U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/29/94 - 05/02/94 ** EVENT NUMBERS ** 27082 27183 27184 27185 27186 27187 27188 27189 27190 27191 27192 27193 27194 27195 27196 27197 27198 27199 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27082 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/12/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:31 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/94 | +------------------------------------------------+EVENT TIME: 18:45[CDT]| |NRC NOTIFIED BY: DOUG BILLESBACH |LAST UPDATE DATE: 04/30/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 PRESSURE ENVELOPE INOPERABLE. | | | | THE LICENSEE PERFORMED A TEST OF THE INTEGRITY OF THE CONTROL ROOM PRESSURE | | ENVELOPE AFTER MAINTENANCE WAS COMPLETED ON A PRESSURE BOUNDARY DOOR. THE | | POST MAINTENANCE TESTING REVEALED THAT PRESSURE IN THE CABLE SPREADING ROOM | | WAS -0.01 INCHES OF WATER, WHEREAS THE ACCEPTANCE CRITERION IS POSITIVE | | PRESSURE. SINCE THE MAINTENANCE PERFORMED DID NOT AFFECT ANY DOOR SEALS, | | INVESTIGATION IS UNDERWAY TO DETERMINE THE CAUSE OF THE FAILURE. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * UPDATE DATE/TIME:4/30/94 @ 1724 EDT**FROM LICENSEE:HITZEL BY:McGINTY* | | THE FOLLOWING IS A FAXED UPDATE SUBMITTED BY THE LICENSEE: | | "THE CONTROL ROOM EMERGENCY VENTILATION SYSTEM WAS DECLARED INOPERABLE ON | | APRIL 11 UPON INITIATING MAINTENANCE FOR AN ENVELOPE DOOR. THE SYSTEM DID | | NOT PASS SUBSEQUENT POST MAINTENANCE TESTING. THE TECHNICAL SPECIFICATION | | LCO FOR THIS SYSTEM IS 7 DAYS. ENFORCEMENT DISCRETION WAS GRANTED BY | | REGION IV, EXTENDING THIS LCO UNTIL MAY 2. TO CORRECT THE CONDITION, DOOR | | SEALS FOR THE ENVELOPE DOORS WERE REFURBISHED, AND AN EXTENSIVE SEARCH WAS | | CONDUCTED TO IDENTIFY LEAKAGE PATHS WHICH WOULD BE DETRIMENTAL TO | | MAINTAINING A POSITIVE PRESSURE. SUBSEQUENT TO SEALING THE LEAKAGE PATHS, | | THE SYSTEM WAS BALANCED AND THE APPROPRIATE SURVEILLANCE CONDUCTED. TESTS | | WERE CONDUCTED TO VERIFY THAT THE VENTILATION SYSTEMS FOR ADJACENT SPACES | | DID NOT PREVENT OBTAINING A POSITIVE PRESSURE. UPON COMPLETION OF THE | | TESTING AND ESTABLISHMENT OF PROCEDURES FOR INTERIM ACTIONS, THE SYSTEM WAS | | DECLARED OPERABLE. WRITTEN NOTIFICATION OF THE COMPLETION OF THESE ACTIONS | | WILL BE PROVIDED TO REGION IV ON MAY 2." | | END OF TEXT | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED THE R4DO | | (CAIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27183 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 04/29/94 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 00:52 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/28/94 | +------------------------------------------------+EVENT TIME: 21:44[EDT]| |NRC NOTIFIED BY: BENSON |LAST UPDATE DATE: 04/29/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT DISCOVERED A CONDITION WHERE SOME OF THEIR INSTRUMENT TUBING MAY | | NOT MEET SEISMIC DESIGN CRITERIA. | | | | DURING A WALKDOWN OF THE PRIMARY COOLANT PUMP SEAL PRESSURE INSTRUMENT | | TUBING, THEY DISCOVERED THAT SOME OF THE TUBING IS NOT PROPERLY MOUNTED IN | | ACCORDANCE WITH THE PLANT SEISMIC DESIGN CRITERIA. BECAUSE OF THIS, THEY | | ARE UNCERTAIN THAT THE LINE WILL SURVIVE A SEISMIC EVENT. IF THE LINE DID | | FAIL, THEY WOULD HAVE A CONDITION OF A SMALL BREAK LOCA. THE CAUSE OF WHY | | THE TUBING IS NOT PROPERLY MOUNTED IS BEING INVESTIGATED. AN ANALYSIS IS | | ALSO BEING MADE TO VERIFY WHETHER OR NOT THE TUBING COULD MEET THE SEISMIC | | DESIGN CRITERIA IN ITS PRESENT CONFIGURATION. THIS PROBLEM WILL BE RESOLVED | | BEFORE PLANT HEATUP. THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/29/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 02:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/29/94 | +------------------------------------------------+EVENT TIME: 00:46[EDT]| |NRC NOTIFIED BY: VARGA |LAST UPDATE DATE: 04/29/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN ESF ACTUATION WHEN THEY RECEIVED AN AUTO START OF THE #11 | | MOTOR DRIVEN AUX FEEDWATER PUMP. | | | | THIS OCCURRED WHILE THEY WERE BREAKING CONDENSER VACUUM AND BOTH S/G FEED | | PUMPS RECEIVED A FIRST OUT TRIP SIGNAL WHEN VACUUM WAS REDUCED TO 0 PSIG. | | THIS FIRST OUT TRIP SIGNAL AUTOMATICALLY SENDS A START SIGNAL TO THE MOTOR | | DRIVEN AUX FEED PUMPS. THE # 11 AUX FEED PUMP HAD BEEN TEMPORARILY | | RELEASED FOR TESTING ON THE DAY SHIFT(4/28/94) AND HAD NOT BEEN RETAGGED | | FOR SHIFT SUPERVISOR. SINCE THIS PUMP HAD NOT BEEN RETAGGED, IT STARTED ON | | THE AUTO START SIGNAL. THE PUMP WAS SECURED WITHIN 5 MINS. THE RI WAS | | INFORMED AND LAC TOWNSHIP WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27185 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 04/29/94 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 03:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/29/94 | +------------------------------------------------+EVENT TIME: 02:02[CDT]| |NRC NOTIFIED BY: BROWN |LAST UPDATE DATE: 04/29/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAD AN ESF ACTUATION WHEN THE #21 EMERGENCY | | DIESEL GENERATOR AUTO STARTED, BUT DID NOT LOAD. | | | | THIS OCCURRED APPROXIMATELY 10 MINS AFTER I & C HAD COMPLETED A | | SURVEILLANCE ON # 21 SEQUENCER, BUT THIS SHOULD NOT HAVE CAUSED THE AUTO | | START. THEIR INITIAL INVESTIGATION HAS NOT DETERMINED THE CAUSE FOR THE | | AUTO START. D/G #21 WAS SHUT DOWN AFTER 30 MINS AND DECLARED INOPERABLE | | PENDING ENGINEERING INVESTIGATION. THEY ALSO ENTERED AN LCO ACTION | | STATEMENT WITH 2 D/G'S INOPERABLE(D/G # 21 AND ALSO D/G #22 BEING | | INOPERABLE BUT FUNCTIONAL) WHERE THEY HAVE TO SUSPEND ALL CORE ALTERATIONS | | AND POSITIVE REACTIVITY, AND WITHIN 8 HRS DEPRESSURIZE AND VENT TO A TWO | | INCH VENT. THEY ARE CURRENTLY VENTED AND THEY ARE NOT DOING ANY CORE | | ALTERATIONS OR POSITIVE REACTIVITY. THE RI WAS INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27186 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/29/94 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 09:47 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/29/94 | +------------------------------------------------+EVENT TIME: 09:06[EDT]| |NRC NOTIFIED BY: STEVEN SUDIGALA |LAST UPDATE DATE: 04/29/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE, LOCAL, AND OTHER FEDERAL AGENCIES OF AN OIL | | RELEASE TO LONG ISLAND SOUND. | | | | THE LICENSEE WAS PUMPING A PLANT SUMP TO STORM DRAINS WHEN IT WAS | | DISCOVERED THAT THE SUMP CONTAINED A SMALL QUANTITY OF OIL THAT HAD | | EVIDENTLY LEAKED FROM NON-CONTAMINATED PLANT EQUIPMENT. THE LICENSEE | | ESTIMATES THAT THE TOTAL VOLUME OF OIL RELEASE WAS LESS THAN ONE GALLON. | | THE SPILL IS CONTAINED WITHIN AN OIL BOOM. | | | | THE COAST GUARD, DEPARTMENT OF ENVIRONMENTAL PROTECTION FOR CONNECTICUT, | | AND LOCAL OFFICIALS HAVE BEEN NOTIFIED. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED OF THESE NOTIFICATIONS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27187 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/29/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 16:58 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/29/94 | +------------------------------------------------+EVENT TIME: 16:35[EDT]| |NRC NOTIFIED BY: NOLL |LAST UPDATE DATE: 04/29/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RECENTLY RE-TUBED TURBINE BUILDING SECONDARY COOLING WATER HEAT EXCHANGERS | | WERE RE-ROLLED TO A HIGHER TORQUE VALUE DUE TO POSSIBLE FAILURE. | | | | THE LICENSEE HAS DETERMINED THAT THE TURBINE BUILDING SECONDARY COOLING | | WATER HEAT EXCHANGERS DID NOT MEET DESIGN REQUIREMENTS. THE CAUSE IS THE | | FAILURE OF A DESIGN CHANGE IMPLEMENTATION, AND HAS NO EFFECT ON THE PLANT | | IN THE CURRENT MODE. | | | | THE LICENSEE RE-TUBED THESE HEAT EXCHANGERS IN 1993 WITH A DIFFERENT | | MATERIAL. PRIOR TO THE RE-TUBING, THE TUBE AND THE TUBE SHEET WERE WELDED | | TOGETHER. WHEN THE NEW TUBES WERE PUT IN, THE NEW TUBE MATERIAL DID NOT | | ALLOW WELDING TO THE TUBE SHEET, SO THEY WERE ROLLED INSTEAD. SUBSEQUENT | | EVALUATION DETERMINED THAT UNDER EXTREME OPERATING CONDITIONS (STILL WITHIN | | DESIGN), THE TEMPERATURES IN THE FLUID SYSTEM COULD LEAD TO A TUBE FAILURE | | AT THE TUBE SHEET SINCE THEY WERE NOT WELDED. THE LICENSEE HAS RE-ROLLED | | THE TUBES TO A HIGHER TORQUE VALUE AS A CORRECTIVE ACTION. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR, THE STATE AND LOCAL | | AUTHORITIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27188 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 04/29/94 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 18:59 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/29/94 | +------------------------------------------------+EVENT TIME: 15:13[EDT]| |NRC NOTIFIED BY: SLEEPER |LAST UPDATE DATE: 04/29/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SIGNS IN CONTAINMENT NOT PROPERLY SECURED AND COULD BLOCK THE SUMP SCREENS | | DURING A DBA. | | | | DURING A CONTAINMENT WALKDOWN IT WAS DETERMINED THAT AN EXCESSIVE AMOUNT OF | | LABELING AND SIGNS ARE NOT PROPERLY SECURED. SOME INSTANCES OF THE SIGNS | | BEING SECURED WITH DOUBLE SIDED TAPE OR OTHER INAPPROPRIATE METHODS HAVE | | BEEN FOUND, VICE BEING PROPERLY SECURED WITH STEEL BOLTING. THIS MATERIAL | | COULD COME LOOSE DURING A DESIGN BASIS ACCIDENT AND POTENTIALLY RESTRICT | | FLOW FROM THE CONTAINMENT SUMP TO THE CONTAINMENT SPRAY PUMPS AND THE HIGH | | PRESSURE SAFETY INJECTION PUMPS. THE CONTAINMENT SPRAY PUMPS AND HIGH | | PRESSURE SPRAY PUMPS ARE CONSIDERED INOPERABLE UNTIL THIS PROBLEM IS | | CORRECTED. ALL EQUIPMENT REQUIRED IN THE CURRENT PLANT MODE (COLD | | SHUTDOWN) IS OPERABLE. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27189 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 04/29/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 19:03 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 04/29/94 | +------------------------------------------------+EVENT TIME: 13:15[PDT]| |NRC NOTIFIED BY: SWANK |LAST UPDATE DATE: 04/29/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | RWCU ISOLATION LOGIC AND SYSTEM COMPONENTS WERE NEVER ANALYZED FOR A FIRE. | | | | THE LICENSEE HAS DETERMINED THAT THE ISOLATION LOGIC AND SYSTEM COMPONENTS | | FOR REACTOR WATER CLEANUP ARE NOT PROPERLY PROTECTED TO MEET THE | | REQUIREMENTS OF APPENDIX R FOR SAFE SHUTDOWN. THIS IS AN INTER-SYSTEM LOCA | | CONCERN. | | | | THE LICENSEE HAS DISCOVERED THAT THE RWCU SYSTEM ISOLATION LOGIC AND SYSTEM | | COMPONENTS HAVE NEVER BEEN ANALYZED FOR A FIRE. THE SYSTEMS AFFECTED ARE | | NOT REQUIRED TO BE OPERABLE IN THE CURRENT MODE, AND THE LICENSEE IS | | WORKING ON CORRECTIVE ACTIONS (PERFORMING AN ANALYSIS, PROVIDE THE REQUIRED | | PROTECTION OR PROCEDURAL GUIDANCE). THE LICENSEE THINKS THAT THIS PROBLEM | | IS NOT COMMON TO ANY OTHER SYSTEMS, AND DID NOT KNOW WHY THE ANALYSIS HAD | | NEVER BEEN PERFORMED. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27190 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/30/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 07:14 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/30/94 | +------------------------------------------------+EVENT TIME: 04:12[CDT]| |NRC NOTIFIED BY: TERMINI |LAST UPDATE DATE: 04/30/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 75 POWER OPERATION | 75 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LOSS OF POWER TO THE REACTOR BUILDING VENTILATION SYSTEM OCCURRED DUE TO | | A SHORTED RELAY. | | | | A LOSS OF CONTROL POWER TO REACTOR BUILDING VENTILATION SUPPLY OUTBOARD | | DAMPERS "2VR04YA" AND "2VR04YV" OCCURRED WHEN RELAY "2ZS-VR002AX" FROM | | MOTOR CONTROL CENTER "235X1", CIRCUIT 16, SHORTED. OPERATORS DISABLED THE | | TWO MAIN STEAM LINE ISOLATION SIGNALS (HIGH STEAM TUNNEL TEMPERATURE, HIGH | | DELTA TEMPERATURE) TO PREVENT AN MSIV ISOLATION WHILE CONTROL POWER WAS | | RESTORED TO THE DAMPERS. THE ISOLATION SIGNALS, AS WELL AS SECONDARY | | CONTAINMENT, WERE DECLARED INOPERABLE AND THE UNIT ENTERED TECHNICAL | | SPECIFICATION (T/S) ACTION STATEMENTS 3.3.2 (1-HOUR LCO) AND 3.6.5.1 | | (4-HOUR LCO). | | | | THE BLOWN RELAY WAS ELECTRICALLY ISOLATED AND BYPASSED. CONTROL POWER TO | | THE DAMPERS WAS RESTORED WITHIN 58 MINUTES. THE SHORTED RELAY WILL BE | | REPLACED. ALL SAFETY BUSES WERE ENERGIZED THROUGHOUT THE EVENT AND AT NO | | TIME WERE ANY OTHER ESF OR ECCS LOADS INOPERABLE. THE CAUSE OF THE SHORTED | | CIRCUIT IS UNDER INVESTIGATION. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | * UPDATE DATE/TIME:4/30/94 @ 1420 EDT *FROM LICENSEE:ENTWISTLE BY:McGINTY* | | THE LICENSEE RETRACTED THIS EVENT AFTER FURTHER DISCUSSION WITH THE LASALLE | | COUNTY STATION REGULATORY ASSURANCE DEPARTMENT. THIS IS BASED ON FURTHER | | REVIEW OF THE REPORTABILITY MANUAL, SPECIFICALLY SECTION SAF 1.12, PAGE 6 | | OF 7, ITEM NUMBER 6. THIS STEP READS AS FOLLOWS: A LIMITED SET OF | | SPECIFICALLY DEFINED, INVALID ESF ACTUATIONS ARE NOT REPORTABLE BECAUSE OF | | THEIR LIMITED SAFETY SIGNIFICANCE. INCLUDED IS THE INVALID ACTUATION, | | ISOLATION , OR REALIGNMENT OF THE VENTILATION SYSTEMS (OR THEIR | | EQUIVALENT), FOR THE CONTROL ROOM, REACTOR BUILDING, OR AUXILIARY BUILDING. | | THEREFORE, THE LOSS OF POWER TO THE REACTOR BUILDING VENTILATION SUPPLY | | OUTBOARD DAMPERS "2VRO4YA AND 2VRO5YB", DUE TO A SHORTED RELAY | | "2ZS-VROO2AX", IS TO BE CONSIDERED AN INVALID ESF ACTUATION OF THE REACTOR | | BUILDING VENTILATION SYSTEM. THE LICENSEE WILL INFORM THE RESIDENT | | INSPECTOR. HOO NOTIFIED THE R3DO (SHEAR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27191 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/30/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 08:52 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/30/94 | +------------------------------------------------+EVENT TIME: 08:41[EDT]| |NRC NOTIFIED BY: NELSON |LAST UPDATE DATE: 04/30/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN INADEQUATE ISOLATION BETWEEN CLASS 1E AND NON-CLASS 1E SYSTEMS WAS | | FOUND. | | | | DURING A REVIEW OF THE ELECTRICAL SYSTEM, IT WAS DISCOVERED THAT THE | | ISOLATION TRANSFORMER WHICH SEPARATES THE REACTOR REGULATING SYSTEM, A | | NON-CLASS 1E SYSTEM, FROM THE AUXILIARY FEEDWATER SYSTEM (AFW), A CLASS 1E | | SYSTEM, DOES NOT MEET CURRENT ISOLATION REQUIREMENTS. THE REACTOR | | REGULATING SYSTEM PROVIDES AN ACTUATION SIGNAL TO THE AFW SYSTEM DURING AN | | ATWS CONDITION. THE INTERFACE BETWEEN THE TWO SYSTEMS OCCURS IN A "SPEC | | 200" CABINET WHICH WAS INSTALLED WITHIN THE LAST 4 YEARS. THIS CONSTITUTES | | INADEQUATE SEPARATION OF CLASS 1E AND NON-CLASS 1E SYSTEMS AND IS A | | CONDITION OUTSIDE OF THE DESIGN BASIS OF THE PLANT. | | | | THE WORST-CASE SCENARIO RESULTING FROM THIS CONDITION IS THAT AN ACTUATION | | OF THE AFW SYSTEM WOULD OCCUR WHEN PLANT CONDITIONS DID NOT WARRANT SUCH AN | | ACTUATION. AN ANALYSIS INDICATES THAT THE INADEQUATE SEPARATION CONDITION | | WOULD NOT PREVENT AN AFW ACTUATION. | | | | THE CORRECTIVE ACTION IS TO THE REPLACE THE EXISTING ISOLATION TRANSFORMER | | WITH A QUALIFIED ISOLATION TRANSFORMER. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. STATE AND LOCAL AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27192 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/30/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:25 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/30/94 | +------------------------------------------------+EVENT TIME: 14:50[EDT]| |NRC NOTIFIED BY: RIDDLE |LAST UPDATE DATE: 04/30/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 60 POWER OPERATION | 60 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SMALL OIL DISCHARGE TO THE DELAWARE RIVER WHILE TESTING A FIRE TRUCK. | | | | THE LICENSEE MADE OFF-SITE NOTIFICATIONS TO THE COAST GUARD, STATE AND | | LOCAL AUTHORITIES REGARDING THE DISCHARGE OF A HAZARDOUS SUBSTANCE INTO THE | | DELAWARE RIVER. DURING TESTING OF THE ABILITY TO PRIME THE MAIN | | CENTRIFUGAL PUMPS OF A FIRE TANKER TRUCK, THE PRIMING PUMP (ROTARY VANED | | VACUUM TYPE) SPILLED SOME OIL ON THE CONCRETE, AND ABOUT ONE PINT OF THE | | SAE-30W OIL MADE IT INTO THE DELAWARE RIVER. THE SPILL WAS CLEANED UP TO | | THE MAXIMUM EXTENT POSSIBLE, AND THE SMALL OIL SHEEN ON THE RIVER WAS | | OBSERVED TO BREAK UP VERY QUICKLY. THE LICENSEE WILL BE INVESTIGATING THE | | OPERATION OF THE VACUUM PUMP. THE PLANT IS OPERATING NORMALLY AT 60%, | | REDUCED IN POWER FOR DIGITAL FEEDWATER SYSTEM TESTING DURING THE WEEKEND. | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27193 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/01/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 01:35 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/30/94 | +------------------------------------------------+EVENT TIME: 23:35[CDT]| |NRC NOTIFIED BY: LIZALEK |LAST UPDATE DATE: 05/01/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 99 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A MANUAL SCRAM WAS INITIATED DUE TO A LOSS OF INSTRUMENT AIR PRESSURE. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "ON 4/30/94 AT 2335CDT UNIT 2 EXPERIENCED A LOSS OF INSTRUMENT AIR DUE TO | | DISCHARGE PIPE SHEAR ON 2A IAC. THE REACTOR WAS MANUALLY SCRAMMED WHEN | | INST. AIR PRESSURE WAS 55 PSIG AS REQUIRED BY PROCEDURE. THE ISOLATION | | CONDENSER WAS MANUALLY INITIATED TO AUGMENT REACTOR PRESSURE CONTROL. | | ADDITIONALLY, DEOP 300-1 WAS ENTERED DUE TO WEST CRD MODULE AND HPCI | | CUBICLE RADIATION LEVELS EXCEEDING MAXIMUM NORMAL. THE MAXIMUM SAFE LEVELS | | WERE NEVER EXCEEDED. MAX NORMAL LEVEL FOR WEST CRD MODULE WAS 500 MR AS | | READ BY THE RADIATION TECHNICIAN AND 40 MR FOR THE HPCI CUBICLE AREA. THE | | MAX SAFE LEVEL IS 2500 MR." | | END OF TEXT. | | | | WITH INSTRUMENT AIR COMPRESSOR "2A" IN SERVICE, A SHEAR OF THE DISCHARGE | | LINE FROM ITS ASSOCIATED AIR RECEIVER RESULTED IN A LOSS OF INSTRUMENT AIR. | | NORMAL AIR PRESSURE IN THE INSTRUMENT AIR SYSTEM IS 100 PSIG. AS AIR | | PRESSURE DECREASED TO 85 PSIG, A SERVICE AIR SYSTEM CROSSTIE OPENED AND THE | | SERVICE AIR COMPRESSOR ATTEMPTED TO MAINTAIN AIR PRESSURE. HOWEVER, AIR | | PRESSURE CONTINUED TO DECREASE. AT 55 PSIG, OPERATORS MANUALLY SCRAMMED | | THE PLANT AND CLOSED THE MAIN STEAM ISOLATION VALVES (MSIVs) PER PROCEDURE. | | AT 45 PSIG, THE SHEARED LINE WAS ISOLATED AND INSTRUMENT AIR COMPRESSOR | | "2B" WAS PLACED IN SERVICE TO RESTORE AIR PRESSURE. | | | | ALL RODS FULLY INSERTED ON THE REACTOR SCRAM. NO ECCS ACTUATIONS OCCURRED. | | AT REACTOR LEVEL OF (+8) INCHES, A GROUP 2 (DRYWELL ISOLATION VALVES AND | | REACTOR BUILDING VENTILATION VALVES) ISOLATION, GROUP 3 (REACTOR WATER | | CLEANUP) ISOLATION, AND STANDBY GAS TREATMENT SYSTEM (SBGT) ACTUATION | | OCCURRED. MINIMUM REACTOR LEVEL WAS (-3) INCHES. NO RELIEF OR SAFETY | | VALVES LIFTED DURING THE SCRAM. OPERATORS MANUALLY ACTUATED THE ISOLATION | | CONDENSER TO ASSIST IN REACTOR PRESSURE CONTROL. MAXIMUM REACTOR PRESSURE | | WAS 1090 PSIG. ALL SAFETY LOADS TRANSFERRED TO OFFSITE POWER PROPERLY. | | | | DURING THE PLANT TRANSIENT FOLLOWING THE SCRAM, REACTOR WATER LEVEL REACHED | | A MAXIMUM OF 63 INCHES. THIS RESULTED IN REACTOR WATER ENTERING THE HIGH | | PRESSURE COOLANT INJECTION (HPCI) STEAM SUPPLY LINE (AT APPROXIMATELY 60 | | INCHES REACTOR WATER LEVEL) CAUSING ELEVATED RADIATION MEASUREMENTS IN THE | | HPCI CUBICLE AND WEST CONTROL ROD DRIVE MODULE (WHICH IS ADJACENT TO THE | | HPCI STEAM SUPPLY LINE). THE REACTOR WATER WAS DRAINED FROM THE HPCI STEAM | | SUPPLY LINE AND DISCHARGED TO THE TORUS VIA THE NORMAL DRAIN SYSTEM. THE | | REASON FOR THE HIGH REACTOR WATER LEVEL WAS THAT FEED REGULATING VALVE "2A" | | DID NOT ISOLATE AT THE FEEDWATER ISOLATION SETPOINT OF 55 INCHES (REACTOR | | WATER LEVEL). THE ISOLATION DID NOT OCCUR BECAUSE THE VALVE WAS IN"MANUAL" | | AT THE TIME OF THE ISOLATION SIGNAL. THIS VALVE HAS HAD A HISTORY OF | | INSTABILITY AND HAS BEEN KEPT IN "MANUAL" PER PROCEDURE. OPERATORS FAILED | | TO CLOSE THIS FEED REGULATING VALVE IN TIME TO PREVENT REACTOR WATER LEVEL | | FROM REACHING THE HPCI STEAM SUPPLY LINE. | | | | CURRENTLY, THE UNIT IS STABLE IN HOT SHUTDOWN. THE REACTOR FEEDWATER | | SYSTEM IS SUPPLYING WATER TO THE VESSEL. THE ISOLATION CONDENSER HAS BEEN | | SECURED AND MSIVs OPENED. THE CONDENSER WILL BE RETURNED TO SERVICE | | SHORTLY. OFFSITE POWER IS STABLE AND SUPPLYING ALL SAFETY LOADS. THE | | EMERGENCY DIESEL GENERATORS (EDGs) AND ECCS ARE FULLY OPERABLE. | | | | THE CAUSE OF THE SHEAR IS UNDER INVESTIGATION. THE LICENSEE WILL INFORM | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27194 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 05/01/94 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 04:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/01/94 | +------------------------------------------------+EVENT TIME: 01:40[EDT]| |NRC NOTIFIED BY: GIBBS |LAST UPDATE DATE: 05/01/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 49 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A REACTOR TRIP OCCURRED ON A TURBINE TRIP DUE TO A LOSS OF MAIN FEEDWATER. | | | | WITH FEED PUMP "B" SHUTDOWN FOR MAINTENANCE, A TECHNICIAN MISTAKENLY OPENED | | A BREAKER WHICH SUPPLIED POWER TO AN OIL PUMP ASSOCIATED WITH THE "A" FEED | | PUMP (INSTEAD OF THE "B" PUMP AS INTENDED). THIS RESULTED IN A TRIP OF THE | | "A" FEED PUMP, A TURBINE TRIP ON LOSS OF FEED, AND A REACTOR TRIP (ON THE | | TURBINE TRIP DUE TO THE P-9 INTERLOCK). ALL RODS FULLY INSERTED ON THE | | REACTOR TRIP. ALL THREE AUXILIARY FEEDWATER (AFW) PUMPS (2 MOTOR-DRIVEN, 1 | | TURBINE-DRIVEN) INITIATED ON THE REACTOR TRIP AND INJECTED APPROXIMATELY | | 1700 GPM OF WATER INTO THE STEAM GENERATORS (SGs). THIS CAUSED REACTOR | | COOLANT SYSTEM (RCS) TEMPERATURE TO DECREASE FROM THE NO-LOAD Tave OF 547 | | DEGREES F TO A LOW OF 534 DEGREES F. A FEEDWATER ISOLATION OCCURRED ON THE | | REACTOR TRIP WITH LOW Tave AND A LETDOWN ISOLATION ON LOW (17%) PRESSURIZER | | LEVEL (DUE TO THE SHRINK). OPERATORS TOOK MANUAL CONTROL OF THE AFW SYSTEM | | AND THROTTLED FLOW (TO INCREASE RCS TEMPERATURE) AND INITIATED EMERGENCY | | BORATION (TO MAINTAIN SHUTDOWN MARGIN) AS PRESCRIBED IN THE EMERGENCY | | OPERATING PROCEDURES. APPROXIMATELY 900 GALLONS OF 20,000 PPM-BORATED | | WATER WAS INJECTED INTO THE RCS. ONCE OPERATORS THROTTLED AFW FLOW, RCS | | TEMPERATURE INCREASED TO THE NO-LOAD Tave SETPOINT OF 547 DEGREES F. | | | | NO ECCS ACTUATIONS OR OTHER ESF ACTUATIONS OCCURRED DURING THE TRIP. NO | | PORVs OR SAFETIES LIFTED ON THE PRIMARY SIDE AND NO RELIEF VALVES OR | | SAFETIES ON THE SECONDARY LIFTED. THE TRANSFER OF SAFETY LOADS TO OFFSITE | | POWER OCCURRED PROPERLY. | | | | CURRENTLY, THE UNIT IS STABLE IN HOT STANDBY. BOTH OF THE MOTOR-DRIVEN AFW | | PUMPS ARE SUPPLYING THE SGs AND DECAY HEAT IS BEING DISSIPATED BY THE | | CONDENSER. OFFSITE POWER IS STABLE AND SUPPLYING ALL OF THE SAFETY LOADS. | | THE EMERGENCY DIESEL GENERATORS AND ALL ECCS EQUIPMENT ARE OPERABLE. | | | | AN INVESTIGATION INTO THE CAUSE OF THE TRIP IS ONGOING. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27195 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/01/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 06:08 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/01/94 | +------------------------------------------------+EVENT TIME: 03:39[CDT]| |NRC NOTIFIED BY: NORRIS |LAST UPDATE DATE: 05/01/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VARIOUS ISOLATIONS AND A HALF-SCRAM OCCURRED WHEN A RELAY FAILED RESULTING | | IN A LOSS OF POWER TO THE DIVISION TWO REACTOR PROTECTION SYSTEM (RPS) | | LOGIC. | | | | WHILE PERFORMING MAINTENANCE ON THE NORMAL DIVISION TWO RPS POWER SUPPLY, | | THE ALTERNATE POWER SUPPLY FOR THE DIVISION TWO RPS TRIPPED WHEN A RELAY IN | | THE ISOLATION LOGIC FAILED. THIS RESULTED IN AN INBOARD ISOLATION OF THE | | FOLLOWING SYSTEMS: REACTOR WATER CLEANUP, SPENT FUEL POOL COOLING, REACTOR | | PLANT COMPONENT COOLING WATER, REACTOR RECIRCULATION HYDRAULICS, REACTOR | | RECIRCULATION SAMPLE, AUXILIARY BUILDING VENTILATION, CONTAINMENT DRYWELL | | CHILLED WATER, CONTAINMENT DRYWELL DRAINS, AND CONTAINMENT AIR LOCK AIR | | SUPPLY. ALSO, A HALF-SCRAM OCCURRED AS A RESULT OF THE LOSS OF POWER TO | | THE DIVISION TWO RPS. A PRELIMINARY INVESTIGATION FOUND A FAILED COIL IN | | THE REFERENCED RELAY. THE INVESTIGATION IS ONGOING. | | | | THE AFFECTED SYSTEMS WILL BE RE-ALIGNED ONCE THE RELAY IS REPLACED. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27196 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 05/01/94 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 12:14 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/01/94 | +------------------------------------------------+EVENT TIME: 10:30[EDT]| |NRC NOTIFIED BY: CROSSMAN |LAST UPDATE DATE: 05/01/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SMALL OIL LEAK INTO THE NORTH ANNA RIVER FROM A HYDRO UNIT AT THE DAM. | | | | NORTH ANNA IS RESPONSIBLE FOR THE MAINTENANCE AND OPERATION OF VIRGINIA | | POWER HYDRO UNITS AT THE NORTH ANNA DAM. AN OFFSITE NOTIFICATION WAS MADE | | TO THE NATIONAL RESPONSE CENTER AND THE VIRGINIA DEPARTMENT OF EMERGENCY | | SERVICES DUE TO A 2-3 GALLON OIL LEAK THAT ENTERED THE NORTH ANNA RIVER. | | THE LEAK WAS FROM THE HYDRO UNIT "05-EP-EE-1" HYDRAULIC OIL SYSTEM. THE | | LEAK IS STOPPED AND OIL HAS BEEN WIPED UP FROM THE AREA. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27197 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/01/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 17:11 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/01/94 | +------------------------------------------------+EVENT TIME: 14:35[CDT]| |NRC NOTIFIED BY: BUSH |LAST UPDATE DATE: 05/01/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALTERNATE POWER SUPPLY FOR THE DIVISION 2 RPS RESULTED IN INBOARD | | ISOLATIONS AND A HALF-SCRAM. | | | | A TRIP OF THE DIVISION 2 REACTOR PROTECTION SYSTEM (RPS) ALTERNATE POWER | | SUPPLY OCCURRED WHILE IT WAS SUPPLYING THE RPS BUS. THIS RESULTED IN A | | DIVISION 2 INBOARD ISOLATION OF THE FOLLOWING SYSTEMS: | | -REACTOR WATER CLEANUP | | -SPENT FUEL POOL COOLING | | -REACTOR PLANT COMPONENT COOLING | | -REACTOR RECIRC SYSTEM HYDRAULICS | | -REACTOR RECIRC SAMPLE | | -AUXILIARY BLDG. VENTILATION | | -CONTAINMENT/DRYWELL CHILLED WATER | | -CONTAINMENT AIRLOCK AIR SUPPLY | | | | AN RPS HALF-SCRAM ALSO RESULTED. THE DIVISION 2 RPS NORMAL SUPPLY WAS OUT | | OF SERVICE FOR MAINTENANCE DURING THIS EVENT. THE CAUSE FOR THE EVENT IS | | UNDER INVESTIGATION. THE ISOLATION GENERATED IS EXACTLY THE SAME THAT | | OCCURRED EARLIER TODAY (SEE SIMILAR EVENT #27195). THIS TIME, HOWEVER, THE | | ISOLATION RELAY IS NOT BURNED UP, SO THE LICENSEE IS STILL TRYING TO | | IDENTIFY THE ROOT CAUSE OF BOTH EVENTS. THE LICENSEE REPLACED THE BURNED | | UP RELAY FROM THE EARLIER EVENT, RESET THE ISOLATION AND RESTORED AIR TO | | THE CONTAINMENT AIRLOCKS. A SHORT WHILE LATER, WHILE ALL THE VALVES | | REMAINED CLOSED FROM THE PREVIOUS ISOLATION, THE SIMILAR ISOLATION WAS | | GENERATED. THE LICENSEE INFORMED THE RESIDENT INSPECTOR, WHO WAS IN THE | | CONTROL ROOM THIS AFTERNOON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27198 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 05/01/94 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 22:20 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/01/94 | +------------------------------------------------+EVENT TIME: 21:02[CDT]| |NRC NOTIFIED BY: BIENKE |LAST UPDATE DATE: 05/01/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FISSION PRODUCT MONITOR TRIPPED OFF WHEN THE "B" RPS MG SET TRIPPED OFF. | | | | UNIT 1 HAD THE "B" RPS MG SET TRIP ON HIGH VOLTAGE DUE TO A LOOSE LUG ON | | THE DOWNSTREAM RPS BUS. THE TRIP OF THE "B" RPS MG SET CAUSED THE | | FOLLOWING: | | | | -A HALF SCRAM AND A HALF GROUP ONE ISOLATION | | -A REACTOR WATER CLEANUP TRIP | | -A PARTIAL GROUP 2 AND GROUP 5 ISOLATION | | -FISSION PRODUCT MONITOR TRIPPED OFF (PART OF GROUP2) | | -CONTROL ROOM VENTILATION TO PRESSURIZATION MODE | | | | THE PORTION OF THE REPORT THAT IS SPECIFICALLY REPORTABLE IS THE FISSION | | PRODUCT MONITOR TRIPPING OFF AS PART OF THE GROUP 2 ISOLATION. THE | | REMAINING ACTIONS OF THE ESF WOULD NOT NORMALLY BE REPORTABLE UNDER THE | | SPURIOUS INVALID ACTUATION GUIDELINES. | | | | THE LICENSEE TIGHTENED THE LUG ONCE ITS LOCATION WAS DETERMINED VIA | | THERMALGRAPH. THE ELECTRICIAN SAID THAT THE HIGH VOLTAGE SIGNAL THAT | | TRIPPED THE MG SET WAS A FALSE HIGH VOLTAGE SIGNAL. THE ISOLATIONS HAVE | | BEEN RESET AND ALL EQUIPMENT HAS BEEN RESTORED TO NORMAL. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27199 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/02/94 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 04:39 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/02/94 | +------------------------------------------------+EVENT TIME: 03:52[EDT]| |NRC NOTIFIED BY: WILLIS |LAST UPDATE DATE: 05/02/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A REACTOR WATER CLEANUP (RWCU) ISOLATION OCCURRED WHEN A RWCU PUMP SEAL | | FAILED DURING OPERATION. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "THE REACTOR WATER CLEANUP SYSTEM AUTOMATICALLY ISOLATED DUE TO SEAL | | FAILURE ON THE "A" REACTOR WATER CLEANUP PUMP AND SUBSEQUENT HIGH PUMP ROOM | | TEMPERATURE. THE ISOLATION SYSTEM RESPONDED AS DESIGNED (I.E. BOTH INBOARD | | AND OUTBOARD ISOLATION VALVES CLOSED WHEN THEIR RESPECTIVE DIVISIONAL | | ISOLATIONS OCCURRED). IN ADDITION, BOTH RWCU PUMPS TRIPPED OFF AS | | DESIGNED. AFTER SEVERAL MINUTES, REACTOR WATER CLEANUP PUMP ROOM | | TEMPERATURES DECREASED BELOW THEIR SETPOINTS AND PRESENTLY ARE WITHIN THEIR | | NORMAL BAND." | | END OF TEXT. | | | | RWCU PUMP "A" SEAL FAILED CAUSING REACTOR WATER (400 DEGREES F) TO BE | | SPILLED INTO THE RWCU PUMP ROOM. THIS RESULTED IN A SEAL FAILURE ALARM, | | HIGH TEMPERATURE ALARM, RWCU ISOLATION, AND AN AUTOMATIC TRIP OF BOTH RWCU | | PUMPS. WITHIN SEVERAL MINUTES OF THE ISOLATION, THE HIGH TEMPERATURE ALARM | | CLEARED. CONTAINMENT AREA RADIATION MONITORS DID NOT ALARM OR ACTUATE ANY | | REACTOR BUILDING VENTILATION EQUIPMENT. NO OTHER ESF ACTUATIONS OCCURRED. | | | | OPERATORS WERE MONITORING THE TEMPERATURE OF THE RWCU PUMP "A" SEAL FOR | | SEVERAL DAYS AS AN INDICATION OF POTENTIAL FAILURE. SEAL TEMPERATURE HAD | | REACHED THE 185 DEGREE F ALARM SETPOINT WHEN THE SEAL FAILURE OCCURRED | | (LESS THAN TEN MINUTES). OPERATORS ARE NOT REQUIRED TO TAKE THE RWCU PUMP | | OUT OF SERVICE UNTIL SEAL TEMPERATURE REACHES 240 DEGREES F. | | | | THE SYSTEM REMAINS ISOLATED AT THIS TIME. HEALTH PHYSICS IS SURVEYING THE | | RWCU PUMP ROOM AT THIS TIME. WHEN THE RADIATION SURVEYS ARE COMPLETED, | | CLEANUP AND SEAL REPLACEMENT WILL BEGIN. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+