Event Notification Report for November 13, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/09/2000 - 11/13/2000
** EVENT NUMBERS **
37439 37507 37508 37509 37510 37511 37512 37513 37514 37515 37516
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37439 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/18/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 18:45[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/18/2000|
+------------------------------------------------+EVENT TIME: 14:37[CDT]|
| NRC NOTIFIED BY: TOM LYNCH |LAST UPDATE DATE: 11/10/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|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 Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT EXPERIENCED A MOMENTARY GRID DISTURBANCE RENDERING SEVERAL |
| SAFETY-RELATED RADIATION MONITORS INOPERABLE |
| |
| "At 1437CDT on 10/18/00, River Bend Station experienced an electrical |
| perturbation in the Baton Rouge area. Line 758 [138 kV] was lost which |
| feeds a local refinery and this loss resulted in a momentary grid |
| undervoltage condition. This undervoltage condition lasted less than one |
| (1) second. As a result of this undervoltage condition, power to selected |
| radiation monitor sample pumps was lost. Specifically, the Control Room |
| Fresh air intake radiation monitors on both Division I and Division II lost |
| sample pump power and this resulted in these monitors being inoperable for |
| approximately three (3) minutes. The monitors were subsequently restarted. |
| As a result of this condition, the radiation monitors would have been unable |
| to initiate the Control Room Fresh Air Filter trains upon receipt of a high |
| radiation signal. This signal is required to be operable when handling |
| irradiated fuel; modes 1, 2, 3 and/or performing operations with the |
| potential to drain the reactor vessel. No fuel handling or reactor vessel |
| drain activities were in progress. This condition also existed for the Fuel |
| Building ventilation radiation monitors. This condition is conservatively |
| being reported as a loss of safety function for the Control Room Fresh Air |
| System. Further evaluation if this condition is in progress." |
| |
| The licensee informed the NRC resident inspector. |
| |
| * * * RETRACTION 1111 11/10/2000 FROM HUSTON TAKEN BY STRANSKY * * * |
| |
| "At 1746 on October 18. 2000 River Bend Station (RBS) reported a loss of |
| power to radiation monitors in accordance with 10 CFR 50.72(b)(2)(iii)(D). |
| Both divisions lost power for approximately 3 minutes until the units were |
| restored due to operator action. |
| |
| "A review indicated a concern for two safety functions related to charcoal |
| filtration. One was related to control room fresh air and one related to the |
| fuel building, specifically related to fuel handling accidents. |
| |
| "The radiation monitors sensed low voltage during the grid transient and |
| correctly shut down. They restarted automatically when voltage was restored: |
| however, the sample pump must be restarted by the operator. The radiation |
| monitors operated correctly per design for the conditions they sensed. |
| |
| "Review of the event by RBS Engineering and Licensing personnel indicate |
| that the loss of both divisions of radiation monitors for Control Room Fresh |
| Air (CRFA) is covered by technical specifications. The allowed outage time |
| in technical specifications was met when the radiation monitor sample pumps |
| were restored within about three minutes. Additionally, plant procedures |
| account for operator action to ensure the safety related monitors are |
| operating and restarting the sample pumps is considered non-heroic, assessed |
| action. Therefore this occurrence is not reportable. |
| |
| "A review of the alarm history for the fuel building radiation monitors |
| indicated that one division did not lose the sample pump and remained |
| operable throughout the transient. Therefore, there was no loss of safety |
| function for the fuel handling accident. |
| |
| "Based on this information, RBS concluded that the loss of the radiation |
| monitor sample pumps is not reportable and the previous report is |
| retracted." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37507 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SIEMENS POWER CORPORATION |NOTIFICATION DATE: 11/09/2000|
| RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 11:29[EST]|
| COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 11/08/2000|
| FABRICATION & SCRAP RECOVERY |EVENT TIME: 08:35[PST]|
| COMMERICAL LWR FUEL |LAST UPDATE DATE: 11/09/2000|
| CITY: RICHLAND REGION: 4 +-----------------------------+
| COUNTY: BENTON STATE: WA |PERSON ORGANIZATION |
|LICENSE#: SNM-1227 AGREEMENT: Y |JOE TAPIA R4 |
| DOCKET: 07001257 |BRIAN SMITH NMSS |
+------------------------------------------------+CHARLES MILLER IRO |
| NRC NOTIFIED BY: LOREN WAAS | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT |
| |
| Event Description: |
| |
| On 11/08/00 at about 8:35 a.m., while conducting an accountability audit of |
| waste material transfers, a Siemens Power Corporation (SPC) process operator |
| identified that a single 4-gallon container of uranium-containing waste |
| material with a net weight of 10.73 kg had been transferred to a 30-gallon |
| drum without first being sampled. |
| |
| Further investigation revealed that the 30-gallon drum contained 40 grams |
| 235U exclusive of the material from the unanalyzed 4-gallon bucket, A high |
| 235U value under normal conditions for a 4-gallon container of this waste |
| weighing 10.73 kg would be 54 grams 235U (waste containing 10% U and |
| assuming 5% 235U enrichment). Based on the highest U content observed in |
| waste from this process (25 %U), the worst case 235U content in this 10.73 |
| kg of waste material would be less than 135 grams. |
| |
| Safety Significance Of Event: |
| |
| The safety significance of this event is low. Assuming the material from the |
| unanalyzed single 4-gallon container contained uranium at historic maximum |
| levels from this process, the mass of 235U present in the 30-gallon waste |
| drum would be less than 175 g (40g + 135g), which is less than 10% of a |
| minimum critical mass. A safe mass of 235U (45% of minimum critical) is 792 |
| grams, assuming 5 wt.% enriched material. If one assumes that all of the |
| waste material in the unanalyzed 4-gallon container was UO2 (an unrealistic |
| assumption), the mass of 235U present in the 30 gallon waste drum would |
| still be less than 513 g assuming 5 wt.% enriched material. The material |
| actually present is < 3.5 wt.% enriched. |
| |
| This waste drum had been stored in a two tier array. However, this type of |
| waste drum is allowed to be stored in a 3 tier array. If this drum, as |
| postulated above to contain 175g 235U, and two additional drums each at |
| SPC's 100 g 235U waste disposal limit were present in a three tier stack, |
| the total mass in the stack would have been approximately 375 g 235U. This |
| is less than 22% of a minimum critical mass. |
| |
| Potential Criticality Pathways Involved: |
| |
| For criticality to occur in a single waste drum, a minimum of about 1760 g |
| 235U is required. Current SOPs require that two independent individuals |
| verify that waste container U contents have been determined by three |
| independent means before the waste container contents are tabulated on a |
| load list (as acceptable for incorporation into a single drum) and allowed |
| to be transferred to a waste packaging area. Two independent individuals are |
| then required to verify the selected buckets are on the load list before the |
| individual bucket contents can be placed into a 30-gallon waste drum. |
| |
| At least 1 3 unanalyzed 4-gallon containers of this type of waste material |
| (at historic high U levels from this process) would have to be placed into a |
| drum before criticality is possible. |
| |
| Multiple additional failures would be required to reach conditions that |
| approach a critical mass in a single drum or in an allowed 3 tier array of |
| drums. |
| |
| Controlled Parameters: |
| |
| For waste drums the controlled criticality parameter mass/allowed surface |
| density |
| |
| Estimated Amount, Enrichment, and Form Of Licensed Material: |
| |
| The licensed material is uranium bearing solid waste. The total 235U present |
| in the waste drum in question was calculated at worst case historic process |
| waste conditions to be <125 grams, with an actual enrichment of < 3.5 wt.% |
| 235U. This is < 10% of the minimum critical mass of material enriched to 5 |
| wt.% 235U. |
| |
| Nuclear Criticality Safety Control(s) Or Control Systems and a Description |
| of the Failures Or Deficiencies: |
| |
| Nuclear criticality safety controls imposed on this waste generation, |
| packaging, and storage process include: |
| |
| analysis of uranium content in the initial waste buckets by three |
| independent means; second party |
| verification of drum load lists for compliance with waste drum limits; |
| second party verification that buckets actually received at the drum loading |
| area match those called for by the drum load list. |
| |
| The control system failed when an operator selected a 4-gallon waste bucket |
| not on the approved load list and the error was not caught by the waste |
| handler tasked to verify that buckets received in the waste handling area |
| matched those on the approved drum load list. |
| |
| A number of factors may have contributed to the failure, including but not |
| limited to: |
| |
| 1 Human factors issues related to reading very similar alpha-numeric |
| characters (in this case AA4072 vs. AC4072); |
| |
| 2 The practice of placing waste buckets inside plastic bags for the sake of |
| contamination control, prior to their being stored in an unlit cargo |
| container. This necessitates transcribing the container ID number to a piece |
| of tape on the outside of the plastic bag, allowing for the possibility of |
| transcription errors. |
| |
| 3 The practice of storing unanalyzed waste buckets destined for process |
| recycle with buckets destined for placement into waste drums. |
| |
| A formal SPC Incident investigation Board (IIB) is investigating the |
| incident. |
| |
| Corrective Actions To Restore Safety Systems and When Each Was Implemented: |
| |
| The process operators finding the infraction promptly notified Criticality |
| Safety. |
| |
| Criticality Safety assembled a multi-disciplinary team to review the |
| infraction and determined the safety significance of the incident to be low |
| but that it met the NRC Bulletin 91-01 Criteria as a 24 hour reportable |
| condition. |
| |
| This team also recommended the following immediate actions: |
| |
| 1 Stop loading waste drums with this type of material. (completed |
| 2 Account for and label all unanalyzed waste buckets of this type of |
| material to assure that no other buckets intended for process recycle have |
| been, or will be, erroneously placed into waste drums. complete) |
| |
| The SPC IIB is formally evaluating incident cause(s) and potential |
| corrective actions. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37508 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 11/09/2000|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 14:15[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/09/2000|
+------------------------------------------------+EVENT TIME: 10:24[EST]|
| NRC NOTIFIED BY: DANIEL MURRAY |LAST UPDATE DATE: 11/09/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHELE EVANS R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Offsite Notification of an oil spill. |
| |
| At 1024 hours, a report was made to the Unit 2 control room identifying a |
| possible oil spill in progress from near the intake structure to the Ohio |
| River. There was a sheen in front of the intake structure; it is not clear |
| if Beaver Valley is the source of the discharge. The abnormal operating |
| procedure for oil spills (1/2AOP-53C.4A.75.6) was entered to respond to the |
| reports. On-site catch basins and oil separators were checked with no |
| evidence of oil in the process streams. On-site equipment was checked for |
| leakage that may have contributed to the spill; none was identified. A boom |
| was placed in front of the apparent discharge point to stop any further |
| release of oil into the Ohio River. Further observation indicated that the |
| oil sheen also existed up river on th e water and on the shore. The source |
| of the oil appears to be the Ohio River, not Beaver Valley Power Station. |
| This report is being made due to the notification of other government |
| agencies as directed by the plant procedure. The notifications began at 1149 |
| hours. |
| |
| The licensee notified the National Response Center, Pennsylvania Department |
| of Environmental Protection, Beaver County Emergency Management Agency and |
| the Pennsylvania Emergency Management Agency. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37509 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 11/09/2000|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 15:01[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 11/09/2000|
+------------------------------------------------+EVENT TIME: 13:25[CST]|
| NRC NOTIFIED BY: KEVIN HUJET |LAST UPDATE DATE: 11/09/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|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 96 Power Operation |96 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - TRAVELING SCREEN COVERS NOT KEPT IN PLACE |
| |
| A review of USAR Section 2.6 identified an apparent discrepancy between |
| plant design and current configuration. USAR and original plant Safety |
| Evaluation identified modification to the plant to mitigate high lake level |
| conditions to preclude flooding within safety related areas. Included in |
| these features are closed and strengthened traveling water screen covers. |
| KNPP has historically operated with these covers in the open position, which |
| is contrary to the USAR. This is being considered as outside of design |
| basis. Actions have been taken to close and brace the covers in the closed |
| position. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37510 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/09/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 21:59[EST]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/09/2000|
+------------------------------------------------+EVENT TIME: 17:20[CST]|
| NRC NOTIFIED BY: BENNETT |LAST UPDATE DATE: 11/09/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY |
| |
| A CONTRACT SUPERVISOR RECEIVED A CONFIRMED POSITIVE TEST RESULT. THE |
| INDIVIDUAL WAS ESCORTED FROM THE PROTECTED AREA AND ACCESS WAS SUSPENDED. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37511 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 11/10/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 04:54[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/10/2000|
+------------------------------------------------+EVENT TIME: 02:17[EST]|
| NRC NOTIFIED BY: KEVIN PHILLIPS |LAST UPDATE DATE: 11/10/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|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 N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF POWER TO 4kV ESF BUS DURING TESTING |
| |
| "A failure of a voltage regulator transformer on 1B diesel generator |
| occurred during a planned ESF test, requiring an emergency shutdown of the |
| diesel generator. This resulted in a loss of power to 4160V essential bus |
| 1ETB. Systems required for the current mode of operation were unaffected as |
| the B train components were removed from service for the test. Power has |
| been restored to the bus from offsite power at this time." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37512 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/10/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 09:52[EST]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/10/2000|
+------------------------------------------------+EVENT TIME: 06:10[CST]|
| NRC NOTIFIED BY: D. COVEYOU |LAST UPDATE DATE: 11/10/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFGAS ISOLATION VALVE FAILED TO CLOSE UPON DEMAND |
| |
| "At 0610 on November 10, 2000, the offgas isolation valve to the station |
| ventilation stack (2N62-F057) failed to close when the main control room |
| control switch for the valve was placed in the 'close' position. The valve |
| subsequently closed approximately 20 minutes later without other action |
| taken. The valve is air operated and is designed to close upon receipt of a |
| high offgas release rate or via the control switch. There were no abnormal |
| radiological releases occurring at the time of the failure. The unit was in |
| the process of being shut down for a planned refueling outage. No other |
| problems occurred during the event. All systems operated as designed except |
| as described. A prompt investigation has been initiated to determine the |
| cause of the valve failure. Corrective actions will be taken to address the |
| cause." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37513 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 11/10/2000|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 11:29[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 11/10/2000|
+------------------------------------------------+EVENT TIME: 10:55[EST]|
| NRC NOTIFIED BY: BOB COOLIDGE |LAST UPDATE DATE: 11/10/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |MICHELE EVANS R1 |
|10 CFR SECTION: |TAD MARSH NRR |
|AAEC |DAVID BARDEN FEMA |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO FIRE ONSITE |
| |
| The licensee declared an Unusual Event due to a small fire in the radwaste |
| truck lock. Grinding was being performed as part of maintenance activities, |
| igniting some material beneath the floor. The site fire brigade responded to |
| the fire, but did not extinguish the fire within 10 minutes. The licensee |
| believes that the fire has been extinguished, but there is still some smoke |
| in the area. The licensee reported that the local fire department also |
| responded to the site. No radiological release has occurred as a result of |
| the fire. |
| |
| The NRC resident inspector will be informed of this event by the licensee. |
| |
| |
| * * * UPDATE AT 1220 ON 11/10/00 BY COOLIDGE, RECEIVED BY WEAVER *** |
| |
| The licensee terminated the Unusual event at 1217. The fire is out, there |
| was no extension and all air samples measured showed no airborne |
| contamination. The resident inspector has been informed. |
| |
| The operations center notified the RDO (Evans); EO (Marsh) and Fema (Eches). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37514 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/10/2000|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 13:33[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/10/2000|
+------------------------------------------------+EVENT TIME: 10:29[CST]|
| NRC NOTIFIED BY: RANDY HASTINGS |LAST UPDATE DATE: 11/10/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|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 |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ESF ACTUATION - EMERGENCY DIESEL GENERATOR STARTS |
| |
| During the performance of the procedure for protective relay calibration and |
| testing on Unit 2 Safeguards Bus 2A06, an undervoltage signal was generated |
| on bus 2A06. The undervoltage signal was generated when the technicians |
| checked the continuity between two test points on bus 2A06 as specified in |
| the procedure. On the undervoltage signal, the main feed breaker to bus |
| 2A06 opened, bus 2A06 de-energized G-03 Emergency Diesel Generator (EDG) |
| started, G-04 EDG started, and the G-04 EDG output breaker closed to |
| re-energize bus 2A06. These actuations are as designed for an undervoltage |
| condition on bus 2A06. |
| |
| Unit 2 is currently defueled in a refueling outage. Spent fuel pool cooling |
| was not interrupted. Unit 1 is at 100% power. |
| |
| The appropriate Abnormal Operating Procedure was entered and completed. G-03 |
| EDG, which was running unloaded, has been shutdown. After determining the |
| cause of the undervoltage and verifying bus 2A06 condition was acceptable, |
| we have re-established normal offsite power to bus 2A06. G-04 EDG has been |
| shutdown. |
| |
| The licensee is investigating the cause of this event. The NRC resident |
| inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37515 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 11/10/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 14:31[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/10/2000|
+------------------------------------------------+EVENT TIME: 11:07[EST]|
| NRC NOTIFIED BY: PAUL MCINTYRE |LAST UPDATE DATE: 11/10/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|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 N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ESF ACTUATION |
| |
| ESF actuation due to a invalid Train B Safety Injection signal. No ECCS |
| system discharge to the Reactor Coolant System occurred. The event cause |
| appears to be a procedure deficiency during scheduled calibration / testing |
| of a Pressurizer Pressure instrument channel. The calibration procedure did |
| not require adequate verification of other channel parameters prior to |
| removing this channel from service, and did not veify blocks normally in |
| place for this plant condition. One channel of Pressurizer Pressure was |
| already in a tripped condition when this channel was removed from service. |
| This satisfied the two out of four logic to initiate the Safety Injection |
| signal. Only the Train B equipment was actuated. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37516 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/11/2000|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 11:55[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 11/11/2000|
+------------------------------------------------+EVENT TIME: 11:19[EST]|
| NRC NOTIFIED BY: DAVE WILLIAMS |LAST UPDATE DATE: 11/11/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION - DEAD GREEN SEA TURTLE |
| |
| AT 1119 ON 11/11/00, a notification was made to the Florida Fish and |
| Wildlife Conservation Commission regarding a dead green sea turtle found in |
| the plant's intake canal. The fatality is not believed to be related to |
| plant operation. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021