U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/14/97 - 08/15/97 ** EVENT NUMBERS ** 32657 32687 32692 32756 32757 32758 32759 32760 32761 32762 32763 32764 32765 32766 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32657 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/20/97 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 20:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/20/97 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTROL ROOM VENTILATION SYSTEM OPERATED IN AN UNANALYZED CONDITION - | | | | SALEM UNIT 1 (MODE 6 - DEFUELED IN A REFUELING OUTAGE) AND UNIT 2 (MODE 3 - | | HOT STANDBY IN A REFUELING OUTAGE) HAVE A COMMON CONTROL ROOM. | | | | AT 1409, A MOMENTARY SPIKE OCCURRED ON THE #1B VITAL INSTRUMENT BUS DURING | | A MAINTENANCE ACTIVITY. THIS SPIKE CAUSED THE COMMON CONTROL ROOM | | VENTILATION SYSTEM TO AUTOMATICALLY SHIFT FROM THE NORMAL MODE TO THE | | ACCIDENT PRESSURIZATION MODE OF OPERATION DUE TO THE MOMENTARY LOSS OF | | POWER TO CONTROL ROOM RADIATION MONITORS #1R1B-1 (UNIT 1) AND #1R1B-2 | | (UNIT 2). | | | | AT 1700, THE LICENSEE DETERMINED THAT THE CONTROL ROOM VENTILATION SYSTEM | | WAS OPERATING IN AN UNANALYZED CONDITION SINCE THE ACCIDENT PRESSURIZATION | | OPERATING MODE OF THE CONTROL ROOM VENTILATION SYSTEM WAS NOT DESIGNED TO | | HAVE A SIMULTANEOUS ACTUATION SIGNAL FROM BOTH UNIT 1 AND UNIT 2 AT THE | | SAME TIME. THE LICENSEE ENTERED TECH SPEC LCO A/S 3.0.3 ON UNIT 2 TO | | TAKE ACTION WITHIN 1 HOUR TO PLACE UNIT 2 IN MODE 4 (HOT SHUTDOWN) WITHIN | | 6 HOURS AND MODE 5 (COLD SHUTDOWN) WITHIN THE FOLLOWING 12 HOURS. | | | | AT 1814, THE LICENSEE RETURNED THE CONTROL ROOM VENTILATION SYSTEM TO ITS | | NORMAL OPERATING MODE. | | | | AT 1846, THE LICENSEE BLOCKED POWER TO ALL 4 CONTROL ROOM RADIATION | | MONITORS (2 FOR EACH UNIT) AND ENTERED TECH SPEC LCO A/S 3.3.3.1 FOR | | INOPERABLE CONTROL ROOM RADIATION MONITORS. | | | | AT 1952, THE LICENSEE EXITED TECH SPEC LCO A/S 3.0.3 FOR UNIT 2. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT AND DETERMINING | | CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1634 ON 08/14/97 FROM GUMBERT TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE PERFORMED A | | CALCULATION TO ASSESS THE DOSE IMPACT TO THE CONTROL ROOM OPERATORS WITH | | THE CONTROL ROOM VENTILATION SYSTEM IN THE NORMAL MODE OF OPERATION (BOTH | | TRAINS OPERATING) AND THE INTAKE DAMPER OPENING FOR THE UNIT HAVING THE | | ACCIDENT. THIS CALCULATION DETERMINED THAT THE DOSE CONSEQUENCES IN THIS | | CONFIGURATION ARE BOUNDED BY THE EXISTING WORST-CASE DOSE ANALYSIS RESULTS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (GRAY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32687 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/28/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 05:42 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/28/97 | +------------------------------------------------+EVENT TIME: 03:29[EDT]| |NRC NOTIFIED BY: MCKEE |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAINMENT VENTILATION ISOLATION ON A HIGH RADIATION MONITOR ALARM | | | | DURING FUEL HANDLING ACTIVITIES (CORE RELOAD), THE CONTAINMENT VENTILATION | | SYSTEM ACTUATED RESULTING IN A CONTAINMENT VENTILATION ISOLATION. THE | | INITIATING SIGNAL WAS A HIGH RADIATION ALARM SPIKE ON THE "R-14" PLANT | | VENTILATION RADIOGAS MONITOR. THIS WAS CAUSED BY DIRECT "RADIATION SHINE" | | FROM A NEUTRON SOURCE IN THE FUEL ASSEMBLY BEING MOVED. THE ISOLATION WAS | | RESET WITHIN 17 MINUTES. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1216 ON 08/14/97 FROM TIERNEY TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. A SUBSEQUENT REVIEW OF THE | | VENT DETERMINED THAT THE CLOSURE OF THE VALVES WAS DUE TO A SIGNAL FROM A | | NON-ENGINEERED SAFETY FEATURE RADIATION INSTRUMENT, AND IT WAS INVALID. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (GRAY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32692 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/29/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 02:26 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 02:04[EDT]| |NRC NOTIFIED BY: LATZ |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT SECURITY EVENT | | | | A SAFEGUARDS SYSTEM DEGRADATION RELATED TO THE SECURITY COMPUTER AND ALARMS | | OCCURRED. COMPENSATORY MEASURES WERE IN PLACE WITHIN TEN MINUTES. (REFER | | TO THE HOO LOG FOR ADDITIONAL DETAILS.) | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 1235 EDT ON 08/14/97 FROM PATRICK ANHALT TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED ON THE FACT THAT | | COMPENSATORY MEASURES WERE TAKEN WITHIN TEN MINUTES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (GRAY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32756 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 08/14/97 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 10:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/14/97 | +------------------------------------------------+EVENT TIME: 08:46[CDT]| |NRC NOTIFIED BY: BRIAN VOSS |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT RECEIVED A GROUP 2 AND 4 ISOLATION DUE TO A FAILED RELAY. | | | | THE UNIT RECEIVED AN ALARM ON 1-C05B INDICATING THAT THE GROUP 2 AND 4 | | ISOLATIONS HAD OCCURRED. UPON INSPECTION, OPERATORS FOUND THAT VALVES | | CV-3705 AND CV-3729 WERE DEENERGIZED AND CLOSED. VALVE CV-4640 WAS ALSO | | CLOSED. A REPORT WAS RECEIVED THAT THE OUTBOARD GROUP 1B, 2, AND 4 | | ISOLATIONS HAD OCCURRED. AN INITIAL INVESTIGATION DISCOVERED THAT FUSE F17 | | (F22-APED) ON TERMINAL STRIP "AA" IN CABINET 1C-42 HAD BLOWN. THE LICENSEE | | REPLACED THE BLOWN FUSE AT WHICH TIME THEY FOUND THE ASSOCIATED K-60 RELAY | | HAD FAILED (DEENERGIZED). THE CAUSE OF THE FAILED RELAY IS UNKNOWN AND | | UNDER INVESTIGATION. THE GROUP 2 AND 4 ISOLATIONS AFFECT THE SHUTDOWN | | COOLING SYSTEM AND THE DRYWELL SUMP. THE UNIT ENTERED TECHNICAL | | SPECIFICATION LIMITING CONDITION FOR OPERATION 3.6.C.4 WHICH REQUIRES THAT | | THE DRYWELL SUMP BE OPERABLE FOR REACTOR COOLANT SYSTEM LEAK RATE | | DETERMINATION. THE LICENSEE HAD IMPLEMENTED CONTAINMENT AIR SAMPLING WHILE | | PURSUING A TEMPORARY MODIFICATION TO ALLOW PUMPING THE DRYWELL SUMP. THERE | | WERE NO MAINTENANCE ACTIVITIES IN PROGRESS AT THE TIME OF THE ENGINEERED | | SAFETY FEATURE ACTUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32757 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/14/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 10:40 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/13/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:55[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/14/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BULLETIN 91-01 ISSUE INVOLVING THE LOSS OF NEUTRON POISON CONTROL (ONE OF | | THE DOUBLE CONTINGENCIES FOR CRITICALITY CONTROL) - (24-HOUR REPORT) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "ON 8/13/97 AT 1300 HOURS, WITH THE X-342 AUTOCLAVES REMOVED FROM SERVICE, | | CHEMICAL OPERATORS WERE PREPARING [THE] X-342 OIL INTERCEPTOR FOR | | MAINTENANCE ON [THE] DRAIN LINE. WHILE REMOVING THE BOROSILICATE GLASS | | RASHIG RING NEUTRON ABSORBERS FROM THE PIT, POLY VINYL CHLORIDE (PVC) | | RASHIG RINGS WERE MIXED WITH THE GLASS RASHIG RINGS IN THE BOTTOM OF [THE] | | OIL INTERCEPTOR. NUCLEAR CRITICALITY SAFETY REQUIREMENTS SPECIFY THAT ONLY | | BOROSILICATE GLASS RINGS ARE ACCEPTABLE FOR NEUTRON POISON CONTROL. THE | | LOSS OF NEUTRON POISON CONTROL REPRESENTS THE LOSS OF ONE [NUCLEAR | | CRITICALITY SAFETY] CONTROL TO ENSURE [THAT THE] DOUBLE CONTINGENCY | | [POLICY] IS MET." | | | | "THE NUCLEAR CRITICALITY SAFETY OF THE OIL INTERCEPTOR IN X-342 IS BASED | | PRIMARILY ON EXCLUDING ALL URANIUM FROM ENTERING THE INTERCEPTOR UNDER | | NORMAL OPERATING CONDITIONS. IN THE EVENT OF A LARGE UF6 RELEASE FROM A | | RUPTURED CYLINDER AND [A] SUBSEQUENT MIGRATION OF THE MATERIAL INTO THE | | INTERCEPTOR, SUBCRITICALITY IS ENSURED BY THE PRESENCE OF RASHIG RINGS." | | | | "THE LOSS OF ONE CONTROL MAKES [THIS] INCIDENT REPORTABLE TO THE NRC UNDER | | THE 24-HOUR REPORTING CRITERIA OUTLINED IN PROCEDURE UE2-RA-RE1030, | | APPENDIX D, SECTION A.4.a." | | | | "AT THE TIME OF DISCOVERY OF THIS EVENT, THE AUTOCLAVES WERE SHUTDOWN FOR | | SCHEDULED MAINTENANCE ON [THE] DRAIN. A LARGE UF6 RELEASE FROM A RUPTURED | | CYLINDER AND SUBSEQUENT MIGRATION INTO THE OIL INTERCEPTOR WOULD BE | | REQUIRED BEFORE CRITICALITY COULD OCCUR." THE CONTROL PARAMETERS INVOLVED | | WERE MASS AND NEUTRON POISON, AND "THERE WAS NO MASS OF URANIUM CONTAINED | | IN THE OIL INTERCEPTOR. [THE] AUTOCLAVES WERE IN [THE] SHUTDOWN MODE | | DURING DISCOVERY[, AND THEY HAVE BEEN] DECLARED INOPERABLE UNTIL [THE] | | DEFICIENCY [IS] CORRECTED." | | | | PORTSMOUTH NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT OF | | ENERGY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32758 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 08/14/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 12:05 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 08/14/97 | +------------------------------------------------+EVENT TIME: 11:25[EDT]| |NRC NOTIFIED BY: CASE |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 +------------------------------------------------------------------------------+ | SAFETY-RELATED CABLES HAVE INADEQUATE FIRE PROTECTION. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ONGOING ENGINEERING EVALUATION OF THE SAFE SHUTDOWN ANALYSIS HAS | | IDENTIFIED [TWO] SEPARATE REQUIRED CABLES IN TWO FIRE AREAS WHICH DO NOT | | HAVE ADEQUATE FIRE PROTECTION. ONE OF THE CABLES RUNS THROUGH A FIRE AREA | | WHICH HAS SUPPRESSION AND DETECTION INSTRUMENTATION. THE OTHER CABLE HAS | | 20 FEET OF SEPARATION BETWEEN REDUNDANT SAFE SHUTDOWN DIVISION CABLES, BUT | | [IT] IS IN A FIRE AREA WHICH DOES NOT HAVE SUPPRESSION OR DETECTION | | INSTRUMENTATION. BOTH AREAS HAVE HAD HOURLY FIRE WATCHES ESTABLISHED SINCE | | 1993 AS A RESULT OF THERMOLAG CONCERNS. THE HOURLY FIRE WATCHES WILL BE | | CONTINUED IN THE AREA WHICH HAS SUPPRESSION AND DETECTION INSTRUMENTATION, | | AND A CONTINUOUS FIRE WATCH HAS BEEN ESTABLISHED FOR THE AREA WHICH DOES | | NOT HAVE SUPPRESSION AND DETECTION INSTRUMENTATION." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32759 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CROW BUTTE RESOURCES |NOTIFICATION DATE: 08/14/97 | | CITY: CRAWFORD REGION: 4 |NOTIFICATION TIME: 12:30 [ET]| | COUNTY: STATE: NE |EVENT DATE: 08/12/97 | |LICENSE#: SUA-1534 AGREEMENT: Y |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 08/14/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOSEPH TAPIA RDO | | |LARRY CAMPER, NMSS EO | +------------------------------------------------+JOE HOLONICH NMSS | |NRC NOTIFIED BY: MAGNUSON | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF PINHOLE LEAKS IN UPPER LINER OF PROCESS WATER EVAPORATION POND | | AT A MINING FACILITY | | | | THE LICENSEE DISCOVERED TWO PINHOLE LEAKS (0.08" DIAMETER) IN THE UPPER | | LINER OF THE #1 PROCESS WATER EVAPORATION POND. THE HOLES ARE LOCATED NEAR | | THE WATERLINE OF THE POND. APPROXIMATELY 68 GALLONS OF WATER HAVE LEAKED | | THROUGH THE HOLES DURING THE PAST WEEK, AND ALL LEAKAGE HAS BEEN CONTAINED | | IN THE POND SUMP. THE LICENSEE BECAME AWARE OF THE LEAKAGE ON 8/12/97 WHEN | | A HIGH CONDUCTIVITY ALARM WAS RECEIVED FROM THE POND SUMP. A CONFIRMATORY | | SAMPLE WAS TAKEN AND A VISUAL INSPECTION OF THE LINER WAS PERFORMED. WATER | | FROM THE POND IS BEING TRANSFERRED TO THE TWO OTHER EVAPORATION PONDS AT | | THE FACILITY. THE VENDOR OF THE POND LINER HAS BEEN CONTACTED AND WILL | | ARRIVE ONSITE WITHIN THE NEXT WEEK TO MAKE REPAIRS. | | | | THE LICENSEE HAS NOTIFIED THE STATE OF NEBRASKA AND NRC REGION IV REGARDING | | THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32760 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MERCY HOSPITAL |NOTIFICATION DATE: 08/14/97 | | CITY: PORT HURON REGION: 3 |NOTIFICATION TIME: 13:13 [ET]| | COUNTY: STATE: MI |EVENT DATE: 08/13/97 | |LICENSE#: 21-15638-01 AGREEMENT: N |EVENT TIME: 20:30[EDT]| | DOCKET: |LAST UPDATE DATE: 08/14/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KERRY LANDIS RDO | | |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CHUCK SMITH | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL MISADMINISTRATION | | | | AT 1045 ON 8/12/97, A TANDEM GYNECOLOGICAL IMPLANT (TOTALING 29.8 mg Ra | | EQUIVALENT) WAS INSERTED INTO A FEMALE PATIENT FOR TREATMENT OF A TUMOR, | | AND IT WAS TO REMAIN IN PLACE FOR 48 HOURS. A NURSE CHECKED THE STATUS OF | | THE APPLICATOR AT 1500 ON 8/13/97, AND THE SOURCES APPEARED TO BE CORRECTLY | | PLACED AT THAT TIME. HOWEVER, AT 2030 ON 8/13/97, A NURSE OBSERVED THAT THE | | APPLICATOR HAD BECOME DISLODGED. THE PHYSICIAN WAS CONTACTED, AND THE | | SOURCES WERE REMOVED SHORTLY THEREAFTER. AT 2230 ON 8/13/97, THE SOURCES | | WERE RE-IMPLANTED BY THE PHYSICIAN, AND TREATMENT WAS CONTINUED. THIS EVENT | | IS REPORTABLE BECAUSE A DOSE WAS ADMINISTERED TO AN UNINTENDED PORTION OF | | THE BODY WHEN THE APPLICATOR BECAME DISLODGED. NO ADVERSE CONSEQUENCES TO | | THE PATIENT ARE ANTICIPATED. | | | | NRC REGION III HAS BEEN CONTACTED BY THE LICENSEE REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32761 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/14/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 13:51 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/14/97 | +------------------------------------------------+EVENT TIME: 13:30[EDT]| |NRC NOTIFIED BY: DILUNA |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT A HIGH ENERGY LINE BREAK ON UNIT 2 COULD | | POTENTIALLY AFFECT THE UNIT 1 VITAL SWITCHGEAR ROOM. | | | | THIS WAS DETERMINED DURING A RE-ANALYSIS OF A HIGH ENERGY LINE BREAK (HELB) | | FOR UNIT 2. AN HELB COULD POTENTIALLY PRESSURIZE THE UNIT 1 VITAL | | SWITCHGEAR ROOM RESULTING IN THE CREATION OF A HARSH ENVIRONMENT AND | | POTENTIALLY MAKING EQUIPMENT IN THE ROOM INOPERABLE. THE REVIEW OF THE | | HELB ANALYSIS FOR UNIT 2 RESULTED IN HIGHER PREDICTED TEMPERATURES AND | | PRESSURES. THESE TEMPERATURES AND PRESSURES COULD BREECH AN ADJOINING WALL | | AND DOORWAY CREATING A FLOW PATH FOR THE STEAM INTO THE UNIT 1 VITAL | | SWITCHGEAR AREA AND AFFECTING A NUMBER OF SAFE SHUTDOWN SYSTEMS. THE | | LICENSEE IS STILL EVALUATING THIS CONDITION AND HAS NOT YET DETERMINED ANY | | CORRECTIVE MEASURES. | | | | THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE AND LOCAL AGENCIES HAVE | | BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32762 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ABB COMBUSTION ENGINEERING |NOTIFICATION DATE: 08/14/97 | | CITY: WINDSOR REGION: 1 |NOTIFICATION TIME: 14:24 [ET]| | COUNTY: STATE: CT |EVENT DATE: 08/14/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/14/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOSEPH TAPIA, REG 4 RDO | | | | +------------------------------------------------+VERN HODGE, NRR RVIB | |NRC NOTIFIED BY: G. HESS |HAROLD GRAY, REG 1 RDO | |HQ OPS OFFICER: BOB STRANSKY |KERRY LANDIS, REG 2 RDO | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT | | | | ENERGY REDISTRIBUTION FACTORS USED IN LARGE-BREAK LOSS OF COOLANT ACCIDENT | | ANALYSES DO NOT DIRECTLY REFLECT THE EFFECTS OF MODERATOR VOIDING. | | SPECIFICALLY, THE ENERGY REDISTRIBUTION FACTORS ARE UNDER PREDICTED BY 0.5% | | TO 1.5%. THIS CORRESPONDS TO A 20øF TO 60øF INCREASE IN PEAK CLAD | | TEMPERATURE DURING LARGE-BREAK LOSS OF COOLANT ACCIDENTS. | | | | THE FOLLOWING UNITS ARE AFFECTED: PALO VERDE UNITS 1, 2, AND 3; SAN ONOFRE | | UNITS 2 AND 3; WATERFORD UNIT 3; ARKANSAS NUCLEAR ONE UNIT 2; CALVERT | | CLIFFS UNITS 1 AND 2; AND SAINT LUCIE UNIT 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32763 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 08/14/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:07 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 08/14/97 | +------------------------------------------------+EVENT TIME: 12:50[EDT]| |NRC NOTIFIED BY: GROFF |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ISOLATION OF TORUS WATER MANAGEMENT SYSTEM | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 1250 ON 8/14/97, AUTOMATIC ISOLATION OF THE PRIMARY CONTAINMENT | | OUTBOARD ISOLATION VALVES FOR THE TORUS WATER MANAGEMENT SYSTEM OCCURRED. | | THIS IS BELIEVED TO HAVE OCCURRED AS A RESULT OF AN INVALID SIGNAL OF TORUS | | SUMP LEVEL HIGH-HIGH. THIS WAS NOT A PREPLANNED ISOLATION. THE VALVES | | CLOSED DUE TO LOSS OF POWER TO [THE] SUMP LOGIC WHICH WAS DEENERGIZED WHILE | | DISCONNECTING WIRES TO REPAIR/REPLACE A TERMINAL BLOCK DURING MAINTENANCE | | ACTIVITIES. INVESTIGATION OF THIS EVENT IS UNDERWAY INCLUDING WHETHER THE | | SUMP LEVEL SIGNAL IS AN ESF [ENGINEERED SAFETY FEATURE] SIGNAL." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32764 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 08/14/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 16:20 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 08/14/97 | +------------------------------------------------+EVENT TIME: 16:20[EDT]| |NRC NOTIFIED BY: JACOBS |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 +------------------------------------------------------------------------------+ | NONSAFETY CONTROL CABLES USED IN CIRCUITS ATTACHED TO SAFETY-RELATED BUSES. | | | | WHILE EVALUATING THE LOAD SHED DESIGN FOR THE CONTROL ROOM AIR CONDITIONERS | | (VRC-101A/B), THE LICENSE IDENTIFIED THAT NONSAFETY-RELATED LOADS THAT ARE | | SHED FROM SAFETY-RELATED BUSES HAVE NONSAFETY-RELATED CABLES IN THEIR | | CONTROL CIRCUITS. THE LICENSEE BELIEVES THAT THIS CONDITION IS OUTSIDE OF | | ITS ORIGINAL DESIGN BASIS AND IS CONSERVATIVELY REPORTING THE CONDITION | | PENDING COMPLETION OF ITS EVALUATION. THE LICENSEE HAS EVALUATED THE | | QUALITY OF THE CABLES, THE RACEWAY SUPPORTS, AND SEPARATION OF CABLES. THE | | LICENSEE HAS ALSO DETERMINED THAT THE LOADING IS WITHIN THE EMERGENCY | | DIESEL GENERATORS' RATINGS AND THAT THE EMERGENCY DIESEL GENERATORS, | | THEREFORE, REMAIN OPERABLE. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32765 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 08/14/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:24 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 08/03/97 | +------------------------------------------------+EVENT TIME: 02:00[EDT]| |NRC NOTIFIED BY: FULLER |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 50 POWER OPERATION | 50 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ELECTRICAL DISTRIBUTION PERFORMANCE OUTSIDE OF DESIGN BASIS | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "FURTHER EVALUATION OF THE EVENTS THAT OCCURRED DURING A PLANT TRIP ON | | AUGUST 1, 1997 [HOO NOTE: SEE EN#32711], DETERMINED THAT THE ELECTRICAL | | DISTRIBUTION SYSTEM RESPONSE WAS OUTSIDE THE DESIGN BASIS. THE DESIGN BASIS | | RESPONSE CALLS FOR THE EMERGENCY POWER SYSTEM TO REMAIN CONNECTED TO THE | | OFFSITE POWER SOURCE DURING DEGRADED (HEAVY DEMAND) CONDITIONS ON THE | | GRID." | | | | "VOLTAGE REGULATORS ON THE STARTUP TRANSFORMERS WERE POSITIONED SUCH THAT | | THEY DID NOT ADEQUATELY MAINTAIN VOLTAGE ON THE EMERGENCY BUSES (i.e., THEY | | WERE POSITIONED TO REDUCE VOLTAGE RATHER THAN BEING IN 'NEUTRAL' WHICH IS | | AN ANALYSIS ASSUMPTION)." | | | | "THE VOLTAGE REGULATORS HAVE BEEN REPAIRED AND RESET TO ENSURE [THAT] PLANT | | BUS VOLTAGES REMAIN WITHIN THE DESIGN BASIS." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32766 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/14/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 20:00 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/14/97 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: DAMMONN |LAST UPDATE DATE: 08/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 TECHNICAL SUPPORT CENTER INOPERABLE DUE TO PLANT MAINTENANCE | | | | THE LICENSEE REPORTED THAT THE TECHNICAL SUPPORT CENTER (TSC) WILL BE | | UNAVAILABLE FROM 2000 EDT ON 8/14/97 UNTIL THE EVENING OF 8/17/97 DUE TO | | ELECTRICAL BUS MAINTENANCE. OTHER ONSITE FACILITIES WILL CONTINUE TO BE | | AVAILABLE IF NEEDED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+