U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/10/2003 - 03/11/2003
** EVENT NUMBERS **
39640 39641 39642 39643 39650 39651 39652 39653 39654 39657 39658
39659
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39640 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LOUISIANA DEPT ENV QUALITY |NOTIFICATION DATE: 03/06/2003|
|LICENSEE: COMPUTALOG WIRELINE SERVICES |NOTIFICATION TIME: 15:29[EST]|
| CITY: REGION: 4 |EVENT DATE: 03/05/2003|
| COUNTY: STATE: LA |EVENT TIME: [CST]|
|LICENSE#: LA-4413-L01 AGREEMENT: Y |LAST UPDATE DATE: 03/06/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SCOTT BALCKWELL | |
| HQ OPS OFFICER: YAMIR DIAZ | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| IRRETRIEVABLE SEALED SOURCE |
| |
| "Computalog was performing analysis of the amount of petroleum in the |
| Strategic Petroleum Reserve salt dome in Hackberry, LA. The tool hung up |
| on the casing near the top and fell to the bottom. The source was a 172 |
| mCi [milli Curie] source of Cs- 137 and it fell to a depth of 4000 ft. |
| Attempts were not made to retrieve the tool because the dome is so wide at |
| the bottom. DEQ is waiting on the written report for additional |
| information." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39641 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LOUISIANA DEPT ENV QUALITY |NOTIFICATION DATE: 03/06/2003|
|LICENSEE: HARTFIELD TECHNICAL SERVICES |NOTIFICATION TIME: 15:30[EST]|
| CITY: REGION: 4 |EVENT DATE: 02/17/2003|
| COUNTY: STATE: LA |EVENT TIME: [CST]|
|LICENSE#: LA-4543-L01 AGREEMENT: Y |LAST UPDATE DATE: 03/06/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SCOTT BLACKWELL | |
| HQ OPS OFFICER: YAMIR DIAZ | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| IRRETRIEVABLE SEALED SOURCE |
| |
| "A 3 Ci [Curie] sealed source of AmBe 241 was lost down hole on February 17, |
| 2003 at a depth of 6600 ft. Attempts were made to retrieve the source but |
| they were unsuccessful. A vented bridge plug was set at 5335 ft and low |
| permeability cement was dumped until 5300 ft. Additional information will be |
| sent at a later date." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39642 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LOUISIANA DEPT ENV QUALITY |NOTIFICATION DATE: 03/06/2003|
|LICENSEE: HALIBURTON |NOTIFICATION TIME: 15:31[EST]|
| CITY: REGION: 4 |EVENT DATE: 02/14/2003|
| COUNTY: STATE: LA |EVENT TIME: [CST]|
|LICENSE#: LA-2353-L01 AGREEMENT: Y |LAST UPDATE DATE: 03/06/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SCOTT BLACKWELL | |
| HQ OPS OFFICER: YAMIR DIAZ | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| IRRETRIEVABLE SEALED SOURCE |
| |
| "An NWA tool with a 2 Ci [Curie] source of Cs-137 and a 4 Ci source of |
| Am241Be were lost down hole at 11540 feet on February 14, 2003. Attempts |
| were made until February 20, 2003 to retrieve the tool, but they were |
| unsuccessful. The well was back filled with 500 ft of cement to a depth of |
| 10881 ft. DEQ is currently waiting for the written report for additional |
| information." |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39643 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 03/07/2003|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 19:17[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 14:40[EST]|
| NRC NOTIFIED BY: ROBERT KIDDER |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: |JOHN DAVIDSON IAT |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 83 Power Operation |83 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 1- HOUR SAFEGUARD REPORT |
| |
| Discovery of criminal act involving individual granted access to the site. |
| Immediate compensatory measures taken upon discovery. Contact the |
| Headquarters Operations Officer for details. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| **** RETRACTION ON 03/10/03 AT 1555 ET BY TOM VEITCH TAKEN BY MACKINNON |
| **** |
| |
| After additional review, it was determined that drugs do not fall into the |
| classification of contraband and thus need not be reported under this |
| criterion. R3DO (Ken O'Brien) notified. |
| |
| The NRC Resident Inspector was notified of this retraction by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39650 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 00:46[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/09/2003|
+------------------------------------------------+EVENT TIME: 20:47[CST]|
| NRC NOTIFIED BY: JONATHAN PIERCE |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DALE POWERS R4 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY INJECTION SYSTEM ACTUATION AND CAUSE UNDER INVESTIGATION |
| |
| "At 20:47 on 3/9/03, Unit 2 experienced a Safety Injection while the plant |
| was stable at NOP(2235 psig)/NOT |
| (567 degrees) in Mode 3. All systems actuated as designed. An operator was |
| operating the 'B' S/G PORV shortly |
| before the event occurred. All MSIVs were closed for ongoing work on the |
| main turbine. The Sequence of |
| events report showed all 3 channels of steam pressure spiking low on the 'B' |
| Steam Generator as the cause of the event. Initial look at trends on the |
| integrated computer system showed [that] steam pressure channels did not |
| lower to a point to cause the safety injection. An Event Review Team is |
| being formed to investigate this event. |
| |
| "A Reactor Coolant System PORV opened due to high pressure when the Spray |
| valves closed due to the Instrument Air isolation (due to phase 'A') with |
| the Pressurizer Heaters in manual. The Pressurizer heaters were secured and |
| Reactor coolant System pressure stabilized. All ESF systems actuated as |
| designed. The following systems actuated: Auxiliary Feedwater, Safety |
| Injection, Phase 'A', Control Room Envelope and Fuel Handling Building HVAC |
| systems, Essential Cooling Water, Component Cooling Water, Emergency Diesel |
| Generators and ESF sequencers." |
| |
| There was no safety injection since pressure was maintained above 2199 psi |
| during the transient (Hi Head is 1700 psi). Heat removal is being performed |
| through S/G PORVs and Unit 2 is currently stable at Mode 3. |
| |
| The Licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39651 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 03:45[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/10/2003|
+------------------------------------------------+EVENT TIME: 00:12[EST]|
| NRC NOTIFIED BY: JOHN RODEN |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |STEPHEN CAHILL R2 |
|10 CFR SECTION: |CAROLYN EVANS R2 |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|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 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP ON GENERATOR DIFFERENTIAL RELAY |
| ACTUATION |
| |
| "At 0012 EST on March 10, 2003, with Watts Bar Unit 1 in Mode 1 at 100% |
| power, the reactor tripped due to an automatic signal. All plant safety |
| systems were in service at the time to the trip, except for the 2B-B diesel |
| generator which was out of service for scheduled maintenance, and all |
| [safety systems] responded as designed. All control rods inserted as |
| required and the Auxiliary Feedwater System [AFW] initiated as expected. |
| |
| "The reactor trip resulted from a turbine trip signal that was generated as |
| a result of a main generator/transformer differential electrical relay |
| actuation. The plant is currently stable in Mode 3 and will remain in this |
| Mode until completion of the investigation." |
| |
| AFW was removed from operation and the main feed pumps have resumed normal |
| feed to the Steam Generators. The Licensee notified the NRC Resident |
| Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 39652 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OAKWOOD HOSPITAL |NOTIFICATION DATE: 03/10/2003|
|LICENSEE: OAKWOOD HOSPITAL |NOTIFICATION TIME: 11:43[EST]|
| CITY: DEARBORN REGION: 3 |EVENT DATE: 03/10/2003|
| COUNTY: WAYNE STATE: MI |EVENT TIME: 10:00[EST]|
|LICENSE#: 21-04515-01 AGREEMENT: N |LAST UPDATE DATE: 03/10/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KEN O'BRIEN R3 |
| |KEVIN HSUEH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TALJIT SANDHER | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|LOTH 35.3045(a)(3) DOSE TO OTHER SITE > SP| |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL EVENT TO AN UNINTENDED SITE |
| |
| At 1000 EST on 03/10/03 it was discovered that a patient at Oakwood |
| Hospital located in Dearborn, MI had implanted 42 Iodine-125 seeds into his |
| bulb of urethra instead of his prostrate. The urologist had misinterpreted |
| the ultrasound scan. The total activity of the Iodine-125 seeds was 14.2 |
| millicuries, each seed was 0.338 millicuries. The patient and his Medical |
| Doctor have been notified of the error. No side affects to the patient. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39653 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [] [2] [] STATE: TN |NOTIFICATION TIME: 12:12[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/10/2003|
+------------------------------------------------+EVENT TIME: 09:18[EST]|
| NRC NOTIFIED BY: CALVIN FIELDS |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CAROLYN EVANS R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP |
| |
| Unit 2 Manual Reactor Trip at 0918 ET on 03/10/03 due to the following |
| sequence events: |
| |
| At 0903 Hotwell Pump "B" tripped on neutral overcurrent. |
| |
| At 0911 Both # 7 Heater Drain Tank Pumps tripped. |
| |
| Per AOP-S.04 started decreasing unit power. |
| |
| At 0918 Main Feedwater Pump "A" tripped initiating Unit Runback Balance of |
| Plant (BOP). |
| |
| At 0918 Manual Reactor Trip. |
| |
| Due to both Main Feedwater Pump's rupture discs blown plant is using Steam |
| Generator Atmospheric Relief Valves to cool the plant and maintain a Hot |
| Standby condition. No leaking steam generator tubes. The electrical grid |
| is stable and the emergency diesel generators are fully operable if needed. |
| Sequoyah Unit 1 is in coastdown. |
| |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39654 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 14:26[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 17:00[CST]|
| NRC NOTIFIED BY: NEIL HARRIS |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 |
|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
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY FOR ALCOHOL |
| |
| On 03/07/03 at 1700 hours CT a contract employee was asked to take a for |
| cause test for alcohol. He refused to take the test and he then resigned |
| from his position. At 1731 hours his unescorted access was terminated. The |
| licensee escorted the individual offsite and to his residence. His work |
| record was reviewed and nothing unusual was found. |
| |
| The NRC Resident Inspector will be informed by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39657 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 17:32[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/10/2003|
+------------------------------------------------+EVENT TIME: 07:31[PST]|
| NRC NOTIFIED BY: JEFF KINSLEY |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR COOLANT SYSTEM LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) NOT |
| ENABLED |
| |
| During the eleventh refueling outage on Unit 2 (2R11) the reactor coolant |
| system low temperature overpressure (LTOP) protection was inoperable due to |
| the individual power operated relief valves (PORV's) control switches being |
| selected to the "closed" position. LTOP was unable to perform its required |
| automatic function from 0829 PT on 03/09/03 until the discovery time of 0731 |
| PT on 03/10/03. This discrepancy was discovered by the operator during the |
| beginning of shift board walkdown, at which time the PORV selector switches |
| were returned to "auto" and LTOP protection was enabled. At no time were |
| any of the LTOP setpoints challenged. Residual Heat Removal (RHR) pump |
| suction relief valves (setpoint is 450 psi) were also available during this |
| time frame to provide overpressure protection. Reactor Coolant temperature |
| was 109 degrees F. LTOP setpoint was for 435 psi. The LTOP PORV's |
| control switches were closed during the vacuum degas procedure. Licensee |
| is still investigating this event. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39658 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 03/10/2003|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 18:24[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/10/2003|
+------------------------------------------------+EVENT TIME: 11:37[CST]|
| NRC NOTIFIED BY: SAM BELCHER |LAST UPDATE DATE: 03/10/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 |
|10 CFR SECTION: | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 87 Power Operation |87 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT AIRLOCK SEALS DEFLATED. |
| |
| At 1137 CST on 03/10/03, with the plant at 87% power, the Main Control Room |
| team received indications that the seals were deflated on both doors of |
| primary containment airlock JRB-DRA1. Personnel were exiting containment |
| through the airlock at this time. Personnel were dispatched and airlock |
| integrity was restored at 1208 CST. The cause of the condition appears to |
| be related to the mechanical interlock. This interlock did not function as |
| required to prevent deflation of the seals on both doors concurrently. This |
| condition is being evaluated. |
| |
| This condition could have resulted in a loss of function of the Primary |
| Containment to confine a postulated release of radioactive material to |
| within limits. |
| |
| The Senior Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39659 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/11/2003|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:23[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/10/2003|
+------------------------------------------------+EVENT TIME: 22:38[CST]|
| NRC NOTIFIED BY: ANDREW OHRABLO |LAST UPDATE DATE: 03/11/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POTENTIAL RAD GROUND RELEASE PATH DISCOVERED DUE TO LOSS OF SECONDARY |
| CONTAINMENT |
| |
| "This notification is being made pursuant to NRC regulation |
| 10CFR50.72(b)(3)(v)(D), any event or condition that at the time of discovery |
| could have prevented the fulfillment of the safety function of structures or |
| systems that are needed to mitigate the consequences of an accident. |
| |
| "On March 10, 2003 at 22:38, it was determined that the secondary |
| containment was inoperable due to a leak in the Z sump manway gasket. The |
| plant was in Mode 5, shutdown, performing fuel shuffle when secondary |
| containment was declared inoperable. LCO 3.6.4.1 was entered. The fuel |
| shuffle was secured at 22:40 after the completion of the fuel move that was |
| in progress. No additional Core Alterations or OPDRVs [Operations |
| Potentially Draining the Reactor Vessel] were in progress. Upon |
| investigation into the secondary containment operability, it was determined |
| that a non-Tech Spec surveillance performed on dayshift also rendered |
| secondary containment inoperable due to additional leakage pathway via the Z |
| sump. A principal safety function of Secondary Containment is to limit the |
| ground level release to the environs of airborne radioactive materials |
| resulting from a fuel handling accident. |
| |
| "As a result of the alignment of the Z sump the potential existed that if a |
| radioactive release were to occur due to a fuel handling accident, part of |
| the filtered release via Standby Gas Treatment System could be a ground |
| level release vice a release through the Elevated Release Point. The |
| surveillance has been completed and the additional leakage paths that were |
| opened due to the surveillance have been sealed. The leaking manway gasket |
| was determined to be due to not adequately torquing the gasket bolts. The |
| bolts have been retorqued. Secondary containment was reestablished, and was |
| declared OPERABLE at 02:55, 3-11-03. |
| |
| "The NRC Senior Resident has been notified." |
+------------------------------------------------------------------------------+
