U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/27/96 - 06/28/96 ** EVENT NUMBERS ** 30684 30685 30686 30687 30688 30689 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30684 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 06/27/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 01:01 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 06/26/96 | +------------------------------------------------+EVENT TIME: 20:56[CDT]| |NRC NOTIFIED BY: JOHN WASHKO |LAST UPDATE DATE: 06/27/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DURING A TEST, MSIVs CLOSED UNEXPECTEDLY CAUSING THE REACTOR TO SCRAM - | | | | DURING THE PERFORMANCE OF A SURVEILLANCE CALIBRATION OF THE MAIN STEAM | | HIGH FLOW ISOLATION INSTRUMENTATION, CHANNEL 'A-2', AN UNEXPECTED TRIP OF | | CHANNEL 'B-2' OCCURRED FOR UNKNOWN REASONS WHICH COMPLETED THE ISOLATION | | LOGIC TO CAUSE THE INBOARD AND OUTBOARD MAIN STEAM ISOLATION VALVES (MSIVs) | | TO CLOSE. THIS GROUP 1 MAIN STEAM LINE ISOLATION CAUSED THE REACTOR TO | | AUTOMATICALLY SCRAM FROM 100% POWER. ALL CONTROL RODS INSERTED COMPLETELY | | INTO THE CORE. | | | | FOUR SAFETY/RELIEF VALVES (SRVs) OPENED, AS DESIGNED, TO DUMP STEAM TO THE | | SUPPRESSION POOL. THE SRVs ARE CYCLING OPEN TO MAINTAIN REACTOR COOLANT | | SYSTEM PRESSURE IN THE NORMAL RANGE. | | | | CONTROL ROOM OPERATORS MANUALLY STARTED THE REACTOR CORE ISOLATION COOLING | | (RCIC) SYSTEM TO MAINTAIN REACTOR VESSEL WATER LEVEL IN THE NORMAL RANGE. | | | | CONTROL ROOM OPERATORS ALSO MANUALLY STARTED BOTH LOOPS OF THE SUPPRESSION | | POOL COOLING SYSTEM TO REMOVE ADDED HEAT FROM THE SUPPRESSION POOL. | | | | UNIT 1 IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT AND HAS INFORMED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30685 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/27/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/27/96 | +------------------------------------------------+EVENT TIME: 14:45[EDT]| |NRC NOTIFIED BY: MCDANIEL |LAST UPDATE DATE: 06/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT FIVE VALVES WOULD NOT CLOSE UNDER DESIGN BASIS | | CONDITIONS. | | | | THE VALVES IN QUESTION ARE THE "3MSS*MOV74A, B, & D" (ATMOSPHERIC RELIEF | | BYPASS VALVES FOR MAIN STEAM) AND "RCS8000A & B" (PORV BLOCK VALVES). THE | | PROBLEM ASSOCIATED WITH THE 3 ATMOSPHERIC RELIEF VALVES IS THAT THE SUMMARY | | TABLE OF MOV DESIGN BASIS DIFFERENTIAL PRESSURE CALCULATION DID NOT INCLUDE | | THE THROTTLE/CLOSE DIRECTION SAFETY FUNCTION STROKE WHICH WAS DESCRIBED IN | | THE BODY OF THE CALCULATION. THIS ERROR WAS CARRIED OVER TO THE THRUST | | CALCULATION, WHICH SPECIFIED TEST ACCEPTANCE CRITERIA WHICH WAS TOO LOW TO | | ATTAIN THE REQUIRED DESIGN MARGIN. THIS ERROR WAS DISCOVERED DURING A | | REVISION OF THE THRUST CALCULATION. THE PROBLEM ASSOCIATED WITH THE TWO | | PORV BLOCK VALVES IS DUE TO DESIGN. THE GUIDE RAIL DESIGN IS TOO SHORT TO | | PROPERLY SUPPORT THE VALVE DISC DURING CLOSURE. | | | | CORRECTIVE ACTION FOR THE ATMOSPHERIC RELIEF VALVES IS TO REVISE THE | | CALCULATION. THE CORRECTIVE ACTION RECOMMENDED FOR THE PORV BLOCK VALVES IS | | PERFORMING INTERNAL MODIFICATIONS TO THE VALVE GUIDE CLEARANCES, IN | | CONJUNCTION WITH OFF-SITE TESTING FOR VALIDATION. THE RI ALONG WITH THE | | STATE AND LOCAL AGENCIES WERE INFORMED. THERE MAY BE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30686 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/27/96 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 15:03 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/27/96 | +------------------------------------------------+EVENT TIME: 14:45[EDT]| |NRC NOTIFIED BY: MIKE DeBAY |LAST UPDATE DATE: 06/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT OPERATION WAS IN AN UNANALYZED CONFIGURATION | | | | THE PLANT CONDITION THAT WAS THE CAUSE FOR THIS REPORT WAS THE ALIGNMENT OF | | THE STARTUP FEEDWATER PUMP TO THE STEAM GENERATORS VIA THE EMERGENCY | | FEEDWATER FLOW CONTROL VALVES IN MODE 1 AT LESS THAN 10% POWER. IT HAS | | BEEN DETERMINED THAT THE CONSEQUENCES OF A TOTAL LOSS OF ALL AC POWER WERE | | NOT COMPLETELY ANALYZED FOR OPERATING IN THE CONFIGURATION AND MAY HAVE | | SIGNIFICANTLY COMPROMISED SAFETY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30687 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ENGINEERING LABORATORIES |NOTIFICATION DATE: 06/27/96 | | CITY: RAHWAY REGION: 1 |NOTIFICATION TIME: 16:41 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 06/27/96 | |LICENSE#: 29-30107-01 AGREEMENT: N |EVENT TIME: 11:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/27/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CURTIS COWGILL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: O'MALLEY | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |NDAM DAMAGE MEASURE GAUGE | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | U.S. ENGINEERING LABORATORIES REPORTED THAT A CAMPBELL PACIFIC MODEL "MC-2" | | MOISTURE DENSITY GAUGE WAS DAMAGED. | | | | THIS EVENT OCCURRED AT A PARKING LOT CONSTRUCTION SITE IN JERSEY CITY, NJ, | | WHEN A TRUCK DAMAGED THE GAUGE. THE SITE WAS ROPED OFF AND A SURVEY WAS | | MADE FOR RADIATION WHICH MEASURED <.5 MILLIREM/HR. THE DEVICE CONTAINED | | 40 MILLICURIES OF CESIUM AND 8 MILLICURIES OF AMERICIUM/BERYLLIUM. AFTER | | THEY CLEANED UP THE GAUGE, THEY SURVEYED THE AREA AND THERE WAS NO | | RADIATION PRESENT. THE DEVICE WAS THEN REMOVED FROM THE SITE AND RETURNED | | TO THEIR LABORATORIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30688 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/27/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 21:27 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/27/96 | +------------------------------------------------+EVENT TIME: 18:05[EDT]| |NRC NOTIFIED BY: PRIESTLEY |LAST UPDATE DATE: 06/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION WHERE THEIR 4KV BREAKERS HAVE A | | POTENTIAL COMMON MODE FAILURE MECHANISM. | | | | ON MAY 30, 1996, A ROOT CAUSE INVESTIGATION CONCLUDED THAT THE GENERAL | | ELECTRIC MAGNE-BLAST 4KV BREAKERS HAVE A POTENTIAL COMMON MODE FAILURE | | MECHANISM WHICH COULD JEOPARDIZE THEIR FAST CLOSURE CAPABILITY. THE | | BREAKERS ARE SAFETY RELATED AND THE FAILURE OF THEM TO CLOSE WOULD RESULT | | IN THE RESPECTIVE EQUIPMENT NOT OPERATING AS DESIGNED. THE INFORMATION ON | | THIS ISSUE WAS MADE AVAILABLE AT 18:05 ON 6/27/96 AND THE CONDITION WILL BE | | RESOLVED PRIOR TO STARTUP. THE RI WILL BE INFORMED. LOWER ALLOWAYS CREEK | | TOWNSHIP WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 30689 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: EMERY WORLDWIDE AIR FREIGHT CO |NOTIFICATION DATE: 06/28/96 | | CITY: VANDALIA REGION: 3 |NOTIFICATION TIME: 02:47 [ET]| | COUNTY: STATE: OH |EVENT DATE: 06/28/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:50[EDT]| | DOCKET: |LAST UPDATE DATE: 06/28/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RONALD GARDNER RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+TED BECK DOE | |NRC NOTIFIED BY: PEKAR, DOT NAT RES CTR |RICH BARRETT AEOD | |HQ OPS OFFICER: DICK JOLLIFFE |STUART RUBIN AEOD | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TRANSPORTATION EVENT - SHIPPING CONTAINER DAMAGED, NO LIQUID P-32 LEAK - | | | | TOM PEKAR, DOT NATIONAL RESPONSE CENTER (INCIDENT REPORT #349415) REPORTED | | THAT A 3 INCH X 3 INCH X 12 INCH CARDBOARD SHIPPING CONTAINER CONTAINING | | APPROXIMATELY 1 OUNCE OF RADIOACTIVE LIQUID SALT PHOSPHORUS-32 (1169 | | GIGABECQUERELS) INSIDE A GLASS VIAL INSIDE A LEAD SLEEVE WAS RUN OVER AND | | DAMAGED BY A VEHICLE AT THE EMERY WORLDWIDE AIR FREIGHT COMPANY SERVICE | | CENTER, VANDALIA, OH. THE CONTAINER IS MARKED "RADIOACTIVE-NOS, UN-1169". | | THE GLASS VIAL WAS NOT BROKEN; THE LEAD SLEEVE WAS NOT DAMAGED. NO | | RADIOACVTIVE LIQUID LEAKED FROM THE GLASS VIAL. THE DAMAGED PACKAGE HAS | | BEEN PLACED INSIDE A 30 GALLON METAL DRUM IN A HAZMAT STORAGE AREA. THE | | PACKAGE WAS BEING SHIPPED BY DUPONT - LIFE SCIENCES COMPANY, BOSTON, MA, | | TO MANDEL SCIENTIFIC, LTD, EDMONTON, ALBERTA, CANADA. | | | | EMERY CONTACT IS MIKE SOWERS OR CHRIS ANDRACKI (REFER TO HOO LOG FOR | | TELEPHONE NUMBER). | | | | DOT NATIONAL RESPONSE CENTER NOTIFIED DOE, US EPA, OHIO EPA, & NOAA. | +------------------------------------------------------------------------------+