U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/04/97 - 06/05/97 ** EVENT NUMBERS ** 32432 32433 32434 32435 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32432 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/04/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 11:44 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/03/97 | +------------------------------------------------+EVENT TIME: 15:55[EDT]| |NRC NOTIFIED BY: L NELSON |LAST UPDATE DATE: 06/04/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STATE OF CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION WAS | | NOTIFIED BY THE LICENSEE THAT THEY EXCEEDED THEIR NATIONAL POLLUTION | | DISCHARGE ELIMINATION SYSTEM (NPDES) DISCHARGE PERMIT LIMIT FOR PH. | | | | WHILE CHIPPING TURBINE BUILDING CEMENT FLOOR SOME OF THE CEMENT DUST GOT | | INTO THE TURBINE BUILDING SUMP WHICH INCREASED THE PH OF THE SUMP. LESS | | THAN 100 GALLONS OF THE TURBINE BUILDING SUMP WAS DISCHARGED TO LONG ISLAND | | SOUND. THE LICENSEE NOTIFIED THE STATE OF CONNECTICUT DEPARTMENT OF | | ENVIRONMENTAL PROTECTION THAT THEY HAD DISCHARGED WATER WITH A PH GREATER | | THAN THE NPDES PERMIT LIMIT OF 8.0 TO LONG ISLAND SOUND ON 06/03/97. THE PH | | LEVEL OF THE WATER DISCHARGED TO LONG ISLAND SOUND WAS 9.05. | | | | THE LICENSEE DETERMINED TODAY AT 1100 EDT THAT THIS WAS A REPORTABLE EVENT | | BECAUSE THEY HAD MADE AN OFFSITE NOTIFICATION TO THE STATE OF CONNECTICUT | | ABOUT EXCEEDING THEIR NPDES PERMIT LIMIT. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT NOTIFICATION. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32433 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/04/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [3] CE |EVENT DATE: 06/04/97 | +------------------------------------------------+EVENT TIME: 12:25[CDT]| |NRC NOTIFIED BY: OSCAR PIPKINS |LAST UPDATE DATE: 06/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A POTENTIAL COMMON MODE FAILURE OF ELECTRICAL BUSES | | DURING A REVIEW OF APPENDIX "R" ELECTRICAL CABLE SEPARATION FOLLOWING A | | POSTULATED CONTROL ROOM FIRE. | | | | "ON 6/4/97, AT 1225 WITH THE PLANT SHUTDOWN DURING REFUEL 8, IT WAS | | DETERMINED THAT A POTENTIAL EXISTED FOR COMMON MODE FAILURE OF PLANT SAFETY | | UNITERRUPTIBLE POWER SUPPLIES (SUPS) SA, SB, SMA, SMB, SMC, AND SMD IN A | | SINGLE 20 FOOT WIDE APPENDIX R POSTULATED FIRE. IT WAS DETERMINED THAT | | UNWRAPPED, NONESSENTIAL CABLES IN THE CABLE VAULT AREA, UNDER THE CONTROL | | ROOM, IF EXPOSED TO THE POSTULATED FIRE, COULD CAUSE FAULTS THAT COULD | | (WORST CASE CONDITION) SHUT DOWN EACH OF THE SUPS. FOR A FIRE IN THE | | CONTROL ROOM/CABLE VAULT, ESSENTIAL SAFE SHUTDOWN CIRCUITS ARE ISOLATED | | FROM THE CONTROL ROOM/CABLE VAULT AND ARE NOT SUBJECT TO FAILURES. HOWEVER, | | REDUNDANT, NONESSENTIAL CIRCUITS ARE NOT PROTECTED AND MAY RESULT IN | | SHUTDOWN OF THE SUPS. THE CONDITION IS APPARENTLY DUE TO A DEFICIENCY IN | | THE CIRCUIT DESIGN SUCH THAT A RACE TO CLEAR THE FAULTS WOULD OCCUR BETWEEN | | EACH OF THE SUPS' INDIVIDUAL LOAD BREAKERS AND THE INDIVIDUAL SUPS SHUTTING | | DOWN. THE TECHNICAL REQUIREMENTS MANUAL LCO WAS ENTERED AND THE | | APPROPRIATE COMPENSATORY ACTIONS (FIRE WATCHES) WERE ESTABLISHED IN AREAS | | KNOWN AND SUSPECTED TO HAVE THE PROBLEM. ADDITIONAL CORRECTIVE MEASURES | | WILL BE TAKEN IN A TIMELY MANNER." | | | | THIS FINDING WAS IDENTIFIED AND DOCUMENTED BY THE LICENSEE IN CONDITION | | REPORT 97-0988 ISSUED 4/23/97. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32434 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 06/04/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:30 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/04/97 | +------------------------------------------------+EVENT TIME: 13:11[CDT]| |NRC NOTIFIED BY: FRED SCHIZAS |LAST UPDATE DATE: 06/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM WAS DECLARED INOPERABLE | | FOLLOWING ITS FAILURE TO MEET THE MONTHLY SURVEILLANCE PROCEDURE FLOW | | ACCEPTANCE CRITERIA. | | | | "AT 1311CDT ON 6/4/97 DURING PERFORMANCE OF SURVEILLANCE PROCEDURE | | 6.HPCI.101, THE HPCI MONTHLY SURVEILLANCE, HPCI FAILED TO MEET THE | | ACCEPTANCE CRITERIA OF STEP 2.48 OF SP 6.HPCI.101, WHICH REQUIRES THAT THE | | OUTPUT SIGNAL OF THE HPCI FLOW CONTROLLER (HPCI-FIC-108) BE LESS THAN OR | | EQUAL TO 100% AND THAT HPCI FLOW BE GREATER THAN OR EQUAL TO 4250 GPM. FLOW | | INDICATIONS SHOWED OSCILLATIONS SUCH THAT CONSTANT FLOW EQUAL TO OR GREATER | | THAN 4250 GPM COULD NOT BE DEMONSTRATED. HPCI WAS SUBSEQUENTLY DECLARED | | INOPERABLE AT THE ALLOWED OUT-OF-SERVICE TIME (AOT) START TIME OF 1237CDT. | | | | THE AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) WAS DEMONSTRATED OPERABLE AND | | BOTH LOOPS OF LOW PRESSURE COOLANT INJECTION (LPCI) AND CORE SPRAY WERE | | VERIFIED OPERABLE. THE SINGLE TRAIN REACTOR CORE ISOLATION COOLING (RCIC) | | SYSTEM WAS ALSO VERIFIED OPERABLE. | | | | PLANNED ACTIVITIES ARE FOR I&C TO TROUBLESHOOT THE CONDITION, PLAN AND | | IMPLEMENT REQUIRED REPAIRS AND PERFORM THE NECESSARY POST MAINTENANCE | | TESTING SUCH THAT OPERABILITY IS SUCCESSFULLY DEMONSTRATED." | | | | THE LICENSEE ENTERED THE 7 DAY TECH SPEC LCO ACTION STATEMENT 3.5.C WHICH | | REQUIRES THAT HPCI BE RESTORED WITHIN THE AOT OR THE UNIT BE PLACED IN HOT | | SHUTDOWN IN 6 HOURS AND COLD SHUTDOWN WITHIN THE FOLLOWING 24 HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32435 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 06/04/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:14 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/04/97 | +------------------------------------------------+EVENT TIME: 16:00[CDT]| |NRC NOTIFIED BY: JOSEPH SIPEK |LAST UPDATE DATE: 06/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |HFIT 26.73 FITNESS FOR DUTY |ROBERT CAPRA EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON-LICENSED SENIOR MANAGER TESTED POSITIVE FOR ALCOHOL DURING A DRUG TEST | | ADMINISTERED FOR CAUSE. THE MANAGER'S PROTECTED AREA ACCESS HAS BEEN | | SUSPENDED PENDING ACTIONS IN ACCORDANCE WITH SITE PROCEDURES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR, REGION 3 (CALDWELL) AND | | WILL INFORM THE NRR PROJECT MANAGER. | +------------------------------------------------------------------------------+