U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/29/97 - 09/30/97 ** EVENT NUMBERS ** 33005 33006 33007 33008 33009 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33005 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 09/29/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 10:17 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/29/97 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: BILL WEBSTER |LAST UPDATE DATE: 09/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ON 09/26/97, THE LICENSEE FOUND A DEAD OSPREY UNDER HIGH VOLTAGE LINES ON | | VEPCO PROPERTY. AT 0950 ON 09/29/97, THE LICENSEE NOTIFIED THE US FISH AND | | WILDLIFE AGENCY OF A DEAD BIRD OF PREY IN ACCORDANCE WITH THE MIGRATORY | | BIRD TREATY ACT. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33006 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 09/29/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 10:22 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 09/29/97 | +------------------------------------------------+EVENT TIME: 06:15[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 09/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - REACTOR BUILDING CCW PRIMARY CONTAINMENT OUTLET VALVE FAILED ITS LLRT - | | | | WITH UNIT 2 IN CONDITION 4 IN A REFUELING OUTAGE, THE LICENSEE PERFORMED A | | LEAK RATE TEST OF THE PRIMARY CONTAINMENT. DURING THE TEST, THE LEAK RATE | | THROUGH THE REACTOR BUILDING CLOSED COOLING WATER (CCW) PRIMARY CONTAINMENT | | OUTLET VALVE #2-FCV-70-47, COMBINED WITH THE THE LEAKAGE THROUGH ALL OTHER | | PRIMARY CONTAINMENT COMPONENTS, EXCEEDED THE TECH SPEC LEAK RATE LIMIT OF | | 655.9 SCFH. | | | | THE LICENSEE PLANS TO SUBMIT A LICENSEE EVENT REPORT TO THE NRC WITHIN | | 30 DAYS AND WILL REPAIR THIS VALVE PRIOR TO RESTARTING UNIT 2. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33007 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 09/29/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 18:56 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 09/29/97 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: COSEO |LAST UPDATE DATE: 09/29/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HPCI SYSTEM HAS BEEN DECLARED INOPERABLE DUE TO BACK LEAKAGE THROUGH | | ONE OF THE SYSTEM'S CHECK VALVES. | | | | DURING THE PERFORMANCE OF THE HPCI SYSTEM PUMP AND VALVE OPERABILITY TEST, | | THE HPCI BAROMETRIC CONDENSER CONDENSATE BOOSTER PUMP DISCHARGE CHECK | | VALVE EXHIBITED A SMALL AMOUNT OF BACK LEAKAGE DURING THE CHECK VALVE TEST | | (~1-2 MM DIAMETER STREAM). THE HPCI SYSTEM WAS CONSERVATIVELY DECLARED | | INOPERABLE, WHICH PLACED THE PLANT IN A 14 DAY LCO ACTION STATEMENT. | | HPCI, HOWEVER, IS CURRENTLY IN STANDBY MODE AND AVAILABLE. CORE SPRAY, | | LPCI, RCIC AND ADS ARE CURRENTLY OPERABLE. THE AUXILIARY EMERGENCY DIESEL | | GENERATORS ARE ALSO OPERABLE. THIS EVENT IS BEING REPORTED AS A POTENTIAL | | EVENT THAT COULD PREVENT THE FULFILLMENT OF A SAFETY FUNCTION OF SYSTEMS | | REQUIRED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. THE EXTENT OF IMPACT | | OF THE CHECK VALVE LEAKAGE IS STILL BEING EVALUATED. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33008 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SIERRA NUCLEAR CORP |NOTIFICATION DATE: 09/29/97 | | CITY: SCOTTS VALLEY REGION: 4 |NOTIFICATION TIME: 19:40 [ET]| | COUNTY: STATE: CA |EVENT DATE: 09/29/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[PDT]| | DOCKET: |LAST UPDATE DATE: 09/29/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL JONES, R4 RDO | | | | +------------------------------------------------+JOHN JACOBSON, R3 RDO | |NRC NOTIFIED BY: MASSEY (BY FAX) |VERN HODGE NRR | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SIERRA NUCLEAR CORPORATION (SNC) IS RESPONDING TO NRC INSPECTION REPORT | | #72-1007/97-212 AND NOTICES OF NONCONFORMANCE. | | | | THE NOTICES OF NONCONFORMANCE CITED IN THE INSPECTION REPORT RELATE TO | | CERTAIN CIRCUMSTANCES IN THE FABRICATION OF COMPONENTS DURING THE 1994-1995 | | TIME FRAME. THE INCIDENTS INVOLVED WELD CRACKING ON COMPONENTS AT TWO | | SITES, ARKANSAS NUCLEAR ONE AND PALISADES. SNC HAS IMPLEMENTED SIGNIFICANT | | CORRECTIVE ACTIONS, STARTING IN LATE 1994, WHICH HAVE PREVENTED RECURRENCE | | OF THESE CIRCUMSTANCES ON RECENTLY FABRICATED COMPONENTS. THEY BELIEVE | | THAT THEIR CURRENT QA PROGRAM IS EFFECTIVE AND MEETS THE REQUIREMENTS OF | | CURRENT CODES AND STANDARDS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33009 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/29/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 20:18 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/29/97 | +------------------------------------------------+EVENT TIME: 19:40[EDT]| |NRC NOTIFIED BY: WILLIAM MCCOLLUM |LAST UPDATE DATE: 09/29/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE LOSS OF ALTERNATE MAKEUP TO THE ISOLATION CONDENSER IN A FLOOD. | | | | IN THE EVENT OF A FLOOD, THE EQUIPMENT IN THE FIRE PUMP HOUSE IS PROTECTED | | BY WATERPROOF DOORS AND PLUGGING THE FLOOR DRAINS. CONTRARY TO THE INTENT | | OF THE "NATURAL OCCURRENCES" PROCEDURE, PLUGGING OF ONE OF THE FLOOR DRAINS | | HAS BEEN OVERLOOKED. IN REVIEW OF THE CONSEQUENCES OF THE DESIGN BASIS | | FLOOD ON THE FIRE PUMP HOUSE EQUIPMENT AND OTHER EQUIPMENT NECESSARY FOR | | THE SAFE SHUTDOWN OF THE FACILITY, IT HAS BEEN DETERMINED THAT A POTENTIAL | | EXISTS FOR THE PLANT TO BE SERIOUSLY DEGRADED AND OUTSIDE THE DESIGN BASIS. | | IT SHOULD BE NOTED THAT PAST CONDITIONS HAVE LED TO THE USE OF THIS | | PROCEDURE. THE FAILURE TO PLUG THE SUBJECT FLOOR DRAIN COULD RENDER FIRE | | WATER MAKEUP TO THE ISOLATION CONDENSER (IC) INOPERABLE DURING DESIGN BASIS | | FLOOD CONDITIONS. THE FLOOD WATERS COULD ALSO RENDER INOPERABLE THE | | ELECTRICAL COMPONENTS OF PUMPS REQUIRED FOR THE ALTERNATE IC MAKEUP WATER | | SOURCES, THE CONDENSATE STORAGE TANK AND THE DEMINERALIZED WATER SYSTEMS. | | ADDITIONALLY, THE EMERGENCY SERVICE WATER PUMPS COULD BE MADE INOPERABLE | | WHICH WOULD PREVENT THE IMPLEMENTATION OF ALTERNATE SHUTDOWN COOLING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+