Event Notification Report for June 14, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/13/2001 - 06/14/2001 ** EVENT NUMBERS ** 37933 38066 38067 38068 38069 38070 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37933 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/19/2001| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 17:24[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 04/19/2001| +------------------------------------------------+EVENT TIME: 14:40[CDT]| | NRC NOTIFIED BY: BRADLY MCMAHON |LAST UPDATE DATE: 06/13/2001| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |RONALD GARDNER R3 | |10 CFR SECTION: | | |AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 96 Power Operation |96 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DEGRADED APPENDIX "R" FIRE BARRIER | | | | While conducting a walk down inspection of 10CFR50 Appendix R Barriers, two | | degraded gypsum walls were identified. The two walls are intended to serve | | as three hour rated Appendix R barriers. The inspection of the walls | | revealed that a segment of the walls approximately 6 feet by 6 inches was | | not constructed as required. The two walls provide separation of safe | | shutdown equipment in the event of an Appendix R design basis fire. The | | walls separate the charging pumps, a dedicated shutdown system component, | | from the safety injection pumps which are alternate shutdown system | | equipment. | | | | Although the walls are not constructed as designed, they appear to be | | completed to about 75% of design and are judged capable of providing some | | protection. Nevertheless, the walls are declared inoperable and | | compensatory actions according to the Kewaunee Fire Plan have been | | initiated. The walls are declared inoperable due to not having any | | documented analysis to support the design basis rating. | | | | The licensee notified the NRC resident inspector. | | | | * * * UPDATE AT 1517 ON 6/13/01 BY HARRINGTON RECEIVED BY WEAVER * * * | | | | The licensee has retracted this event based upon further review. On 4/19/01 | | Kewaunee Nuclear Power Plant (KNPP) reported to NRC via the Event | | Notification System (ENS) an unanalyzed condition related to two Appendix R | | fire barriers. The report was made based on a cursory visual inspection of | | two barriers that appeared to be missing a portion of a layer of gypsum | | board. Based on what appeared to be less than the three required layers of | | gypsum board, a conservative assumption was made that the barriers did not | | meet design requirements. Since the ENS report was filed, the barriers were | | partially disassembled to gather data for-performing a fire hazards analysis | | of the apparently degraded barriers in accordance with Generic Letter 86-10. | | Disassembling the barriers revealed that what appeared to be a partially | | missing layer was in fact an additional partial layer of gypsum board. | | | | Based on the additional data gathered from disassembling the barriers, the | | barriers met design requirements for a three hour rated Appendix R fire | | barrier. Therefore, the barriers were not degraded and an unanalyzed | | condition never existed. Consequently, the reporting criteria for an | | unanalyzed condition was not exceeded and is the basis for retracting the | | ENS report notification made on 4/19/01. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 38066 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MT DEPARTMENT OF TRANSPORTATION |NOTIFICATION DATE: 06/13/2001| |LICENSEE: MT DEPARTMENT OF TRANSPORTATION |NOTIFICATION TIME: 10:02[EDT]| | CITY: GREAT FALLS REGION: 4 |EVENT DATE: 06/12/2001| | COUNTY: STATE: MT |EVENT TIME: 08:15[MDT]| |LICENSE#: 25-11498-01 AGREEMENT: N |LAST UPDATE DATE: 06/13/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |JOHN PELLET R4 | | |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: REX HOY | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED MOISTURE/DENSITY GAUGE | | | | A Troxler Model 3440 moisture/density gauge (s/n 25332), containing one 8 | | mCi Cs-137 and one 40 mCi Am-241/Be sources, was slightly damaged when it | | was struck by a roller. The area surrounding the gauge was immediately roped | | off until the gauge could be surveyed. The licensee stated that the sources | | were retracted at the time of the event and results of surveys and wipe | | tests were negative. The damage appears to be limited to a slight denting | | of the plastic cover. The licensee has visually inspected the sources but | | did not observe any damage. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38067 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/13/2001| | UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 10:57[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 05/12/2001| +------------------------------------------------+EVENT TIME: 16:53[EDT]| | NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 06/13/2001| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANIELLO DELLA GRECA R1 | |10 CFR SECTION: | | |AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 60 DAY OPTIONAL REPORT IN ACCORDANCE WITH 10 CFR 50.73(a)(1) | | | | "During performance of a loss of offsite power test with a LOCA, an | | automatic start of the A and B emergency diesel generators, the A and B core | | spray systems, and the A, B, C and D low pressure coolant injection pumps | | occurred. All actuations were complete and functioned as designed. The | | start was inadvertent and occurred when a 125 VDC knife blade was closed. | | The switch was installed as part of the procedure and was wired incorrectly | | such that when it was closed it caused an inadvertent LOCA signal to the | | affected systems." | | | | The NRC resident inspector has been informed of this notification by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38068 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 06/13/2001| | UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 11:21[EDT]| | RXTYPE: [2] GE-4 |EVENT DATE: 06/13/2001| +------------------------------------------------+EVENT TIME: 05:30[EDT]| | NRC NOTIFIED BY: HARRY B. GILES |LAST UPDATE DATE: 06/13/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 | |10 CFR SECTION: |ANNE BOLAND R2 | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |JOHN HICKEY NMSS | | |JOHN TAPPERT NRR | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TRANSPORTATION REPORT INVOLVING RAD WASTE SHIPMENT FROM FERMI TO BARNWELL, | | SOUTH CAROLINA | | | | "Event notification resulting from an offsite notification of a | | transportation accident involving a radioactive waste shipment from Fermi 2 | | to Barnwell, South Carolina. NRC reportable under 10CFR50.72(b)(2)(xi) any | | event or situation for which notification to other government agencies has | | been made. | | | | "At approximately 0530 hours on 06-13-2001, a Hittman Transport vehicle | | transporting Class 'A' radioactive waste material [proper shipping name: | | Radioactive Material, Low Specific Activity, n.o.s. 7, UN2912, Fissile | | Excepted, Compacted Dry Active Waste] from Enrico Fermi 2 facility to | | Barnwell, SC was involved in a vehicle accident west of Columbia, South | | Carolina. | | | | "Hittman Transport notified the South Carolina Department of Health and | | Environmental Control at approximately 0805 hours on 06-13-2001 concerning | | the transportation accident. Hittman Transport also notified Fermi 2 at | | approximately 0810 hours on 06-13-2001 of the vehicle accident. | | | | "The transportation accident was related to rain storm activity in the area | | and the driver of a passenger vehicle, responsible for the accident, | | received a traffic citation for speed too fast for conditions. The tractor | | suffered minor damage, but once released by the South Carolina State Police | | was able to be driven approximately 6 miles to a repair facility. No damage | | was noted to the trailer, shipping cask, or cask tie down equipment at the | | accident scene | | | | "At the repair facility, a mechanic evaluated the tractor condition and | | cleared the tractor and trailer for continued service to the Chem Nuclear | | Consolidation Facility in Barnwell, SC. The driver of the tractor performed | | a dose rate survey of the trailer and the dose rates were unchanged from the | | measured values at the Fermi site. | | | | "Fermi 2 does not intend to submit a press release in Michigan since the | | accident occurred in South Carolina and the proper South Carolina agencies | | were notified. | | | | "A follow up report is not anticipated, since no damage to the waste | | shipping cask was noted at the repair facility." | | | | The licensee informed the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38069 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 06/13/2001| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 12:31[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 06/13/2001| +------------------------------------------------+EVENT TIME: 08:39[CDT]| | NRC NOTIFIED BY: BRETT WELLER |LAST UPDATE DATE: 06/13/2001| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 | |10 CFR SECTION: | | |ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PARTIAL LOSS OFFSITE COMMUNICATIONS | | | | On Wednesday, June 13th at 0839, a lightning strike caused a loss of the | | commercial phone systems at the Monticello Nuclear Plant Site. This | | affected phones in the control room and Technical Support Center as well as | | plant paging capabilities. One commercial phone line in the control room, | | the ENS system, auto-ring hotlines to the State EOC/Duty Officer, fax | | capabilities and the Radio System to Off-site agencies remained operational. | | Notification to the State and Local Counties were made informing them of the | | degraded communication capabilities. The EOF phone system remained | | operational. All communication systems were restored at approximately 1100 | | on June 13th. | | | | The licensee informed the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38070 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/13/2001| | UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 20:12[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 06/13/2001| +------------------------------------------------+EVENT TIME: 19:30[EDT]| | NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 06/13/2001| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANIELLO DELLA GRECA R1 | |10 CFR SECTION: |JOHN HICKEY NMSS | |KSNM 70.52(a) LOSS OF SNM/CRIT |DAVID MATTHEWS NRR | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A SMALL QUANTITY OF SPECIAL NUCLEAR MATERIAL UNACCOUNTED FOR | | | | During the process of investigation of the Transverse In-Core Probe (TIP) | | detector accountability issue reported on 6/8/01 (EN 38059) it has been | | discovered that one additional detector cannot be readily accounted for. | | This was discovered during verification of the detectors installed in the | | TIP machines. The TIP detector is a fission chamber that utilizes | | approximately 1 mg of enriched uranium and is therefore considered Special | | Nuclear Material (SNM). | | | | During 1975 to 1986 Pilgrim did not track TIP detectors as SNM due to the | | detectors containing less than one gram of SNM. It is suspected that during | | this time frame this detector was changed out. In 1987 a records search was | | made but did not reveal maintenance performed on this detector. It Is | | believed that this TIP detector has been properly disposed of as radioactive | | waste and is not in the public domain. Investigation is continuing. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021