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Event Notification Report for February 7, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/04/2000 - 02/07/2000

                              ** EVENT NUMBERS **

36659  36660  36661  36662  36663  36664  36665  36666  36667  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36659       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 02/04/2000|
|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 12:18[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/04/2000|
+------------------------------------------------+EVENT TIME:        12:00[EST]|
| NRC NOTIFIED BY:  W. SUSLICK                   |LAST UPDATE DATE:  02/04/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|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       65       Power Operation  |65       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOW HEAD SAFETY INJECTION PUMPS SUCTION MAY SWAP FROM FWST CONTAINMENT SUMP  |
| BEFORE LOW FWST LEVEL IS REACHED.                                            |
|                                                                              |
| "On February 4. 2000 during a review of engineering staff comments on a      |
| proposed technical specification change, a condition was discovered that may |
| have resulted in operation outside the design basis of the plant. The        |
| specific condition is a deficiency in the current ACTION statement for       |
| McGuire Technical Specifications when invoked for one inoperable level       |
| channel of the refueling water storage tank (FWST). Currently this Technical |
| Specification allows for the option of placing the affected channel in the   |
| trip condition, operation is permitted in this condition for an indefinite   |
| period of time.                                                              |
|                                                                              |
| "Because Technical Specifications allow operation in this condition for an   |
| indefinite period of time, this condition can not be considered a design     |
| basis single failure during a design basis accident.  A single failure of an |
| FWST level channel coincident with a design basis LOCA, with another channel |
| in trip as allowed by technical specifications would result in premature     |
| swapover of the low head safety injection pumps to the containment sump.  As |
| a result of this premature swapover both trains of low head safety injection |
| pumps could fail, which could result in a complete loss in recirculation     |
| phase post accident cooling.                                                 |
|                                                                              |
| "Currently all 3 channels of FWST level instrumentation of both McGuire      |
| Units are operable. Therefore, the plant is not operating with this single   |
| failure vulnerability.  Administrative controls have been put into place to  |
| limit the time which the plant could operate in this condition until such    |
| time as Technical Specifications can be revised to limit this single failure |
| vulnerability"                                                               |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee..      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36660       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 02/04/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 17:14[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        02/04/2000|
+------------------------------------------------+EVENT TIME:        16:39[EST]|
| NRC NOTIFIED BY:  M VASELY                     |LAST UPDATE DATE:  02/04/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TONY DIMITRIADIS     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALIDITY OF ASSUMPTIONS FOR THE 30 MINUTE NITROGEN BACKUP SUPPLY IN QUESTION |
|                                                                              |
|                                                                              |
| During the review of Consolidated Edison calculation FIX0030-00, Nitrogen    |
| Backup Supply for control of Auxiliary Feedwater Flow Control Valves,        |
| Turbine Driven Auxiliary Feedwater Pump, and Atmospheric Steam Dump          |
| Controls, questions arose as to the validity of the assumption statements    |
| that resulted in the design basis for 30 minutes of Nitrogen could not be    |
| sustained.  The assumptions are in the process of being validated.  A third  |
| nitrogen bottle has been placed in backup alignment to maintain the 30       |
| minute requirement.                                                          |
|                                                                              |
| 3 of the 6 Nitrogen Backup Bottles are now valved in instead of 2.           |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36661       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 02/04/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 19:36[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        02/04/2000|
+------------------------------------------------+EVENT TIME:        18:00[CST]|
| NRC NOTIFIED BY:  ROBERT POWERS                |LAST UPDATE DATE:  02/04/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TONY VEGEL           R3      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) DECLARED INOPERABLE                   |
|                                                                              |
| AT 1042 CST SPDS WAS DECLARED INOPERABLE BECAUSE OF A HARDWARE PROBLEM WITH  |
| THEIR PLANT PROCESS COMPUTER WHICH FEEDS DATA INTO THE SPDS. THE LICENSEE    |
| HAS INCREASED MONITORING PLANT PARAMETERS.  CARDS ARE BEING REPLACED IN THE  |
| PROCESS PLANT COMPUTER AT THIS TIME.                                         |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE.       |
|                                                                              |
| * * * UPDATE AT 2143ET ON 02/04/00 BY HALVERSON TAKEN BY MACKINNON * * *     |
|                                                                              |
| SPDS RETURNED TO SERVICE AT 1847CST.  R3DO (VEGEL) NOTIFIED.                 |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE.                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36662       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 02/05/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 08:42[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/04/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        20:00[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/05/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |TONY VEGEL           R3      |
|  DOCKET:  0707001                              |JOE HOLONICH         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM HORN FAILED SURVEILLANCE                   |
|                                                                              |
| At 1600 on 02-04-2000 the PSS was informed of the failure of a criticality   |
| accident alarm system (CAAS) air horn to sound during the performance of     |
| surveillance testing.  The cause of the failure was determined to be debris  |
| in the air line fouling the flow path for the horn.   Subsequently, after    |
| this horn was repaired and the air horn line blown out, another air horn on  |
| the same branch line became clogged and would not sound sufficiently.  This  |
| horn was also repaired and its line blown out.  The system was retested      |
| satisfactorily and declared operable at 2245 on 02-04-00.  It is possible    |
| that the system would not have performed its intended safety function if it  |
| had been required to before it was declared inoperable.                      |
|                                                                              |
| This event is reportable under 10 CFR 76.120(c)(2) as an event in which      |
| equipment required by the TSR is disabled or fails to function as designed.  |
|                                                                              |
| The NRC Senior Resident Inspector has been notified of this event.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36663       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 02/05/2000|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 13:54[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/04/2000|
+------------------------------------------------+EVENT TIME:        20:59[CST]|
| NRC NOTIFIED BY:  GREG JANAK                   |LAST UPDATE DATE:  02/05/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLAUDE JOHNSON       R4      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 2 TRAINS OF ESSENTIAL CHILLED WATER INOPERABLE                               |
|                                                                              |
| On 02/04/00 at 2059 CST, Essential Chiller 12C was declared inoperable due   |
| to tripping after being started at 2056 CST on 02/04/00.  This resulted in   |
| an entry into Technical Specification 3.7.14.  Investigation revealed that   |
| Essential Chiller 12C tripped on high condenser pressure which was caused by |
| not having cooling water flow properly aligned.  Found Essential Cooling     |
| Water valve EVV-3025 to be closed, when it's required position is throttled  |
| to maintain Essential Cooling Water flow.  The valve alignment was restored  |
| to normal and Essential Chiller 12C was declared operable at 2358 CST on     |
| 02/04/00.                                                                    |
|                                                                              |
| The investigation revealed that EVV-3025 was closed at approximately 1121    |
| CST on 02/02/00 as indicated on integrated computer system trends.  At that  |
| time Essential Chilled Water Train "B" was inoperable for planned            |
| maintenance and remained inoperable until 1527 CST on 02/02/00.  This        |
| resulted in 2 trains of Essential Chilled Water being inoperable for 4 hours |
| and 6 minutes which placed the plant in Technical Specification 3.0.3 (did   |
| not require plant shutdown).                                                 |
|                                                                              |
| A Licensee Event Report will be submitted within 30 days.                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36664       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 02/05/2000|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 15:06[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        02/05/2000|
+------------------------------------------------+EVENT TIME:        13:06[CST]|
| NRC NOTIFIED BY:  TOM MOSBY                    |LAST UPDATE DATE:  02/06/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLAUDE JOHNSON       R4      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |JOSEPH GIITTER       IRO     |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION 3.0.3 ENTERED AT 1306 CST DUE TO BOTH TRAINS OF LOW  |
| PRESSURE INJECTION/RESIDUAL HEAT REMOVAL (LPI/RHR) DECLARED INOPERABLE.      |
|                                                                              |
| "At 1306 on 02/05/00, both Low Pressure Injection/Decay Heat Removal Pumps   |
| (P-34A and B)  were declared inoperable and Technical Specification 3.0.3    |
| was entered.   The pumps were declared inoperable after the inboard pump     |
| bearing temperatures exceeded their alarm setpoint after being placed in     |
| service for decay heat removal for normal cooldown.                          |
|                                                                              |
| "Unit 1 was taken offline at 0010 on 02/05/00 for scheduled maintenance.     |
| The unit was in the process of cooling down at the time Tech Spec 3.0.3 was  |
| entered.  Decay heat removal is being maintained with the use of the         |
| operable "B" Reactor Coolant System Loop."                                   |
|                                                                              |
| Low Pressure Injection pump "A" was placed in service at 1206 CST and a high |
| temperature alarm for the inboard pump bearing was received. Later Low       |
| Pressure Injection pump "B" was placed in service and a high temperature     |
| alarm for the pump inboard bearing was also received at which time Tech Spec |
| 3.0.3 was entered.  The outboard bearing temperatures for both Low Pressure  |
| Injection pumps were below their high temperature alarm setpoint. The Low    |
| Pressure Injection pumps inboard and outboard bearing are cooled by the      |
| Service Water system.  Reactor Coolant System pressure is currently 262 psig |
| and plant temperature is 263 degrees F.  The licensee said that as far as he |
| knew the Service Water system was properly aligned for cooling both the      |
| inboard and outboard bearings of the Low Pressure Injection pumps.   Reactor |
| Coolant System Loop "A" is also fully operable if needed.  All other         |
| Emergency Core Cooling Systems are operable.   The licensee is investigating |
| the cause of the high inboard bearing temperatures.                          |
|                                                                              |
| The NRC Resident Inspector will notified of this event by the licensee.      |
|                                                                              |
| * * * UPDATE AT 1730 HOURS ON 02/05/00 BY MOSBY TAKEN BY MACKINNON * * *     |
|                                                                              |
| LICENSEE UPDATED EVENT AS A 4 HOUR CALL UNDER 10 CFR 50.72 (b)(2)(I) -       |
| DEGRADED WHILE SHUTDOWN.                                                     |
|                                                                              |
| "When P-34A was initially placed in service, the inboard bearing temperature |
| reached the alarm setpoint of 160 degrees F at which time the pump was       |
| secured.  Currently, P-34A is aligned to recirculate the Borated Water       |
| Storage Tank (BWST) and is in operation with the temperature of the pump     |
| inboard bearing steady at 84.5 degrees F.  Engineering, Operation and        |
| Predictive Maintenance are currently involved with the continued testing of  |
| the pump.  The testing and subsequent operability assessment will be         |
| concluded prior to placing the pump in service for decay heat removal."      |
| R4DO (C. Johnson) notified.                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event update by the          |
| licensee.                                                                    |
|                                                                              |
| * * * UPDATE AT 1040 ON 02/06/00 BY SCHEIDE TAKEN BY WEAVER * * *            |
|                                                                              |
| The licensee has retracted this event notification based on the following    |
| discussion.  Technical Specifications require LPI to be operable when three  |
| conditions are exist.  1.  Fuel in the reactor vessel.  2.  Reactor coolant  |
| temperature above 200 degrees F and 3.  Primary system pressure > 300 psig.  |
| A subsequent review of the event verified that RCS pressure was at 240 psig  |
| at the time of the event.  Therefore, LPI was not required to be operable    |
| and 3.0.3 was not applicable.  Conditions for decay heat removal were        |
| satisfied since both reactor coolant loops and associated OTSGs remained     |
| operable.                                                                    |
|                                                                              |
| The licensee will notify the NRC resident inspector.  The operations center  |
| notified the RDO (Johnson).                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36665       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 02/06/2000|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 18:37[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/06/2000|
+------------------------------------------------+EVENT TIME:        17:55[EST]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  02/06/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       93       Power Operation  |93       Power Operation  |
|2     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PUBLIC PROMPT NOTIFICATION SYSTEM INOPERABLE FOR 2 MINUTES                   |
|                                                                              |
| Due to technical difficulties in Jacksonville, Florida, the Public Prompt    |
| Notification System (NOAA weather radio) was lost at 1755 ET and was         |
| restored to service at 1757 ET.  Primary and backup system were inoperable   |
| during this period of time.                                                  |
|                                                                              |
| The NRC Resident will be notified of this event notification by the          |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36666       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 02/07/2000|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 03:11[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        02/07/2000|
+------------------------------------------------+EVENT TIME:        00:55[CST]|
| NRC NOTIFIED BY:  KEVIN PEDERSON               |LAST UPDATE DATE:  02/07/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TONY VEGEL           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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION - RECIRC SAMPLE ISOLATION VALVES                               |
|                                                                              |
| During the performance of standby liquid control refueling tests, a signal   |
| is sent to the reactor  water cleanup isolation valves and the recirc sample |
| valves.  The procedure addresses the RWCU valves, but not the recirc sample  |
| valves.  Since the outboard sample valve was secured (tagged) open, it       |
| unexpectedly closed upon initiation of the standby liquid control system.    |
|                                                                              |
| The valves were returned to their pre-test positions.                        |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36667       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 02/07/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 04:28[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        02/07/2000|
+------------------------------------------------+EVENT TIME:        02:40[CST]|
| NRC NOTIFIED BY:  DAVE KLIMECK                 |LAST UPDATE DATE:  02/07/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TONY VEGEL           R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| Minimum security personnel staffing requirements not met.  Immediate         |
| compensatory actions taken upon discovery.    The licensee will notify the   |
| NRC resident inspector.  Additional details of this event may be obtained by |
| contacting the NRC operations officer.                                       |
+------------------------------------------------------------------------------+