Event Notification Report for September 20, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/19/2001 - 09/20/2001 ** EVENT NUMBERS ** 38295 38296 38297 38298 38299 +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38295 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/19/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:00[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/19/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:13[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/19/2001| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA R3 | | DOCKET: 0707002 |SUSAN FRANT NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: MIKE RICHIE | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING AN OPACITY VIOLATION (4-hour Report) | | | | The following text is a portion of a facsimile received from Portsmouth | | personnel: | | | | "At 0813 hours [on] 09/19/01, the Ohio Environmental Protection Agency | | (OEPA) was notified per Ohio Administrative Code (OAC) 3745-15-06(B) that an | | opacity exceedance had occurred at the X-600 Steam Plant. The opacity | | violation occurred on [the] #2 Boiler when our #2A Precipitator voltages | | began to fluctuate. Operators adjusted load/air requirements on the #2 | | Boiler in an effort to prevent further exceedances. [The] cause of the | | voltage fluctuations has not been determined at this time." | | | | "This is reportable as a 4-hour NRC Event due to notification to an outside | | agency (OEPA) being made per Nuclear Regulatory Reporting Procedure | | UE2-PAE1030, Appendix D, Criteria P (Miscellaneous)." | | | | Portsmouth personnel notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38296 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HONEYWELL INTERNATIONAL, INC. |NOTIFICATION DATE: 09/19/2001| | RXTYPE: URANIUM HEXAFLUORIDE PRODUCTION |NOTIFICATION TIME: 10:16[EDT]| | COMMENTS: UF6 CONVERSION (DRY PROCESS) |EVENT DATE: 09/19/2001| | |EVENT TIME: 09:05[CDT]| | |LAST UPDATE DATE: 09/19/2001| | CITY: METROPOLIS REGION: 3 +-----------------------------+ | COUNTY: MASSAC STATE: IL |PERSON ORGANIZATION | |LICENSE#: SUB-526 AGREEMENT: Y |JOHN MADERA R3 | | DOCKET: 04003392 |SUSAN FRANT NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: HUGH ROBERTS | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |JBBE 40.60(b)(2) SAFETY EQUIPMENT FAILUR| | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY DIESEL GENERATOR FAILED TO START AND IS UNAVAILABLE | | | | The licensee reported that a standby diesel generator failed to start in | | manual and automatic during a test. The generator is unavailable as | | redundant for required safety function. The generator is being worked on. | | The plant is shutting down their processing until repairs are made. | | | | The licensee will submit a 30-day written report and is notifying NRC Region | | 3. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38297 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/19/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:04[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/19/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:45[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/19/2001| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA R3 | | DOCKET: 0707002 |BRIAN SMITH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: MCCLEERY | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE ISOLATION | | | | OTHER NON-CFR REQUIREMENT - 24 HOUR NOTIFICATION | | | | At 1245 hours on 09/19/01, both the "A" and "B" High Level Condensate probes | | activated on Autoclave # 3 in the X-334 uranium hexafluoride Sampling | | Facility causing a High Condensate Alarm. The activation of either of these | | probes will cause the autoclave steam supply valves ("Q" components) to | | actuate (close). The steam supply valves closed, as designed, autoclave # 3 | | was in TSR Mode 2 (Heating) at the time of the alarm activation. Operations | | personnel immediately responded to the alarm in accordance with the approved | | Alarm Response Procedures. The alarm reset when operations personnel | | drained excess condensate from autoclave drain line, and then acknowledged | | the alarm at the local autoclave control panel. All autoclave (and | | cylinder) operating parameters were determined to be within normal ranges. | | Autoclave # 3 was placed in TSR mode 7 (Shutdown) by operations personnel | | and declared inoperable by the Plant Shift Superintendent. Based on the | | actuation of both High Level Condensate probes, 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. | | | | The NRC Resident Inspector was notified of this event by the certificate | | holder. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38298 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/19/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:36[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/19/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:06[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/19/2001| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA R3 | | DOCKET: 0707002 |ERIC LEEDS NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: MCCLEERY | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 24 NOTIFICATION | | | | During a meeting to discuss compensatory actions for PR-PTS-01-04202, | | additional concerns were raised regarding compliance with the requirements | | of NCSA-705-076. Specifically, exterior walls have openings (windows and | | gaps) which could allow uranium bearing solution to spray outside the | | facility and collect in an unfavorable geometry inadvertent container. A | | walk down was performed. The findings resulted in a violation of control # | | 3 of NCSA 705-76, inadvertent containers. Compliance with NCSA was | | reestablished with the closure of windows, caulking of identified openings | | and continued shutdown of system involved. | | | | SAFETY SIGNIFICANCE OF EVENTS: | | | | The safety significance is low because there was no leak of uranium bearing | | material! near the identified openings in the walls of the X-705. The two | | areas in question are designated as "Inadvertent Container Area" due to the | | presence of the Recovery System and Microfiltration, neither of which are | | currently in operation due to a stand down of all X-705 operations. The | | presence of an inadvertent container in the area is a violation of NCS | | controls and one leg of the double contingency principle as described in | | NCSE-0705 _076.E.03. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW | | CRITICALITY COULD OCCUR): | | | | For a criticality to occur, the following events would be required: The | | recovery system or Microfiltration would have to be operating and processing | | uranium bearing liquid with a high concentration of uranium. Then a leak in | | this system must occur such that an unsafe amount of liquid sprays from the | | system directly through an open window or through another penetration in the | | building wall. The liquid would then have to flow or drip into a potentially | | unfavorable geometry that may be present immediately adjacent to the outside | | building wall. Depending on the volume collected, some reflection would | | also be required to sustain a critical chain reaction The Recovery and | | Microfiltration systems are not currently in operation. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION. ETC.): | | | | Inadvertent containers are controlled based upon volume (2.5 liters maximum) | | or geometry (1.5 inches in depth or 4 inches in diameter). The exact | | potential collection volume for this event is unknown. Although analyzed | | for 100% enriched materials, the Recovery System would Currently process | | materiel with less than or equal to 5% enrichment | | | | ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE OF CRITICAL MASS): | | | | No uranium bearing material was involved in this event. There were no leaks | | of uranium bearing materiel in the area during this event. The event | | involves the presence of an unsafe geometry (via an opening in the building | | block wall) that could collect solution in the event of a spill. | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: | | | | The presence of holes in the exterior building walls could lead to the | | collection of a spill or leak in the unfavorable geometry space. This is a | | violation of control #3 of NCSA-0705_076, Inadvertent Containers, which | | specifically evaluates this event. Compliance with inadvertent container | | controls was reestablished for a shutdown Recovery system and for the | | Microfiltration system (running or shutdown) within four hours of | | discovery. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: | | | | Compliance with the NCSA was reestablished with the closure of windows, | | caulking of identified openings and continued shutdown of Systems involved. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38299 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 09/19/2001| | UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 22:12[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/19/2001| +------------------------------------------------+EVENT TIME: 20:15[EDT]| | NRC NOTIFIED BY: P. MCINTYRE |LAST UPDATE DATE: 09/19/2001| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |SCOTT SPARKS R2 | |10 CFR SECTION: | | |ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N N 0 Refueling |0 Refueling | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BORIC RESIDUE BUILDUP | | | | Visual inspection of the Unit 2 Steam Generator 2B (SG 2B) lower head bowl | | drain during the current refueling outage indicated boron residue buildup on | | the 0.5" piping immediately below the SG. The total volume of residue was | | approximately 1 cubic inch. The origin appears to be the partial | | penetration of a weld between the reducing coupling and the lower head | | shell. Exact location could not be conclusively determined at this time and | | additional inspection using NDE will be conducted. Visual inspection of the | | other three SG's was also conducted and no indications of leakage were | | identified. State and Local officials will be given a courtesy call. | | | | | | The NRC Resident Inspector will be notified by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021