U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/17/2003 - 01/21/2003
** EVENT NUMBERS **
39508 39519 39520 39521 39522 39523 39525 39526
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39508 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OK DEQ RAD MANAGEMENT |NOTIFICATION DATE: 01/14/2003|
|LICENSEE: ST FRANCIS HOSPITAL |NOTIFICATION TIME: 15:02[EST]|
| CITY: TULSA REGION: 4 |EVENT DATE: 01/13/2003|
| COUNTY: STATE: OK |EVENT TIME: 19:30[CST]|
|LICENSE#: OK-07163-01 AGREEMENT: Y |LAST UPDATE DATE: 01/15/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MIKE BRODERICK | |
| HQ OPS OFFICER: JASON FLEMMING | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING LOST SOURCES |
| |
| The Licensee reported the loss of five 0.355 microcurie, I-125 brachytherapy |
| seeds. The seeds were model # IAI-125A and they were inventoried upon |
| receipt from the manufacturer, Iso-Aid. The seeds were being washed prior |
| to sterilization (this is a deviation from procedure) and the licensee |
| believes they were washed down the drain to the public sewer system. The |
| Licensee reports that surveys do not indicate that they are in the sink or |
| trap. |
| |
| ***UPDATE 01/15/03 1202 EST MIKE BRODERICK TO MIKE NORRIS*** |
| |
| The seeds are actually 0.355 millicurie sources. Notified NMSS (Brown) and |
| R4DO (Sanborn). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39519 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/17/2003|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 14:35[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/17/2003|
+------------------------------------------------+EVENT TIME: 11:30[EST]|
| NRC NOTIFIED BY: KEN TIEFENTHAL |LAST UPDATE DATE: 01/17/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO VIOLATION OF DISCHARGE PERMIT |
| |
| The following information was obtained from a facsimile from the Licensee: |
| |
| "On 1/17/2003 at 1130 hours, the Beaver Valley Power Station received |
| notification that an operator found raw sewage running from the Unit 2 |
| Sewage Treatment Plant through a slightly open connection and immediately |
| closed the isolation valve, stopping the flow. |
| |
| "Assessment by the Beaver Valley response determined that a sewage removal |
| vendor had previously attempted to pump sludge from a plant sewage system, |
| but nothing came out. He then apparently only partially closed the |
| isolation valve and left the site. Subsequently, sewage began to flow out. |
| Approximately 750 gallons of sewage was released down a storm sewer [drain]. |
| An unknown quantity of sewage entered the Ohio River via Peggs Run. |
| Approximately 50 gallons of sewage remaining on the surface at the local |
| location is being cleaned up. |
| |
| "Pennsylvania Department of Environmental Protection (DEP) has been |
| notified. |
| |
| "This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi) as a |
| situation related to the protection of the environment for which |
| notification to other government agencies have been made. The NRC resident |
| has been notified." |
| |
| The notification to the Pennsylvania DEP was made due to a violation of the |
| plant's discharge permit. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39520 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 01/17/2003|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 16:28[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 01/17/2003|
+------------------------------------------------+EVENT TIME: 14:43[EST]|
| NRC NOTIFIED BY: PHILLIP ROSE |LAST UPDATE DATE: 01/17/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAY HENSON R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |95 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO FAILED SURVEILLANCE ON |
| REACTOR TRIP BREAKER |
| |
| The following information was obtained from the licensee via facsimile: |
| |
| "At 11:40 [EST] on January 17, 2003, during surveillance testing of the 'B' |
| train Reactor Trip Breaker (RTB), the breaker spuriously opened. This |
| caused the RTB to fail its surveillance test and be declared inoperable. |
| The facility Technical Specifications (TS), LCO 3.3.1 (Reactor Trip System |
| Instrumentation), Action 8 of Table 3.3-1 requires 6 hours to Mode 3, Hot |
| Standby. Rework activities were begun but the station commenced a power |
| decrease at 14:43 [EST] to comply with the requirements of the TS. |
| |
| "At 15:10 [EST] on January 17, 2003, the activities, including retesting |
| were completed and the breaker was declared operable at which time the plant |
| exited from the TS Limiting Condition for Operability Action. At this time |
| the power decrease was stopped. Power was held stable at 95% awaiting |
| completion of all paperwork associated with this surveillance test. Power |
| ascension commenced at 15:55 [EST]." |
| |
| Determined from the Licensee that the Reactor Trip Breaker spuriously opened |
| after it was closed during the test. The breaker was replaced with another |
| breaker and the surveillance test was performed on the new breaker |
| successfully. |
| |
| The Licensee has informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39521 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 01/19/2003|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 12:19[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/19/2003|
+------------------------------------------------+EVENT TIME: 10:11[EST]|
| NRC NOTIFIED BY: DAVID WALSH |LAST UPDATE DATE: 01/19/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD BARKLEY R1 |
|10 CFR SECTION: |TAD MARSH NRR |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS |MOHAMED SHANBAKY R1 |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 77 Power Operation |50 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SUSQUEHANNA UNIT 1 SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| The following is taken from a facsimile sent by the licensee: |
| |
| "At 10:11 hrs on 1/19/2003 Susquehanna Unit 1 began a shut down required by |
| Technical Specifications. |
| |
| "At 13:06 hrs on 1/16/2003 the 'B' diesel generator was being returned to |
| service following maintenance. This placed Unit 1 and Unit 2 into a 72 hour |
| LCO (3.8.1 Cond. B). During its operability run, the governor exhibited |
| erratic operation and the diesel was shut down. The 'E' diesel generator was |
| re-substituted for the 'B' and an operability run was initiated. During the |
| run, the 'E' diesel generator tripped on reverse power. Station personnel |
| continue to troubleshoot the unrelated problems with the diesel generators. |
| Initial engineering analysis has determined that there is no common mode |
| failure with these 2 problems or with the remaining 3 operable diesel |
| generators. |
| |
| "The 72 hour LCO for inoperability of 1 Diesel Generator (3.8.1 Cond. B) |
| will expire at 13:06 hrs today. This will require both Unit 1 and Unit 2 to |
| enter LCO 3.8.1 Cond. F, which requires both units to be in Hot Shutdown |
| within 12 hours and Cold Shutdown within 36 hours. |
| |
| "An additional ENS report will be made when power reduction begins on Unit |
| 2." |
| |
| The licensee has notified the NRC Resident Inspector of this event and plans |
| to make a press release. |
| |
| * * * UPDATE 1600EST ON 1/19/03 FROM DAVID WALSH TO S. SANDIN * * * |
| |
| "At 15:38 hrs on 1/19/2003 the 'E' diesel generator was declared operable. |
| This returned the station to 4 operable diesel generators and allowed |
| exiting the LCO 3.8.1 Cond. B and Cond. F. Power reduction on Unit 1 was |
| halted at approximately 50%. Unit 2 remained at 100% power. Current plans |
| are to return Unit 1 to 100% power." |
| |
| The licensee is reviewing whether a press release will be made. Also, the |
| licensee informed the NRC resident inspector of this update. Notified |
| R1DO(Barkley) and NRR EO(Marsh). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39522 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/19/2003|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 14:59[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/19/2003|
+------------------------------------------------+EVENT TIME: 12:52[EST]|
| NRC NOTIFIED BY: B. J. BROWN |LAST UPDATE DATE: 01/19/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAY HENSON R2 |
|10 CFR SECTION: | |
|AMED 50.72(b)(3)(xii) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTAMINATED, INJURED WORKER TRANSPORTED TO LOCAL MEDICAL FACILITY |
| |
| The following is taken from a facsimile from the licensee: |
| |
| "At 1252 today, a worker in a Contaminated Area in Unit 2 Containment became |
| overheated and required medical attention. The first aid team responded and |
| required that the individual be transported while he was still contaminated. |
| The individual has 100K [100,000] dpm by direct frisk on his skin in the |
| area of his face and 10K [10,000] dpm by direct frisk on his clothing he was |
| wearing. He was transported by local Rescue Squad. While in the ambulance he |
| was decontaminated by HP [Health Physics] personnel that were assisting. |
| Medical College of Virginia (MCV) was notified of a potentially contaminated |
| person that was enroute. The individual is still being transported to MCV |
| where he will receive medical treatment. The individual and ambulance are |
| now clean and all contaminated material will be transported back to NAPS |
| [North Anna Power Station]" |
| |
| The contaminated, injured worker was working on the installation of the |
| blind flange on the fuel transfer tube. The North Anna Unit 2 reactor is |
| refueled. |
| |
| The licensee will notify the NRC Resident Inspector of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39523 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/19/2003|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 21:25[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/19/2003|
+------------------------------------------------+EVENT TIME: 12:55[CST]|
| NRC NOTIFIED BY: GREG JANAK |LAST UPDATE DATE: 01/19/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GARY SANBORN R4 |
|10 CFR SECTION: |TAD MARSH NRR |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VARIOUS SYSTEM ACTUATIONS AS A RESULT OF THE LOSS OF OFFSITE POWER |
| |
| The following information was received via facsimile: |
| |
| "At 1255 hrs on January 19, 2003, Unit 1 was in Mode 1 at 100% power and |
| Unit 2 was in Mode 3 with Trains A and D reactor coolant pumps (RCP) |
| running. While placing a surge reactor in the switchyard in service the Unit |
| 1 standby transformer received a lockout and total loss of the North bus. |
| |
| "Unit 1 experienced a loss of offsite power (LOOP) to ESF Trains B & C. Both |
| the Train B & Train C emergency diesel generators (EDG) started as expected. |
| The Train C sequencer operated as expected and the Train C components |
| automatically loaded, However, the Train B sequencer failed resulting in the |
| manual loading of the Train B components in accordance with station |
| off-normal procedures. This resulted in TS 3.0.3 entry in Unit 1 due to the |
| loss of two (2) offsite power sources and the B train EDG (due to the |
| failure of the B Train sequencer). There was a loss of letdown in Unit 1 |
| when Train C isolated. Letdown was restored at 1313 hrs. At 1345 Unit 1 |
| exited TS 3.0.3 when offsite power was restored to B Train. At 1406, offsite |
| power was restored to C Train. The cause of the fault in the switchyard and |
| failed Train B sequencer are under Investigation. |
| |
| "In Unit 2, Train A was aligned to the Unit 1 Standby transformer therefore, |
| Unit 2 experienced a LOOP to ESF Train A. Train A emergency diesel generator |
| automatically started and loaded as expected. As a result of the LOOP, Unit |
| 2 experienced a loss of circulating water and loss of condenser vacuum. The |
| Steam Generators (SGs) were already being supplied by the Auxiliary |
| Feedwater system therefore no interruption to SG cooling. In addition, both |
| Train A and Train D reactor coolant pumps tripped resulting in entry into TS |
| 3.4.1.2, action B & C (boron control limitations and ensure Rx trip breakers |
| open). There was a loss of charging due to the LOOP resulting in a Loss of |
| RCP seal injection, however, component cooling water flow to the thermal |
| barrier maintained seal cooling. Charging has been restored to supply seal |
| injection. At 1840, when starting RCP 2A, pressurizer PORV 655A opened and |
| reseated due to a pressure spike. Unit 1 remains at 100% power and Unit 2 |
| remains in Mode 3." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39525 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 01/20/2003|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 14:40[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/20/2003|
+------------------------------------------------+EVENT TIME: 10:40[EST]|
| NRC NOTIFIED BY: DENNIS MOORE |LAST UPDATE DATE: 01/20/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAY HENSON R2 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| RANDOM FITNESS FOR DUTY TEST FAILURE |
| |
| "A non-licensed contract supervisor tested positive during a random test. |
| The employee's access to the plant has been restricted." Contact the HOO for |
| additional details. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39526 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/20/2003|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 20:13[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/20/2003|
+------------------------------------------------+EVENT TIME: 14:30[EST]|
| NRC NOTIFIED BY: JAMES WITTER |LAST UPDATE DATE: 01/20/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SERVICE WATER SYSTEM VALVE PIT PIPING PENETRATION SEAL |
| |
| "On 1/20/2003 at 1430 hours, the Beaver Valley Power Station control room |
| was notified by Engineering that a penetration seal previously installed in |
| a wall which separates two service water system valve pits may have not been |
| adequate. A review of the supporting analysis shows that this penetration |
| seal may not be qualified to withstand the hydraulic pressure which could |
| result from a postulated internal flooding event occurring due to a service |
| water system pipe failure filling the valve pit and its above compartment |
| prior to operator intervention. A failure of this seal during a postulated |
| internal flooding event may result in the loss of motor operated valve |
| movement in both trains of the service water system that would be needed |
| following a design basis accident (DBA). |
| |
| "This design basis calculation and the penetration seal capability are |
| continuing to be evaluated. However, this seal could potentially have |
| prevented the service water system from meeting single failure criterion |
| during a postulated service water system pipe failure. Therefore, Technical |
| Specification (TS) 3.7.4.1 was entered due to less than two trains of |
| service water system being operable as a conservative decision based upon |
| the limited information immediately available to show acceptable seal |
| integrity at the postulated conditions. The TS Action requires restoration |
| of two independent service water system trains within 72 hours. Actions are |
| in progress to install a qualified seal which will prevent the unacceptable |
| flooding conditions from being able to occur. |
| |
| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an |
| unanalyzed condition that significantly degraded plant safety since this |
| seal has been installed for five months and may have invalidated the |
| independence between the two service water system trains. The NRC resident |
| has been notified of the degraded condition." |
+------------------------------------------------------------------------------+
