U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/24/97 - 04/25/97 ** EVENT NUMBERS ** 32212 32213 32214 32215 32216 32217 32218 32219 32220 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32212 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/24/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:05 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/23/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:42[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/24/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS RDO | | DOCKET: 0707001 |JOHN HICKEY, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: MATT C. MAURER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACTUATION OF A 'Q' SAFETY SYSTEM DUE TO A VALID SIGNAL (OTHER NON-CFR | | REQUIREMENT REPORTED WITHIN 24 HOURS PER PLANT PROCEDURES.) | | | | AT 1542 CDT ON APRIL 23, 1997, THE WATER INVENTORY CONTROL SAFETY SYSTEM | | ACTUATED ON THE POSITION #1 AUTOCLAVE IN THE C-360 TOLL AND TRANSFER | | FACILITY. THE AUTOCLAVE HAD BEEN PLACED IN MODE 5 (HEATING) AT | | APPROXIMATELY 1445 CDT ON APRIL 23, 1997. THE ACTUATION OF THE WATER | | INVENTORY CONTROL SAFETY SYSTEM AUTOMATICALLY CLOSED STEAM SUPPLY VALVES | | XV-153 AND FV-105 AND THERMOSTATIC VENT VALVE XV-134 THUS LIMITING THE | | AMOUNT OF WATER IN THE AUTOCLAVE. THE ACTUATION WAS DETERMINED TO BE A | | VALID RESPONSE TO EXCESS WATER IN THE AUTOCLAVE. | | | | ALL SYSTEMS FUNCTIONED AS REQUIRED. THE AUTOCLAVE WAS DECLARED INOPERABLE | | AT 1648 CDT. AN ENGINEERING INVESTIGATION OF THE ACTUATION WAS INITIATED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32213 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/24/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 11:29 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 09:10[EDT]| |NRC NOTIFIED BY: MIKE EMPEY |LAST UPDATE DATE: 04/24/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |AL CHAFFEE, NRR EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO REACTOR SCRAM FROM 100% POWER DUE TO INADVERTENT SWITCH OPERATIONS - | | | | THE PLANT AUTOMATICALLY SCRAMMED FROM 100% POWER DUE TO INADVERTENT SWITCH | | OPERATIONS BY PERSONNEL (MOVING SWITCHES IN THE INCORRECT ORDER) DURING AN | | AVERAGE POWER RANGE MONITOR TECHNICAL SPECIFICATION SURVEILLANCE TEST. ALL | | CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER. PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 (TRAVERSING | | IN-CORE PROBE ISOLATION), GROUP 3 (CONTAINMENT AIR ISOLATION), AND GROUP 5 | | (REACTOR WATER CLEANUP SYSTEM ISOLATION) OCCURRED DUE TO LOW REACTOR VESSEL | | WATER LEVEL. REACTOR VESSEL WATER LEVEL RETURNED TO NORMAL LEVEL. THE | | PLANT IS STABLE IN A HOT SHUTDOWN CONDITION. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32214 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/24/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:10 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 12:01[EDT]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 04/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McFADDEN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN DUE TO TWO INOPERABLE EMERGENCY DIESEL GENERATORS (EDG) | | | | WHILE PERFORMING A MONTHLY EDG SURVEILLANCE, THE '22' EDG TRIPPED ON | | OVERSPEED. THE LICENSEE ENTERED A 7-DAY LIMITING CONDITION FOR OPERATION | | (LCO) AND BEGAN TESTING THE TWO OTHER EDGs ASSOCIATED WITH THE UNIT. AT | | 1123 EDT, A DC CONTROL POWER FUSE FOR THE '23' EDG BLEW, AND THE LICENSEE | | DETERMINED THAT A JACKET WATER PRESSURE SWITCH HAD FAILED. | | | | WITH TWO EDGs DECLARED INOPERABLE, THE LICENSEE ENTERED TECHNICAL | | SPECIFICATION 3.0.1, WHICH REQUIRES THAT THE UNIT BE PLACED IN HOT SHUTDOWN | | WITHIN 7 HOURS. AT 1207 EDT, THE LICENSEE COMMENCED A UNIT SHUTDOWN TO | | COMPLY WITH TECHNICAL SPECIFICATIONS. THE LICENSEE REPORTED THAT THE THIRD | | EDG HAS NOT YET BEEN TESTED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32215 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/24/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:47 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/23/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:45[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/24/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |PHILLIPS RDO | | DOCKET: 0707001 |COMBS, NMSS EO | +------------------------------------------------+CONGEL, AEOD IRD | |NRC NOTIFIED BY: CAGE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPRINKLER SYSTEM DEFICIENCIES IDENTIFIED DURING INSPECTIONS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE SUBMITTED BY PADUCAH: | | | | "ON 04/23/97, ADDITIONAL INSPECTIONS OF SPRINKLER SYSTEM PIPING SYSTEMS IN | | [THE] C-333 PROCESS BUILDING WERE CONDUCTED. THREE (3) SPRINKLER SYSTEMS | | (A-4, B-4, AND C-5) ON THE CELL FLOOR WERE FOUND TO HAVE DEFICIENCIES. | | DEFICIENCIES IDENTIFIED INCLUDED MISSING SPRINKLER HEADS, MISSING BRANCH | | LINES, PIPE HANGERS DISCONNECTED, HEADS INSTALLED AT IMPROPER ANGLES, AND | | HEADS INSTALLED TOO CLOSE TOGETHER. IN ADDITION, SEVEN (7) LOCATIONS IN | | C-333 WERE IDENTIFIED THAT REQUIRED SPRINKLER SYSTEMS; HOWEVER, NONE WERE | | INSTALLED. THESE LOCATIONS INCLUDED THE DISPLAY CELL OBSERVATION ROOM, | | DISPLAY CELL ENCLOSURE, TWO OFFICE-TYPE TRAILERS, AND AREAS BENEATH THREE | | EQUIPMENT ACCESS PLATFORMS WITH GRATING DECKS." | | | | "THESE DISCREPANCIES ARE IN ADDITION TO THE SPRINKLER SYSTEM DEFICIENCIES | | IDENTIFIED IN NRC EVENT NOTIFICATION WORK SHEETS 32148, 32162, AND 32170." | | | | "THE AFFECTED SYSTEMS WERE DECLARED INOPERABLE AND HOURLY FIRE PATROLS | | INITIATED AS REQUIRED BY TSR 2.4.4.5. AN INVESTIGATION AND FURTHER | | INSPECTIONS ARE ONGOING AT THIS TIME." | | | | "THE NRC SENIOR RESIDENT [INSPECTOR] HAS BEEN NOTIFIED OF THIS EVENT." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32216 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/24/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 14:03 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: VALLECORSA |LAST UPDATE DATE: 04/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McFADDEN RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |VERN HODGE, RVIB NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT REGARDING AUXILIARY FEEDWATER (AFW) CHECK VALVE | | FAILURE | | | | THE LICENSEE HAS IDENTIFIED THAT NOZZLE CHECK VALVES MANUFACTURED BY | | ENERTECH AND USED IN THE AFW SYSTEM MAY BE SUSCEPTIBLE TO A FAILURE IN | | WHICH THE SEATING RING CAN BECOME LOOSENED AND BE SWEPT INTO THE FLOW | | STREAM. THIS COULD CAUSE A PARTIAL BLOCKAGE AND POTENTIALLY PREVENT THE AFW | | SYSTEM FROM PERFORMING ITS INTENDED FUNCTION. | | | | THE PHENOMENON DESCRIBED IS ONE IN WHICH THE HOT VALVE BODY AND SEAT | | EXPERIENCE DIFFERENT RATES OF THERMAL CONTRACTION DUE TO THE FLOW OF COOL | | AUXILIARY FEEDWATER CAUSING THE SEATING RING TO SHRINK TO THE POINT THAT | | THERE IS NO LONGER AN INTERFERENCE FIT BETWEEN THE RING AND THE VALVE BODY. | | THE RING COULD THEN BE SWEPT INTO THE FLOW STREAM. | | | | THE LICENSEE REPORTED THAT ENERTECH HAS BEEN NOTIFIED OF THIS PHENOMENON | | AND HAS MODIFIED THE VALVES AT BEAVER VALLEY TO PREVENT THIS CONDITION IN | | THE FUTURE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32217 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ARMY (ROCK ISLAND ILLINOIS) |NOTIFICATION DATE: 04/24/97 | | CITY: ROCK ISLAND REGION: 3 |NOTIFICATION TIME: 15:08 [ET]| | COUNTY: STATE: IL |EVENT DATE: 04/24/97 | |LICENSE#: 12-00722-06 AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 04/24/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PHILLIPS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MOHS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | |IBAC 30.50(b)(1)(i) ACCESS DENIED >24 HRS | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SEVERAL REPORTS RECEIVED BY THE RADIOISOTOPE COMMITTEE TODAY | | | | ABERDEEN PROVING GROUNDS, MD (DISCOVERED 1500 04/23/97): FOUR VIALS (EACH | | CONTAINING 0.075 Ci OF TRITIUM) WERE DISCOVERED BROKEN IN A BUCKET INSIDE A | | MAINTENANCE SHED ALONG WITH A NUMBER OF UNBROKEN ONES. THESE ITEMS WERE | | DISCOVERED AS PART OF A FOLLOWUP INVESTIGATION OF A PREVIOUS EVENT (REFER | | TO EVENT #32157). THE BUILDING HAS BEEN SEALED OFF, AND AN INVESTIGATION | | CONTINUES. | | | | FT. RILEY, KS: ONE M43A1 CHEMICAL AGENT DETECTOR (CONTAINING 250 mCi OF | | Am-241) HAS BEEN MISSING SINCE THE GULF WAR (1991). ITS LOCATION IS | | UNKNOWN. | | | | FT. DEVONS, MA: FOUR COLLIMATORS, USED WITH M-191 HOWITZERS, ARE MISSING. | | THE GUNS AND ASSOCIATED ITEMS WERE RECEIVED BY THE MASSACHUSETTS NATIONAL | | GUARD UNIT STATIONED AT FT. DEVONS APPROXIMATELY TWO YEARS AGO. A RECENT | | INSPECTION OF SEALED SHIPPING CRATES CONTAINING ITEMS FOR THE GUNS REVEALED | | THAT THE COLLIMATORS (EACH CONTAINING 10 Ci OF TRITIUM) WERE PROBABLY NOT | | RECEIVED AT THE BASE. AN INVESTIGATION IS CONTINUING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32218 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 04/24/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 16:46 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: ALTHERHOLT |LAST UPDATE DATE: 04/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCFADDEN 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 +------------------------------------------------------------------------------+ | REACTOR BUILDING COOLING FANS COULD HAVE BEEN DISABLED DUE TO ENVIRONMENTAL | | QUALIFICATION (EQ) CONCERNS. | | | | THE LICENSEE HAS DECLARED TWO OF THE THREE REACTOR BUILDING COOLING FANS | | INOPERABLE DUE TO AN IMPROPER RAYCHEM SPLICE ON THE FAN MOTORS. SOME TIME | | AGO, ONE OF THE FAN MOTORS WAS DISCOVERED TO HAVE AN IMPROPER SPLICE ON THE | | ELECTRICAL CONDUCTOR TO THE MOTOR. (APPROXIMATELY 1/4 TO 1/2 INCH OF | | CONDUCTOR WAS EXPOSED AT THE POINT WHERE THE CONDUCTOR CONNECTS TO THE | | MOTOR.) THIS SPLICE WAS REPLACED WITH ONE WHICH COVERS THE ENTIRE | | CONDUCTOR, BUT WORK ORDERS WERE NOT WRITTEN TO INSPECT THE OTHER TWO FAN | | MOTORS AT THAT TIME. THE LICENSEE STATED THAT, IN THE PAST, ALL THREE FANS | | WOULD HAVE FAILED TO MEET EQ REQUIREMENTS MAKING THIS CONDITION REPORTABLE | | UNDER 10 CFR 50.72(b)(2)(iii)(D). | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32219 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/24/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:08 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: PRZEKOP |LAST UPDATE DATE: 04/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCFADDEN 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 +------------------------------------------------------------------------------+ | INSUFFICIENT SEPARATION OF SAFETY AND NONSAFETY ELECTRICAL CIRCUITRY | | | | THE LICENSEE REPORTED THAT INADEQUATE SEPARATION OF 'KEYWAY' AND | | 'NON-KEYWAY' CIRCUITRY COULD CAUSE FAILURES OF THE GAS TURBINE, EMERGENCY | | DIESEL GENERATOR, AND FEEDWATER COOLANT INJECTION SYSTEM. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | HOO NOTE: REFER TO AEOD/92-02, INSIGHTS FROM COMMON MODE FAILURE EVENTS, | | AND TO AEOD/92-02, SUPPLEMENT 1, INSIGHTS FROM COMMON MODE | | FAILURE EVENTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32220 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/24/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 20:14 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/24/97 | +------------------------------------------------+EVENT TIME: 18:17[CDT]| |NRC NOTIFIED BY: BENNETT |LAST UPDATE DATE: 04/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BELISLE RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION DUE TO | | CLOSURE OF THE MAIN STEAM ISOLATION VALVES (MSIV) | | | | AT 1814 CDT, THE UNIT SCRAMMED FROM 100% POWER WHEN ALL MSIVs WENT CLOSED. | | ALL CONTROL RODS INSERTED, AND ONE SAFETY/RELIEF VALVE (SRV) AUTOMATICALLY | | LIFTED TO CONTROL REACTOR PRESSURE. OPERATORS MANUALLY INITIATED REACTOR | | CORE ISOLATION COOLING (RCIC) DUE TO LEVEL SHRINKAGE CAUSED BY THE MSIV | | CLOSURE, AND HIGH PRESSURE COOLANT INJECTION (HPCI) AUTOMATICALLY STARTED | | IN RESPONSE TO LOW REACTOR VESSEL WATER LEVEL AT 1817 CDT. OPERATORS | | CONTINUED TO CYCLE THE OTHER 11 SRVs TO CONTROL REACTOR PRESSURE AND | | MINIMIZE LOCAL HEATING OF THE SUPPRESSION POOL. HPCI HAS BEEN SECURED, AND | | RCIC IS BEING USED TO CONTROL REACTOR VESSEL LEVEL. THE UNIT IS CURRENTLY | | STABLE IN HOT SHUTDOWN. | | | | THE LICENSEE STATED THAT THE CAUSE OF THE MSIV CLOSURE IS UNKNOWN. A | | SURVEILLANCE TEST WAS BEING PERFORMED AT THE TIME OF THE EVENT, BUT IT WAS | | UNRELATED TO THE MSIV LOGIC. THE LICENSEE PLANS TO INVESTIGATE THE CAUSE OF | | THE EVENT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+