U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/08/94 - 11/09/94 ** EVENT NUMBERS ** 28002 28003 28004 28005 28006 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28002 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 11/08/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 03:17 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/08/94 | +------------------------------------------------+EVENT TIME: 00:40[CST]| |NRC NOTIFIED BY: DAVE PEARSON |LAST UPDATE DATE: 11/08/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | |McPEEK IAT | | |DAVIDSON IAT | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING POSSIBLE TAMPERING WITH A CAN OF COKE. | | | | A CAN OF COKE WAS PURCHASED FROM AN ONSITE VENDING MACHINE AT 1830 CST ON | | 11/7/94. THE COKE WAS SHARED BY TWO PLANT EMPLOYEES, BOTH OF WHOM NOTICED | | AN UNUSUAL TASTE. EXAMINATION OF THE CAN REVEALED A SCREW INSERTED INTO THE | | BOTTOM WITH A SEALANT AROUND IT. | | | | THE TWO EMPLOYEES WENT TO THE LOCAL HOSPITAL FOR PRECAUTIONARY OBSERVATION. | | IN ADDITION, THEY CONTACTED THE FDA, LOCAL FBI, AND THE WILL COUNTY | | SHERIFF'S DEPARTMENT. AT 0040 ON 11/8/94, THE WILL COUNTY SHERIFF'S | | DEPARTMENT OPENED AN INVESTIGATION AND INDICATED THAT THEY WOULD PROBABLY | | CONTACT THE FBI. | | | | ALL VENDING MACHINES AT THE SITE HAVE BEEN SECURED. A COCA-COLA | | REPRESENTATIVE HAS ALSO BEEN INVOLVED IN THESE DEVELOPMENTS AND IS PURSUING | | A PARALLEL INVESTIGATION. | | | | NO ILL EFFECTS HAVE BEEN EXPERIENCED BY THE EMPLOYEES TO DATE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28003 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 11/08/94 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 09:13 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 11/08/94 | +------------------------------------------------+EVENT TIME: 04:45[CST]| |NRC NOTIFIED BY: KEITH POLSON |LAST UPDATE DATE: 11/08/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 24 POWER OPERATION | 24 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROD FAILED TO SCRAM DURING SCRAM TIME TESTING. | | | | WHILE PERFORMING FULL CORE SCRAM TIME TESTING, CONTROL ROD DRIVE E-10 | | FAILED TO SCRAM. THE ROD WAS MANUALLY INSERTED TO THE 00 POSITION AND TAKEN | | OUT OF SERVICE. | | | | INITIAL INDICATIONS ARE THAT THE PROBLEM WAS RELATED TO A MALFUNCTION OF | | THE SCRAM PILOT SOLENOIDS. THE SOLENOIDS FOR THIS ROD WERE REBUILT DURING | | THE LAST REFUELING OUTAGE. THE LICENSEE NOTES THAT THIS ROD WAS PREVIOUSLY | | SCRAM TESTED SUCCESSFULLY AFTER THE SOLENOIDS HAD BEEN REBUILT. | | | | ABOUT 35 ROD SCRAM PILOT SOLENOIDS WERE REBUILT DURING THE LAST OUTAGE. NO | | PROBLEMS HAVE BEEN OBSERVED WITH THE OTHER RODS WITH REBUILT SOLENOIDS. | | | | THE LICENSEE PLANS TO CONTINUE SCRAM TIME TESTING WHILE THE PROBLEM WITH | | ROD E-10 IS RESOLVED. OPERATION CAN CONTINUE WITH E-10 INSERTED AT THE | | CURRENT POWER LEVEL. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28004 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 11/08/94 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 15:02 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 11/08/94 | +------------------------------------------------+EVENT TIME: 14:25[EST]| |NRC NOTIFIED BY: CROOK |LAST UPDATE DATE: 11/08/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EMERGENCY SIRENS OUT OF SERVICE. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "ON NOVEMBER 8, 1994, AT 1425 HOURS, FOLLOWING SCHEDULED TESTING OF THE | | OFFSITE EMERGENCY NOTIFICATION SYSTEM SIRENS, WE HAVE DETERMINED THAT AT | | LEAST TWELVE OUT OF FORTY-FIVE SIRENS WITHIN THE LOCAL TEN MILE EPZ WERE | | OUT OF SERVICE. A ROUTE ALERTING PROCESS VIA LOCAL GOVERNMENT AGENCIES IS | | IN PLACE AS BACK-UP FOR THE INOPERABLE SIRENS. THE ANNUAL FULL VOLUME | | SIREN TEST WAS JUST COMPLETED ON OCTOBER 27, 1994, ANS WAS FULLY | | SUCCESSFUL. | | | | THE SIRENS WILL BE REPAIRED AND RESTORED TO OPERABLE STATUS AS SOON AS | | PRACTICAL. THE AFFECTED COUNTY HAS BEEN NOTIFIED." END OF TEXT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28005 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 11/08/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 15:24 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/08/94 | +------------------------------------------------+EVENT TIME: 13:28[CST]| |NRC NOTIFIED BY: WEBER |LAST UPDATE DATE: 11/08/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ENGINEERING ANALYSIS DETERMINED THAT THE RAW WATER (RW) SYSTEM MAY BE | | DISABLED DUE TO AN INTAKE STRUCTURE CRANE ACCIDENT. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "THE CURRENT HEAVY LOAD INCIDENT ANALYSIS (USAR SECTION 14.24) ADDRESSES | | LOAD DROPS FROM THE INTAKE STRUCTURE CRANE THAT COULD AFFECT THE RAW WATER | | (RW) SYSTEM. THE CURRENT DISCUSSION DOES NOT IDENTIFY THE POSSIBILITY | | THAT, UNDER SPECIFIC CIRCUMSTANCES, FLOODING OF THE RW PUMP ROOM FOLLOWING | | A LOAD DROP COULD POTENTIALLY THREATEN THE OPERABILITY OF ALL FOUR RW | | PUMPS. TWO SCENARIOS HAVE BEEN IDENTIFIED THAT INVOLVE THIS POSSIBILITY. | | THE FIRST SCENARIO INVOLVES A LOAD DROP RUPTURING RW PUMP DISCHARGE PIPING | | IN THE PUMP ROOM, AND THE SECOND INVOLVES A LOAD DROP THROUGH THE FLOOR OF | | THE PUMP ROOM DURING HIGH RIVER LEVEL CONDITIONS. BOTH SCENARIOS HAVE THE | | POTENTIAL TO RESULT IN LOSS OF OPERABILITY OF ALL FOUR RW PUMPS BEFORE | | OPERATOR ACTION COULD BE ASSUMED TO STOP THE FLOODING. | | | | THE SAFETY FUNCTION OF THE RW SYSTEM IS TO REMOVE RESIDUAL HEAT FROM THE | | REACTOR AND COOL THE SPENT FUEL POOL. THE SCENARIOS ABOVE, WHICH ARE NOT | | ADDRESSED IN THE CURRENT USAR SECTION 14.24 ANALYSIS, COULD HAVE PREVENTED | | THE FULFILLMENT OF THIS SAFETY FUNCTION BY THE RW SYSTEM. THIS WAS | | DETERMINED TO BE REPORTABLE PURSUANT TO 10CFR50.72(b)(2)(iii). HOWEVER, AN | | ALTERNATE METHOD OF COOLING IS AVAILABLE AND PROCEDURALIZED, INVOLVING | | CROSS-CONNECTING THE NON-SAFETY RELATED FIRE PROTECTION SYSTEM TO THE RW | | SYSTEM." END OF TEXT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28006 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 11/08/94 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 19:08 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 11/08/94 | +------------------------------------------------+EVENT TIME: 18:55[EST]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 11/08/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 89 POWER OPERATION | 89 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTROL ROD DRIVE MECHANISM (CRDM) FAN WAS REMOVED FROM SERVICE WHEN ITS | | MOORINGS COULD NOT BE SECURED PROPERLY. | | | | AFTER REPLACING CRDM FAN "22" DUE TO A MOTOR FAILURE, BOLTS IN THE U-BRACE | | ANCHORING THE CRDM FAN COULD NOT BE RE-INSTALLED. TECHNICIANS UTILIZED | | FOUR TIE-WRAPS TO SECURE THE CRDM FAN TO COMPLETE THE RE-INSTALLATION. AN | | ANALYSIS OF THE TIE-WRAP CONFIGURATION DETERMINED THAT IT WAS OVERSTRESSED. | | A FAILURE OF THE TIE-WRAPS WOULD CAUSE THE CRDM FAN TO DROP INTO THE | | REACTOR CAVITY WITH NO EXPECTED COLLATERAL DAMAGE. NO SAFETY EQUIPMENT | | WOULD BE AFFECTED AND NO SAFETY FUNCTION WOULD BE COMPROMISED. | | | | A CONTAINMENT ENTRY IS BEING CONDUCTED AT THIS TIME TO REMOVE THE CRDM FAN. | | THREE OTHER FANS REMAIN OPERABLE TO COOL THE ASSOCIATED CRDM. NO SAFETY | | EQUIPMENT HAS BEEN DECLARED INOPERABLE AND NO TECHNICAL SPECIFICATION | | ACTION STATEMENT HAS BEEN ENTERED. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+