U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/06/96 - 08/07/96 ** EVENT NUMBERS ** 30834 30835 30836 30837 30838 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30834 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 08/06/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 05:00 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 08/06/96 | +------------------------------------------------+EVENT TIME: 01:45[CDT]| |NRC NOTIFIED BY: DAN ORR |LAST UPDATE DATE: 08/06/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 +------------------------------------------------------------------------------+ | - TECH SPEC SURVEILLANCE TEST FAILED DUE TO PUMP PACKING OVERHEATING - | | | | DURING THE PERFORMANCE OF A TECH SPEC SURVEILLANCE TEST OF THE CONTAINMENT | | COOLING SERVICE WATER (CCSW) LOOP FLOW VERIFICATION, THE #3A CCSW LOOP | | DELIVERED 6,900 GPM INSTEAD OF THE 7,000 GPM REQUIRED BY THE UPDATED FINAL | | SAFETY ANALYSIS REPORT, SECTION 6.2.1.3.2. DURING THE TEST, THE OUTBOARD | | PUMP PACKING OF THE #3A CCSW PUMP OVERHEATED. | | | | THE LICENSEE IS DETERMINING THE CAUSE AND WILL TAKE CORRECTIVE ACTIONS | | PRIOR TO RESTARTING UNIT 3. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30835 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NEW HAVEN HOSPITAL |NOTIFICATION DATE: 08/06/96 | | CITY: NEW HAVEN REGION: 1 |NOTIFICATION TIME: 15:28 [ET]| | COUNTY: STATE: CT |EVENT DATE: 07/26/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/06/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES NOGGLE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MIKE BOHAN | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -FIVE I-125 SEEDS LOST- | | | | THE LICENSEE DISCOVERED THAT FIVE I-125 SEEDS WERE MISSING WHILE IMPLANTING | | THE SEEDS INTO A PATIENT. THE ACTIVITY OF EACH SEED IS APPROXIMATELY 1/2 | | mCi. THE SEEDS HAD BEEN USED PREVIOUSLY AND HAD BEEN IN STORAGE FOR | | SEVERAL MONTHS. THE LICENSEE DOES NOT BELIEVE THE SEEDS COULD HAVE BEEN | | LEFT IN THE LAST PATIENT BECAUSE OF THE SURVEY CONDUCTED AT THAT TIME | | INDICATED THAT ALL OF THE SEEDS HAD BEEN REMOVED. THE NORMAL INVENTORY | | PROCESSES WOULD ALSO HAVE INDICATED A PROBLEM. | | | | THE LICENSEE CONDUCTED A SEARCH BUT COULD NOT LOCATE THE SEEDS. A CONTACT | | NUMBER IS AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30836 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 08/06/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:00 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 08/06/96 | +------------------------------------------------+EVENT TIME: 13:19[EDT]| |NRC NOTIFIED BY: MIKE RUBY |LAST UPDATE DATE: 08/06/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - AUTOMATIC START OF THE "A" AFW PUMP | | | | PLANT CONDITIONS WERE AS FOLLOWS: MODE 4, RCS TEMPERATURE 340 F, PRESSURE | | 350 PSIG WITH A BUBBLE IN THE PRESSURIZER. THE MAIN TURBINE WAS LATCHED AS | | PART OF THE PREPARATIONS FOR A CALIBRATION OF THE #2 TURBINE CONTROL VALVE. | | SINCE BOTH MAIN FEEDWATER PUMP BREAKERS WERE OPEN, THE "A" AFW PUMP | | AUTOMATICALLY STARTED. | | | | AFTER VERIFYING THAT ALL CONDITIONS WERE NORMAL FOR THE AUTOMATIC START, | | THE PUMP WAS SECURED. THIS RESULTED IN A SLIGHT COOLDOWN OF APPROXIMATELY | | 3øF. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30837 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NAK ENGINEERING, INC. |NOTIFICATION DATE: 08/06/96 | | CITY: SANTA ROSA REGION: 4 |NOTIFICATION TIME: 16:53 [ET]| | COUNTY: STATE: CA |EVENT DATE: 06/20/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[PDT]| | DOCKET: |LAST UPDATE DATE: 08/06/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE FEMA | |NRC NOTIFIED BY: NORMAN NELSON | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL DEFECT AFFECTING NORDBERG DIESEL GENERATORS | | | | NAK ENGINEERING, INC. OF SANTA ROSA, CALIFORNIA, REPORTED A POTENTIAL | | DEFECT IN A COMPONENT OF THE NORDBERG MODEL FS1316HSC STANDBY DIESEL | | GENERATOR. THERE EXISTS A POTENTIAL PROBLEM WITH THE FUEL INJECTION LINE | | ASSEMBLY WHICH CONNECTS THE FUEL PUMP TO THE INJECTOR. THESE FUEL LINE | | ASSEMBLIES HAVE BEEN SUPPLIED TO THE MCGUIRE AND BRUNSWICK PLANTS. | | | | NAK ENGINEERING, INC. WILL PASS THIS INFORMATION TO THE AFFECTED PLANTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30838 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 08/07/96 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 01:37 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 08/06/96 | +------------------------------------------------+EVENT TIME: 20:41[CDT]| |NRC NOTIFIED BY: TIM GOLDEN |LAST UPDATE DATE: 08/07/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF POWER TO THE SENSORS FOR DIVISION 1 ECCS RENDER SEVERAL SAFETY | | FUNCTIONS INOPERABLE. THE MOST RESTRICTIVE TECH SPEC LCO IS 6 HOURS DUE TO | | HPCI INOPERABILITY. | | | | THE DIVISION 1 ECCS ANALOG TRIP UNIT INVERTER LOST POWER DUE TO A BLOWN | | FUSE. THE ECCS DIVISION 1 INVERTER SUPPLIES POWER TO 2 OF 4 CHANNELS OF | | DRYWELL PRESSURE AND REACTOR WATER LEVEL SENSORS. THESE SENSORS FEED BOTH | | DIVISIONS OF INITIATION LOGIC FOR ALL ECCS SYSTEMS (RHR, CORE SPRAY, HPCI, | | ADS, AND DIESEL GENERATORS). OTHER SENSORS FOR REACTOR PRESSURE AND | | CONTAINMENT PARAMETERS ARE ALSO SUPPLIED BY THIS INVERTER AS IS THE RCIC | | FLOW CONTROLLER. THE REMAINING INVERTER IS SUFFICIENT TO INITIATE THE | | LOGIC OF ALL ECCS DIVISIONS. ALL OF THE ABOVE SYSTEMS WOULD HAVE FULFILLED | | THEIR DESIGN FUNCTIONS WITH THE EXCEPTION OF RCIC AND LOOP 1 CORE SPRAY DUE | | TO LOSS OF THE LOW PRESSURE PERMISSIVE FOR THE INJECTION VALVE. THE | | ATWS/RPT LOGIC WAS ALSO MADE INOPERABLE RESULTING IN A 72-HOUR LCO PER TECH | | SPEC TABLE 3.2.L. PER TECH SPEC 3.5.G ADS WAS DECLARED INOPERABLE | | RESULTING IN A 12-HOUR LCO. ALL AFFECTED ECCS AND RCIC WERE DECLARED | | INOPERABLE DUE TO THE LOSS OF LOGIC IN ACCORDANCE WITH TECH SPEC TABLE | | 3.2.B. THE LOSS OF HPCI TRIGGERS A 6-HOUR LCO AND IS REPORTABLE DUE TO THE | | LOSS OF A SINGLE TRAIN SAFETY SYSTEM. THE LOSS OF POWER TO THE INVERTER | | DOES NOT CAUSE THE PARTIAL ACTIVATION OF THE TRIP LOGIC. THE LICENSEE IS | | TROUBLESHOOTING THE ROOT CAUSE OF THE BLOWN FUSE AND IS WORKING TO RESTORE | | POWER TO THE INVERTER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+