Event Notification Report for April 20, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/19/2000 - 04/20/2000
** EVENT NUMBERS **
36852 36891 36904 36905 36906 36907
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36852 |
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| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/01/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 11:02[EST]|
| RXTYPE: [1] CE |EVENT DATE: 04/01/2000|
+------------------------------------------------+EVENT TIME: 09:20[CST]|
| NRC NOTIFIED BY: LARRY LEES |LAST UPDATE DATE: 04/19/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KRISS KENNEDY R4 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Standby |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| TECH SPEC REQUIRED SHUTDOWN DUE TO EMERGENCY FEEDWATER STORAGE TANK LEVEL |
| DECREASING BELOW TECH SPEC LIMIT |
| |
| THE PLANT ENTERED ABNORMAL OPERATING PROCEDURE (AOP) 30, "EMERGENCY FILL OF |
| EMERGENCY FEEDWATER STORAGE TANK," AS A RESULT OF THE EMERGENCY FEEDWATER |
| STORAGE TANK LEVEL FALLING BELOW TECH SPEC LOW LIMIT OF 91%. THIS RESULTED |
| IN ENTRY INTO TECH SPEC 2.0.1 WHICH DIRECTS PLACING THE PLANT IN HOT |
| SHUTDOWN WITHIN 6 HOURS, LESS THAN 300 DEGREES F IN ANOTHER 6 HOURS AND IN |
| COLD SHUTDOWN IN 30 HOURS. AT THE TIME OF ENTRY INTO THIS TECH SPEC THE |
| PLANT WAS ALREADY IN HOT SHUTDOWN. ACTIONS TO REFILL THE EMERGENCY |
| FEEDWATER STORAGE TANK WERE TAKEN BY OPENING THE CONDENSATE FILL LINE AND |
| EMERGENCY FILLING. FILLING WAS IN PROGRESS BEFORE GOING BELOW 91%, HOWEVER, |
| SYSTEM DEMAND WAS GREATER THAN THE MAKEUP ABILITY OF THE DEMINERALIZED WATER |
| SOURCE (STEAM GENERATOR WATER SUPPLY SWAPOVER). LEVEL WAS ABOVE 91% AT |
| 0944CST AT WHICH TIME AOP 30 AND TECH SPEC 2.0.1 WERE EXITED. |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 1007 ON 4/19/00 BY MATZKE RECEIVED BY WEAVER * * * EVENT |
| RETRACTION |
| |
| On April 1, 2000, at 1102 EDT, Fort Calhoun Station made a 1-hour |
| notification of entry into a shutdown-required Technical Specification |
| Limiting Condition for Operation (LCO) to the NRC Operations Center under |
| 10CFR50.72(b)(1)(i)(A). At the time the plant had completed a normal |
| shutdown to hot standby per plant procedures. While maintaining the plant |
| in Hot Standby (Mode 3), the indicated level in the Emergency Feedwater |
| Storage Tank (EFWST), FW-19, appeared to fall below the Technical |
| Specification (TS) minimum level of 55,000 gallons. Operators conservatively |
| entered TS 2.0.1 (equivalent to standard TS 3.0.3). This LCO would have |
| required the plant to be placed in Cold Shutdown (Mode 4). The tank level |
| was quickly recovered and the TS exited. Subsequent investigation determined |
| that the TS for EFWST level had not been violated and TS 2.0.1 not entered. |
| Therefore, the notification of April 1, is being withdrawn. |
| |
| The Resident Inspector was notified. Reg 4 RDO(Powers) was notified. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36891 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/14/2000|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 19:58[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/14/2000|
+------------------------------------------------+EVENT TIME: 17:41[CDT]|
| NRC NOTIFIED BY: TIM WITSCHEN |LAST UPDATE DATE: 04/19/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| BURNT SMELL FROM HIGH PRESSURE COOLANT INJECTION (HPCI) STEAM SUPPLY VALVE |
| BREAKER. HPCI DECLARED INOPERABLE AND 14 DAY LIMITING CONDITION OF |
| OPERATION ENTERED PER TECHNICAL SPECIFICATION. |
| |
| An undervoltage alarm was received in control room from HPCI Direct Current |
| Motor Control Center (DCMCC) D312 which is located in the HPCI room. An |
| operator was immediately dispatched to investigate the undervoltage |
| condition on D312. The operator discovered that HPCI Steam Supply Valve, ( |
| MOV-2036), breaker, (D31206), had a burnt smell. The breaker was opened and |
| HPCI Steam Supply Inboard Isolation Valve was closed. HPCI was declared |
| inoperable and a 14 day Limiting Condition of Operation was entered per |
| their Technical Specification. Emergency Core Cooling Systems and Reactor |
| Core Isolation Cooling are fully operable if needed. Their was no fire and |
| the licensee is investigating. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
| |
| * * * RETRACTION 1717 4/19/2000 FROM BISTODEAU TAKEN BY STRANSKY * * * |
| |
| "This notification retracts a notification made 4/14/00 for HPCI being |
| declared inoperable due to a suspected electrical problem in a DC motor |
| control center (MCC). An undervoltage alarm was received, and a burnt smell |
| near the MCC was observed. The HPCI system was isolated per procedure. |
| Investigation revealed a low voltage monitoring coil had failed The coil was |
| replaced and successfully tested. The system was returned to its normal |
| standby condition. |
| |
| "This coil performs a monitoring function only. Failure of the coil, or any |
| effects of the failure would not have prevented the MCC or HPCI system from |
| performing their required safety function. The HPCI system was fully |
| operable until removed from service to investigate the condition and replace |
| the coil." |
| |
| The NRC resident inspector has been informed of this retraction. Notified |
| R3DO (Ring). |
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|Other Nuclear Material |Event Number: 36904 |
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| REP ORG: HONEYWELL SENSOR AND GUIDANCE PRODS |NOTIFICATION DATE: 04/19/2000|
|LICENSEE: HONEYWELL SENSOR AND GUIDANCE PRODS |NOTIFICATION TIME: 16:09[EDT]|
| CITY: MINNEAPOLIS REGION: 3 |EVENT DATE: 03/23/2000|
| COUNTY: STATE: MN |EVENT TIME: [CDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 04/19/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK RING R3 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM OSTRATEG | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| MISSING AIR IONIZER |
| |
| A generally licensed NRD model P-2021-3000 air ionizer (s/n 115737) was |
| discovered missing from a clean room at the Honeywell SGP facility in |
| Minneapolis. The device had an initial activity of 10 mCi of Po-210, but the |
| caller did not know the current activity. The device was declared lost on |
| 3/23/00 after repeated searches of the facility and interviews of employees |
| did not lead to its recovery. Honeywell has contacted the vendor regarding |
| this matter. |
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|Power Reactor |Event Number: 36905 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/19/2000|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 17:55[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/19/2000|
+------------------------------------------------+EVENT TIME: 14:33[EDT]|
| NRC NOTIFIED BY: RUSSELL LONG |LAST UPDATE DATE: 04/19/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| INADVERTENT AFW ACTUATION FOLLOWING TESTING |
| |
| "At about 1433 hours on 19 April 2000, there was an inadvertent actuation of |
| 32 Auxiliary Boiler Feedwater Pump (ABFP). The actuation occurred following |
| the completion of the required monthly test of 32 Emergency Diesel Generator |
| (EDG), when the diesel output breaker was opened. Normally the 'Non-SI |
| Blackout Logic' circuitry prevents automatic starting of equipment until |
| manually reset. For some reason, currently under investigation, this |
| circuitry automatically reset when the EDG output breaker was opened. The |
| cause of the automatic reset of the Non-SI Blackout Logic, and the automatic |
| start of 32 ABFP is under investigation. 32 EDG was inoperable prior to this |
| event for planned testing, and remains inoperable while the investigation |
| continues. 32 EDG is currently available and aligned for automatic start. |
| There were no plant conditions requiring operation of 32 ABFP and the |
| automatic start sent no water to any steam generator (since this requires |
| additional manual action). Immediate corrective action taken was to secure |
| 32 ABFP." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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|Fuel Cycle Facility |Event Number: 36906 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/19/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:50[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/19/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:55[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/19/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MARK RING R3 |
| DOCKET: 0707002 |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETHE | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NRC BULLETIN 91-01 4 HOUR REPORT |
| |
| "At 1555 hrs April 19, 2000, laboratory personnel were preparing samples |
| when they discovered that 8 uranium bearing samples (16-40 ml vials) were in |
| an Environmental Safety & Health (ES&H) Analytical Laboratory without having |
| had a gamma scan performed to determine total uranium. NCSA-0710_015.A02 |
| administrative control #1, states in part, "Any sample containers that are |
| postulated to contain uranium contamination >=100 ppm uranium based on their |
| origin shall be gamma scanned for total uranium." Control #1 of the NCSA |
| was lost, leading to a possible error in the mass tally for the high |
| concentration containers. The total volume of the containers was 640 ml, |
| and the concentration of the containers was subsequently determined to be |
| 500 ppm U-235. Mass control was lost for the high concentration |
| containers. Mass control for low concentration containers and volume |
| controls for process waste were maintained. |
| |
| "At the direction of the Plant Shift Superintendent (PSS) the requirements |
| for an NCS anomalous condition were initiated. At 1920 hrs compliance was |
| regained by scanning the samples and properly logging them into the |
| container mass inventory. |
| |
| "At the direction of the PSS the X-710 management staff will conduct |
| briefings with the respective personnel to prevent re-occurrence." |
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|Power Reactor |Event Number: 36907 |
+------------------------------------------------------------------------------+
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| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 04/19/2000|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 21:36[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/19/2000|
+------------------------------------------------+EVENT TIME: 18:16[EDT]|
| NRC NOTIFIED BY: ALLEN HARROW |LAST UPDATE DATE: 04/19/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| FILTERED EXHAUST FANS CANNOT BE OPERATED IN PARALLEL |
| |
| "Based on Unit 1H and 1J emergency bus logic testing performed on 4/18/00 |
| and 4/19/00 in accordance with 1-OPT-ZZ-001 and 1-OPT-ZZ-002, it has been |
| concluded that the Cat 1 Filtered Exhaust Fans, 1-VS-F-58A & B, will not |
| operate in parallel without tripping one or both fans. As a result, an event |
| or condition that alone could have prevented the fulfillment of a safety |
| function of structures or systems that are needed to control the release of |
| radioactive material, or mitigate the consequences of an accident exists for |
| Surry Units 1 and 2. This condition is reportable in accordance with 10 CFR |
| 50.72(b)(2)(iii). |
| |
| "Both fans have been tested by operating the fans individually. This testing |
| has determined that operation and performance of each fan is entirely |
| satisfactory when operated independently. |
| |
| "The current system alignment is that one of the two fans is in the |
| pull-to-lock position, and the other fan is in automatic stand-by. In this |
| configuration, one fan is operable, and fully capable of performing its |
| required functions. Unit 2 entered a 7 day Technical Specification 3.22.B |
| action statement on 4/18/00 at 1240 hours as a result of this condition. |
| |
| "The Surry Emergency Operating Procedures provide required directions to |
| place a Cat 1 Filtered Exhaust Fan in service, if the fans fail to |
| automatically start upon initiation of a Safety Injection. In the current |
| configuration, if the operable Cat 1 Filtered Exhaust fan fails to start, |
| the fan that is currently in PTL can be immediately placed in service." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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