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). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021