Event Notification Report for February 20, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/16/2001 - 02/20/2001
** EVENT NUMBERS **
37630 37694 37735 37749 37753 37754 37755 37756 37757 37758 37759 37760
37761 37762 37763 37764 37765 37766
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37630 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 12/22/2000|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 11:29[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 12/22/2000|
+------------------------------------------------+EVENT TIME: 09:45[CST]|
| NRC NOTIFIED BY: RICK HUBBARD |LAST UPDATE DATE: 02/19/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE TECHNICAL SUPPORT CENTER (TSC) |
| |
| Breaker 13-40 tripped with the ground flag dropped. This breaker supplies |
| primary power to the TSC. There is a backup diesel generator available to |
| supply power to the TSC but will not be energized until it is determined |
| that there is no ground at the TSC. Once the TSC D/G is energized the |
| facility will once again be available. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * Update at 1150 on 12/22/00 by Hubbard received by Weaver * * * |
| |
| The diesel generator is now supplying the TSC with electrical power (as of |
| 1041 CST). Investigation continues into why breaker 13-40 tripped. |
| |
| Notified the R4DO(Jones). |
| |
| * * * RETRACTED AT 1309 EST ON 2/19/01 BY CHRIS REEKIE TO FANGIE JONES * * |
| * |
| |
| The licensee is retracting this event. Upon review of the potential loss of |
| emergency communications and assessment capability they have determined that |
| no such loss would have happened with the initial problem. |
| |
| The licensee notified the NRC Resident Inspector. The R4DO (Greg Pick) has |
| been notified. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Hospital |Event Number: 37694 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: WAUSAU HOSPITAL |NOTIFICATION DATE: 01/26/2001|
|LICENSEE: WAUSAU HOSPITAL |NOTIFICATION TIME: 11:36[EST]|
| CITY: WAUSAU REGION: 3 |EVENT DATE: 01/24/2001|
| COUNTY: STATE: WI |EVENT TIME: 07:30[CST]|
|LICENSE#: 48-01032-01 AGREEMENT: N |LAST UPDATE DATE: 02/16/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JAMES CREED R3 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF LIMMER | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION |
| |
| A Cs-137 vaginal cylinder implant was loaded at 9:30 am on 1/23/01. The |
| written directive called for a total implant time of 49 hours. During a |
| check of the patient at 7:30 am on 1/24/01, the authorized user found the |
| loaded vaginal cylinder on the patient's toilet seat. The patient's nurse |
| stated that the source came out at about 6:30 am on 1/24/01 (i.e., after |
| about 42% of the prescribed dose was delivered). The licensee was not sure |
| how the source got to where it was found. The authorized user placed the |
| cylinder in a lead pig and transported it to the secured storage area. The |
| authorized user decided to write another written directive and reload the |
| patient at 10:00 am on 1/24/01 with a prescribed implant time of 7 hours. |
| After the 7 hours, the sources were explanted as intended. The authorized |
| user decided to deliver the remaining radiation dose to the treatment site |
| via teletherapy. |
| |
| At 6:00 am on 1/24/01, the nurse emptied the patient's foley bag and noted |
| that the patient was in bed. Between 6:00 and 6:30 am on 1/24/01, the nurse |
| noticed that the patient was leaving the bathroom to go back to bed. The |
| nurse also noticed that the patient's "T-binder" (used to hold the |
| applicator in place), was loose, so she tightened it. The authorized user |
| visited the patient at 7:30 am and noticed that the T-binder was on the |
| bathroom floor and the loaded vaginal cylinder was on the toilet seat. |
| Based on nurse interviews, all nurses caring for the patient were badged, |
| and none of them handled the applicator. |
| |
| ***** UPDATE/RETRACTION AT 1043 EST ON 02/16/01 FROM JEFF LIMMER TO LEIGH |
| TROCINE ***** |
| |
| An investigation was performed, and the NRC Region 3 office (Tony Go and |
| Geoffrey Wright) notified the license that there was patient intervention. |
| Therefore, the licensee is retracting this event. |
| |
| The NRC operations officer notified the R3DO (Monte Phillips) and NMSS EO |
| (Brian Smith). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37735 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STANDARD TESTING AND ENGINEERING CO |NOTIFICATION DATE: 02/11/2001|
|LICENSEE: STANDARD TESTING AND ENGINEERING CO |NOTIFICATION TIME: 19:11[EST]|
| CITY: DEL CITY REGION: 4 |EVENT DATE: 02/10/2001|
| COUNTY: STATE: OK |EVENT TIME: [CST]|
|LICENSE#: 35-17054-01 AGREEMENT: Y |LAST UPDATE DATE: 02/17/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |PHILIP TING NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HURST | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN TROXLER GAUGE |
| |
| A Troxler 3430 serial #16299 was stolen out of the back of an employee's |
| truck while it was parked at his house in Del City(a suburb of Oklahoma |
| City). The gauge, which contained 8 millicuries Cs-137 and 40 millicuries |
| Am-241/Br, was triple locked in the back of the truck. It was stolen on the |
| night of 2/10/01 or the morning of 2/11/01. The local police were notified. |
| Troxler was notified and they will notify the state. |
| |
| * * * UPDATE 1409 2/17/2001 FROM HURST TAKEN BY STRANSKY * * * |
| |
| The gauge was recovered earlier today. It was found intact in its case. The |
| licensee is currently performing a wipe test of the device to be sure that |
| there was no leakage. |
| |
| Notified R4DO(Pick). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37749 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 02/14/2001|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 17:05[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 02/14/2001|
+------------------------------------------------+EVENT TIME: 08:51[CST]|
| NRC NOTIFIED BY: BRUCE SCHOENBACH |LAST UPDATE DATE: 02/16/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GREG PICK R4 |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH TRAINS OF CONTAINMENT COOLERS AND ONE TRAIN OF CONTAINMENT SPRAY |
| INOPERABLE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 2/14/01, the 'A' train containment cooling train was removed from |
| service at 0507 CST for associated circuit breaker work. At 0851 CST the 'B' |
| Train Essential Service Water pump was started to support performance of the |
| 'A' Train SIS/CIS Slave Relay Test. |
| |
| "The 'B' Essential Service Water pump failed to achieve rated flow and |
| pressure and was declared inoperable at 0851 CST. This resulted in entry |
| into Technical Specification LCO 3.6.6, Required Action F.1 for both trains |
| of containment coolers inoperable and one train ('B') of Containment Spray |
| inoperable. LCO 3.6.6 Required Action F.1 also requires entry into LCO |
| 3.0.3. Technical Specification 3.0.3 was entered at 0851 CST and exited at |
| 1123 CST when the 'A' train of Containment Cooling was returned to service. |
| The plant remains in Technical Specification LCO 3.7.8 Required Action A.1 |
| (72-Hour Action Statement) for one train ('B') of Essential Service Water |
| inoperable. |
| |
| "This condition at the time of discovery could have prevented the |
| fulfillment of the safety function of structures or systems that are needed |
| to control the release of radioactive material or mitigate the consequences |
| for an accident. It was concluded that this event was reportable per |
| 10CFR50.72(b) (3) (v) since: |
| |
| (1) Both trains of containment cooling were lost as a result of the |
| unanticipated failure of the 'B' train Essential Service Water pump in |
| conjunction with the 'A' train containment coolers being removed from |
| service. |
| (2) Cascading through technical specification resulted in the loss of 'B' |
| train containment spray system. |
| |
| "The failure of the 'B' train Essential Service Water pump is under |
| evaluation." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| UPDATE 1706 2/15/2001 VIA FACSIMILE TO STRANSKY * * * |
| |
| "Upon investigation of the 'B' Essential Service Water pump problem, an |
| obstruction was found in the suction of the pump. The obstruction was |
| subsequently removed and the pump was then started to evaluate the |
| operability condition of 'B' Essential Service Water pump. The pump was |
| evaluated for normal flow, discharge pressure, and vibration. All parameters |
| were found within normal operating limits, the 'B' Essential Service Water |
| pump was declared Operable at 0231 on 2/15/O1 and Technical Specifications |
| 3.7.8.A.1 and 3.8.1.B were exited." |
| |
| Notified R4DO (Pick). |
| |
| *** UPDATE AT 0615 ON 02/16/01 - LEIGH TROCINE CALLED SITE (JOHN DAMPS) *** |
| |
| The obstruction was a 20-foot long piece of tygon tubing. It was reported |
| that the tubing had been hanging from a funnel near a hole in a pre-lube |
| tank for the pump's seals. Apparently, the tubing fell into a drain and |
| made its way to the pump suction. |
| |
| The licensee stated that the resident inspectors were aware of this |
| information. The NRC operations center notified the R4DO (Pick). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37753 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MARTIN MARIETTA ANDERSON CREEK QUAR |NOTIFICATION DATE: 02/16/2001|
|LICENSEE: UNKNOWN |NOTIFICATION TIME: 10:59[EST]|
| CITY: ROCKVILLE REGION: 2 |EVENT DATE: 02/15/2001|
| COUNTY: GOOCHLAND STATE: VA |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 02/16/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLIFFORD ANDERSON R1 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BENJAMIN BROWN | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TRANSPORT AND SUBSEQUENT DISCOVERY OF SCRAP METAL CONTAINING 50 MILLICURIES |
| OF CESIUM-137 (NRC GENERALLY LICENSED MATERIAL) AT MARTIN MARIETTA ANDERSON |
| CREEK QUARRY |
| |
| On 02/13/01, Martin Marietta Anderson Creek Quarry (located in Rockville, |
| Virginia, near Richmond) shipped scrap metal to Cycle Systems (a scrap yard |
| located in Lynchburg, Virginia). Cycle Systems surveyed the material and |
| discovered 50 millicuries of cesium-137. (The material was apparently a |
| sensor or level gauge from a conveyer system.) |
| |
| Cycle Systems notified the quarry and the State of Virginia. The State of |
| Virginia notified the NRC Region 2 office, and the NRC Region 2 office (Wade |
| Loo) contacted the quarry. |
| |
| The material was returned to the quarry on 02/15/01. The shutter is |
| currently locked closed, and the material has been placed in an office. |
| Martin Marietta Anderson Creek Quarry believes that the material may have |
| come from another quarry. The actual source of the material is currently |
| being investigated. |
| |
| (Call the NRC Operations Center for quarry contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37754 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 02/16/2001|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 14:47[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/16/2001|
+------------------------------------------------+EVENT TIME: 08:15[EST]|
| NRC NOTIFIED BY: GRANT FERNSLER |LAST UPDATE DATE: 02/16/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLIFFORD ANDERSON R1 |
|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 |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY REPORT |
| |
| A non-licensed employee tested positive for the use of illegal drugs during |
| a random test. The test results were confirmed positive by the licensee |
| Medical Review Officer. The individual's access to the plant has been |
| suspended in accordance with the licensee's FFD program. The NRC resident |
| inspector has been informed of this notification by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37755 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 02/16/2001|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 15:40[EST]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 02/16/2001|
+------------------------------------------------+EVENT TIME: 15:05[EST]|
| NRC NOTIFIED BY: JIM HICKEY |LAST UPDATE DATE: 02/16/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANNE BOLAND 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO RECEIPT OF CONTAMINATED ITEMS |
| |
| "While performing routine surveys, Turkey Point Health Physics personnel |
| discovered low levels of radioactivity on several plastic Caution signs |
| received from the Byron Nuclear Power Station. The signs were surveyed at |
| Turkey Point prior to use in the site's radiation controlled area. These |
| items were counted in a Small Articles Monitor (SAM) and indicated low level |
| contamination was present. In total, 6 out of approximately 650 items |
| surveyed indicated the presence of low level fixed activity. The highest |
| level measured was 7,000 disintegrations per minute (dpm) using a standard |
| HP-210 (pancake GM) probe. Isotopic analysis indicates cobalt-60 and |
| manganese-54. One item had low levels of loose surface contamination (57 |
| dpm/100 cm2). The items identified with low level fixed contamination are |
| now being held inside the Turkey Point radiation controlled area. The signs |
| were shipped in cardboard boxes and no loose surface contamination was found |
| on the exterior of the boxes |
| |
| "Florida Power & Light Company has notified the Byron Station and the State |
| of Florida (Department of Health, Bureau of Radiation Control) of this |
| matter." |
| |
| The licensee has informed the NRC resident inspector of this notification. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37756 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/16/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/15/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 23:20[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/16/2001|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MONTE PHILLIPS R3 |
| DOCKET: 0707002 |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALID ACTIVATION OF SAFETY SYSTEM |
| |
| "At 2320 hours on 02/15/01, both the 'A' and 'B' High Level Condensate |
| Alarms activated on Autoclave #2 in the X-343 Feed and Sampling Facility. |
| The activation of either of these alarms will cause the autoclave steam |
| supply valves ('Q' components) to actuate (close). The steam supply valves |
| closed, as designed, upon the activation of the High Condensate Alarms, |
| Autoclave #2 was in TSR Mode IV (FEEDING) at the time of the alarm |
| activations. Operations personnel immediately responded to the alarms in |
| accordance with the approved Alarm Response Procedures. Both alarms reset |
| when the operations personnel acknowledged the alarms at the local autoclave |
| control panel. All autoclave (and cylinder) operating parameters were |
| determined be to within normal ranges. Autoclave #2 was placed in TSR mode |
| VII (Shutdown) by operations personnel and declared Inoperable by the Plant |
| Shift Superintendent's Office. Based on the actuation of both High Level |
| Condensate alarms, this event is being reported as a valid safety system |
| actuation, a 24-hour NRC event." |
| |
| The NRC resident inspector has been informed of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37757 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 02/16/2001|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 19:41[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/16/2001|
+------------------------------------------------+EVENT TIME: 16:30[CST]|
| NRC NOTIFIED BY: MARTY McADORY |LAST UPDATE DATE: 02/16/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GREG PICK R4 |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY SYSTEM DECLARED INOPERABLE |
| |
| "During performance of 1C3 battery all-cell checks, battery cell #38 was |
| found to be >0.020 below the average for specific gravity. Tech Spec 3.8.6, |
| 'Battery Cell Parameters,' requires declaring 1C3 battery inoperable. This |
| caused entry into Tech Spec 3.8.4 Action D, which is to declare the High |
| Pressure Core Spray system inoperable. This requires entry into a 14 day |
| LCO. This event is reportable since High Pressure Core Spray is a single |
| train system." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37758 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/17/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:17[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/16/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:20[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/17/2001|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS R3 |
| DOCKET: 0707001 |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM WHITE | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2) SAFETY EQUIPMENT FAILUR| |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILED TO FUNCTION AS REQUIRED BY TECHNICAL SAFETY |
| REQUIREMENT |
| |
| "At 1020 on 02-16-01, the Plant Shift Superintendent (PSS) was notified of a |
| safety system failure in the C-315 building. While closing the cylinder |
| valve on a full liquid cylinder, the valve failed to close completely when a |
| shear pin broke on the emergency cylinder valve closure mechanism. At the |
| time of the failure the cylinder valve was still approximately one eighth of |
| a turn open. The operator manually closed the valve thus placing the |
| cylinder in a safe mode. The emergency cylinder valve closure mechanism is |
| part of the Low Voltage UF6 Release Detection and Isolation System at the |
| Withdrawal Stations, and is required to be operable according to TSR |
| 2.3.4.1. |
| |
| "This event is reportable under 10 CFR 76.120(c)(2) as an event in which |
| equipment required by the TSR is disabled or falls to function as designed. |
| |
| "The NRC Senior Resident has been notified of this event." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37759 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/17/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:49[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/16/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 21:37[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/17/2001|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MONTE PHILLIPS R3 |
| DOCKET: 0707002 |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALID ACTUATION OF SAFETY SYSTEM |
| |
| "At 2137 hours on 02/16/01, both the 'A' and 'B' High Level Condensate |
| Alarms activated on Autoclave #1 in the X-343 Feed and Sampling Facility. |
| The activation of either of these alarms will cause the autoclave steam |
| supply valves ('Q' components) to actuate (close). The steam supply valves |
| closed, as designed, upon the activation of the High Condensate Alarms. |
| Autoclave #1 was in TSR Mode II (HEATING) at the time of the alarm |
| activations. Operations personnel immediately responded to the alarms in |
| accordance with the approved Alarm Response Procedures. Both alarms reset |
| when the operations personnel acknowledged the alarms at the local autoclave |
| control panel. All autoclave (and cylinder) operating parameters were |
| determined be to within normal ranges, Autoclave #1 was placed in TSR mode |
| VII (Shutdown) by operations personnel and declared Inoperable by the Plant |
| Shift Superintendent's Office. Based on the actuation of both High Level |
| Condensate alarms, this event is being reported as a valid safety system |
| actuation, a 24-hour NRC event. An Engineering Evaluation has been requested |
| to investigate the circumstances surrounding this safety system actuation." |
| |
| The NRC resident inspector has been informed of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37760 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 02/19/2001|
| UNIT: [] [] [3] STATE: SC |NOTIFICATION TIME: 01:22[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 02/18/2001|
+------------------------------------------------+EVENT TIME: 21:00[EST]|
| NRC NOTIFIED BY: LOUIS NOWELL |LAST UPDATE DATE: 02/19/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANNE BOLAND R2 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP |NADER MAMISH IRO |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| INDICATION OF PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING VISUAL INSPECTION |
| OF REACTOR VESSEL HEAD |
| |
| "Event: Preliminary Reactor Vessel Head visual inspection indicates a small |
| amount of boron residue surrounding 6 Control Rod Drive mechanism head |
| penetrations. These indications are similar to those previously reported |
| during U-1 EOC-19 refueling outage. |
| |
| "Initial Safety Significance: Preliminary indication of leakage through |
| Reactor Coolant System Pressure Boundary. |
| |
| "Corrective Action(s): Additional inspections will be performed to |
| determine the cause of identified boron accumulation." |
| |
| Unit 3 is currently in mode 5 (Cold Shutdown) depressurized to atmosphere |
| with RCS temperature at 120 degrees F. The licensee is making preparations |
| to enter mode 6 (Refueling) in order to lift the RV Head. The licensee |
| informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37761 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 02/19/2001|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 03:00[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/18/2001|
+------------------------------------------------+EVENT TIME: 22:45[EST]|
| NRC NOTIFIED BY: VICTOR WALZ |LAST UPDATE DATE: 02/19/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLIFFORD ANDERSON R1 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|*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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) DECLARED INOPERABLE |
| |
| "During normal monitoring of the standby lineup of the High Pressure Coolant |
| Injection System (HPCI), the building rounds operator noticed that the HPCI |
| discharge flow switch (23FS-78) was indicating 140 gpm with zero actual |
| flow. This flow switch controls the operation of the HPCI pump minimum flow |
| valve during HPCI operations. Upon further investigation by the operating |
| crew, it was also determined that the HPCI pump discharge flow transmitter |
| was exhibiting sporadic flow spikes of 50 to 100 gpm with zero system flow. |
| This flow signal is used to control HPCI turbine speed and flowrate. Based |
| on these findings, the HPCI system was declared inoperable per Technical |
| Specification 3.5.c and a 7 day Limiting Condition for Operation was |
| entered." |
| |
| The licensee called in an engineering team to address this problem. The |
| licensee will inform the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37762 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 02/19/2001|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 13:04[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/19/2001|
+------------------------------------------------+EVENT TIME: 06:12[CST]|
| NRC NOTIFIED BY: BRAD MOORE |LAST UPDATE DATE: 02/19/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANNE BOLAND R2 |
|10 CFR SECTION: | |
|*COM 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF EMERGENCY COMMUNICATIONS TO THE STATE |
| |
| The licensee lost the emergency communications line to the states of Alabama |
| and Georgia at 0512 CST on 2/19/01 due to the failure of a communications |
| power inverter located offsite in Dothan, Alabama. The inverter was |
| restored at 0758 CST, restoring the emergency communications line. All |
| other communications were available during this time. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37763 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 02/19/2001|
|LICENSEE: QUALITY INSPECTION SERVICES, INC. |NOTIFICATION TIME: 13:47[EST]|
| CITY: JACKSONVILLE REGION: 2 |EVENT DATE: 02/16/2001|
| COUNTY: STATE: FL |EVENT TIME: 12:30[EST]|
|LICENSE#: 3043-1 AGREEMENT: Y |LAST UPDATE DATE: 02/19/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANNE BOLAND R2 |
| |E. WILLIAM BRACH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHARLES ADAMS | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT OF PERSONNEL OVEREXPOSURE |
| |
| The following is a portion of the information provided: |
| |
| "Approximately 12:30 am February 16 following a shoot, the source was reeled |
| into what was thought to be a locked position. A complete survey was not |
| done to confirm position of the source. The two individuals involved |
| proceeded in front of the camera to set up the next shot, taking less than 5 |
| minutes. When they went to unlock the source they realized that it was not |
| locked and noticed the survey meter was off scale. They exited the area and |
| fully retracted the source. Both pocket dosimeters were off scale. One rate |
| alarm meter was turned off and the other had a low battery and did not give |
| a audio alarm. Film badges showed 2.9 and 39.2 R exposure. The individual |
| with the high exposure has had blood drawn for analysis but no results are |
| available yet. Landauer has been asked recheck the film badge readings. The |
| wrong state office was notified 16 February. This office was notified 19 |
| February." |
| |
| The camera contains a 58 Ci source of Ir-192. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37764 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 02/19/2001|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 15:24[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/19/2001|
+------------------------------------------------+EVENT TIME: 12:00[EST]|
| NRC NOTIFIED BY: KENNETH RUSSELL |LAST UPDATE DATE: 02/19/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE OHIO EPA NOTIFIED OF AN UNINTENTIONAL DISCHARGE OF CONDENSER COOLING |
| WATER |
| |
| The Ohio EPA was notified of an unintentional bypass of the wastewater |
| treatment system as required by the NPDES Permit. No reportable quantities |
| were discharged. This was a non-radioactive effluent, main condenser |
| cooling water. |
| |
| The license intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37765 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 02/19/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 23:38[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 02/19/2001|
+------------------------------------------------+EVENT TIME: 20:30[CST]|
| NRC NOTIFIED BY: DUANE SCHMIDT |LAST UPDATE DATE: 02/19/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION FOR RESIDUAL HEAT REMOVAL CAPABILITY |
| |
| The licensee has determined that torus cooling initiation has not been |
| validated as part of operator actions to be initiated within 10 minutes of a |
| design basis accident in the containment. The licensee, as an interim |
| action, has added an extra licensed operator whose only responsibility is |
| the initiation of torus cooling at the direction of the emergency operating |
| procedures. Further analysis is being carried out for a final resolution. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37766 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 02/20/2001|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 01:56[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/19/2001|
+------------------------------------------------+EVENT TIME: 21:08[CST]|
| NRC NOTIFIED BY: JOHN MYERS |LAST UPDATE DATE: 02/20/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GREG PICK R4 |
|10 CFR SECTION: | |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |54 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN COMMENCED AFTER DECLARING BOTH STANDBY GAS |
| TREATMENT (SGT) TRAINS INOPERABLE |
| |
| "While performing Surveillance 6.SUMP.101, Z SUMP AND AIR EJECTOR HOLDUP |
| LINE DRAIN OPERABILITY TEST (IST), Z-1 sump pump exceeded its operability |
| time limit of 151 seconds by 3 seconds. When Z-2 sump pump was subsequently |
| tested, the pump failed to start on the essential HI-HI level switch. Both |
| sump pumps were declared INOPERABLE. These pumps support Standby Gas |
| Treatment OPERABILITY. The SGT line from the plant runs underground to the |
| Elevated Release Point tower, and the offgas line and SGT both enter this |
| sump. The pumps remove condensation from both the offgas lines and SGT, and |
| must be available post-accident to prevent flooding of the SGT lines. |
| |
| "Per administrative direction in the Surveillance procedure, both trains of |
| SGT were declared INOPERABLE at 2108. Per Technical Specification 3.6.4.3, |
| Condition D, with two SGT subsystems INOPERABLE in Mode 1, the Required |
| Action is to enter LCO 3.0.3 immediately. LCO 3.0.3 requires the plant to |
| be in Mode 2 within 7 hours, Mode 3 within 13 hours, and Mode 4 within 37 |
| hours. A power reduction was commenced at 2250. Present power level is |
| 54%. |
| |
| "Engineering personnel have responded to the plant and are evaluating the |
| two conditions." |
| |
| The above surveillance is performed quarterly. The licensee noted a past |
| history of problems with the system's level switches. The current rate of |
| power reduction is approximately 100 MW/hr or 12-15% reactor power. The |
| licensee informed the NRC resident inspector. |
| |
| * * * UPDATE 0441 2/20/01 FROM TERRY BORGAN TO S. SANDIN * * * |
| |
| Tech Spec required shutdown exited at 0334CST after engineering determined |
| that one train of SGT was OPERABLE. The Unit remains in a 7-day LCO for the |
| other INOPERABLE train. Notified R4DO(Pick). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021