Event Notification Report for January 26, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/25/2001 - 01/26/2001 ** EVENT NUMBERS ** 37680 37684 37685 37686 37687 37688 37689 37690 37691 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37680 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/23/2001| | UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 19:03[EST]| | RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/23/2001| +------------------------------------------------+EVENT TIME: 11:09[CST]| | NRC NOTIFIED BY: MIKE MacLENNAN |LAST UPDATE DATE: 01/25/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JAMES CREED R3 | |10 CFR SECTION: | | |*IND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTROL ROOM EMERGENCY VENTILATION SYSTEM DECLARED INOP ON LOW FLOW | | | | "On January 23, 2001, while performing the Control Room Emergency Filtration | | System (CREVS) monthly surveillance, the system flow was found to be 1741 | | SCFM [standard cubic feet per minute]. The required Technical Specification | | flow is 2000 SCFM +/- 10%. | | | | "The CREVS system was declared inoperable per Technical Specification 3.8.D | | and both Units entered a 7 day shutdown LCO. | | | | "This is being reported in accordance with 10CFR50.72(b)(3)(v)(D). | | | | "The initial flow measured was 1741 SCFM. Approximately 15 minutes later | | the flow was measured to be within Technical Specification limits. The | | station is continuing an evaluation of this issue." | | | | The licensee informed the NRC resident inspector. | | | | * * RETRACTION ON 01/25/01 AT 1107 ET BY D. NOHR TAKEN BY MACKINNON * * * | | | | The licensee has completed their evaluation and has determined that the | | CREVS was always capable of performing its intended function in response to | | a LOCA. Therefore the licensee is retracting this event. R2DO (Jim Creed) | | notified. | | | | The NRC Resident Inspector was notified of this retraction by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37684 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/25/2001| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 06:53[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 01/25/2001| +------------------------------------------------+EVENT TIME: 02:47[EST]| | NRC NOTIFIED BY: M ADRAMSKI |LAST UPDATE DATE: 01/25/2001| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |STEVEN DENNIS R1 | |10 CFR SECTION: | | |*INB 50.72(b)(3)(v)(B) POT RHR INOP | | |*IND 50.72(b)(3)(v)(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 | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE. | | | | At 0247 ET on 01/25/01, the flow transmitter controller for HPCI system | | spiked from zero to approximately 1500 gpm. The HPCI system was in standby | | lineup at the time. The flow indication has been slowly drifting down. | | | | A similar event occurred on 01/23/01 at 0725ET. HPCI was declared | | inoperable. The flow transmitter, 23FT-82, and flow switch, 23FS-78, were | | vented and a small amount of air was noted. The flow indication returned to | | zero (normal standby indication). After a HPCI operability surveillance | | test, HPCI was declared operable at 1332 ET on 01/24/01. | | | | After the second flow indication perturbation on 01/25/01, HPCI was again | | declared inoperable with an LCO start date of 01/23/01 at 0725 ET (7 days to | | returned HPCI to operable status). The cause of this condition is still | | under investigation. All other systems are operable. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37685 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: SKW-MBT SERVICES, INC. |NOTIFICATION DATE: 01/25/2001| |LICENSEE: SKW-MBT SERVICES, INC. |NOTIFICATION TIME: 09:48[EST]| | CITY: CLEVELAND REGION: 3 |EVENT DATE: 01/18/2001| | COUNTY: STATE: OH |EVENT TIME: 12:00[EST]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 01/25/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |JAMES CREED R3 | | |KERRY LANDIS R2 | +------------------------------------------------+STEVEN DENNIS R1 | | NRC NOTIFIED BY: ALICE MCFARLAND |VERN HODGE NRR | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE NONCONFORMANCE RELATED TO THE PERFORMANCE OF EMBECO 636 (CMTR) | | GROUT. | | | | SKW-MBT Management, Inc. supplied Embeco 636 (CMTR) Grout, as a nuclear | | safety-related product, to six customers since June 1999. This product may | | have been purchased through either ChemRex, Inc. or Master Builders, Inc; | | both of these companies are part of SKW-MBT Management Inc. | | | | "Recently, to ensure continued quality of the products that ChemRex and | | SKW-MBT provide, samples of our stock of Embeco 636( CMTR) Grout that were | | late in shelf life were submitted to re-analysis by our Quality Control (QC) | | Department. Based upon the results of the analysis of some of the samples, | | we want to inform you of a possible shelf life issue that may exist for | | specific lot(s) under certain conditions. During the course of preparation | | for application, Embeco 636 (CMTR) Grout, lot number M4-73733PO, if mixed to | | a fluid consistency may possibly segregate. | | | | "Based on our review and in accordance with the requirements and operating | | procedures of the SKW-MBT Quality Assurance Program, we are notifying | | nuclear facilities that have ordered Embeco 636 (CMTR) since June 1999 of | | this situation described above" | | | | | | Customers: Davis Besse Power Station, Peach Bottom Power Plant, Limerick | | Generating Station, Robinson Plant, Cook Nuclear Plant (both units), and | | Beaver Valley Power Station. | | | | (Call the NRC Operation Center for licensee contact information) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 37686 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: COGEMA MINING, INC. |NOTIFICATION DATE: 01/25/2001| |LICENSEE: COGEMA MINING, INC. |NOTIFICATION TIME: 13:23[EST]| | CITY: MILLS REGION: 4 |EVENT DATE: 01/24/2001| | COUNTY: NATRONA STATE: WY |EVENT TIME: 10:00[MST]| |LICENSE#: SUA-1341 AGREEMENT: N |LAST UPDATE DATE: 01/25/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |M. LAYTON/MINING XPT NMSS | | |DALE POWERS R4 | +------------------------------------------------+FRED BROWN, EO NMSS | | NRC NOTIFIED BY: JOHN VASELIN |JOE STAMBAUGH DOE | | HQ OPS OFFICER: LEIGH TROCINE |PINKNEY, NRC #554745 EPA | +------------------------------------------------+ROBERT CONLEY USDA | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NMIN MINING EVENT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GROUNDWATER RESTORATION SPILL INTO AN ONSITE DRY DRAW IN JOHNSON COUNTY, | | WYOMING (48-hour report in accordance with the license) | | | | The following text is a portion of a facsimile received from the licensee: | | | | "Reported Event - A groundwater restoration spill was discovered on | | 01-24-01, which was estimated at 13,392 gallons. License Section 12.4 | | states that the 'NRC staff considers any spill of 10,000 gallons or more to | | be significant from an operations standpoint, regardless of the chemical and | | radioactive characteristics of the spill.' Therefore, the NRC [Operations] | | Center is notified as instructed by this license section. Note that the | | Wyoming Department of Environmental Quality was also notified." | | | | "Spill Date, Time, and Gallons - January 23 (10:00 [MST]) to January 24, | | 2001 (10:00 [MST]), estimated at 13,392 gallons" | | | | "Spill Location - Irigaray Project, Unit 9, Well HP-63, NW, NW, S16, T45N, | | R77W, Johnson County, WY. The spill entered a dry draw where it was | | contained and didn't enter any surface water or leave the NRC permit area." | | | | "Spill Cause - The spill resulted from human error when the pump in | | restoration well LP-63 was inadvertently energized and allowed to pump | | groundwater onto the surface." | | | | "Spill Source and Analysis - The spill consisted of groundwater from a | | wellfield which had completed the final phase of restoration. The spill | | contained only 3.1 mg/I uranium as U." | | | | "Health or Environmental Hazards, and Corrective Actions - No recovery of | | the spill was conducted since the groundwater was from a wellfield which had | | completed the final phase of restoration and is considered clean. The | | nearest community is Linch, Wyoming, approximately 21 miles to the SSE. No | | health or environmental hazards are anticipated." | | | | "Written Notification - A written notification will be submitted to NRC Fuel | | Cycle Licensing Branch Chief within 7 days." | | | | The licensee stated that the water was considered to be clean and that this | | event was reported because of the quantity of water involved in the spill. | | The licensee also stated that drinking water standards for uranium content | | are 5 mg/l and the spill contained only 3.1 mg/I uranium as U. In addition, | | the licensee reported that a Wyoming Department of Environmental Quality | | representative was onsite when the spill occurred and that the State | | representative did not have any problem with the spill. | | | | It was determined that there was no adverse impact to the public or the | | environment. | | | | (Call the NRC Operations Center for licensee contact information.) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37687 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: US AIR FORCE |NOTIFICATION DATE: 01/25/2001| |LICENSEE: US AIR FORCE |NOTIFICATION TIME: 14:00[EST]| | CITY: HICKAM AFB REGION: 4 |EVENT DATE: 01/23/2001| | COUNTY: STATE: HI |EVENT TIME: 00:00[HST]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/25/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |DALE POWERS R4 | | |BRIAN SMITH NMSS | +------------------------------------------------+JOSEPH GIITTER IRO | | NRC NOTIFIED BY: PUGH | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NUCLEAR MATERIAL WAS DISCOVERED IN A TRASH TRUCK MAKING A DELIVERY TO A | | TRASH YARD | | | | A trash truck hauling trash from Hickam AFB to the Hawaii Electric Company's | | trash yard set off the portal monitor upon entry into the yard. The driver | | immediately returned to Hickam AFB where he had picked up the trash load. A | | Major from the Trippler Medical Center was dispatched to Hickam AFB and | | surveyed the material and determined that it was 1 millicurie of I-131 | | which could be a radiopharmaceutical. The truck was secured and surveyed | | and measured 18 mr/hr at the back truck surface and 1 mr/hr at one meter | | from the truck. It was determined that the material was picked up with a | | load of trash from the Billeting Office on Base and it appears was probably | | bodily excretions from an individual housed at the billets who recently had | | been treated with radiopharmaceuticals. There is no way to determine the | | individual or where the treatment was administered. The material will be | | transferred to the Trippler Medical Center where it will be held for 3 | | months for decay. | | | | ***** UPDATE AT 2112 ON 01/25/01 FROM ARTHUR MORTON TO LEIGH TROCINE ***** | | | | Arthur Morton of Trippler Army Medical Center called to NRC Operations | | Center to ask a question. The NRC operations officer notified R3DO (Creed) | | that the Army was also participating in corrective actions for this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37688 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 01/25/2001| | UNIT: [1] [] [] STATE: FL |NOTIFICATION TIME: 15:02[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 01/25/2001| +------------------------------------------------+EVENT TIME: 15:00[EST]| | NRC NOTIFIED BY: JIM TOTTON |LAST UPDATE DATE: 01/25/2001| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |KERRY LANDIS R2 | |10 CFR SECTION: | | |*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING A STRANDED SEA TURTLE | | | | The following text is a portion of a facsimile received from the licensee: | | | | "At 1500 on 01/25/01, notification of a sea turtle stranding was made to the | | Florida Fish and Wildlife Conservation Commission. [The sea] turtle has | | minor injuries and require[s] rehabilitation and transport to [the] Florida | | Fish and Wildlife Conservation Commission. Notification [to the NRC was] | | made due to notification of other government agencies." | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37689 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 01/25/2001| | UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 17:29[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/25/2001| +------------------------------------------------+EVENT TIME: 07:00[CST]| | NRC NOTIFIED BY: STEVEN SEWELL |LAST UPDATE DATE: 01/25/2001| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DALE POWERS R4 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |86 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS-FOR-DUTY REPORT REGARDING A CONTRACT SUPERVISOR WHO TESTED POSITIVE | | FOR ALCOHOL DURING A RANDOM TEST | | | | At 0700 CST on 01/25/01, the licensee received confirmatory results | | indicating that a contract employee supervisor tested positive for alcohol | | during a random test. The individual's access has been pulled, and a review | | of the individual's work has been performed. (Contact the NRC operations | | officer for additional details.) | | | | HOO NOTE: The licensee stated that the load reduction on Unit 1 (100% power | | to 86% power) was not related to this event notification. (Contact the NRC | | operations officer for additional details.) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37690 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 01/25/2001| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 20:10[EST]| | RXTYPE: [1] GE-3 |EVENT DATE: 01/25/2001| +------------------------------------------------+EVENT TIME: 16:53[CST]| | NRC NOTIFIED BY: STEVE CHRISTIAN |LAST UPDATE DATE: 01/25/2001| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JAMES CREED R3 | |10 CFR SECTION: | | |*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | |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 +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A SNUBBER ISSUE | | | | The following text is a portion of a facsimile received from the licensee: | | | | "A review of compliance with Plant Technical Specifications relative to | | safety-related snubber operability requirements has revealed that certain | | elements of the inservice inspection and testing program were not satisfied. | | The discovery and resultant evaluation has also determined that the 72-hour | | LCO applicable to snubbers has elapsed. An engineering evaluation to | | support an operability determination of these snubbers is in progress. In | | the interim the plant has defaulted to the most restrictive LCO associated | | with the subject equipment and has commenced an orderly shutdown." | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37691 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 01/25/2001| | UNIT: [] [4] [] STATE: FL |NOTIFICATION TIME: 21:03[EST]| | RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 01/25/2001| +------------------------------------------------+EVENT TIME: 19:51[EST]| | NRC NOTIFIED BY: THOMAS S. WACH |LAST UPDATE DATE: 01/25/2001| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |KERRY LANDIS R2 | |10 CFR SECTION: | | |*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |4 M/R Y 50 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO TWO DROPPED RODS IN DIFFERENT BANKS | | | | The following text is a portion of a facsimile received from the licensee: | | | | "While conducting a plant shutdown due to a dropped rod in shutdown bank 'B' | | (H-6), another rod in control bank 'D' (H-10) dropped. In accordance with | | [procedure] 4-ONOP-028.3, 'Dropped RCC,' with two dropped rods in different | | banks the reactor was manually tripped and [procedure] 4-EOP-E-0 was | | entered. All equipment operated as expected, and [the] plant is stable in | | Mode 3. [An] investigation is in progress to determine [the] reason for | | [the] dropped rods." | | | | The licensee stated that all rods fully inserted. Auxiliary feedwater | | automatically started as expected and has since been secured. Normal | | feedwater is currently being utilized to supply water to the steam | | generators, and the main condenser is available as the heat sink for | | secondary steam. Normal charging, makeup, and letdown are being utilized | | for primary system inventory control. Pressurizer heaters and sprays are | | being utilized for primary system pressure control, and the reactor coolant | | pumps are being utilized for primary system transport control. Offsite | | power is available. There were no emergency core cooling system actuations, | | and none were required. | | | | The licensee plans to notify the NRC resident inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021