U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/05/96 - 11/06/96 ** EVENT NUMBERS ** 31275 31276 31277 31278 31279 31280 31281 31282 31283 +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31275 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: TVA'S KINGSTON STEAM PLANT (SITI) |NOTIFICATION DATE: 11/05/96 | | CITY: KINGSTON REGION: 2 |NOTIFICATION TIME: 10:23 [ET]| | COUNTY: STATE: TN |EVENT DATE: 11/04/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 22:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/05/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |AL BELISLE RDO | | |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: STATE OF TENNESSEE | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RADIOGRAPHY SOURCE STOLEN | | | | * * * THIS EVENT WAS REPORTED TO REGION II AND THIS INFORMATION WAS RELAYED | | TO THE OPERATIONS CENTER * * * | | | | THIS EVENT OCCURRED AT TVA'S KINGSTON STEAM PLANT IN KINGSTON, TN. | | | | WORKERS OF SITI (THE LICENSEE) REPORTED THE LOSS OF A RADIOGRAPHY CAMERA | | CONTAINING A 67 Ci Ir-192 RADIOGRAPHY SOURCE. THE EXACT TIMES OF THIS | | EVENT WERE NOT REPORTED, BUT THE CAMERA WAS DISCOVERED MISSING ON THE NIGHT | | OF 11/4/96, AND RECOVERED ON THE MORNING OF 11/5/96. THE WORKERS LEFT THE | | CAMERA UNATTENDED FOR ABOUT FIVE MINUTES. UPON THEIR RETURN, THE CAMERA | | WAS GONE. | | | | THE CAMERA WAS FOUND WITH THE SOURCE STILL IN ITS SHIELDED AND LOCKED | | POSITION, AND THEREFORE THERE IS DOUBT THAT ANYONE RECEIVED A SIGNIFICANT | | EXPOSURE DUE TO THIS EVENT. THE STATE OF TENNESSEE IS STILL INVESTIGATING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31276 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: OMART |NOTIFICATION DATE: 11/05/96 | | CITY: CINCINNATI REGION: 3 |NOTIFICATION TIME: 12:53 [ET]| | COUNTY: HAMILTON STATE: OH |EVENT DATE: 11/05/96 | |LICENSE#: 34-00639-01 AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/05/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JORDAN RDO | | |WEBER EO | +------------------------------------------------+CONGEL IRD | |NRC NOTIFIED BY: KEN FELDMANN | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAD1 20.2202(a)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PERSONNEL CONTAMINATION EVENT | | | | THE LICENSEE REPORTED THAT RADIOACTIVE CONTAMINATION WAS DETECTED IN THE | | NOSE OF AN EMPLOYEE. THE INDIVIDUAL HAD BEEN HANDLING A 20-25 YEAR OLD | | Cs-137 "STRIP" SOURCE, WHICH IS APPARENTLY LEAKING. THE SOURCE HAD AN | | INITIAL ACTIVITY OF 2,000 mCi, BUT THE LICENSEE DID NOT KNOW THE CURRENT | | ACTIVITY. THE SOURCE IS CURRENTLY LOCKED IN THE LICENSEE'S SOURCE ROOM. | | | | THE LICENSEE MEASURED A CONTAMINATION OF 273 CPM (>100 CPM ABOVE | | BACKGROUND) IN THE INSIDE OF THE INDIVIDUAL'S NOSE. THE INDIVIDUAL IS | | CURRENTLY BEING DECONTAMINATED, AND THE LICENSEE HAS NOT YET ESTIMATED THE | | DOSE TO THIS INDIVIDUAL DUE TO THE CONTAMINATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31277 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 11/05/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 14:25 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 11/05/96 | +------------------------------------------------+EVENT TIME: 13:00[EST]| |NRC NOTIFIED BY: TERRY WHITE |LAST UPDATE DATE: 11/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CONTE 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SINGLE FAILURE COULD DISABLE BOTH PRESSURIZER PORVs | | | | "WHILE PERFORMING a REVIEW OF PSA ANALYSIS, IT WAS DETERMINED THAT A | | FAILURE OF ONE DC BUS COULD RENDER BOTH PRESSURIZER PORVs INOPERABLE IF ONE | | PORV BLOCK VALVE WAS CLOSED INITIALLY. DC CONTROL POWER TO ONE BLOCK VALVE | | AND TO THE OPPOSITE PORV NITROGEN SUPPLY VALVE IS SUPPLIED FROM ONE TRAIN | | OF DC POWER. ONLY PORV OPERATION VIA NITROGEN SUPPLY (LTOP) IS CREDITED IN | | THE ACCIDENT ANALYSIS; HOWEVER, OPERATION OF PORVs VIA THE INSTRUMENT AIR | | SUPPLY SHOULD NORMALLY BE AVAILABLE. THIS CONFIGURATION WOULD NOT MEET | | SINGLE FAILURE CRITERIA ASSUMING ONE PORV BLOCK VALVE CLOSED AT EVENT | | INITIATION." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31278 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 11/05/96 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 16:04 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/05/96 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: STRICKLAND |LAST UPDATE DATE: 11/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CONTE 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED EPA AND NHDES REGARDING UNUSUALLY LARGE FISH KILL | | | | THE LICENSEE NOTIFIED THE U.S. ENVIRONMENTAL PROTECTION AGENCY (EPA) AND | | THE NEW HAMPSHIRE DEPARTMENT OF ENVIRONMENTAL SERVICES (NHDES) REGARDING | | AN UNUSUALLY LARGE FISH IMPINGEMENT ON THE PLANT INTAKE STRUCTURE. | | APPROXIMATELY 2,000 HERRING (4-6" LONG) WERE REMOVED FROM THE INTAKE | | SCREENS DURING THE PERIOD FROM 11/1/96 TO 11/3/96. THIS IS APPROXIMATELY | | EIGHT TIMES THE NUMBER OF HERRING REMOVED FROM THE SCREEN DURING ALL OF | | 1995. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31279 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 11/05/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 16:59 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/05/96 | +------------------------------------------------+EVENT TIME: 16:07[EST]| |NRC NOTIFIED BY: WALSH |LAST UPDATE DATE: 11/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CONTE 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 75 POWER OPERATION | 75 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CLASS 1E 4160 VAC SWITCHGEAR NOT SEISMICALLY QUALIFIED WHEN BREAKERS ARE | | RACKED OUT. | | | | "AT 1607 ON 11/5/96, IT WAS IDENTIFIED THAT THE UNIT 1 AND UNIT 2 CLASS 1E | | 4.16 kV WESTINGHOUSE SWITCHGEAR IS NOT SEISMICALLY QUALIFIED WITH ANY | | BREAKERS RACKED OUT AND INSTALLED IN THE CUBICLE OR RACKED INTO THE 'TEST' | | POSITION. IN ADDITION, WHEN THE BREAKERS ARE RACKED OUT AND LEFT WITHIN THE | | CUBICLE, THE SWITCHGEAR IS NOT OPERABLE. IT IS NORMAL OPERATING PRACTICE OF | | THE PLANT TO HAVE BREAKERS IN THIS UNQUALIFIED POSITION DURING ALL | | OPERATING CONDITIONS. THIS REPRESENTS A CONDITION THAT IS OUTSIDE THE | | DESIGN BASIS OF THE PLANT AND THEREFORE REQUIRES A 1 HOUR NOTIFICATION PER | | 10 CFR 50.72(b)(1)(ii)(B). | | | | A TOTAL OF 7 BREAKERS ON BOTH UNITS WERE IDENTIFIED TO BE IN AN UNQUALIFIED | | POSITION. FIVE OF THE SEVEN BREAKERS WERE SPARE BREAKERS AND THE OTHER | | BREAKERS FED THE UNIT 2 MECHANICAL VACUUM PUMP AND THE UNIT 2 TURBINE | | BUILDING CHILLER. THESE BREAKERS WERE IMMEDIATELY PLACED IN THE RACKED IN | | POSITION. ALL INSTALLED 4.16 kV UNIT 1 AND UNIT 2 BREAKERS WERE | | INDEPENDENTLY VERIFIED TO BE FULLY RACKED IN." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 11/05/96 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 17:58 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/02/96 | +------------------------------------------------+EVENT TIME: 02:41[CST]| |NRC NOTIFIED BY: ZIMMERMAN |LAST UPDATE DATE: 11/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORDAN 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 +------------------------------------------------------------------------------+ | LPCI SWING BUS FAILED TO TRANSFER IN REQUIRED TIME DURING TEST. | | | | WHILE PERFORMING A TEST OF THE LOW PRESSURE COOLANT INJECTION (LPCI) SWING | | BUS, THE BUS FAILED TO TRANSFER TO ITS ALTERNATE FEEDER BUS WITHIN THE | | REQUIRE TIME PERIOD AFTER THE PRIMARY FEEDER BUS WAS DISCONNECTED. THE | | LICENSEE STATED THAT THE TRANSFER TOOK 5 MINUTES TO COMPLETE; HOWEVER, THIS | | TRANSFER NORMALLY TAKES 5 SECONDS. | | | | THE LICENSEE DETERMINED THAT AN UNDERVOLTAGE RELAY WAS NOT WORKING | | PROPERLY. THE RELAY WAS REPLACED, AND THE TEST WAS REPERFORMED | | SATISFACTORILY. THE LICENSEE IS CURRENTLY EXAMINING THE RELAY TO DETERMINE | | THE CAUSE OF THE FAILURE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY | | THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31281 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/05/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 22:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/05/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: ARMANDO |LAST UPDATE DATE: 11/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CONTE 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL RELAYS NOT SEISMICALLY QUALIFIED | | | | "BASED ON FOLLOWUP INVESTIGATION OF A 10 CFR PART 21 NOTIFICATION FROM THE | | PSE&G VENDOR FOR 28V AND 125V CONTROL RELAYS, IT WAS DETERMINED THAT THE | | SEISMIC ADEQUACY OF THESE RELAYS WAS IN QUESTION. THE ORIGINAL PART 21 | | NOTIFICATION WAS DUE TO THE LATCHING FEATURE OF THESE RELAYS RESETTING | | WITHOUT A RESET DEMAND. FURTHER INVESTIGATION REVEALED THAT THE RELAYS | | CURRENTLY BEING SUPPLIED BY THE VENDOR, WHEN TESTED IN A VERTICAL, FLOOR | | MOUNTED CONFIGURATION, FAILED TO MEET A SEISMIC QUALIFICATION. | | | | THIS TEST CONFIGURATION IS AS USED IN BAILEY RELAY CABINETS IN THE PLANT, | | WHICH ARE THE MAIN INTERFACING CONTROL MECHANISM BETWEEN THE CONTROL ROOM | | AND PLANT EQUIPMENT. ACTUAL EFFECTS OF THE RELAYS BECOMING UNLATCHED DURING | | PLANT OPERATION HAS NOT BEEN EVALUATED ON A CIRCUIT-BY-CIRCUIT BASIS. IN | | THE CURRENT PLANT CONFIGURATION, WITH BOTH UNITS DEFUELED, OPERATION WITH | | THESE RELAYS INSTALLED IS NOT EXPECTED TO POSE A SIGNIFICANT CHALLENGE TO | | MAINTAINING SPENT FUEL POOL COOLING. BOTH UNIT 1 AND UNIT 2 ARE DEFUELED, | | AND THIS ISSUE WILL BE RESOLVED PRIOR TO MODE CHANGE. | | | | PSE&G WILL WORK WITH THE VENDOR TO IDENTIFY THE AFFECTED RELAY BATCH | | NUMBERS, AND QUANTITY IN USE AT SALEM. AN EVALUATION OF THE ADEQUACY OF | | EXISTING TESTING AND A POTENTIAL DESIGN MODIFICATION IS IN PROGRESS, AS | | WELL AS AN EVALUATION TO DETERMINE IF THIS CONDITION EXISTED DURING | | PREVIOUS PLANT OPERATION." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31282 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/06/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 00:16 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/05/96 | +------------------------------------------------+EVENT TIME: 22:53[EST]| |NRC NOTIFIED BY: SAENCZAK |LAST UPDATE DATE: 11/06/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT HAD A REACTOR SCRAM FROM 100% POWER DUE TO A TURBINE TRIP. | | | | PRELIMINARY INVESTIGATION INDICATES THAT THE TURBINE TRIP MAY HAVE BEEN | | CAUSED BY A GENERATOR FIELD GROUND RELAY TRIP. UNIT 1 ALSO HAD A HPCI | | ACTUATION. THE PLANT ENTERED EOP-2 DUE TO REACTOR WATER LEVEL BEING <53" | | (WATER LEVEL DROPPED TO APPROXIMATELY 32"). EOP-2 WAS EXITED WHEN WATER | | LEVEL WAS RETURNED TO >53" AND HPCI WAS SECURED. ALL RODS FULLY INSERTED | | AND NO SAFETY RELIEF VALVES OPENED. THE MAIN CONDENSER IS THE HEAT SINK. | | THE CAUSE OF THE GENERATOR FIELD GROUND RELAY TRIP IS BEING INVESTIGATED. | | THE PLANT IS GOING TO COLD SHUTDOWN. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31283 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 11/06/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:05 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/06/96 | +------------------------------------------------+EVENT TIME: 03:00[CST]| |NRC NOTIFIED BY: HODEL |LAST UPDATE DATE: 11/06/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN 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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION WHERE THE SECONDARY CONTAINMENT MAY BE | | INOPERABLE IN MODES 1, 2, & 3 DUE TO INVALID TESTING. | | | | DURING SECONDARY CONTAINMENT INTEGRITY WALKDOWNS, THE LICENSEE NOTICED | | THAT RHR "A", "B" & "C" ROOM FLOOR DRAIN SUMP VENTS ARE CONNECTED TO THE | | AUXILIARY BUILDING EXHAUST VENTILATION SYSTEM SUCTION WITHOUT AN ISOLATION | | VALVE. AS A RESULT OF THIS CONDITION, FIELD MEASUREMENTS INDICATE THAT THE | | AUX BUILDING VENT SYSTEM IS PULLING AIR OUT OF THE RHR "A" ROOM. BASED ON | | THIS PRELIMINARY INFORMATION, ENGINEERING HAS CONSERVATIVELY ASSUMED THAT | | THE AUX BUILDING VENT SYSTEM HAS BEEN ASSISTING THE SECONDARY CONTAINMENT | | VENT SYSTEM IN MAINTAINING SECONDARY CONTAINMENT. THIS CONDITION COULD | | AFFECT THE SURVEILLANCE REQUIREMENTS FOR SECONDARY CONTAINMENT IF THE AUX | | BUILDING VENT SYSTEM ACTUALLY ASSISTS IN THE DRAW DOWN TEST, AND | | INVALIDATES THE TEST. THIS WOULD MAKE SECONDARY CONTAINMENT INOPERABLE IN | | MODES 1, 2 & 3. THIS ENGINEERING EVALUATION WAS ONLY PERFORMED ON RHR "A" | | VENTS, BUT RHR "B" & "C" VENTS WILL ALSO BE EVALUATED. IT APPEARS THAT THIS | | CONDITION HAS EXISTED SINCE THE PLANT WAS BUILT. CORRECTIVE MEASURES HAVE | | NOT YET BEEN DETERMINED. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+