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Event Notification Report for March 8, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/07/2000 - 03/08/2000

                              ** EVENT NUMBERS **

36603  36676  36734  36745  36762  36763  36764  36765  36766  36767  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36603       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  UTAH DIVISION OF RADIATION CONTROL   |NOTIFICATION DATE: 01/18/2000|
|LICENSEE:  NUCLEAR TESTING SERVICES             |NOTIFICATION TIME: 17:41[EST]|
|    CITY:  SALT LAKE CITY           REGION:  4  |EVENT DATE:        01/18/2000|
|  COUNTY:                            STATE:  UT |EVENT TIME:        10:00[MST]|
|LICENSE#:  UT 1800139            AGREEMENT:  Y  |LAST UPDATE DATE:  03/07/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |WAYNE HODGES         NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  JULIE FELICE                 |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING TROXLER DENSITY GAUGE MISSING FROM NUCLEAR  |
| TESTING SERVICES LOCATED IN SALT LAKE CITY, UTAH                             |
|                                                                              |
| At 1000 MST on 01/18/00, Nuclear Testing Services located in Salt Lake City  |
| notified the Utah Division of Radiation Control of a lost, missing, or       |
| stolen gauge (Utah Incident Report UT-00-0002).  The missing gauge was a     |
| Troxler Electronic Laboratories, Inc.  gauge (model number 3430, gauge       |
| serial number 20882).  The gauge contained two sealed sources:  cesium-137 ( |
| source serial number 7-2293) and americium-241/beryllium (source serial      |
| number 47-16381).  Apparently, the licensee last had possession of the gauge |
| during April of 1999.  This was also when the last leak test was performed.  |
| The licensee believes that the gauge may have been leased out to another     |
| company during August of 1999.  However, there may have been problems with   |
| the paperwork or accountability, and there were also changes in personnel.   |
|                                                                              |
| The Utah Division of Radiation Control instructed the licensee to contact    |
| local Police Department because there is the possibility of theft.  It was   |
| also reported that the licensee had been in touch with Troxler.              |
|                                                                              |
| The Utah Division of Radiation Control stated that this event seemed to fit  |
| the Abnormal Occurrence Criteria under any substantial breakdown of physical |
| security or material control.  It was stated that one of those deals with    |
| accountability systems.                                                      |
|                                                                              |
| (Call the NRC operations center for a state contact telephone number.)       |
|                                                                              |
| * * * UPDATE AT 1608 ON 03/07/00 BY JULIE FELICE TO JOLLIFFE * * *           |
|                                                                              |
| Representatives from Geomatrix Consultants, Inc,, Costa Mesa, CA, notified   |
| representatives of Nuclear Testing Services, Salt Lake City, UT that the     |
| missing Troxler Moisture Density Gauge, Model #3430, Serial #20882, is in    |
| Geomatrix's possession and had been all along.  Geomatrix representatives    |
| plan to return the undamaged gauge to Nuclear Testing Services.              |
|                                                                              |
| The NRC Operations Officer notified the R4DO Dave Loveless and NMSS EO Scott |
| Moore.                                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36676       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/09/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 16:50[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/08/2000|
+------------------------------------------------+EVENT TIME:        12:09[EST]|
| NRC NOTIFIED BY:  CHRISTOPHER HYNES            |LAST UPDATE DATE:  03/07/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |HAROLD GRAY          R1      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|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       93       Power Operation  |93       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INFORMATION CALL REGARDING RIVER WATER PUMP PROBLEMS                         |
|                                                                              |
| "This report is being made to provide preliminary notification of an event   |
| that is currently under investigation at Beaver Valley Power Station Unit    |
| No. 1 (BVPS Unit 1).                                                         |
|                                                                              |
| "River Water Pump #WR-P-1B at BVPS Unit 1 tripped on overcurrent shortly     |
| after it was attempted to be started at 1209 on 02/08/00.  The Action        |
| Statement for Technical Specification 3/4.7.4.1 was entered for less than    |
| two River Water subsystems being operable.  River Water Pump #WR-P-1C (swing |
| pump) was then aligned to the 'B' train header and it also tripped on        |
| overcurrent shortly after it was started at 1716 on 02/08/00.                |
|                                                                              |
| "Preliminary information identified that the #1B and #1C River Water Pumps   |
| would not operate due to the loss of gap between the pumps rotating assembly |
| and the pump bowl.  Investigation into the cause of the loss of the pumps'   |
| gap is ongoing.  BVPS Unit 1 River Water Pump #1A on the 'A' train continues |
| to operate satisfactorily and is operable.  The 'A' train is being treated   |
| as protected equipment (i.e., no elective work is being done on or near 'A'  |
| train components).  The BVPS Unit 1 operating crews have reviewed the        |
| procedures associated with operating the BVPS Unit 1 Auxiliary River Water   |
| System in the Alternate Intake Structure and the use of the cross tie        |
| connection with the diesel driven fire pump."                                |
|                                                                              |
| The licensee stated that BVPS Unit 1 entered a 72 hour Technical             |
| Specification Limiting Condition for Operation at 1209 on 02/08/00.  The NRC |
| resident inspector has been informed of this notification by the licensee.   |
|                                                                              |
| * * * UPDATE AT 1827 ON 02/10/00 BY DAN MURRAY TO JOLLIFFE * * *             |
|                                                                              |
| The licensee has identified that the #1B and #1C River Water Pumps would not |
| operate due to the loss of gap between the pump's rotating assembly and the  |
| pump bowl.  This event is believed to have been initiated by a temporary     |
| operating procedure that started on 02/05/00 for maintenance on the          |
| non-safety related filtered water system.  This procedure altered the        |
| filtered water system configuration which was the normal supply to the River |
| Water Pumps' seal water system.  One effect of this change was an increase   |
| in the seal water temperature at times as much as 30 degrees above its       |
| previous temperature which had been near the current river water             |
| temperature.  This temperature increase adversely affects a pump in the      |
| standby configuration whereby thermal expansion of the pump's rotating       |
| assembly causes a loss of clearance.  River Water Pump #WR-P-1A has remained |
| operating satisfactorily throughout this event.  The identified increased    |
| seal water temperature condition would not adversely affect an operating     |
| pump.  Administrative controls have been implemented to require only the use |
| of seal water supply sources with temperatures at or near the current river  |
| water temperature for the River Water Pumps.                                 |
|                                                                              |
| This condition is being reported to the NRC pursuant to                      |
| 10CFR50.72(b)(1)(ii)(B) as a condition that is outside the design basis of   |
| the plant because of the potential for one train of the two-train safety     |
| related River Water System (required to be operable per Technical            |
| Specification 3/4.7.4.1) to have been incapable of performing its design     |
| safety function for an extended period of time during operation.             |
|                                                                              |
| The licensee plans to revise the test procedure, perform the tech spec       |
| surveillance test using the safety related seal water supply source, and     |
| exit the tech spec action statement.                                         |
|                                                                              |
| The licensee notified the NRC Resident Inspector of this update.             |
|                                                                              |
| The NRC Operations Officer notified the R1DO Harold Gray of this update.     |
|                                                                              |
| * * * UPDATE AT 1816 ON 03/07/00 BY JOHN THOMAS TO JOLLIFFE * * *            |
|                                                                              |
| The following additional information is provided from a subsequent licensee  |
| evaluation of the safety related seal water design for the River Water       |
| System pumps at BVPS and the above event update:                             |
|                                                                              |
| River Water Pump #WR-P-1C at BVPS Unit 1 was placed into service on 03/03/00 |
| with bearing and motor cooling water supplied by its own discharge via the   |
| safety related "Y" strainer #RW-YS-42.  Within 10-15 seconds of pump         |
| startup, the seal water pressure dropped to approximately 5 psig from its    |
| normal operating pressure of approximately 30 psig.  The control room        |
| operator then blew down the strainer and normal seal water operation ensued. |
| The normal non-safety related sources of seal water for the River Water      |
| System pumps have only recently been removed from service as a result of the |
| above event update.   A review of the adequacy of the current BVPS Unit 1    |
| seal water design for the River Water System was initiated as part of the    |
| above event update.  The partial plugging of the "Y" strainer on 03/03/00    |
| identifies that starting a River Water Pump which has been idle for a period |
| of time may initially ingest a slug of silt from the Intake Structure Bay    |
| large enough to restrict the flow of seal water through this strainer.       |
| Following an evaluation, the licensee has determined that a potential        |
| inadequacy may exist in the BVPS Unit 1 seal water design for the River      |
| Water System pumps that has been credited since initial operation of BVPS    |
| Unit 1.  Given that the strainer anomaly was quickly corrected, this seal    |
| water design concern involves the operability of a non-operating pump during |
| startup.  Seal water strainer plugging during pump operation is more gradual |
| and allows time for control room operator action.                            |
|                                                                              |
| River Water System Pump #WR-P-1C remains in operation with seal water        |
| supplied from its self-supplied strainer.  An Auxiliary River Water Pump in  |
| the Alternate Intake Structure is also available with its own separate seal  |
| water supply.  BVPS Unit 1 is currently in a refueling outage with all fuel  |
| removed from the reactor vessel.                                             |
|                                                                              |
| The seal water design condition was previously reported pursuant to          |
| 10CFR50.72(b)(1)(ii)(B) as a condition that was outside the design basis of  |
| the plant because of the potential for one train of the two-train safety     |
| related River Water System (required to be operable per Technical            |
| Specification 3/4.7.4.1) to have been incapable of performing its design     |
| safety function for an extended period of time during operation.  This       |
| additional information provides further basis that the seal water design for |
| the River Water System pumps was not sufficient to meet the design basis of  |
| the plant.                                                                   |
|                                                                              |
| The licensee is continuing to investigate this event and plans to resolve    |
| this issue prior to restarting Unit 1.                                       |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector of this update.      |
|                                                                              |
| The NRC Operations Officer notified the R1DO Greg Cranston of this update.   |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36734       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 02/28/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 06:34[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/28/2000|
+------------------------------------------------+EVENT TIME:        05:45[EST]|
| NRC NOTIFIED BY:  DAN BOYLE                    |LAST UPDATE DATE:  03/07/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |ROBERT SKELTON       IAT     |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |JOHN DAVIDSON        IAT     |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |WILLIAM BECKNER      NRR     |
|                                                |WILLIAM BRACH        NMSS    |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OVERDUE SHIPMENT OF NEW FUEL                                                 |
|                                                                              |
| The licensee reported that a shipment of new fuel from ABB was due to arrive |
| onsite at 0530 2/28/00. At the time of the report, the shipment had not yet  |
| arrived. The licensee is attempting to contact the shipper. The NRC resident |
| inspector will be informed of this event by the licensee.                    |
|                                                                              |
| * * * UPDATE 0809 2/28/00 FROM PARKER TAKEN BY STRANSKY * * *                |
|                                                                              |
| The fuel shipment arrived onsite at 0735 2/28/00. The shipper (Roberts       |
| Express) believed that the scheduled delivery time was 0700. The licensee    |
| plans to investigate the discrepancy in the delivery schedule. The NRC       |
| resident inspector will be informed of this update by the licensee. Notified |
| R1DO (White), NRR IAT (Skelton), NMSS IAT (Davidson), NRR EO (Beckner), and  |
| NMSS IAT (Brach).                                                            |
|                                                                              |
| * * * UPDATE 1012EST ON 3/7/00 FROM ERV PARKER TO S.SANDIN * * *             |
|                                                                              |
| "On 02/28/00, at 0634, Hope Creek made a one hour notification (NRC event    |
| #36734). This notification stated 'Hope Creak Generating Station expected a  |
| new fuel receipt to arrive on site at approximately 0530 this morning. As of |
| this time the shipment has not arrived. Station personnel are attempting to  |
| contact the shipping vendor. Our information indicates that the truck was    |
| dispatched at 1040 on Saturday and should have arrived by now.' The shipment |
| subsequently arrived on February 28, 2000, at 0735. This information was     |
| provided to the NRC at 0805.                                                 |
| This notification was made in accordance with 10CFR73.71, Reporting Of       |
| Safeguards Events, as a lost fuel shipment. The shipment was reported as     |
| lost because the Control Room expected the shipment to arrive at 0530, and   |
| it did not. The cause of the shipment not arriving at 0530 has been          |
| determined to be miscommunication. Due to this miscommunication, the         |
| trucking company believed that the shipment was expected at 0800. While      |
| conducting the investigation, plant staff determined that the truck was      |
| continually being tracked via satellite and the dispatcher was aware of its  |
| location at all times. Therefore, the fuel truck was not lost and this event |
| is not reportable in accordance with 10CFR73.71. As a result, the            |
| notification is being retracted."                                            |
|                                                                              |
| The licensee will inform the NRC resident inspector.  Notified               |
| R1DO(Cranston).                                                              |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36745       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 03/01/2000|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 13:56[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        03/01/2000|
+------------------------------------------------+EVENT TIME:        12:35[CST]|
| NRC NOTIFIED BY:  LARRY MCLERRAN               |LAST UPDATE DATE:  03/07/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION - USING THE AUXILIARY FEEDWATER PUMP TO FEED THE STEAM  |
| GENERATORS VIA THE MAIN FEEDWATER SYSTEM IS UNANALYZED.                      |
|                                                                              |
| ANO engineering has determined that using the Auxiliary Feedwater (AFW) pump |
| to feed steam generators (S/Gs) via the Main Feedwater (MFW) System is       |
| unanalyzed.  The ability of the MFW block valves to shut and isolate the     |
| affected S/G on a Main Steam Line Break (MSLB) has not been fully evaluated. |
| Preliminary evaluation indicates that the valves may not shut under worst    |
| case conditions (low voltage supplied to the MOV and high D/P across the     |
| valves).  This condition is only applicable during low power operations with |
| AFW feeding via the MFW piping.                                              |
|                                                                              |
| AFW is not an Engineered Safety Feature at ANO Unit 2.  The plant has a      |
| separate Emergency Feedwater (EFW) System which is not affected by this      |
| problem.                                                                     |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
|                                                                              |
| * * * UPDATE AT 1336 ON 03/07/00 BY TOM SCOTT TO JOLLIFFE * * *              |
|                                                                              |
| A licensee engineering review has determined that the consequences of the    |
| above event would have had no safety significance.  Review of the Hot Zero   |
| Power (HZP) Containment Analysis for a MSLB showed that consequences of a    |
| small amount of additional AFW would be bounded by the current limiting MSLB |
| containment analysis for Hot Full Power.  A previous sensitivity analysis of |
| the effects of isolating EFW to the S/Gs indicated no significant impact due |
| to continued flow for the HZP Nuclear Steam Supply System MSLB analysis.     |
| Since the consequences of having operated in an unanalyzed condition have    |
| been determined not to have significantly compromised plant safety,          |
| reporting to the NRC per 10CFR50.72(b)(1)(ii) is not applicable.             |
|                                                                              |
| Thus, the licensee desires to retract this event.                            |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified the R4DO Dave Loveless.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36762       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 03/07/2000|
|LICENSEE:  ROCKY MOUNTAIN CONSULTANTS           |NOTIFICATION TIME: 12:39[EST]|
|    CITY:                           REGION:  4  |EVENT DATE:        03/06/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:        12:00[PST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  03/07/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID LOVELESS       R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DON BUNN                     |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - CESIUM-137 SOURCE LOCATED IN A LOAD OF SCRAP STEEL IN A SCRAP YARD IN UTAH |
| -                                                                            |
|                                                                              |
| On 03/06/00, Ed Johnson of Rocky Mountain Consultants notified California    |
| Radiologic Health Branch (RHB)  that he had discovered a 10 millicurie       |
| Cs-137 source in a load of scrap steel that originated from California. The  |
|                                                                              |
| source was in a train car of scrap steel that set off the radiation monitor  |
| at Nucor Steel Company, Utah.  Mr Johnson searched the load and discovered a |
| Cs-137 source that had been removed from the body of a CPN portable gauge.   |
| The source appeared to have been through a shredder but the serial number    |
| was visible.  The source manufacturer, Amersham, said it was delivered to    |
| CPN who said they installed it in a MC-1 gauge, serial number M-19089075.    |
| The gauge was sold to Petra Geotechnical Company, license #2933 in 1989.     |
| This gauge was reported stolen on 12/12/94 and an investigation was          |
| conducted at that time.  Mr Johnson said the source will be shipped to CPN   |
| who will dispose of it.                                                      |
|                                                                              |
| The Am-241 neutron source was not located in the load of scrap steel.        |
| RHB-LA plans to go to Williams Recycling Company, Los Angeles, where the     |
| load originated, and survey their facility to try to locate it.  The scrap   |
| yard operator had installed a $30,000 Bicron gate monitor system three years |
| ago to keep unwanted radioactive material out of the scrap yard, but         |
| apparently this did not work.  A 5010 has been opened and assigned to RHB-LA |
| & Brea to investigate.                                                       |
|                                                                              |
| RBH plans to notify NRC of this incident after results of the survey at      |
| Williams Recycling Company are known.                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36763       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/07/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:23[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/06/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        21:42[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/07/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |ROGER LANKSBURY      R3      |
|  DOCKET:  0707002                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JEFF CASTLE                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - X-342 BUILDING EVACUATED DUE TO A VALID ACTUATION OF A "Q" SAFETY SYSTEM   |
| -                                                                            |
|                                                                              |
| At 2142 on 03/06/00, X-342 building feed and sampling operations personnel   |
| viewed smoke escaping from the pigtail (female) to manifold (male) fitting   |
| for a cylinder in autoclave #2.  The release started when the cylinder valve |
| was opened.  The building personnel evacuated the building and remotely      |
| placed the autoclave in containment shutdown.  Placing the autoclave in      |
| containment shutdown by design resulted in closure of the pigtail line       |
| isolation/safety valve and a manual actuation of that particular safety      |
| system.  The safety system was actuated while the autoclave was in an        |
| applicable TSR mode (TSR 2.1.3.13).  The plant emergency response process    |
| and procedures were implemented.  Results of all surveys performed during    |
| the emergency response were less than detectable.  Plant personnel plan to   |
| inspect the subject area and repair/replace damaged parts.                   |
|                                                                              |
| This event is reportable to the NRC as a valid actuation of a "Q" Safety     |
| System in accordance with Safety Analysis Report, Section 8.9 (24-Hour       |
| Report).                                                                     |
|                                                                              |
| There was no loss of hazardous or radioactive material nor radioactive or    |
| radiological contamination exposure as a result of this event.               |
|                                                                              |
| Plant personnel notified the NRC Resident Inspector and the Site DOE         |
| Representative.                                                              |
|                                                                              |
| PTS-2000-026,  PR-PTS-00-01308.                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36764       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 03/07/2000|
|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 15:45[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/07/2000|
+------------------------------------------------+EVENT TIME:        15:04[EST]|
| NRC NOTIFIED BY:  ANNETTE POPE                 |LAST UPDATE DATE:  03/07/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |EDWARD MCALPINE      R2      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|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          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - TEN OFFSITE EMERGENCY SIRENS INOPERABLE FOR 19 MINUTES -                   |
|                                                                              |
| At 1504 on 03/07/00, the licensee notified Brunswick County Officials that   |
| ten offsite emergency sirens for Brunswick County were inoperable from 1444  |
| to 1503 on 03/07/00.  Alternate offsite notification mechanisms were         |
| available during this 19 minute period.                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36765       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 03/07/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 19:47[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        03/07/2000|
+------------------------------------------------+EVENT TIME:        14:22[PST]|
| NRC NOTIFIED BY:  BOB BROWNLEE                 |LAST UPDATE DATE:  03/07/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID LOVELESS       R4      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |THOMAS ESSIG         NMSS    |
|                                                |JOSEPH GIITTER       IRO     |
|                                                |BILL BEECHER         PAO     |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - NEWS RELEASE REGARDING THE RETRIEVAL OF BOXES OF RADIOACTIVE WASTE -       |
|                                                                              |
| The following news release was issued by the licensee to the general public  |
| at 1422 PST on 03/07/00 regarding the retrieval of boxes of radioactive      |
| waste that also may contain a hazardous substance:                           |
|                                                                              |
| "Energy Northwest retrieves low-level radioactive waste shipment - RICHLAND, |
| WA --                                                                        |
|                                                                              |
| Acting on its own initiative, Energy Northwest has retrieved four boxes of   |
| low-level radioactive waste from US Ecology Inc. because the boxes possibly  |
| also contain what is classified as a hazardous substance.  The combination   |
| of radioactive and hazardous wastes is considered mixed waste.  US Ecology   |
| operates the commercial low-level radioactive waste disposal site at         |
| Hanford.  US Ecology is not licensed to accept mixed waste.  Energy          |
| Northwest discovered this potential problem internally and notified US       |
| Ecology, the state departments of Health and Ecology, the Nuclear Regulatory |
| Commission and other interested parties.  Energy Northwest owns the          |
| Northwest's only commercial nuclear power plant, which produces enough       |
| electricity to serve a city the size of Seattle with power at a competitive  |
| price.  The plant is located about 10 miles north of Richland.  During the   |
| plant's last refueling outage, which ended in October, Energy Northwest used |
| a specialized process to clean and coat the interior of certain steam lines  |
| that had become somewhat corroded during 15 years of operation.  The pipe    |
| was cleaned with blasting grit that became slightly radioactive.  The grit   |
| and the corrosion deposits removed from the pipe are considered to be        |
| low-level waste.  Immediately after cleaning, a metal coating was sprayed    |
| onto the inside of the piping.  The spray was created by melting a           |
| nickel-chromium wire in an electrical arc, creating fine particles that      |
| coated the walls of the piping.  Some of these fine particles possibly mixed |
| with some of the used grit.  The nickel-chromium wire is made of materials   |
| very much like those used to make kitchen cookware.  However, under certain  |
| conditions nickel-chromium could be considered to be hazardous waste.  When  |
| the pipe cleaning-coating operation was under way, it wasn't clear to Energy |
| Northwest officials that the final waste could be classified as mixed waste. |
| In October, waste from the pipe operation was gathered and placed in four    |
| metal boxes, each four feet by four feet by six feet.  In December, the      |
| boxes were taken to the US Ecology disposal site on the Hanford Nuclear      |
| Reservation.  The US Ecology site is licensed for low-level radioactive      |
| waste, such as that from medical clinics.  In January, an Energy Northwest   |
| employee questioned whether the mixture of arc-spray residue and grit might  |
| possibly be classified as mixed waste, rather than low-level waste.  Energy  |
| Northwest then told US Ecology it would retrieve the boxes. The boxes had    |
| not yet been buried.  Energy Northwest retrieved the boxes in late February. |
| A plan to sample and analyze waste is being prepared.  The material will be  |
| tested to determine if the waste should be classified as mixed waste.  If    |
| not, the boxes will be returned to US Ecology.  If the waste is classified   |
| as mixed waste, Energy Northwest will explore other storage and disposal     |
| options."                                                                    |
|                                                                              |
| The licensee notified Washington State Officials and plan to notify the NRC  |
| Resident Inspector.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36766       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 03/07/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:33[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/07/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        02:32[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/07/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |ROGER LANKSBURY      R3      |
|  DOCKET:  0707001                              |THOMAS ESSIG         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - C-333A AUTOCLAVE WATER INVENTORY CONTROL SYSTEM PRIMARY CONDENSATE ALARM   |
| RECD -                                                                       |
|                                                                              |
| At 0232 CST on 03/07/00, the Plant Shift Superintendent (PSS) was notified   |
| that a primary condensate alarm was received on the C-333A Position 2 South  |
| autoclave Water Inventory Control (WIC) System. The WIC System is required   |
| to be operable while heating in Mode 5 according to TSR 2.2.4.2.  The        |
| autoclave was checked according to the alarm response procedure, removed     |
| from service, and the WIC System was declared inoperable by the PSS.         |
|                                                                              |
| Troubleshooting was Initiated and is continuing in order to determine the    |
| reason for the alarm.                                                        |
|                                                                              |
| The safety system actuation is reportable to the NRC as required by Safety   |
| Analysis Report, Section 6.9, Table 1, Criterion J.2, Safety System          |
| Actuation due to a valid signal as a 24-hour event notification.             |
|                                                                              |
| The NRC resident Inspector has been notified of this event.                  |
|                                                                              |
| PGDP Problem Report No, ATR-00-1340;  PGDP Event Report No, PAD-2000-020.    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36767       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/08/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 02:37[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/07/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:38[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/08/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |ROGER LANKSBURY      R3      |
|  DOCKET:  0707002                              |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KURT SISLER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BULLETIN 91-01 24 HOUR REPORT                                                |
|                                                                              |
| At 1038 hours on 3/7/00, was discovered that a 5 gallon bucket containing    |
| used, potentially contaminated oil was spaced less than 2 feet from another  |
| like container.  The two containers were 23 inches apart rather than the     |
| minimum 24 inches required by NCSA-PLANTO45.AO1 requirement #5.  This        |
| spacing violation constitutes the loss of one control of the double          |
| contingency principle.  The spacing violation was corrected at 1055 hours.   |
| A walk-down of the affected area verified that no other spacing issues       |
| exist.                                                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+