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Event Notification Report for April 18, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/17/2000 - 04/18/2000

                              ** EVENT NUMBERS **

36858  36897  36898  36899  36900  36901  36902  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36858       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 04/03/2000|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 10:43[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        04/03/2000|
+------------------------------------------------+EVENT TIME:        08:45[CDT]|
| NRC NOTIFIED BY:  STEVE GHEEN                  |LAST UPDATE DATE:  04/17/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         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       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH ENERGY LINE BREAK ANALYSES (HELB) REQUIRE DOORS IN AREAS CONTAINING     |
| MAIN STEAM LINES NOT BE BLOCKED OR OBSTRUCTED                                |
|                                                                              |
| "DOORS 155/177 OBSTRUCTED BY SCAFFOLDING CAUSING DOORS TO BE PARTIALLY       |
| BLOCKED.  DUE TO HELB CONSIDERATIONS, DOORS NEED TO BE ABLE TO SWING OPEN    |
| FULLY.  SCAFFOLDING WAS MOVED AT 0925 CDT."                                  |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
|                                                                              |
| * * * RETRACTED AT 1130 EDT ON 4/17/00 BY WILLIAM MATHER TO FANGIE JONES * * |
| *                                                                            |
|                                                                              |
| "Northern States Power Company's Nuclear Analysis Department (NAD) completed |
| calculations based on the doors being blocked and as a result of these       |
| calculations is withdrawing the Event Notification #36858."  The analysis    |
| indicates that there is no significant effect on peak pressure during the    |
| analyzed event.                                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R3DO (Patrick Hiland).                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36897       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 04/17/2000|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 04:57[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        04/17/2000|
+------------------------------------------------+EVENT TIME:        02:51[EDT]|
| NRC NOTIFIED BY:  JEFF GROFF                   |LAST UPDATE DATE:  04/17/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CLOSURE OF A RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING OUTBOARD ISOLATION |
| VALVE RESULTING IN LOSS OF AN RHR PUMP AND SUBSEQUENT LOSS OF SHUTDOWN       |
| COOLING FOR 21 MINUTES                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0251 on 04/17/00, the E1150-F008 'RHR Shutdown Cooling (SDC) Outboard    |
| Isolation Valve' closed causing the RHR 'B' pump to trip due to loss of      |
| suction flow path.  At the time of the trip, the RHR 'B' pump was in         |
| operation for [SDC]."                                                        |
|                                                                              |
| "[SDC] was restored at 0312.  During the event, Unit 2 was in Mode 5 --      |
| Refueling -- with the vessel cavity flooded up to greater than 20' 6" above  |
| the vessel flange with the fuel pool gates removed.  No temperature rise in  |
| the vessel was noted during the time SDC was out of service.  No core        |
| alterations were in progress at the time."                                   |
|                                                                              |
| "Prior to the closure of the E1150-F008 valve, [the] Division 2 core spray   |
| system was being tagged out of service for [refueling] outage maintenance.   |
| Part of the tag-out was to remove fuses for the core spray AC/DC inverter.   |
| Upon removing power to the inverter, a reactor high pressure signal caused a |
| trip system B, group 4 -- Shutdown Cooling/Head Spray Isolation, which       |
| closes the E1150-F008 valve.  After the isolation, the core spray AC/DC      |
| inverter was returned to service, the E1150-F008 valve opened, and RHR 'B'   |
| pump was placed back into [the] SDC mode."                                   |
|                                                                              |
| "This event is being reported under 10CFR50.72(b)(2)(ii), any event or       |
| condition that results in the manual or automatic actuation of any           |
| engineered safety feature."                                                  |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36898       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COMMUNITY HOSPITAL OF LANCASTER      |NOTIFICATION DATE: 04/17/2000|
|LICENSEE:  COMMUNITY HOSPITAL OF LANCASTER      |NOTIFICATION TIME: 09:48[EDT]|
|    CITY:  LANCASTER                REGION:  1  |EVENT DATE:        04/16/2000|
|  COUNTY:  LANCASTER                 STATE:  PA |EVENT TIME:        14:30[EDT]|
|LICENSE#:  37-12495-01           AGREEMENT:  N  |LAST UPDATE DATE:  04/17/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN WHITE           R1      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+CHARLIE MILLER       IRO     |
| NRC NOTIFIED BY:  MARY FEKETE                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RECEIPT OF A PACKAGE WITH SURFACE CONTAMINATION GREATER THAN THE 2,000       |
| DPM/100 cm² LIMIT                                                            |
|                                                                              |
| On 04/16/00, a package arrived from Syncore (a pharmacy located in           |
| Harrisburg, Pennsylvania), and calculations following a wipe test of the     |
| package revealed surface contamination of 13,600 DPM/cm².  This was          |
| discovered at 0230 on 04/16/00.  The licensee reported that the package      |
| contained technetium-99m and that the licensee normally receives 50 mCi in   |
| each package.  At the time of this event notification, the package had not   |
| been opened, and there was no report of a breach.  The licensee quarantined  |
| the package in a storage area and notified Syncore at 0245 on 04/16/00.      |
|                                                                              |
| The licensee reported that the contamination is more likely to be around     |
| 2,400 DPM/cm² because the efficiency of the well counter is based on cesium  |
| and the isotope involved was identified to be technetium-99m.                |
|                                                                              |
| (Call the NRC operations officer for a licensee contact telephone number.)   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36899       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  INTERNAT. RAD & INSPECT. SVCS. INC.  |NOTIFICATION DATE: 04/17/2000|
|LICENSEE:  INTERNAT. RAD & INSPECT. SVCS. INC   |NOTIFICATION TIME: 11:44[EDT]|
|    CITY:  CATOOSA                  REGION:  4  |EVENT DATE:        04/14/2000|
|  COUNTY:                            STATE:  OK |EVENT TIME:        11:30[CDT]|
|LICENSE#:  35-30246-01           AGREEMENT:  N  |LAST UPDATE DATE:  04/17/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DALE POWERS          R4      |
|                                                |BRIAN SMITH          MNSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WIELAND                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|IBBF 30.50(b)(2)(ii)     EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SOURCE DISCONNECT ON CAMERA OWNED BY INTERNATIONAL RADIOGRAPHY & INSPECTION  |
| SERVICES INC.                                                                |
|                                                                              |
| A radiography camera being used for an inspection by International           |
| Radiography & Inspection Services Inc. at the Matrix Fabrication Division    |
| site in Catoosa, Ok. had a source disconnect while being cranked out.  The   |
| source, which contained 72 curies of Iridium-192, was manufactured by AEA    |
| Technologies and mounted in a SPEC camera.  During the time of the source    |
| disconnect, the area around the camera was secured.  The licensee RSO went   |
| to the site, did a source recovery and returned the camera to their          |
| facility.  There were no exposures >40 mrem.  The licensee has packaged the  |
| equipment and will FedEx it to AEA Technologies for their analysis of the    |
| problem.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36900       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/17/2000|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 12:35[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/16/2000|
+------------------------------------------------+EVENT TIME:        12:00[EDT]|
| NRC NOTIFIED BY:  STEVE MERRILL                |LAST UPDATE DATE:  04/17/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    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       68       Power Operation  |68       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING DISCOVERY OF SEA TURTLE IN PLANT INTAKE       |
| CANAL                                                                        |
|                                                                              |
| "At approximately 12:00 on 4/16/00, a loggerhead sea turtle was recovered    |
| from the plant's intake canal. The turtle was alive, but in need of          |
| rehabilitation, and was subsequently sent to a facility at Sea World. As     |
| required by the plant's sea turtle permit, the Florida Department of         |
| Environmental Protection (DEP) was notified of the event. The notification   |
| of the DEP necessitates a four (4) hour phone call to the NRC.               |
|                                                                              |
| "The licensee recognizes that this notification is being made outside the    |
| allotted four (4) hour window. The root cause will be investigated through   |
| the Condition Report process."                                               |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36901       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 04/17/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 15:56[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/17/2000|
+------------------------------------------------+EVENT TIME:        13:09[EDT]|
| NRC NOTIFIED BY:  TOM COTTER                   |LAST UPDATE DATE:  04/17/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSER VACUUM                          |
|                                                                              |
| "At 13:04 on 4/17/00, BVFS Unit 1 experienced a loss of the turbine          |
| auxiliary steam header pressure. The loss of auxiliary steam pressure        |
| resulted in a decrease in condenser vacuum, rapidly approaching the low-low  |
| vacuum turbine trip setpoint. At 1309, the reactor was tripped manually.     |
| Steam Generator 1C feed valve FCV-1FW-498 was isolated during recovery due   |
| to minor leakby. Auxiliary Feedwater and all other equipment responded as    |
| expected. The initial problem was caused by a failure of the auxiliary steam |
| supply pressure control valve air diaphragm packing. This valve is air to    |
| open and spring operated to close. Air pressure was lost through the failed  |
| packing causing the valve to fail in the closed position. Auxiliary steam    |
| was restored during plant stabilization. The plant is in Hot Standby and all |
| systems are functioning properly. Heat removal is via the normal condenser   |
| steam dump system."                                                          |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36902       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 04/17/2000|
|    UNIT:  [] [2] []                 STATE:  WI |NOTIFICATION TIME: 16:02[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        04/17/2000|
+------------------------------------------------+EVENT TIME:        14:40[CDT]|
| NRC NOTIFIED BY:  JOHN SELL                    |LAST UPDATE DATE:  04/17/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SOURCE RANGE NEUTRON MONITOR COULD BE AFFECTED BY 10 CFR PART 50, APPENDIX R |
| ISSUE                                                                        |
|                                                                              |
| "The cabling for Unit 2 source range monitor 2N-32 was found to be impacted  |
| by a postulated fire in either the CCW pump room or the Unit 2 MCC room in   |
| the 8' PAB. Per 10 CFR 50 Appendix R at least one nuclear instrument (2N-31, |
| 2N-32 or 2N-40) must be available to monitor source range flux while         |
| shutting down the unit. [Monitor] 2N-32 is relied upon for a fire in [fire   |
| zone] FZ  142 and 166 due to cable losses on the 2N-31 and 2N-40             |
| instruments. Loss of 2N-32 will cause a total loss of SR monitoring          |
| capability which places the plant outside the Appendix R design basis."      |
|                                                                              |
| The NRC resident inspector will be informed of this notification by the      |
| licensee.                                                                    |
+------------------------------------------------------------------------------+