U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/14/96 - 06/17/96 ** EVENT NUMBERS ** 30528 30631 30632 30633 30634 30635 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30528 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 05/22/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 19:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/22/96 | +------------------------------------------------+EVENT TIME: 17:55[EDT]| |NRC NOTIFIED BY: BRYAN HAMILTON |LAST UPDATE DATE: 06/14/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | |JOHN STOLZ NRR | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STEEL SPENT FUEL POOL LINER COULD BUCKLE AND LEAK AT TEMPERATURES ABOVE | | 180øF. | | | | THE DESIGN BASIS FOR THE SPENT FUEL POOL IS THAT IT WITHSTAND SUSTAINED | | BOILING CONDITIONS. THE LICENSEE FOUND THAT ABOVE 180øF, THERMAL EXPANSION | | COULD CAUSE BUCKLING OF THE LINER AND FAILURE OF WELD PLUGS WHICH SECURE | | THE LINER PLATES TO THE EXTERIOR OF THE SPENT FUEL POOL STRUCTURE. WITH | | THE LINER PERFORATED, SIGNIFICANT AND SUSTAINED POOL INVENTORY LOSS IS | | POSSIBLE. THIS IS OUTSIDE THE CURRENT DESIGN FOR THE SYSTEM. | | | | BASED ON CURRENT HEAT LOAD ASSUMPTIONS, THE LICENSEE CALCULATED THE MAXIMUM | | POSSIBLE TEMPERATURE TO BE 172øF IF LOSS OF POOL COOLING WERE TO OCCUR. | | THIS CALCULATION ASSUMES THAT AT LEAST ONE FUEL HANDLING BUILDING EXHAUST | | FAN REMAINS IN SERVICE DURING THE EVENT. THEREFORE, THE LICENSEE DOES NOT | | CONSIDER BUCKLING OF THE LINER TO BE POSSIBLE WITH THE CURRENT CONDITIONS | | IN THE SPENT FUEL POOL. THE LICENSEE IS EVALUATING THIS SITUATION AND IS | | STUDYING CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR, THE LOWER ALLOWAYS CREEK | | TOWNSHIP, AND THE NEW JERSEY BUREAU OF NUCLEAR ENGINEERING. | | | | * * * UPDATE @ 1733 ON 06/14/96 BY JOHN ROBERTSON ENTERED BY JOLLIFFE * * * | | | | FINAL SPENT FUEL POOL ENGINEERING CALCULATIONS PERFORMED BY THE LICENSEE | | INDICATE THAT THE SHEAR AND PULL-OUT FORCES ON THE SPENT FUEL POOL LINER | | PLUG WELDS ARE SIGNIFICANTLY REDUCED DUE TO THE DUCTILE PROPERTIES OF THE | | PLUG WELDS AND THE FLEXIBILITY OF THE CONCRETE EMBEDMENTS. THUS, THE | | SPENT FUEL POOL LINER IS CAPABLE OF MAINTAINING ITS INTEGRITY DURING | | BOILING CONDITIONS IN THE POOL. | | | | THEREFORE, THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THIS ISSUE HAS BEEN DISCUSSED WITH NRR STAFF MEMBERS ON 06/10/96. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R1DO KEN JENISON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30631 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 06/14/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 20:05 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 06/14/96 | +------------------------------------------------+EVENT TIME: 19:38[EDT]| |NRC NOTIFIED BY: WALTER NEUMAN |LAST UPDATE DATE: 06/14/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ES INDICATING LIGHT MATRIX SYSTEM TRANSFER SWITCH PROCURED AS NON-Q - | | | | DURING A REVIEW OF THE PLANT FUSE CONTROL PROGRAM, THE LICENSEE DISCOVERED | | THAT THE MANUAL TRANSFER SWITCH IN THE POWER LINE TO THE ENGINEERED | | SAFEGUARDS (ES) INDICATING LIGHT MATRIX SYSTEM WAS PROCURED AS NON-SAFETY | | RELATED (NON-Q) BUT SHOULD HAVE BEEN PROCURED AS SAFETY RELATED (Q). | | | | THE TRANSFER SWITCH PROVIDES POWER TO THE ES INDICATING LIGHT MATRIX FROM | | TWO DIFFERENT VITAL BUSES. THE SWITCH ENCLOSURE, SUPPORTS, AND BREAKERS | | HAVE BEEN EVALUATED TO MEET SEISMIC REQUIREMENTS. | | | | THE LICENSEE CONSIDERS THE SWITCH TO BE DEGRADED, BUT OPERABLE, PENDING | | FULL UPGRADE TO SAFETY RELATED STATUS. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTION AND WILL PROBABLY REPLACE | | THE SWITCH WITH ONE PROCURED AS SAFETY RELATED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30632 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 06/15/96 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 05:13 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 06/15/96 | +------------------------------------------------+EVENT TIME: 03:14[CDT]| |NRC NOTIFIED BY: SAND |LAST UPDATE DATE: 06/15/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 55 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR SCRAM FROM 30% POWER DUE TO A TURBINE TRIP. | | | | THE TURBINE TRIP WAS CAUSED BY A TURBINE GENERATOR LOAD REJECT SIGNAL. THE | | TRIP WAS INITIATED FOLLOWING A TURBINE RUNBACK FROM 55% POWER. THE RUNBACK | | WAS INITIATED DUE TO A BLOWN FUSE IN THE GENERATOR CONTROL PANEL. FOLLOWING | | LOSS OF POWER TO THE GENERATOR CONTROL PANEL, THEY LOWERED RECIRC FLOW TO | | MINIMUM AND DROVE RODS IN, WHICH RAN POWER BACK TO APPROXIMATELY 30% PRIOR | | TO THE TURBINE TRIP AND REACTOR SCRAM. ALL RODS FULLY INSERTED, AND THERE | | WAS NO ECCS INJECTION AND NO SAFETY RELIEF VALVES LIFTED. THE FUSE BLEW | | WHILE THEY WERE REPLACING A LIGHT BULB IN THE GENERATOR CONDITION MONITOR. | | THE FUSE HAS BEEN REPLACED, BUT THEY ARE STILL INVESTIGATING THE CAUSE OF | | THE EVENT. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30633 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 06/15/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/15/96 | +------------------------------------------------+EVENT TIME: 13:10[CDT]| |NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 06/15/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 +------------------------------------------------------------------------------+ | - DIESEL FIRE PUMP INOPERABLE DURING POST MAINTENANCE TESTING - | | | | THIS 24 HOUR REPORT IS BEING MADE IAW TECHNICAL SPECIFICATION 3.15.A.1. | | | | THE DIESEL FIRE PUMP WAS DECLARED INOPERABLE AT 1310 ON 6/15/96. THE | | CONTROL SWITCH WAS PLACED IN PULL TO LOCK WHILE POST MAINTENANCE TESTING | | WAS BEING PERFORMED. THE FIRE PUMP SWITCH WAS RETURNED TO THE AUTO | | POSITION AND THE PUMP WAS DECLARED OPERABLE AT 1331. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 30634 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SCHLUMBERGER TECHNOLOGY |NOTIFICATION DATE: 06/15/96 | | CITY: REGION: 4 |NOTIFICATION TIME: 20:00 [ET]| | COUNTY: STATE: LA |EVENT DATE: 06/14/96 | |LICENSE#: 42-0090-03 AGREEMENT: Y |EVENT TIME: 07:00[CDT]| | DOCKET: |LAST UPDATE DATE: 06/15/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN PELLET RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: GUY LOMBARDO | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | | | WELL LOGGING SOURCE EVENT | | | | NAME OF WELL OWNER: SHELL OFF SHORE, INC | | | | LOCATION OF THE WELL: OFF THE COAST OF LOUISIANA | | | | WELL IDENTIFICATION: VERMILLION BLOCK 370 OCSG 12880, WELL C-6, ADRIATIC 2 | | | | ISOTOPE & QUANTITY: Cs-137 1.7 Ci ; Am-241 10 Ci | | | | REQUEST FOR IMMEDIATE NRC APPROVAL TO BEGIN ABANDONMENT (Y/N): Y | | | | REGION 4 (LINDA HOWELL) CONTACTED | | | | A CONTACT NUMBER IS AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30635 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 06/15/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 23:51 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/15/96 | +------------------------------------------------+EVENT TIME: 21:30[CDT]| |NRC NOTIFIED BY: JAWORSKI |LAST UPDATE DATE: 06/15/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |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 SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION THAT COULD PROHIBIT PRESSURE RELIEF | | PANELS IN THE AUXILIARY BUILDING FROM FUNCTIONING AS THEY ARE REQUIRED. | | | | DURING THE PERFORMANCE OF A STRUCTURAL INSPECTION OF THE AUX BUILDING AS | | PER PROCEDURE "SE-PM-AE-1001"(AUXILIARY BUILDING STRUCTURAL INSPECTION), IT | | WAS REALIZED THAT 3 OF THE 4 PRESSURE RELIEF PANELS IN THE SOUTH END OF THE | | FLOOR OF ROOM 81 HAVE STRUCTURAL STEEL EQUIPMENT SUPPORTS AND BRACES | | ATTACHED TO THEIR TOP SURFACES WITH EXPANSION BOLTS. PER THE AUX BUILDING | | DESIGN BASIS DOCUMENT(SDBD-AUX-502 REV.7), "SUFFICIENT VENT AREA THROUGH | | DOORS AND PRESSURE RELIEF PANELS MUST BE PROVIDED TO LIMIT THE DIFFERENTIAL | | PRESSURE ACROSS WALLS AND SLABS TO 1.5PSI DUE TO THE PASSAGE OF A TORNADO". | | | | AN ANALYSIS WAS PERFORMED TO DETERMINE THE MINIMUM VENTING AREA NEEDED TO | | MEET THE DESIGN LIMIT OF THE 1.5 PSID. THE DIFFERENTIAL PRESSURE ACROSS THE | | ROOM 81 FLOOR ABOVE THE SWITCHGEAR ROOM IS PREDICTED TO EXCEED 1.5 PSID, | | EVEN IF ALL VENT PANELS ARE CREDITED AS FUNCTIONING. THIS IS BECAUSE FIRE | | DOORS PREVENT PRESSURE EQUALIZATION BETWEEN THE SWITCHGEAR AND UPPER | | ELECTRICAL PENETRATION ROOMS AND ONLY THE UPPER ELECTRICAL PENETRATION ROOM | | IS DIRECTLY VENTED TO ROOM 81(BY THE TORNADO VENT PANELS). IF THE DOORS ARE | | ASSUMED TO BE OPEN, ANALYSIS INDICATES THAT AT LEAST THREE OF THE FOUR VENT | | PANELS ARE REQUIRED TO ROOM 81 FLOOR DIFFERENTIALS TO 1.5 PSID. THE | | ANALYSIS FURTHER SHOWED THAT THE PANELS MUST LIFT ABOVE THE FLOOR TO | | DEVELOP ADEQUATE VENTING AREA. THE PIPING AND STAIRCASE SUPPORTS WOULD | | PREVENT THE REQUIRED MOVEMENT FROM OCCURRING. IT HAS THEREFORE BEEN | | CONCLUDED THAT THE ADDITION OF THE FIRE DOORS BETWEEN THE UPPER ELECTRICAL | | PENETRATION AND SWITCHGEAR ROOMS, ALONG WITH THE ANCHORAGE OF PIPING AND | | STAIRCASE RESTRAINTS TO THE TORNADO VENT PANELS, CAUSES A PLANT CONDITION | | OUTSIDE THE DESIGN BASIS AND CREATES AN UNANALYZED CONDITION. | | | | THE FOLLOWING CORRECTIVE ACTIONS WILL BE IMPLEMENTED PRIOR TO RCS | | TEMPERATURE EXCEEDING 300F. | | 1. REMOVE STRUCTURAL ATTACHMENTS TO THE TORNADO VENT PANELS. | | 2. OPEN THE FIRE DOORS BETWEEN THE ELECTRICAL PENETRATION AND SWITCHGEAR | | ROOMS AND POST FIRE WATCH, WHENEVER A TORNADO WATCH IS ISSUED FOR AN AREA | | INCLUDING THE PLANT SITE. THE INTERIOR DOORS OF THE PYROCRETE FIRE BARRIER | | WALL WITHIN THE UPPER ELECTRICAL PENETRATION ROOM SHOULD ALSO BE OPENED. | | | | IN THE LONG TERM THEY WILL DEVELOP AND IMPLEMENT APPROPRIATE ACTIONS TO | | RESOLVE THIS ISSUE. | | | | THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+