U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/23/98 - 07/24/98 ** EVENT NUMBERS ** 34448 34567 34568 34569 34570 34571 34572 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34448 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 06/29/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 00:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/28/98 | +------------------------------------------------+EVENT TIME: 20:00[CDT]| |NRC NOTIFIED BY: HOLMES |LAST UPDATE DATE: 07/23/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 +------------------------------------------------------------------------------+ | HIGH PRESSURE SAFETY INJECTION (HPCI) WAS DECLARED INOPERABLE DUE TO | | SPIKING FLOW CONTROLLER | | | | WHILE PERFORMING PANEL TOURS, THE CONTROL ROOM OPERATOR NOTED THAT THE | | DEVIATION METER AND OUTPUT METER ON THE HPCI FLOW CONTROLLER WERE | | OSCILLATING. BASED ON THE POTENTIAL FOR THIS CONDITION TO IMPACT THE SPEED | | AND FLOW OF THE HPCI PUMP, HPCI WAS DECLARED INOPERABLE AT 2000 CDT. THE | | AUTOMATIC DEPRESSURIZATION SYSTEM HAS BEEN DEMONSTRATED TO BE OPERABLE; AND | | REACTOR CORE ISOLATION COOLING, LOW PRESSURE COOLANT INJECTION, AND CORE | | SPRAY WERE VERIFIED OPERABLE AS REQUIRED BY TECHNICAL SPECIFICATION | | 4.5.C.2. THIS PLACES THE PLANT IN A 7-DAY ACTION STATEMENT TO REPAIR OR | | SHUT DOWN. PRELIMINARY TROUBLESHOOTING BY INSTRUMENTATION AND CONTROL | | PERSONNEL INDICATES THE PROBLEM IS WITH THE FLOW METER CONTROLLER. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | | | | * * * UPDATE AT 1555 EDT ON 07/23/98 FROM BART CROW TO S.SANDIN * * * | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "EVENT NUMBER 34448 REPORTED A CONDITION AT COOPER NUCLEAR STATION (CNS) | | WHERE, WHILE THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM WAS IN A | | STANDBY MODE, IT WAS NOTED THAT THE DEVIATION METER AND THE OUTPUT METER ON | | THE HPCI FLOW CONTROLLER WERE OSCILLATING. BASED ON THE POTENTIAL FOR THIS | | CONDITION TO IMPACT THE SPEED AND FLOW OF THE HPCI PUMP, THE HPCI SYSTEM | | WAS DECLARED INOPERABLE. SUBSEQUENT INVESTIGATIONS DETERMINED THAT THE | | CAUSE OF THESE OSCILLATIONS WAS DUE TO TWO LEAKING CAPACITORS IN THE OUTPUT | | CIRCUIT OF THE FLOW CONTROLLER, AND THE FLOW CONTROLLER WAS REPLACED WITH A | | SPARE FLOW CONTROLLER. THE FUNCTION OF THESE CAPACITORS IS TO REMOVE AC | | RIPPLE FROM THE DC OUTPUT, AND ALTHOUGH THESE CAPACITORS WERE DEGRADED, | | THEY HAD NOT FAILED. THE LEAKAGE FROM THE CAPACITORS WOULD HAVE HAD THE | | EFFECT OF ADDING A SMALL AC RIPPLE ON TOP OF THE DC OUTPUT SIGNAL." | | | | "ANY NOISE GENERATED BY THE AC SUPPLY WOULD BE EITHER 60 OR 120 Hz. A | | DISCUSSION WITH THE REPRESENTATIVE FROM THE HPCI VENDOR INDICATED ANY NOISE | | ABOVE 20 Hz WOULD HAVE BEEN FILTERED OUT BY THE RAMP GOVERNOR SIGNAL | | CONVERTER (RGSC). THE FUNCTION OF THE RGSC IS TO CONVERT THE INPUT FROM | | THE HPCI CONTROLLER TO A LOW VOLTAGE DC TO THE EGM CONTROLLER (ELECTRONIC | | SPEED CONTROL) WHICH IN TURN CONVERTS THE DC SIGNAL TO A HYDRAULIC SIGNAL | | TO CONTROL THE HPCI GOVERNOR CONTROL VALVE. THUS, HAD HPCI OPERATION BEEN | | REQUIRED IN AN EMERGENCY, THE RGSC WOULD HAVE REMOVED ANY OSCILLATIONS FROM | | THE FLOW CONTROLLER SIGNAL, AND THE HPCI SYSTEM WOULD HAVE FULFILLED ITS | | REQUIRED SAFETY FUNCTION OF SUPPLYING 4,250 GPM OF COOLING WATER TO THE | | REACTOR VESSEL." | | | | "THUS, THE HPCI SYSTEM WAS NOT INOPERABLE, AND THIS EVENT IS NOT REPORTABLE | | UNDER [10 CFR] 50.72(b)(2)(iii) CRITERIA." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R4DO (TAPIA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34567 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/23/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:39 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/22/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/23/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GEOFFREY WRIGHT RDO | | DOCKET: 0707002 |JOSIE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 RESPONSE - DEFICIENT VOLUME IN A NUCLEAR CRITICALITY | | SAFETY APPROVAL (NCSA) PROCEDURE BECAUSE IT DOES NOT ADEQUATELY COVER THE | | HETEROGENEOUS CONFIGURATION (24-HOUR REPORT) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH | | PERSONNEL: | | | | "AT 1400 HOURS, ENGINEERING [PERSONNEL] DISCOVERED THAT [PROCEDURE] | | NCSA-PLANT048.A03 IS NON-CONSERVATIVE WITH RESPECT TO THE TOTAL VOLUME | | PERMITTED TO BE BATCHED TOGETHER IN AN UNFAVORABLE GEOMETRY CONTAINER. | | [PROCEDURE] NCSA-PLANT048.A03 PERMITS THE BATCHING OF UP TO 1 GALLON OF | | TOTAL HIDDEN VOLUME INTO AN UNFAVORABLE GEOMETRY CONTAINER. CONSIDERED AS | | A SINGLE UNIT, 1 GALLON IS A SAFE VOLUME FROM A CRITICALITY STANDPOINT. | | HOWEVER, UNDER CERTAIN SPECIFIC CONDITIONS WHERE THE 1 GALLON IS ARRANGED | | AS A REGULAR HETEROGENEOUS LATTICE WITH INTERSTITIAL MODERATION AND 100% | | ENRICHED MATERIAL, 1 GALLON IS NOT A SAFE VOLUME. THIS WAS NOT ADEQUATELY | | ANALYZED IN THE NCSA. HANDBOOK LA-10860 INDICATES THAT THE SAFE VOLUME | | UNDER HETEROGENEOUS CONDITIONS AT 100% ENRICHMENT IS SLIGHTLY ABOVE 1 | | LITER. AT 10% ENRICHMENT, [HANDBOOK] LA-10860 INDICATES THAT THE | | HETEROGENEOUS SAFE VOLUME IS APPROXIMATELY 8 LITERS (ABOVE 2 GALLONS). FOR | | THE NORMAL ENRICHMENTS OF MATERIAL ENCOUNTERED IN [UNITED STATED ENRICHMENT | | CORPORATION (USEC)] SPACE, THE NCSA CONTROL IS ADEQUATE AT 1 GALLON." | | | | "SAFETY SIGNIFICANCE OF EVENTS: THE SAFETY SIGNIFICANCE OF THIS EVENT IS | | LOW. EVEN THOUGH THE NCSA DID NOT ADEQUATELY CONTROL THE BATCHING OF | | CONTAMINATED METAL BY VOLUME, THERE ARE SEVERAL UNLIKELY CONDITIONS THAT | | WOULD HAVE BEEN NECESSARY FOR A CRITICALITY TO OCCUR. FIRST, THE | | ENRICHMENT WOULD HAVE TO BE ABOVE APPROXIMATELY 20% BEFORE A HETEROGENEOUS | | 1-GALLON VOLUME COULD BE MADE CRITICAL (SEE HANDBOOK LA-10860, FIGURE 23). | | [LOCKHEED MARTIN UTILITY SYSTEM (LMUS)] OPERATIONS INVOLVING MATERIAL ABOVE | | 20% ENRICHMENT ARE STRICTLY LIMITED BY THE FUNDAMENTAL NUCLEAR MATERIALS | | CONTROL PLAN TO LESS THAN 1,000 GRAMS U-235 TOTAL. SECOND, IN ORDER FOR A | | HETEROGENEOUS DISTRIBUTION OF HIDDEN VOLUMES UP TO A TOTAL OF 1 GALLON TO | | ACHIEVE CRITICALITY, A REGULAR PITCHED LATTICE WOULD HAVE TO BE CREATED AND | | ARRANGED IN A LOW LEAKAGE GEOMETRY (SIMILAR TO A REACTOR FUEL BUNDLE) AND | | MODERATED INTERSTITIALLY. IT IS UNLIKELY THAT ANY RANDOMLY CREATED BATCH | | OF CONTAMINATED METAL WOULD HAVE THE REGULAR GEOMETRY NECESSARY FOR A | | CRITICALITY TO OCCUR. IN ADDITION, THE PRESENCE OF MODERATOR IS CONTROLLED | | AND LIMITED UNDER PLANT048, SO THE CONDITION OF INTERSTITIAL MODERATION | | COULD NOT DEVELOP WITHOUT AN ADDITIONAL LOSS OF CONTROL." | | | | "POTENTIAL CRITICALITY PATHWAYS INVOLVED...: CRITICALITY COULD ONLY OCCUR | | IF THERE [WAS] GREATER THAN A SAFE MASS OF [HIGH ENRICHED URANIUM] MATERIAL | | INVOLVED, ARRANGED IN A LATTICE, AND MODERATED." | | | | "CONTROLLED PARAMETERS...: VOLUME - LIMITED IN THE NCSA TO 1 GALLON TOTAL | | HIDDEN VOLUME. MODERATION - NO FREE LIQUIDS [ARE] PERMITTED TO BE | | INTRODUCED IN [A] CONTAINER." | | | | "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL...: ENRICHMENT - | | UP TO 100% [IS] PERMITTED BY [THE] NCSA. MASS - UP TO 18.6 KG U-235 COULD | | BE PRESENT IN 1 GALLON OF UO2F2 AT 100% ENRICHMENT." | | | | "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DISCREPANCIES: VOLUME CONTROL IN [THE] NCSA (1 GALLON | | TOTAL HIDDEN VOLUME) IS DEFICIENT BECAUSE IT DOES NOT ADEQUATELY COVER THE | | HETEROGENEOUS CONFIGURATION." | | | | "CORRECTIVE ACTIONS...: [PROCEDURE] NCSA-PLANT048 NEEDS TO BE REVISED. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT | | OF ENERGY SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34568 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NUCLEAR FUEL SERVICES INC. |NOTIFICATION DATE: 07/23/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 09:18 [ET]| |COMMENTS: HEU CONVERSION & SCRAP RECOVERY |EVENT DATE: 07/22/98 | | NAVAL REACTOR FUEL CYCLE |EVENT TIME: 13:30[EDT]| | LEU SCRAP RECOVERY |LAST UPDATE DATE: 07/23/98 | | CITY: ERWIN REGION: 2 +-----------------------------+ | COUNTY: UNICOI STATE: TN |PERSON ORGANIZATION| |LICENSE#: SNM-124 AGREEMENT: Y |MARK LESSER RDO | | DOCKET: 07000143 |JOSIE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: COLMAN WOODHALL | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |KBCA 70.50(b)(3) MED TREAT INVOLV CONT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAMINATED INJURED MAN TRANSPORTED OFFSITE FOR MEDICAL TREATMENT | | | | A CONTRACT EMPLOYEE SUSTAINED FRACTURES TO AN ARM AND LEG WHEN HE WAS | | INJURED WHILE REPAIRING A FORK LIFT. THE INDIVIDUAL'S PANTS AND BOOTS HAD | | UP TO 1,200 DPM/100 CMý ALPHA CONTAMINATION, BUT THE INDIVIDUAL HAD NO | | DETECTABLE CONTAMINATION ON HIS BODY. THE INDIVIDUAL WAS TRANSPORTED TO THE | | JOHNSON CITY MEDICAL CENTER FOR TREATMENT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34569 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 07/23/98 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/23/98 | +------------------------------------------------+EVENT TIME: 10:30[EDT]| |NRC NOTIFIED BY: DONALD F. PENDAGAST |LAST UPDATE DATE: 07/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES 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 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE STATE OF MAINE THAT SOUND LEVELS WERE BEING | | EXCEEDED AT THREE LOCATIONS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "IN MAY OF 1998, MAINE YANKEE PLACED A NEW SPENT FUEL POOL COOLING SYSTEM | | IN SERVICE. THIS NEW SYSTEM INCLUDES SIX OUTDOOR COOLING FAN UNITS. THE | | ORIGINAL SPENT FUEL POOL COOLING SYSTEM USED RIVER WATER TO COOL A | | COMPONENT COOLING SYSTEM, WHICH COOLED THE SPENT FUEL POOL VIA A HEAT | | EXCHANGER. WHEN THE SIX FAN UNITS WERE STARTED, THE NOISE LEVEL WAS MUCH | | HIGHER THAN EXPECTED. THIS WEEK THE MAINE DEPARTMENT OF ENVIRONMENTAL | | PROTECTION (MDEP), REQUESTED MAINE YANKEE TO PERFORM NOISE MONITORING TO | | VERIFY COMPLIANCE WITH STATE LAWS. AT 1030 EDT ON THURSDAY, JULY 23, 1998, | | THE MDEP WAS NOTIFIED THAT THE NIGHT TIME RESIDENTIAL NOISE LIMITS ARE | | BEING EXCEEDED AT THREE LOCATIONS. [THE] STANDARD IS LESS THAN 45 dBa. | | MEASURED LEVELS AT THE THREE LOCATIONS WERE 48-52 dBa." | | | | "MAINE YANKEE IS IN THE PROCESS OF REMOVING THE ROOF OVER THE FANS AND | | ADDING SOUND BARRIERS AROUND THE FANS TO DAMPEN THE NOISE LEVELS." | | | | "MAINE YANKEE IS CURRENTLY SHUTDOWN AND DEFUELED WHILE PLANS ARE BEING MADE | | FOR DECOMMISSIONING." | | | | "THE FOLLOW-UP ACTIONS WILL INCLUDE REPLACING THE FAN BLADES AND MOTORS. | | THE FAN BLADE PITCH WILL BE CHANGED[, AND THE] MOTOR SPEED REDUCED TO | | REDUCE OVERALL NOISE LEVELS WHILE MAINTAINING THE ABILITY TO COOL THE SPENT | | FUEL POOL." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34570 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 07/23/98 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 15:35 [ET]| |RX TYPE: [3] CE |EVENT DATE: 07/23/98 | +------------------------------------------------+EVENT TIME: 13:39[CDT]| |NRC NOTIFIED BY: GREG SCOTT |LAST UPDATE DATE: 07/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 1-HOUR SECURITY REPORT INVOLVING THE SITE SECURITY PLAN | | | | THERE WAS A DISCOVERY OF A COMPROMISE OF SAFEGUARDS INFORMATION. IMMEDIATE | | COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. (REFER TO THE HOO LOG FOR | | DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34571 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 07/23/98 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 18:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/23/98 | +------------------------------------------------+EVENT TIME: 17:23[EDT]| |NRC NOTIFIED BY: JACK BRISSON |LAST UPDATE DATE: 07/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNITS ENTERED TECHNICAL SPECIFICATION 3.0.3 DUE TO MULTIPLE INOPERABLE | | REFUELING WATER STORAGE TANK (FWST) LEVEL INDICATORS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING [A] STORM EVENT WITH SEVERAL LIGHTNING STRIKES, FWST LEVEL CHANNELS | | (TWO ON EACH UNIT) FAILED PLACING THE UNITS IN [TECHNICAL SPECIFICATION] | | 3.0.3. PER [TECHNICAL] SPECIFICATIONS FOUR TOTAL CHANNELS ARE REQUIRED, | | BUT ONE CHANNEL CAN BE INOPERABLE IF PLACED IN BYPASS." | | | | "ON UNIT 1, CHANNELS 2 AND 4 FAILED. CHANNEL 2 SUBSEQUENTLY RETURNED | | WITHIN RANGE BUT IS BEING CONSIDERED INOPERABLE PENDING EVALUATION. | | CHANNEL 4 IS CURRENTLY FAILED LOW." | | | | "ON UNIT 2, BOTH CHANNELS 1 AND 3 ARE FAILED TO HIGH SCALE." | | | | "THESE CHANNELS ARE REQUIRED FOR CONTAINMENT SUMP SWAPOVER ON LOW LEVEL | | WITH SAFETY INJECTION." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34572 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 07/23/98 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 19:34 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 07/23/98 | +------------------------------------------------+EVENT TIME: 18:20[EDT]| |NRC NOTIFIED BY: KEVIN UMPHREY |LAST UPDATE DATE: 07/23/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE MANUALLY TRIPPED THE UNIT 2 REACTOR FROM 100% POWER FOLLOWING | | A STEAM LINE BREAK IN THE TURBINE BUILDING. | | | | AT 1820 EDT ON 07/23/98, UNIT 2 WAS MANUALLY TRIPPED FROM 100% POWER AFTER | | IDENTIFYING THAT A RUPTURED 2" VENT TO A FEEDWATER HEATER STEAM LINE (MOST | | LIKELY ASSOCIATED WITH MOISTURE SEPARATOR REHEATER #22) COULD NOT BE | | ISOLATED. NO PERSONNEL WERE INJURED. ALL CONTROL RODS FULLY INSERTED | | FOLLOWING THE TRIP. OPERATORS MANUALLY INITIATED BOTH TURBINE-DRIVEN | | AUXILIARY FEEDWATER (AFW) PUMPS TO RESTORE AND MAINTAIN STEAM GENERATOR | | WATER LEVELS. NO PRIMARY OR SECONDARY SAFETY VALVES OR POWER-OPERATED | | RELIEF VALVES LIFTED DURING THE TRANSIENT. | | | | APPROXIMATELY 19 MINUTES FOLLOWING THE TRIP, THE MAIN STEAM ISOLATION | | VALVES (MSIV) WERE CLOSED BASED ON OPERATOR JUDGMENT. UNIT 2 IS CURRENTLY | | STABLE IN MODE 3 REMOVING DECAY HEAT VIA THE ATMOSPHERIC DUMPS WITH AFW IN | | SERVICE TO BOTH STEAM GENERATORS. OPERATORS HAVE PLACED THE MSIV BYPASSES | | IN SERVICE IN PREPARATION FOR REOPENING THE MSIVs. ONCE THE MSIVs ARE | | REOPENED, DECAY HEAT WILL BE REJECTED TO THE MAIN CONDENSER. CHEMISTRY | | CALCULATED (PRIOR TO THIS EVENT) PRIMARY-SECONDARY TUBE LEAKAGE AS 0.51 GPD | | (07/14/98). THERE ARE NO MAIN STEAM RADIATION ALARMS PRESENT WITH THE | | ATMOSPHERIC DUMPS IN SERVICE. ALL EMERGENCY CORE COOLING SYSTEM EQUIPMENT | | INCLUDING EMERGENCY DIESEL GENERATORS IS AVAILABLE. NO GRID INSTABILITY OR | | ELECTRICAL TRANSIENTS WERE OBSERVED. THE LICENSEE ANTICIPATES UNIT 2 | | RESTART IN APPROXIMATELY 36 HOURS AND, ALTHOUGH NOT PLANNED, BELIEVES THAT | | A PRESS RELEASE WILL BE MADE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+