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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35173 |
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+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
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