Event Notification Report for January 13, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/12/2000 - 01/13/2000
** EVENT NUMBERS **
36552 36580 36581 36582 36583 36584 36585 36586
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|Fuel Cycle Facility |Event Number: 36552 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/30/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:45[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/30/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:30[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/12/2000|
| 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: ERIC WALKER | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NOTE: THIS EVENT IS A CONTINUATION OF EVENT #35790. |
| |
| At 1130 CST on 12/30/99, the Plant Shift Superintendent (PSS) was notified |
| that during walkdowns of the High Pressure Fire Water System in C-337, a |
| total of 13 corroded sprinkler heads were discovered in System B-2. The |
| system was declared inoperable and actions were taken as required by the |
| technical safety requirement. The PSS determined that an update to this |
| event report is required. |
| |
| The NRC Resident Inspector has been notified of this event. |
| |
| * * * UPDATE 2233EST ON 1/12/00 FROM ERIC WALKER TO S. SANDIN * * * |
| |
| At 0910 on 1/12/00 the Plant Shift Superintendent (PSS) was notified that |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337, |
| two adjacent corroded heads were discovered on system B-10. Per Engineering |
| Notice C-822-99-047 Rev. 2, the criteria necessary for system operability |
| was not being met. The system was declared Inoperable and actions were taken |
| as required by the TSR. The PSS determined that an update to this event |
| report is required. |
| |
| 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 notified of this event. Notified |
| R3DO(Clayton) and NMSS(Haughney). |
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|Power Reactor |Event Number: 36580 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/11/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 22:26[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/11/2000|
+------------------------------------------------+EVENT TIME: 17:52[CST]|
| NRC NOTIFIED BY: STEVE WHEELER |LAST UPDATE DATE: 01/12/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
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EVENT TEXT
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| POSTULATED CONDUCTOR-TO-CONDUCTOR SHORT IN FIRE PUMP CONTROL CIRCUITRY COULD |
| INHIBIT THE ABILITY OF THE PLANT TO SAFELY SHUT DOWN FOLLOWING A FIRE. |
| |
| "During preparation of the permanent plant modification to replace a |
| Temporary Modification associated with LER 96-009-03, another configuration |
| was found that could inhibit the ability of the plant to safely shutdown |
| following a fire. For an Alternate Shutdown Fire (10 CFR 50 Appendix R |
| Section III.L) in the Cable Spreading Room fire area, the Diesel Fire pump |
| is relied upon to provide emergency backup gland seal water to the essential |
| service water pumps. A fire scenario in the cable spreading room assumes of |
| a loss of offsite power (which disables the normal gland water supply) as |
| well as concurrent hot shorts which disable the emergency gland seal water |
| supply MOV's (because their control cables are routed through the Cable |
| Spreading Room). A multi-conductor cable located in the Cable Spreading Room |
| carries 24 VDC start control circuits and 120 VAC annunciator power |
| circuits. The postulated fire scenario requires the assumption that the fire |
| could cause a conductor to conductor short within this cable such that the |
| 24 VDC circuits would be energized by the 120 VAC power. This would disable |
| the automatic starting capability of the diesel fire pump (the currently |
| credited emergency backup gland seat water). A fire watch has been posted |
| in the Cable Spreading Room as a compensatory measure. The Cable Spreading |
| Room fire area is the only fire area affected by this configuration. The |
| operator's ability to recognize and correct a loss of gland water to the |
| Service Water pumps would not be impaired. Sufficient procedural guidance is |
| provided for the post-fire restoration of the essential service water pumps |
| such that loss of gland seal water would have been detected prior to service |
| water pump damage. Fire fighting activities would have immediately indicated |
| loss of the fire pump. A modification to separate the starting circuits from |
| the power circuits is being pursued. CNS has conservatively concluded that |
| this postulated scenario is reportable under 10CFR50. 72(b)(2)(iii)(A). |
| |
| "The NRC Resident Inspector has been notified." |
| |
| * * * UPDATE 1833EST ON 1/12/00 FROM STEVEN JOBE TO S. SANDIN * * * |
| |
| "Per the requirements of 10 CFR 50.72 (c) (2), the licensee is providing the |
| following additional information. |
| |
| "The 120 VAC annunciator power circuits referred to in the initial report |
| are more appropriately described as indicating lamp power circuits. |
| |
| "As additional clarification, the diesel fire pump running capability would |
| be disabled along with the automatic starting capability. |
| |
| "Based on further investigation, the licensee has determined that |
| insufficient time exists to recognize and correct the loss of gland seal |
| water prior to the onset of service water pump damage. |
| |
| "The compensatory measures described in the initial report (posting of fire |
| watch) are still in place. These measures, in conjunction with the defense |
| in depth fire protection program, are adequate to ensure the ability of the |
| plant to safely shutdown following a fire, and are consistent with the |
| facility license and the guidance of Information Notice 97-78 'Inadequate or |
| Inappropriate Interim Fire Protection Compensatory Measures." |
| |
| "Evaluation of this postulated scenario is ongoing and additional action |
| will be taken as appropriate. |
| |
| "The Senior Resident lnspector has been notified." |
| |
| Notified R4DO(Shackelford). |
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|General Information or Other |Event Number: 36581 |
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| REP ORG: TEST-CON |NOTIFICATION DATE: 01/12/2000|
|LICENSEE: TEST-CON |NOTIFICATION TIME: 12:19[EST]|
| CITY: DANBURY REGION: 1 |EVENT DATE: 01/12/2000|
| COUNTY: STATE: CT |EVENT TIME: 08:00[EST]|
|LICENSE#: 06-30240-01 AGREEMENT: N |LAST UPDATE DATE: 01/12/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LAWRENCE DOERFLEIN R1 |
| |KEVIN RAMSEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHIN OKWUKA | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STOLEN HUMBOLT MOISTURE DENSITY GAUGE |
| |
| THE RADIATION SAFETY OFFICER (RSO) FOR TEST-CON , LOCATED AT 16 E. FRANKLIN |
| IN DANBURY, CT 06810, REPORTED THAT A HUMBOLT MODEL 5001 MOISTURE DENSITY |
| GAUGE, SERIAL NUMBER 1967, CONTAINING TWO (2) RADIOACTIVE SOURCES [8 mCi |
| Cs-137 AND 40 mCi Am-241:Be) WAS STOLEN FROM A VEHICLE PARKED ON MORRIS AVE |
| IN BRONX, NY. THE DEVICE WAS REMOVED BETWEEN 0500 AND 0700 HOURS ON 1/12 |
| FROM THE TRUNK OF A HYUNDAI AUTO WITH NO VISIBLE SIGN OF FORCED ENTRY. |
| |
| THE LICENSEE INFORMED NRC REGION I AND WILL FILE A POLICE REPORT WITH THE NY |
| CITY PD. |
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|Power Reactor |Event Number: 36582 |
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| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 01/12/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 14:52[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 01/12/2000|
+------------------------------------------------+EVENT TIME: 14:19[EST]|
| NRC NOTIFIED BY: TOM EGAN |LAST UPDATE DATE: 01/12/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| UNPLANNED INOPERABILITY OF HIGH PRESSURE CORE SPRAY DUE TO REQUIRED |
| SURVEILLANCE TESTING NOT PERFORMED (TECH. SPEC. 4.3.3.3) |
| |
| "THE REQUIRED RESPONSE TIME TESTING OF HIGH PRESSURE CORE SPRAY SYSTEM |
| ACTUATION INSTRUMENTATION WAS NOT PERFORMED WITH THE TECH SPEC SURVEILLANCE |
| FREQUENCY. THE INSTRUMENTATION HAS BEEN DECLARED INOPERABLE. THE HIGH |
| PRESSURE CORE SPRAY HAS BEEN DECLARED INOPERABLE PER TECH SPEC 3.3.3 ACTION |
| 36b. |
| |
| "WITH HIGH PRESSURE CORE SPRAY INOPERABLE, ENTERED TECH SPEC 3.5.1.c.1 (14 |
| DAY LCO)." |
| |
| THIS IS AN 18-MONTH SURVEILLANCE WHICH WAS LAST PERFORMED MARCH 1997. THE |
| LICENSEE IDENTIFIED THAT AN INCORRECT SURVEILLANCE INTERVAL WAS USED IN THE |
| TRACKING SYSTEM. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
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|Power Reactor |Event Number: 36583 |
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/12/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 17:26[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/12/2000|
+------------------------------------------------+EVENT TIME: 15:15[CST]|
| NRC NOTIFIED BY: MARK S. FELTNER |LAST UPDATE DATE: 01/12/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|AMED 50.72(b)(2)(v) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| TRANSPORT OFFSITE OF POTENTIALLY CONTAMINATED INJURED EMPLOYEE |
| |
| "At 1515 on 1/12/2000, an injured contract employee at River Bend Station |
| was transported offsite to the West Feliciana Hospital for medical |
| treatment. The individual was erecting scaffolding in the Turbine Building, |
| fell approximately 20 feet and sustained injuries. The individual was |
| working inside the Controlled Access Area, but not inside a Contaminated |
| Area, and a thorough survey for radioactive contamination could not be |
| performed prior to transport. Therefore, the individual is considered to be |
| potentially contaminated. |
| |
| "In accordance with plant administrative procedures. a radiation protection |
| technician is accompanying the ambulance to the hospital and a second |
| radiation protection technician has been dispatched to the hospital as |
| well." |
| |
| The NRC Resident Inspector was informed. |
| |
| * * * UPDATE 2057EST ON 1/12/2000 FROM ROHM TO S. SANDIN * * * |
| |
| "The injured contract employee has been verified not contaminated. |
| Preliminary medical evaluation revealed no life threatening injuries." |
| |
| The licensee informed the NRC Resident Inspector. Notified |
| R4DO(Shackelford). |
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|General Information or Other |Event Number: 36584 |
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| REP ORG: STATE OF CALIFORNIA |NOTIFICATION DATE: 01/12/2000|
|LICENSEE: GOFFMAN, McCORMICK & URBAN |NOTIFICATION TIME: 19:14[EST]|
| CITY: RANCHO SANTA MARGARITA REGION: 4 |EVENT DATE: 01/10/2000|
| COUNTY: STATE: CA |EVENT TIME: [PST]|
|LICENSE#: 3674 (CA) AGREEMENT: Y |LAST UPDATE DATE: 01/12/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JEFF SHACKELFORD R4 |
| |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DONALD BUNN | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
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EVENT TEXT
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| STOLEN CAMPBELL PACIFIC NUCLEAR MOISTURE DENSITY GAUGE |
| |
| ON 1/10, A CAMPBELL PACIFIC NUCLEAR (CPN) MOISTURE DENSITY GAUGE MODEL M, |
| SERIAL NUMBER 36076956, WAS STOLEN FROM A VEHICLE IN IRVINE, CA. THE GAUGE |
| CONTAINS TWO (2) SOURCES (9 mCi Cs-137 AND 40 mCi Am-241: Be). THE |
| LICENSEE, GOFFMAN, McCORMICK AND URBAN, INC. LOCATED IN RANCHO SANTA |
| MARGARITA, CA, REPORTED THE LOSS TO THE STATE OF CALIFORNIA RADIOLOGIC |
| HEALTH BRANCH (INCIDENT #011100) AND THE IRVINE POLICE DEPARTMENT. A REWARD |
| HAS BEEN OFFERED IN THE LOCAL NEWSPAPER. |
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|Power Reactor |Event Number: 36585 |
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| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 01/13/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 02:55[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/13/2000|
+------------------------------------------------+EVENT TIME: 00:59[CST]|
| NRC NOTIFIED BY: STEWART DRESSER |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SWITCHYARD FAULT RESULTED IN MAIN GENERATOR TRIP/TURBINE TRIP/REACTOR TRIP. |
| |
| At 0059CT a Reactor Trip occurred on Unit 2. A fault in the switchyard |
| resulted in a Main Generator Trip which caused a Turbine Trip/Reactor Trip. |
| All rods fully inserted into the core. All other systems responded per |
| design with the following exceptions: |
| |
| 1). Unit 1/Unit 2 Containment Ventilation Actuation occurred (caused by |
| electrical spike in the switchyard). This is not an ESF Actuation because |
| all the Containment Ventilation Isolation valves were already closed. |
| |
| 2). Fuel Handling Building Ventilation ESF Actuation occurred (caused by |
| the electrical spike in the switchyard). |
| |
| 3). "A" Train Main Control Room Makeup Air Filter Unit ESF Actuation |
| occurred (caused by the electrical spike in the switchyard). |
| |
| All Emergency Core Cooling Systems and the Emergency Diesel Generators are |
| fully operable if needed. At this time the Motor Driven Auxiliary Feedwater |
| Pump is maintaining proper Steam Generator Water Levels with Tave being |
| maintained at a no load temperature of 557 degrees F. |
| |
| Switchyard fault is being investigated. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
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|Power Reactor |Event Number: 36586 |
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| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 01/13/2000|
| UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 04:21[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/13/2000|
+------------------------------------------------+EVENT TIME: 03:26[EST]|
| NRC NOTIFIED BY: JIM BURGESS |LAST UPDATE DATE: 01/13/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR 17 MINUTES DUE TO LOW DIFFERENTIAL |
| PRESSURE BETWEEN CONTROL ROOM AND THE AUXILIARY BUILDING. |
| |
| A LOW CONTROL ROOM VENTILATION SYSTEM DIFFERENTIAL PRESSURE WAS DISCOVERED |
| WHILE CONTROL ROOM VENTILATION SYSTEM AND AUXILIARY BUILDING VENTILATION |
| SYSTEM COMPENSATORY ACTION IN EFFECT DUE TO AUXILIARY BUILDING VENTILATION |
| SYSTEM WORK. LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 AT 0326ET. AT |
| 0333ET THE LICENSEE SECURED "2A" AUXILIARY BUILDING VENTILATION FILTER |
| EXHAUST FAN. TECHNICAL SPECIFICATION 3.0.3 WAS EXITED AT 0343ET AFTER |
| CONTROL ROOM DIFFERENTIAL PRESSURE WAS VERIFIED ABOVE MINIMUM LIMIT. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. |
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Page Last Reviewed/Updated Thursday, March 25, 2021