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Event Notification Report for January 11, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/08/1999 - 01/11/1999

                              ** EVENT NUMBERS **

35173  35228  35229  35230  35231  35232  35233  35234  35235  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35173       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 12/18/1998|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 22:42[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/18/1998|
+------------------------------------------------+EVENT TIME:        18:00[PST]|
| NRC NOTIFIED BY:  JOY SKAGGS                   |LAST UPDATE DATE:  01/08/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |IAN BARNES           R4      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RCS PRESSURE BOUNDARY LEAKAGE DISCOVERED                                     |
|                                                                              |
| "On 12/17/98, at 0611 hours, Unit 1 was placed in Hot Standby in order to    |
| perform repairs on a lube oil cooler for Reactor Coolant Pump ( RCP) 1-3. On |
| 12/18/98, during routine inspections of the work area, a buildup of boric    |
| acid was discovered. At 1800 hours on 12/18/98, the source of the boric acid |
| was determined to be RCS leakage from the lower radial bearing RTD           |
| thermowell on RCP 1-3. In addition, the leakage was determined to be RCS     |
| pressure boundary leakage. In accordance with plant Technical                |
| Specifications, preparations are being made to place the Unit in Cold        |
| Shutdown. The magnitude of the leakage is significantly less than 1 gpm."    |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
|                                                                              |
| ******************* UPDATE AT 1649 ON 1/8/99, BY PIERCE, TAKEN BY WEAVER     |
| *****************************                                                |
|                                                                              |
| PG&E has concluded this event is not reportable and retracts the 50.72       |
| report. The basis for retracting this report is that the leakage has been    |
| confirmed to NOT be pressure boundary leakage. The leakage was due to a      |
| loose instrument fitting which is not indicative of an impending gross       |
| failure of the pressure boundary. Furthermore, the boric acid residue was    |
| removed from components in the vicinity and the effects on carbon steel      |
| components was evaluated. The boric acid had not seriously degraded          |
| components or left components in an unanalyzed condition that could          |
| significantly compromise plant safety.                                       |
|                                                                              |
| The licensee will inform the NRC resident inspector.  The Operations Center  |
| notified the R4DO (Harrell).                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35228       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 01/07/1999|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 16:44[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/07/1999|
+------------------------------------------------+EVENT TIME:        16:28[EST]|
| NRC NOTIFIED BY:  TOM TYNAN                    |LAST UPDATE DATE:  01/08/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEN WERT             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       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FTS AND COMMERCIAL PHONE LINES OUT OF SERVICE                                |
|                                                                              |
| The licensee notified the NRC via cellular phone that both their FTS-2000    |
| and their commercial lines were unavailable for dial out.   However, the     |
| commercial lines could be accessed by dialing in from the Operations Center. |
| The licensee is troubleshooting this problem and believes it may be related  |
| to some other work (digging) in progress.                                    |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE 0153 1/8/99 FROM SHFLIGER TAKEN BY STRANSKY * * *               |
|                                                                              |
| All telephones are now working properly.  The NRC resident inspector will be |
| informed by the licensee.  Notified R2DO (Wert).                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35229       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STATE OF LOUSIANA                    |NOTIFICATION DATE: 01/08/1999|
|LICENSEE:  EAST JEFF GENERAL HOSPITAL           |NOTIFICATION TIME: 09:48[EST]|
|    CITY:  NEW ORLEANS              REGION:  4  |EVENT DATE:        01/08/1999|
|  COUNTY:                            STATE:  LA |EVENT TIME:             [CST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  01/08/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PHIL HARRELL         R4      |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOE NOBLE                    |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| While changing sources in a high dose rate afterloader, the source became    |
| disconnected from the drive cable.  The afterloader device is located in a   |
| shielded room.  The licensee has contacted the vendor to retrieve the        |
| source. No further details were provided.  A representative of the state is  |
| responding to the site.                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35230       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 01/08/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 10:43[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/08/1999|
+------------------------------------------------+EVENT TIME:        08:52[CST]|
| NRC NOTIFIED BY:  MATHER                       |LAST UPDATE DATE:  01/08/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| AUTO START OF THE #11 TURBINE DRIVEN AUX FEED PUMP.                          |
|                                                                              |
| WHILE TESTING OF THE #11 REACTOR COOLANT PUMP BREAKER WAS IN PROGRESS ON     |
| 4.16KV BUS 11, AN INADVERTENT UNDERVOLTAGE OCCURRED ON BUS 12 CAUSING TRIP   |
| OF REACTOR COOLANT PUMP (RCP) 12, PUTTING THE PLANT IN A SECOND LCO FOR      |
| HAVING TWO RCPS OUT OF SERVICE.  THIS RESULTED IN THE INITIATING SIGNAL FOR  |
| THE AUTO START OF THE # 11 TURBINE DRIVEN AUX FEEDWATER PUMP.  THE #11       |
| TURBINE DRIVEN AUX FEED PUMP WAS SECURED WHEN THE UNDERVOLTAGE SIGNAL WAS    |
| CLEARED ON BUS 12 AND #12 REACTOR COOLANT PUMP WAS RESTARTED, AT WHICH TIME  |
| THEY EXITED THE SECOND LCO.  THE CAUSE OF THIS EVENT IS BEING INVESTIGATED.  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35231       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 01/08/1999|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 11:28[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/08/1999|
+------------------------------------------------+EVENT TIME:        10:35[EST]|
| NRC NOTIFIED BY:  M. MAGNUSON                  |LAST UPDATE DATE:  01/08/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RHR SERVICE WATER PUMPS MAY NOT HAVE ADEQUATE NPSH                           |
|                                                                              |
|                                                                              |
| A review of calculation VYC-990, R4 shows that inadequate NPSH exists for    |
| RHR Service Water (RHRSW) pumps.  VYC-990, R4 may not have conservatively    |
| taken into account pump and system parameters, resulting in a condition of   |
| being outside the design basis of the plant for the RHRSW system.            |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35232       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ST. VINCENT'S MEDICAL CENTER         |NOTIFICATION DATE: 01/08/1999|
|LICENSEE:  ST. VINCENT'S MEDICAL CENTER         |NOTIFICATION TIME: 13:50[EST]|
|    CITY:  BRIDGEPORT               REGION:  1  |EVENT DATE:        01/08/1999|
|  COUNTY:                            STATE:  CT |EVENT TIME:        12:00[EST]|
|LICENSE#:  06-00843-03           AGREEMENT:  N  |LAST UPDATE DATE:  01/08/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM COOK         R1      |
|                                                |DR. COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT LANGE                 |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL PERSONNEL OVEREXPOSURE                                             |
|                                                                              |
| A radiation oncology technologist's film badge recorded a dose of 19,490 mR  |
| for the month of November.  The results were provided to the licensee on     |
| 12/18/98.  The licensee requested confirmation of the results and the        |
| confirmation was received today, 1/8/99.                                     |
|                                                                              |
| The licensee does not believe the technologist actually received this dosage |
| based on an interview with the employee.  The employee denies being present  |
| during any treatments that could have resulted in the dose.  The employee    |
| provided a blood sample and it was found to be normal.                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35233       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON                    REGION:  3  |NOTIFICATION DATE: 01/08/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 15:00[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/08/1999|
+------------------------------------------------+EVENT TIME:        13:41[CST]|
| NRC NOTIFIED BY:  LARRY BUNNER                 |LAST UPDATE DATE:  01/08/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|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  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN                                    |
|                                                                              |
| "During testing of the 'A' train of the solid state protection system, the   |
| Reactor Trip breaker 'A' failed to function normally and was declared        |
| inoperable.  Technical specifications require the unit to be placed in Mode  |
| 3 (shutdown condition) within 6 hours.  At 1341 the ramp was initiated to    |
| decrease reactor power to mode 3."                                           |
|                                                                              |
| Technical Specifications allow six hours to reach mode 3.  The six hour      |
| clock started at 1224.  No other equipment is out of service that will       |
| impact the plant shutdown.  The licensee notified the NRC resident           |
| inspector.                                                                   |
|                                                                              |
|                                                                              |
| ***************************** UPDATE AT 1707 ON 1/8/99, BY BUNNER TAKEN BY   |
| WEAVER *****************                                                     |
|                                                                              |
| The licensee repaired and completed testing the breaker at 1555.  Power had  |
| been reduced to 54% and is now increasing.  The Tech Spec LCO action         |
| statement has been exited.  The licensee will inform the NRC resident        |
| inspector.  The HOO notified the R3DO (Clayton).                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35234       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 01/08/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:17[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/08/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        12:30[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/08/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRENT CLAYTON        R3      |
|  DOCKET:  0707002                              |SUSAN SHANKMAN       NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRD     |
| NRC NOTIFIED BY:  KURT SISLER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BULLETIN 91-01 FOUR HOUR REPORT                                              |
|                                                                              |
| "On January 8. 1999, at 1230 hours it was discovered that no Nuclear         |
| Criticality Safety Approval (NCSA) was in place for the X-326 Evacuation     |
| Booster Station.  The Evacuation Booster Station has been abandoned in place |
| for more than twenty years.  A UF6 negative was obtained on this equipment   |
| before it was isolated from the rest of the X-326 cascade equipment.         |
| Applied Nuclear Technology (ANTS) is analyzing to determine if greater than  |
| 15 grams of U235 is present.                                                 |
|                                                                              |
| "This event is being reported under criticality control (Bulletin 91-01)     |
| 4-hour due to the potential that abandoned equipment contains more than 15   |
| grams U235 requiring NCSA per Technical Safety Requirement 3.11.2."          |
|                                                                              |
| The NRC resident inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35235       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 01/09/1999|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 21:55[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/09/1999|
+------------------------------------------------+EVENT TIME:        20:58[EST]|
| NRC NOTIFIED BY:  JOHN THOMAS                  |LAST UPDATE DATE:  01/09/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF EMERGENCY SIREN CAPABILITY                                           |
|                                                                              |
| "At 1905, the control room received notification from the Beaver County      |
| Emergency Management Agency that the siren activation computer was beeping,  |
| but not displaying any other indication of a fault.  The system is designed  |
| to auto-dial the control room and play a pre-recorded message when it        |
| detects a fault.  That message was not activated.  Operations personnel      |
| called out Telecommunications to investigate the siren computer status, but  |
| based on indications available, the sirens were believed to be operable.     |
|                                                                              |
| "At 2058, telecommunications personnel reported that the siren activation    |
| system had a loss of communication between the activation computer and the   |
| radio transmitter, which might have prevented the sirens from functioning    |
| properly if needed. This failure constitutes a loss of a significant portion |
| of the Emergency Notification System.                                        |
|                                                                              |
| "At 2106, telecommunications personnel reported they had been successful in  |
| resetting the computer communication module and had tested the system        |
| satisfactorily. The siren activation system is currently operable."          |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
+------------------------------------------------------------------------------+