Event Notification Report for August 2, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/01/2001 - 08/02/2001 ** EVENT NUMBERS ** 38149 38179 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38149 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/18/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:05[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/17/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:30[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/01/2001| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN R3 | | DOCKET: 0707002 |BRIAN SMITH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: SALYERS | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |OCBA 76.120(c)(2) SAFETY EQUIPMENT FAILUR| | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE FIRE WATER SPRINKLER SYSTEM DECLARED INOPERABLE | | | | On 7/17/01 at approximately 1530 hrs, the Plant Shift Superintendent (PSS) | | was notified that during a Fire Protection Engineering assessment/inspection | | that High Pressure Fire Water (HPFW) sprinkler system #165 in the X-333 | | Building contained five adjacent sprinkler heads with visible corrosion | | deposits. Previous engineering reviews have concluded that the system under | | this condition would not be capable of meeting the Technical Safety | | Requirements (TSR) to maintain operability. | | | | The PSS declared the affected sprinkler system inoperable and TSR required | | actions were implemented. | | | | The NRC Resident Inspector was notified along with the DOE Representative. | | | | * * * RETRACTION ON 08/01/01 AT 1600 ET BY KURT SISLER TAKEN BY MACKINNON * | | * * | | | | This event is being retracted based upon engineering evaluation | | (EVAL-SE-2001-0321) approved on July 31, 2001. Functional testing of these | | sprinkler heads was conducted. The results showed that all these sprinkler | | heads would have operated when needed and performed their intended safety | | function. R3DO (John Madera) & NMSS EO (Brian Smith) notified. | | | | The NRC resident inspector was notified of this retraction by the | | certificate holder. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38179 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/01/2001| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 09:05[EDT]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/01/2001| +------------------------------------------------+EVENT TIME: 07:01[CDT]| | NRC NOTIFIED BY: BRUCE ANDERSON |LAST UPDATE DATE: 08/02/2001| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |PATRICK HILAND R3 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 NEGATIVE FLUX RATE | | | | The unit automatically tripped from 100%; the first out annunciator was Flux | | Rate Reactor Trip. Immediately following the trip, the rod position | | indicator showed that five control rods did not insert completely. The stuck | | control rods indicated 15-20 steps out from bottom. Operators entered their | | reactor trip/safety injection emergency procedure (1E0), but were able to | | transition to the trip recovery procedure (1ES0.1). One of the stuck control | | rods subsequently indicated full insertion. The unit is currently stable in | | Mode 3. Operators are emergency borating the reactor per 1ES0.1 a total of | | 1000 gallons (250 gallons per stuck rod). The licensee is continuing their | | trip recovery. Preliminary investigation indicates a problem with the rod | | control system may have led to one or more dropped control rods. | | | | The NRC resident inspector has been informed of this event by the licensee. | | | | * * * UPDATE 1025 EDT 8/1/01 FROM DAMMANN TAKEN BY JONES * * * | | | | The licensee reported that the auxiliary feedwater (AFW) system (pumps 11 | | and 12) automatically actuated on steam generator low-low level following | | the trip, as expected. In addition, two of the stuck rods are now | | indicating full insertion. The NRC resident inspector has been informed of | | this update. | | | | * * * UPDATE 1624 EDT 08/01/01 FROM GOSMAN TAKEN BY MACKINNON * * * | | | | After interviewing the Reactor Operators it was determined that 6 rod bottom | | lights did not immediately come on after the reactor trip. Also a media | | press release will be made concerning this event. R3DO (John Madera) | | notified. | | | | The NRC resident inspector was notified of this update by the licensee. | | | | * * * UPDATE 0431 EDT 8/2/01 FROM IRVIN TAKEN BY STRANSKY * * * | | | | "Investigation into the cause of the reactor trip has determined that | | control rods associated with Rod Control Power Cabinet 2AC began to insert | | into the core. As designed, the reactor protection system actuated to insert | | the remaining control rods. | | | | "In accordance with procedures, operators verified the reactor had safely | | shutdown. However, indicator lights for six of twenty-nine individual | | control rods did not indicate that the rods had fully inserted. This | | situation is addressed in the reactor trip procedure and the operators | | responded appropriately by borating to compensate. | | | | "Control rod drop testing has been performed and has verified that all | | control rods fully inserted. Individual rod position indication calibration | | check is in progress." | | | | The NRC resident inspector will be informed of this update by the licensee. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021