U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/24/97 - 01/27/97 ** EVENT NUMBERS ** 31562 31636 31644 31645 31646 31647 31648 31649 31650 31651 31652 31653 31654 31655 31656 31657 31658 31659 31660 31661 31662 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31562 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ALTOONA HOSPITAL, ALTOONA, PA |NOTIFICATION DATE: 01/09/97 | | CITY: ALTOONA REGION: 1 |NOTIFICATION TIME: 15:40 [ET]| | COUNTY: STATE: PA |EVENT DATE: 01/09/97 | |LICENSE#: 37-11826-01 AGREEMENT: N |EVENT TIME: 13:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/24/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |HAROLD GRAY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DR. VINCE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE POSSIBLE MEDICAL MISADMINISTRATIONS DISCOVERED DURING A QUALITY | | MANAGEMENT PROGRAM AUDIT. | | | | THREE PATIENTS WERE GIVEN WHOLE BODY SCANS FOR THYROID CANCER. THE PATIENTS | | WERE SUPPOSED TO RECEIVE 3 mCi OF SODIUM IODIDE (I-131) BEFORE THE WHOLE | | BODY SCAN WAS PERFORMED. DURING A QUALITY MANAGEMENT PROGRAM AUDIT, THE | | LICENSEE DISCOVERED THAT, ON 6/24/96, A PATIENT RECEIVED ONLY 77% OF THE | | PRESCRIBED DOSE, AND ON 7/25/96 AND 9/19/96, PATIENTS RECEIVED 76% OF THE | | PRESCRIBED DOSES. THESE UNDERDOSES OF I-131 POSE NO MEDICAL THREAT TO THE | | PATIENTS. | | | | THE PATIENTS AND THEIR DOCTORS WILL BE INFORMED OF THE ABOVE INFORMATION BY | | THE ALTOONA HOSPITAL MEDICAL STAFF. THE RADIATION SAFETY OFFICER STATED | | THAT GOOD IMAGES OF THE PATIENTS COULD BE OBTAINED EVEN WITH THE 24% | | UNDERDOSE OF I-131. THE LICENSEE HAS ALREADY REPORTED THIS EVENT TO NRC | | REGION 1 (JIM DWYER). | | | | * * * UPDATE 1055 1/24/97 FROM DR. VINCE TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. A REGION 1 INSPECTOR (BHALLA) | | HAS INFORMED THE LICENSEE THAT THESE INSTANCES ARE NOT REPORTABLE. NOTIFIED | | R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31636 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NATIONAL INSTITUTE OF HEALTH |NOTIFICATION DATE: 01/22/97 | | CITY: BETHESDA REGION: 1 |NOTIFICATION TIME: 16:17 [ET]| | COUNTY: MONTGOMERY STATE: MD |EVENT DATE: 01/22/97 | |LICENSE#: 19-00296-10 AGREEMENT: Y |EVENT TIME: 10:30[EST]| | DOCKET: |LAST UPDATE DATE: 01/24/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM MOSLAK RDO | | |JOE HOLONICH (NMSS) EO | +------------------------------------------------+FRANK CONGEL, IRD AEOD | |NRC NOTIFIED BY: ROBERT ZOON | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL INSTITUTE OF HEALTH REPORTED THAT ONE MILLICURIE OF SODIUM | | IODIDE (NaI) WAS MISSING. | | | | AT 1030 EST ON 01/22/97, A NATIONAL INSTITUTE OF HEALTH RESEARCH SCIENTIST | | REPORTED TO THE RADIATION SAFETY BRANCH THAT HE WAS UNABLE TO LOCATE A | | PACKAGE OF I-125 LABELED SODIUM IODIDE WHICH HAD BEEN DELIVERED TO HIS | | RESEARCH LABORATORY ON 01/10/97. THE I-125 ACTIVITY IN THE VIAL WAS 1 | | MILLICURIE (37 MBq), (DUPONT NEN PRODUCT NUMBER NEZ-033L). THE PACKAGE | | CONSISTED OF A US DOT 7A TYPE 'A' CARDBOARD BOX, INNER STYROFOAM LINER, AND | | THE VIAL, A DUPONT NENSURE LUCITE VIAL SECURED WITHIN A PLASTIC-COATED | | SCREW-TOP LEAD SHIELD. | | | | THE SCIENTIST FIRST BEGAN LOOKING FOR THE PACKAGE AT APPROXIMATELY 1500 EST | | ON 01/21/97. WHEN HE DID NOT FIND IT IN THE EXPECTED LOCATION, HE | | INITIATED A SEARCH. IT WAS NOT UNTIL HE INTERVIEWED OTHER LAB PERSONNEL | | AND COMPLETED HIS SEARCH THAT HE CONCLUDED THE PACKAGE WAS MISSING. HE | | THEN REPORTED THE POSSIBLE LOSS TO THE RADIATION SAFETY BRANCH. A SECOND | | EXTENSIVE SEARCH WAS CONDUCTED BY THE SCIENTISTS INVOLVED, WITH THE | | ASSISTANCE OF THE RADIATION SAFETY BRANCH ON 01/22/97. AS OF 1400 EST, THE | | MATERIAL HAD NOT BEEN LOCATED. | | | | THE FOLLOWING POSSIBLE DISPOSITIONS ARE BEING INVESTIGATED FURTHER: | | | | 1. THE PACKAGE CONTAINING THE SOURCE VIAL WAS INADVERTENTLY DISCARDED AS | | NON-RADIOACTIVE WASTE; | | 2. INADVERTENT DISPOSAL INTO DRY RADIOACTIVE WASTE, WHICH WAS COLLECTED ON | | 01/16/97; AND | | 3. STORAGE OF THE PACKAGE IN A LOCATION NOT YET DISCOVERED. | | | | * * * 1352 JANUARY 24, 1997, UPDATE FROM BOB ZOON RECEIVED BY TROCINE * * * | | | | THE MISSING MATERIAL WAS LOCATED AT APPROXIMATELY 1330 TODAY. IT HAD BEEN | | MISTAKENLY PLACED WITH RADIOACTIVE WASTE. THE SOLID WASTE BAGS ARE | | TYPICALLY BOXED, EACH BOX IS NUMBERED WITH A RECORD OF THE WASTE TAG, AND | | THE BOXES ARE THEN PLACED IN SECURED SEA/LAND CONTAINERS. WHEN ENOUGH | | MATERIAL HAS BEEN COLLECTED, THE SEA/LAND CONTAINERS ARE TRANSPORTED UNDER | | MANIFEST TO SEG OAK RIDGE FOR PROCESSING AND VOLUME REDUCTION. IN THIS | | CASE, THE CARGO CONTAINER CONTAINING THE MISSING MATERIAL WAS STILL ONSITE | | AND HAD NOT BEEN SHIPPED TO OAK RIDGE. THE LICENSEE VERIFIED THAT THE | | MATERIAL FOUND HAD THE CORRECT CATALOG NUMBER AND DATE, AND THE MATERIAL | | HAS BEEN ASSAYED AT APPROXIMATELY ONE MILLICURIE. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (MOSLAK), NMSS EO (HOLONICH), | | AND AEOD IRD (CONGEL). THE REGIONAL OFFICE PLANS TO NOTIFY THE STATE OF | | MARYLAND. (REFER TO THE HOO LOG FOR A SITE CONTACT NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31644 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/23/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 23:12 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/23/97 | +------------------------------------------------+EVENT TIME: 22:24[EST]| |NRC NOTIFIED BY: EDWARD HYNES |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |ROBERT CAPRA, NRR EO | | |FRANK CONGEL, IRD AEOD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 58 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOAD REDUCTION FROM 100% POWER AND MANUAL REACTOR SCRAM FROM 58% POWER DUE | | TO ICE FOULING ON THE CIRCULATING WATER SCREEN INTAKES. | | | | THE LICENSEE'S INITIAL INDICATION OF ICE FOULING ON THE CIRCULATING | | WATER SCREEN INTAKES WAS A DECREASED LAKE INTAKE LEVEL INDICATION. | | THE SECOND INDICATION WAS AN INCREASE IN THE SCREEN DIFFERENTIAL PRESSURE. | | AS A RESULT, THE LICENSEE BEGAN REDUCING REACTOR POWER FROM 100% AT | | APPROXIMATELY 2210. CREWS WERE DISPATCHED TO INVESTIGATE. EFFORTS TO | | MOVE THE SCREENS WERE UNSUCCESSFUL, AND THE SHEAR PINS ON ALL OF THE | | MOTORS BROKE ON ALL THREE SCREENS. AS A RESULT, THE LICENSEE INITIATED | | A MANUAL REACTOR SCRAM FROM 58% POWER AT 2224. ALL RODS FULLY INSERTED, | | AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THERE WERE NO ENGINEERED SAFETY | | FEATURES ACTUATIONS. | | | | THE UNIT IS CURRENTLY IN HOT SHUTDOWN CONDITION WITH REACTOR COOLANT SYSTEM | | TEMPERATURE GREATER THAN 212øF. NORMAL CONDENSATE AND FEEDWATER IS BEING | | SUPPLIED TO THE REACTOR VESSEL, AND STEAM IS BEING BYPASSED TO THE MAIN | | CONDENSER. THE LICENSEE PLANS TO COOL THE UNIT DOWN AND TO PLACE THE MODE | | SWITCH IN REFUELING POSITION. | | | | THERE IS CURRENTLY A DIFFERENTIAL PRESSURE HEAD OF APPROXIMATELY 4 FEET | | ACROSS THE SCREENS, AND THE LICENSEE ESTIMATED THAT FLOW ACROSS THE | | SCREENS IS AT ABOUT 60,000 GALLON PER MINUTE. THE BAYS ON THE DOWNSTREAM | | SIDE OF THESE SCREENS SUPPLY WATER TO THE SERVICE WATER PUMPS, RESIDUAL | | HEAT REMOVAL PUMPS, FIRE WATER PUMPS, AND ESSENTIAL SERVICE WATER PUMPS. | | THERE IS ONE FIRE WATER PUMP THAT TAKES A SUCTION FROM THE UPSTREAM SIDE | | OF THE SCREENS. | | | | THE LICENSEE DID NOT MAKE AN EMERGENCY DECLARATION AS A RESULT OF THIS | | EVENT. THE UNUSUAL EVENT CRITERIA WOULD BE MET IF THE MAIN INTAKE LEVEL | | INDICATION DECREASED TO 237 FEET. THE LOWEST LEVEL INDICATION WAS 240 | | FEET, AND IT IS CURRENTLY HIGHER THAN THAT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0400 ON 01/24/97 TAKEN BY STRANSKY * * * | | | | HIGH DIFFERENTIAL PRESSURE ACROSS THE INTAKE SCREENS WAS CAUSED BY A | | LARGE ACCUMULATION OF 1-1/2" LONG STICKLEBACK FISH. THE LICENSEE STATED | | THAT APPROXIMATELY 1 CUBIC YARD OF FISH WERE REMOVED FROM THE SCREENS. | | THE LICENSEE HAD SUSPECTED ICE ACCUMULATION DUE TO WEATHER CONDITIONS | | SIMILAR TO PREVIOUS ICE EVENTS. WHEN THE LICENSEE INITIALLY ATTEMPTED TO | | CLEAR THE SCREENS, THE HIGH LOADING CAUSED SHEAR PINS ON THE TRAVELING | | SCREEN TO BREAK. THE LICENSEE HAS ENTERED A FORCED OUTAGE AND EXPECTS TO | | REMAIN SHUTDOWN FOR APPROXIMATELY THREE DAYS. HOO NOTIFIED R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31645 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 01:43 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 01:24[EST]| |NRC NOTIFIED BY: GOODHOPE |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FREDRICKSON RDO | |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 100 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN DUE TO SMALL THRU-WALL LEAK ON STEAM TRAP LINE | | | | AT 0124, THE LICENSEE COMMENCED A UNIT SHUTDOWN IN ACCORDANCE WITH PLANT | | TECHNICAL SPECIFICATION 4.15.C DUE TO THE DISCOVERY OF A SMALL (WISPING) | | STEAM LEAK ON A 1-1/2" DIAMETER STEAM TRAP LINE ATTACHED TO THE 'B' MAIN | | STEAM LINE. THE STEAM TRAP LINE CONNECTS TO THE MAIN STEAM LINE DOWNSTREAM | | OF THE MAIN STEAM TRIP VALVE, AND IT CANNOT BE ISOLATED. REACTOR POWER IS | | BEING REDUCED AT A RATE OF 0.33% PER MINUTE, AND THE LICENSEE ANTICIPATES | | TAKING THE UNIT TO HOT SHUTDOWN FOR REPAIRS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31646 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 01/24/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 10:30 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 06:35[EST]| |NRC NOTIFIED BY: LYNCH |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FARBER 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REMOTE MANUAL CONTAINMENT ISOLATION VALVE FOUND CLOSED | | | | THE LICENSEE DISCOVERED THAT A PRIMARY CONTAINMENT REMOTE MANUAL ISOLATION | | VALVE (T50-F0458, DIVISION 2 PRIMARY CONTAINMENT MONITORING SYSTEM LEVEL | | INSTRUMENT ISOLATION VALVE) WAS CLOSED. THE VALVE WAS REOPENED, AND A | | DEFICIENCY REPORT WAS GENERATED TO INVESTIGATE THE VALVE CLOSURE. THE | | LICENSEE STATED THAT THIS VALVE HAS NO AUTOMATIC CLOSURE FUNCTION, AND THEY | | DO NOT BELIEVE THAT IT WAS CLOSED BY THE MANUAL PUSH BUTTON LOCATED IN THE | | CONTROL ROOM. THIS VALVE IS ASSOCIATED WITH THE PRIMARY CONTAINMENT WATER | | LEVEL RECORDER, WHICH IS NOT REQUIRED BY TECHNICAL SPECIFICATIONS. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31647 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 11:16 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 10:31[EST]| |NRC NOTIFIED BY: STRICKLAND |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOSLAK RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL FOR PIPING FAILURE DURING ACCIDENT CONDITIONS (NRC GL 96-06) | | | | WHILE CONDUCTING ENGINEERING EVALUATIONS IN RESPONSE TO NRC GENERIC LETTER | | 96-06, THE LICENSEE HAS DETERMINED THAT PIPING INSIDE CONTAINMENT | | ASSOCIATED WITH THE WASTE LIQUID SYSTEM COULD BECOME OVERPRESSURIZED DURING | | CERTAIN DESIGN BASIS ACCIDENTS AND COULD RESULT IN FAILURE OF CONTAINMENT | | ISOLATION VALVE #WLD-V81. THE LICENSEE HAS ENTERED TECHNICAL SPECIFICATION | | 3.6.3 AND HAS CLOSED, LOCKED, AND DEENERGIZED THE OUTBOARD CONTAINMENT | | ISOLATION VALVE #WLD-V82. LICENSEE PERSONNEL ARE CURRENTLY INSIDE | | CONTAINMENT REALIGNING VALVES TO ESTABLISH A VENT PATH AND ELIMINATE THIS | | CONCERN. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | [HOO NOTE: SEE RELATED EN 31582] | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31648 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:02 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 09:37[EST]| |NRC NOTIFIED BY: CLYDE BURNSWORTH |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK 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 +------------------------------------------------------------------------------+ | CLOSURE OF SHUTDOWN COOLING ISOLATION VALVES AND RESIDUAL HEAT REMOVAL PUMP | | TRIP POTENTIALLY DUE TO A SPURIOUS PRESSURE SIGNAL | | | | WHILE PLACING THE PLANT INTO A SHUTDOWN COOLING LINEUP, THE 'D' RESIDUAL | | HEAT REMOVAL PUMP TRIPPED AND THE SHUTDOWN COOLING ISOLATION VALVES | | (10-MOV-17 AND 10-MOV-18) CLOSED. THIS OCCURRED SHORTLY AFTER THE 'D' | | RESIDUAL HEAT REMOVAL PUMP WAS STARTED. OTHER RESIDUAL HEAT REMOVAL PUMPS | | WERE AVAILABLE AT THE TIME OF THIS EVENT, BUT THEY WERE NOT MANUALLY | | STARTED BECAUSE THEY WERE NOT NEEDED FOR SHUTDOWN COOLING. | | | | THE LICENSEE CURRENTLY BELIEVES THAT THE PUMP TRIP WAS CAUSED BY THE LOSS | | OF A SUCTION PATH DUE TO THE CLOSURE OF THE ISOLATION VALVES, AND THAT THE | | CLOSURE OF THE SHUTDOWN COOLING ISOLATION VALVES WAS CAUSED BY A SPURIOUS | | PRESSURE SIGNAL. THE ISOLATION SIGNALS FOR THESE VALVES ARE REACTOR VESSEL | | WATER LEVEL LESS THAN 177 INCHES OR REACTOR PRESSURE GREATER THAN 75 PSIG. | | AT THE TIME OF THIS EVENT, ACTUAL WATER LEVEL WAS 219 INCHES, AND REACTOR | | PRESSURE WAS 4.5 PSIG. THERE WERE NO RELATED MAINTENANCE OR SURVEILLANCE | | ACTIVITIES OCCURRING AT THE TIME OF THIS EVENT. THE UNIT DID NOT ENTER A | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION AS A RESULT OF | | THIS EVENT. | | | | THE LICENSEE DIRECTED I&C TECHNICIANS TO ENSURE PRESSURE SWITCHES ARE | | VENTED TO PREVENT AN INVALID ISOLATION. THE LICENSEE ALSO DIRECTED | | OPERATORS TO RE-PERFORM PROCEDURAL STEPS TO ENSURE THAT THE SHUTDOWN | | COOLING SUCTION PIPING IS FULL. THE 'D' RESIDUAL HEAT REMOVAL PUMP WAS | | PLACED IN SHUTDOWN COOLING AT 1256. PLANT RESTART HAS TENTATIVELY BEEN | | PLANNED FOR THE EVENING OF JANUARY 26, 1997. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31649 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TROJAN REGION: 4 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [ ] [ ] STATE: OR |NOTIFICATION TIME: 13:49 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 08:14[PST]| |NRC NOTIFIED BY: JAMES NELSON |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION AND RESPONSE DUE TO A SMALL ELECTRICAL FIRE IN AN | | ADMINISTRATION BUILDING LOCATED OUTSIDE THE PROTECTED AREA NEAR THE | | SWITCHYARD | | | | A SMALL ELECTRICAL FIRE IN THE TROJAN NORTH BUILDING TELECOMMUNICATIONS | | ROOM REQUIRED NOTIFICATION AND RESPONSE BY THE RAINIER FIRE DEPARTMENT. AT | | 0814 PST, THIS SMALL ELECTRICAL FIRE CREATED HEAVY SMOKE AND CAUSED TWO | | HALON BOTTLES TO ACTUATE. THE FIRE WAS EXTINGUISHED WITHIN TEN MINUTES, | | AND THE RAINIER FIRE DEPARTMENT ARRIVED ONSITE AT 0827 PST. FIRE | | DEPARTMENT PERSONNEL FOUND THAT THE FIRE HAD ALREADY BEEN EXTINGUISHED AND | | CLEARED THE SMOKE FROM THE ROOM BY 0938 PST. THE IDENTIFICATION OF THE | | SMOKE SOURCE AND THE CAUSE OF THE FIRE ARE STILL UNDER INVESTIGATION. | | | | THE AFFECTED BUILDING WAS AN ADMINISTRATION BUILDING LOCATED OUTSIDE THE | | PROTECTED AREA NEAR THE SWITCHYARD. THERE WERE NO ONSITE SYSTEMS OR | | PERSONNEL AFFECTED, AND EMERGENCY PLAN ENTRY WAS NOT REQUIRED. | | | | THE LICENSEE PLANS TO NOTIFY THE OREGON DEPARTMENT OF ENERGY. AN NRC | | RESIDENT INSPECTOR IS NOT CURRENTLY ASSIGNED TO TROJAN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31650 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 14:26 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 11:00[EST]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR CONDENSATION-INDUCED WATER HAMMERS IN THE LOW PRESSURE | | SERVICE WATER PIPING ASSOCIATED WITH THE FOUR NON-SAFETY-RELATED AUXILIARY | | AIR COOLERS | | | | THE LICENSEE'S THERMAL-HYDRAULIC ANALYSIS IN RESPONSE TO GENERIC LETTER | | 96-06 INVESTIGATED THE POSSIBILITY OF WATER HAMMERS IN THE LOW PRESSURE | | SERVICE WATER (LPSW) PIPING ASSOCIATED WITH FOUR NON-SAFETY-RELATED | | AUXILIARY AIR COOLERS. THESE ANALYSES PREDICTED CONDITIONS WHICH MAY BE | | CONDUCIVE TO CONDENSATION-INDUCED WATER HAMMERS IN CERTAIN PORTIONS OF THE | | LPSW PIPING (ASSOCIATED WITH THE NON-SAFETY-RELATED AUXILIARY AIR COOLERS) | | DURING A POTENTIAL LOSS OF COOLANT ACCIDENT/LOSS OF OFFSITE POWER EVENT. | | | | AS AN IMMEDIATE CONSERVATIVE CORRECTIVE ACTION, THE LICENSEE PLANS TO | | ISOLATE AND DRAIN PORTIONS OF THE AFFECTED AUXILIARY AIR COOLER LPSW PIPING | | PRIOR TO THE STARTUP OF EACH OCONEE UNIT. THESE ACTIONS ARE BEING TAKEN AS | | A PRECAUTIONARY TO ELIMINATE THE POSSIBILITY OF CONDENSATION-INDUCED WATER | | HAMMER WHILE FURTHER ANALYSES ARE PERFORMED. IF A POSTULATED WATER HAMMER | | RESULTED IN A PIPE BREAK IN THE AFFECTED AUXILIARY AIR COOLER PORTION OF | | THE LPSW SYSTEM, THEN LPSW COOLING FLOW WOULD BE DIVERTED FROM THE REACTOR | | BUILDING COOLING UNITS (RBCU) TO THE PIPE BREAK LOCATION. THIS COULD | | RESULT IN INADEQUATE LPSW FLOW TO THE RBCUs AND COULD ADVERSELY IMPACT | | CONTAINMENT INTEGRITY. IN ADDITION, FLOW FROM THE BREAK WOULD RESULT IN | | BORON DILUTION OF THE REACTOR BUILDING EMERGENCY SUMP WATER. THEREFORE, | | THE RBCUs MAY NOT HAVE BEEN CAPABLE OF PERFORMING THEIR INTENDED SAFETY | | FUNCTION UNDER THESE CONDITIONS. | | | | THE LICENSEE CONSERVATIVELY REPORTED THIS ISSUE BASED ON PRELIMINARY | | FINDINGS FROM THE GENERIC LETTER 96-06 REVIEW. ADDITIONAL ANALYSES ARE | | ONGOING. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A | | LICENSEE EVENT REPORT. THE LICENSEE ALSO STATED THAT A CONFERENCE CALL | | WITH LICENSEE MANAGEMENT AND NRC REGION 2 PERSONNEL WAS ONGOING AT THE TIME | | OF THIS NOTIFICATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31651 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: STEVENS GRAPHICS |NOTIFICATION DATE: 01/24/97 | | CITY: BIRMINGHAM REGION: 2 |NOTIFICATION TIME: 15:25 [ET]| | COUNTY: STATE: AL |EVENT DATE: 01/24/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 15:12[CST]| | DOCKET: |LAST UPDATE DATE: 01/24/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PAUL FREDRICKSON RDO | | |JOE HOLONICH, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: THOMAS R. DECKER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISPOSAL OF A PRINTING MACHINE CONTAINING THREE 1.9 mCi POLONIUM-210 STATIC | | ELIMINATORS | | | | AN NRC REGION 2 REPRESENTATIVE (T. DECKER) NOTIFIED THE OPERATIONS CENTER | | OF THE RECEIPT OF AN EVENT NOTIFICATION FROM THE STATE OF ALABAMA (JIM | | McNEISS) AT 1512 TODAY. STEVENS GRAPHICS, LOCATED IN BIRMINGHAM, AL, | | NOTIFIED THE STATE OF ALABAMA THAT A PRINTING MACHINE CONTAINING THREE | | Po-210 STATIC ELIMINATORS WAS DISPOSED OF EARLIER THIS WEEK. IN MARCH 1996, | | THE ACTIVITY OF THESE ELIMINATORS WAS 10 mCi EACH, AND THE CURRENT ESTIMATE | | IS 1.9 mCi EACH. THESE ELIMINATORS ARE LOW ACTIVITY ALPHA SOURCES WITH | | SHORT HALF LIVES, AND THE STATE HAS DECIDED NOT TO LOOK FOR THEM. | | | | (REFER TO THE HOO LOG FOR STATE OF ALABAMA CONTACT TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31652 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 01/24/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 15:46 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 15:30[EST]| |NRC NOTIFIED BY: ROY GREEN |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THERMAL EXPANSION OF ENTRAPPED FLUID IN PENETRATIONS DURING ACCIDENT | | CONDITIONS COULD EXCEED THE DESIGN PRESSURES | | | | FURTHER EVALUATION OF PIPING SYSTEMS IN RESPONSE TO NRC GENERIC LETTER | | 96-06 HAS INDICATED THAT PRESSURE IN THE FOLLOWING PENETRATIONS COULD | | EXCEED THE DESIGN PRESSURE DUE TO CLOSURE OF THE INBOARD AND OUTBOARD | | ISOLATION VALVES AS A RESULT OF THERMAL EXPANSION OF ENTRAPPED FLUID DURING | | ACCIDENT CONDITIONS: 2RCS*Z99A THROUGH 2RCS*Z99D AND 2RCS*Z100A THROUGH | | 2RCS*Z100D. THESE PENETRATIONS ALLOW FLOW OF HYDRAULIC FLUID BETWEEN THE | | HYDRAULIC POWER UNITS AND THE RECIRCULATION FLOW CONTROL VALVE ACTUATORS. A | | PRELIMINARY EVALUATION PERFORMED BY ENGINEERING INDICATES THAT THE | | OPERABILITY OF THE SYSTEM IS NOT AFFECTED DUE TO THE POTENTIAL | | OVERPRESSURIZATION OF THE PIPING SYSTEM, AND THE PENETRATIONS ARE | | OPERATIONAL UNDER ALL MODES OF OPERATION. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31653 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:58 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 16:20[CST]| |NRC NOTIFIED BY: HENNIG |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 90 POWER OPERATION | 90 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR AN EMERGENCY DIESEL OVERLOAD CONDITION | | | | DURING A REVIEW OF PROCEDURES FOR PERFORMANCE OF HIGH HEAD SAFETY INJECTION | | SYSTEM FILL AND VENTING, THE LICENSEE DISCOVERED THE POTENTIAL FOR AN | | EMERGENCY DIESEL OVERLOAD CONDITION. THIS IS BASED UPON HAVING A SINGLE | | DIESEL ALIGNED TO ONE TRAIN OF BOTH UNITS, THE TESTING OF A HIGH HEAD | | SAFETY INJECTION PUMP IN THAT TRAIN OF ONE UNIT, AND A COINCIDENT DESIGN | | BASIS ACCIDENT ON THE OTHER UNIT WITH A TOTAL LOSS OF OFFSITE POWER. THE | | AFFECTED DIESEL WOULD PROVIDE POWER TO BOTH UNITS, WITH A FULL SAFEGUARDS | | ACTUATION IN THE ACCIDENT UNIT, AND THE HIGH HEAD SAFETY INJECTION PUMP | | UNDER TEST IN THE NON-ACCIDENT UNIT. THIS COULD POTENTIALLY LOAD THE | | SHARED DIESEL ABOVE THE 1/2-HOUR RATING FOR GO1 AND GO2 (THE 'A' TRAIN | | DIESELS) OR THE 4-HOUR RATING OF GO3 AND GO4 (THE 'B' TRAIN DIESELS). THIS | | LOADING COULD BE HIGH ENOUGH TO CAUSE A VOLTAGE DROP ON THE POWERED BUSSES. | | THE LICENSEE IS IMPLEMENTING PROCEDURE CHANGES TO PREVENT DIESEL OVERLOAD | | WHEN TESTING HIGH HEAD SAFETY INJECTION PUMPS WHEN A DIESEL IS BEING SHARED | | BETWEEN UNITS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31654 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 18:49 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 15:40[CST]| |NRC NOTIFIED BY: JOHN JOHNSON |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY OF UNSECURED SAFEGUARDS INFORMATION | | | | AT 1540 CST, THE LICENSEE IDENTIFIED THAT A SAFEGUARDS INFORMATION CABINET | | WAS UNSECURED. IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. | | (REFER TO THE HOO LOG FOR ADDITION INFORMATION.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO | | LOG FOR A SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31655 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 17:55[CST]| |NRC NOTIFIED BY: CURT BASNER |LAST UPDATE DATE: 01/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL TO EXCEED PIPING DESIGN PRESSURES OF VARIOUS SYSTEMS DUE TO | | HEATING FOLLOWING A LOSS OF COOLANT ACCIDENT AND CONTAINMENT ISOLATION | | | | DURING A REVIEW OF GENERIC LETTER 96-06 ISSUES, THE LICENSEE DETERMINED | | THAT, SUBSEQUENT TO A LOSS OF COOLANT ACCIDENT AND CONTAINMENT ISOLATION, | | SYSTEMS WHICH ARE ISOLATED IN THE CONTAINMENT WILL OVERPRESSURIZE DUE TO | | HEATING, RESULTING IN PIPING PRESSURES BEING BEYOND DESIGN PRESSURES. THE | | LICENSEE ANALYZED THE FIRE PROTECTION, WASTE DISPOSAL BLOWDOWN, WASTE | | DISPOSAL AUXILIARY BUILDING DRAIN, REACTOR COOLANT, CHEMICAL AND VOLUME | | CONTROL, RESIDUAL HEAT REMOVAL, SAFETY INJECTION, DEMINERALIZED FLUSHING | | WATER, PRIMARY PROCESS SAMPLING, HEATING SYSTEM HOT WATER AND WASTE DRAIN | | SYSTEMS, AND DETERMINED THAT SOME AFFECTED PIPING SECTIONS MAY HAVE | | CALCULATED PRESSURES LESS THAN THE ACCEPTABLE FAULTED LIMIT. THE LICENSEE | | DETERMINED THAT THE FINAL PRESSURE MAY EXCEED THE ELASTICALLY CALCULATED | | FAULTED PRESSURE FOR PENETRATIONS IN THE FOLLOWING SYSTEMS: FIRE | | PROTECTION, DEMINERALIZED WATER, WASTE DRAIN, HEATING SYSTEM, PRIMARY | | WATER, ACCUMULATOR TEST LINE, AND SAMPLE SYSTEM. THE LICENSEE HAS NOT | | DECLARED ANY SYSTEMS INOPERABLE AS A RESULT OF THIS DETERMINATION, AND THE | | UNITS ARE CURRENTLY NOT IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31656 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 01/24/97 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 23:51 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/24/97 | +------------------------------------------------+EVENT TIME: 23:00[EST]| |NRC NOTIFIED BY: JERRY RADISHOFSKI |LAST UPDATE DATE: 01/25/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PARTIAL LOSS OF TELEPHONE COMMUNICATIONS AT THE SITE DUE TO A TRAFFIC | | ACCIDENT NEARBY | | | | A TRAFFIC ACCIDENT ON U.S. ROUTE 11 IN THE VICINITY OF THE SITE CAUSED A | | PARTIAL LOSS OF TELEPHONE COMMUNICATIONS. THE TELA-NOTIFICATION SYSTEM, | | WHICH IS USED TO CONFIRM THAT ON CALL EMERGENCY RESPONDERS HAVE BEEN | | NOTIFIED VIA THE PAGING SYSTEM, IS INOPERABLE. PAGERS CAN BE ACTIVATED, BUT | | THE AUTOMATED CONFIRMATION CAPABILITIES HAVE BEEN LOST. THE EMERGENCY | | NOTIFICATION SYSTEM FTS-2000 TELEPHONE LINE WAS REPORTED TO BE INOPERABLE | | BY THE NRC OPERATIONS CENTER. LINES OF COMMUNICATIONS WERE ESTABLISHED WITH | | THE NRC VIA OTHER COMMERCIAL LINES AVAILABLE TO THE CONTROL ROOM. | | COMMUNICATIONS CAPABILITIES WITH THE LUZERNE AND COLUMBIA COUNTY EMERGENCY | | OFFSITE FACILITIES AND WITH PEMA HAVE ALSO BEEN VERIFIED. THE COUNTIES | | STATED THAT EMERGENCY SIREN ACTIVATION WAS NOT AFFECTED. IN ADDITION, THE | | NUCLEAR EMERGENCY RESPONSE ORGANIZATION IS BEING NOTIFIED TO HAVE PERSONNEL | | REPORT TO THEIR RESPECTIVE LOCATIONS SHOULD THE PAGING SYSTEM ACTIVATE AND | | USE AN ALTERNATE ROUTE SHOULD U.S. ROUTE 11 REMAIN CLOSED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 2014 JANUARY 25, 1997, UPDATE FROM RADISHOFSKI TAKEN BY TROCINE * * * | | | | THE LICENSEE RESTORED FULL CAPABILITY FOR EMERGENCY RESPONSE AT 1945 ON | | JANUARY 25, 1997. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED | | THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31657 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 01/26/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 00:25 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/25/97 | +------------------------------------------------+EVENT TIME: 23:15[EST]| |NRC NOTIFIED BY: MUSGROVE |LAST UPDATE DATE: 01/26/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE PLANT HAD A NON-VALID PRIMARY CONTAINMENT ISOLATION WHICH ALSO INVOLVED | | AN ACCIDENT MITIGATION ISSUE. | | | | I&C PERSONNEL WERE CALIBRATING A HIGH PRESSURE COOLANT INJECTION (HPCI) | | SYSTEM TIME DELAY RELAY (2E41-K14) PER PROCEDURE 57CP-CAL-051-2S, WHICH | | REQUIRES LIFTING THE COIL WIRE ON THE RELAY. WHEN THE WIRE WAS LIFTED, | | VALVE 2E41-F111, HPCI EXHAUST VACUUM BREAKER (PCIV), ACTUATED AND WENT | | CLOSED. THIS WAS A NON-VALID ISOLATION SIGNAL, BUT SINCE IT INVOLVED A | | PCIV, IT IS REPORTABLE. THE VALVE CLOSED AT 2315, THE PROCEDURE WAS | | STOPPED, AND ALL EQUIPMENT WAS RETURNED TO ITS PRETEST CONFIGURATION AT | | 2335. THE LICENSEE DOES NOT FULLY UNDERSTAND WHY THE VALVE CLOSED AND IS | | CONTINUING ITS INVESTIGATION. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * 1640 JANUARY 26, 1997, UPDATE FROM MADISON TAKEN BY TROCINE * * * | | | | AFTER FURTHER INVESTIGATION OF THE WIRING DIAGRAMS OF THE 2E41-K14 RELAY, | | THE LICENSEE DISCOVERED THAT WHILE THE CORE WIRE WAS LIFTED, HPCI AUTOMATIC | | INITIATION CAPABILITY WAS LOST. THIS ACTIVITY WAS BEING PERFORMED AS PART | | OF PROCEDURE 57CP-CAL-051-2S. AS STATED ABOVE, ALL EQUIPMENT WAS RETURNED | | TO ITS PRETEST CONFIGURATION AT 2335 ON JANUARY 25, 1997. I&C AND | | ENGINEERING PERSONNEL ARE CONTINUING TO INVESTIGATE THE CLOSURE OF PCIV | | 2E41-F111. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED | | THE R2DO (FREDRICKSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31658 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/26/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 09:41 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/26/97 | +------------------------------------------------+EVENT TIME: 08:55[EST]| |NRC NOTIFIED BY: SAVINO |LAST UPDATE DATE: 01/26/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 36 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN DUE TO A PROBLEM WITH THE FEEDWATER REGULATING VALVES | | | | THE PLANT WAS OPERATING AT 100% POWER WHEN THE '21' MAIN FEEDWATER | | REGULATING VALVE EXPERIENCED TROUBLE. STEAM GENERATOR LEVEL STARTED | | INCREASING, AND THE CONTROLLER CALLED FOR VALVE CLOSURE, BUT THE VALVE DID | | NOT MOVE. A POWER REDUCTION WAS COMMENCED, AND SHORTLY THEREAFTER, THE '22' | | AND '24' MAIN FEEDWATER REGULATING VALVES EXPERIENCED SIMILAR PROBLEMS. A | | PLANT SHUTDOWN WAS COMMENCED WITH THE THREE MAIN FEED VALVES PLACED IN | | MANUAL AND FEEDWATER FLOW BEING CONTROLLED BY MANUALLY CONTROLLING THE MAIN | | FEED PUMPS. THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION ACTION STATEMENT, AND ALL OTHER SAFETY EQUIPMENT IS | | OPERABLE. THE LICENSEE IS SHUTTING DOWN THE UNIT AT THE RATE OF 25-50 | | MW/HR. THE CAUSE OF THE FEED REG VALVE PROBLEM IS UNKNOWN AND IS BEING | | INVESTIGATED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31659 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/26/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:36 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/26/97 | +------------------------------------------------+EVENT TIME: 12:08[EST]| |NRC NOTIFIED BY: MICHELLE SAVINO |LAST UPDATE DATE: 01/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION |NEIL SHEEHAN, REG 1 PAO | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 14 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP FROM 14% DUE TO LOW STEAM GENERATOR LEVEL FOLLOWING | | A MANUAL TURBINE TRIP | | | | AS PART OF A UNIT SHUTDOWN DUE TO FEEDWATER REGULATING VALVE PROBLEMS (SEE | | EN 31658), THE LICENSEE MANUALLY TRIPPED THE TURBINE AT 1208 WITH THE | | REACTOR AT 14% POWER. DUE TO THE RESULTING RAPID LEVEL DECREASE IN THE '23' | | STEAM GENERATOR, AN AUTOMATIC REACTOR TRIP OCCURRED, AND AUXILIARY | | FEEDWATER AUTOMATIC INITIATED. ALL CONTROL RODS FULLY INSERTED DUE TO THE | | REACTOR TRIP. THERE WERE NO OTHER ENGINEERED SAFETY FEATURE ACTUATIONS, | | THERE WERE NO SAFETY INJECTIONS, AND NONE OF THE RELIEF VALVES LIFTED. THE | | LOWEST STEAM GENERATOR LEVEL REACHED WAS 2% OF NARROW RANGE. THE AUTOMATIC | | REACTOR TRIP SETPOINT WAS AT 8% OF NARROW RANGE LEVEL. | | | | THE UNIT IS CURRENTLY IN HOT STANDBY. NORMAL CHARGING AND MAKEUP AND THE | | REACTOR COOLANT PUMPS ARE BEING USED FOR PRIMARY INVENTORY AND TRANSPORT | | CONTROL. SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER, AND AUXILIARY | | FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE LICENSEE ALSO PLANS | | TO NOTIFY STATE, LOCAL, AND COUNTY OFFICIALS AND TO ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 31660 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NORTHERN STATES POWER CO. |NOTIFICATION DATE: 01/26/97 | | CITY: ALLENTOWN REGION: 1 |NOTIFICATION TIME: 19:38 [ET]| | COUNTY: LEHIGH STATE: PA |EVENT DATE: 01/26/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 19:25[EST]| | DOCKET: |LAST UPDATE DATE: 01/26/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS MOSLAK, REG 1 RDO | | |JOE HOLONICH, NMSS EO | +------------------------------------------------+FRANK CONGEL, IRD AEOD | |NRC NOTIFIED BY: LEN INSALACO |WAYNE KROPP, REG 3 RDO | |HQ OPS OFFICER: LEIGH TROCINE |KEVIN MOORE DOE | +------------------------------------------------+LTJG MOORHOUSE, NRC DOT | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT 1925, CONRAIL (RAY GLOEDE) IN MT. LAUREL, NEW JERSEY, NOTIFIED THE | | PENNSYLVANIA DEPARTMENT OF ENVIRONMENTAL PROTECTION IN WILKES-BARRE, | | PENNSYLVANIA, OF A TRANSPORTATION EVENT INVOLVING AN OPEN DOOR ON A | | SHIPPING CONTAINER IN ALLENTOWN, PENNSYLVANIA. [HOO NOTE: SEE RELATED EN | | 31661] | | | | A SHIPMENT OF USED STAINLESS STEEL TURBINE DIAPHRAGMS WAS BEING TRANSPORTED | | FROM THE MONTICELLO NUCLEAR PLANT LOCATED NEAR MINNEAPOLIS, MN, TO ALLERON | | IN KOPPEL, PA. THE DOOR OF ONE OF TWO 20-FOOT LONG C-VANS CONTAINING THESE | | DIAPHRAGMS WAS FOUND TO BE OPEN IN THE CONRAIL RAIL YARD IN ALLENTOWN, PA. | | THE C-VAN CONTAINERS WERE LOCATED ON A RAIL CAR, AND THEY EACH CONTAINED | | APPROXIMATELY 40,000 POUNDS OF USED STAINLESS STEEL TURBINE DIAPHRAGMS WITH | | LOW LEVEL SURFACE CONTAMINATION (SEVERAL THOUSAND DPM/100 CM^2 SMEARABLE, | | OR APPROXIMATELY 1 mREM/HR) (CLASS-7 2913-PLACARD MATERIAL). THE HIGHEST | | DOSE RATE ON CONTACT WITH THE C-VAN WAS 0.8 mREM/HR. EACH DIAPHRAGM WAS | | WRAPPED IN PLASTIC, AND THERE WAS NO OBVIOUS DAMAGE TO THE WRAPPING. A | | LICENSEE REPRESENTATIVE STATED THAT THERE WAS NO EXPOSURE DANGER IF THE | | PLASTIC WRAPPING WAS NOT BREACHED. THE RIGHT DOOR (LOOKING FROM THE REAR) | | WAS FOUND TO BE OPEN APPROXIMATELY 3 FEET, AND THE WOOD LOCKING AND BRACING | | WAS VISIBLE INSIDE THE CONTAINER NEAR THE DOOR. THERE WERE NO PARTS FOUND | | OUTSIDE OF THE CONTAINER, AND THE DOOR WAS BELIEVED TO HAVE OPENED DUE TO | | SHIFTING OF THE CONTENTS AGAINST THE DOOR AT THE ALLENTOWN RAIL YARD. A | | MONTICELLO REPRESENTATIVE (DECKER) STATED THAT THE EVENT WAS IDENTIFIED AT | | APPROXIMATELY 1630 CST. | | | | THERE IS SOME CONFUSION REGARDING THE SHIPPING PAPERS AND HOW THE RAIL CAR | | IN QUESTION ARRIVED IN ALLENTOWN, PA. THE PA DEPARTMENT OF ENVIRONMENTAL | | PROTECTION REPORTED THAT SHIPMENT ENTERED THE CONRAIL SYSTEM ON JANUARY 19, | | 1997, AND WAS MISTAKENLY TRANSPORTED TO THE MAHER TERMINAL LOCATED IN | | DOCKSIDE, NJ. THE ERROR WAS DISCOVERED, AND THE SHIPMENT WAS FORWARDED TO | | KOPPEL, PA. HOWEVER, THE INFORMATION IN THE CONRAIL COMPUTER INDICATED THAT | | THE RAIL CAR HAD BEEN EMPTIED, EVEN THOUGH IT HAD NEVER BEEN UNLOADED. | | | | THE RAIL CAR HAS BEEN ISOLATED. CONRAIL CURRENTLY HAS A HAZARDOUS MATERIALS | | REPRESENTATIVE ONSITE AND HAS CONTRACTED REACT TO ENSURE THAT THE LOAD WILL | | BE ADEQUATELY SECURED PRIOR TO ANY FURTHER SHIPMENT. THE PA DEPARTMENT OF | | ENVIRONMENTAL PROTECTION HAS NOTIFIED THE PA EMERGENCY MANAGEMENT AGENCY | | AND HAS DISPATCHED A REPRESENTATIVE TO THE SITE. A RADIATION PROTECTION | | SUPERVISOR FROM MONTICELLO HAS ALSO BEEN DISPATCHED TO THE RAIL YARD AND IS | | EXPECTED TO ARRIVE TOMORROW MORNING. IN ADDITION, MONTICELLO REQUESTED | | LIMERICK (LOCATED NEAR PHILADELPHIA, PENNSYLVANIA) TO SEND A HEALTH PHYSICS | | REPRESENTATIVE TO THE RAIL YARD TO HELP ASSESS THE STATUS. THE LIMERICK | | REPRESENTATIVE IS EXPECTED TO ARRIVE AT THE RAIL YARD BY 2230 TONIGHT AND | | PLANS TO REPORT THE STATUS OF THE SHIPMENT TO MONTICELLO. MONTICELLO PLANS | | TO INFORM THE NRC OF THIS STATUS WHEN THE REPORT FROM LIMERICK HAS BEEN | | RECEIVED. | | | | A TELEPHONE CONFERENCE CALL WAS CONDUCTED WITH REPRESENTATIVES FROM THE PA | | DEP (INSALACO); CONRAIL (GLOEDE, RICKTER, AND UNDERWOOD); MONTICELLO | | (WINDSCHILL); AND NRC REGION 1 (HEHL, WHITE, AND MOSLAK); REGION 3 (KROPP); | | AEOD IRD (CONGEL); AND THE NMSS EO (HOLONICH). THE NATIONAL RESPONSE | | CENTER HAS NOTIFIED US EPA REGION 3 (STEUTEVILLE). [SEE HOO LOG FOR PA DEP, | | CONRAIL, AND MONTICELLO CONTACT TELEPHONE NUMBERS.] | | | | * * * UPDATE AT 0018 BY WINDSCHILL(MONTICELLO) TO GOULD * * * | | | | CONFERENCED WINDSCHILL WITH WHITE (REG 1) TO INFORM NRC THAT A SURVEY HAD | | BEEN COMPLETED AND NO LEAKAGE WAS FOUND OR SPREAD OF CONTAMINATION | | OCCURRED. IT APPEARS THAT SOME SHORING HAD FORCED THE DOOR OPEN. THEY WERE | | ABLE TO GET THE DOOR PARTIALLY CLOSED, BUT IT APPEARS THAT THE DOOR MAY BE | | BENT, PROHIBITING IT FROM BEING CLOSED COMPLETELY. THEY WILL COMPLETELY | | CLOSE THE DOOR PRIOR TO THE SHIPMENT BEING SENT TO ITS FINAL DESTINATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31661 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 01/26/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 21:47 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 01/26/97 | +------------------------------------------------+EVENT TIME: 20:00[CST]| |NRC NOTIFIED BY: PAT DECKER |LAST UPDATE DATE: 01/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 +------------------------------------------------------------------------------+ | TRANSPORTATION EVENT INVOLVING AN OPEN DOOR OF A CONTAINER ON A RAIL CAR | | [HOO NOTE: SEE RELATED EN 31660.] | | | | AT APPROXIMATELY 1630 CST, A TRAIN CAR CONTAINING OLD TURBINE DIAPHRAGMS | | WAS 'BUMPED' AT THE ALLENTOWN RAIL YARD IN PENNSYLVANIA, AND THIS | | APPARENTLY CAUSED THE C-VAN DOORS TO OPEN. THE INTERNAL PACKAGING IS INTACT | | (WRAPPED IN LAYERS OF PLASTIC TO PREVENT THE SPREAD OF CONTAMINATION). THE | | RAIL CAR IS CURRENTLY LOCATED AT THE RAIL YARD IN ALLENTOWN, PENNSYLVANIA, | | AND A REPRESENTATIVE FROM THE SITE IS EN ROUTE TO THE RAIL YARD. A | | REPRESENTATIVE FROM LIMERICK (LOCATED NEAR PHILADELPHIA, PENNSYLVANIA) IS | | ALSO EN ROUTE. THE DETERMINATION TO INFORM THE DEPARTMENT OF TRANSPORTATION | | WAS MADE AT APPROXIMATELY 2000 CST. | | | | ANOTHER AGENCY NOTIFIED THE DEPARTMENT OF TRANSPORTATION, AND THE LICENSEE | | NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31662 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/27/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 03:11 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/27/97 | +------------------------------------------------+EVENT TIME: 01:52[CST]| |NRC NOTIFIED BY: DUCK |LAST UPDATE DATE: 01/27/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT REPORTED FAILURE OF THE ENS (FTS 2000) PHONE SYSTEM ALONG WITH | | FAILURE OF THEIR NARS AND LOCAL COMMERCIAL PHONE SYSTEMS. | | | | THE LICENSEE WAS MADE AWARE OF THIS PROBLEM WHEN NOTIFIED BY NRC OPERATIONS | | CENTER VIA LICENSEE'S BULK POWER OPERATIONS(DISPATCHER), THAT THE FTS | | 2000(ENS) SYSTEM WAS OUT OF SERVICE. THE LICENSEE CURRENTLY HAS THE DIXON | | MICROWAVE SYSTEM AND BULK POWER OPERATIONS PHONE AVAILABLE FOR SERVICE. | | | | THE RESIDENT INSPECTOR AND THE STATE WILL BE NOTIFIED. | | | | ***UPDATE AT 0525 FROM REED TO GOULD*** THE PHONE PROBLEM WAS FOUND TO BE | | CAUSED BY A BREAKER WHICH TRIPPED DURING A POWER TRANSFER THAT OCCURRED ON | | SUNDAY. IT WAS RESET AT 0415CST AND IT APPEARS THAT THE TELEPHONES ARE | | OPERABLE. | +------------------------------------------------------------------------------+