This determination was based on the fact that HPCI | | must meet various design basis conditions. One of these conditions requires | | that the system be able to operate through multiple start-stop-start cycles. | | In this mode, HPCI is acting as a backup to the Reactor Core Isolation | | Cooling System. In addition, HPCI may be required to restart due to | | specific transient conditions. With this line isolated, water could be | | drawn up into the turbine exhaust line upon turbine shutdown, with a | | subsequent restart potentially causing a water hammer in the turbine exhaust | | line. This water hammer could result in the turbine tripping on high | | turbine exhaust pressure, with potential damage to the turbine exhaust line | | itself. | | | | "After discussions with Engineering, the Control Room (at approximately 1025 | | hours on 12/16/98) determined that HPCI should be declared inoperable with | | the turbine exhaust line isolated, the appropriate LCOs were initiated, and | | the event reviewed for reportability. Since the valve was closed to support | | scheduled maintenance, and the valve was declared inoperable, it was felt | | that this event met the criteria for a planned maintenance evolution, and | | was therefore not reportable as a condition that alone could have prevented | | the fulfillment of a safety function needed to mitigate the consequences of | | an accident. Following a review of the event by plant management, it was | | determined at approximately 1200 hours on 12/17/98, that the event did not | | fit the criteria for a planned event under the guidance of NUREG 1022 | | Revision 1, and was indeed reportable. This determination was based on the | | fact that the inoperability of HPCI itself was not identified as part of the | | planned maintenance activity." | | The NRC Resident Inspector has been informed of this report by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35166 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 12/17/1998| | UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 18:18[EST]| | RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 12/17/1998| +------------------------------------------------+EVENT TIME: 15:22[MST]| | NRC NOTIFIED BY: A. BREESE |LAST UPDATE DATE: 12/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |IAN BARNES R4 | |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 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | |3 N Y 100 Power Operation |100 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INABILITY TO PROPERLY ACTIVATE OFFSITE SIRENS | | | | During a monthly surveillance, the licensee discovered that the offsite | | sirens in the emergency planning zone could not be properly activated due to | | a dirty relay in a microwave repeater. The sirens were restored to service | | at 1530 MST. The NRC Resident Inspector will be informed of this event by | | the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35167 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 12/17/1998| | UNIT: [1] [] [] STATE: AL |NOTIFICATION TIME: 18:28[EST]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/17/1998| +------------------------------------------------+EVENT TIME: 15:30[CST]| | NRC NOTIFIED BY: CUMBY |LAST UPDATE DATE: 12/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 STEAM GENERATOR TUBES NOT STRUCTURALLY SOUND | | | | The licensee has determined that several Unit 1 steam generator tubes failed | | to meet the structural integrity burst requirement of three times the normal | | operating differential pressure. The affected tubes are: | | | | Steam Generator Tube | | Basis | | 1B R25C51 | | in-situ testing and destructive examination | | 1B R43C32 | | in-situ testing | | 1C R10C02 | | in-situ testing | | | | The NRC Resident Inspector will be informed of this notification by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35168 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/17/1998| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 23:25[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 12/17/1998| +------------------------------------------------+EVENT TIME: 20:50[CST]| | NRC NOTIFIED BY: CRAIG JORGENSEN |LAST UPDATE DATE: 12/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |IAN BARNES R4 | |10 CFR SECTION: | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 1 Startup |1 Startup | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE | | | | While performing High Pressure Coolant Injection (HPCI) System surveillance | | procedure #6.HPCI.313, "HPCI (150 psig) Beginning of Cycle Test," the HPCI | | turbine tripped on overspeed. Reactor pressure was approximately 160 psig | | at the time of the test. The RCIC System was inoperable at the time of this | | event (see related EN 35162). The licensee is currently troubleshooting and | | venting the HPCI System. | | | | The NRC Resident Inspector has been informed by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 35169 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/18/1998| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 04:53[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/17/1998| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/18/1998| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JOHN JACOBSON R3 | | DOCKET: 0707002 |WILLIAM KANE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEITH WILLIAMSON | | | HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NRC BULLETIN 91-01 REPORT - 24 HOUR REPORT - LOSS OF ENRICHMENT CONTROL - | | | | AT 1830 ON 12/17/98, PORTSMOUTH GASEOUS DIFFUSION PLANT NUCLEAR CRITICALITY | | SAFETY DEPARTMENT PERSONNEL DETERMINED THAT A NUCLEAR CRITICALITY SAFETY | | APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED WITHIN THE X-333 | | PROCESS BUILDING. NCSA PLANT-033.A01 REQUIREMENT #6 STATES "THE ENRICHMENT | | IN THE X-333 SURGE DRUMS IS LIMITED TO 3.0% U-235". THIS REQUIREMENT WAS | | NOT MAINTAINED, THUS VIOLATING CONTROL "A" (ENRICHMENT) OF THE DOUBLE | | CONTINGENCY MATRIX A/B.5.1. ENRICHMENT SAMPLE RESULTS INDICATED 3.46% | | U-235. | | | | AT 2133, CONTROL "A" WAS REESTABLISHED BY CALCULATED DILUTION. | | | | AT 2206, ENRICHMENT SAMPLE RESULTS (1.45% U-235) CONFIRMED THE ADEQUACY OF | | THIS DILUTION. | | | | CONTROL "B" (MODERATION) WAS MAINTAINED THROUGHOUT THIS EVENT. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL NOR RADIOACTIVE OR | | RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | +------------------------------------------------------------------------------+