Event Notification Report for April 18, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/17/2001 - 04/18/2001 ** EVENT NUMBERS ** 37902 37923 37924 37925 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37902 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/09/2001| | UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 11:08[EDT]| | RXTYPE: [3] B&W-L-LP |EVENT DATE: 04/09/2001| +------------------------------------------------+EVENT TIME: 09:54[EDT]| | NRC NOTIFIED BY: RICHARD SWEENEY |LAST UPDATE DATE: 04/17/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 | |10 CFR SECTION: | | |*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |3 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION TO THE NATIONAL MARINE AND FISHERIES SERVICE AS A | | RESULT OF THE ENDANGERED SEA TURTLES NON-LETHAL TAKE LIMIT BEING EXCEEDED | | | | "On April 09, 2001 at 0940 the 40th non-lethal sea turtle take in the | | biennial period occurred. | | | | "In accordance with Crystal River Unit #3 Operating License, Appendix B, | | Environmental Protection Plan (Non-Radiological), 'Endangered or threatened | | sea turtles shall be protected in accordance with the Incidental Take | | Statement issued by the National Marine and Fisheries Service (NMFS).' The | | NMFS has established numerical limits on live takes, lethal takes causally | | related to plant operation, and lethal takes not related to plant | | operations. | | | | "The NMFS must be notified within five days whenever: | | | | a. The 40th non-lethal take occurs in the biennial period, or | | b. The third causally related mortality occurs in the biennial period, or | | c. The sixth non-causally related mortality occurs in the biennial | | period. | | | | "The current biennial period for monitoring sea turtle takes began January | | 1, 2001. | | | | "Thus, in accordance with Crystal Unit #3 Administrative Instruction 571, | | Sea Turtle Rescue and Handling Guidance, the NMFS must be notified within | | five days. | | | | "In accordance with Crystal River Unit #3 Compliance Procedure 151, External | | Reporting Requirements, this 40th non-lethal sea turtle take is Reportable | | as a 4-Hour Report under 10 CFR 50.72(b)(2)(xi) as this event is related to | | the protection of the environment for which a notification to other | | government agencies has been or will be made." | | | | The licensee will inform the NRC resident inspector. | | | | * * * UPDATE 0944EDT ON 4/10/01 FROM R. SWEENEY TO S. SANDIN * * * | | | | "On April 10, 2001 at 0859 the 41st non-lethal sea turtle take in the | | biennial period occurred." | | | | The licensee informed the NRC resident inspector. Notified R2DO(Julian). | | | | ***** UPDATE RECEIVED AT 0911 ON 04/17/01 FROM CHRISTOPHER PELLERIN TO LEIGH | | TROCINE ***** | | | | The 42nd, non-lethal, sea turtle take in the biennial period occurred at | | 0810 on April 17, 2001. | | | | The licensee notified the NRC resident inspector. The NRC operations | | officer notified the R2DO (Ernstes). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 37923 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/17/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 05:46[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/16/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 07:10[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/17/2001| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |RONALD GARDNER R3 | | DOCKET: 0707002 |JOSEPHINE PICCONE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ERIC SPAETH | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT INVOLVING A VALID ACTUATION OF A "Q" CLASS SAFETY SYSTEM | | | | "At 0710 hours on 04/16/01, Autoclave #4 in the X-344 UF6 Sampling Facility | | had an 'AUTOCLAVE HI HI PRESSURE' alarm activation. This alarm initiates an | | 'Autoclave Shell High Pressure Containment Shutdown', which causes the | | autoclave containment isolation valves ('Q' components) to actuate. The | | containment isolation valves closed, as designed. The initiating devices for | | this alarm are redundant pressure switches with a TSR set point of 8.0 psig. | | Autoclave #4 was in TSR Operational Mode IV (Feeding, Transfer, or Sampling) | | at the time of the alarm activation. Operations personnel immediately | | responded to the alarm in accordance with the approved Alarm Response | | Procedures. Autoclave #4 was placed in TSR mode VII (Shutdown) by operations | | personnel and declared inoperable by the Plant Shift Superintendent. | | | | "Instrument Maintenance was requested to perform 'as-founds' on the | | 'Autoclave Pressure Loop Instrumentation'. The results of this data | | indicated that the instrumentation associated with the 'Autoclave Internal | | Pressure Loop' was found to be within acceptable 'as-found' tolerance. Based | | on these results, this event is being reported as a valid safety system | | actuation, a 24-hour NRC event. An Engineering Evaluation has been requested | | to investigate the circumstances surrounding this safety system actuation." | | | | Operations will inform the DOE site representative and has informed the NRC | | resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37924 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/17/2001| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 17:24[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 04/17/2001| +------------------------------------------------+EVENT TIME: 13:30[EDT]| | NRC NOTIFIED BY: ROBERT MCCOY |LAST UPDATE DATE: 04/17/2001| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |WILLIAM RULAND R1 | |10 CFR SECTION: | | |*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EMERGENCY NOTIFICATION SIRENS INOPERABLE | | | | "During modification of siren system, testing resulted in 30% of the sirens | | not communicating with the activation points. Modification stopped. | | Troubleshooting in progress." | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37925 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/17/2001| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 17:40[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/17/2001| +------------------------------------------------+EVENT TIME: 15:42[EDT]| | NRC NOTIFIED BY: SUE SIMPSON |LAST UPDATE DATE: 04/17/2001| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |WILLIAM RULAND R1 | |10 CFR SECTION: | | |*ESF 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 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VALID CONTAINMENT VENTILATION ISOLATION | | | | "While in Mode Undefined (core offloaded), Salem Unit 1 received a | | Containment Ventilation Isolation signal due to elevated count rate on | | 1R11A, the Containment Particulate Radiation Monitor. The 1R11A setpoint is | | set two times background in accordance with Tech Spec 3.3.3.1 for Mode 6. | | Background count rate prior to the CVI was 2100 cpm (counts per minute). The | | alarm setpoint was 2980 cpm. | | | | "The observed count rate when the actuation occurred was 3300 cpm. | | Maintenance activities in progress included the breech of 14SJ43, Cold Leg | | Injection Check Valve. Elevated airborne activity was expected due to this | | evolution and had been discussed by Control Room personnel. When 1R11A | | exceeded its setpoint, all containment ventilation isolation valves closed | | as designed. This actuation has not impacted the Unit 1 outage. | | | | "Plant status before and after event: | | Reactor Coolant System drained to mid-loop | | RCS at approximately 90�F | | Core completely offloaded | | Mode Undefined" | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021