U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/24/95 - 10/25/95 ** EVENT NUMBERS ** 29497 29499 29500 29501 29502 29503 29504 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29497 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/23/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/23/95 | +------------------------------------------------+EVENT TIME: 16:25[CDT]| |NRC NOTIFIED BY: ED LAMKEN |LAST UPDATE DATE: 10/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO A HYDRAZINE DISCHARGE THAT MAY HAVE EXCEEDED | | THE NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT | | | | WHILE IN A PLANNED MAINTENANCE OUTAGE FOR WORK ON THE SECONDARY SIDE STEAM | | GENERATOR (SG), DRAINING THE 'A' SG RESULTED IN THE RELEASE OF 12 PPM | | HYDRAZINE TO THE CIRC WATER SYSTEM WHICH WAS SUBSEQUENTLY RELEASED TO THE | | ROCK RIVER. A SAMPLE OF THE CIRC WATER BLOWDOWN AT THE TIME OF THE RELEASE | | WAS LESS THAN THE LOWER LIMIT OF DETECTION. THE LICENSEE NOTIFIED THE | | ILLINOIS EPA AND THE UNITED STATES COAST GUARD (USCG) NATIONAL RESPONSE | | CENTER AS A PRECAUTIONARY MEASURE. THE LICENSEE IS CURRENTLY REVIEWING THE | | EVENT TO SEE IF AN ACTUAL NPDES PERMIT LIMIT WAS EXCEEDED. | | | | THE SECONDARY SIDE DRAIN DOWN OF THE 'A' SG HAS BEEN COMPLETED, AND THE | | LICENSEE IS CURRENTLY DRAINING THE SECOND SG WHICH IS THE 'D' SG. A | | SAMPLING PROGRAM HAS BEEN INITIATED WITH ADMINISTRATIVE CONTROL DURING THE | | CONTINUATION OF THE SG DRAINING. DURING THE RELEASE, THE LICENSEE SAMPLED | | THE 'A' SG FOR CHEMICAL ANALYSIS, AND THE RESULTS OF THE ANALYSIS SHOWED | | THE PRESENCE OF HYDRAZINE WHICH THE LICENSEE DID NOT EXPECT. THE LICENSEE | | IS INVESTIGATING THE CAUSE OF THE HYDRAZINE IN THE 'A' SG. AT THIS TIME, | | THE LICENSEE SUSPECTS THAT THE CAUSE OF THE PROBLEM IS PERSONNEL ERROR. | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE @ 19:57 ON OCTOBER 24, 1995, FROM LAMKEN BY SEBROSKY * * * | | THE LICENSEE HAS DETERMINED THAT THE HYDRAZINE RELEASE DID NOT EXCEED NPDES | | LIMITS AND HAS INFORMED THE NRC RESIDENT INSPECTOR. IN ADDITION, THE | | ILLINOIS EPA AND THE USCG ARE AWARE THAT THE NPDES LIMITS WERE NOT | | EXCEEDED. THE HOO NOTIFIED THE R3DO (SHEAR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29499 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 10/24/95 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 12:59 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/24/95 | +------------------------------------------------+EVENT TIME: 12:01[EDT]| |NRC NOTIFIED BY: JOHN REINSBURROW |LAST UPDATE DATE: 10/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | |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 91 POWER OPERATION | 91 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NUMEROUS OFFSITE SIRENS FAILED DURING A SCHEDULED TEST | | | | DURING A SCHEDULED TEST OF THE EMERGENCY WARNING OFFSITE SIRENS, 18 OF 34 | | OFFSITE SIRENS HAD REMOTE INDICATION THAT THEY DID NOT SOUND. PERSONNEL | | STATIONED AT 3 OF THESE 18 SIRENS REPORTED THAT THE SIRENS DID ACTUALLY | | SOUND. AN INVESTIGATION INTO THE COMMUNICATIONS LINK BETWEEN THE SIRENS | | AND THE REMOTE INDICATION IS CONTINUING. THE COUNTY HAS BEEN NOTIFIED OF | | THE RESULTS OF THIS TEST, AND COMPENSATORY ACTIONS HAVE BEEN PUT IN PLACE | | TO INSURE THAT THE PUBLIC IS NOTIFIED IN THE EVENT OF AN ACTUAL EMERGENCY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29500 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/24/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:39 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/24/95 | +------------------------------------------------+EVENT TIME: 12:30[EDT]| |NRC NOTIFIED BY: MARTIN LICHTNER |LAST UPDATE DATE: 10/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE | | | | THE HPCI SYSTEM WAS DECLARED INOPERABLE DUE TO THE FAILURE OF THE LIMIT | | SWITCH ASSOCIATED WITH THE TURBINE STOP VALVE (1FD-FV-4880). FOLLOWING | | OPERATION OF THE HPCI AUXILIARY OIL PUMP DURING A ROUTINE LUBE OIL SAMPLE, | | THE TURBINE STOP VALVE CONTINUED TO INDICATE OPEN FROM THE CONTROL ROOM. | | THE VALVE POSITION WAS CONFIRMED TO BE CLOSED LOCALLY AT THE VALVE. THE | | VALVE POSITION IS USED TO INITIATE THE TURBINE SPEED CONTROL CIRCUIT (RAMP | | GENERATOR) AND VARIOUS VALVE INTERLOCKS. HPCI WAS DECLARED INOPERABLE DUE | | TO CONCERNS WITH THE SYSTEMS ABILITY TO RESTART IF IT WAS TRIPPED AFTER | | RECEIPT OF AN AUTOMATIC OR MANUAL INJECTION SIGNAL. THE LIMIT SWITCH WAS | | FOUND TO BE OUT OF ADJUSTMENT, AND THE LICENSEE IS TAKING ACTIONS TO ADJUST | | THE LIMIT SWITCH. | | | | THE LICENSEE IS IN A 14-DAY LCO DUE TO THE PROBLEM. ALL OTHER ECCS SYSTEMS | | AND THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ARE OPERABLE. | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR AND LOWER ALLOWAYS | | CREEK TOWNSHIP OFFICIALS OF THE EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29501 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 10/24/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/95 | +------------------------------------------------+EVENT TIME: 16:55[CDT]| |NRC NOTIFIED BY: TOM PATELLE |LAST UPDATE DATE: 10/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 +------------------------------------------------------------------------------+ | GREATER THAN 1% OF THE 4476 IN-SERVICE TUBES IN STEAM GENERATOR '1B' WERE | | FOUND TO BE DEFECTIVE AS DEFINED IN TECHNICAL SPECIFICATION 4.4.5.4.a. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "ON OCTOBER 7, 1995 A STEAM GENERATOR (SG) TUBE INSERVICE INSPECTION WAS | | INITIATED ON BRAIDWOOD UNIT 1 IN ACCORDANCE WITH TECHNICAL SPECIFICATION | | SURVEILLANCE REQUIREMENT (TSSR) 4.4.5.0. | | | | "THE INITIAL SAMPLE SIZE OF 100% OF ALL AVAILABLE TUBES WAS SELECTED. | | | | "TSSR 4.4.5.2.c REQUIRES THAT THE RESULTS OF EACH SAMPLE INSPECTION BE | | CLASSIFIED INTO ONE OF THREE CATEGORIES. A SG WILL BE CLASSIFIED IN | | CATEGORY C-3 IF MORE THAN 10% OF THE TOTAL TUBES INSPECTED ARE DEGRADED OR | | MORE THAN 1% OF THE INSPECTED TUBES ARE DEFECTIVE. A SG TUBE IS CONSIDERED | | DEGRADED IF IT HAS AN IMPERFECTION OF GREATER THAN OR EQUAL TO 20% NOMINAL | | TUBE WALL THICKNESS. A SG TUBE IS CONSIDERED DEFECTIVE IF IT HAS AN | | IMPERFECTION OF GREATER THAN OR EQUAL TO 40% NOMINAL TUBE WALL. ON OCTOBER | | 24,1995 AT 16:55 HOURS, THE RESULTS OF THE SAMPLE INSPECTION RESULTED IN SG | | 1B BEING CLASSIFIED INTO CATEGORY C-3 BASED ON GREATER THAN 1% OF THE 4476 | | INSERVICE TUBES BEING DEFECTIVE. MOST OF THESE DEFECTIVE TUBES ARE DUE TO | | INDICATIONS AT THE HOT LEG TUBE SUPPORT PLATE REGIONS. | | | | "THE ACCEPTANCE CRITERIA SPECIFIED IN BRAIDWOOD UNIT 1 TECHNICAL | | SPECIFICATION 4.4.5.4.a.6 REQUIRES A TUBE TO BE PLUGGED OR REPAIRED IF AN | | IMPERFECTION IS GREATER THAN OR EQUAL TO 40% THROUGH WALL. FOR UNIT 1 | | CYCLE 5, AN INTERIM PLUGGING CRITERIA (IPC) ALLOWED TUBES WITH INDICATIONS | | AT THE TUBE SUPPORT PLATES THAT ARE WITHIN THE LIMITS SPECIFIED BY THE | | TECHNICAL SPECIFICATION TO NOT BE CLASSIFIED AS DEFECTIVE. UNIT 1 CYCLE 5 | | IS NO LONGER IN EFFECT, THEREFORE, THE IPC DOES NOT APPLY. COMMONWEALTH | | EDISON HAS SUBMITTED A 3.0 VOLT IPC TECHNICAL SPECIFICATION AMENDMENT FOR | | NRC APPROVAL. THIS AMENDMENT HAS NOT BEEN APPROVED BY THE NRC AT THIS | | TIME. THE 1B STEAM GENERATOR DOES NOT MEET C-3 CRITERIA FOR A 3.0 VOLT | | IPC. | | | | "TECHNICAL SPECIFICATION TABLE 4.4-2 REQUIRES NRC NOTIFICATION PURSUANT TO | | 10 CFR 50.72(B)(2)(i) FOR ANY SG CLASSIFICATION IN CATEGORY C-3." END OF | | TEXT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29502 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/24/95 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 19:30 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/95 | +------------------------------------------------+EVENT TIME: 16:10[PDT]| |NRC NOTIFIED BY: BRAD HINDS |LAST UPDATE DATE: 10/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON-SEISMICALLY QUALIFIED RELAYS WERE FOUND TO BE INSTALLED IN UNIT 1's | | UNINTERRUPTIBLE POWER SUPPLIES. | | | | ON OCTOBER 17, 1995, IT WAS DISCOVERED THAT OMRON RELAYS INSTALLED IN UNIT | | 1'S VITAL UNINTERRUPTIBLE POWER SOURCES (UPS) WERE NOT TESTED AND VERIFIED | | TO BE SEISMICALLY QUALIFIED. THE UPSs WERE RECEIVED FROM THE VENDOR IN THIS | | CONFIGURATION AND INSTALLED DURING THE UNIT'S SIXTH REFUELING OUTAGE IN | | MARCH OF 1994. DURING A DESIGN BASIS SEISMIC EVENT CONCURRENT WITH A LOSS | | OF OFFSITE POWER EVENT, THE OMRON RELAYS COULD HAVE CHATTERED. THE RELAY | | CHATTER COULD HAVE CAUSED THE STATIC SWITCH OF THE UPS TO TRANSFER TO A | | DEAD BYPASS POWER SOURCE FOR APPROXIMATELY 10 SECONDS UNTIL THE EMERGENCY | | DIESEL GENERATORS LOAD AND THE BYPASS SOURCE IS RE-ENERGIZED. THIS | | CONDITION WOULD RESULT IN A LOSS OF POWER TO THE 120-VOLT VITAL INSTRUMENT | | AC BUSSES. THE VITAL UPS AND THE VITAL INSTRUMENT AC SYSTEM PROVIDES | | UNINTERRUPTIBLE, REGULATED, 120-VOLT, AC POWER TO NUCLEAR SAFEGUARD | | FUNCTIONS, REACTOR PROTECTION ACTUATION, CONTROL INDICATION, AND OTHER | | SAFETY-RELATED SYSTEMS. | | | | ALL FOUR UNIT 2 VITAL UPSs HAVE BEEN INSPECTED TO CONFIRM THAT SEISMICALLY | | QUALIFIED RELAYS WERE INSTALLED. IN ADDITION, SEISMICALLY QUALIFIED RELAYS | | HAVE BEEN INSTALLED IN ALL OF UNIT 1'S UPSs. | | | | ON OCTOBER 24, 1995, THE LICENSEE DETERMINED THAT THIS WAS A CONDITION THAT | | ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF THE | | SAFETY SYSTEMS THAT ARE NEEDED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29503 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/25/95 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 02:13 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/24/95 | +------------------------------------------------+EVENT TIME: 23:17[CDT]| |NRC NOTIFIED BY: JIM BOYLE |LAST UPDATE DATE: 10/25/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ISOLATION DUE TO A FAILED | | TEMPERATURE SWITCH | | | | THE LICENSEE REPLACED TEMPERATURE SWITCH E31K605F (A RILEY TRIP UNIT) FOR | | THE DIVISION 2 RCIC ISOLATION LOGIC WHILE THE RCIC SYSTEM WAS IN ITS | | STANDBY CONFIGURATION, AND THE NEW TEMPERATURE SWITCH FAILED FOLLOWING | | INSTALLATION. (THIS SWITCH IS PART OF THE LEAK DETECTION LOGIC, AND IT | | SENSES MAIN STEAM LINE DIFFERENTIAL TEMPERATURE.) THE FAILURE OF THE NEW | | SWITCH CAUSED AN ISOLATION OF THE RCIC SYSTEM IN THAT A CONTAINMENT | | ISOLATION VALVE (E51MOV63) IN THE RCIC STEAM SUPPLY LINE AND THE TRIP | | THROTTLE VALVE (E51MOVCOO2) BOTH CLOSED. ALL SYSTEMS FUNCTIONED AS | | REQUIRED. | | | | REPAIRS ARE CURRENTLY IN EFFECT TO REPLACE THE FAILED TEMPERATURE SWITCH. | | THE HIGH PRESSURE CORE SPRAY SYSTEM IS CURRENTLY AVAILABLE AND OPERABLE, | | AND ALL OF THE REMAINING EMERGENCY CORE COOLING SYSTEMS ARE IN THE STANDBY | | ALIGNMENT. THE LICENSEE HAS RESTORED THE RCIC SYSTEM TO ITS STANDBY | | CONFIGURATION, AND THE UNIT IS CURRENTLY IN A 24-HOUR LIMITING CONDITION | | FOR OPERATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29504 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 10/25/95 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 06:05 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/25/95 | +------------------------------------------------+EVENT TIME: 02:50[CDT]| |NRC NOTIFIED BY: DAMMANN |LAST UPDATE DATE: 10/25/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | NOTIFICATION OF OFFSITE AGENCIES OF A SMALL SPILL OF CHROMATED WATER | | | | DURING THE PERFORMANCE OF A HYDROSTATIC TEST OF THE D1 JACKET COOLING | | SYSTEM, AN EXPANSION TANK WAS NOT ISOLATED, AND THE TANK OVERFLOWED WHEN | | THE SYSTEM WAS PRESSURIZED. AS A RESULT, APPROXIMATELY 5 GALLONS OF | | CHROMATED WATER (562 PPM) SPILLED FROM THE D1 JACKET COOLING SYSTEM TO THE | | MISSISSIPPI RIVER VIA THE TURBINE BUILDING SUMP. THE SPILL HAS BEEN | | SECURED. | | | | THE LICENSEE NOTIFIED THE MINNESOTA STATE DUTY OFFICE DIVISION OF EMERGENCY | | MANAGEMENT, THE NATIONAL RESPONSE CENTER, AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+