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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+
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