U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/10/94 - 11/14/94 ** EVENT NUMBERS ** 27885 28012 28013 28014 28015 28016 28017 28018 28019 28020 28021 28022 28023 28024 28025 28026 28027 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27885 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/11/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/11/94 | +------------------------------------------------+EVENT TIME: 02:20[CDT]| |NRC NOTIFIED BY: PHILLIP SHORT |LAST UPDATE DATE: 11/10/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JEFF WRIGHT 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 89 POWER OPERATION | 89 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE WAS IN A REQUIRED TECH SPEC SHUTDOWN WHEN THEY ENTERED TECH SPEC | | 3.0.3. FOR CONTROL ROOM POSITIVE PRESSURE BEING OUT OF SPECIFICATION. | | LICENSEE EXITED TECH SPEC 3.0.3 AND TECH SPEC REQUIRE SHUTDOWN AT 0253CT. | | | | AT 0220CT IT WAS NOTED BY MAIN CONTROL ROOM PERSONNEL THAT THE CONTROL ROOM | | VENTILATION SYSTEM TRAIN "B" IN OPERATION WAS NOT MAINTAINING A POSITIVE | | PRESSURE OF 0.125" OF WATER AS REQUIRED PER TECH SPEC. A MAINTENANCE OUTAGE | | IS CURRENTLY IN PROGRESS FOR CONTROL ROOM VENTILATION TRAIN "A". THEREFORE, | | BOTH CONTROL ROOM VENTILATION TRAINS WERE DECLARED INOPERABLE AND TECH SPEC | | 3.0.3 WAS ENTERED. IT IS BELIEVED THAT THEY HAVE A TAGOUT PROBLEM WITH | | CONTROL ROOM VENTILATION TRAIN "A" AND THIS WAS CAUSING THE INABILITY OF | | TRAIN "B" NOT TO MAINTAIN A POSITIVE PRESSURE OF 0.125" OF WATER. | | ALL WORK ON TRAIN "A" WAS STOPPED AND LICENSEE IS TRYING TO FIND/CORRECT | | THE PROBLEM. | | AT 0253CT CONTROL ROOM VENTILATION TRAIN "B" WAS SHIFTED TO THE HIGH | | RADIATION MODE OF OPERATION (TECH SPEC 3.0.3 WAS EXITED AT THIS TIME) AND | | POSITIVE PRESSURE IS NOW 0.125" OF WATER. LICENSEE WILL LEAVE CONTROL ROOM | | VENTILATION TRAIN "B" IN THE HIGH RADIATION MODE OF OPERATION UNTIL PROBLEM | | IS CORRECTED. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | ** UPDATE DATE/TIME:11/10/94 @ 1154 ET FROM LICENSEE:MOTSEGOOD BY:McGINTY** | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION OF A T/S REQUIRED | | SHUTDOWN DUE TO BOTH TRAINS OF CONTROL ROOM VENTILATION BEING INOPERABLE. | | IT WAS SUBSEQUENTLY DETERMINED THAT THE "B" TRAIN WAS OPERABLE AT THE TIME | | OF THE EVENT. THE OPERATOR ACTION OF SWITCHING FROM THE NORMAL MODE TO THE | | HIGH RAD MODE INDICATED THAT THE ALLOWABLE CONTROL ROOM LEAK RATE WAS NOT | | EXCEEDED. THE SWITCH FROM THE NORMAL MODE TO THE HIGH RAD MODE ISOLATES A | | NORMAL MAKEUP FLOWPATH (APPROXIMATELY 2000 SCFM) AND INITIATES THE MAKEUP | | FILTER TRAIN SUPPLYING APPROXIMATELY 3000 SCFM. THE SUBSEQUENT INCREASE IN | | CONTROL ROOM PRESSURE DURING THE HIGH RAD MODE OF OPERATION INDICATES THAT | | THE CONTROL ROOM LEAKAGE RATE IS ACCEPTABLE. | | | | THE CALLER STATED THAT THE REQUIREMENT IS TO BE ABLE TO MAINTAIN POSITIVE | | PRESSURE (0.125" OF WATER) WITH 4000 SCFM OF SUPPLY AIR. BY SWITCHING TO | | THE HIGH RAD MODE, WHERE THE TOTAL SUPPLY IS 3000 SCFM, AND DEMONSTRATING | | THE ABILITY TO MAINTAIN POSITIVE PRESSURE, THEN THE LEAKAGE RATE CANNOT BE | | GREATER THAN 4000 SCFM. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. HOO | | NOTIFIED THE R3DO (JORDAN). | | | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28012 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 11/10/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:35 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 11/10/94 | +------------------------------------------------+EVENT TIME: 10:47[EST]| |NRC NOTIFIED BY: RHEA |LAST UPDATE DATE: 11/10/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GROUP 12 ISOLATION WHILE PUMPING FROM THE DRYWELL EQUIPMENT SUMP TO THE | | DRYWELL FLOOR DRAIN SUMP. | | | | A GROUP 12 (TORUS WATER MANAGEMENT SYSTEM) ISOLATION OF THE PCIS OCCURRED | | DUE TO A DRYWELL FLOOR DRAIN SUMP LEVEL "HI-HI" SIGNAL. AT THE TIME OF THE | | EVENT THE DRYWELL EQUIPMENT SUMP WAS BEING PUMPED TO THE DRYWELL FLOOR | | DRAIN SUMP, IN ORDER TO CLEAN THE DRYWELL EQUIPMENT SUMP. THE PCIS IS NOT | | REQUIRED TO BE OPERABLE IN COLD SHUTDOWN. THE CAUSE OF THE EVENT IS BEING | | INVESTIGATED. THE INITIAL INTERPRETATION OF THE DATA INDICATES THAT THE | | SIGNAL MAY HAVE COME IN AT A LOWER LEVEL THAN IT SHOULD HAVE. THE SETPOINT | | OF THE "HI-HI" SIGNAL IS 41", WHICH IN ADDITION TO THE GROUP 12 PROVIDES AN | | AUTOMATIC START OF BOTH DRYWELL SUMP PUMPS. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 28013 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMBUSTION ENGINEERING INC. |NOTIFICATION DATE: 11/10/94 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 14:54 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 11/09/94 | | COMMERCIAL LWR FUEL |EVENT TIME: 14:06[CST]| | |LAST UPDATE DATE: 11/10/94 | | CITY: HEMATITE REGION: 3 +-----------------------------+ | COUNTY: JEFFERSON STATE: MO |PERSON ORGANIZATION| |LICENSE#: SNM-33 AGREEMENT: N |MICHAEL J. JORDAN RDO | | DOCKET: 07000036 |WILLIAM BRACH EO | +------------------------------------------------+ | |NRC NOTIFIED BY: SHARKEY | | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BULLETIN 91-01 REPORT | | | | A 24 HOUR REPORT PER BULLETIN 91-01 (DEGRADED CRITICALITY SAFETY CONTROLS, | | SAFETY SIGNIFICANCE UNKNOWN) WAS RECEIVED FROM THE COMBUSTION ENGINEERING, | | HEMATITE NUCLEAR FUEL MANUFACTURING FACILITY, LOCATED IN JEFFERSON COUNTY, | | MO. | | | | THE PORTION OF THE PLANT AFFECTED IS THE ERBIA PELLET PRODUCTION PLANT. THE | | ERBIA PELLET AREA OF THE HEMATITE PLANT HAS BEEN IN PRODUCTION FOR | | APPROXIMATELY EIGHTEEN MONTHS. A LARGE UO2 BLENDER IN THE ERBIA PELLET | | AREA USES PLANT COMPRESSED AIR IN THE BLENDING PROCESS. NOMINAL LOT SIZE | | IN THE BLENDER IS 1000 kg. A DUAL-BANK ELECTRICAL DRYER AND A MOISTURE | | ALARM SERVE AS TWO BARRIERS TO THE INTRODUCTION OF MODERATOR INTO THE | | BLENDER VIA THE PLANT AIR SYSTEM. THE MOISTURE ALARM SETPOINT IS -30øF. | | | | DURING A REVIEW OF BLENDING OPERATIONS, IT WAS REALIZED THAT THE MOISTURE | | ALARM RESPONSE SET FORTH IN PLANT PROCEDURES DOES NOT ADEQUATELY ADDRESS | | THE BLENDER IN THE ERBIA AREA. NO RECORDS OF MOISTURE ALARMS ARE KEPT, AND | | IT CANNOT BE SAID WITH ANY CERTAINTY IF A MOISTURE ALARM HAS BEEN ACTIVATED | | AT THE OUTPUT OF THE DRYER SINCE THE ERBIA BLENDER HAS BEEN IN OPERATION. | | OCCASIONAL MOISTURE ALARMS HAVE BEEN NOTED AT THE END OF THE PLANT AIR | | SYSTEM, WHERE MOISTURE TENDS TO ACCUMULATE, BUT THIS HAS BEEN AT VERY LOW | | LEVELS. NO SIGNIFICANT AMOUNT OF MOISTURE HAS EVER BEEN FOUND IN THE PLANT | | AIR SYSTEM, NOR WOULD IT BE EXPECTED. | | | | THE ERBIA BLENDER WAS EMPTY AT THE TIME OF THE REVIEW. LOCK-AND-TAG WAS | | USED TO SECURE THE BLENDER WHICH WILL REMAIN OUT OF SERVICE UNTIL A REVIEW | | OF THE SYSTEM IS COMPLETED. THE LICENSEE NOTIFIED REGION 3. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28014 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/10/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/10/94 | +------------------------------------------------+EVENT TIME: 14:17[EST]| |NRC NOTIFIED BY: FAULKNER |LAST UPDATE DATE: 11/10/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | |HAASS RIVB | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ECCS ROOM COOLER COOLING WATER SUPPLY VALVES FAILED TO OPEN FOR UNKNOWN | | REASONS. | | | | WHILE TESTING THE SACS (SAFETY AUXILIARIES COOLING SYSTEM), LOOP AIR | | OPERATED GATE VALVES FOR QUARTERLY SURVEILLANCE, SEVERAL OF THE VALVES HAVE | | FAILED TO OPEN WHEN REQUIRED. THE SACS IS A "SAFETY RELATED COOLING WATER | | SYSTEM FOR ECCS PUMPS AND EDGs". THE LICENSEE HAS DISASSEMBLED AND | | INSPECTED THE VALVES AND HAS NOT FOUND ANY REASON FOR THE FAILURES. THIS | | REPORT IS BEING MADE DUE TO THE POSSIBLE GENERIC FAILURE OF THIS TYPE OF | | VALVE. | | | | HOPE CREEK HAS 32 OF THIS TYPE OF VALVE PACKAGE. THEY ARE HILLAR ACTUATOR, | | AIR POWERED GATE VALVES. THERE ARE THREE DIFFERENT TYPES OF HILLAR | | ACTUATOR MODEL #'s: | | 1) MODEL # 8-SA-A026, WITH A 3" ANCHOR-DARLING GATE VALVE | | 2) MODEL # 10-SA-A047, WITH A 4" ANCHOR-DARLING GATE VALVE | | 3) MODEL # 10-SA-A049, WITH A 6" ANCHOR-DARLING GATE VALVE | | | | THE LICENSEE IS CURRENTLY TESTING THE VALVES AT A WEEKLY INTERVAL (VICE 92 | | DAYS), AND HAS NOT EXPERIENCED ANY PROBLEMS SINCE INSTITUTING MORE FREQUENT | | TESTING. THE MOST RECENT FAILURE INVOLVED TWO VALVES ABOUT A WEEK AGO. | | HISTORICALLY, HOWEVER, THERE HAVE BEEN OTHER FAILURES THAT THEY HAVE NOT | | BEEN ABLE TO ATTRIBUTE TO A SPECIFIC MECHANICAL PROBLEM. THE LICENSEE IS | | WORKING WITH BOTH THE ACTUATOR AND VALVE MANUFACTURERS TO ATTEMPT TO | | IDENTIFY THE SOURCE OF THE PROBLEM. | | | | ALL OF THE VALVES ARE ON THE SAME COOLING WATER SYSTEM (SACS), PROVIDING | | FLOW TO THE ECCS EQUIPMENT ROOM COOLERS IN VARIOUS LOCATIONS (TWO COOLERS | | PER ECCS PUMP). BOTH VALVES TO BOTH COOLERS FOR A PARTICULAR ECCS PUMP | | WOULD HAVE TO FAIL TO AFFECT AN INDIVIDUAL ECCS PUMP, AND THERE IS | | PROCEDURAL GUIDANCE IN PLACE FOR OPERATOR ACTION ON HIGH ROOM TEMPERATURES. | | THE VALVES ARE NORMALLY CLOSED, AND FAIL SAFE (SPRING OPEN) WHEN THE | | SOLENOID IS DE-ENERGIZED. | | | | THE LICENSEE HAS NOT CURRENTLY DECLARED ANY ECCS EQUIPMENT INOPERABLE AT | | THIS TIME DUE TO THIS PROBLEM. THE PROBLEM SEEMS TO SHOW UP ONLY WHEN THE | | QUARTERLY TEST IS PERFORMED, AND NO FAILURES HAVE BEEN FOUND WHEN THEY ARE | | STROKED WEEKLY. ABOUT A YEAR AGO, A DESIGN CHANGE TO THE AIR SUPPLY OF THE | | ACTUATOR WAS PERFORMED, AND THERE WERE NO ADDITIONAL FAILURES UNTIL THE TWO | | THAT OCCURRED LAST WEEK. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28015 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COOPER-BESSEMER RECIPROCATING PROD |NOTIFICATION DATE: 11/10/94 | | CITY: GROVE CITY REGION: 1 |NOTIFICATION TIME: 15:52 [ET]| | COUNTY: STATE: PA |EVENT DATE: 11/03/94 | |LICENSE#: AGREEMENT: N |EVENT TIME: 10:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/10/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SCHNEIDER |HAASS RVIB | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ON 1/12/87, COOPER-BESSEMER REPORTED A POTENTIAL PROBLEM WITH THE MASTER | | POWER CONNECTING ROD (KSV-4-2A#1) UTILIZED IN COOPER-BESSEMER "KSV" EDG's. | | THE REPORT DESCRIBED MASTER ROD FAILURE DUE TO AN IRON PLATING REPAIR. | | | | ON 11/3/94, BRAIDWOOD STATION EXPERIENCED A MASTER ROD FAILURE IN THE "2B" | | EDG. EXAMINATION OF THE MASTER ROD INDICATED A FAILURE MODE SIMILAR TO | | THAT DESCRIBED IN THE 1987 REPORT. | | | | THE PURPOSE OF THIS LETTER IS TO REPORT ADDITIONAL AFFECTED ITEMS. A | | RECORDS REVIEW IDENTIFIED 4 AFFECTED MASTER RODS IN ADDITION TO THOSE | | REPORTED IN 1987. THESE FOUR RODS ALL BEAR "8H22XX" SERIES SERIAL NUMBERS. | | DUE TO THE MANUFACTURING PRACTICES IN USE IN THE 70's WHEN THESE MASTER | | RODS WERE PRODUCED, THE AFFECTED RODS ARE IDENTIFIABLE BY A PRODUCTION | | ORDER NUMBER. | | | | COOPER RECOMMENDS THAT THE FOLLOWING UTILITIES PERFORM A VISUAL INSPECTION | | OF THE MASTER RODS TO DETERMINE APPLICABILITY OF THIS REPORT. THIS MAY BE | | CONDUCTED IN THE INSTALLED STATE. | | | | BRAIDWOOD | | PALO VERDE | | NINE MILE POINT | | WATERFORD 3 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28016 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 11/10/94 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 16:18 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/09/94 | +------------------------------------------------+EVENT TIME: 19:45[CST]| |NRC NOTIFIED BY: PINZON |LAST UPDATE DATE: 11/10/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TS 3.0.3 ENTERED DUE TO INADEQUATE SURVEILLANCES ON VENTILATION SYSTEMS. | | | | TECHNICAL SPECIFICATION 3.0.3 WAS ENTERED AT 1945 CST ON 11/9/94 DUE TO THE | | INOPERABILITY OF ALL THREE TRAINS OF REACTOR CONTAINMENT FAN COOLERS, | | CONTROL ROOM ENVELOPE HEATING, VENTILATION AND AIR CONDITIONING SYSTEM AND | | FUEL HANDLING BUILDING HEATING, VENTILATION AND AIR CONDITIONING SYSTEM | | CAUSED BY THE LACK OF ADEQUATE SURVEILLANCE TESTING. TECHNICAL | | SPECIFICATION 4.0.3 WAS INVOKED WHICH ALLOW DELAYING THE ACTION | | REQUIREMENTS OF TECHNICAL SPECIFICATION 3.0.3 FOR 24 HOURS IN ORDER TO | | PERFORM AN ADEQUATE SURVEILLANCE. DATA COLLECTION IS COMPLETE WITH | | SATISFACTORY RESULTS. UNIT 1 AND UNIT 2 EXITED TECHNICAL SPECIFICATION | | 3.0.3 AT 1450 HOURS ON 11/10/94. | | | | THE INADEQUATE TIME RESPONSE TESTING SURVEILLANCE WAS DUE TO THE FAILURE TO | | TAKE INTO ACCOUNT MOTOR SPIN UP TIME FOR ALL TRAINS OF REACTOR CONTAINMENT | | FAN COOLERS, CONTROL ROOM ENVELOPE HEATING, VENTILATION AND AIR | | CONDITIONING SYSTEM AND FUEL HANDLING BUILDING HEATING, VENTILATION AND AIR | | CONDITIONING SYSTEM. | | | | THIS IS BEING REPORTED AS A VIOLATION OF THE PLANT OPERATING LICENSE Nos. | | NPF-76 AND NPF-80 (2G) SECTION 2.C(2). THE LICENSEE HAS INFORMED THE | | RESIDENT INSPECTOR, AND IS INVESTIGATING TO DETERMINE THE ROOT CAUSE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28017 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 11/10/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:30 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 11/10/94 | +------------------------------------------------+EVENT TIME: 18:05[EST]| |NRC NOTIFIED BY: HUTTON |LAST UPDATE DATE: 11/10/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT VENT AND PURGE ISOLATION DUE TO HUMAN ERROR DURING TESTING. | | | | THE LICENSEE WAS PERFORMING A CONTAINMENT RAD MONITOR FRONT PANEL TEST. | | THERE ARE TWO MONITORS, AND THE PROCEDURE REQUIRED THAT THE #1 MONITOR BE | | BYPASSED AND THEN TESTED. THE #1 MONITOR WAS BYPASSED, BUT THE #2 MONITOR | | WAS TESTED. THIS RESULTED IN A CONTAINMENT VENT AND PURGE ISOLATION. | | | | THE SIGNAL WAS RESET AND THE SYSTEM RESTORED TO NORMAL. THE CAUSE OF THE | | EVENT IS ATTRIBUTED TO HUMAN ERROR. THE LICENSEE WILL NOTIFY THE RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28018 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 11/11/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 03:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/11/94 | +------------------------------------------------+EVENT TIME: 01:49[CST]| |NRC NOTIFIED BY: BRIAN HUPKE |LAST UPDATE DATE: 11/11/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |M JORDAN RDO | |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 +------------------------------------------------------------------------------+ | LICENSEE RECEIVED A GROUP 5 (RWCU) PRIMARY CONTAINMENT ISOLATION SIGNAL | | (PCIS) AFTER PLACING RWCU "B" DEMINERALIZER BACK IN SERVICE. | | | | AFTER BACK WASHING RWCU "B" DEMINERALIZER BED AND PLACING IT BACK IN | | SERVICE LICENSEE RECEIVED A RWCU HIGH DIFFERENTIAL FLOW ALARM FOLLOWED BY | | RWCU PUMP TRIP AND RWCU SYSTEM ISOLATION (PCIS GROUP 5). LICENSEE THINKS | | THAT RWCU "A" DEMINERALIZER BLEW A HEAD GASKET WHILE IN SERVICE WHICH | | CAUSED RWCU HIGH DIFFERENTIAL FLOW ALARM FOLLOWED BY THE RWCU SYSTEM | | ISOLATION AND RWCU PUMP TRIP. LICENSEE THINKS RWCU "A" DEMINERALIZER BLEW A | | HEAD GASKET BECAUSE THE RWCU "A" DEMINERALIZER PRESSURE IS 0 PSI WHEREAS | | THE RWCU "B" DEMINERALIZER PRESSURE IS 150 PSI. LICENSEE WILL CHECK "A" | | DEMINERALIZER ON DAY SHIFT. THE RWCU SYSTEM WILL NOT BE RETURNED TO | | SERVICE UNTIL SOMETIME ON DAY SHIFT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28019 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 11/11/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:16 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 11/11/94 | +------------------------------------------------+EVENT TIME: 10:40[EST]| |NRC NOTIFIED BY: PETERS |LAST UPDATE DATE: 11/11/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A NON-LICENSED CONTRACTOR EMPLOYEE WAS CONFIRMED TO HAVE TESTED POSITIVE | | FOR COCAINE UNDER THE RANDOM DRUG TESTING PROGRAM. THE EMPLOYEE'S ACCESS | | TO THE PLANT HAS BEEN TERMINATED. SEE HOO LOG FOR ADDITIONAL DETAILS. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28020 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COMMONWEALTH EDISON |NOTIFICATION DATE: 11/11/94 | | CITY: DOWNERS GROVE REGION: 3 |NOTIFICATION TIME: 16:40 [ET]| | COUNTY: STATE: IL |EVENT DATE: 11/11/94 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 15:00[CST]| | DOCKET: |LAST UPDATE DATE: 11/11/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: CHROMIZKY |HAASS RIVB | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMMONWEALTH EDISON, LOCATED IN DOWNERS GROVE, IL, SUBMITTED A PART 21 | | PERTAINING TO THE POTENTIAL FOR MOTOR PINION KEY FAILURE ON LIMITORQUE | | ACTUATORS. | | | | FAILURES OF LIMITORQUE MOTOR OPERATED VALVE ACTUATOR AISI TYPE 1018 MOTOR | | PINION KEYS HAVE OCCURRED, AND ARE ATTRIBUTED TO INSUFFICIENT MATERIAL | | STRENGTH FOR CERTAIN LIMITORQUE ACTUATORS. ComEd, ALONG WITH KALSI | | ENGINEERING, IS EVALUATING AISI TYPE 1018 MOTOR PINION KEY FAILURES IN | | SMB-O AND SMB-2 ACTUATORS. EARLY RESULTS INDICATED THAT KEY FAILURE MAY | | OCCUR AT TORQUE LEVELS BELOW THE PUBLISHED LIMITORQUE ACTUATOR TORQUE | | RATINGS. FURTHER TECHNICAL EVALUATION IS REQUIRED TO IDENTIFY WHICH, IF | | ANY, INSTALLED ACTUATORS MAY BE AFFECTED. | | | | ComEd HAS ISSUED GUIDELINES TO ITS SIX NUCLEAR STATIONS ON THE METHODS FOR | | PROPERLY INSTALLING MOTOR PINION KEYS. IN ADDITION, THE STATIONS HAVE | | INITIATED REPLACEMENT OF AISI TYPE 1018 KEYS IN THOSE SMB-O AND LARGER | | ACTUATORS IN WHICH THE MOTOR PINION GEAR IS BEING REPAIRED OR REPLACED, AS | | A PRECAUTIONARY MEASURE. REMOVED KEYS ARE BEING REPLACED, AND INSPECTIONS | | HAVE FOUND NO FAILED KEYS TO DATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28021 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 11/11/94 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:00 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/11/94 | +------------------------------------------------+EVENT TIME: 08:30[EST]| |NRC NOTIFIED BY: RADISHOFSKI |LAST UPDATE DATE: 11/11/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | VOLUNTARY NOTIFICATION BECAUSE A RECENT RO/SRO LICENSE RENEWAL REQUEST WAS | | SUBMITTED PRIOR TO ALL OF THE QUALIFICATIONS BEING MET. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SENT TO THE OPS CENTER: | | "THIS VOLUNTARY NOTIFICATION IS TO PROVIDE INFORMATION RELATIVE TO A | | DOCUMENT ISSUED TO NRC REGION 1 BY PP&L Co. | | | | LICENSEE DOCUMENT PLA-4225. DATED NOVEMBER 8, 1994, TO Mr. GLENN MEYERS, | | USNRC REGION 1, TRANSMITTED REQUEST FOR RO/SRO LICENSE RENEWAL FOR ONE SRO. | | | | SUBSEQUENT TO ISSUANCE OF THE DOCUMENT, IT WAS DISCOVERED THAT NOT ALL | | REQUIREMENTS NECESSARY FOR REQUALIFICATION HAD BEEN COMPLETED BY THE | | APPLICANT. | | | | THE APPLICANT HAS SINCE COMPLETED THE NECESSARY REQUIREMENTS FOR | | REQUALIFICATION. A SUPPLEMENTAL APPLICATION FOR RO/SRO LICENSE RENEWAL FOR | | THE SUBJECT SRO WILL BE SUBMITTED." | | END OF TEXT | | | | THE NECESSARY REQUIREMENTS MISSED WERE THE "WEEKLY CYCLE QUIZZES", FOR | | WHICH SEVERAL WERE FOUND TO BE MISSED. THE LICENSEE WILL INFORM THE | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28022 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 11/11/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 19:30 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 11/11/94 | +------------------------------------------------+EVENT TIME: 16:57[EST]| |NRC NOTIFIED BY: KIEL |LAST UPDATE DATE: 11/11/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BRIEF LOSS OF SHUTDOWN COOLING DURING A SURVEILLANCE DUE TO A COMBINATION | | OF OPERATOR ERROR AND LACK OF PROCEDURAL GUIDANCE. | | | | RESIDUAL HEAT REMOVAL (RHR) PUMP "B" TRIPPED WHILE IN THE SHUTDOWN COOLING | | (SDC) MODE WHILE PERFORMING A SURVEILLANCE ON THE RHR SDC HIGH PRESSURE | | CUT-IN PERMISSIVE. VALVE "E11-F009" (RHR SUCTION OUTBOARD ISOLATION VALVE) | | CLOSED AS EXPECTED. THE VALVE CLOSURE REMOVED THE SUCTION PATH FOR THE RHR | | "B" PUMP, WHICH SUBSEQUENTLY TRIPPED ON INTERLOCK, AS DESIGNED. THIS | | CAUSED A LOSS OF SHUTDOWN COOLING. | | | | ALL EQUIPMENT AND LOGIC FUNCTIONED AS DESIGNED. RHR WAS RESTORED TO THE | | SDC MODE AFTER 37 MINUTES. INDICATIONS AND FLOW ARE NORMAL. RX COOLANT | | TEMPERATURE RISE WAS LESS THAN 1øF, AS MEASURE AT THE REACTOR VESSEL BOTTOM | | HEAD DRAIN. | | | | THE CAUSE OF THE LOSS OF SDC IS UNDER INVESTIGATION. OPERATORS DID NOT | | EXPECT THE "B" RHR PUMP TO TRIP DURING THE TEST. THE SURVEILLANCE TEST | | PROCEDURE DID NOT GIVE SPECIFIC GUIDANCE REGARDING THE PERFORMANCE OF THE | | TEST, IN TERMS OF A PRECAUTION TO AVOID THE VALVE CLOSURE, AND RELIES ON | | THE SYSTEM KNOWLEDGE OF THE OPERATORS. THE OPERATORS COULD HAVE | | DE-ENERGIZED THE SUCTION ISOLATION VALVE OPEN (THE PUMP TRIP COMES OFF A | | LIMIT SWITCH BASED ON VALVE POSITION) AND STILL PERFORM THE TEST | | SATISFACTORILY. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28023 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/11/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 21:20 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 11/11/94 | +------------------------------------------------+EVENT TIME: 17:26[PST]| |NRC NOTIFIED BY: PERINO |LAST UPDATE DATE: 11/11/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FIRE IN THE MAIN CONTROL ROOM MAY CAUSE THE INABILITY TO COMPLETELY | | DEPRESSURIZE THE RPV FROM THE ALTERNATE REMOTE SHUTDOWN PANEL. | | | | WNP-2 HAS DISCOVERED THAT DURING A SAFE SHUTDOWN FIRE IN THE MAIN CONTROL | | ROOM, CONTAINMENT INSTRUMENT AIR VALVE 20 (CIA-V-20) MAY CLOSE DUE TO A HOT | | SHORT. THIS VALVE IS THE SUPPLY TO THE INBOARD MSIVs AND NON-ADS SAFETY | | RELIEF VALVES. WITH THE VALVE CLOSED, THE 10 gal NON-ADS ACCUMULATORS ON | | THE SRVs WILL ONLY SUPPLY ENOUGH NITROGEN FOR THREE CYCLES IN THE RELIEF | | MODE. | | | | THE CONTROL ROOM EVACUATION AND REMOTE COOLDOWN ABNORMAL PROCEDURE CREDITS | | USING SIX SRVs, INCLUDING THE THREE NON-ADS SRVs ON THE ALTERNATE REMOTE | | SHUTDOWN PANEL. FOLLOWING AN EVACUATION OF THE CONTROL ROOM, THE SRVs | | WOULD CYCLE ENOUGH THAT THERE WOULD BE INADEQUATE NITROGEN PRESSURE TO | | FULLY DEPRESSURIZE THE RPV USING THE NON-ADS SRVs AT THE ALTERNATE REMOTE | | SHUTDOWN PANEL. THIS WOULD LEAVE ONLY THE THREE ADS SRVs ON THE REMOTE | | SHUTDOWN PANEL FOR DEPRESSURIZATION. SIX VALVES ARE REQUIRED TO MEET | | LICENSING COMMITMENTS. | | | | THE SYSTEMS REMAIN OPERABLE SINCE THE CONTROL ROOM IS CONTINUOUSLY MANNED. | | THIS ENSURES THAT THE POSTULATED FIRE CAN BE QUICKLY IDENTIFIED AND | | SUPPRESSED THUS TERMINATING THIS POSTULATED SCENARIO. WNP-2 HAS PLACED A | | FIRE IMPAIRMENT ON THE CONTROL ROOM APPLICABLE CABLE RUNS AND PANELS, AND | | TAKES CREDIT FOR THE CONTINUOUS MANNING OF THE CONTROL ROOM. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28024 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 11/12/94 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 11:54 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/12/94 | +------------------------------------------------+EVENT TIME: 09:59[CST]| |NRC NOTIFIED BY: HESSLING |LAST UPDATE DATE: 11/12/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO MONITORING CAPABILITIES. IMMEDIATE | | COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL INFORM THE | | RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28025 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/12/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/12/94 | +------------------------------------------------+EVENT TIME: 12:35[CST]| |NRC NOTIFIED BY: KAUL |LAST UPDATE DATE: 11/12/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 +------------------------------------------------------------------------------+ | 8 HOUR EMERGENCY LIGHTING APPENDIX R REQUIREMENTS CANNOT BE ASSURED FOR | | SEVERAL REASONS. | | | | DURING A REVIEW OF APPENDIX R EMERGENCY LIGHTING, THE FOLLOWING CONDITIONS | | WERE DISCOVERED: | | | | 1) THERE ARE MANY RECORDED FAILURES OF EITHER THE LAMPS (WHICH ARE TESTED | | EACH MONTH) OR THE BATTERIES (WHICH ARE TESTED EVERY 18 MONTHS). | | | | 2) THE LAMP MANUFACTURER SPECIFIES A 20 HOUR LIFE, BUT THERE ARE NO | | PREVENTATIVE MAINTENANCE PROCEDURES TO ENSURE THAT THE LAMPS HAVE AT | | LEAST EIGHT HOURS OF LIFE REMAINING. | | | | 3) THE BATTERY MANUFACTURER SPECIFIES A 15 YEAR LIFE AT 77øF, AND CHANGES | | IN TEMPERATURE CAN DEGRADE BATTERY PERFORMANCE. NO EVALUATION OF | | TEMPERATURE EFFECTS HAS BEEN PERFORMED. | | | | 4) THE EXISTING CONTROL BOARDS FOR TRICKLE CHARGING MAY BE UNDER/OVER | | CHARGING THE BATTERIES, THEREBY SHORTENING THE LIFE. | | | | BASED ON THE ABOVE, THE 8 HOUR APPENDIX R EMERGENCY LIGHTS REQUIREMENTS | | CANNOT BE ASSURED. THE LICENSEE IS INVESTIGATING POTENTIAL CORRECTIVE | | ACTIONS, AND HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28026 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 11/13/94 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 10:53 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/13/94 | +------------------------------------------------+EVENT TIME: 09:57[EST]| |NRC NOTIFIED BY: FELLOWS |LAST UPDATE DATE: 11/13/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KELLOGG 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM INOPERABLE DUE TO COMPUTER FAILURE | | | | FOLLOWING IS TEXT OF FACSIMILE SUBMITTED BY LICENSEE: | | "SAFETY PARAMETER DISPLAY SYSTEM (SPDS) WAS UNAVAILABLE DUE TO FAILURE FOR | | GREATER THAN ONE HOUR AS OF 0957 (FAILURE OCCURRED AT 0857). RESTORATION | | EFFORTS IN PROGRESS. CAUSE OF FAILURE UNKNOWN." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28027 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NATIONAL RESPONSE CENTER |NOTIFICATION DATE: 11/13/94 | | CITY: WATAUGA REGION: 2 |NOTIFICATION TIME: 16:25 [ET]| | COUNTY: CARTER STATE: TN |EVENT DATE: 11/13/94 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 14:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/13/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PAUL KELLOGG RDO | | |WILLIAM BRACH EO | +------------------------------------------------+ | |NRC NOTIFIED BY: SHORES |SOLLENBERGER SP | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRIVATE CITIZEN CALLED THE NATIONAL RESPONSE CENTER ABOUT 2 LEAD CYLINDERS | | THAT MAY HAVE RADIOACTIVE MATERIAL. | | | | NOTIFIED BY THE NATIONAL RESPONSE CENTER OF AN INDIVIDUAL IN WATAUGA, TN, | | WHO HAS BECOME AWARE OF TWO 6"x 6" LEAD CYLINDERS THAT THE INDIVIDUAL | | THINKS MAY BE RADIOACTIVE. THE CYLINDERS HAVE TAGS STATING THAT THEY | | CONTAIN 40 MICRO-CURIES OF Cs-137. THE TAGS ARE DATED 7/20/71. THE | | INDIVIDUAL NOTIFIED THE LOCAL FIRE DEPARTMENT. THE NRC NOTIFIED THE EPA. | +------------------------------------------------------------------------------+