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Event Notification Report for September 13, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/10/1999 - 09/13/1999

                              ** EVENT NUMBERS **

35688  36110  36143  36144  36145  36146  36147  36148  36149  36150  

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35688       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  USAF RADIOISOTOPE COMMITTEE          |NOTIFICATION DATE: 05/07/1999|
|LICENSEE:  USAF RADIOISOTOPE COMMITTEE          |NOTIFICATION TIME: 10:45[EDT]|
|    CITY:  Sumptor                  REGION:  2  |EVENT DATE:        05/07/1999|
|  COUNTY:                            STATE:  SC |EVENT TIME:        09:38[EDT]|
|LICENSE#:  42-23539-01AF         AGREEMENT:  Y  |LAST UPDATE DATE:  09/10/1999|
|  DOCKET:  03028641                             |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHRIS CHRISTENSEN    R2      |
|                                                |BILL JONES           R4      |
+------------------------------------------------+DON COOL             NMSS    |
| NRC NOTIFIED BY:  MAJOR JAMES HICKS            |FRANK CONGEL         IRO     |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A MISSING CHEMICAL AGENT MONITOR CONTAINING 15 mCi OF NICKEL-63 |
| FROM SHAW AIR FORCE BASE LOCATED IN SUMTER, SOUTH CAROLINA                   |
|                                                                              |
| At 0938 on 05/07/99, Shaw Air Force Base (AFB) located in Sumter, South      |
| Carolina, notified the U.S. Air Force Radioisotope Committee located at      |
| Bolling AFB located in Washington D.C. of a missing chemical agent monitor   |
| (CAM) containing a 15-mCi nickel-63 source.                                  |
|                                                                              |
| On 04/27/99, the base radiation safety officer (RSO) at Shaw AFB conducted   |
| an inventory of CAMs located in building #1981.  The correct number of CAMs  |
| were there, but one had the wrong serial number.  Examination of previous    |
| inventories shows one CAM with a different serial number.  The building had  |
| been searched with no success.  The 20CES/CEX RSO has no explanation for the |
| different serial number on one CAM or where the correct CAM may be located.  |
|                                                                              |
|                                                                              |
| It is suspected that the CAM may have been exchanged with another Air Force  |
| Unit or may have been sent off for calibration.  At this time, the U.S. Air  |
| Force Radioisotope Committee believes that the CAM is still in Air Force     |
| possession.  Past shipping records will be researched, and calibration labs  |
| that serve Shaw AFB will be notified.  The completion time for these actions |
| is currently estimated to be 06/07/99.                                       |
|                                                                              |
| Call the NRC Operations Officer for a licensee contact telephone number.     |
|                                                                              |
| The licensee plans to notify the NRC Region 4 office and plans to issue a    |
| 30-day written report.                                                       |
|                                                                              |
| *** UPDATE ON 6/11/99 @ 1242 BY HICKS TO GOULD ***  INTERIM REPORT           |
|                                                                              |
| MISSING CAM SERIAL NUMBER:  CAN-C-04646                                      |
|                                                                              |
| RADIOACTIVITY MATERIAL CONTAINED: 10 mCi OF Ni-63                            |
|                                                                              |
| ACTIVITY: 0.05 Ci                                                            |
|                                                                              |
| CHEMICAL AND PHYSICAL FORM: SOLID                                            |
|                                                                              |
| A SERIAL NUMBER DISCREPANCY WAS NOTED DURING A SEMIANNUAL CAM INVENTORY      |
| CONDUCTED 4/27/99.  THE PREVIOUS INVENTORY CONDUCTED 10/98 INDICATED NO      |
| DISCREPANCIES.                                                               |
|                                                                              |
| A DISPOSITION, OR PROBABLE DISPOSITION, OF THE MATERIAL IS UNDETERMINABLE.   |
|                                                                              |
| THERE EXISTS THE POSSIBILITY THAT CALIBRATION SERVICES MAY HAVE SWAPPED OUT  |
| THE CAM WITH ANOTHER MONITOR.  ALSO, A POLICE INVESTIGATION MAY BE REQUIRED  |
| SINCE THE DEVICE IS WORTH OVER $3,000.00.                                    |
|                                                                              |
| NOTIFIED REG 2 RDO(BONSER), REG 4 RDO(ANDREWS), AND NMSS EO(COOL).           |
|                                                                              |
| *** UPDATE ON 9/10/99 AT 1316 FROM HICKS (FAX) TO POERTNER ***               |
|                                                                              |
| The investigative officer concluded a one-for-one swap out of a CAM must     |
| have occurred.  There is no supporting documentation, but numerically this   |
| unit is in possession of 5 CAMS which is consistent with the quantity always |
| on hand.  They believe the CAM was exchanged with one belonging to a unit    |
| deployed overseas.  The investigation is closed.                             |
|                                                                              |
| Notified R4DO (SANBORN), R2DO (HAAG), and NMSS (PICCONE).                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36110       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 09/01/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 11:57[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        08/31/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:00[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/10/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |DAVID HILLS          R3      |
|  DOCKET:  0707002                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOE HALCOMB                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MICROFILTRATION SYSTEM pH PROBES DISCOVERED TO BE OUT OF TOLERANCE           |
|                                                                              |
| "On 8/31/99 at 1200 hrs, the Plant Shift Superintendent was notified that a  |
| previously discovered X-705 Microfiltration System (MFS) pH probe out of     |
| tolerance condition likely existed during a time period when the MFS was in  |
| operation. The out of tolerance condition was in a non-conservative          |
| direction and previously discovered during a routine weekly surveillance on  |
| 8/27/99. An evaluation to determine the condition existed while the MFS was  |
| in operation was initiated at that time. Engineering suspected that the      |
| probe calibration may have been affected when the probes were exposed to a   |
| high pH solution on 8/23/99. Subsequent discussion with the probe            |
| manufacturer confirmed that a high pH solution could affect probe            |
| calibration. As a result, it was concluded that the out of tolerance         |
| condition likely existed from approximately 8/23/99 to 8/27/99.              |
|                                                                              |
| "The out of tolerance condition affected 2 of the 3 pH probes (2 out of 3    |
| logic required to activate the safety system). The as found data for the 2   |
| probes indicated they would actuate at 6.73 pH and 6.65 pH, which is below   |
| the 7 pH required setpoint. A review of the MFS operational history          |
| indicated that the MFS pH was maintained above a 7 pH during the time the    |
| probes are suspected to have been out of tolerance."                         |
|                                                                              |
| The NRC resident inspector has been informed of this notification.           |
|                                                                              |
| *** RETRACTION AT 1145 EDT ON 9/10/99 FROM SPAETH TO POERTNER ***            |
|                                                                              |
| Based on completion of Engineering Evaluation EVAL-PS-1999-0523, the plant   |
| has determined that the pH probes were out of tolerance in a conservative    |
| direction and therefore would have actuated earlier than required.           |
|                                                                              |
| The NRC resident inspector has been notified.                                |
|                                                                              |
| Notified R3DO (Phillips), and NMSS (Piccone).                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36143       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 09/10/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 11:39[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/09/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        15:00[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/10/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707002                              |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  WILLIAM POERTNER             |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM HORN INOPERABLE DUE TO IMPROPER            |
| CONNECTION                                                                   |
|                                                                              |
| At 1500 hours, on 9/9/99, the Criticality Accident Alarm System (CAAS) slave |
| horn in the X-344B building was discovered to be not connected to the X-344A |
| CAAS evacuation alarm as designed.  During troubleshooting activities,       |
| maintenance personnel found that the horn was connected to the gas release   |
| alarm system instead of the CAAS evacuation horn system.                     |
|                                                                              |
| This condition is reportable to the NRC per 10CFR76.120(c) "Safety Equipment |
| Failure/Actuation", the equipment is required by a TSR to be available and   |
| operable and no redundant equipment is available and operable to perform the |
| required safety function.                                                    |
|                                                                              |
| There was no loss of hazardous material or radioactive/radiological          |
| contamination exposure as a result of this event.                            |
|                                                                              |
| The NRC resident inspector has been notified.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36144       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 09/10/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 12:01[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        09/10/1999|
+------------------------------------------------+EVENT TIME:        08:13[EDT]|
| NRC NOTIFIED BY:  PETER ABBOTT                 |LAST UPDATE DATE:  09/10/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM MOSLAK           R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM INOPERABLE DUE TO INOPERABLE   |
| TRIP MODULE.                                                                 |
|                                                                              |
| During routine High Pressure Coolant Injection (HPCI) system temperature     |
| isolation logic testing, an isolation trip module was found to be            |
| inoperable.  Per Technical Specification requirements, the HPCI system steam |
| supply primary containment isolation outboard valves must be closed within   |
| four hours.  This renders the HPCI system inoperable.  The isolation valves  |
| were closed and deactivated at 1153 EDT.                                     |
|                                                                              |
| The NRC resident inspector has been notified.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36145       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 09/10/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 14:53[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        09/10/1999|
+------------------------------------------------+EVENT TIME:        14:00[EDT]|
| NRC NOTIFIED BY:  MICHAEL TESORIERO            |LAST UPDATE DATE:  09/10/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM MOSLAK           R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       87       Power Operation  |86       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
|  PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO PINHOLE LEAK IN  |
| THE ESSENTIAL SERVICE WATER SYSTEM.                                          |
|                                                                              |
| At approximately 1400 hours on September 10, 1999, a plant shutdown was      |
| commenced as scheduled to enter a refueling outage. The ENS notification is  |
| being made because a portion of the Essential Service Water (SW) header was  |
| declared inoperable at approximately 1215 hours.  A pinhole leak on 18 inch  |
| SW pipe number 408 was evaluated using the guidance of Generic Letter 90-05  |
| and it was determined that the SW pipe could not be declared operable using  |
| the criteria provided in the Generic Letter. Concurrent with the planned     |
| shutdown, Technical Specification 3.3.F.2 requires the reactor be brought to |
| the cold shutdown condition starting no later than 12 hours after the SW     |
| pipe was declared inoperable. The SW pipe will be repaired prior to plant    |
| startup.                                                                     |
|                                                                              |
| The SW pipe leak is located outside containment and can not be isolated for  |
| repairs until the plant is in cold shutdown. The SW pipe supplies the        |
| containment Fan Cooler units which are required by Technical Specifications. |
| The leak rate is I to 2 drops per minute.                                    |
|                                                                              |
| The NRC resident inspector has been notified.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36146       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 09/10/1999|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 21:27[EDT]|
|   RXTYPE: [3] CE                               |EVENT DATE:        09/10/1999|
+------------------------------------------------+EVENT TIME:        19:58[CDT]|
| NRC NOTIFIED BY:  NEAL BERNARD                 |LAST UPDATE DATE:  09/10/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP AND FEEDWATER ACTUATION DUE TO RCP 2B SEAL FAILURE.      |
|                                                                              |
| The licensee performed a manual reactor trip due to failure of the Reactor   |
| Coolant Pump 2B seals.  Emergency feedwater actuated following the trip.     |
| All control rods fully inserted.  No relief valves or safety valves opened   |
| and excess energy is being released via steam to the main condenser.  RCP 2B |
| was secured following the trip.  RCP 2B seal pressures are significantly     |
| lower than normal and seal leakoff flow is also low.  The plant is in hot    |
| standby and stable.  The licensee plans to go to cold shutdown to repair the |
| RCP.                                                                         |
|                                                                              |
| The NRC resident was notified.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36147       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 09/11/1999|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 06:00[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        09/11/1999|
+------------------------------------------------+EVENT TIME:        03:01[CDT]|
| NRC NOTIFIED BY:  FRED VANBUSKERK              |LAST UPDATE DATE:  09/11/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY FEEDWATER AUTO STARTED ON TRIPPING OF ALL REACTOR COOLANT PUMPS    |
|                                                                              |
| "During a planned shutdown for refueling, while securing 2 of 4 Reactor      |
| Coolant Pumps (RCP), 'D' Reactor Coolant Pump experienced reverse rotation   |
| when it was secured.  In this condition, the Abnormal Operating Procedure    |
| directs operators to stop all RCPs.  In response to the loss of all 4 RCPs,  |
| the Emergency Feedwater (EFW) System auto-actuated, as expected, and Natural |
| Circulation Cooling initiated.                                               |
|                                                                              |
| "Natural Circulation Cooling is in progress. All systems responded normally  |
| to this event.                                                               |
|                                                                              |
| "The current plan is to install a restraining device to prevent 'D' RCP      |
| rotation and then reestablish forced-flow cooling with two operable RCPs     |
| (one per loop)."                                                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36148       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 09/12/1999|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 06:31[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/12/1999|
+------------------------------------------------+EVENT TIME:        03:44[CDT]|
| NRC NOTIFIED BY:  GREG JANAK                   |LAST UPDATE DATE:  09/12/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DURING TURBINE TRIP SYSTEM TESTING                    |
|                                                                              |
| During the performance of Main Turbine Emergency Trip System testing on      |
| Channel 1, the plant experienced an automatic turbine trip which initiated a |
| reactor trip.  All control rods fully inserted and systems responded as      |
| expected including the start of the Auxiliary Feedwater System, an           |
| Engineered Safety Feature system.  No relief valves or safety valves opened  |
| and excess energy is being released via steam to the main condensers.  The   |
| licensee is investigating exact cause of trip.                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36149       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 09/12/1999|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 09:30[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        09/12/1999|
+------------------------------------------------+EVENT TIME:        09:04[EDT]|
| NRC NOTIFIED BY:  VICKY HARTE                  |LAST UPDATE DATE:  09/12/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|10 CFR SECTION:                                 |                             |
|AENS 50.72(b)(1)(v)      ENS INOPERABLE         |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       60       Power Operation  |60       Power Operation  |
|2     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST SAFETY PARAMETER DISPLAY SYSTEM AND THE TECHNICAL SUPPORT CENTER        |
| COMPUTER                                                                     |
|                                                                              |
| Power was lost  to the Safety Parameter Display System (SPDS) and the        |
| Technical Support Center (TSC) computer system at 0904 EDT on 9/12/99.  The  |
| bus supplying power to the battery charger for the SPDS and TSC computer was |
| lost when the supply breaker opened on a ground detection, on the            |
| underground cable supply.  The normal alternate power supply to the battery  |
| charger was previously lost, some time ago, due to another ground on its     |
| underground cable supply.  The licensee made the decision to preserve the    |
| battery and deenergized the battery bus.  Also, with the TSC computer system |
| out-of-service, the control room will serve as the alternate TSC facility.   |
|                                                                              |
| This event is a major loss of emergency  assessment capability and is        |
| reportable.  Troubleshooting and repairs to the electrical distribution      |
| system are in progress.  Also, the licensee is investigating an alternate    |
| methods to power the battery charger.                                        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36150       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 09/12/1999|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 16:17[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        09/12/1999|
+------------------------------------------------+EVENT TIME:        15:30[EDT]|
| NRC NOTIFIED BY:  RICHARD TRUAX                |LAST UPDATE DATE:  09/13/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM MOSLAK           R1      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       85       Power Operation  |85       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE TSC DUE TO BREAKER FAILURE.                             |
|                                                                              |
| During planned electrical switching at the Unit 1 training center a breaker  |
| failed to close causing a loss of power to the Unit 1 training center which  |
| provides power to the Technical Support Center (TSC).  This resulted in a    |
| loss of assessment capability from the TSC .  Assessment capability is still |
| available from the main control room and Emergency Operation Facility.       |
|                                                                              |
| The licensee is investigating the cause of the breaker failure.              |
|                                                                              |
| The NRC resident will be notified.                                           |
|                                                                              |
| * * * UPDATE AT 0155 EDT ON 9/13/99 BY ED EILOLA TO FANGIE JONES * * *       |
|                                                                              |
| Repairs were made and power was restored to the TSC at 0145 EDT on 9/13/99.  |
| The licensee intends to notify the NRC Resident Inspector.  The NRC          |
| operations officer notified the R1DO (Tom Moslak).                           |
+------------------------------------------------------------------------------+