Event Notification Report for February 23, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/22/2000 - 02/23/2000
** EVENT NUMBERS **
36689 36716 36717 36718 36719
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36689 |
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| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 02/14/2000|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 12:19[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/14/2000|
+------------------------------------------------+EVENT TIME: 10:30[CST]|
| NRC NOTIFIED BY: TIM ERGER |LAST UPDATE DATE: 02/22/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|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 |
| | |
| | |
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EVENT TEXT
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| THREE CONTAINMENT NITROGEN MAKEUP FOR TORUS AND DRYWELL VALVES ARE NOT |
| CAPABLE OF CLOSING DURING A DESIGN BASIS ACCIDENT. |
| |
| Control Room was notified by system engineering that design basis review |
| calculations have determined that Air Operated Valves CV4311, CV4312, and |
| CV4313 (containment nitrogen makeup for torus and drywell) are not capable |
| of closing during a design basis accident. The spring closing force is |
| borderline such that the spring force may not be large enough to close the |
| valve when the containment is at its maximum pressure during a design basis |
| accident. |
| |
| CV4311, CV4312, and CV4313 have been declared inoperable. The licensee |
| entered Technical Specification 3.6.1.3 condition B to isolate the affected |
| penetrations within one hour. The valves have been closed and at this time |
| the licensee is de-energizing the power to the valves. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE AT 1137 ON 02/22/00 BY BRIAN HUPKE TO JOLLIFFE * * * |
| |
| After testing the above valves and reviewing the margins in the analysis |
| used, the licensee has concluded that the valves were actually capable of |
| performing their intended containment isolation function. The licensee |
| declared these valves operable at 1619 CST on 02/17/00. Since this event is |
| no longer reportable to the NRC, the licensee desires to retract this event |
| and does not plan to submit an LER on this event. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R3DO Jim Creed. |
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|General Information or Other |Event Number: 36716 |
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| REP ORG: NC DIV OF RADIATION PROTECTION |NOTIFICATION DATE: 02/22/2000|
|LICENSEE: SRB TECHNOLOGIES |NOTIFICATION TIME: 12:16[EST]|
| CITY: WINSTON-SALEM REGION: 2 |EVENT DATE: 02/22/2000|
| COUNTY: STATE: NC |EVENT TIME: 10:15[EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 02/22/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES OGLE R2 |
| |DON COOL NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: LEE COX | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| - UPS is searching for an overdue shipment of a box of 10 fire exit signs |
| which contain tritium gas - |
| |
| At 1015 on 02/22/00, Lee Cox, North Carolina Division of Radiation |
| Protection (NC DRP), was notified that 1 of 10 cardboard boxes of fire exit |
| signs did not arrive at the intended destination. The missing box contains |
| 10 model #B-100 fire exit signs; each sign contains 17 curies of tritium |
| gas. The signs were shipped via UPS from SRB Technologies Company (NC |
| Licensee), Winston-Salem, NC on 01/27/00 and were scheduled to arrive at DMA |
| Company, Salt Lake City, UT on 02/03/00. On 02/07/00, the shipper, SRB |
| Technologies Company, was notified by the receiver, DMA Company, that 1 of |
| the 10 boxes of signs had not arrived in Salt Lake City. On 02/22/00, the |
| shipper notified NC DRP of the missing box of signs and that UPS is |
| searching for the missing box of signs. |
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|Fuel Cycle Facility |Event Number: 36717 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/22/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:54[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/22/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:00[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/22/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED R3 |
| DOCKET: 0707002 |BRIAN SMITH NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NRC BULLETIN 91-01, 4 HOUR REPORT - |
| |
| At 1200 on 02/22/00, the Plant Shift Superintendent (PSS) was notified by |
| the Nuclear Criticality Safety staff that there was a Fissile Material |
| Operation (FMO) for which no Nuclear Criticality Safety Approval (NCSA) |
| existed. While reviewing NCSAs to determine the requirements for moving |
| cylinders into the X-710 laboratory building, it was discovered that the |
| transportation or movement of a five inch diameter cylinder in the X-710 |
| laboratory building hallways was not addressed in any current NCSA. |
| |
| Activities involving the use of five inch diameter cylinders in the X-710 |
| laboratory are addressed by NCSA-0710-006 (Uranium Sampling Laboratory). |
| The laboratory extracts samples from process sampling cylinders, empties, |
| decontaminates and prepares cylinders for reuse in the process facilities. |
| NCSA-0710-006 failed to specifically identify and analyze the movement of |
| five inch diameter cylinders in the X-710 building hallway as an activity to |
| be evaluated. |
| |
| SAFETY SIGNIFICANCE OF EVENTS: |
| |
| Since there is an issue of non-coverage of An FMO, this event is being |
| reported as a Level 2 event - Loss of all double contingency controls |
| applicable to an FMO. However, in practice, the requirements of |
| NCSA-0710-006 are followed. The only time a five inch diameter cylinder is |
| moved out of the Uranium Sampling Laboratory (and into the hallway) is to |
| load them into a PLANT043 transport vehicle. There are also spacing |
| requirements associated with this NCSA. All of the spacing requirements |
| have been met while transporting five inch diameter cylinders through the |
| X-710 building hallway. Therefore, the safety significance is very low. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED [BRIEF SCENARIO(S) OF HOW CRITICAUTY |
| COULD OCCUR]: |
| |
| If a cylinder was not spaced 24 inches from other uranium-bearing material, |
| the chance of a criticality would be increased. Since the cylinders from |
| the Uranium Sampling Laboratory are limited to 5% U-235 enrichment, multiple |
| cylinder spacing upsets would be required before a criticality would be |
| possible (since the evaluation performed in PLANT043 considers two eight |
| inch diameter cylinders in contact at 97.65% U-235 and determines that they |
| would be subcritical). |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, etc): |
| |
| The parameters controlled are the geometry of the five inch diameter |
| cylinder, the enrichment of the cylinder, and spacing between |
| uranium-bearing material and a five inch diameter cylinder. All controls on |
| parameters were maintained. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| The five inch diameter cylinders have a favorable geometry for any |
| enrichment, but are limited to 5% U-235 by an administrative control. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: |
| |
| The NCS controls on cylinder geometry, enrichment, and spacing were |
| maintained. A failure has occurred in that the boundaries for NCSAs are |
| unclear as written in their process descriptions. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| At the direction of the PSS, the requirements for an NCS Anomalous Condition |
| were initiated. A "Stop Work Notice" was implemented with the following |
| requirements: 1) No movement of five inch diameter cylinders in hallways of |
| the X-710 building. 2) No movement of five inch diameter cylinders into or |
| out of the X-710 building. |
| |
| There was no loss of hazardous or radioactive material nor radioactive or |
| radiological contamination exposure as a result of this event. |
| |
| The NRC Resident Inspector has been notified of this event. |
| |
| PTS-2000- 018 PR-PTS-00-01046 |
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|Power Reactor |Event Number: 36718 |
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| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 02/22/2000|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 22:59[EST]|
| RXTYPE: [2] GE-4 |EVENT DATE: 02/22/2000|
+------------------------------------------------+EVENT TIME: 22:05[EST]|
| NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 02/22/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 97 Power Operation |97 Power Operation |
| | |
| | |
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EVENT TEXT
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| Plant Physical Security Event - |
| |
| Vital area door keys inadvertently removed from the site. Compensatory |
| measures were not fully implemented in the required time but are now fully |
| implemented. The licensee plans to notify the NRC Resident Inspector. |
| Contact the NRC Operations Officer for additional details. |
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|Fuel Cycle Facility |Event Number: 36719 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/22/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:29[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/21/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 23:45[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/23/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED R3 |
| DOCKET: 0707002 |ROBERT PIERSON NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| HIGH DISCHARGE ALARM FOR THE W-2 COMPRESSOR. LEAK TESTING OF THE W-2 |
| COMPRESOR INDICATE A SEAL FAILURE WITH POTENTIAL FOR URANIUM HEXAFLUORIDE |
| OUT GASSING. |
| |
| At approximately 2347 hours, 02/21/00, operations personnel received a |
| Cascade Automatic Data Processing (CADP) smoke head alarm for Extended Range |
| Product (ERP) W-2 withdrawal station compressor. Operations personnel had |
| responded to a High Discharge Alarm for the W-2 compressor and upon arrival |
| discovered the compressor shutdown and the CADP smoke head in alarm. No |
| smoke was discovered during the investigation of the alarm, however the |
| smoke head is located inside a heated housing not readily accessible to |
| operations personnel. Leak testing of the W-2 compressor indicated a seal |
| failure with potential for uranium hexafluoride out gassing. |
| |
| Operations and engineering personnel are continuing to investigate the cause |
| of the smoke head alarm, but have not provided evidence at this time to |
| invalidate the alarm. PORTS is reporting this alarm as a valid actuation to |
| a "Q" Safety System. |
| |
| There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this event. |
| |
| |
| The NRC Resident Inspector was notified of this event by the certificate |
| holder. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021