Event Notification Report for December 15, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/14/1999 - 12/15/1999
** EVENT NUMBERS **
36506 36507 36508 36509 36510 36511 36512
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|Power Reactor |Event Number: 36506 |
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/14/1999|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 00:27[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/13/1999|
+------------------------------------------------+EVENT TIME: 20:45[CST]|
| NRC NOTIFIED BY: DAVE BOWMAN |LAST UPDATE DATE: 12/14/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SAFETY SYSTEM FAILURE: THE BREAKER FOR THE "B" TRAIN REFRIGERATION CONTROL |
| UNIT (RCU) TRIPPED. |
| |
| The licensee started the "B" control room HVAC to support routine |
| maintenance on "A" train. The "B" train would not operate properly on |
| non-safety-related cooling (station service water). Safety-related cooling |
| (RHR service water ) was started to provide cooling to the "B" train, which |
| operated properly on safety-related cooling. After the control room had |
| cooled down, the "B" train was shut down and then restarted with |
| non-safety-related cooling, after which it operated properly. During |
| subsequent swap to the "A" train, the breaker for the "B" train RCU tripped. |
| This is a safety system functional failure. The licensee entered Technical |
| Specification 3.8.D.1.b for RCU inoperable, which is a 30-day limiting |
| condition of operation. Troubleshooting of the problem is in progress. |
| This is part of the control room emergency ventilation system. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 36507 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 12/14/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 07:21[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 12/14/1999|
+------------------------------------------------+EVENT TIME: 03:55[EST]|
| NRC NOTIFIED BY: M GRIFFIN |LAST UPDATE DATE: 12/14/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSATE PUMP |
| |
| The plant was initially at 100% power. At 0354 EST, a ground fault occurred |
| on the "A" condensate pump resulting in a loss of the "A" condensate pump. |
| This caused a subsequent trip of the "A" condensate booster pump and "A" |
| main feedwater (MFW) pump. The plant automatically ran back to |
| approximately 60% power. Steam generator (SG) levels lowered and approached |
| the automatic trip setpoint so the reactor was manually tripped from |
| approximately 60% at 0355 EST. All rods fully inserted into the core. The |
| auxiliary feedwater (AFW) pumps were manually started to aid SG level |
| control; however, an automatic AFW initiation signal was properly received. |
| All ESF components actuated as required. There were no safety problems |
| encountered after the trip. The plant is stable in Hot Shutdown with main |
| feedwater in service. No power-operated relief valves opened. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36508 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 12/14/1999|
| UNIT: [] [2] [3] STATE: AL |NOTIFICATION TIME: 10:05[EST]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 12/13/1999|
+------------------------------------------------+EVENT TIME: 14:25[CST]|
| NRC NOTIFIED BY: R. SANFIELD |LAST UPDATE DATE: 12/14/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A RANDOM DRUG TEST WAS PERFORMED ON A CONTRACT FOREMAN, AND NITRATES WERE |
| FOUND IN HIS SAMPLE WHICH INDICATED THAT THE SAMPLE HAD BEEN ADULTERATED. |
| THE CONTRACT FOREMAN'S ACCESS AND BADGE WERE PULLED ON CONFIRMATION. HE WAS |
| ESCORTED OFFSITE, AND HIS WORK IS BEING REVIEWED. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36509 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TN DIVISION OF RADIOLOGICAL HEALTH |NOTIFICATION DATE: 12/14/1999|
|LICENSEE: AMERICAN ECOLOGY RECYCLE CENTER |NOTIFICATION TIME: 12:18[EST]|
| CITY: OAK RIDGE REGION: 2 |EVENT DATE: 12/09/1999|
| COUNTY: STATE: TN |EVENT TIME: 13:15[EST]|
|LICENSE#: R-01037 AGREEMENT: Y |LAST UPDATE DATE: 12/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANN BOLAND R2 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DEBRA SHULTS | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FIRE IN SLUDGE DRYER |
| |
| "The licensee reported a fire (no flames) in their sludge dryer. |
| Technicians noticed a glow in the dryer. The building was evacuated |
| immediately. The gas line, which provide heat to the dryer, was cut off, |
| and the smoke began to subside. Water was piped into the sludge dryer to |
| squelch the remaining embers. A stop-work order was placed on the dryer |
| after it was secured. The air filtration system was shut down in order to |
| change the pre-filters. The contamination was localized to the sooty |
| deposits that appeared to be within a few feet of the sludge dryer. There |
| was no spread of contamination beyond that area. Work place air samplers |
| operated continuously during the event. Results have not been released at |
| this time. Employees who were in the area during the event received whole |
| body counts. Results were negative. The fire department was not called." |
| |
| (Call the NRC operations officer for a contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36510 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MERITER HOSPITAL |NOTIFICATION DATE: 12/14/1999|
|LICENSEE: MERITER HOSPITAL |NOTIFICATION TIME: 12:50[EST]|
| CITY: MADISON REGION: 3 |EVENT DATE: 12/14/1999|
| COUNTY: STATE: WI |EVENT TIME: 10:25[CST]|
|LICENSE#: 480039502 AGREEMENT: N |LAST UPDATE DATE: 12/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SHEAR R3 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JAMES YANG | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| POSSIBLE MEDICAL MISADMINISTRATION |
| |
| During insertion of iodine-125 (I-125) seeds in a prostate treatment, one of |
| the needles broke during seed planting and remains in the patient about 3 |
| centimeters outside the prostate gland. The needle retained four of the |
| seeds, each containing 0.326 mCi of I-125. The needle has been left in |
| place, as that has been determined to be in the best interest of the patient |
| at this time. The attending physician was present and the patient informed. |
| There will be little impact on the treatment of the prostrate. The licensee |
| is evaluating whether any adverse effect to the patient is expected of this |
| possible misadministration, the seeds located outside the treatment site. |
| The hospital contacted NRC Region 3 inspector (James Cameron). |
| |
| (Call the NRC operations officer for a contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36511 |
+------------------------------------------------------------------------------+
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| REP ORG: H. C. NUTTING CO. |NOTIFICATION DATE: 12/14/1999|
|LICENSEE: H. C. NUTTING CO. |NOTIFICATION TIME: 13:08[EST]|
| CITY: CINCINATTI REGION: 3 |EVENT DATE: 12/14/1999|
| COUNTY: STATE: OH |EVENT TIME: 09:50[EST]|
|LICENSE#: 34-18882-01 AGREEMENT: Y |LAST UPDATE DATE: 12/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SHEAR R3 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HAROLD WIDNER | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN TROXLER MOISTURE DENSITY GAUGE |
| |
| The licensee reported a Troxler moisture density gauge (model 3430, serial |
| number 28862) stolen some time last night after 2110 CST from the cargo area |
| of a locked Nissan Pathfinder. The gauge was in a locked box in the vehicle |
| at the technician's home in Cincinnati. The gauge sources contain 8 mCi of |
| Cs-137 and 40 mCi of Am/Be-241. The City of Cincinnati Police responded and |
| are investigating the theft (no report number at this time). The licensee |
| notified the Ohio Bureau of Radiation Safety, part of the Department of |
| Health as part of their license requirement. |
| |
| (Call the NRC operations officer for a contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36512 |
+------------------------------------------------------------------------------+
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| REP ORG: ITT INDUSTRIES |NOTIFICATION DATE: 12/14/1999|
|LICENSEE: ITT INDUSTRIES |NOTIFICATION TIME: 17:10[EST]|
| CITY: LANCASTOR REGION: 1 |EVENT DATE: 12/14/1999|
| COUNTY: STATE: PA |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 12/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |HAROLD GRAY R1 |
| |ANN BOLAND R2 |
+------------------------------------------------+GARY SHEAR R3 |
| NRC NOTIFIED BY: RICHARD RANSALL |PHIL HARRELL R4 |
| HQ OPS OFFICER: FANGIE JONES |VERN HODGE (Fax) NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 10-CFR-PART-21 REPORT ON 3-INCH DIAPHRAGM VALVES WITH 3250L ACTUATORS |
| |
| "Recently, Engineered Valves was asked by a customer to perform tests and |
| analysis documenting the maximum shutoff pressure for a diaphragm valve |
| configuration. Based on testing and engineering calculations performed in |
| November and December of 1999, Engineered Valves has discovered that 3" |
| diaphragm valves with 3250L actuators, supplied to the nuclear power |
| industry, may not be capable of bubble tight shutoff at customer specified |
| operating conditions. |
| |
| "These valves were supplied to the nuclear power industry for design |
| pressures up to 200 psig and were factory tested at or above specified |
| shutoff pressure depending on design specification or ASME Section III |
| requirements. The testing and analysis described above indicate that there |
| is a statistical possibility, depending on the tolerances of each valve and |
| actuator component, that a valve can be built which will shut off bubble |
| tight at no more than 147 psig. Therefore, it is possible that a valve, |
| which has been maintained or repaired with new components or subassemblies |
| might not have sufficient actuator thrust to shut off against the specified |
| pressure." |
| |
| Purchasers and sites include the following: |
| Westinghouse Electric Corporation at multiple locations |
| TVA at Bellefonte |
| Louisiana Power and Light at Waterford |
| Toledo Edison at Davis Besse |
| Iowa Electric at Duane Arnold |
| Pacific Gas and Electric at Diablo Canyon |
| Consolidated Edison at Indian Point |
| Virginia Electric and Power Company at Surry |
| Florida Power and Light at Turkey Point and St. Lucie |
| Duke Energy Corp. at Oconee |
| |
| Due to organizational and name changes, include the following names as |
| possible organizations over the past 31 years: ITT Corporation, ITT |
| Grinnell Corporation, ITT Grinnell Valve Division, ITT Dia Flo, ITT |
| Specialty Valve Group, ITT Fluid Products Corporation, ITT Fluid Technology |
| Corporation, ITT Engineered Valves, and ITT Industries. |
| |
| Engineered Valves is now finalizing the list of affected purchasers and will |
| notify them by Monday, 12/20/99. |
| |
| (Call the NRC operations officer for ITT Engineered Valves contact |
| information.) |
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