Event Notification Report for August 12, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/11/1999 - 08/12/1999 ** EVENT NUMBERS ** 35943 36010 36014 36015 36016 36017 36018 36019 36020 36021 36022 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35943 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/21/1999| | UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 18:48[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/21/1999| +------------------------------------------------+EVENT TIME: 18:00[EDT]| | NRC NOTIFIED BY: MIKE VASELY |LAST UPDATE DATE: 08/11/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JAMES NOGGLE R1 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 99 Power Operation |99 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS - SILICONE SEALANT NOT PROPERLY APPLIED TO SOME | | EQUIPMENT | | | | During an engineering inspection of the condition of the sealant used to | | satisfy environmental qualification requirements, several components were | | found to have seal conditions that did not meet the Con Edison design | | specifications. In each case it is believed that the degraded condition | | identified will not prevent the associated equipment from performing its | | intended safety functions and operability determinations are being completed | | to document these conclusions. The specific problems identified are as | | follows: | | | | - MSIV limit switches | | - Auxiliary feedwater flow indication | | - Motor driven auxiliary feedwater pumps recirculation valves | | - City water backup solenoid valves and limit switches to motor driven | | auxiliary feedwater pumps. | | | | An inspection plan is being developed to determine the extent of this | | condition. | | | | The licensee informed the NRC Resident Inspector. | | | | *** UPDATE ON 8/11/99 @ 1110 BY BALLETTA TO GOULD *** RETRACTION | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE FURTHER INVESTIGATION | | DETERMINED, THAT IN ALL CASES WHERE THE COMPONENTS' SEALANT WAS NOT WITHIN | | THE ACCEPTANCE CRITERIA FOR THE LICENSEE'S DESIGN SPECIFICATION, THE | | COMPONENTS WERE OPERABLE AND CAPABLE OF PERFORMING THEIR RESPECTIVE SAFETY | | FUNCTIONS. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | | | | THE REG 1 RDO(GRAY) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36010 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/10/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:49[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/09/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:30[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/12/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 | | DOCKET: 0707002 |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: RICK LARSON | | | HQ OPS OFFICER: WILLIAM POERTNER | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BULLETIN 91-01 24 HOUR REPORT | | | | Operations personnel during a walkdown of the seal exhaust system discovered | | that a nuclear criticality safety analysis (NCSA) requirement, maximum oil | | volume, could not be verified when an oil level was observed in the pumps | | separator's sight glass. The pumps in question were used for the highly | | enriched uranium (HEU) program, and after it's suspension, prior to March | | 1997, the pumps were placed out of service. Visible oil level in the sight | | glass without supporting documentation for oil capacity of these pumps | | constitutes a loss of one control (Volume) for double contingency. The | | second control (Interaction) was maintained. | | | | There was no loss of hazardous/radioactive material or | | radioactive/radiological contamination exposure as a result of this event. | | | | The licensee notified the NRC resident inspector and DOE. | | | | *** UPDATE ON 8/12/99 @ 0130 BY SPAETH TO GOULD *** | | | | WALKDOWNS OF SEAL EXHAUST PUMPS IN THE X-326 BUILDING REVEALED THAT SEVERAL | | OLD STYLE/OUT OF SERVICE PUMPS (KDH-80, DVD-8810) HAD INDICATION OF OIL IN | | THE SEPARATOR SITE GLASS, ABOVE THE LEVEL OF THE OVERFLOW. THIS IS A LOSS | | OF ONE CONTROL (VOLUME) OF THE DOUBLE CONTINGENCY PRINCIPLE. THE SECOND | | CONTROL (INTERACTION) REMAINS IN PLACE. THIS UPDATE IS BEING SUBMITTED TO | | IDENTIFY THE FACT THAT ADDITIONAL PUMPS WERE IDENTIFIED IN WHICH THE MAXIMUM | | AMOUNT OF OIL COULD NOT BE VERIFIED. | | | | THE NRC RESIDENT INSPECTOR AND DOE WERE NOTIFIED BY THE LICENSEE. | | | | REG 3 RDO(BURGESS) AND NMSS EO(HICKEY) WERE NOTIFIED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36014 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 08/11/1999| | UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 10:40[EDT]| | RXTYPE: [1] W-3-LP |EVENT DATE: 08/11/1999| +------------------------------------------------+EVENT TIME: 06:40[EDT]| | NRC NOTIFIED BY: PALMER |LAST UPDATE DATE: 08/11/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHARLES OGLE R2 | |10 CFR SECTION: | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE ENTERED AN LCO ACTION STATEMENT DUE TO INCORRECT RADIATION | | MONITOR SETPOINTS. | | | | FOUR CONTAINMENT VENTILATION ISOLATION RADIATION AREA MONITORS WERE | | DETERMINED TO HAVE A NON-CONSERVATIVE HIGH VALUE FOR BACKGROUND RADIATION | | LEVEL. THIS RESULTS IN A NON-CONSERVATIVE SETPOINT FOR THE CONTAINMENT | | VENTILATION ISOLATION FUNCTION. THIS CONDITION ALSO PLACED THE PLANT IN AN | | LCO ACTION STATEMENT REQUIRING THEM TO ISOLATE NORMAL CONTAINMENT PURGE, | | WHICH THEY HAVE ALREADY DONE. CORRECTIVE ACTION WILL BE TO RECALIBRATE THE | | SETPOINTS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | | | | * * * UPDATE 1653 8/11/1999 FROM PALMER TAKEN BY STRANSKY * * * | | | | "This is a followup notification to our report made at 1040 this morning. | | The nonconservative setpoints for the containment ventilation isolation | | function from the four containment area radiation monitors has been | | corrected. The setpoints were corrected and the area radiation monitors | | declared operable at 1225 today. We are still investigating if this was an | | actual 'loss of a safety function'. Followup notification will be provided | | in the applicable 10 CFR 50.73 notification." | | | | The NRC resident inspector will be informed of this update by the licensee. | | Notified R2DO (Ogle). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36015 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 08/11/1999| | UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 12:04[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 08/11/1999| +------------------------------------------------+EVENT TIME: 09:25[CDT]| | NRC NOTIFIED BY: DAVE NETERER |LAST UPDATE DATE: 08/11/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DALE POWERS R4 | |10 CFR SECTION: |ROBERT BENNEDICT NRR | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |FRANK CONGEL IRO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 M/R Y 100 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO HEATER DRAIN LINE BREAK | | | | Operators manually tripped the reactor after receiving indication of a steam | | leak in the turbine building. An 8" diameter line from the 'D' 1st stage | | reheater drain tank to the '6B' high pressure heater experienced a double | | ended guillotine break. All control rods inserted into the core following | | the trip, and all systems functioned as designed. The licensee reported that | | the unit is currently stable in Hot Standby, and the steam leak has been | | isolated. No personnel injuries resulted from this event. | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36016 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 08/11/1999| | UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 13:43[EDT]| | RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 08/11/1999| +------------------------------------------------+EVENT TIME: 10:06[EDT]| | NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 08/11/1999| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |HAROLD GRAY R1 | |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INADVERTENT DIESEL GENERATOR START DURING TROUBLESHOOTING OF A SPEED CONTROL | | PROBLEM | | | | The following text is a portion of a facsimile received from the licensee: | | | | "On 08/11/99 at 1006, Nine Mile Point Unit 2 experienced an inadvertent | | start of the Division I Diesel Generator during troubleshooting of a speed | | control problem. This speed control problem had been experienced earlier | | when the Diesel no-load frequency could not be controlled from the control | | room when the Diesel was started for the monthly surveillance/PMT run. The | | Division I Diesel has been inoperable since 0710 on 08/10/99 for preplanned | | maintenance." | | | | "The primary starting circuit relay 4X1 had already been diagnosed with high | | resistance readings across shut contacts indicating that it needed | | replacement. Further troubleshooting was desired to ensure the remainder of | | the primary starting circuit was operating correctly prior to restarting the | | Diesel. The primary starting circuit relay 4X1 was removed from the circuit | | and a test meter was placed on the coil inputs for the 4X1 relay to monitor | | coil voltage when the DS9 optical isolator receiver was actuated by a | | flashlight. This action allowed testing of the optical isolator receiver | | board 'E' without inducing an engine start. The fact that board 'A' DS11 | | optical isolator receiver would also turn on was missed during the planning | | of the emergent work order. The DS11 optical isolator activation caused a | | secondary start signal to be generated which initiated the inadvertent | | Diesel start." | | | | "This notification is being made per 10CFR50.72 (b)(2)(ii) for 'any event or | | condition that results in a manual or automatic actuation of any Engineered | | Safety Feature.' Although the actuation was invalid, the actuation was not | | pre-planned, and the Diesel was not removed from service." | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36017 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/11/1999| | UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 14:08[EDT]| | RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/11/1999| +------------------------------------------------+EVENT TIME: 13:53[EDT]| | NRC NOTIFIED BY: KEN TRUESDALE |LAST UPDATE DATE: 08/11/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |HAROLD GRAY R1 | |10 CFR SECTION: | | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY OF A HISTORICAL CONDITION INVOLVING LOW DIESEL GENERATOR VOLTAGE | | | | The licensee determined that voltage for the 'B' emergency diesel generator | | would not have met the technical specification criteria, and this rendered | | the 'B' emergency diesel generator inoperable approximately 32 days prior to | | 08/05/99. Although the voltage was discovered to be low during a test run | | of the 'B' emergency diesel generator on 08/05/99, it was thought to be | | acceptable (satisfactory) at the time of the test run. However, subsequent | | engineering review determined that the voltage was in fact below the | | technical specification acceptance criteria. | | | | The licensee determined this event to be reportable at 1353 on 08/11/99. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36018 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/11/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:46[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/10/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/11/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 | | DOCKET: 0707002 |JOHN HICKEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM McCLEERY | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF 13 HIGH PRESSURE FIRE WATER SPRINKLER SYSTEMS TO MEET SYSTEM | | OPERABILITY REQUIREMENTS (24-Hour Report) | | | | The following text is a portion of a facsimile received from Portsmouth: | | | | "On 08/10/99 at approximately 1600 hours, the Plant Shift Superintendent | | (PSS) was notified that 13 sprinkler systems associated with the High | | Pressure Fire Water (HPFW) system were not capable of meeting system | | operability requirements. This condition was discovered as a result of an | | engineering review of individual sprinkler heads that had previously been | | identified as exhibiting corrosion around the valve seat. The engineering | | review was conducted following the discovery that similar corrosion problems | | experienced at the Paducah Gaseous Diffusion Plant resulted in sprinkler | | heads being unable to actuate at normal pressure. An initial screening of | | PORTS sprinkler heads known to exhibit corrosion was conducted, and systems | | where the potential for two or more adjacent heads to be corroded were | | inspected. This identified 11 systems in the X-333 and 2 systems in the | | X-326 that did not meet the sprinkler system operability requirement that no | | two adjacent sprinkler heads be inoperable." | | | | "The PSS declared the affected sprinkler systems inoperable, and TSR | | required actions were completed. Further inspections of sprinkler systems | | are planned. This report will be updated if additional sprinkler systems | | are determined to be inoperable." | | | | "There was no loss of hazardous/radioactive material or | | radioactive/radiological contamination exposure as a result of this | | event." | | | | Portsmouth personnel notified the NRC resident inspector as well as the | | onsite Department of Energy representative. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36019 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 08/11/1999| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 15:12[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 08/11/1999| +------------------------------------------------+EVENT TIME: 15:00[EDT]| | NRC NOTIFIED BY: MIKE MICKLOW |LAST UPDATE DATE: 08/11/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |HAROLD GRAY R1 | |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 | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT ONE OF SIX RESIDUAL HEAT REMOVAL (RHR) PUMP ANCHOR BOLTS WAS | | MISSING | | | | The following text is a portion of a facsimile received from the licensee: | | | | "During [an] engineering walkdown of [the] 'B' RHR pump, it was determined | | that (1) corner anchor bolt was missing out of a total of (6) anchor bolts. | | Preliminary analysis indicates that [the] existing anchorage configuration | | cannot be seismically qualified." | | | | The unit is in a 72-hour limiting condition for operation as a result of | | this issue. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36020 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 08/11/1999| | UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 16:34[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 08/11/1999| +------------------------------------------------+EVENT TIME: 15:33[CDT]| | NRC NOTIFIED BY: DAVID CLARIDGE |LAST UPDATE DATE: 08/11/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DALE POWERS R4 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | VCT OUTLET VALVES DO NOT MEET 10 CFR 50, APPENDIX R SEPARATION REQUIREMENT | | | | The volume control tank (VCT) outlet valves (BG-LCV-1112B and C) are located | | approximately 42" apart, and are not separated by a three hour rated fire | | barrier. A postulated fire in this area could prevent these valves from | | being closed. The valves are normally open to provide a suction source for | | the centrifugal charging pumps. The postulated fire could prevent the VCT | | from being isolated from the CCP suction, permitting the hydrogen cover gas | | in the VCT to enter the suction of the CCPs, damaging the pumps and causing | | the loss of high head safety injection. In addition, the VCT level | | transmitters associated with the above mentioned valves are not separated by | | a fire barrier, and are less than 20 feet apart. A postulated fire could | | damage both level transmitters, preventing the VCT from isolating upon low | | level. | | | | The licensee considers this condition to be outside the design basis of the | | plant for fire protection of safe shutdown components. A continuous fire | | watch has been posted, and, in the event of a fire, actions will be taken to | | isolate the VCT. If these actions are not successful, the boric acid | | transfer pump will be started to provide a water source to the CCPs to | | prevent hydrogen intrusion into the CCP suction. The licensee is currently | | working to find a permanent solution to this condition. | | | | The NRC resident inspector will be informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36021 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/11/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:51[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/11/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:50[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/11/1999| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |BRUCE BURGESS R3 | | DOCKET: 0707001 |JOHN HICKEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEVIN BEASLEY | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GASEOUS DIFFUSION REPORT - UF6 DETECTION SYSTEM RENDERED INOPERABLE | | | | "At 1350, on 8/11/99. maintenance personnel were in the process of | | completing repairs to valves in the C-333-A feed facility. During this work, | | a pressure indicator was bumped by the maintenance personnel causing a | | spark, which shorted out the fuse to the #1 North and South autoclaves power | | supply. The power supply, for the local autoclave area audible and visual | | alarms for the UF6 Release Detection System are fed from the #1 autoclaves | | control power. Due to the loss of control power to the #1 autoclaves, the | | UF6 Release Detection System was rendered inoperable. At the time of this | | incident, the C-333-A facility was in an operational mode in which the UF6 | | Release Detection System was required to be operable. Limiting Conditions | | for Operation (LCO) required actions were put in place until power could be | | restored. Power was restored, and the UF6 Release Detection was operable at | | 1715 on 8/11/98. | | | | "It has been determined that this event is reportable under | | 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to | | function as designed." | | | | The NRC resident inspector has been informed of this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 36022 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/12/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:30[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/11/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:35[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/12/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 | | DOCKET: 0707002 |JOHN HICKEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: SPAETH | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR 91-01 BULLETIN RESPONSE | | | | On 8/11/99 at 1235 hrs the Plant Shift Superintendent(PSS) was notified that | | a Nuclear Criticality Safety Approval (NCSA) requirement was not being | | maintained in the X-333 process building. NCS Engineering, while performing | | a Pre-implementation walkdown of an NCSA, noticed a depression in the floor | | around a building column (X-333 operating floor) that is greater than 1.5 | | inches deep (approx. 1.75 to 2 inches). A 12-position rack for storing | | small diameter uranium bearing containers is located directly above the | | depression. (NCSA-PLANT025) | | | | Requirement #10 of NCSA-PLANT025.A01 states in part, "Storage areas shall | | not be located over equipment or spaces that could confine a spill to a | | depth of greater than 1.5 inches. In the event of a spill or a loss of | | container integrity, the depression in the floor (a violation of requirement | | #10) could result in an unfavorable geometry." | | | | At the direction of the Plant Shift Superintendent the requirements for an | | NCS anomalous condition were initiated and the area bounded off. | | | | Safety significance of the event is low and the diked area would have to be | | full of uranium at optimum moderated conditions for criticality to be | | possible. Geometry was the controlled parameter that was lost. The mass of | | material (uranium solution with a max allowed enrichment of 10%) is not | | controlled therefore more than a safe mass could be in the containers. | | | | Corrective action was to remove all small containers from the storage area | | and reestablish NCS compliance. | | | | 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. | | | | The DOE Representative will be notified. | +------------------------------------------------------------------------------+
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