Event Notification Report for April 27, 2000
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/26/2000 - 04/27/2000 ** EVENT NUMBERS ** 36911 36930 36931 36932 36933 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36911 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/20/2000| | UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 20:29[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/20/2000| +------------------------------------------------+EVENT TIME: 19:30[EDT]| | NRC NOTIFIED BY: DOUG AMTHFIELD |LAST UPDATE DATE: 04/26/2000| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN WHITE R1 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LICENSEE NOTIFIED NATIONAL RESPONSE CENTER AND STATE DEP OF A CHEMICAL | | SPILL ONSITE - | | | | The licensee notified the National Response Center and the State Department | | of Environmental Protection (DEP) that approximately 5 gallons of a mixture | | of sulfuric acid and sodium hydroxide spilled from a tank truck onto the | | ground after a chemical reaction took place. The spill was contained within | | a portable dike area onsite and is being cleaned up. | | | | The licensee plans to notify the NRC Resident Inspector. | | | | * * * UPDATE AT 0948 EDT ON 04/26/00 FROM ROY HARDING TO S. SANDIN * * * | | | | The licensee is retracting this report based on the following: | | | | "This is a retraction of the notification made on 04/20/00 at 2029 hours | | (Event 36911). This event was reported as a notification of another | | government agency [National Response Center and Pennsylvania Department of | | Environmental Protection (PADEP)] pursuant to 10CFR50.72(2)(b)(vi). | | | | "On April 20, 2000 at 1930 hours while Limerick Unit 1 was shutdown for | | refueling, 5 to 10 gallons of a dilute and partially neutralized acid | | (Sulfuric Acid-pH 3) was expelled from a temporary trailer tank onto asphalt | | and stone surface in an adjacent area outside a temporary dike. In | | addition, approximately 30 gallons of the acid/sludge mixture spilled into | | the temporary dike. The spill never threatened navigable waterways, and | | subsequently was cleaned up within a 24 hour period. The initial | | notification was conservatively reported based on information known at the | | time of the event. | | | | "A minor spill of this nature is not reportable to the PADEP in accordance | | with 40CFR112 and the Preparedness Prevention Plan for Limerick Generating | | Station. This spill from a temporary tank had no impact on navigable | | waterways and was less than the Reportable Quantity (69 gallons)." | | | | The licensee will inform the NRC Resident Inspector. The NRC Operations | | Officer notified the R1DO (Noggle). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36930 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/26/2000| | UNIT: [] [] [3] STATE: AL |NOTIFICATION TIME: 03:23[EDT]| | RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/25/2000| +------------------------------------------------+EVENT TIME: 23:42[CDT]| | NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 04/26/2000| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 N N 0 Cold Shutdown |0 Cold Shutdown | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VARIOUS ESF ACTUATIONS DUE TO RPS BUS 3B DEENERGIZING AS A RESULT OF A | | FAILED RELAY | | | | "At 2342 CDT on 04/25/00, the RPS bus 3B deenergized causing PCIS Group 2 | | and Group 6 isolation valves to automatically close. A burnt relay was the | | initiating condition. Group 2 outboard drywell equipment drain valve and | | drywell floor drain valve closed. Group 6 drywell radiation monitor | | isolation valves closed. All other expected group isolations occurred along | | with the automatic starts of SBGT and CREV Systems. | | | | "Unit 3 is in Mode 5 with primary containment integrity not required. | | | | "This event is reportable under criteria 10CFR50.72.b.2.ii : Any event or | | condition that results in manual or automatic actuation of any engineered | | safety feature (ESF), including the reactor protection system (RPS)." | | | | RPS bus 3B was reenergized from its alternate power supply. Electricians | | are currently troubleshooting the cause of the failed relay. There was no | | electrical maintenance or testing ongoing at the time of the relay failure. | | | | The licensee informed the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 36931 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: DRESSER EQUIPMENT GROUP |NOTIFICATION DATE: 04/26/2000| |LICENSEE: DRESSER VALVE DIVISION |NOTIFICATION TIME: 14:40[EDT]| | CITY: BURLINGTON REGION: |EVENT DATE: 04/25/2000| | COUNTY: STATE: |EVENT TIME: 14:00[EST]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 04/26/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PAUL FREDRICKSON R2 | | |VERN HODGE NRR | +------------------------------------------------+ | | NRC NOTIFIED BY: L. H. WINDFIELD | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DRESSER VALVES NAME PLATE AND CODE PLATE HAVE INCORRECT SET PRESSURE | | INFORMATION AT HATCH. | | | | PART 21 FROM DRESSER EQUIPMENT GROUP, DRESSER VALVE DIVISION, BURLINGTON, | | ONTARIO, CANADA. | | | | | | The following noncompliance has been determined to be reportable within the | | requirements of 10CFR Part 21. The noncompliance involves seven safety | | relief valves that were purchased for the Hatch Electric Generating Plant by | | the Georgia Power Company through its agent, Southern Nuclear Operating | | Company, Inc. The valves are for use in a safely related service. | | | | The valves were purchased on Southern Nuclear Operating Company purchase | | order #6040304 and produced on Dresser Valve Division sales order #119588N | | and are further described as follows: | | | | Contract Item 002 Quantity 7 Part Number | | 3990C-1-S4-MS-33-SC-SC-GS produced ASME Section | | III Class 2 valves with the following serial numbers and | | required set pressures: | | | | SERIAL NO. SET PRESSURE REQD | | B119588-2-1 250 psig | | B119588-2-2 250 psig | | B119588-2-3 250 psig | | B119588-2-4 250 psig | | B119588-2-5 250 psig | | | | B119588-3-1 170 psig | | B119588-3-2 170 psig | | | | NONCOMPLIANCE SITUATION AND BRIEF HISTORY | | | | On Tuesday April 25, 2000, the customer was performing receiving inspection | | and noticed that the set pressure information on the Code Plates and the | | Name Plates do not conform to the specification requirements or the history | | docket testing information. The customer called the Quality Assurance | | Department of Dresser Valve Division to discuss the finding. It appears | | that the set pressure information on the plates has been interchanged. | | | | A summary of the information is as follows: | | | | SERIAL NO SET PRESSURE REQD CODE | | PLATE NAME PLATE | | B119588-2-1 250 psig | | 170 psig 170 psig | | B119588-2-2 250 psig | | 170 psig 170 psig | | B119588-2-3 250 psig | | 170 psig 170 psig | | B119588-2-4 250 psig | | 170 psig 170 psig | | B119588-2-5 250 psig | | 170 psig 170 psig | | | | B119588-3-1 170 psig | | 250 psig 250 psig | | B119588-3-2 170 psig | | 250 psig 250 psig | | | | Our investigation has begun and we have conducted a full review of our | | records to confirm that the valves are set correctly to the contract | | requirements. A notice has been given to the customer to return the | | affected valves to Dresser Valve Division for confirmation of the plate | | information and correction if required. The ANI will be involved in the | | investigation and corrective actions as required. | | | | We have conducted a full review of our records and confirmed that these are | | the only valves involved. A full review of our procedures regarding plate | | preparation, inspection and installation will be completed. Corrective | | actions will be initiated to address the internal issues, if warranted, and | | details will be provided in our closure reports at the completion of our | | investigation into the cause of this situation. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36932 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/26/2000| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 16:01[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 04/26/2000| +------------------------------------------------+EVENT TIME: 13:42[CDT]| | NRC NOTIFIED BY: DAVID LOHMAN |LAST UPDATE DATE: 04/26/2000| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JAMES CREED R3 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUXILIARY BUILDING SPECIAL VENTILATION AND CONTROL ROOM POST ACCIDENT | | RECIRCULATION ACTUATED DUE TO A STEAM EXCLUSION SIGNAL. | | | | At 1342 CDT on 04/26/00, the Auxiliary Building Special Ventilation and | | Control Room Post Accident Recirculation Systems actuated due to a steam | | exclusion signal. Auxiliary Building Special Ventilation and Control Room | | Post Accident Recirculation are Engineered Safety Features Systems. The | | steam exclusion signal was due to the rupture disk on Boric Acid Recovery | | System rupturing. Steam to the Boric Acid Recovery System was isolated. At | | 1425 CDT, steam exclusion was reset and the Auxiliary Building Special | | Ventilation and Control Room Post Accident Recirculation Systems were | | shutdown. All equipment operated as designed. There was no radiological | | release. The licensee is currently investigating why the rupture disc | | ruptured. Nobody was injured. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 36933 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: OFFICE OF EMERGENCY PREPAREDNESS |NOTIFICATION DATE: 04/26/2000| |LICENSEE: U.S. PUBLIC HEALTH SERVICE |NOTIFICATION TIME: 16:16[EDT]| | CITY: WINSTON-SALEM REGION: 2 |EVENT DATE: 04/06/2000| | COUNTY: STATE: NC |EVENT TIME: 12:00[EDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/26/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PAUL FREDRICKSON R2 | | |JAMES NOGGLE R1 | +------------------------------------------------+JOE HOLONICH NMSS | | NRC NOTIFIED BY: ROBERT CORNISH | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO CHEMICAL AGENT MONITORS EACH CONTAINING 15 MILLICURIES OF NICKEL-63 | | MISSING DURING SHIPMENT FROM WINSTON-SALEM, NC TO BALTIMORE, MD VIA FEDEX | | | | On March 29, 2000, two Chemical Agent Monitors, APD-2000, each containing 15 | | mCi of Nickel-63 were shipped by FEDEX from Winston-Salem, North Carolina | | to Environmental Technology Group, Baltimore, Maryland to be wiped tested. | | On April 06, 2000, U.S. Public Health Service was notified that the two | | Chemical Agent Monitors were missing. The U.S. Public Health Service and | | FEDEX are unable to located the missing monitors using the FEDEX tracking | | number. FEDEX is still trying to locate the missing monitors. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021