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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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).                                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36904       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
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| 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                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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."           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36907       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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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