United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 1999

Event Notification Report for March 30, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/29/1999 - 03/30/1999

                              ** EVENT NUMBERS **

35400  35513  35517  35521  35522  35523  35524  35525  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35400       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 02/24/1999|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 19:19[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/24/1999|
+------------------------------------------------+EVENT TIME:        19:07[EST]|
| NRC NOTIFIED BY:  JIM BROOKS                   |LAST UPDATE DATE:  03/29/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD BARKLEY      R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TORUS WATER LEVEL DETERMINED TO BE OUTSIDE DESIGN BASIS DUE TO INSTRUMENT    |
| ERROR                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During the design installation of a more accurate narrow range torus level  |
| instrument, as part of our [basis for maintaining operations] process, it    |
| was identified that the current level indication was 1.5 inches lower than   |
| actual level.  Under these conditions we had the potential to be slightly    |
| outside the acceptable torus operating level band high.  At this time, we    |
| are within the Tech Spec limit but outside our administrative limit.  With   |
| the 1.5-inch discrepancy, it is likely that in the past we have unknowingly  |
| operated outside the Tech Spec limit for more than 24 hours.                 |
|                                                                              |
| "We don't feel that this is of a significant safety concern since even with  |
| the 1.5-inch error, the torus level would only have been approximately 1/2   |
| inch outside the Tech Spec limit.  This would still be greater than three    |
| feet below a level where emergency depressurization would be required by the |
| emergency operating procedures.                                              |
|                                                                              |
| "The new indication installed by the design process has been declared        |
| operable, and the instrument in error                                        |
| has been declared inoperable.  The plant has entered a 24-hour shutdown      |
| [limiting condition for operation (LCO)] for being outside our               |
| administrative limit as required by plant procedures.  Plans are in place to |
| lower torus water level to within administrative limits and exit the 24-hour |
| LCO."                                                                        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * RETRACTION 1011 3/29/1999 FROM SALTWELL TAKEN BY STRANSKY * * *        |
|                                                                              |
| "VY has been operating since its 05/98 outage with an administrative limit   |
| that credited in-place torus narrow-range level instrument uncertainties as  |
| <= 1.0 inches.  On 02/24/99, VY installed a new torus water level indication |
| system.  Upon energizing the new level indication system, it was noted that  |
| there existed a disparity between the in-place/operable level indication     |
| instrumentation and the new instrument.  The difference between the original |
| and operable level indication, and the newly installed instrument was        |
| approximately 1.5 inches.  It was believed at that time that the new         |
| instrument indication was very close to actual torus level.                  |
|                                                                              |
| "Upon observing the variance between the new and old indications, VY made    |
| the conservative determination that the new instrument was indicating actual |
| torus level, completed the necessary testing, declared the new system        |
| operable, and began controlling level based upon that indication.            |
|                                                                              |
| "It was concluded that the instrument uncertainty must have been             |
| significantly higher than the 1 inch credited for operation following the    |
| 05/98 outage, indicating up to 1.5 inches below actual level.  Were this     |
| true VY would have been operating with a torus water volume greater than     |
| allowed by its Technical Specifications for periods greater than those       |
| Technical Specifications allow.  It was further concluded that such          |
| operation may have invalidated the conclusions of several VY calculations    |
| and analyses which demonstrate the adequacy of the VY Primary Containment    |
| System.  VY therefore made an ENS notification for operation outside of the  |
| design basis of the plant.                                                   |
|                                                                              |
| "On 02/25/99, VY installed, and placed in service, a second high accuracy    |
| torus level indication instrument.  The two new instruments unexpectedly     |
| showed a 0.5 inch difference between one another.  The 1 inch administrative |
| margin to TS maximum and minimum levels were still in place; therefore,      |
| there was no immediate operability concern.                                  |
|                                                                              |
| "An evaluation was performed on 03/11/99 using temporary stand-pipes to      |
| determine the actual torus water level and thereby determine the accuracy of |
| the newly installed instrumentation.  That evaluation concluded that the     |
| first new instrument (activated on 02/24/99) had been consistently           |
| indicating approximately 0.5 inches higher than actual level.                |
|                                                                              |
| "This evaluation revealed that the report made on 02/24/99 was not required. |
| The actual instrument inaccuracy identified on 03/11/99 indicated that the   |
| administrative limits in place since the 05/98 outage accounted for all but  |
| 0.08 inches of the maximum error observed in the instrumentation used to     |
| control torus water volume.                                                  |
|                                                                              |
| "Plant operating logs taken since the 05/98 plant start up were reviewed.    |
| The logs show that VY operated consistent with its Technical                 |
| Specifications.                                                              |
|                                                                              |
| "The maximum error observed (0.08 inches) was evaluated in light of the      |
| analyses and calculations used to verify the adequacy of the Vermont Yankee  |
| Primary Containment.  In no case did this minor variance challenge the       |
| conclusions of any of the analyses/calculations.                             |
|                                                                              |
| "Therefore, it was concluded that the conditions were not inconsistent with  |
| the design bases of the VY plant, and the report made on 02/24/99 is being   |
| retracted."                                                                  |
|                                                                              |
| The licensee will inform the NRC resident inspector of this retraction.      |
| Notified R1DO (K. Modes).                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35513       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/25/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:16[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/25/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:03[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/29/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MELVYN LEACH         R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  J. B. HALCOMB                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALID ACTUATION OF A 'Q' SAFETY SYSTEM                                       |
|                                                                              |
| "At 1003 hours on March 25, 1999, during normal charging of cell 31-3-3      |
| prior to placing onstream, an Operations                                     |
| Front Line Manager was investigating a Cascade Automatic Data Processing     |
| smokehead alarm from this cell when a second smokehead alarmed.  He than saw |
| what appeared to be smoke above the Stage 6 area.                            |
|                                                                              |
| "All personnel in the area immediately evacuated, implemented the 'See &     |
| Flee' Procedure, activated the building recall system, and notified          |
| Emergency Response Forces.  The cell was taken offstream and cell pressure   |
| was reduced below atmosphere.                                                |
|                                                                              |
| "All airborne and surface contamination sample results were less than        |
| detectable and there was no release of                                       |
| Hazardous/Radioactive material or Radioactive/Radiological contamination     |
| exposure as a result of this event."                                         |
|                                                                              |
| The facility notified the NRC Resident Inspector and the DOE Site Manager.   |
|                                                                              |
| * * * UPDATE 1112 3/29/1999 FROM VANDERPOOL TAKEN BY STRANSKY * * *          |
|                                                                              |
| The original report was reissued with the following change to the third      |
| paragraph above:                                                             |
|                                                                              |
| "All airborne and surface contamination sample results were less than        |
| detectable, and there was no  Radioactive/Radiological contamination         |
| exposure as a result of this event."                                         |
|                                                                              |
| HOO notified R3DO (Ring).                                                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35517       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 03/27/1999|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 07:04[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/27/1999|
+------------------------------------------------+EVENT TIME:        06:05[EST]|
| NRC NOTIFIED BY:  ALAN RABENOLD                |LAST UPDATE DATE:  03/29/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RHR PUMP FAILS TO START                                                      |
|                                                                              |
| While attempting to place the unit onto RHR shutdown cooling, the 'A' RHR    |
| pump failed to start. The unit is currently in Condition 3 at 227F, and the |
| main condenser is being used to remove decay heat. The licensee suspects     |
| that the failure of the pump to start may be due to a problem with a pump    |
| interlock. The licensee is currently troubleshooting the pump.               |
|                                                                              |
| The licensee entered Technical Specification Action Statement 3.0.3 due to   |
| the unavailability of shutdown cooling loop 'A'. The unit was shut down      |
| overnight in order to commence a refueling outage. The licensee will inform  |
| the NRC resident inspector of this report.                                   |
|                                                                              |
| ***RETRACTION ON 03/29/99 AT 1603 ET BY S. SANFORD TAKEN BY MACKINNON***     |
|                                                                              |
| At 0704, an entry was made into Technical Specification 3.0.3 due to the 1   |
| hour action of not verifying that a second alternate decay heat removal      |
| system was available within the 1 hour.  A 1 hour non-emergency report was   |
| made to the NRC under 50.72 (b)(1)(I)(A), Tech Spec shutdown. The reactor    |
| was already shutdown, and this event is not reportable under this criterion. |
| This is in accordance with the guidance in NUREG 1022, Event Reporting       |
| Guidelines 10 CFR 50.72 and 50.73.                                           |
|                                                                              |
| The Technical Specification bases states that "it is also required to reduce |
| reactor temperature to the point where mode 4 is entered." This statement    |
| was incorrectly determined to apply to the requirements of a Decay Heat      |
| Removal  system.  The "it" in this case refers to the requirement of the     |
| required action A.3 to be in mode 4 within 24 hours.                         |
|                                                                              |
| Therefore, the action requirement to have TWO Alternate Decay Heat Removal   |
| methods to maintain or reduce temperature was met within the required time   |
| limit of 1 hour.  The entry into Technical Specification 3.0.3 was not       |
| required.                                                                    |
|                                                                              |
| The failure of RHR "A" to start was determined to be a faulty optical        |
| isolator in the suction path logic, which was replaced. The RHR "A"          |
| subsystem was restarted in the Shutdown Cooling mode, and Mode 4 was reached |
| at 1148 hours.  R3DO (Mark Ring) notified.                                   |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35521       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ILLINOIS DEPT OF NUCLEAR SAFETY      |NOTIFICATION DATE: 03/29/1999|
|LICENSEE:  PROVENA- ST JOSEPH MED CTR           |NOTIFICATION TIME: 08:57[EST]|
|    CITY:  JOLIET                   REGION:  3  |EVENT DATE:        03/25/1999|
|  COUNTY:                            STATE:  IL |EVENT TIME:             [CST]|
|LICENSE#:  IL-01326-01           AGREEMENT:  Y  |LAST UPDATE DATE:  03/29/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PATRICK HILAND       R3      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PATRICIA LARKINS (OSP)       |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| The following is a compilation of information sent to the Operations Center  |
| by the Office of State Programs:                                             |
|                                                                              |
| The RSO from the Provena-St. Joseph Medical Center reported that a decay     |
| error involving an HDR source resulted in a 31% underdose to three patients  |
| (53 year old female, 43 year old female, and 60 year old male). The apparent |
| cause was the use of the certificate activity instead of the current         |
| activity for the dose planning.  The device was a Nucletron Microselectron   |
| HDR with an Ir-192 source.  The source had recently been replaced by         |
| Nucletron.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35522       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 03/29/1999|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 11:35[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/29/1999|
+------------------------------------------------+EVENT TIME:        08:37[EST]|
| NRC NOTIFIED BY:  MARK SCHALL                  |LAST UPDATE DATE:  03/29/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       97       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE TRIP/REACTOR SCRAM DUE TO SPURIOUS HIGH VIBRATION SIGNAL   |
|                                                                              |
| The unit received an automatic turbine trip/reactor scram due to a suspected |
| spurious turbine high vibration signal. Following the scram, all control     |
| rods inserted, and all systems functioned as expected. Two safety/relief     |
| valves lifted but immediately reseated. Primary Containment Isolation System |
| (PCIS) Group 2 (drywell equipment and floor drains, TIP, radwaste, and       |
| process sampling), 6 (containment atmosphere and post-accident sampling),    |
| and 8 (RHR shutdown cooling) isolations occurred due to reactor vessel water |
| level shrinkage following the scram.  Reactor vessel water level recovered   |
| shortly after the scram.                                                     |
|                                                                              |
| The licensee is currently investigating the cause of the turbine vibration   |
| signal. The NRC resident inspector has been informed of this event by the    |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35523       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLORIDA BUREAU OF RADIATION CONTROL  |NOTIFICATION DATE: 03/29/1999|
|LICENSEE:  H.W. LOCHNER                         |NOTIFICATION TIME: 12:45[EST]|
|    CITY:  CLEARWATER               REGION:  2  |EVENT DATE:        03/29/1999|
|  COUNTY:                            STATE:  FL |EVENT TIME:             [EST]|
|LICENSE#:  2333-1                AGREEMENT:  Y  |LAST UPDATE DATE:  03/29/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK LESSER          R2      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLES ADAMS                |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - AGREEMENT STATE REPORT - TROXLER MOISTURE DENSITY GAUGE RUN OVER -         |
|                                                                              |
| While taking a measurement, a Troxler #3440 gauge (serial number 029358) was |
| run over by a dump truck.  The handle was broken off, and the source could   |
| not be retracted into the case.  The source was extended approximately 12    |
| inches.  Investigators responded and put a pig over the source and           |
| transported the gauge to the state environmental lab.  The gauge was placed  |
| in the Radioactive Activity Material storage facility until the owner can    |
| get a special shipping case from Troxler:  to return the gauge for repair.   |
| Any further actions are referred to Materials Licensing.  The licensee is    |
| the H. W. Lochner facility is located in Clearwater, Florida.                |
|                                                                              |
| Troxler Model #3440 contains 8 mCi of Cesium-137 and 40 mCi of               |
| Americium-241/Beryllium.                                                     |
|                                                                              |
| Call the NRC Operations Officer for contact numbers.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35524       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COGEMA MINING, INC.                  |NOTIFICATION DATE: 03/29/1999|
|LICENSEE:  COGEMA MINING, INC.                  |NOTIFICATION TIME: 16:15[EST]|
|    CITY:  Linch                    REGION:  4  |EVENT DATE:        03/26/1999|
|  COUNTY:  Campbell                  STATE:  WY |EVENT TIME:        12:00[MST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  03/29/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA HOWELL         R4      |
|                                                |SCOTT MOORE          NMSS    |
+------------------------------------------------+JOE HOLONICH         NMSS    |
| NRC NOTIFIED BY:  JOHN VASELIN                 |JOHN MORRIS          DOE     |
|  HQ OPS OFFICER:  JOHN MacKINNON               |M. ROBERTSON, NRC    EPA     |
+------------------------------------------------+G. BICKERTON         USDA    |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SPILLED 60,918 GALLONS OF WATER CONTAINING 1.0 mg/l OF URANIUM ON 03/26/99   |
| AND SPILLED 23,520 GALLONS OF WATER CONTAINING LESS THAN 0.4 mg/l OF URANIUM |
| ON 03/29/99                                                                  |
|                                                                              |
| This event was called in under as a 48 hour report per Cogema Mining, Inc.,  |
| license.                                                                     |
|                                                                              |
| Two spills of injection mining solution recently occurred at the Christensen |
| Mine in Campbell County Wyoming. Both spills were located in Mine Unit 3     |
| which is currently in restoration and resulted from plumbing failures.  The  |
| following data summarizes the spills:                                        |
|                                                                              |
| Date                                  Location                               |
| Estimated                        Uranium                                     |
| Gallons                                mg/l                                  |
|                                                                              |
| 03/26/99                           Well H17-1                         60,918 |
| 1.0                                                                          |
|                                                                              |
| 03/29/99                             Module bldg 3-1              23,520     |
| <0.4                                                                         |
|                                                                              |
| For purposes of reporting spills, the NRC license considers any spill of     |
| 10,000 gallons of more to be significant from an operations standpoint,      |
| regardless of the chemical and radioactive characteristics of the spill.     |
| Therefore, both spills are reported.                                         |
|                                                                              |
| Health and Environmental Hazards:   None expected.  The solution does not    |
| pose a health or environmental hazard and did not leave the NRC permitted    |
| area.  Note that the nearest community is Linch, Wyoming, approximately 15   |
| miles to the southwest.                                                      |
|                                                                              |
| Corrective Actions:    Well H17-1:  Well was shut down until the plumbing    |
| failure can be repaired.                                                     |
| Available spill solution is being recovered.                                 |
|                                                                              |
| Module building 3-1:  The plumbing failure was repaired and flow is back on  |
| line.                                                                        |
|                                                                              |
| Soil samples have been collected at both spill locations and will be         |
| analyzed for Ra-226 to determine if soil clean-up is needed.                 |
|                                                                              |
| Written Notification:  A written notification giving further details will be |
| submitted to the NRC Uranium Recovery  Branch Chief within 7 days.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35525       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 03/29/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 20:22[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/29/1999|
+------------------------------------------------+EVENT TIME:        18:01[EST]|
| NRC NOTIFIED BY:  TOM COTTER                   |LAST UPDATE DATE:  03/29/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KATHLEEN MODES       R1      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |FRANK CONGEL         IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PARTIAL LOSS OF POWER DUE TO 4.10KV BUS UNIT STATION SERVICE TRANSFORMER     |
| SUPPLY OVERCURRENT TRIP. EMERGENCY DIESEL GENERATOR 2-1 SUPPLYING POWER TO   |
| VITAL BUS "AE".                                                              |
|                                                                              |
| At 1801 hours, "4160V Bus Unit Station Service Transformer Supply            |
| Overcurrent Trip" alarm was received. This alarm indicates that the supply   |
| breaker, 42C, to the normal 4kV bus "2A" opened and deenergized the bus. The |
| "2A" bus supplies train "A" emergency 4kV bus "AE" so it also deenergized.   |
| The emergency diesel generator 2-1 started and reenergized the "AE"          |
| emergency bus.  The "B" train of electrical power and safeguards equipment   |
| remained fully operable, the emergency diesel generator is fully operable if |
| needed.  Prior to the overcurrent trip, the plant was in mode 5 (cold        |
| shutdown) with Reactor Coolant System temperature at 97F and 280 psig.      |
| Their was no interruption to core cooling during the event.  Core cooling    |
| was being provided by the "B" train of the residual heat removal system and  |
| was unaffected.  Both trains of residual heat removal remain operable.  The  |
| site maintenance department is evaluating the cause for the relay protection |
| actuation.  The 2-1 emergency diesel generator will continue to supply the   |
| emergency bus until this investigation is completed and normal power is      |
| restored.  The vital buses cannot be cross connected and emergency diesel    |
| generator 2-1 has plenty of fuel to keep it operating.   Spent fuel pool     |
| cooling was not lost.                                                        |
|                                                                              |
| Offsite power is stable, and the other emergency bus "2DF" can supply enough |
| electrical power to safe plant operation while shutdown if electrical power  |
| is lost from emergency bus "2AE".                                            |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+