U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/10/96 - 04/11/96 ** EVENT NUMBERS ** 30134 30135 30215 30258 30261 30262 30263 30264 30265 30266 30267 30268 30269 30270 30271 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: BURCHFIELD |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENTRY INTO A 4-HOUR TECHNICAL SPECIFICATION ACTION STATEMENT DUE TO THE | | 2HP-3 CONTAINMENT ISOLATION VALVE BEING DECLARED INOPERABLE | | | | AS A RESULT OF EVALUATING DATA, AN ENGINEERING ANALYSIS HAS DETERMINED THAT | | VALVE 2HP-3 (CONTAINMENT ISOLATION VALVE FOR THE LETDOWN COOLER OUTLET) MAY | | NOT BE ABLE TO CLOSE AGAINST FULL DIFFERENTIAL PRESSURE UNDER CERTAIN | | ACCIDENT SCENARIOS. ASSUMING A SINGLE FAILURE OF THE SECOND CONTAINMENT | | ISOLATION VALVE FOR THE SAME PENETRATION, IT COULD POTENTIALLY RESULT IN | | THE FAILURE TO ISOLATE A CONTAINMENT PENETRATION FOLLOWING AN ACCIDENT. | | THE IMMEDIATE TECHNICAL SPECIFICATION ACTION STATEMENT ACTION IS TO CLOSE | | THE SUSPECT VALVE AND OPEN ITS BREAKER. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. (REFER TO RELATED EVENT NUMBERS 30135, 30139, AND | | 30140.) | | | | * * * 0759 APRIL 10, 1996, UPDATE FROM CLARKSON RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED UPON FURTHER ENGINEERING | | EVALUATION WHICH DETERMINED THAT VALVE 2HP-3 WAS OPERABLE (BOTH PAST AND | | PRESENT). THIS ANALYSIS LOOKED AT VALVE PERFORMANCE CONTINUALLY THROUGH | | THE VALVE STROKE AND WAS A MORE DETAILED ANALYSIS THAN THE ORIGINAL | | ANALYSIS USED TO DETERMINE THE OPERABILITY OF THE VALVE. THIS ANALYSIS | | DETERMINED THE DIFFERENTIAL PRESSURE THAT THE VALVE COULD CLOSE AGAINST | | DURING EACH MILLISECOND OF THE DESIGN BASIS EVENT. THIS INFORMATION WAS | | THEN REVIEWED AGAINST THE SYSTEM MODEL. THE LICENSEE'S REVIEW YIELDED THAT | | THE VALVE COULD HAVE INDEED STROKED AGAINST THE EXPECTED DIFFERENTIAL | | PRESSURE DURING THE DESIGN BASIS EVENT. THE LICENSEE NOTIFIED THE NRC | | RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (VERRELLI). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: BURCHFIELD |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABILITY OF THE 3HP-3 CONTAINMENT ISOLATION VALVE | | | | AS A RESULT OF EVALUATING DATA, AN ENGINEERING ANALYSIS HAS DETERMINED THAT | | VALVE 3HP-3 (CONTAINMENT ISOLATION VALVE FOR THE LETDOWN COOLER OUTLET) MAY | | NOT BE ABLE TO CLOSE AGAINST FULL DIFFERENTIAL PRESSURE UNDER CERTAIN | | ACCIDENT SCENARIOS. ASSUMING A SINGLE FAILURE OF THE SECOND CONTAINMENT | | ISOLATION VALVE FOR THE SAME PENETRATION, IT COULD POTENTIALLY RESULT IN | | THE FAILURE TO ISOLATE A CONTAINMENT PENETRATION FOLLOWING AN ACCIDENT. | | THE LICENSEE TAGGED THE VALVE OUT OF SERVICE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. (REFER TO SEE RELATED | | EVENT NUMBERS 30134, 30139, AND 30140.) | | | | * * * 0759 APRIL 10, 1996, UPDATE FROM CLARKSON RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED UPON FURTHER ENGINEERING | | EVALUATION WHICH DETERMINED THAT VALVE 3HP-3 WAS OPERABLE (BOTH PAST AND | | PRESENT). THIS ANALYSIS LOOKED AT VALVE PERFORMANCE CONTINUALLY THROUGH | | THE VALVE STROKE AND WAS A MORE DETAILED ANALYSIS THAN THE ORIGINAL | | ANALYSIS USED TO DETERMINE THE OPERABILITY OF THE VALVE. THIS ANALYSIS | | DETERMINED THE DIFFERENTIAL PRESSURE THAT THE VALVE COULD CLOSE AGAINST | | DURING EACH MILLISECOND OF THE DESIGN BASIS EVENT. THIS INFORMATION WAS | | THEN REVIEWED AGAINST THE SYSTEM MODEL. THE LICENSEE'S REVIEW YIELDED THAT | | THE VALVE COULD HAVE INDEED STROKED AGAINST THE EXPECTED DIFFERENTIAL | | PRESSURE DURING THE DESIGN BASIS EVENT. THE LICENSEE NOTIFIED THE NRC | | RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO | | (VERRELLI). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30215 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/01/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:51 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/01/96 | +------------------------------------------------+EVENT TIME: 13:00[EST]| |NRC NOTIFIED BY: DAVID PIETRUSKI |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE 25% TECHNICAL SPECIFICATION ALLOWABLE EXTENSION TIME FOR | | TWO 18-MONTH SURVEILLANCES WAS EXCEEDED DURING THE LAST UNIT RUN CYCLE | | (PRIOR TO DECEMBER 1994) | | | | DURING A REVIEW OF DOCUMENTATION ON COMPLETED SURVEILLANCES, IT WAS | | DISCOVERED THAT THE 25% TECHNICAL SPECIFICATION ALLOWABLE EXTENSION TIME | | FOR TWO 18-MONTH SURVEILLANCES WAS EXCEEDED DURING THE LAST RUN CYCLE | | (BETWEEN REFUELING OUTAGES #14R AND #15R). (THE #15R REFUELING OUTAGE WAS | | COMPLETED IN DECEMBER 1994.) THE TWO PROCEDURES THAT WERE IDENTIFIED AS | | EXCEEDING THE 25% TECHNICAL SPECIFICATION ALLOWABLE EXTENSION TIME WERE | | PROCEDURE #602.4.003, ELECTROMATIC RELIEF VALVE OPERABILITY TEST, AND | | PROCEDURE #665.5.002, SECONDARY CONTAINMENT LEAK RATE TEST. BOTH OF THESE | | 18-MONTH SURVEILLANCES WERE SATISFACTORILY PERFORMED DURING REFUELING | | OUTAGE #15R. THE LICENSEE IS STILL REVIEWING SURVEILLANCE RELATED | | DOCUMENTATION AND MAY FIND ADDITIONAL EXAMPLES OF THIS PROBLEM. ADDITIONAL | | EXAMPLES WILL BE DOCUMENTED IN THE LICENSEE EVENT REPORT FOR THE TWO | | EXAMPLES REFERENCED IN THIS NOTIFICATION. THE LICENSEE PLANS TO NOTIFY THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1523 EDT ON 04/10/96, FROM PIETRUSKI TAKEN BY KARSCH * * * | | | | UPON FURTHER REVIEW, THE LICENSEE DETERMINED THAT THE 25% TIME EXTENSION | | FOR COMPLETION OF THE SURVEILLANCE TESTING WAS NOT EXCEEDED AS STATED IN | | THE ORIGINAL REPORT. ALL TESTING WAS COMPLETED WITHIN THE TECHNICAL | | SPECIFICATION ALLOWABLE TIME LIMIT. THEREFORE, NO EVENT NOTIFICATION WAS | | REQUIRED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30258 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/09/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/09/96 | +------------------------------------------------+EVENT TIME: 17:45[EDT]| |NRC NOTIFIED BY: ERIC DeMONCH |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A MISSED SURVEILLANCE TEST | | (THIS EVENT IS SIMILAR TO EVENT #30267.) | | | | NRC GENERIC LETTER 96-01 AND NRC INFORMATION NOTICE 95-15 REQUIRE LOGIC | | SYSTEM TESTING TO THE RELAY CONTACT LEVEL. THE LICENSEE'S REVIEW OF THESE | | REQUIREMENTS REVEALED THAT THE LICENSEE'S TESTING FOR BUS UNDER VOLTAGE AND | | DEGRADED VOLTAGE DOES NOT MEET THIS REQUIREMENT. THIS CONSTITUTES A MISSED | | SURVEILLANCE UNDER TECHNICAL SPECIFICATIONS 3.0.A AND 3.1, TABLE 3.1.1.N | | (PROTECTIVE INSTRUMENTATION), TESTING EVERY 24 MONTHS. A SHUTDOWN OF 20 | | MWE WAS STARTED AND WILL CONTINUE AT A RATE OF 15 MWE PER HOUR UNTIL EITHER | | THE TESTING IS SUCCESSFULLY COMPLETED OR THE UNIT REACHES COLD SHUTDOWN. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 0109 APRIL 10, 1996, UPDATE FROM RUMBIN RECEIVED BY TROCINE * * * | | | | THE LICENSEE SUCCESSFULLY COMPLETED THE REQUIRED TESTING AND CEASED THE | | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN AT 0005 ON APRIL 10, 1996. | | REACTOR POWER WAS AT 85% AT THE TIME OF THIS NOTIFICATION, AND THE LICENSEE | | CURRENTLY PLANS TO RESTORE THE UNIT TO 100% REACTOR POWER. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30261 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 02:46 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 01:48[EDT]| |NRC NOTIFIED BY: DON BOSNIC |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE LOSS OF REACTOR | | COOLANT SYSTEM (RCS) LEAKAGE DETECTION MONITORING WHEN AN ELECTRICAL | | PROTECTION ASSEMBLY (EPA) BREAKER TRIPPED | | | | AT 0011, EPA BREAKER 2VBS*ACB2A TRIPPED RESULTING IN A HALF SCRAM, HALF | | MAIN STEAM ISOLATION VALVE (MSIV) ISOLATION, AND DIVISION 1 NUCLEAR STEAM | | SUPPLY SHUTOFF SYSTEM (NSSSS) ISOLATION. THE NSSSS ISOLATION CAUSED A LOSS | | OF THE RCS LEAKAGE DETECTION MONITORING SYSTEM DUE TO THE LOSS OF LOGIC | | POWER. IT APPEARS THAT ENGINEERED SAFETY FEATURES (ESF) ACTUATION OCCURRED | | AS EXPECTED. THE UNIT RECEIVED A SECONDARY CONTAINMENT ISOLATION. THE | | STANDBY GAS TREATMENT TRAINS INITIATED AS EXPECTED, AND THE CONTROL ROOM | | SPECIAL FILTER TRAIN ALSO INITIATED ON DIVISION 1 AS EXPECTED. THE | | LICENSEE PLANS TO MAKE AN ADDITIONAL FOUR-HOUR NOTIFICATION WITH REGARD TO | | THE ESF ACTUATIONS. | | | | AT 0148, THE LICENSEE DETERMINED THAT ENTRY INTO TECHNICAL SPECIFICATION | | 3.0.3 WAS REQUIRED DUE TO THE LOSS OF RCS LEAKAGE DETECTION, AND A | | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN WAS COMMENCED AT THAT TIME. IF | | CONTAINMENT MONITORING WAS NOT RESTORED, TECHNICAL SPECIFICATION 3.0.3 | | REQUIRED THAT THE LICENSEE INITIATE A UNIT SHUTDOWN WITHIN 1 HOUR, PLACE | | THE UNIT IN STARTUP WITHIN THE FOLLOWING 6 HOURS, AND PLACE THE UNIT IN HOT | | SHUTDOWN WITHIN THE FOLLOWING 6 HOURS. | | | | THE LICENSEE STRIPPED THE DOWNSTREAM LOADS, RECLOSED THE EPA BREAKER, AND | | RE-ENERGIZED TWO OF THE FIVE DOWNSTREAM PANELS. THIS ALLOWED THE LICENSEE | | TO RECOVER SOME PORTION OF THE ISOLATIONS THAT OCCURRED (ONE OF WHICH WAS | | LEAKAGE DETECTION). AS A RESULT, THE LICENSEE RESTORED CONTAINMENT | | MONITORING AND EXITED TECHNICAL SPECIFICATION 3.0.3 AT 0232. THE UNIT | | SHUTDOWN WAS CEASED AT THAT TIME WITH THE UNIT AT APPROXIMATELY 95% REACTOR | | POWER. | | | | THE LICENSEE PLANS TO MAINTAIN THE UNIT AT THIS POWER LEVEL UNTIL THE LOGIC | | SYSTEM IS RECOVERED BECAUSE PART OF THE ISOLATION ISOLATES THE HYDRAULICS | | TO THE RECIRCULATION FLOW CONTROL VALVE WHICH CONTROLS THE LICENSEE'S | | ABILITY TO THROTTLE BACK ON POWER WITH RECIRCULATION. IN ADDITION, THE | | LICENSEE IS CURRENTLY RECOVERING THE NON-MSIV ISOLATION LOGICS AND PLANS TO | | TROUBLESHOOT THE CAUSE FOR THE EPA BREAKER TRIP. THE LICENSEE BELIEVES | | THAT THE PROBLEM MAY BE IN THE INBOARD OR OUTBOARD MSIV LOGIC CIRCUITS OR | | IN THE REACTOR PROTECTION SYSTEM LOGIC CIRCUITS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 0357 APRIL 10, 1996, UPDATE FROM BOSNIC RECEIVED BY TROCINE * * * | | | | THE EPA BREAKER TRIP CAUSED THE FOLLOWING ESF ACTUATIONS: SECONDARY | | CONTAINMENT ISOLATION; STANDBY GAS TREATMENT SYSTEM INITIATION; DIVISION 1 | | CONTROL ROOM SPECIAL FILTER TRAIN AUTOMATIC START; NSSSS GROUP 2, 3, 4, 5, | | 6, 8, AND 9 ISOLATIONS ON DIVISION 1. THESE ACTUATIONS WERE ALL EXPECTED | | AND RESPONDED CORRECTLY. THE LICENSEE SUBSEQUENTLY OPENED THE DOWNSTREAM | | LOADS FROM THE EPA BREAKER, AND THE EPA BREAKER WAS RECLOSED AT 0128. THUS | | FAR, NSSSS ISOLATION LOGIC HAS BEEN RESTORED TO GROUPS 2, 3, 4, 5, 6, 8, | | AND 9; AND THE LICENSEE IS CURRENTLY IN THE PROCESS OF RESTORING THE | | SYSTEMS THAT WERE AFFECTED BY THOSE ISOLATIONS TO THEIR NORMAL LINEUPS. THE | | BREAKERS FOR THREE PANELS DOWNSTREAM OF THE EPA BREAKER ARE STILL OPEN. | | THESE INCLUDE THE GROUP 1 ISOLATION FOR DIVISION 1 AND FOR REACTOR | | PROTECTION SYSTEM LOGIC INITIATIONS. THE HALF SCRAM AND HALF MSIV | | ISOLATION TRIPS ARE CURRENTLY IN AS REQUIRED BY TECHNICAL SPECIFICATIONS. | | THE UNIT IS ALSO IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION DUE TO THE LOSS OF THE ON-LINE CONDUCTIVITY MONITORING. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30262 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 03:00[CDT]| |NRC NOTIFIED BY: PHILLIP A. SHORT |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN HANNON, NRR EO | |NLCO TECH SPEC LCO A/S |RALPH HERSKO FEMA | | |FRANK CONGEL IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DECLARATION OF UNUSUAL EVENT DUE THE REACTOR COOLANT BOTTOM HEAD DRAIN | | TEMPERATURE INCREASING GREATER THAN 100øF PER HOUR | | | | BETWEEN 2210 CDT AND 2310 CDT ON APRIL 9, 1996, THE REACTOR COOLANT BOTTOM | | HEAD DRAIN TEMPERATURE INCREASED GREATER THAN 100øF PER HOUR. THIS | | REQUIRED ENTRY INTO TECHNICAL SPECIFICATION 3.4.11 AND REQUIRES THAT A | | NOTIFICATION OF UNUSUAL EVENT BE DECLARED. THE CONDITION WAS CORRECTED | | ALMOST IMMEDIATELY (WITHIN THE ALLOTTED 30-MINUTE TIME FRAME OF THE | | TECHNICAL SPECIFICATION), AND AN ENGINEERING EVALUATION OF THE REACTOR | | COOLANT SYSTEM IS REQUIRED PRIOR TO RESUMING OPERATIONS. APPARENTLY, THERE | | WAS ONE READING THAT WAS 20øF TO 25øF HIGHER THAN THE THE REST OF THE | | READINGS (WHICH WERE BEING TAKEN AT 5-MINUTE INTERVALS). THIS INDICATION | | IS SUSPECT AND WAS ORIGINALLY DISCOUNTED. THE LICENSEE CHECKED THE | | RECORDER BUT DID NOT FIND A REASON TO DISCOUNT THE READING. THE UNUSUAL | | EVENT WAS DECLARED AT 0300 CDT ON APRIL 10, 1996. | | | | THE LICENSEE PLANS TO STAY IN THE UNUSUAL EVENT UNTIL THERE IS GOOD CONTROL | | AND THERE IS ASSURANCE THAT THIS WILL NOT OCCUR AGAIN. READINGS ARE | | CURRENTLY BEING TAKEN AT 30-MINUTE INTERVALS. THE LICENSEE IS ALSO | | CURRENTLY WORKING TOWARD GETTING THE REACTOR RECIRCULATION SYSTEM RESTARTED | | FOLLOWING AN EARLIER EVENT (#30253). THE CONDENSER IS NOT AVAILABLE, AND | | THE LICENSEE IS USING SAFETY RELIEF VALVES TO REMOVE DECAY HEAT. RESIDUAL | | HEAT REMOVAL IS IN SUPPRESSION POOL COOLING, AND THE CONTROL ROD DRIVE | | SYSTEM IS IN ITS NORMAL MODE. REACTOR CORE ISOLATION COOLING IS | | OCCASIONALLY BEING USED AS A SUPPLEMENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL GOVERNMENTS. | | | | * * * UPDATE AT 2146 EDT ON 04/10/96, FROM HALVERSON TAKEN BY KARSCH * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 1945 CDT. ENGINEERING | | EVALUATION DETERMINED THAT THIS EVENT IS WITHIN THE ANALYZED DESIGN BASIS | | FOR THE PLANT. RECIRCULATION PUMP 'B' HAS BEEN PLACED IN SERVICE TO | | PREVENT THERMAL STRATIFICATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL | | GOVERNMENT AGENCIES. THE NRC OPERATIONS CENTER NOTIFIED THE R3DO | | (BURGESS), NRR EO (HANNON), AND FEMA (STORER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:28 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 09:45[EDT]| |NRC NOTIFIED BY: DAVID PIETRUSKI |LAST UPDATE DATE: 04/10/96 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL LIFTING LEVER ON CONTAINMENT SPRAY HEAT EXCHANGER RELIEF VALVE FOUND | | IN THE OPEN POSITION | | | | DURING THE PERFORMANCE OF CONTAINMENT SPRAY HEAT EXCHANGER MAINTENANCE, ONE | | OF THE RELIEF VALVES ON THE 1-2 CONTAINMENT SPRAY HEAT EXCHANGER WAS | | DISCOVERED TO BE OPEN AT 2102 ON APRIL 9, 1996. THE MANUAL LIFTING LEVER | | ON THE RELIEF VALVE WAS IN THE OPEN POSITION. THIS SYSTEM WAS TIED INTO | | THE PRIMARY CONTAINMENT. | | | | APPARENTLY, THE MANUAL LEVER WAS FOUND TO BE IN THE OPEN POSITION WHEN A | | PUMP WAS STARTED TO TEST THE SYSTEM FOR HEAT EXCHANGER LEAKAGE. SOME WATER | | ESCAPED, BUT THERE WERE NO PERSONNEL CONTAMINATIONS. THE LICENSEE STOPPED | | THE PUMP, CLOSED THE RELIEF VALVE, AND PERFORMED A TEST RUN OF THE SYSTEM | | IN ORDER TO VERIFY THAT THE VALVE WAS ACTUALLY CLOSED. | | | | THE DETERMINATION THAT THIS ISSUE INVOLVED OPERATION OUTSIDE THE DESIGN | | BASIS WAS MADE AT 0945 ON APRIL 10, 1996. TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION WERE NOT ENTERED AS A RESULT OF THIS EVENT BECAUSE | | THE VALVE HAD BEEN CLOSED UPON DISCOVERY. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30264 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: JOHN LIJOI |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INOPERABILITY OF 77 EMERGENCY SIRENS IN WESTCHESTER COUNTY DUE TO A RADIO | | REPEATER FAILURE (SAME AS EVENT #30266 FOR INDIAN POINT UNIT 3 EXCEPT THAT | | 77 SIRENS WERE REPORTED TO BE AFFECTED IN LIEU OF 79 SIRENS) | | | | AT 1210 EDT, THE LICENSEE WAS NOTIFIED BY THE WESTCHESTER COUNTY EMERGENCY | | MANAGEMENT DIRECTOR THAT THE RADIO REPEATER FOR THE WESTCHESTER COUNTY | | EMERGENCY SIRENS HAD FAILED AT 0950 EDT. FAILURE OF THE RADIO REPEATER | | RENDERED 77 EMERGENCY SIRENS IN WESTCHESTER COUNTY INOPERABLE. THE RADIO | | REPEATER WAS REPAIRED AT 1109 EDT, AND THE SIRENS WERE SATISFACTORILY | | TESTED AT 1110 EDT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 12:52 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/09/96 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: PAUL METIVIER |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSITIVE RESULTS FROM A RANDOM DRUG SCREENING TEST | | | | A LICENSEE SUPERVISOR TESTED POSITIVE FOR MARIJUANA DURING A RANDOM DRUG | | SCREENING TEST, AND THE INDIVIDUAL'S SITE ACCESS HAS BEEN REVOKED. | | ATTENDANCE AT A COUNSELLING PROGRAM HAS BEEN OFFERED. (REFER TO THE HOO | | LOG FOR ADDITIONAL INFORMATION.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30266 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 12:58 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: CARL SMYERS |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABILITY OF 79 EMERGENCY SIRENS IN WESTCHESTER COUNTY DUE TO A RADIO | | REPEATER FAILURE (SAME AS EVENT #30264 FOR INDIAN POINT UNIT 2 EXCEPT THAT | | 79 SIRENS WERE REPORTED TO BE AFFECTED IN LIEU OF 77) | | | | AT 1200 EDT, THE LICENSEE WAS NOTIFIED BY THE WESTCHESTER COUNTY EMERGENCY | | MANAGEMENT DIRECTOR THAT A RADIO REPEATER FOR THE WESTCHESTER COUNTY | | EMERGENCY SIRENS HAD FAILED AT 0950 EDT. FAILURE OF THE RADIO REPEATER | | RENDERED 79 EMERGENCY SIRENS IN WESTCHESTER COUNTY INOPERABLE. THE RADIO | | REPEATER WAS REPAIRED AT 1109 EDT, AND THE SIRENS WERE SATISFACTORILY | | TESTED AT 1110 EDT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30267 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:43 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 12:55[EDT]| |NRC NOTIFIED BY: STEVE FULLER |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK 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 +------------------------------------------------------------------------------+ | INADEQUATE TESTING OF THE AIR EJECTOR OFF-GAS RADIATION MONITOR'S ISOLATION | | FUNCTION (THIS EVENT REPORT IS SIMILAR TO EVENT #30258.) | | | | THE ISOLATION FUNCTION OF THE AIR EJECTOR OFF-GAS RADIATION MONITOR HAS NOT | | BEEN TESTED ADEQUATELY. THE EQUIPMENT HAS NOT BEEN TESTED TO THE RELAY | | CONTACT LEVEL AS DESCRIBED IN NRC INFORMATION NOTICE 95-15. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30268 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:11 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 16:45[EDT]| |NRC NOTIFIED BY: BRUCE SENSENBACH |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK 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 +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION | | THAT BETWEEN 100 AND 200 FISH WERE KILLED IN THE DISCHARGE CANAL BY THE | | INADVERTENT RELEASE OF AMMONIA. THE LICENSEE WILL NOTIFY THE U.S. COAST | | GUARD AND HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30269 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 20:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 17:44[CDT]| |NRC NOTIFIED BY: MIKE NIEMEYER |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN TO REPLACE A LEAKING 3/4-INCH RELIEF VALVE IN A COMMON | | INJECTION LINE FROM BOTH SAFETY INJECTION (SI) PUMPS TO THE REACTOR COOLANT | | SYSTEM COLD (RCS) LEGS | | | | A CRACKED WELD ON A 3/4-INCH RELIEF VALVE (VALVE 1-8851) ON THE COMMON | | INJECTION LINE TO THE RCS COLD LEGS FROM BOTH SI PUMPS NECESSITATED A PLANT | | SHUTDOWN PER TECHNICAL SPECIFICATION 3.0.3. THREE SMALL PUDDLES OF WATER | | WERE OBSERVED ON THE FLOOR OF THE ROOM WHEN AN SI PUMP WAS RUN YESTERDAY | | FOR A TEST. THE LICENSEE WILL CUT OUT AND REPLACE THE VALVE. UNIT | | SHUTDOWN WAS STARTED AT 1844 CDT AT A RATE OF 20% PER HOUR. THE PLANT WILL | | PROBABLY REACH MODE 4 PRIOR TO COMPLETION OF THE REPAIR. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30270 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 22:03 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 21:15[EDT]| |NRC NOTIFIED BY: JESSE PIKE |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 THAT THE UPPER TECHNICAL SPECIFICATION TEMPERATURE LIMIT FOR THE | | ULTIMATE HEAT SINK IS TOO HIGH BASED ON PRELIMINARY CALCULATIONS | | | | PRELIMINARY CALCULATIONS BY THE LICENSEE SHOW THAT THE PRESENT TECHNICAL | | SPECIFICATION LIMIT OF 88.6øF FOR THE ULTIMATE HEAT SINK (UHS) MAY NOT | | SUPPORT A SAFE SHUTDOWN AFTER A SEISMIC EVENT. INCLUDED IN THE LICENSING | | BASIS IS THE POSTULATED FAILURE OF THE NON-SAFETY NON-SEISMIC SERVICE WATER | | SYSTEM WHICH DISCHARGES TO THE COOLING TOWER BASIN. TO ACCOMMODATE THIS | | FAILURE, THE SERVICE WATER PIPING HAS A RUPTURE DISK TO PERMIT CONTINUED | | FLOW THROUGH THE SAFETY-RELATED HEAT EXCHANGER IF THE NORMAL DISCHARGE PATH | | IS BLOCKED. SUFFICIENT COOLING WATER CANNOT FLOW THROUGH THE HEAT | | EXCHANGER RUPTURE DISK TO SUPPORT THE HEAT REMOVAL REQUIREMENTS AT THE | | TECHNICAL SPECIFICATION UHS LIMIT OF 88.6øF. THE FLOW CALCULATIONS | | INDICATE THAT THE MAXIMUM UHS TEMPERATURE LIMIT SHOULD BE 87.7øF. THE | | SYSTEM IS CURRENTLY OPERABLE. THE UHS TEMPERATURE IS 47øF. PENDING | | FURTHER ANALYSIS THE LICENSEE HAS ADMINISTRATIVELY SET A NEW UHS | | TEMPERATURE LIMIT OF 85øF. | | | | THE LICENSEE HAS INFORMED LOWER ALLOWAYS CREEK TOWNSHIP AND WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LONGVIEW INSPECTION |NOTIFICATION DATE: 04/10/96 | | CITY: REGION: 2 |NOTIFICATION TIME: 23:33 [ET]| | COUNTY: CAMDEN STATE: GA |EVENT DATE: 04/10/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 22:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID VERRELLI RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM HARDAMAN | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A STOLEN | | LONGVIEW INSPECTION SERVICE (OF VIRGINIA) TRUCK WHICH HAD BEEN TRANSPORTING | | A RADIOGRAPHY CAMERA WAS FOUND. | | | | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A TRUCK STOLEN | | FROM LONGVIEW INSPECTION SERVICE OF VIRGINIA AND TRANSPORTING A RADIOGRAPHY | | CAMERA WAS CAPTURED AT A TRAFFIC STOP IN CAMDEN COUNTY, GEORGIA. THE | | CAMERA, A TECH-OPS-660, CONTAINS AN IRIDIUM-192 SOURCE OF UNKNOWN STRENGTH. | | AT THIS TIME, IT IS NOT KNOWN IF THE SOURCE IS IN THE SHIELDED POSITION. | | THE TRUCK IS CURRENTLY PARKED AT THE SIDE OF ROAD UNDER POLICE GUARD. | | | | * * * 0022 APRIL 11, 1996, UPDATE FROM HARDAMAN RECEIVED BY TROCINE * * * | | | | THE CAMDEN COUNTY SHERIFF'S OFFICE WAS ABLE TO PROVIDE MONITORING | | ASSISTANCE AND DETERMINED THAT THE RADIOGRAPHY CAMERA SOURCE WAS IN THE | | SHIELDED POSITION. THERE WERE NO READINGS IN EXCESS OF ONE MILLIREM PER | | HOUR UNTIL THE SURVEYORS GOT UP ONTO THE TRUCK. THE VEHICLE IS CURRENTLY | | BEING TRANSPORTED TO AN IMPOUND LOT ON THE BACK OF A WRECKER. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO (VERRELLI). (REFER TO THE HOO | | LOG FOR CONTACT NAMES AND TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/10/96 - 04/11/96 ** EVENT NUMBERS ** 30134 30135 30215 30258 30261 30262 30263 30264 30265 30266 30267 30268 30269 30270 30271 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: BURCHFIELD |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENTRY INTO A 4-HOUR TECHNICAL SPECIFICATION ACTION STATEMENT DUE TO THE | | 2HP-3 CONTAINMENT ISOLATION VALVE BEING DECLARED INOPERABLE | | | | AS A RESULT OF EVALUATING DATA, AN ENGINEERING ANALYSIS HAS DETERMINED THAT | | VALVE 2HP-3 (CONTAINMENT ISOLATION VALVE FOR THE LETDOWN COOLER OUTLET) MAY | | NOT BE ABLE TO CLOSE AGAINST FULL DIFFERENTIAL PRESSURE UNDER CERTAIN | | ACCIDENT SCENARIOS. ASSUMING A SINGLE FAILURE OF THE SECOND CONTAINMENT | | ISOLATION VALVE FOR THE SAME PENETRATION, IT COULD POTENTIALLY RESULT IN | | THE FAILURE TO ISOLATE A CONTAINMENT PENETRATION FOLLOWING AN ACCIDENT. | | THE IMMEDIATE TECHNICAL SPECIFICATION ACTION STATEMENT ACTION IS TO CLOSE | | THE SUSPECT VALVE AND OPEN ITS BREAKER. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. (REFER TO RELATED EVENT NUMBERS 30135, 30139, AND | | 30140.) | | | | * * * 0759 APRIL 10, 1996, UPDATE FROM CLARKSON RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED UPON FURTHER ENGINEERING | | EVALUATION WHICH DETERMINED THAT VALVE 2HP-3 WAS OPERABLE (BOTH PAST AND | | PRESENT). THIS ANALYSIS LOOKED AT VALVE PERFORMANCE CONTINUALLY THROUGH | | THE VALVE STROKE AND WAS A MORE DETAILED ANALYSIS THAN THE ORIGINAL | | ANALYSIS USED TO DETERMINE THE OPERABILITY OF THE VALVE. THIS ANALYSIS | | DETERMINED THE DIFFERENTIAL PRESSURE THAT THE VALVE COULD CLOSE AGAINST | | DURING EACH MILLISECOND OF THE DESIGN BASIS EVENT. THIS INFORMATION WAS | | THEN REVIEWED AGAINST THE SYSTEM MODEL. THE LICENSEE'S REVIEW YIELDED THAT | | THE VALVE COULD HAVE INDEED STROKED AGAINST THE EXPECTED DIFFERENTIAL | | PRESSURE DURING THE DESIGN BASIS EVENT. THE LICENSEE NOTIFIED THE NRC | | RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (VERRELLI). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: BURCHFIELD |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABILITY OF THE 3HP-3 CONTAINMENT ISOLATION VALVE | | | | AS A RESULT OF EVALUATING DATA, AN ENGINEERING ANALYSIS HAS DETERMINED THAT | | VALVE 3HP-3 (CONTAINMENT ISOLATION VALVE FOR THE LETDOWN COOLER OUTLET) MAY | | NOT BE ABLE TO CLOSE AGAINST FULL DIFFERENTIAL PRESSURE UNDER CERTAIN | | ACCIDENT SCENARIOS. ASSUMING A SINGLE FAILURE OF THE SECOND CONTAINMENT | | ISOLATION VALVE FOR THE SAME PENETRATION, IT COULD POTENTIALLY RESULT IN | | THE FAILURE TO ISOLATE A CONTAINMENT PENETRATION FOLLOWING AN ACCIDENT. | | THE LICENSEE TAGGED THE VALVE OUT OF SERVICE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. (REFER TO SEE RELATED | | EVENT NUMBERS 30134, 30139, AND 30140.) | | | | * * * 0759 APRIL 10, 1996, UPDATE FROM CLARKSON RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED UPON FURTHER ENGINEERING | | EVALUATION WHICH DETERMINED THAT VALVE 3HP-3 WAS OPERABLE (BOTH PAST AND | | PRESENT). THIS ANALYSIS LOOKED AT VALVE PERFORMANCE CONTINUALLY THROUGH | | THE VALVE STROKE AND WAS A MORE DETAILED ANALYSIS THAN THE ORIGINAL | | ANALYSIS USED TO DETERMINE THE OPERABILITY OF THE VALVE. THIS ANALYSIS | | DETERMINED THE DIFFERENTIAL PRESSURE THAT THE VALVE COULD CLOSE AGAINST | | DURING EACH MILLISECOND OF THE DESIGN BASIS EVENT. THIS INFORMATION WAS | | THEN REVIEWED AGAINST THE SYSTEM MODEL. THE LICENSEE'S REVIEW YIELDED THAT | | THE VALVE COULD HAVE INDEED STROKED AGAINST THE EXPECTED DIFFERENTIAL | | PRESSURE DURING THE DESIGN BASIS EVENT. THE LICENSEE NOTIFIED THE NRC | | RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO | | (VERRELLI). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30215 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/01/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:51 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/01/96 | +------------------------------------------------+EVENT TIME: 13:00[EST]| |NRC NOTIFIED BY: DAVID PIETRUSKI |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE 25% TECHNICAL SPECIFICATION ALLOWABLE EXTENSION TIME FOR | | TWO 18-MONTH SURVEILLANCES WAS EXCEEDED DURING THE LAST UNIT RUN CYCLE | | (PRIOR TO DECEMBER 1994) | | | | DURING A REVIEW OF DOCUMENTATION ON COMPLETED SURVEILLANCES, IT WAS | | DISCOVERED THAT THE 25% TECHNICAL SPECIFICATION ALLOWABLE EXTENSION TIME | | FOR TWO 18-MONTH SURVEILLANCES WAS EXCEEDED DURING THE LAST RUN CYCLE | | (BETWEEN REFUELING OUTAGES #14R AND #15R). (THE #15R REFUELING OUTAGE WAS | | COMPLETED IN DECEMBER 1994.) THE TWO PROCEDURES THAT WERE IDENTIFIED AS | | EXCEEDING THE 25% TECHNICAL SPECIFICATION ALLOWABLE EXTENSION TIME WERE | | PROCEDURE #602.4.003, ELECTROMATIC RELIEF VALVE OPERABILITY TEST, AND | | PROCEDURE #665.5.002, SECONDARY CONTAINMENT LEAK RATE TEST. BOTH OF THESE | | 18-MONTH SURVEILLANCES WERE SATISFACTORILY PERFORMED DURING REFUELING | | OUTAGE #15R. THE LICENSEE IS STILL REVIEWING SURVEILLANCE RELATED | | DOCUMENTATION AND MAY FIND ADDITIONAL EXAMPLES OF THIS PROBLEM. ADDITIONAL | | EXAMPLES WILL BE DOCUMENTED IN THE LICENSEE EVENT REPORT FOR THE TWO | | EXAMPLES REFERENCED IN THIS NOTIFICATION. THE LICENSEE PLANS TO NOTIFY THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1523 EDT ON 04/10/96, FROM PIETRUSKI TAKEN BY KARSCH * * * | | | | UPON FURTHER REVIEW, THE LICENSEE DETERMINED THAT THE 25% TIME EXTENSION | | FOR COMPLETION OF THE SURVEILLANCE TESTING WAS NOT EXCEEDED AS STATED IN | | THE ORIGINAL REPORT. ALL TESTING WAS COMPLETED WITHIN THE TECHNICAL | | SPECIFICATION ALLOWABLE TIME LIMIT. THEREFORE, NO EVENT NOTIFICATION WAS | | REQUIRED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30258 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/09/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/09/96 | +------------------------------------------------+EVENT TIME: 17:45[EDT]| |NRC NOTIFIED BY: ERIC DeMONCH |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A MISSED SURVEILLANCE TEST | | (THIS EVENT IS SIMILAR TO EVENT #30267.) | | | | NRC GENERIC LETTER 96-01 AND NRC INFORMATION NOTICE 95-15 REQUIRE LOGIC | | SYSTEM TESTING TO THE RELAY CONTACT LEVEL. THE LICENSEE'S REVIEW OF THESE | | REQUIREMENTS REVEALED THAT THE LICENSEE'S TESTING FOR BUS UNDER VOLTAGE AND | | DEGRADED VOLTAGE DOES NOT MEET THIS REQUIREMENT. THIS CONSTITUTES A MISSED | | SURVEILLANCE UNDER TECHNICAL SPECIFICATIONS 3.0.A AND 3.1, TABLE 3.1.1.N | | (PROTECTIVE INSTRUMENTATION), TESTING EVERY 24 MONTHS. A SHUTDOWN OF 20 | | MWE WAS STARTED AND WILL CONTINUE AT A RATE OF 15 MWE PER HOUR UNTIL EITHER | | THE TESTING IS SUCCESSFULLY COMPLETED OR THE UNIT REACHES COLD SHUTDOWN. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 0109 APRIL 10, 1996, UPDATE FROM RUMBIN RECEIVED BY TROCINE * * * | | | | THE LICENSEE SUCCESSFULLY COMPLETED THE REQUIRED TESTING AND CEASED THE | | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN AT 0005 ON APRIL 10, 1996. | | REACTOR POWER WAS AT 85% AT THE TIME OF THIS NOTIFICATION, AND THE LICENSEE | | CURRENTLY PLANS TO RESTORE THE UNIT TO 100% REACTOR POWER. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30261 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 02:46 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 01:48[EDT]| |NRC NOTIFIED BY: DON BOSNIC |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE LOSS OF REACTOR | | COOLANT SYSTEM (RCS) LEAKAGE DETECTION MONITORING WHEN AN ELECTRICAL | | PROTECTION ASSEMBLY (EPA) BREAKER TRIPPED | | | | AT 0011, EPA BREAKER 2VBS*ACB2A TRIPPED RESULTING IN A HALF SCRAM, HALF | | MAIN STEAM ISOLATION VALVE (MSIV) ISOLATION, AND DIVISION 1 NUCLEAR STEAM | | SUPPLY SHUTOFF SYSTEM (NSSSS) ISOLATION. THE NSSSS ISOLATION CAUSED A LOSS | | OF THE RCS LEAKAGE DETECTION MONITORING SYSTEM DUE TO THE LOSS OF LOGIC | | POWER. IT APPEARS THAT ENGINEERED SAFETY FEATURES (ESF) ACTUATION OCCURRED | | AS EXPECTED. THE UNIT RECEIVED A SECONDARY CONTAINMENT ISOLATION. THE | | STANDBY GAS TREATMENT TRAINS INITIATED AS EXPECTED, AND THE CONTROL ROOM | | SPECIAL FILTER TRAIN ALSO INITIATED ON DIVISION 1 AS EXPECTED. THE | | LICENSEE PLANS TO MAKE AN ADDITIONAL FOUR-HOUR NOTIFICATION WITH REGARD TO | | THE ESF ACTUATIONS. | | | | AT 0148, THE LICENSEE DETERMINED THAT ENTRY INTO TECHNICAL SPECIFICATION | | 3.0.3 WAS REQUIRED DUE TO THE LOSS OF RCS LEAKAGE DETECTION, AND A | | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN WAS COMMENCED AT THAT TIME. IF | | CONTAINMENT MONITORING WAS NOT RESTORED, TECHNICAL SPECIFICATION 3.0.3 | | REQUIRED THAT THE LICENSEE INITIATE A UNIT SHUTDOWN WITHIN 1 HOUR, PLACE | | THE UNIT IN STARTUP WITHIN THE FOLLOWING 6 HOURS, AND PLACE THE UNIT IN HOT | | SHUTDOWN WITHIN THE FOLLOWING 6 HOURS. | | | | THE LICENSEE STRIPPED THE DOWNSTREAM LOADS, RECLOSED THE EPA BREAKER, AND | | RE-ENERGIZED TWO OF THE FIVE DOWNSTREAM PANELS. THIS ALLOWED THE LICENSEE | | TO RECOVER SOME PORTION OF THE ISOLATIONS THAT OCCURRED (ONE OF WHICH WAS | | LEAKAGE DETECTION). AS A RESULT, THE LICENSEE RESTORED CONTAINMENT | | MONITORING AND EXITED TECHNICAL SPECIFICATION 3.0.3 AT 0232. THE UNIT | | SHUTDOWN WAS CEASED AT THAT TIME WITH THE UNIT AT APPROXIMATELY 95% REACTOR | | POWER. | | | | THE LICENSEE PLANS TO MAINTAIN THE UNIT AT THIS POWER LEVEL UNTIL THE LOGIC | | SYSTEM IS RECOVERED BECAUSE PART OF THE ISOLATION ISOLATES THE HYDRAULICS | | TO THE RECIRCULATION FLOW CONTROL VALVE WHICH CONTROLS THE LICENSEE'S | | ABILITY TO THROTTLE BACK ON POWER WITH RECIRCULATION. IN ADDITION, THE | | LICENSEE IS CURRENTLY RECOVERING THE NON-MSIV ISOLATION LOGICS AND PLANS TO | | TROUBLESHOOT THE CAUSE FOR THE EPA BREAKER TRIP. THE LICENSEE BELIEVES | | THAT THE PROBLEM MAY BE IN THE INBOARD OR OUTBOARD MSIV LOGIC CIRCUITS OR | | IN THE REACTOR PROTECTION SYSTEM LOGIC CIRCUITS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 0357 APRIL 10, 1996, UPDATE FROM BOSNIC RECEIVED BY TROCINE * * * | | | | THE EPA BREAKER TRIP CAUSED THE FOLLOWING ESF ACTUATIONS: SECONDARY | | CONTAINMENT ISOLATION; STANDBY GAS TREATMENT SYSTEM INITIATION; DIVISION 1 | | CONTROL ROOM SPECIAL FILTER TRAIN AUTOMATIC START; NSSSS GROUP 2, 3, 4, 5, | | 6, 8, AND 9 ISOLATIONS ON DIVISION 1. THESE ACTUATIONS WERE ALL EXPECTED | | AND RESPONDED CORRECTLY. THE LICENSEE SUBSEQUENTLY OPENED THE DOWNSTREAM | | LOADS FROM THE EPA BREAKER, AND THE EPA BREAKER WAS RECLOSED AT 0128. THUS | | FAR, NSSSS ISOLATION LOGIC HAS BEEN RESTORED TO GROUPS 2, 3, 4, 5, 6, 8, | | AND 9; AND THE LICENSEE IS CURRENTLY IN THE PROCESS OF RESTORING THE | | SYSTEMS THAT WERE AFFECTED BY THOSE ISOLATIONS TO THEIR NORMAL LINEUPS. THE | | BREAKERS FOR THREE PANELS DOWNSTREAM OF THE EPA BREAKER ARE STILL OPEN. | | THESE INCLUDE THE GROUP 1 ISOLATION FOR DIVISION 1 AND FOR REACTOR | | PROTECTION SYSTEM LOGIC INITIATIONS. THE HALF SCRAM AND HALF MSIV | | ISOLATION TRIPS ARE CURRENTLY IN AS REQUIRED BY TECHNICAL SPECIFICATIONS. | | THE UNIT IS ALSO IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION DUE TO THE LOSS OF THE ON-LINE CONDUCTIVITY MONITORING. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30262 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 03:00[CDT]| |NRC NOTIFIED BY: PHILLIP A. SHORT |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN HANNON, NRR EO | |NLCO TECH SPEC LCO A/S |RALPH HERSKO FEMA | | |FRANK CONGEL IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DECLARATION OF UNUSUAL EVENT DUE THE REACTOR COOLANT BOTTOM HEAD DRAIN | | TEMPERATURE INCREASING GREATER THAN 100øF PER HOUR | | | | BETWEEN 2210 CDT AND 2310 CDT ON APRIL 9, 1996, THE REACTOR COOLANT BOTTOM | | HEAD DRAIN TEMPERATURE INCREASED GREATER THAN 100øF PER HOUR. THIS | | REQUIRED ENTRY INTO TECHNICAL SPECIFICATION 3.4.11 AND REQUIRES THAT A | | NOTIFICATION OF UNUSUAL EVENT BE DECLARED. THE CONDITION WAS CORRECTED | | ALMOST IMMEDIATELY (WITHIN THE ALLOTTED 30-MINUTE TIME FRAME OF THE | | TECHNICAL SPECIFICATION), AND AN ENGINEERING EVALUATION OF THE REACTOR | | COOLANT SYSTEM IS REQUIRED PRIOR TO RESUMING OPERATIONS. APPARENTLY, THERE | | WAS ONE READING THAT WAS 20øF TO 25øF HIGHER THAN THE THE REST OF THE | | READINGS (WHICH WERE BEING TAKEN AT 5-MINUTE INTERVALS). THIS INDICATION | | IS SUSPECT AND WAS ORIGINALLY DISCOUNTED. THE LICENSEE CHECKED THE | | RECORDER BUT DID NOT FIND A REASON TO DISCOUNT THE READING. THE UNUSUAL | | EVENT WAS DECLARED AT 0300 CDT ON APRIL 10, 1996. | | | | THE LICENSEE PLANS TO STAY IN THE UNUSUAL EVENT UNTIL THERE IS GOOD CONTROL | | AND THERE IS ASSURANCE THAT THIS WILL NOT OCCUR AGAIN. READINGS ARE | | CURRENTLY BEING TAKEN AT 30-MINUTE INTERVALS. THE LICENSEE IS ALSO | | CURRENTLY WORKING TOWARD GETTING THE REACTOR RECIRCULATION SYSTEM RESTARTED | | FOLLOWING AN EARLIER EVENT (#30253). THE CONDENSER IS NOT AVAILABLE, AND | | THE LICENSEE IS USING SAFETY RELIEF VALVES TO REMOVE DECAY HEAT. RESIDUAL | | HEAT REMOVAL IS IN SUPPRESSION POOL COOLING, AND THE CONTROL ROD DRIVE | | SYSTEM IS IN ITS NORMAL MODE. REACTOR CORE ISOLATION COOLING IS | | OCCASIONALLY BEING USED AS A SUPPLEMENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL GOVERNMENTS. | | | | * * * UPDATE AT 2146 EDT ON 04/10/96, FROM HALVERSON TAKEN BY KARSCH * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 1945 CDT. ENGINEERING | | EVALUATION DETERMINED THAT THIS EVENT IS WITHIN THE ANALYZED DESIGN BASIS | | FOR THE PLANT. RECIRCULATION PUMP 'B' HAS BEEN PLACED IN SERVICE TO | | PREVENT THERMAL STRATIFICATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL | | GOVERNMENT AGENCIES. THE NRC OPERATIONS CENTER NOTIFIED THE R3DO | | (BURGESS), NRR EO (HANNON), AND FEMA (STORER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:28 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 09:45[EDT]| |NRC NOTIFIED BY: DAVID PIETRUSKI |LAST UPDATE DATE: 04/10/96 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL LIFTING LEVER ON CONTAINMENT SPRAY HEAT EXCHANGER RELIEF VALVE FOUND | | IN THE OPEN POSITION | | | | DURING THE PERFORMANCE OF CONTAINMENT SPRAY HEAT EXCHANGER MAINTENANCE, ONE | | OF THE RELIEF VALVES ON THE 1-2 CONTAINMENT SPRAY HEAT EXCHANGER WAS | | DISCOVERED TO BE OPEN AT 2102 ON APRIL 9, 1996. THE MANUAL LIFTING LEVER | | ON THE RELIEF VALVE WAS IN THE OPEN POSITION. THIS SYSTEM WAS TIED INTO | | THE PRIMARY CONTAINMENT. | | | | APPARENTLY, THE MANUAL LEVER WAS FOUND TO BE IN THE OPEN POSITION WHEN A | | PUMP WAS STARTED TO TEST THE SYSTEM FOR HEAT EXCHANGER LEAKAGE. SOME WATER | | ESCAPED, BUT THERE WERE NO PERSONNEL CONTAMINATIONS. THE LICENSEE STOPPED | | THE PUMP, CLOSED THE RELIEF VALVE, AND PERFORMED A TEST RUN OF THE SYSTEM | | IN ORDER TO VERIFY THAT THE VALVE WAS ACTUALLY CLOSED. | | | | THE DETERMINATION THAT THIS ISSUE INVOLVED OPERATION OUTSIDE THE DESIGN | | BASIS WAS MADE AT 0945 ON APRIL 10, 1996. TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION WERE NOT ENTERED AS A RESULT OF THIS EVENT BECAUSE | | THE VALVE HAD BEEN CLOSED UPON DISCOVERY. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30264 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: JOHN LIJOI |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INOPERABILITY OF 77 EMERGENCY SIRENS IN WESTCHESTER COUNTY DUE TO A RADIO | | REPEATER FAILURE (SAME AS EVENT #30266 FOR INDIAN POINT UNIT 3 EXCEPT THAT | | 77 SIRENS WERE REPORTED TO BE AFFECTED IN LIEU OF 79 SIRENS) | | | | AT 1210 EDT, THE LICENSEE WAS NOTIFIED BY THE WESTCHESTER COUNTY EMERGENCY | | MANAGEMENT DIRECTOR THAT THE RADIO REPEATER FOR THE WESTCHESTER COUNTY | | EMERGENCY SIRENS HAD FAILED AT 0950 EDT. FAILURE OF THE RADIO REPEATER | | RENDERED 77 EMERGENCY SIRENS IN WESTCHESTER COUNTY INOPERABLE. THE RADIO | | REPEATER WAS REPAIRED AT 1109 EDT, AND THE SIRENS WERE SATISFACTORILY | | TESTED AT 1110 EDT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 12:52 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/09/96 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: PAUL METIVIER |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSITIVE RESULTS FROM A RANDOM DRUG SCREENING TEST | | | | A LICENSEE SUPERVISOR TESTED POSITIVE FOR MARIJUANA DURING A RANDOM DRUG | | SCREENING TEST, AND THE INDIVIDUAL'S SITE ACCESS HAS BEEN REVOKED. | | ATTENDANCE AT A COUNSELLING PROGRAM HAS BEEN OFFERED. (REFER TO THE HOO | | LOG FOR ADDITIONAL INFORMATION.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30266 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 12:58 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: CARL SMYERS |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABILITY OF 79 EMERGENCY SIRENS IN WESTCHESTER COUNTY DUE TO A RADIO | | REPEATER FAILURE (SAME AS EVENT #30264 FOR INDIAN POINT UNIT 2 EXCEPT THAT | | 79 SIRENS WERE REPORTED TO BE AFFECTED IN LIEU OF 77) | | | | AT 1200 EDT, THE LICENSEE WAS NOTIFIED BY THE WESTCHESTER COUNTY EMERGENCY | | MANAGEMENT DIRECTOR THAT A RADIO REPEATER FOR THE WESTCHESTER COUNTY | | EMERGENCY SIRENS HAD FAILED AT 0950 EDT. FAILURE OF THE RADIO REPEATER | | RENDERED 79 EMERGENCY SIRENS IN WESTCHESTER COUNTY INOPERABLE. THE RADIO | | REPEATER WAS REPAIRED AT 1109 EDT, AND THE SIRENS WERE SATISFACTORILY | | TESTED AT 1110 EDT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30267 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:43 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 12:55[EDT]| |NRC NOTIFIED BY: STEVE FULLER |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK 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 +------------------------------------------------------------------------------+ | INADEQUATE TESTING OF THE AIR EJECTOR OFF-GAS RADIATION MONITOR'S ISOLATION | | FUNCTION (THIS EVENT REPORT IS SIMILAR TO EVENT #30258.) | | | | THE ISOLATION FUNCTION OF THE AIR EJECTOR OFF-GAS RADIATION MONITOR HAS NOT | | BEEN TESTED ADEQUATELY. THE EQUIPMENT HAS NOT BEEN TESTED TO THE RELAY | | CONTACT LEVEL AS DESCRIBED IN NRC INFORMATION NOTICE 95-15. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30268 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:11 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 16:45[EDT]| |NRC NOTIFIED BY: BRUCE SENSENBACH |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK 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 +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION | | THAT BETWEEN 100 AND 200 FISH WERE KILLED IN THE DISCHARGE CANAL BY THE | | INADVERTENT RELEASE OF AMMONIA. THE LICENSEE WILL NOTIFY THE U.S. COAST | | GUARD AND HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30269 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 20:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 17:44[CDT]| |NRC NOTIFIED BY: MIKE NIEMEYER |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN TO REPLACE A LEAKING 3/4-INCH RELIEF VALVE IN A COMMON | | INJECTION LINE FROM BOTH SAFETY INJECTION (SI) PUMPS TO THE REACTOR COOLANT | | SYSTEM COLD (RCS) LEGS | | | | A CRACKED WELD ON A 3/4-INCH RELIEF VALVE (VALVE 1-8851) ON THE COMMON | | INJECTION LINE TO THE RCS COLD LEGS FROM BOTH SI PUMPS NECESSITATED A PLANT | | SHUTDOWN PER TECHNICAL SPECIFICATION 3.0.3. THREE SMALL PUDDLES OF WATER | | WERE OBSERVED ON THE FLOOR OF THE ROOM WHEN AN SI PUMP WAS RUN YESTERDAY | | FOR A TEST. THE LICENSEE WILL CUT OUT AND REPLACE THE VALVE. UNIT | | SHUTDOWN WAS STARTED AT 1844 CDT AT A RATE OF 20% PER HOUR. THE PLANT WILL | | PROBABLY REACH MODE 4 PRIOR TO COMPLETION OF THE REPAIR. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30270 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/10/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 22:03 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 21:15[EDT]| |NRC NOTIFIED BY: JESSE PIKE |LAST UPDATE DATE: 04/10/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 THAT THE UPPER TECHNICAL SPECIFICATION TEMPERATURE LIMIT FOR THE | | ULTIMATE HEAT SINK IS TOO HIGH BASED ON PRELIMINARY CALCULATIONS | | | | PRELIMINARY CALCULATIONS BY THE LICENSEE SHOW THAT THE PRESENT TECHNICAL | | SPECIFICATION LIMIT OF 88.6øF FOR THE ULTIMATE HEAT SINK (UHS) MAY NOT | | SUPPORT A SAFE SHUTDOWN AFTER A SEISMIC EVENT. INCLUDED IN THE LICENSING | | BASIS IS THE POSTULATED FAILURE OF THE NON-SAFETY NON-SEISMIC SERVICE WATER | | SYSTEM WHICH DISCHARGES TO THE COOLING TOWER BASIN. TO ACCOMMODATE THIS | | FAILURE, THE SERVICE WATER PIPING HAS A RUPTURE DISK TO PERMIT CONTINUED | | FLOW THROUGH THE SAFETY-RELATED HEAT EXCHANGER IF THE NORMAL DISCHARGE PATH | | IS BLOCKED. SUFFICIENT COOLING WATER CANNOT FLOW THROUGH THE HEAT | | EXCHANGER RUPTURE DISK TO SUPPORT THE HEAT REMOVAL REQUIREMENTS AT THE | | TECHNICAL SPECIFICATION UHS LIMIT OF 88.6øF. THE FLOW CALCULATIONS | | INDICATE THAT THE MAXIMUM UHS TEMPERATURE LIMIT SHOULD BE 87.7øF. THE | | SYSTEM IS CURRENTLY OPERABLE. THE UHS TEMPERATURE IS 47øF. PENDING | | FURTHER ANALYSIS THE LICENSEE HAS ADMINISTRATIVELY SET A NEW UHS | | TEMPERATURE LIMIT OF 85øF. | | | | THE LICENSEE HAS INFORMED LOWER ALLOWAYS CREEK TOWNSHIP AND WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LONGVIEW INSPECTION |NOTIFICATION DATE: 04/10/96 | | CITY: REGION: 2 |NOTIFICATION TIME: 23:33 [ET]| | COUNTY: CAMDEN STATE: GA |EVENT DATE: 04/10/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 22:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID VERRELLI RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM HARDAMAN | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A STOLEN | | LONGVIEW INSPECTION SERVICE (OF VIRGINIA) TRUCK WHICH HAD BEEN TRANSPORTING | | A RADIOGRAPHY CAMERA WAS FOUND. | | | | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A TRUCK STOLEN | | FROM LONGVIEW INSPECTION SERVICE OF VIRGINIA AND TRANSPORTING A RADIOGRAPHY | | CAMERA WAS CAPTURED AT A TRAFFIC STOP IN CAMDEN COUNTY, GEORGIA. THE | | CAMERA, A TECH-OPS-660, CONTAINS AN IRIDIUM-192 SOURCE OF UNKNOWN STRENGTH. | | AT THIS TIME, IT IS NOT KNOWN IF THE SOURCE IS IN THE SHIELDED POSITION. | | THE TRUCK IS CURRENTLY PARKED AT THE SIDE OF ROAD UNDER POLICE GUARD. | | | | * * * 0022 APRIL 11, 1996, UPDATE FROM HARDAMAN RECEIVED BY TROCINE * * * | | | | THE CAMDEN COUNTY SHERIFF'S OFFICE WAS ABLE TO PROVIDE MONITORING | | ASSISTANCE AND DETERMINED THAT THE RADIOGRAPHY CAMERA SOURCE WAS IN THE | | SHIELDED POSITION. THERE WERE NO READINGS IN EXCESS OF ONE MILLIREM PER | | HOUR UNTIL THE SURVEYORS GOT UP ONTO THE TRUCK. THE VEHICLE IS CURRENTLY | | BEING TRANSPORTED TO AN IMPOUND LOT ON THE BACK OF A WRECKER. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO (VERRELLI). (REFER TO THE HOO | | LOG FOR CONTACT NAMES AND TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+