U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/02/95 - 11/03/95 ** EVENT NUMBERS ** 29545 29546 29547 29548 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29545 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 11/02/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:18 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 11/02/95 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: BILL BANDHAUER |LAST UPDATE DATE: 11/02/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR BUILDING PURGE VALVE CONTROL CIRCUITS ARE DESIGNATED AS SAFETY | | RELATED BUT UTILIZE NON-SAFETY TERMINATION BOXES. | | | | DURING FOLLOW UP TO AN EARLIER ELECTRICAL PROBLEM IDENTIFIED BY OPERATIONS, | | THE ENGINEERING DEPARTMENT DISCOVERED THAT THEIR REACTOR BUILDING PURGE | | CONTROL CIRCUITS ARE DESIGNATED AS SAFETY RELATED, BUT UTILIZE A NON-SAFETY | | TERMINATION TERMINAL BOX AND OTHER UNISOLATED DEVICES IN THEIR ROUTING. THE | | REACTOR BUILDING PURGE SYSTEM IS CONSIDERED FOR MODE 6 (REFUELING OUTAGE) | | REACTOR BUILDING FUEL HANDLING DESIGN BASIS ACCIDENTS. THIS PROBLEM WILL BE | | CORRECTED BEFORE ENTERING THE NEXT REFUELING OUTAGE. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29546 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 11/02/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 16:15 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/02/95 | +------------------------------------------------+EVENT TIME: 14:00[CST]| |NRC NOTIFIED BY: BREWER |LAST UPDATE DATE: 11/02/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTROL ROOM LEAKAGE RATE EXCEEDED. | | | | THIS IS A 24 HOUR REPORT MADE IN ACCORDANCE WITH CONDITION 2F OF OPERATING | | LICENSEE NPF-29. ON OCTOBER 12, 1995, CONTROL ROOM AIR CONDITIONER "B" WAS | | OPENED FOR A 12 HOUR MAINTENANCE ACTIVITY. DURING THE PAPER CLOSE OUT ON | | OCTOBER 16th, AN EVALUATION WAS INITIATED TO DETERMINE IF THE DUCT ACCESS | | PORT REMOVAL AFFECTED THE CONTROL ROOM BOUNDARY. THE LICENSEE'S EVALUATION | | CONCLUDED ON NOVEMBER 2 THAT THE ACTIVITY CAUSED A VIOLATION OF OPERATING | | LICENSEE 2.C (38), CONTROL ROOM LEAK RATE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29547 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: APPLIED CONSTRUCTION TECHNOLOGY |NOTIFICATION DATE: 11/02/95 | | CITY: CLEVELAND REGION: 3 |NOTIFICATION TIME: 18:57 [ET]| | COUNTY: STATE: OH |EVENT DATE: 11/02/95 | |LICENSE#: 34-258-34-01 AGREEMENT: N |EVENT TIME: 17:30[EST]| | DOCKET: |LAST UPDATE DATE: 11/02/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEWIS MILLER RDO | | |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: G WOZNIAK | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TROXLER MOISTURE DENSITY GAUGE STOLEN FROM THE BACK OF AN ENCLOSED LOCKED | | PICKUP TRUCK. | | | | APPLIED CONSTRUCTION TECHNOLOGY LOCATED IN CLEVELAND, OHIO REPORTED THAT A | | TROXLER MOISTURE DENSITY GAUGE WAS STOLEN FROM THE BACK OF A TECHNICIANS | | PICKUP TRUCK. THE TROXLER MOISTURE DENSITY GAUGE WAS LOCKED INSIDE THE | | ENCLOSED BACK SECTION OF THE PICKUP TRUCK. THE TECHNICIAN NOTIFIED THE | | MENTOR POLICE DEPARTMENT OF THE THEFT. POLICE TOOK FINGER PRINTS FROM THE | | BACK OF THE PICKUP TRUCK. THE LICENSEE DID NOT KNOW THE POLICE REPORT | | NUMBER AT THE TIME OF THE CALL. THE TROXLER MOISTURE DENSITY GAUGE | | CONTAINED TWO SOURCES; ONE BEING A 10 mCi Cs-137 SOURCE, AND THE OTHER A 50 | | mCi Am-241/Be SOURCE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29548 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/02/95 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 23:43 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/02/95 | +------------------------------------------------+EVENT TIME: 21:30[EST]| |NRC NOTIFIED BY: BARRY COLEMAN |LAST UPDATE DATE: 11/02/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |LEE SPESSARD EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT DRAINING OF THE REACTOR VESSEL LED TO AN ISOLATION OF THE | | SHUTDOWN COOLING SYSTEM. SHUTDOWN COOLING WAS LOST FOR APPROXIMATELY 30 | | MINUTES WITH NO APPRECIABLE INCREASE IN REACTOR TEMPERATURE. | | | | THE CAUSE OF THE EVENT WAS THE OPENING OF BOTH THE SHUTDOWN COOLING SUCTION | | ISOLATION VALVE FOR THE 'B' RHR PUMP (F006B) AND THE TORUS SUCTION VALVE | | FOR THE 'B' RHR PUMP (F004B) SIMULTANEOUSLY. THIS PROVIDED A DRAIN PATH | | FROM THE REACTOR VESSEL TO THE TORUS. THE EVENT WAS TERMINATED WHEN THE | | CONTAINMENT ISOLATION VALVES FOR THE SHUTDOWN COOLING SYSTEM (F008 AND | | F009) AUTOMATICALLY CLOSED DUE TO LOW REACTOR VESSEL LEVEL. | | | | PRIOR TO THE EVENT, REACTOR VESSEL WATER LEVEL WAS AT +60 INCHES. AS A | | RESULT OF THE EVENT, REACTOR VESSEL WATER LEVEL DROPPED TO +3 INCHES, | | CAUSING AN ISOLATION OF THE SHUTDOWN COOLING SYSTEM WHICH TERMINATED THE | | EVENT. THE LOWEST REACTOR VESSEL WATER LEVEL REACHED WAS APPROXIMATELY 0 | | INCHES. THIS LEVEL DECREASE OCCURRED IN ABOUT 1 MINUTE. REACTOR VESSEL | | WATER LEVEL, REMAINED ABOVE THE TOP OF ACTIVE FUEL (-160 INCHES) AT ALL | | TIMES. REACTOR VESSEL WATER LEVEL WAS RESTORED TO +53 INCHES AT 2155 | | THROUGH THE USE OF THE CONDENSATE TRANSFER SYSTEM. | | | | THE LICENSEE WAS IN THE PROCESS OF ATTEMPTING TO STROKE THE SHUTDOWN | | COOLING ISOLATION VALVE FOR THE 'B' RHR PUMP (F006B) FROM THE REMOTE | | SHUTDOWN PANEL. THE OPERATOR WHO WAS PERFORMING THIS WAS IN COMMUNICATION | | WITH OPERATORS IN THE CONTROL ROOM AT ALL TIMES. BOTH F006B AND F004B WERE | | SHUT PRIOR TO THE START OF THE TEST. WHEN THE OPERATOR OPENED THE F006B | | VALVE FROM THE REMOTE SHUTDOWN PANEL, THE F004B VALVE ALSO UNEXPECTEDLY | | OPENED. OPERATORS IMMEDIATELY RECOGNIZED THE PROBLEM, AND ATTEMPTED TO | | CLOSE THESE VALVES. HOWEVER, THE VALVES MUST GO FULLY OPEN BEFORE THEY CAN | | BE SHUT, AND THE CONTAINMENT ISOLATION VALVES FOR THE SHUTDOWN COOLING | | SYSTEM SHUT PRIOR TO THE F006B AND F004B VALVES SHUTTING. | | | | THE LICENSEE WAS PERFORMING THIS TEST AS A FOLLOWUP TO A SURVEILLANCE TEST | | THAT HAD RECENTLY BEEN PERFORMED FOR THE FIRST TIME. THE LICENSEE HAS NEW | | TECHNICAL SPECIFICATIONS IN PLACE THAT REQUIRE THE TESTING OF FUNCTIONS | | FROM THE REMOTE SHUTDOWN PANEL DURING EACH REFUELING OUTAGE. WHEN THE TEST | | WAS FIRST PERFORMED, THE F006B VALVE FAILED TO OPERATE FROM THE REMOTE | | SHUTDOWN PANEL. A WORK ORDER WAS INITIATED TO FIX THE PROBLEM AND THE | | LICENSEE WAS PERFORMING THIS TEST PER THE WORK ORDER TO VERIFY THAT THE | | VALVE HAD BEEN REPAIRED. | | | | THE LICENSEE IS INVESTIGATING WHY BOTH THE F006B AND F004B SUCTION VALVES | | OPENED AT THE SAME TIME. TORUS WATER LEVEL WENT OUT OF SPEC HIGH BECAUSE | | OF THIS EVENT AND HAS SINCE BEEN RESTORED TO ITS NORMAL BAND. APPROXIMATELY | | 12,000 GALLONS OF WATER WAS DRAINED FROM THE REACTOR TO THE TORUS. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+