Event Notification Report for September 18, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/15/2000 - 09/18/2000
** EVENT NUMBERS **
37254 37324 37325 37326 37327 37328 37329 37330 37331 37332 37333 37334
37335 37336 37337 37338
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37254 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 08/24/2000|
| UNIT: [1] [2] [] STATE: NJ |NOTIFICATION TIME: 21:22[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/24/2000|
+------------------------------------------------+EVENT TIME: 20:30[EDT]|
| NRC NOTIFIED BY: VAN FORD |LAST UPDATE DATE: 09/15/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRISTOPHER CAHILL R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 VENTILATION NOT ALIGNED PROPERLY FOR TOXIC CHEMICAL DELIVERY |
| |
| The licensee reported that they were potentially outside of design license |
| basis for the receipt of hazardous/toxic chemicals, specifically ammonium |
| hydroxide 15 % by weight. A delivery truck arrived at the site and was |
| admitted to the protected area before the proper alignment was made for |
| receipt. The control room was contacted, but the alignment of control room |
| ventilation was not completed prior to admitting the truck. The control |
| room ventilation has been placed in full recirculation for chemical receipt |
| at this time. The total time ventilation was not properly aligned is not |
| available at this time. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * UPDATE AT 2345 EDT ON 8/24/00 BY VAN FORD TO FANGIE JONES * * * |
| |
| The licensee reported there were no spills or discharges during the |
| offloading process and there was no risk to onsite or offsite personnel at |
| any time. The chemical unloading procedure contains all requirements for |
| personal protective equipment and appropriate precautions. The chemistry |
| department procedure for chemical delivery may be in conflict with Salem |
| UFSAR requirements (Section 2.2.3.3), Hazardous Chemicals - Offsite. |
| Station personnel are evaluating the issue. |
| |
| The licensee intends to notify the NRC Resident Inspector. The NRC |
| Operations Officer notified the R1DO (Christopher Cahill). |
| |
| * * * RETRACTION AT 1412 ET ON 09/15/00 BY FRANK SOENS TO JOHN MACKINNON * * |
| * |
| |
| An assessment of the consequences of a postulated failure of the ammonia |
| tanker with the control room ventilation system being in its normal mode of |
| operation results in a maximum Salem control room concentration of |
| approximately 2.11 ppm which is less than the 100 ppm limit of Reg Guide |
| 1.78. Salem was within the design basis for the given situation, therefore, |
| this event is being retracted. R1DO (Jim Trapp) notified. |
| |
| The NRC Resident Inspector was notified of this event retraction by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37324 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 09/15/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 01:40[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/14/2000|
+------------------------------------------------+EVENT TIME: 23:33[EDT]|
| NRC NOTIFIED BY: KERRY ALLEN |LAST UPDATE DATE: 09/15/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION LOGIC RELAY COIL FAILED CAUSING SOME |
| ISOLATIONS |
| |
| The primary containment isolation logic relay 16A-K61 coil apparently burned |
| out causing the relay to de-energize. This caused valves 20 MOV-94 (DW |
| equipment sump pump inboard isolation), 20 MOV-82 (DW floor sump pump |
| inboard isolation), and 10 MOV-18 (RHR shutdown cooling inboard isolation) |
| to receive a close signal. 20 MOV-94 and -82 went closed while 10 MOV-18 was |
| already closed. The drywell sumps can not be pumped down. This places the |
| plant in the coolant leakage monitoring per technical specification 3.6.d |
| which allows 24 hours for repair of the problem. The problem is being |
| worked on and investigated and it is expected to be completed within the 24 |
| hour limit. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37325 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 09/15/2000|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 10:27[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/15/2000|
+------------------------------------------------+EVENT TIME: 06:30[CDT]|
| NRC NOTIFIED BY: DAVID HANKS |LAST UPDATE DATE: 09/15/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SANBORN R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO ELECTRICAL GRID DISTURBANCE |
| |
| A Baxter Wilson Station 500 kV breaker opened inducing a grid disturbance |
| that caused a reactor scram for an unknown reason. The breaker opening |
| cause a loss of one offsite source. The disturbance also was picked up as |
| an undervoltage on bus 15, which caused the division 3 (high pressure core |
| spray) diesel generator to start. The bus 16, which is fed from the same |
| engineered safeguards features transformer, did not pick up the undervoltage |
| condition. The reactor core isolation cooling system started and injected. |
| The licensee is investigating the actual cause of the reactor scram. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 37326 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: KANSAS CITY RESEARCH MEDICAL CENTER |NOTIFICATION DATE: 09/15/2000|
|LICENSEE: KANSAS CITY RESEARCH MEDICAL CENTER |NOTIFICATION TIME: 10:36[EDT]|
| CITY: KANSAS CITY REGION: 3 |EVENT DATE: 08/30/2000|
| COUNTY: STATE: MO |EVENT TIME: [CDT]|
|LICENSE#: 2418625-01 AGREEMENT: N |LAST UPDATE DATE: 09/15/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MIKE JORDAN R3 |
| |FREDRICK STURTZ NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EDMUND CYTACKI | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF ONE I-125 SEED, 0.55 mCi |
| |
| The licensee discovered 1 of 65 iodine-125 seeds missing when installing |
| them in an applicator for a permanent implant on 8/17/00. Multiple surveys |
| failed to find the seed if present in the shipment. The shipment was |
| received on 8/15/00 and surveyed, but not opened until the applicator was |
| ready to be loaded. The licensee contacted the manufacturer, Uramed |
| Company, of Norwood, MA about the missing seed. The manufacturer could not |
| determine that they had not sent 65 seeds. The seed is considered lost, |
| probably in the hot lab of the hospital, and the licensee does not consider |
| it to be a serious health risk. |
| |
| A written report will be submitted to the NRC. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37327 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 09/15/2000|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 10:38[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 09/14/2000|
+------------------------------------------------+EVENT TIME: 18:30[EDT]|
| NRC NOTIFIED BY: BRIAN TAYLOR |LAST UPDATE DATE: 09/15/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEPHEN CAHILL R2 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| ERROR IDENTIFIED IN LOCA MODEL THAT COULD RESULT IN PEAK CLAD TEMPERATURE > |
| 2200�F |
| |
| "At 1830 hours on September 14, 2000, a condition potentially outside the |
| design basis of the facility was identified at CR-3. This event notification |
| is being made as required by 10 CFR 50.46 for an error identified in the |
| Evaluation Model for CR-3 which may result in peak clad temperature in |
| excess of 2200�F. This notification is being made while the unit is shutdown |
| prior to entry into MODE 2 following a recent maintenance outage. |
| |
| "The condition is that, in the event of a small break loss of coolant |
| accident involving the core flood line at CR-3, it may be necessary to shut |
| down the CR-3 reactor coolant pumps within 1 minute of loss of subcooling |
| margin in order to limit peak cladding temperatures to less than 2200 |
| degrees Fahrenheit (the 10 CFR 50.46 limit for peak cladding temperatures). |
| The current licensing/design basis analysis assumes that the pumps are shut |
| down within 2 minutes of loss of subcooling margin. |
| |
| "Existing procedural guidance in Emergency Operating Procedure requires |
| turning off the reactor coolant pumps as an immediate manual action in |
| response to loss of subcooling margin. Operator actions to trip the reactor |
| coolant pumps are routinely monitored in training. Thc action to turn off |
| the reactor coolant pumps upon loss of subcooling margin is routinely |
| completed within 1 minute in plant simulator accident training unannounced |
| casualty scenarios. |
| |
| "Plant personnel for CR-3 have determined that, based upon the existing |
| procedural guidance and simulator training experience, there is reasonable |
| expectation that procedurally directed operator actions will successfully |
| shut down the reactor coolant pumps within 1 minute of loss of subcooling |
| margin and therefore, the peak cladding temperature will remain unchanged |
| and below the 2200 degrees Fahrenheit limit of 10 CFR 50.46. Thus, the CR-3 |
| emergency core cooling systems continue to be operable because, based upon |
| engineering judgement, the systems are capable of performing their intended |
| safety function. |
| |
| "This determination that a condition potentially outside the design basis of |
| the plant will be followed with more detailed evaluation and analysis of the |
| issue. It is possible that the-follow-up analysis-will provide technical |
| justification which demonstrates that CR-3 remains within the existing |
| design basis. |
| |
| "CR-3 is reporting this prior to placing the plant in operation. This report |
| is being made under 10 CFR 50.72(b)(1)(ii)(B) as 'Any event or condition |
| during operation that results in a condition that is outside the design |
| basis of the plant.' CR-3 is currently in a shutdown condition in the |
| process of performing a plant start-up. Therefore, the one-hour criteria of |
| this reporting requirement is not in effect. |
| |
| "At its most fundamental level, PSC 2-00 identifies an analytical issue that |
| requires resolution. A telecon with NRC technical staff held on 9/13/2000 |
| identified the analytical issue as one that is principally concerned with an |
| ECCS evaluation model assumption. The safety significance was alleviated by |
| discussions on consistent, demonstrated performance of immediate operator |
| action to trip the RCPs well within 1 minute, with no challenge to the |
| preliminary (conservative) accident analysis. Additionally, discussions were |
| also presented on the relative probability of this specific scenario. The |
| combination of the break with the specific failure represents a very small |
| probability (<E-10), which helps diminish the safety significance of this |
| scenario. |
| |
| "CR3 is proceeding with an approach that conservatively addresses Mode 2 |
| restraint because decay heat power is low at this time since the reactor is |
| shutdown and will not increase significantly until further power operation |
| is commenced." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37328 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 09/15/2000|
|LICENSEE: WASHINGTON STATE UNIVERSITY |NOTIFICATION TIME: 15:38[EDT]|
| CITY: PULLMAN REGION: 4 |EVENT DATE: 09/01/2000|
| COUNTY: STATE: WA |EVENT TIME: [PDT]|
|LICENSE#: WA-C003-1 AGREEMENT: Y |LAST UPDATE DATE: 09/15/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TERRY FRAZEE | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LEAKING SOURCE, SODIUM-22, DISCOVERED DURING LEAK TEST. |
| |
| THE FOLLOWING EVENT WAS EVENT WAS E-MAILED TO THE HEADQUARTERS OPERATION |
| CENTER |
| |
| Washington State University located in Pullman, WA Radiation Safety Officer |
| performed a leak test on a 1.5 millicurie sodium-22 source that was planned |
| to be transferred from one authorized user to another. The source was found |
| to be leaking and will be disposed. Surveys of the storage area and work |
| area were done and decontamination performed on the remote handling tools. |
| The source is one of four custom made by a researcher at Brookhaven National |
| Lab in June 1996 and transferred to Washington State University (WSU) when |
| the researcher moved to WSU. Of the four sources, one was found to be |
| leaking and disposed of several years ago, one is still at WSU, and the last |
| was transferred to another academic institution (WSU has notified the |
| recipient of this event). |
| |
| Leak test? 0.027 microcuries of removable contamination detected. |
| |
| Activity and isotope involved: 1.5 millicuries of Na-22 as of June 1996. |
| |
| Washington State event report: WA-00-044. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37329 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 09/15/2000|
|LICENSEE: AGILENT TECHNOLOGIES, INC. |NOTIFICATION TIME: 17:04[EDT]|
| CITY: NEWARK REGION: 4 |EVENT DATE: 08/15/2000|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 09/15/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KENT PRENDERGAST | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 187 MICROCURIE PROMETHIUM-147 SOURCE LOST |
| |
| Promethium-147 is held under a General License. State of California event # |
| CA-09-15-00 |
| |
| Agilent Technologies, Inc. located in Newark, CA was preparing to ship a 187 |
| microcurie Promethium-147 source back to Hewlett Packard located in San |
| Jose, CA. The source was taken out of its container and placed on a desk |
| in a cubicle located in an Agilent Technology, Inc. building. When the |
| person came back to get the source it was missing. Employees in the area |
| were asked if they had seen or taken the small source and a survey of the |
| area was performed to find the source. The source was not found. The |
| original activity of the source, November 1994, was 900 microcuries. The |
| half life of Promethium-147 is 2.62 years. The missing Promethium-147 was |
| used in a Betascope which is used to measure the thickness of silicon |
| wafers. |
| |
| Agilent Technologies, Inc. notified the State of California regarding the |
| missing source on 08/17/00 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37330 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/15/2000|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 17:57[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/15/2000|
+------------------------------------------------+EVENT TIME: 15:05[EDT]|
| NRC NOTIFIED BY: JESSE JAMES |LAST UPDATE DATE: 09/15/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 M/R Y 15 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUALLY SCRAMMED THE REACTOR AFTER ENTERING THE RESTRICTIVE AREA OF THE |
| POWER TO FLOW MAP. |
| |
| On September 15, 2000 at Peach Bottom Atomic Power Station, Unit 2 was |
| manually scrammed per operating procedure during turbine testing in |
| preparation for the refuel outage. |
| |
| The manual scram was due to entering restricted area of the power to flow |
| map from Technical Specification 3.4.1, after the trip of the "2B" |
| recirculation pump. All rods fully inserted and the reactor was shutdown. |
| Reactor level during the scram lowered to 0" and a Group II and III primary |
| and secondary containment isolation was received. The isolations functioned |
| as designed. The plant is stable in hot shutdown with the main condenser as |
| a heat sink and the feedwater system is in service for level control. No |
| radioactive release or Emergency Core Cooling System injection occurred |
| during the scram. |
| |
| The turbine was tripped in accordance with the refuel outage plan when the |
| recirculation pump tripped. The plan was to perform turbine testing and |
| then to manually scram the reactor at the same power level. |
| |
| The reactor was manually scrammed less than one minute after entering the |
| restricted area of the power to flow map. No power oscillations were seen. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37331 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 09/15/2000|
|LICENSEE: TRANSALTA CENTRALIA MINING LLC |NOTIFICATION TIME: 19:32[EDT]|
| CITY: CENTRALIA REGION: 4 |EVENT DATE: 09/13/2000|
| COUNTY: STATE: WA |EVENT TIME: [PDT]|
|LICENSE#: WN-I0241-1 AGREEMENT: Y |LAST UPDATE DATE: 09/15/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TERRY FRAZEE | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MECHANICAL FAILURE OF A RONAN MODEL SA-4 GAUGING DEVICE |
| |
| THE FOLLOWING EVENT WAS E-MAILED TO THE HEADQUARTERS OPERATION CENTER |
| |
| Transalta Centralia Mining LLC notified the WA Department of Health, |
| Division of Radiation Protection, of a mechanical failure involving a Ronan |
| Engineering Company Model SA-4 gauging device. The device is specifically |
| licensed for density process measurements and uses a Cesium-137 sealed |
| source, Amersham Model CDC.711M not to exceed 74 gigabecquerels (2 curies). |
| The source is normally mounted at the end of a source rod and secured by |
| pins. When not in operation, the rod with source can be withdrawn into a |
| safe position inside the shielding device. When operating, the rod with |
| source is inserted into the process area through a dry well. An authorized |
| user realized that a problem existed when attempting to return the source to |
| the safe position. Apparently the rod did not have normal feel when it was |
| withdrawn. The licensee's RSO and their health physics consultant surveyed |
| the area and stated there wasn't a dose rate problem since the process |
| mixture was still providing ample shielding. The mixture will remain |
| in-place until the source can be returned to the device's normal shielded |
| position. The area adjacent to the dry-well access point has been marked as |
| a restricted area. |
| |
| Preliminary indications are the source has separated from the source rod and |
| fallen to the bottom of the insertion well. The consultant indicated that |
| this type Ronan device (but not this particular device) has suffered similar |
| failures in the past. |
| |
| The consultant has contacted Ronan Engineering requesting they send |
| procedures and special equipment. The recovery operation is anticipated to |
| take place on September 18. The Department of Health, Division of Radiation |
| Protection will be on-site during the recovery operation. |
| |
| Type of License: Fixed Gauge |
| |
| Washington Event Report: WA-00-046. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37332 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 09/15/2000|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 23:47[EDT]|
| RXTYPE: [1] CE |EVENT DATE: 09/15/2000|
+------------------------------------------------+EVENT TIME: 23:25[EDT]|
| NRC NOTIFIED BY: M MLYNARBK |LAST UPDATE DATE: 09/16/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |MARK RING R3 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|AAEC |FRANK CONGEL IRO |
| |DAN SULLIVAN FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - UNIDENTIFIED LEAKAGE GREATER THAN 1GPM |
| |
| The plant is in hot shutdown making preparations for startup. Reactor |
| coolant is back leaking from loop "1A" through two check valves into a |
| safety injection tank. The safety injection tank is approximately 95% full. |
| If the tank should over pressurize the relief valve will relieve to the |
| containment. The primary containment integrity is set. The maximum leak |
| rate observed was 1.64 GPM. The licensee has taken steps to seat the check |
| valves and is now measuring the leak rate again. The unusual event was |
| declared at 2325. |
| |
| The licensee notified the NRC resident inspector, the state and Van Buren |
| county. |
| |
| * * * UPDATE AT 0145 ON 9/16/00 BY SLEEPER, RECEIVED BY WEAVER * * * |
| |
| The licensee terminated the unusual event at 0121. Unidentified leakage has |
| returned to its normal value of less than 1 GPM. The licensee will notify |
| the NRC resident inspector. The Operations center notified the RDO (RING); |
| NRR EO (ZWOLINSKI); IRO (CONGEL) and FEMA (CEGIELSKI). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37333 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 09/16/2000|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 23:43[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 09/16/2000|
+------------------------------------------------+EVENT TIME: 23:15[EDT]|
| NRC NOTIFIED BY: LEON GAGNE |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |STEPHEN CAHILL R2 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|AAEC |FRANK CONGEL IRO |
| |AUSTIN FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - HURRICANE WARNING |
| |
| The licensee declared an unusual event at 2315 due to a hurricane warning |
| being declared for Citrus County, Florida. Further actions will be taken |
| depending upon the direction Hurricane Gordon takes in the next 24 hours. |
| The licensee intends to remain at power and will continue to evaluate this |
| storm. |
| |
| The licensee notified both state and local governments of the declaration as |
| well as the NRC resident inspector. |
| |
| * * * UPDATE AT 0049 ON 9/18/00 BY GAGNEY, RECEIVED BY WEAVER * * * |
| |
| The licensee exited the unusual event at 0035. The hurricane warning is no |
| longer in effect. The storm caused no damage at the plant and it continues |
| to operate at full power. |
| |
| The licensee notified both state and local governments of the declaration as |
| well as the NRC resident inspector. |
| |
| HOO notified FEMA (CIBOCH); RDO (CAHILL); EO (ZWOLINSKI); IRO(CONGEL) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37334 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 09/17/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 11:03[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/17/2000|
+------------------------------------------------+EVENT TIME: 08:09[EDT]|
| NRC NOTIFIED BY: WILLIAM DUNN |LAST UPDATE DATE: 09/17/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEPHEN CAHILL R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Standby |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BRIEF ENTRY INTO TECHNICAL SPECIFICATION 3.0.3 |
| |
| "During attempts to restore Train 'A' Safety Injection (SI) system following |
| planned testing, the Train 'B' SI system was rendered inoperable for 1 |
| minute requiring entry in TS 3.0.3. The high and low head injection systems |
| were operable. |
| |
| "Train 'A' SI was inoperable due to planned RCS pressure isolation valve |
| inservice testing. During the Train 'A' SI testing, valve 1HV-8802A (SI-PMP |
| A TO HOT LEG 1&4 ISO VLV) had to be manually closed. In order to return |
| Train 'A' SI to service, 1HV-8802A would have to be manually unseated and |
| then electrically stroked. The Train 'A' SI pump was placed in PTL |
| [pull-to-lock] to ensure that the SI pump would not run out should the SI |
| pump auto start. The control room staff, however did not recognize the |
| impact on Train 'B' SI, during stroke of 1HV-8802A with the SIP TO COLD LEG |
| isolation valves (1HV-8821 A&B) open. In this configuration, the potential |
| existed to run out the Train 'B' SI pump should the pump auto start. The |
| control staff within a few minutes of stroking 1 HV-8802A recognized the |
| entry into TS 3.0.3." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37335 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/17/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 16:33[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/17/2000|
+------------------------------------------------+EVENT TIME: 15:20[EDT]|
| NRC NOTIFIED BY: GREGG R. PITTS |LAST UPDATE DATE: 09/17/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 70 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNEXPECTED MAIN TURBINE TRIP CAUSED AN AUTOMATIC REACTOR SCRAM. |
| |
| During power ascension following a planned outage, Nine Mile Point Unit 2 |
| automatically scrammed from approximately 70% reactor power. The scram |
| signal was generated when the Main Turbine tripped. The cause of the |
| Turbine Trip is being investigated. All control rods fully inserted. |
| Reactor pressure is stable and being controlled through Turbine Bypass |
| Valves to the Main Condenser. One additional scram signal was received on |
| low Reactor Vessel Water Level during level recovery efforts. Reactor level |
| control is stable and being fed from the condensate/feedwater system. All |
| Emergency Core Cooling Systems are operable and in standby. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37336 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 09/17/2000|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 17:45[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/17/2000|
+------------------------------------------------+EVENT TIME: 06:46[CDT]|
| NRC NOTIFIED BY: RANDY MAU |LAST UPDATE DATE: 09/17/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK RING R3 |
|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
+------------------------------------------------------------------------------+
| A licensee employee in the protected area was found with a metal flask |
| containing a small amount of alcohol, approximately one teaspoon or less. |
| It was later determined that the individual was unaware that the flask was |
| in his coat pocket. The individual was escorted offsite. A behavior |
| observation was performed, and the individual was allowed to return to work. |
| |
| |
| The NRC Resident will be notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37337 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION DATE: 09/17/2000|
|LICENSEE: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION TIME: 19:07[EDT]|
| CITY: IDAHO FALLS REGION: 4 |EVENT DATE: 09/17/2000|
| COUNTY: STATE: ID |EVENT TIME: 16:47[MDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 09/17/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |ELLIS MERSCHOFF RA |
+------------------------------------------------+LARRY CAMPER NMSS |
| NRC NOTIFIED BY: JOE GARCIA |FRANK CONGEL IRO |
| HQ OPS OFFICER: JOHN MacKINNON |DAN SULLIVAN FEMA |
+------------------------------------------------+ROBERT CONLEY USDA |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| COURTESY NOTIFICATION OF A DOE EMERGENCY DECLARATION AT AN INDEPENDENT SPENT |
| FUEL STORAGE INSTALLATION (ISFSI) IN IDAHO. |
| |
| At 1647MDT, DOE INEEL declared a Site Area Emergency due to wildland fires |
| on DOE controlled property, 2 miles North East of INTEC. The ISFSI |
| containing the TMI spent fuel is not threatened. This notification is a |
| courtesy call only and does not involve the NRC Radiological Emergency Plan. |
| No NRC assistance is requested. |
| |
| DOE INEEL has notified the State of Idaho, all surrounding counties and DOE |
| Headquarters. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37338 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 09/18/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 06:16[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 04:50[EDT]|
| NRC NOTIFIED BY: KEITH POPE |LAST UPDATE DATE: 09/18/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEPHEN CAHILL R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH TRAINS OF RHR (RECIRC CAPABILITY) INOPERABLE FOR APPROXIMATELY SEVEN |
| HOURS |
| |
| "While placing RHR Train'B' in shutdown cooling during a refueling outage |
| the pump minimum flow valve did not close as expected. Investigation |
| revealed that the mini-flow transmitter 1 FIS-0611 was isolated causing the |
| valve 1 FV0611 to remain open with RHR flow in excess of setpoint that would |
| cause the valve to close. Work was performed on August 29, 2000, to |
| calibrate this transmitter. On September 9, 2000, RHR Train 'A' seal |
| cooler was isolated for maintenance rendering both trains of RHR inoperable |
| for 6 hours and 54 minutes. The Cold leg injection capability from RHR |
| Train 'A' remained available during this time. The Cold leg recirculation |
| capability during these inoperabilities was not available. This would have |
| required entry into T. S. 3.0.3. |
| |
| "RHR Train 'B' mini-flow transmitter 1FIS-0611 was discovered isolated |
| causing the valve 1FV0611 to remain open with RHR flow in excess of setpoint |
| that would cause the valve to close. The transmitter has been returned to |
| service and the valve 1 FV0611 is operating properly." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021