U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/07/94 - 10/11/94 ** EVENT NUMBERS ** 27875 27876 27877 27878 27879 27880 27881 27882 27883 27884 27885 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27875 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/06/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 20:19 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/06/94 | +------------------------------------------------+EVENT TIME: 16:55[CDT]| |NRC NOTIFIED BY: RATZLAFF |LAST UPDATE DATE: 10/08/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |LINDA KASNER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND |AL CHAFFEE EO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |LOUZONIS FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | APPENDIX R CONCERN REGARDING LOCATION OF CO2 FIRE SUPPRESSION SYSTEM | | PRESSURE SWITCHES. | | | | THE CO2 FIRE SUPPRESSION SYSTEM PRESSURE SWITCHES FOR THE EMERGENCY DIESEL | | GENERATORS CAUSE THE EDG HVAC SYSTEM TO SHUTDOWN AFTER ACTIVATION OF CO2 | | DURING A FIRE. THE LICENSEE HAS FOUND THE PRESSURE SWITCHES FOR THIS SYSTEM | | ARE BOTH LOCATED IN THE SAME FIRE AREA (FIRE AREA 8) OUTSIDE OF EITHER OF | | THE EDG GENERATOR ROOMS. THE LICENSEE STATES THAT A FIRE IN VICINITY OF THE | | PRESSURE SWITCHES COULD CAUSE BOTH EDG HVAC UNITS TO BE RENDERED INOPERABLE | | BY DISABLING CONTROL POWER TO THE HVAC FAN MOTORS. IF THE EDG'S WERE | | RUNNING, THIS COULD EVENTUALLY CAUSE THEM TO OVERHEAT AND BE RENDERED | | INOPERABLE AS WELL. THIS IS IN VIOLATION OF APPENDIX R SEPARATION | | REQUIREMENTS AND IS NOT IN ACCORDANCE WITH THE PLANT'S DESIGN BASIS | | DOCUMENTS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | ***UPDATE FROM LICENSEE:HITZEL TO NRC:HUFFMAN AT 1528 EDT ON 10/7/94*** | | | | UNUSUAL EVENT DECLARED AT 1418 CDT ON 10/7/94 BASED ON INOPERABILITY OF | | BOTH EMERGENCY DIESEL GENERATORS. | | | | UPON FURTHER EVALUATION OF THE ABOVE CONDITION, IT WAS REALIZED THAT THE | | CO2 SWITCHES WERE LOCATED IN A SEISMIC CATEGORY 2 STRUCTURE. THIS | | REPRESENTS A POTENTIAL COMMON MODE FAILURE FOR THE EDG'S. THE SEISMIC | | CONCERN IS AN UNANALYZED CONDITION. BOTH EDG'S HAVE BEEN DECLARED | | INOPERABLE BUT ARE STILL CONSIDERED AVAILABLE. | | | | THE INOPERABILITY OF BOTH EDG'S RESULTS IN THE UNUSUAL EVENT | | CLASSIFICATION. THIS WAS NOT CONSIDERED A UNUSUAL EVENT BASED ON THE FIRE | | CONCERN CITED ABOVE BECAUSE OF A FIRE WATCH THAT WAS POSTED AT THE LOCATION | | OF THE CO2 SWITCHES. NO SIMILAR COMPENSATORY ACTION IS AVAILABLE TO | | MITIGATE THE SEISMIC CONCERN. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED AS WELL AS STATE AND LOCAL | | AUTHORITIES. | | | | | | *** UPDATE 10/08/94 @ 0704ET BY R TANDERUP TAKEN BY MACKINNON*** | | | | UNUSUAL EVENT WAS TERMINATED AT 0600CT AFTER # 2 EDG WAS DECLARED OPERABLE. | | | | AT 0600CT LICENSEE EXITED NOTIFICATION OF AN UNUSUAL EVENT DUE TO ENTERING | | EAL 4.12 (INOPERABILITY OF BOTH EDGs WITH OFFSITE POWER AVAILABLE). AT | | 0545CT # 2 EDG WAS DECLARED OPERABLE AFTER A PLANT TEMPORARY MODIFICATION | | WAS INSTALLED TO BYPASS THE DIESEL GENERATOR HEATING & VENTILATION FAN TRIP | | ON THE INITIATION OF THE DIESEL GENERATOR CARBON DIOXIDE SYSTEM. PLANT | | TEMPORARY MODIFICATION WILL BE MADE TO # 1 EDG LATER TODAY AT WHICH TIME # | | 1 EDG WILL BE DECLARED OPERABLE. STATE AND LOCAL AUTHORITIES HAVE BEEN | | NOTIFIED OF THE TERMINATION OF THE UNUSUAL EVENT CLASSIFICATION. R4DO | | (LINDA KASNER), EO (GUS LAINAS) & FEMA (BAGWELL) NOTIFIED. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27876 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/07/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:30 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/07/94 | +------------------------------------------------+EVENT TIME: 07:30[EDT]| |NRC NOTIFIED BY: POWELL |LAST UPDATE DATE: 10/07/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 16 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - REACTOR SCRAM FROM 16% POWER DUE TO MANUAL MAIN TURBINE TRIP - | | | | DURING PLANT STARTUP, CONTROL ROOM OPERATORS WERE ROLLING THE MAIN TURBINE. | | | | WITH THE 100 RPM MAIN TURBINE SPEED SELECTOR SWITCH POSITION SELECTED | | (POSSIBLE POSITIONS ARE 100, 800, 1500, AND 1800 RPM), THE MAIN TURBINE | | BYPASS VALVES SUDDENLY THROTTLED CLOSED FOR UNKNOWN REASONS CAUSING THE | | MAIN TURBINE FIRST STAGE PRESSURE TO INCREASE TO 160 PSIG (REACTOR SCRAM | | SIGNAL IS ENABLED AT 135 PSIG) AND THE MAIN TURBINE TO QUICKLY ACCELERATE | | ABOVE 700 RPM. | | | | CONTROL ROOM OPERATORS CLOSED THE MAIN TURBINE STOP VALVES TO STOP THE | | ACCELERATION AND TRIP THE MAIN TURBINE. | | | | THE REACTOR SCRAMMED FROM 16% POWER DUE TO THE CLOSURE OF THE MAIN TURBINE | | STOP VALVES. | | | | ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER. | | | | THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE UNEXPECTED CLOSURE OF THE MAIN | | TURBINE BYPASS VALVES. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #27851 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27877 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 10/07/94 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 11:40 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 09/30/94 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: WHITNEY |LAST UPDATE DATE: 10/07/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INCORRECT SPARE TRIP UNITS FOR 480V BUS FEEDER BREAKERS WERE DISCOVERED | | DURING AN OVERHAUL OF THE DEVICES. | | | | DURING AN OVERHAUL OF SPARE TRIP UNITS UTILIZED IN THE FEEDER BREAKERS FROM | | 480V BUS "MCC B2" TO "MCC B6", IT WAS DISCOVERED THAT THE GE SUPPLIED | | BREAKERS WERE INSTANTANEOUS TYPE BREAKERS (LSIT1) INSTEAD OF THE SPECIFIED | | LONG TIME - SHORT TIME TYPE BREAKERS (LST1). THIS COULD RESULT IN A LOSS | | OF BREAKER TRIP COORDINATION. IN THIS CONDITION, AN ELECTRICAL FAULT IN A | | NON SAFETY RELATED LOAD FEED FROM "MCC B6" COULD CAUSE THE FEEDER BREAKERS | | TO TRIP BEFORE THE LOAD BREAKER, CAUSING A LOSS OF EDG "A" AND BUS "B6" TO | | DEENERGIZE. | | | | THE INCORRECT BREAKERS WERE RETURNED TO GE FOR REWORK TO INSTALL THE | | CORRECT TYPE OF TRIP UNIT AS SPECIFIED IN THE ORIGINAL PURCHASE ORDER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27878 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/07/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:25 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/07/94 | +------------------------------------------------+EVENT TIME: 10:29[CDT]| |NRC NOTIFIED BY: ALAN RICHARD |LAST UPDATE DATE: 10/07/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA KASNER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 +------------------------------------------------------------------------------+ | NON-SAFETY RELATED SEAL WATER TO SAFETY RELATED PUMPS. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SENT BY THE LICENSEE REPORTING | | THIS EVENT: | | "THE RAW WATER PUMPS REQUIRE A SEAL WATER SOURCE FOR LUBRICATION AND | | COOLING OF THE SHAFT SEAL PACKING. SEAL WATER IS NORMALLY SUPPLIED BY THE | | POTABLE WATER SYSTEM. SEAL WATER CAN ALSO BE SUPPLIED TO EACH PUMP FROM A | | TAP OFF THE PUMP'S DISCHARGE LINE, BUT THIS SOURCE IS NORMALLY ISOLATED. | | PREVIOUSLY, IT WAS THOUGHT THAT SEAL WATER TO THE PUMPS ONLY SERVED TO | | PROLONG SERVICE LIFE OF THE PUMP BEARINGS AND, AS SUCH, DID NOT SERVE A | | SAFETY-RELATED FUNCTION. POTABLE WATER WAS PREFERRED BECAUSE IT IS A CLEAN | | WATER SOURCE WHEREAS THE WATER SOURCE FROM THE PUMP DISCHARGE COMES | | DIRECTLY FROM THE MISSOURI RIVER. | | | | RECENT ENGINEERING ANALYSIS INDICATES THAT SEAL FLOW IS CRITICAL TO THE | | OPERATION OF AN IN-SERVICE RAW-WATER PUMP AND THUS SHOULD BE FROM A | | SAFETY-RELATED SOURCE. A PRA MODEL WAS RUN TO ACCOUNT FOR THE DEPENDENCY OF | | THE RAW WATER PUMPS ON THE POTABLE WATER SUPPLY. THE OVERALL CHANGE IN CORE | | DAMAGE FREQUENCY INCREASES ONLY 1.8 PERCENT. AN OPERABILITY EVALUATION HAS | | BEEN PREPARED WHICH DEMONSTRATES THAT THE RAW WATER PUMPS ARE OPERABLE IN | | THE PRESENT CONFIGURATION USING POTABLE WATER AS THE SEAL WATER SOURCE. | | SAFE SHUTDOWN FOR THE FORT CALHOUN STATION IS HOT SHUTDOWN. THE RAW WATER | | SYSTEM IS NOT REQUIRED TO BRING THE PLANT TO HOT SHUTDOWN. ADDITIONALLY, AS | | DISCUSSED IN THE USAR, BACKUP COOLING WATER FOR THE COMPONENT COOLING WATER | | HEAT EXCHANGERS CAN BE OBTAINED FROM THE FIRE PROTECTION SYSTEM TO REMOVE | | RESIDUAL CONTAINMENT HEAT. | | | | CORRECTIVE ACTIONS INCLUDE VERIFICATION THAT THE PUMP DISCHARGE SEAL WATER | | SUPPLY LINES ARE CLEAR; REVISION OF THE OPERATING INSTRUCTIONS TO OPEN THE | | PUMP DISCHARGE SEAL WATER ISOLATION VALVES ON THE NON-OPERATING PUMPS TO | | ENSURE THEY ARE AVAILABLE FOR OPERATION IF POTABLE WATER WERE LOST; REVISE | | ANNUNCIATOR RESPONSE PROCEDURES TO REDUCE DEMANDS ON THE POTABLE WATER | | SYSTEM AND ENSURE POTABLE WATER IS NOT ISOLATED TO THE RAW WATER PUMPS IN | | RESPONSE TO LOW POTABLE WATER TANK LEVEL; ENHANCE ADMINISTRATIVE CONTROLS | | ON CERTAIN VALVES IN THE POTABLE WATER SYSTEM TO AVOID POTENTIAL | | INADVERTENT ISOLATION OF THIS SOURCE OF SEAL WATER; PROVIDE TRAINING TO | | OPERATORS ON THE IMPORTANCE OF POTABLE WATER TO RAW WATER PUMP OPERATION; | | AND PREPARE A MODIFICATION TO THE SEAL WATER SUPPLY CONFIGURATION TO THE | | RAW WATER PUMPS TO PROVIDE A SAFETY-RELATED SOURCE OF SEAL WATER." | | | | ESSENTIALLY, THE LICENSEE IS STATING THAT THE RAW WATER PUMPS, WHICH | | PROVIDE ULTIMATE HEAT SINK COOLING TO THE SAFETY-RELATED COMPONENTS AT THE | | PLANT, HAVE A NON-SAFETY RELATED SOURCE OF PUMP BEARING SEAL WATER (THE | | POTABLE WATER SYSTEM). INVESTIGATION INTO THE IMPORTANCE OF THE SEAL WATER | | SYSTEM TO THESE PUMPS (BYRON-JACKSON) HAS DETERMINE THAT THEY COULD FAIL | | WITHOUT THIS SEAL WATER SUPPLY. THE LICENSEE IS TAKING IMMEDIATE | | ADMINISTRATIVE ACTIONS TO ENHANCE THE RELIABILITY OF THE SYSTEM. THEY ARE | | INVESTIGATING LONGER TERM CORRECTIVE ACTIONS TO MODIFY THE DESIGN TO MEET | | SAFETY-RELATED QUALIFICATIONS. IN THE MEAN TIME, THE LICENSEE CONSIDERS THE | | SYSTEM FULLY OPERABLE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 27879 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SANOFE DIAGNOSTICS |NOTIFICATION DATE: 10/07/94 | | CITY: CHASKA REGION: 3 |NOTIFICATION TIME: 14:30 [ET]| | COUNTY: STATE: MN |EVENT DATE: 10/07/94 | |LICENSE#: 22138-38-01 AGREEMENT: N |EVENT TIME: 13:30[CDT]| | DOCKET: |LAST UPDATE DATE: 10/07/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GEOFFREY WRIGHT RDO | | |JOHN GREEVES EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ROY KROENING |FRED COMBS NMSS | |HQ OPS OFFICER: WILLIAM HUFFMAN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST IODINE-125 SHIPMENT. | | | | SANOFE DIAGNOSTICS IS A MANUFACTURER OF IN-VITRO DIAGNOSTICS LOCATED IN | | CHASKA, MINNESOTA. ON 10/3/94, 200 MILLICURIES OF IODINE-125 WAS ORDERED | | FROM A CANADIAN RADIOISOTOPE SUPPLIER CALLED NORDIAN. THE SHIPMENT WAS MADE | | VIA FEDERAL EXPRESS (DANGEROUS BILL GOODS #0434058424) AND WAS DOCUMENTED | | TO HAVE PASSED THROUGH NEW YORK ON 10/3/94. WHEN THE SHIPMENT HAD NOT BEEN | | RECEIVED BY 10/6/94, FEDERAL EXPRESS PLACED A TRACE ON IT. THE LAST KNOWN | | LOCATION OF THE PACKAGE WAS BLOOMINGTON, MN. SANOFE DIAGNOSTICS CONSIDERS | | THE PACKAGE LOST AND, CONSEQUENTLY, REPORTABLE. | | | | SANOFE HAS BEEN WORKING WITH BOTH NORDIAN AND FEDERAL EXPRESS TO LOCATE THE | | PACKAGE. THE IODINE-125 WAS SHIPPED IN A LIQUID FORM (SODIUM IODIDE). | | SANOFE HAS VERIFIED WITH THEIR RECEIVING DEPARTMENT THAT NO SUCH SHIPMENT | | HAS BEEN RECEIVED. THEY WILL CONTINUE THEIR EFFORTS TO LOCATE THE PACKAGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27880 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 10/07/94 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 15:56 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/07/94 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: BENSON |LAST UPDATE DATE: 10/07/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STATE OF MICHIGAN WAS NOTIFIED OF AN OIL LINE LEAK TO THE COOLING TOWER | | FAN WHICH RESULTED IN A 5-18 GALLON OIL RELEASE TO LAKE MICHIGAN. | | | | AT 1100EDT ON 10/6/94, AN OIL LEAK ON AN OIL SUPPLY LINE TO THE COOLING | | TOWER FANS OCCURRED RESULTING IN AN OIL RELEASE OF APPROXIMATELY 5-18 | | GALLONS TO LAKE MICHIGAN VIA THE CIRCULATING WATER SYSTEM. THE LEAK WAS | | SECURED AND ABSORBENT PILLOWS ARE BEING USED TO ABSORB THE REMAINING OIL IN | | THE BASIN. AT 1500EDT ON 10/7/94, THE MICHIGAN DEPARTMENT OF NATURAL | | RESOURCES WAS NOTIFIED OF THE RELEASE. NO FURTHER RELEASE HAS BEEN | | DETECTED. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27881 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 10/07/94 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 18:41 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/07/94 | +------------------------------------------------+EVENT TIME: 17:20[CDT]| |NRC NOTIFIED BY: BILLY LOLLAR |LAST UPDATE DATE: 10/07/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA KASNER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 1 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL TRIP FROM LESS THAN 1% POWER UPON LOSS OF ROD POSITION INDICATION. | | | | THE LICENSEE WAS CONDUCTING A CONTROLLED SHUTDOWN TO ENTER INTO A REFUELING | | OUTAGE. POWER LEVEL HAD BEEN REDUCED TO 10E-5 AMPS WHEN ALL INDICATIONS | | FROM DIGITAL ROD POSITION INDICATION (DRPI) FOR BANK D, ROD H-8, WAS LOST. | | THE LICENSEE CONSERVATIVELY INITIATED A MANUAL REACTOR TRIP TO COMPLETE THE | | SHUTDOWN. ALL RODS FULLY INSERTED AND ALL SYSTEMS FUNCTIONED AS REQUIRED. | | | | THE REACTOR IS STABLE IN MODE 3 AND WILL CONTINUE ONTO MODE 6. CAUSE OF THE | | LOST DRPI INDICATION IS STILL UNDER INVESTIGATION. THE LICENSEE NOTES THAT | | THEY HAD EXPERIENCED PREVIOUS PROBLEMS WITH THE DRPI ON THIS ROD EARLIER | | TODAY DURING THE SHUTDOWN AND HAD ALREADY DECLARED THE DRPI INOPERABLE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27882 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/08/94 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 15:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/08/94 | +------------------------------------------------+EVENT TIME: 15:25[EDT]| |NRC NOTIFIED BY: MARK MLACHAK |LAST UPDATE DATE: 10/08/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DEGRADED OFFSITE COMMUNICATIONS CAPABILITY. | | | | PROBLEMS WITH THE LOCAL TELEPHONE COMPANY (ALLTELL) SWITCHING NETWORK HAS | | RESULTED IN LOSS OF THE FTS AND LOCAL CALLING CAPABILITY TO AND FROM THE | | SITE. THE LICENSEE STILL HAS THE CAPABILITY TO MAKE COMMERCIAL LONG | | DISTANCE CALLS AND TO CONTACT STATE AND LOCAL AUTHORITIES DURING AN | | EMERGENCY. THE FTS TROUBLE TRACKING SYSTEM HAS BEEN INFORMED. ALLTELL IS | | WORKING TO REPAIR THE PROBLEM. | | | | THE RESIDENT WILL BE NOTIFIED. | | | | ***UPDATE FROM LICENSEE(DAVON) AT 2043 EDT *** | | FTS AND NORMAL TELEPHONE SERVICE HAS BEEN RESTORED AND WAS TESTED SAT. | | R3DO(WRIGHT) INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27883 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 10/09/94 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 19:12 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/09/94 | +------------------------------------------------+EVENT TIME: 17:15[CDT]| |NRC NOTIFIED BY: ROGER VARNADORE |LAST UPDATE DATE: 10/09/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAINMENT PENETRATION NOT PROPERLY SEALED. | | | | THE CONTAINMENT PENETRATION FOR THE TRANSVERSING INCORE PROBE (#2T52-X35B) | | WAS FOUND TO BE NOT PROPERLY SEALED DURING A ROUTINE CONTAINMENT | | PENETRATION SURVEILLANCE PROCEDURE. ALL FOUR RETAINING BOLTS ON THE | | PENETRATION FLANGE WERE FOUND TO BE LOOSE. THE BOLTS WERE RETIGHTENED AND | | THE PENETRATION LEAK RATE TESTED SATISFACTORILY. | | | | THE CAUSE OF THE LOOSENED BOLTS IS UNKNOWN. THE PENETRATION WAS LAST | | CHECKED 30 DAYS AGO. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27884 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT SAINT VRAIN REGION: 4 |NOTIFICATION DATE: 10/10/94 | |UNIT: [1] [ ] [ ] STATE: CO |NOTIFICATION TIME: 13:02 [ET]| |RX TYPE: [1] GA (GENERAL ATOMIC) |EVENT DATE: 10/10/94 | +------------------------------------------------+EVENT TIME: 08:30[MDT]| |NRC NOTIFIED BY: SHAFER |LAST UPDATE DATE: 10/10/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE COLORADO DEPARTMENT OF HEALTH WAS NOTIFIED OF A BORON DISCHARGE IN | | VIOLATION OF THE PLANT WASTE WATER DISCHARGE LIMIT. | | | | THE COLORADO DEPARTMENT OF HEALTH WAS NOTIFIED OF THE DISCHARGE OF BORATED | | WATER WITH A CONCENTRATION OF 0.813 MILLIGRAMS/LITER, GREATER THAN THE 0.75 | | MILLIGRAMS/LITER LIMIT IN THE PLANT'S WASTE WATER DISCHARGE PERMIT. THE | | RELEASE OF BORATED WATER TO THE SOUTH PLATTE RIVER WAS CONDUCTED DURING THE | | NORMAL EVOLUTION OF A REACTOR VESSEL DRAIN DOWN WHILE PERFORMING ROUTINE | | DECOMMISSIONING ACTIVITIES. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27885 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/11/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/11/94 | +------------------------------------------------+EVENT TIME: 02:20[CDT]| |NRC NOTIFIED BY: PHILLIP SHORT |LAST UPDATE DATE: 10/11/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 89 POWER OPERATION | 89 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE WAS IN A REQUIRED TECH SPEC SHUTDOWN WHEN THEY ENTERED TECH SPEC | | 3.0.3. FOR CONTROL ROOM POSITIVE PRESSURE BEING OUT OF SPECIFICATION. | | LICENSEE EXITED TECH SPEC 3.0.3 AND TECH SPEC REQUIRE SHUTDOWN AT 0253CT. | | | | AT 0220CT IT WAS NOTED BY MAIN CONTROL ROOM PERSONNEL THAT THE CONTROL ROOM | | VENTILATION SYSTEM TRAIN "B" IN OPERATION WAS NOT MAINTAINING A POSITIVE | | PRESSURE OF 0.125" OF WATER AS REQUIRED PER TECH SPEC. A MAINTENANCE OUTAGE | | IS CURRENTLY IN PROGRESS FOR CONTROL ROOM VENTILATION TRAIN "A". THEREFORE, | | BOTH CONTROL ROOM VENTILATION TRAINS WERE DECLARED INOPERABLE AND TECH SPEC | | 3.0.3 WAS ENTERED. IT IS BELIEVED THAT THEY HAVE A TAGOUT PROBLEM WITH | | CONTROL ROOM VENTILATION TRAIN "A" AND THIS WAS CAUSING THE INABILITY OF | | TRAIN "B" NOT TO MAINTAIN A POSITIVE PRESSURE OF 0.125" OF WATER. | | ALL WORK ON TRAIN "A" WAS STOPPED AND LICENSEE IS TRYING TO FIND/CORRECT | | THE PROBLEM. | | AT 0253CT CONTROL ROOM VENTILATION TRAIN "B" WAS SHIFTED TO THE HIGH | | RADIATION MODE OF OPERATION (TECH SPEC 3.0.3 WAS EXITED AT THIS TIME) AND | | POSITIVE PRESSURE IS NOW 0.125" OF WATER. LICENSEE WILL LEAVE CONTROL ROOM | | VENTILATION TRAIN "B" IN THE HIGH RADIATION MODE OF OPERATION UNTIL PROBLEM | | IS CORRECTED. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+