U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/31/95 - 04/03/95 ** EVENT NUMBERS ** 28481 28615 28616 28617 28618 28619 28620 28621 28622 28623 28624 28625 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28481 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/04/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 15:17[EST]| |NRC NOTIFIED BY: FROEBRICH |LAST UPDATE DATE: 03/31/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH HEAD SAFETY INJECTION FLOW MAY BE OUTSIDE OF ITS DESIGN LIMITS. | | | | ENGINEERING IDENTIFIED A CONDITION THAT MAY HAVE PLACED THE PLANT IN AN | | UNANALYZED CONDITION. A HIGH HEAD SAFETY INJECTION FLOW BALANCE TEST WAS | | COMPLETED DURING THE 1992 REFUELING OUTAGE. A REVIEW OF THE POST TEST | | CALIBRATION CHECKS REVEALED THAT SEVERAL OF THE DIFFERENTIAL PRESSURE | | CELLS, UTILIZED DURING THE TEST, WERE OUTSIDE OF THE REQUIRED 0.25% FULL | | SCALE ACCURACY, AND THIS MAY HAVE RESULTED IN THE HIGH HEAD SAFETY | | INJECTION FLOW BEING OUTSIDE THE PLANT DESIGN CRITERIA. PRIOR TO | | ESTABLISHING SAFETY INJECTION SYSTEM OPERABILITY, ENGINEERING WILL COMPLETE | | THE VERIFICATION TESTING AND PERFORM ANY NECESSARY CORRECTIVE ACTIONS TO | | ENSURE THE FLOW BALANCE IS WITHIN THE PLANT DESIGN CRITERIA AND SAFETY | | INJECTION PUMP OPERATING LIMITS. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1747 3/31/95 BY FROEBRICH TAKEN BY STRANSKY * * * | | | | LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. BASED UPON SUBSEQUENT | | TESTING, THE LICENSEE HAS DETERMINED THAT THE AS-FOUND CONDITION OF THE | | HIGH HEAD SAFETY INJECTION SYSTEM IS NOT OUTSIDE OF ITS DESIGN BASIS. THE | | NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R1DO (LINVILLE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28615 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/31/95 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 06:10 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/31/95 | +------------------------------------------------+EVENT TIME: 04:38[CST]| |NRC NOTIFIED BY: VARNADORE |LAST UPDATE DATE: 03/31/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF UNIT 1's SGTS BRIEFLY INOPERABLE DUE TO A BLOWN FUSE. | | | | DURING THE PERFORMANCE OF A DESIGN CHANGE REQUEST (DCR) TO THE "1B" STANDBY | | GAS TREATMENT SYSTEM (SGTS), A FUSE BLEW WHEN A JUMPER SHORTED. THIS | | RESULTED IN THE SUCTION AND DISCHARGE DAMPERS TO THE "1A" SGTS FAILING | | CLOSED. THE "1A" TRAIN OF SGTS WAS RUNNING AT THE TIME OF THE OCCURRENCE | | AS PART OF THE DCR FUNCTIONAL TEST BEING PERFORMED (THE DCR IS MODIFYING | | THE STANDBY GAS HEATER LOGIC CONTROLS). | | | | SINCE "1B" SGTS WAS ALREADY INOPERABLE DUE TO THE PERFORMANCE OF THE DCR, | | BOTH TRAINS OF SGTS BECAME INOPERABLE (12 HOURS TO HOT SHUTDOWN LCO). THE | | FUSE WAS REPLACED IN FIVE MINUTES AND THE "1A" TRAIN OF THE SGTS WAS | | RETURNED TO OPERABLE STATUS. THE "1A" AND "1B" TRAINS OF SGTS ARE UNIT 1 | | SPECIFIC, WITH EFFECT ON UNIT 2 BEING THROUGH THE COMMON REFUELING FLOOR. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28616 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 03/31/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 13:47 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/31/95 | +------------------------------------------------+EVENT TIME: 13:15[EST]| |NRC NOTIFIED BY: EBERT |LAST UPDATE DATE: 03/31/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINVILLE 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED THE U.S. DOT NATIONAL RESPONSE CENTER REGARDING A SMALL | | OIL SHEEN DISCOVERED ON THE BACK RIVER. | | | | THE LICENSEE NOTIFIED THE NATIONAL RESPONSE CENTER OF THE DISCOVERY OF A | | SMALL OIL SHEEN ON THE BACK RIVER. THE LICENSEE ESTIMATES THAT | | APPROXIMATELY 1 PINT OF OIL WAS SPILLED INTO THE RIVER. THE OIL ENTERED | | THE RIVER THROUGH A STORM SEWER OUTFLOW FROM THE PLANT. THE LICENSEE IS | | UNSURE OF THE SOURCE OF THE OIL, BUT THE LEAK HAS BEEN STOPPED AND CLEANUP | | IS UNDERWAY. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28617 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/31/95 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 16:20 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 04/01/95 | +------------------------------------------------+EVENT TIME: 23:00[MST]| |NRC NOTIFIED BY: GRABO |LAST UPDATE DATE: 04/02/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE WILL BE REQUIRED TO NOTIFIED STATE AGENCIES OF RELEASES OF AMMONIA | | AND HYDRAZINE TO ATMOSPHERE AS PART OF STEAM GENERATOR CLEANING. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "NOTIFICATION IS BEING MADE TO INFORM THE NRC THAT PVNGS UNIT 1 IS IN THE | | PROCESS OF STEAM GENERATOR HIGH TEMPERATURE CHEMICAL CLEANING. IN THAT | | PROCESS AS THE ATMOSPHERIC DUMP VALVE IS OPENED TO CAUSE BOILING IN THE | | STEAM GENERATOR, RELEASES OF AMMONIA AND HYDRAZINE WILL BE MADE. THE | | RELEASE IS ABOVE THE THRESHOLD FOR REPORTS TO STATE AGENCIES BUT BELOW OSHA | | STANDARDS. ALL APPROPRIATE REPORTS AND PERMITS HAVE BEEN FILED AND | | GRANTED. | | | | AGENCIES NOTIFIED: | | | | ARIZONA DEPARTMENT OF ENVIRONMENTAL QUALITY | | MARICOPA COUNTY EMERGENCY PLANNING | | NATIONAL RESPONSE CENTER | | ARIZONA DEPARTMENT OF EMERGENCY SERVICES" | | | | THE LICENSEE EXPECTS TO BEGIN CLEANING THE STEAM GENERATORS SOMETIME DURING | | THE EVENING OF 4/1/95. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF | | THIS NOTIFICATION BY THE LICENSEE. | | | | ***UPDATE ON 04/02 @ 07:28 FROM NATIONAL RESPONSE CENTER(BLANCHARD) TO | | GOULD*** THE NATIONAL RESPONSE CENTER REPORTED THAT IT HAD BEEN NOTIFIED OF | | THE ABOVE ACTIVITY TODAY AT 07:10. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28618 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/31/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:03 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/31/95 | +------------------------------------------------+EVENT TIME: 16:46[EST]| |NRC NOTIFIED BY: NOWELL |LAST UPDATE DATE: 03/31/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINVILLE 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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED THAT INCORRECT BOLTS WERE USED ON BONNET OF REACTOR | | WATER CLEANUP ISOLATION VALVE. | | | | WHILE INSPECTING THE REACTOR WATER CLEANUP (RWCU) OUTBOARD SUCTION | | ISOLATION VALVE (1-CU3) DUE TO A BODY-TO-BONNET FLANGE LEAK, THE LICENSEE | | DISCOVERED THAT INCORRECT BOLTS HAD BEEN INSTALLED TO ATTACH THE BONNET OF | | THE VALVE TO THE VALVE BODY. THE LICENSEE STATED THAT THE SPECIFICATIONS | | OF THESE BOLTS DO NOT COMPLY WITH THE WEAK-LINK CALCULATIONS PERFORMED FOR | | THIS VALVE AS PART OF THE PLANT MOTOR-OPERATED VALVE PROGRAM. MAINTENANCE | | ON THIS VALVE HAD BEEN PERFORMED DURING THE LAST REFUELING OUTAGE BY A | | CONTRACTOR. | | | | THE LICENSEE IS PURCHASING NEW BOLTS, WHICH SHOULD ARRIVE ONSITE ON 4/3/95. | | THE RWCU SYSTEM REMAINS OUT OF SERVICE, AND REACTOR VESSEL CONDUCTIVITY | | LEVELS HAVE BEEN SLOWLY INCREASING. THE LICENSEE HOPES TO REPAIR THE VALVE | | AND PLACE THE RWCU SYSTEM BACK INTO SERVICE BEFORE CONDUCTIVITY LEVELS | | INCREASE SUCH THAT THE UNIT WOULD NEED TO BE SHUT DOWN. THE LICENSEE | | STATED THAT THE INCORRECT BOLTS WERE INSTALLED BECAUSE THE BOLT | | SPECIFICATION WAS PROPRIETARY INFORMATION OF THE VALVE VENDOR, AND THAT THE | | MAINTENANCE CONTRACTOR DID NOT HAVE ACCESS TO IT. THE LICENSEE IS | | CURRENTLY REVIEWING OTHER WORK PERFORMED BY THIS CONTRACTOR TO SEE IF OTHER | | VALVES MAY BE SIMILARLY AFFECTED. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED OF THIS NOTIFICATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28619 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/31/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 17:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/31/95 | +------------------------------------------------+EVENT TIME: 15:50[CST]| |NRC NOTIFIED BY: HESSLING |LAST UPDATE DATE: 03/31/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 24-HOUR REPORT DUE TO INOPERABLE PERSONNEL AIRLOCK | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "IN ACCORDANCE WITH SECTION 2.G OF OPERATING LICENSE NPF-76, A 24 HOUR | | REPORT IS BEING MADE DUE TO OPERATION NOT IN ACCORDANCE WITH TECHNICAL | | SPECIFICATIONS. | | | | A LOCAL LEAK RATE TEST WAS PERFORMED ON THE INNER DOOR OF THE PERSONNEL | | AIRLOCK (PAL) ON MARCH 30, 1995, WHICH IDENTIFIED LEAKING EQUALIZING | | VALVES. INDICATIONS ARE THAT THIS CONDITION HAD EXISTED SINCE MAINTENANCE | | WAS PERFORMED WITH THE PLANT IN MODE 1 AT 100% POWER ON FEBRUARY 28, 1995. | | | | SINCE THE AIRLOCK WAS THOUGHT TO BE OPERABLE BECAUSE POST-MAINTENANCE | | TESTING DID NOT REVEAL THE LEAKAGE, THE OUTER DOOR WAS NOT LOCKED IN | | ACCORDANCE WITH TECHNICAL SPECIFICATION 3.6.1.3 ACTION a.1, AND ACCESS TO | | THE REACTOR CONTAINMENT BUILDING WAS ALLOWED THROUGH THE AIRLOCK FOR 1RE05 | | PREPARATIONS. | | | | THE RCB AIRLOCK WAS THOUGHT TO BE OPERABLE FOR TECHNICAL SPECIFICATION | | REQUIREMENTS FOR APPROXIMATELY 95 HOURS FROM 2/28/95 AT 1707 THROUGH MODE 5 | | ENTRY ON 3/4/95 AT 1603." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS NOTIFICATION BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28620 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/31/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:42 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/31/95 | +------------------------------------------------+EVENT TIME: 17:20[EST]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 03/31/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINVILLE 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY COMPONENT COOLING WATER PUMPS STARTED DURING CIRCUIT BREAKER | | REPLACEMENT DUE TO PROCEDURAL INADEQUACY | | | | WHILE REPLACING CIRCUIT BREAKERS ON INSTRUMENT BUS "23", DEENERGIZATION OF | | A CIRCUIT BREAKER CAUSED A LOW-PRESSURE TRIP RELAY FOR THE COMPONENT | | COOLING WATER (CCW) SYSTEM PUMPS TO PICK UP, AUTOMATICALLY STARTING THE | | BACKUP CCW PUMPS. THE PUMPS STARTED AS DESIGNED, AND WERE MANUALLY SECURED | | BY THE LICENSEE AFTER DETERMINING THE CAUSE OF THE AUTOMATIC START. | | | | THE LICENSEE STATED THAT THE PROCEDURE BEING USED FOR THE BREAKER | | REPLACEMENT DID NOT ADEQUATELY ADDRESS THE EXPECTED RESPONSE OF THE | | LOW-PRESSURE TRIP CIRCUIT TO THE DEENERGIZATION OF CIRCUIT BREAKER "19". | | THE CCW SYSTEM IS AN EMERGENCY SAFETY FEATURE AT INDIAN POINT 2, AND | | ALTHOUGH THE LOW-PRESSURE TRIP CIRCUIT IS NOT SAFETY-RELATED, THE LICENSEE | | CONSIDERS THIS EVENT TO BE REPORTABLE. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED OF THIS NOTIFICATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28621 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/01/95 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 03:34 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/01/95 | +------------------------------------------------+EVENT TIME: 01:27[CST]| |NRC NOTIFIED BY: CANADY |LAST UPDATE DATE: 04/01/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 PLANT REPORTED THAT THEIR ERDS IS INOPERABLE. | | | | THE LICENSEE REPORTED THAT THEIR ERDS IS NOT CAPABLE OF SENDING INFORMATION | | TO THE NRC BECAUSE THEIR COMPUTER IS DOWN. THEY HAVE A TECHNICIAN COMING IN | | TO MAKE REPAIRS. THE RI HAS NOT BEEN NOTIFIED. | | | | ***UPDATE AT 11:41 BY FUCICH TO GOULD*** THE ERDS COMPUTER WAS FUNCTIONAL | | AS OF 05:45CST. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28622 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/01/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:32 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/01/95 | +------------------------------------------------+EVENT TIME: 03:42[CST]| |NRC NOTIFIED BY: HODEL |LAST UPDATE DATE: 04/01/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE LOST THEIR SECURITY KEYS. COMPENSATORY MEASURES TAKEN ON | | DISCOVERY. SEE HOO LOG FOR DETAILS. THE RI WAS INFORMED. | | | | * * * UPDATE 1235 4/1/95 FROM SHURT TAKEN BY STRANSKY * * * | | | | ALL CORES FOR VITAL AREA DOORS HAVE BEEN CHANGED. THE KEYS HAVE NOT YET | | BEEN LOCATED. THE RI WILL BE INFORMED. NOTIFIED R3DO (JORDAN) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28623 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/01/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 08:08 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/01/95 | +------------------------------------------------+EVENT TIME: 04:42[EST]| |NRC NOTIFIED BY: SCHALL |LAST UPDATE DATE: 04/01/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 24 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A MANUAL REACTOR SCRAM FROM 24% POWER AS PER SHUTDOWN | | PROCEDURES. | | | | THE PLANT WAS BEING SHUTDOWN FOR A REFUELING OUTAGE AND AS PER THEIR | | SHUTDOWN PROCEDURE, OGP-05, THEY HAD A CHOICE OF MANUALLY SCRAMMING THE | | REACTOR OR INSERTING INDIVIDUAL RODS FOR SHUTDOWN. THE WATER LEVEL | | TRANSIENT DURING THE SCRAM RESULTED IN AN AUTOMATIC SCRAM SIGNAL AND GROUP | | 2, 6, AND 8 ISOLATION SIGNALS ON LOW WATER LEVEL. ALL RODS FULLY INSERTED | | AND THERE WAS NO ECCS INJECTION OR SAFETY RELIEF VALVES LIFTING. THE GROUP | | 2(DRYWELL FLOOR & EQUIPMENT DRAIN ISOLATION VALVES) AND GROUP 6(CONTAINMENT | | ATMOSPHERIC CONTROL VALVES) ISOLATION VALVES CLOSED. THE GROUP 8(SHUTDOWN | | COOLING ISOLATION VALVES) ISOLATION VALVES WERE ALREADY CLOSED. ALL SYSTEMS | | FUNCTIONED AS REQUIRED. THE LEVEL WAS RESTORED TO NORMAL BAND USING | | FEEDWATER AND CONDENSATE SYSTEM. PRESSURE CONTROL IS BEING MAINTAINED BY | | THE BYPASS VALVES TO THE CONDENSER. THE REACTOR IS STABLE AND THEY ARE | | COOLING DOWN TO GO INTO THEIR REFUELING OUTAGE. THE GROUP ISOLATIONS WERE | | RESET AND SYSTEMS WERE RESTORED TO NORMAL. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28624 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/01/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:06 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/01/95 | +------------------------------------------------+EVENT TIME: 14:46[CST]| |NRC NOTIFIED BY: HITZEL |LAST UPDATE DATE: 04/01/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL 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 +------------------------------------------------------------------------------+ | LICENSEE 24-HOUR REPORT DUE TO PLACING FIRE PROTECTION PUMP CONTROL | | SWITCHES IN PULL-TO-LOCK POSITION. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 1446 CST A SMALL LEAK DEVELOPED IN THE FIRE PROTECTION JOCKEY PUMP | | DISCHARGE PIPING (PRESSURE MAINTENANCE). THIS LEAK WAS ISOLATED AND THAT | | ACTION REQUIRED FIRE PUMP "D" AND "E" TO BE PLACED IN A "PULL-TO-LOCK" | | CONFIGURATION, THIS IS REQUIRED DUE TO A REDUCED PRESSURE MAINTENANCE OF | | THE ALTERNATE JOCKEY PUMP. | | | | A MAINTENANCE TEAM HAS BEEN CALLED TO REPAIR THE LEAK. THIS REPORT IS | | REQUIRED BY TECHNICAL SPECIFICATION 3.15.C.2.a: SUBMIT A SPECIAL REPORT | | WITHIN 24 HOURS. PER TS 3.15.C.2.b A WRITTEN REPORT WILL BE SUBMITTED NO | | LATER THAN THE FIRST WORKING DAY FOLLOWING THE EVENT." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS NOTIFICATION BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28625 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 04/01/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/01/95 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: BOYLE |LAST UPDATE DATE: 04/01/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINVILLE RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN STEAM ISOLATION VALVES FAIL LOCAL LEAK RATE TEST. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "DATA EVALUATION FROM THE MAIN STEAM ISOLATION VALVE LOCAL LEAK RATE | | TESTING INDICATES THAT LEAKAGE THROUGH THE MAIN STEAM ISOLATION VALVES HAS | | DEGRADED BEYOND THE TECHNICAL SPECIFICATION 3.6.1.2.c LIMIT OF 21.7 | | LITERS/MIN (46 SCFH). THE AS FOUND LEAKAGE WAS 25 LITERS/MIN. THE UNIT IS | | CURRENTLY IN CONDITION 5 AND IN A REFUELING OUTAGE. | | | | THE LEAKAGE OF THE MAIN STEAM ISOLATION VALVES ABOVE THE TECHNICAL | | SPECIFICATION LIMIT CONSTITUTES AN EVENT FOUND WHILE THE REACTOR IS | | SHUTDOWN THAT RESULTED IN A DEGRADATION OF PRINCIPAL SAFETY BARRIERS." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS NOTIFICATION BY THE | | LICENSEE. | +------------------------------------------------------------------------------+