U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/10/97 - 03/11/97 ** EVENT NUMBERS ** 31802 31854 31920 31921 31922 31923 31924 31925 31926 31927 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31802 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/18/97 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 02:06 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 02/17/97 | +------------------------------------------------+EVENT TIME: 23:27[EST]| |NRC NOTIFIED BY: STEVE MERRILL |LAST UPDATE DATE: 03/10/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 +------------------------------------------------------------------------------+ | CONTROL ROOM EMERGENCY FILTRATION FAN DAMPER FAILED TO OPEN UPON RECEIPT OF | | AN ACTUATION SIGNAL. | | | | THE "A" CHANNEL CONTROL ROOM AIR INTAKE RADIATION MONITOR GENERATED A | | SPURIOUS HIGH RADIATION SIGNAL. THE DAMPER FOR THE CONTROL ROOM EMERGENCY | | FILTRATION FAN "HVE-13A" SHOULD HAVE OPENED UPON RECEIPT OF THE SIGNAL, BUT | | DIDN'T. THE CAUSE OF THE DAMPER'S FAILURE TO OPEN IS NOT YET KNOWN. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 3/10/97 @ 0746 BY MERRILL TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT DUE TO THE ACTUATION BEING INVALID AND IT INVOLVED | | ONLY THE CONTROL ROOM EMERGENCY VENTILATION SYSTEM. ADDITIONALLY, THE | | PLANT PROPERLY ENTERED THE APPLICABLE ACTION STATEMENT AT THE TIME OF | | DISCOVERY OF THE FAILURE, AND THE SYSTEM WAS RETURNED TO OPERABLE STATUS | | WITHIN THE ALLOWABLE OUTAGE TIME. THE RESIDENT INSPECTOR WAS NOTIFIED. REG | | 2 RDO(PEEBLES) WAS NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31854 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 02/26/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 15:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/25/97 | +------------------------------------------------+EVENT TIME: 02:00[EST]| |NRC NOTIFIED BY: HOPKINS |LAST UPDATE DATE: 03/10/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCALPINE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT DUE TO EXCEEDING 102% OF THE LICENSED THERMAL POWER LIMIT | | | | THE FOLLOWING IS TEXT OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON 2/25/97, AT APPROXIMATELY 0200 EST, UQ1118 (REACTOR THERMAL POWER | | CALCULATED VALUE) MOMENTARILY INDICATED 3637.9 MWt FOLLOWING A PLANNED | | MANUAL ISOLATION OF THE 6B FEEDWATER HEATER EXTRACTION STEAM SUPPLY. THIS | | REACTOR POWER OUTPUT REPRESENTS A POWER LEVEL OF 102.04%. INITIALLY, THIS | | CONDITION WAS NOT INTERPRETED AS AN ACTUAL RISE IN POWER ABOVE 102% BECAUSE | | IT WAS KNOWN FROM PREVIOUS EVENTS THAT UQ1118 IS INACCURATE DURING A | | FEEDWATER FLOW TRANSIENT; HOWEVER, DURING THE EVALUATION OF THE EVENT, | | FEEDWATER FLOW WAS FOUND TO REMAIN CONSTANT AND ONLY TEMPERATURE CHANGED. | | THIS EVENT REPRESENTS A VIOLATION OF THE VOGTLE ELECTRIC GENERATING PLANT | | OPERATING LICENSE REQUIREMENTS, WHICH LIMITS OPERATION TO 3565 MWt. THIS | | EVENT IS BEING REPORTED PER SECTION 2.H OF OPERATING LICENSE NPF-68. | | ENGINEERING IS CONTINUING THEIR EVALUATION OF THIS EVENT." | | | | THE LICENSEE STATED THAT INDICATED REACTOR THERMAL POWER REMAINED ABOVE | | 102% FOR LESS THAN 5 MINUTES. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE AT 1613 EST ON 3/10/97 FROM THORNTON TAKEN BY KARSCH * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. UPON FURTHER INVESTIGATION THE | | LICENSEE DETERMINED THAT THEY DID NOT EXCEED THEIR POWER LIMIT OF 102%. THE | | INITIAL CALCULATION WAS BASED ON SECONDARY PLANT CALORIMETRIC CALCULATIONS. | | THESE CALCULATIONS MAY BE IN ERROR DURING FEEDWATER TRANSIENTS. A | | FEEDWATER TRANSIENT WAS IN PROGRESS AT THE TIME OF THE CALCULATION. | | CONFIRMATORY POWER READINGS BASED ON REACTOR COOLANT LOOP DELTA TEMPERATURE | | RESULTED IN A POWER OF 101.3% AND A READING BASED ON EX-CORE | | INSTRUMENTATION GAVE A READING OF 100.5%. BASED ON THESE OBSERVATIONS THE | | LICENSEE CONSIDERS THE VALUE FROM THE CALORIMETRIC CALCULATION TO BE IN | | ERROR AND NO LICENSE VIOLATION OCCURRED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. R2DO (PEEBLES) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31920 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/10/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 08:51 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/10/97 | +------------------------------------------------+EVENT TIME: 07:23[EST]| |NRC NOTIFIED BY: SAVINO |LAST UPDATE DATE: 03/10/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED NEW YORK DEPARTMENT OF ENVIRONMENTAL CONTROL, THE | | COAST GUARD, WESTCHESTER COUNTY DEPARTMENT OF HEALTH AND THE INTERSTATE | | SANITATION COMMISSION OF AN OIL SPILL INTO THE DISCHARGE CANAL. | | | | THIS OCCURRED WHEN ONE OF THE LICENSEE'S SNOW PLOWS LEAKED APPROXIMATELY | | ONE PINT OF HYDRAULIC OIL, SOME OF WHICH ENTERED TWO STORM DRAINS AND | | FLOWED TO THE DISCHARGE CANAL, BUT HAS NOT ENTERED THE RIVER. THE OIL IS | | UPSTREAM OF THE BOOMS INSTALLED IN THE DISCHARGE CANAL. THEIR HAZMAT CREWS | | HAVE ALSO INSTALLED BOOMS IN THE STORM DRAINS AND ALL THE OTHER OIL HAS | | BEEN REMOVED. THEY HAVE A CONTRACTOR COMING IN TO CLEAN UP THE DISCHARGE | | CANAL. THE RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31921 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTERN WAKE MEDICAL CENTER |NOTIFICATION DATE: 03/10/97 | | CITY: CARY REGION: 2 |NOTIFICATION TIME: 09:50 [ET]| | COUNTY: WAKE STATE: NC |EVENT DATE: 03/09/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 10:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM PEEBLES RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: LEE COX | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICIUM-99M MISTAKENLY FLUSHED TO THE SANITARY SYSTEM | | | | | | THE STATE OF NORTH CAROLINA DEPARTMENT OF HEALTH PHYSICS, DIVISION OF | | RADIATION PROTECTION RECEIVED THE FOLLOWING REPORT FROM A CERTIFIED NUCLEAR | | MEDICAL TECHNOLOGIST ABOUT THE FOLLOWING EVENT THAT TOOK PLACE AT THE | | WESTERN WAKE MEDICAL CENTER LOCATED IN CARY, NC, WHICH IS IN WAKE COUNTY. | | | | A CONTRACT TECHNICIAN DURING HER SHIFT MISTAKENLY FLUSHED 39 mCi OF BULK | | TECHNICIUM-99M DOWN THE TOILET TO THE SANITARY SEWER SYSTEM. SHE THOUGHT | | SHE WAS FLUSHING A SALINE SOLUTION BUT GRABBED THE WRONG SYRINGE AND | | DISCHARGED IT INTO THE TOILET. | | | | THE PERSON CALLING FROM THE STATE OF NORTH CAROLINA DID NOT KNOW IF THE | | SYRINGES WERE PROPERLY LABELLED. THE STATE OF NORTH CAROLINA IS WAITING FOR | | A WRITTEN REPORT FROM THE WESTERN WAKE MEDICAL CENTER TO GIVE THEM MORE | | DETAILS OF THE EVENT. | | | | THE STATE OF NORTH CAROLINA ASSIGNED THE FOLLOWING DESIGNATION, ICD-97-09, | | FOR THIS EVENT. | | | | SEE HOO LOG BOOK FOR PHONE NUMBERS AND CONTACTS. | | | | | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31922 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/10/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 11:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/10/97 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: MARY BETH DEPUYDT |LAST UPDATE DATE: 03/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |VERN HODGE, RVIB NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DC COOK DETERMINED THAT THE STANDARD SMB-00 LIMITORQUE TORQUE SWITCH | | ASSEMBLIES REMAINING IN STOCK WERE ALL MISSING A SPACER. | | | | | | ON JANUARY 8, 1997, WHILE INSTALLING A NEW TORQUE SWITCH ASSEMBLY FOR MOTOR | | OPERATED VALVE 2-MMO-421, IT WAS NOTED THAT A SPACER APPEARED TO BE MISSING | | FROM THE TORQUE SWITCH. AN INSPECTION OF ALL THE STANDARD SMB-00 TORQUE | | SWITCH ASSEMBLIES REMAINING IN STOCK DETERMINED THAT THEY WERE ALL MISSING | | A SPACER. THESE TORQUE SWITCH ASSEMBLIES WERE PART OF A GROUP OF 7 RECEIVED | | FROM LIMITORQUE FOR GENERAL USE AT DC COOK UNDER ASP 18787. A CONDITION | | REPORT WAS WRITTEN TO INVESTIGATE IF THIS WAS A NEW DESIGN. | | | | THE DEFECTIVE LOT OF 7 RECEIVED FROM LIMITORQUE APPARENTLY RESULTED FROM A | | MANUFACTURING ASSEMBLY ERROR AT THE LIMITORQUE FACILITY. | | | | THE DOUBLE POLE TORQUE SWITCH IS A STANDARD CONFIGURATION FOR AMERICAN | | ELECTRIC POWER AND IS USED EXTENSIVELY AT THE DC COOK PLANT IN SMB-00 | | ACTUATORS. THE 7 ASSEMBLIES SUPPLIED UNDER ASP 18787 WERE PLACED IN OPEN | | STOCK FOR USE IN THE NEXT VALVE REQUIRING ONE. THEREFORE, THE 3 TORQUE | | SWITCH ASSEMBLIES IN OPEN STOCK COULD HAVE BEEN USED IN ANY NUMBER OF | | SAFETY RELATED APPLICATIONS WITH UNKNOWN RESULTS. THE FAILURES IN THE 4 | | VALVES IN WHICH THEY WERE INSTALLED DID NOT RESULT IN ANY SAFETY IMPACT, | | HOWEVER, THIS COULD NOT BE GUARANTEED FOR ALL OTHER SMB-00 VALVE ACTUATORS | | IN THE PLANT DUE TO THE LARGE VARIETY OF APPLICATIONS FOR THE ASSEMBLY. | | SINCE IT IS NOT POSSIBLE TO DEFINITIVELY EVALUATE ALL POSSIBLE APPLICATIONS | | FOR SIGNIFICANT SAFETY HAZARD, IT WAS CONSERVATIVELY DECIDED TO SUBMIT THIS | | EVENT AS A PART 21. | | | | ALL 4 OF THE DEFECTIVE ASSEMBLIES WHICH WERE INSTALLED HAVE BEEN EITHER | | REPLACED, OR REPAIRED BY ADDITION OF A SPACER. ALL 7 ASSEMBLIES WERE | | RETURNED TO LIMITORQUE FOR EVALUATION ON MARCH 10, 1997. LIMITORQUE HAS NOT | | BEEN ABLE TO PREDICT WHEN THEIR EVALUATION MIGHT BE COMPLETE. | | | | COPY OF PART 21 SENT TO VERN HODGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31923 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/10/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 12:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/10/97 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: ANDREW WISNIEWSKI |LAST UPDATE DATE: 03/10/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE MAXIMUM FLOOD LEVEL FOR THE SWITCHGEAR ROOM IS NOT IN CONFORMANCE WITH | | FSAR 2.4-9. WATER COULD BACK UP INTO THE SWITCHGEAR ROOM THROUGH THE FLOOR | | DRAIN. PROCEDURAL AND DESIGN CHANGES ARE BEING CONSIDERED. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31924 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: THE MARION STEEL COMPANY |NOTIFICATION DATE: 03/10/97 | | CITY: MARION REGION: 3 |NOTIFICATION TIME: 15:21 [ET]| | COUNTY: STATE: OH |EVENT DATE: 03/10/97 | |LICENSE#: 34-21123-01 AGREEMENT: N |EVENT TIME: 08:30[EST]| | DOCKET: |LAST UPDATE DATE: 03/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WAYNE KROPP RDO | | |COMBS EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: MADERA (REG 3) |FLETCHER EPA | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE WAS GETTING SOME HIGH RADIATION READINGS ON ONE OF THE ROADS | | ON THEIR PROPERTY. WHEN THEY INVESTIGATED, THEY DUG UP A SEALED SOURCE | | CAPSULE BURIED UNDER 8" OF DIRT. THIS CAPSULE, WHICH MEASURED | | APPROXIMATELY 1CM X 4CM, WAS ORIGINALLY THOUGHT TO BE A SOURCE FROM A PIECE | | RADIOGRAPHIC EQUIPMENT. READINGS INITIALLY TAKEN BY THE LICENSEE MEASURED | | CONTACT RADIATION DOSE RATES >200MR/HR GAMMA. THE CAPSULE WAS PUT INTO A | | PIPE, CAPPED AND TAKEN TO AN ISOLATED AREA IN THE PLANT. THE STATE WAS | | CONTACTED AND THEY SENT TWO STATE HP'S TO THE SITE. AT 1215 THE HP'S | | REPORTED BACK THAT THE INITIAL INFORMATION WAS INCORRECT AND THAT THE | | SOURCE ACTUALLY EXHIBITED DOSE RATES OF UP TO 30R/HR GAMMA ON CONTACT. THE | | STATE DISPATCHED TWO MORE HP'S TO THE SITE FOR ADDITIONAL HELP. THEY NOW | | HAVE DETERMINED THAT THE SOURCE CAPSULE CONTAINS 500 MILLICURIES OF | | CESIUM-137 (READ FROM THE CAPSULE) AND WAS MEASURING UP TO 60R/HR AT THE | | SURFACE. THE STATE HAS PUT THE SOURCE, WHICH IS NOW BELIEVED TO BE A | | GAUGING SOURCE, IN A SHIELDED CONTAINER, PLACED IT IN A RESTRICTED AREA AND | | ADDED ADDITIONAL LEAD SHIELDING AROUND IT. IT IS NOW LOCKED AWAY AND | | CORDONED AT 200MR/HR. THEY DO NOT BELIEVE AT THIS TIME THAT ANYONE HAS | | BEEN CONTAMINATED. REGION 3 IS SENDING TWO INSPECTORS TO THE SITE TONIGHT | | TO ASSURE THE SOURCE IS SECURED AND TO CONDUCT AN INSPECTION IN THE | | MORNING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31925 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/10/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:34 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/10/97 | +------------------------------------------------+EVENT TIME: 15:50[EST]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 03/10/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THEY HAVE NEGLECTED THEIR COMMITMENT TO SEAL | | FOUR EQUIPMENT HATCHES IN THE RHR CORNER ROOMS. THESE HATCHES ALLOW | | EQUIPMENT ACCESS BETWEEN THE RHR PUMPS ON THE 213 LEVEL AND THE UPPER ROOMS | | ON THE 232 AND 252 LEVELS. THE LICENSEE HAS NOW SEALED THE HATCHES. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31926 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/10/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 20:05 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/10/97 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 03/10/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ANALYSIS OF A TURBINE BUILDING HIGH ENERGY LINE BREAK (HELB) HAS | | IDENTIFIED A PATHWAY FOR STEAM TO ENTER THE SWITCHGEAR ROOMS THROUGH DUCT | | WORK COMMON TO THE TURBINE BUILDING AND SWITCHGEAR ROOMS. THE SWITCHGEAR | | ROOMS ARE CURRENTLY DEFINED AS A MILD ENVIRONMENT DURING A TURBINE BUILDING | | HELB. THIS CONDITION IS OUTSIDE THE DESIGN BASIS OF THE PLANT. CORRECTIVE | | ACTIONS ARE UNDER EVALUATION. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31927 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/11/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 05:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/11/97 | +------------------------------------------------+EVENT TIME: 03:30[EST]| |NRC NOTIFIED BY: RADISHOFSKI |LAST UPDATE DATE: 03/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 88 POWER OPERATION | 88 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE "B" REACTOR PROTECTION SYSTEM (RPS) NORMAL POWER SUPPLY FAILED CAUSING | | A DIVISION II HALF SCRAM AND SEVERAL ESF ACTUATIONS. | | | | THE RPS NORMAL POWER SUPPLY FAILED CAUSING A DIVISION II HALF SCRAM. THE | | FOLLOWING OCCURRED DUE TO THE LOSS OF ELECTRICAL POWER FROM THE "B" RPS | | MOTOR GENERATOR SET: | | | | 1. ISOLATION OF THE REACTOR WATER CLEANUP SYSTEM | | 2. ISOLATION OF SECONDARY CONTAINMENT ZONES II AND III VENTILATION | | 3. INITIATION OF THE STANDBY GAS TREATMENT SYSTEM | | 4. INITIATION OF THE CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM | | 5. ISOLATION OF BOTH DIVISIONS OF THE CONTAINMENT RADIATION MONITORING | | SYSTEM | | 6. DIVISION II PRIMARY CONTAINMENT ISOLATION VALVES | | | | THE REACTOR PROTECTION SYSTEM WAS PLACED ON ITS ALTERNATE POWER SUPPLY. AN | | EVALUATION OF PLANT RESPONSE TO THE LOSS OF THE POWER SUPPLY WAS PERFORMED. | | ALL EQUIPMENT ACTUATED AS EXPECTED FOR THIS OCCURRENCE. THE HALF SCRAM WAS | | RESET. ALL OTHER EQUIPMENT INITIATIONS AND ISOLATIONS WERE SECURED AND | | RESET IN ACCORDANCE WITH PLANT PROCEDURES. | | | | THE "B" RPS NORMAL POWER SUPPLY MOTOR GENERATOR SET WAS DE-ENERGIZED AND | | REMOVED FROM SERVICE FOR INVESTIGATION AND REPAIRS. LICENSEE THINKS THAT | | THEY MAY HAVE A VOLTAGE REGULATOR PROBLEM WITH THE RPS MOTOR GENERATOR. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+